proposed tech specs revising rts & esfas instrumentation ... · technical specification·3.3.1...

t.

.. ' •

ATTACHMENT Bl

Technical Specification·3.3.1 insert •

• . INSERT 1:

ACTION 10 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours or be in at least HOT STANDBY in the next 6 hours; however, one channel may be bypassed for up to 4 hours for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

,..

~ - '. I lllY ii. ii-I IConli&aumu I •ucnw Dir '.'IDI lllDIMpAllM i .. .. ••••IWll - TOl'AL llUIUIU CllAllllSU aea.RllLS APPLICABLE fVllCllQML VIII oj QIAM!!,I m n•• ....... IQQIS ACtlOlf

11. rrMMriur lhtec Lewel--lligla J 2 2 1.2 6 ' 12. S.O.• of •laW - 81 .. le l.oop l/loop 2/loop in 2/loop ln 1 :i1 ~~ • ......... , ••r oper- each oper-

atl111 locp atlnv loop

ll. Lo8• of •low - ~ ..._.. J/loop 2/loop ln 2/loop ln 1 -ff- ~13-tAllowe ._.,Md Mlow 11-11 two aper- each oper-

atlnv loope at.ln«J loop

... . 14. Ste .. GeA9rator Water Level-- l/loop 2/loop 1111 . 2/loop ln 1,2 -ff- ~$ ....... Low-Low anr oper- ea.ch oper--w atlnv locpe atln«J loop I w

lS. Ste .. /Feedvat•r Fiow Ml ... tcb 2/loop-lewel 1/loop-lewel 1/loop-level 1,2 -ff- ~-:ti and Low at.... Oe•rat01r .. t•r and 2/loop- coincident and 2/loop-..... 1 flow •1-tcll wltla flow •1-tch

I/loop-flow or 2/loop-•1-tcla la l•w•l and e -- loop I/loop-flow

•1-tcll

16. Ulldenolt.ave - ... nor •-1/bu• 1/2 twice l 1 6 COolaat: ._..

11. Uadulr.,...acr - ... ctor t-1/bu• 1/2 twice J 1 ' r COolut: hllpl

~

' .. a 0

,.,.. ~ V1

en lb ....

'• 11· lAl!LI ~1~-1 (~oot!ouedt

BEACTQR TRIP SYSTEM INSTRQHENTAlION c: :II .... r> - MINIMUM

TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIQNAL UNIT or CHANNELS IO TRIP Ol?ERl\BLB MODES ACTION 18. Turbine Trip

a. Low ~uto•top Oil Pressure J 2 2 1 -,.,- ~-:ft

~ b. Turbine Stop Valve Clo•ure 4 .. J 1 __,,.,__ c,-#'

19. Safety Injection Input f rOll ESF 2 1 2 1,2 -+- /0 20. Reactor Cool~nt Pump Breaker 1/breaker 2 1/breaker 1 11 Po•ition Tri~ (above P-lt per opera-

ting loop

w 21. Reactor Trip Breakers 2 1 2 1,2 1111, 14 ....... .. 3*,4*,5* 13 w

I ... 22. Automatic T~ip Logic 2 1 2 1,2 --I- JO

3*,4*,5* 13

TABLE J.J-1 IContinuedl . • TABLE NOTA~ION

• With th• reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

# The provisions of Specification 3.0.4 are not applicable.

## High voltage to detector may be de-energized above P-6.

### If ACTION Statement l is entered a• a re•ult of Reactor Trip Breaker (RTB) or Reactor Trip Bypas• Breaker• (RTBB) maintenance t••ting r••ults exceeding th• following acceptance criteria, NRC reporting •hall be made within 30 day• in accordance with Specification 6.9.2:

1. A RTB or RTBB trip failure during any •urvei.llance te•t with leu than or equal to 300 gram• of weight added to th• breaker trip bar.

2. A RTB er R'l'BB time re11pon11e failure that re•ult• in the overall reactor trip •ystem time re•pon•• exceeding the Technical Specification limit.

ACTlON STA'fEM!j1'fTS

ACTION 1 With th• number of channel• OPERABLE one l••• than required

ACTION 2

SAL!M UNIT 1

by th• Minimum Channel• OPERABLE requirement, be in HOT STANDBY within 6 hour•; however, one channel may be bypa•••d for up to 2 hour• for •urveillance te•tin9 per Specification 4.3.l.l provided the other channel i• OPERABLE. L/.3.1.l.I

With th• number of OPERABLE channel• one l••• than the Total Number Of Channel•, STARTUP and/or POWER OPERATION may proceed provided the following condition• are •ati•fiecl:

a.

c.

Th• inoper&Dl• channel i• placed in th• tripped condition within ,Y hou~.

~ s Th• Minimum Channel• OPERABLE requirement i• met; however, one additional channel may be bypa••ed for up to ~ houn for •urveillanc• t••tin9~per Specification 4.3.l.l~

OF o"T'l-#U CHANtv*t...S ~ ... 3.1, I, I Sither, THERMAL POWER i• r••tricted to $ 75\ of RAT~O TBSRMAI. POWER and.th• Power Range, Neutron Flux trip •etpoint is reduced to $ 85' of RATED THERMAL POWER within 4 hour•; er, the QUADRANT POWER TILT RATIO l8

monitored At least once par 12 hour•.

3/4 3-5 Amendment No. 134

9-C '1/t

CllQ .t.Oll q 3 sn .Lor;

•aftMi t 8'~QlA U0~1lPUO~ p9Cld13• eqi Ul P•~•td ., twua•qo 81"82edovt eqi P9PlAC2d ~·~ 'IVllOll:t"Q'

'DKJMl:3 ,.,q ... 2 .... 9'11• fO eDUWOJ.1'N tlliU8' peeH.-1 An llQU.WHO awn/.,,.. !!!\!¥U 'etevuwq; JG .a..-. .tft~

·~~ a•q~ •••t 9U9 •teuuwtilD .. l'l!llldQ JC 2eqllftU ... i ~Ja 1"1'1°£.'ft ·rre·t uo~+e:>~~H:>ldS .a9d

s t•uue4:> ..11uio ,olat••~ unttt~n• .zo1 a.znoq t'n dn 2c- ~·...uq -. '•· 1•nqD •Lqt.aadou~ 14+ '.z••..-.

,~ .. •1 iu-..zr~ l'llWWl'O •t•uuwq~ mftll'tUTK 9111. •Q

•s.anolf 9 ut'lil" uo1i1...pedd1n 9'li at ....,. •t tHn14~ •tQW.zecloul -.i. ·•

•StelJ•l~ .. ea. eaotitf'IOD 6ul..attOJ •q~ P9PTA0.1t P9•:io.ad An llOiiwuo aw .ZO/f/GW ~" '•t•uuwq:> JO .Zeqlll\ll t••.t.

•q~ ~i •••t •• •teuuwqo nswa•o 10 29qm\u -.i ~t• •.zai1•e.zeq~ e.zaaq Ct .z .. aouo ~•••t i• paw .aftOll t

UTQiTA '•tCIW~ttdd• .. 'C•t•t•r .zo t•t•t•t ao1i•o111DeC11 JO •i~ftl»u llianll MOCH.OMS eqi qiTA Nftltdllo~

A11n. '•• 1.ztaltu l'lft-U.O •t•uuwq~ wnwfvt11 ~ JC1 peztnba.z ~ mt m nanuo •teunq~ JO .zaqwnu Ml~ 'At•

·iu1ocbes ·-· eici eaoqw 1lallOll 'I\~ lut•••.Z~Ul o~ .ZOT.Zd •ni•i• nswuo ·~ tMmlt\SD •tqsa&d@V'J 8'(a a.zo~••.z 't·• Mt.. ·•

&t•••t VlllOll ~ aqi qa1A ... ~.zt~ l"ilYISdO •t•uuwq~ WNl'fUTM eqi Aq

pez1U.2 nqi •Mt euo rmftljO ~teina•q~ JO .zeqmnu eqa qa1A

•anutiuo~

.<n •o:"na•o ~ 'lllllOI 1VlnlD.t. auw JO •s •AOCIY ·o .. ..,. 'ftlinlsm. GUYii JO •s •.oqw VIACW "?VMallEU. 6u'T•••.ZOUT o~ ~ot~d •na•~• l'lSYWa•o oi t•uu•q~ •tcrw2edoul eq~

•~o~••.z 'VZAGI TGn&IJU. Cl2.l.~ JO •s ..ot•q ~nq t•d ••OCN •q

·~u1od~•s t-• •q~ •AOqW llaAO.I "!VlinlZU. 6u'T•••~~ur o~ ~01~d •n~•~• l'l~o oi teuvwq~ •tcrw.zedou1 eq~ •~o~••~ 't-• .-ot•I ·w

JfaAet ll~ '?YMVIJU •q~ q~r- pU9 ~U ... .ZTl\lae.z r?IYWl•O •t•uuwq~ mft"TUTN •q~ ~~

pezrni,e~ u•q~ •••t auo 1"%~140 •t•uu•q~ JO 2eqmnu aq~ Q~TA

(pinUiiUS3J t-e't iiiil e

• I llO%.t.:W

- • llOi.i:N

• I llO%.=Y

- " ll0%1.:W

- t llO%,:.:)Y

. .

ACTION 9

ACTION 10 -

ACTION 11 -

ACTION 12 -

ACTION 13 -

ACTION 14 -

DISIGffM'ION

P-6

P-7

SALEM - UHI'l' 1

- TABLE 3.3-1 /Continued)~ NOT USED

'NB• fTll!•"' SE£ /,A.JS££/

With l••• than the Minimum Number of Channel• OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within,( hourA

~ s With the number of channels OPERABLE one l••• than required by the Minimum Channel• OPERABLE requirement, r••tore the inoper&Dl• channel to OPERABLE •tatu• within 48 hour• or be in HOT STANDBY within the next 6 hour• and/or open the reactor trip breaker•.

With the number of OPERABLE channel• one l••• than the Minimum Channel• OPERABLE requirement, re•tore the inoperable channel to OPERABLE •tatu• within 48 hour• or open th5 rQaetor trip breaker• within the next hour.

With one of the div•rH trip feature• (Undervol.ta9e or •hunt trip attachment) inoperable, re•tore it to OPERABLE 8t~tue within 48 houra or declare the breaker inoper&Dl• and be in at lea•t HOT STANDBY within 6 hour•. The breaker •hall not be bypa~••d while one of the diver•• trip featur•• i• inoperable except for the time required for performin9 maintenance to r••tore the breaker to OPSRABI.I: •tatu•.

RIACIOR TRIP SYSTEM IBTERLOCgS

CQNJ)ITION ARD SETPOINT

With 2 of 2 Intermediate Rani!i Neutron Plux Channel• < 6x10 ampa.

?-'

With 2 of 4 Power Ranqe Neutron Flwc Channel• ~ 11 \ of RATED TIUIUGL POWER or l of 2 Turbin• impul•• chamber pre••ure channel• ~ a pr•••ure equivalent to 11\ of RA'l'SD 'l'HERMAL POWER.

l/4·3-7

1'1JR9'l'IOH

P-6 pr•vent• or d•f•at• the manual block of •ourc• range reac~or trip.

P-7 prevent• or defeat• the autcmatic block of reactor trip ona t.ov flaw in more than one primary coolant loop, reactor coolant ~ undervoltac;• and under-frequency, pr@!!l!urizer lCN pr•••ure, pr•••ur~&•r high level, and th• openin9·of more than one reactor coolant

_ pump breaker.

Amendment No. : J 4

IA )• r- TABLE 4.3-1 m•• '• :.~

~= ~lEACTOll_}_l!!_P~~STlM _ _!_NST_llUHENTATION SURVEILLA~CE REQUIRE~E-~TS

~ .,. .. -·

CHANNEL MODES IN Wll I Cll

- .CHANNEL FUNCTIONAL SUllVE lllANC£

FUNCTIONAL UNIT CHECK CAL I DRAT ION TEST _RE_Q!!~~---1. Manual Reactor TrJp Swttch H.A. N.A. S/U(9) ·N.A.

2. Power Range. Neutron Flux s ·0(2) 1 H(J) and Q(6)

Q -ff- I,. I i

3. Power Range, Neutron Flux. .. N.A. R(6) Q -M-lligh PostttvCR Rate 1, 2

4: .• Power Rang~. Neutron Flux, Iii 9h Negat tve Rate H.A. R(6) Q-H- .1. 2

lJ ....... ... " .&a I ntermedhte Rdnge, 5.

lJ I Neutron Flux s R(6) S/ll(l) 1, 2 and • - ;:· ....

6. Source Range, Neutron flux S(7) R(6) Q -ft-and S/U( l )' 2. l, 4. 5 and I

7. OvertemperatureA T s R Q -ft- 1, 2 I

8. Overpower 6 T s R Q -ft- 1. '9 I

9. Pressurizer Pressure--low s .R Q -H- 1, 2 I ii ID R Q I :a 10. Pressurizer Piressure--lltgh s ·-H- 1. 2

I :a 11. Pressurizer ~ater Level--lliyla s R Q I • 2 rt

:z ' 0 12 • loss of Flow - Single Loop s R Q -ff- l I . . I-' w VI

. D16o-J d1i~ Dll...,l ... "tt " • puw Z 't «SIM •••• . .... "' ...4

• ••t•• .... I Crt'ctln .. 'lrt'ttlM I • puw i 't •tot to/• •••• • ••• 2"9P• •12& ~ •tc

•12& Wl11 ... I •••• • •••• • ••• 2.it...a• ..... .-1oao .wo10~ ·oc

. i 't CsUtlM •••• • ••• ... -.WI ~ ... I •1--J•1 11•1 .. ·11

r 't Cthtl• •••• • ••• NMD10 •at•A.61DU "1CID& •• E 'I Cthi/8 •••• • ••• •2-••2• 110 ~eo:a ....... •• •v2& eu1cpn& ·et

.... .-... ... •

t ~-II-- • • ••• 1••tooa ~o~~·.. -~iJiepun ·u .., .. ...... ...... .., 1 t> ----- • • ••• 1 .. toao ~010W91I - e&w11ouepan ·11

,__.. ~ .. acr.a•niae '99919 _,,

I i 't b ::--w- • • • •1-111 ,.,. ~-..... 1-1• ·11 ,,

.......... • i 't b --- • • _,..,. D1 .. 20'1t2Ml99 -1• •tt

t •••• • • ...... ... • ADt• JO •llO'I .,, dfilftbli DU IOllMl'lid maim nm •11as1w

SHNT11u•n 91UOJ.mml 'IWVll3 11:>11111 •1 nao11 '1•mHID ...

IDiiililW ZMfiiiDM MftitWMIGHI llDll 4111 WWWll i • lfllll,"Saaal ,_,., ... a

., g

. ' *

(1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

(9)

(10) -

( 11) -

(12) -

CA.J:lLE 4.3-1 !Continued)

NOTATION • With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous.,,r"days. 31

Heat balance only, above 157. of RATED THERMAL POWER.

Compare incore to excore axial off set above 157. of RATED THERMAL POWER. Recalibrate if absolute difference ~ 3 percent.

Manual SSPS functional input check every 18 months.

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

Below P-6 (~lock of Source Range Reactor Trip) setpoint.

Deleted

If not performed in the previous 24 hours, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and shunt trip ·wiring.

If not performed in the previous 24 hours, conduct a functional test of:

ReactQ.r Trip Breaker independent operation of U. V. and Shunt Trip (via SSPS)

Reactor Trip Breaker Shunt Trip (via manual pushbutton controlsJ

Perform a functional test of:

Reactor Trip Breaker independent operation of U.V. Trip and Shunt Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip/Breakers (event recorders)

Reactor Trip Breaker Shunt Trip (via manual pushbutton contro~s1

Perform periodic maintenance on Reactor Trip Breakers and Re•c~~r Trip Bypass Breakers semiannually as follows:

a. response.time testing, (3 times) (visicorder) trend daa b. trip bar lift force measurements c. UV output force measurement d. dropout voltage check e. servicing/lubrication/adjustments (See Table 3.3-1 Notation

111111) f. repeat testing steps (a-d) following any necessary actions at

step (e)

SALEM - UNIT 1 3/4 3-13 Amendment No. 97

.. \

ATTACHMENT B2

Markup of Salem Unit 1 Technical Specification 3/4.3.2 -Engineered Safety Feature Actuation System Instrumentation

ti>

~ I

i H Ii

......

w

' ~ w I .....

U1

...... w OJ

T~DLI J.~-~ l!!ill!llBI~ §6EBIY [IAIU81i ACTUa:tlQB H:sua1 ll!§tBUHfiJ!IM'.IOJ!

MINIMUM TOTAL NO. CHANNELS CHANNELS

[Ul!~IOftAI.t UftlI O[ ~HANf!IL§ IQ DIE OflMl!LI

1. SAFETY INJECT!"' ~INE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation 2 1 2

b. Automatic Actuation Logic 2 1 2

c. Containmellt Pr•••ure-High 3 2 2

d. Pressurizer Prea•ure-Low J 2 2

e. Differential Pressure Between 3/steam line 2/steam line 2/steam Steam Linea - High any steam line

line

f. Steam Flow in Two Steam 2/steam line l/eteam line !/steam Lines-High any 2 steam line

lines

COINCIDBNT.WITH.BITHBR

T --Low-Low 1 T /loop 1 T in 1 T avg avg anya!91oopa av~ in an

OR, COIHCIDBNT WITH J loops

Steam Line Pressure-Low 1 pree•ure/ 1 pres•ure 1 pressure loop any 2 loops any 3 loops

,•

APPLICABLE ~ ACTION

1,2,3,4 18

1,2,3,4 13 e 1,2,3 -;.+a- ,qk

1,2,3# --+14- 19 -k

1,2,3## -w- l'l -t

1,2,3## 14• ,q 1'

1,2,3## """"H- ,q* • 1,2,3## 14• JC)~

w ........ .. w I ....

ID

TABLE J.J-3 (Continued) ENGINEERED SAFETY FEATURE l\CTUAIION SYSTEM INSTRUMENTAIION

FUNCTIONAL UNIT

4. STEAM LINE ISOL&~l~

a. Manual

b. Automatic Actuation Logic

c. containment Pr•••ure--High-High

d. Steam Plow in Two steam Lines--High

COINCIDENT WITH EITHER

T --Low-Low avg

OR, COINCIDBNT WITH

Steam Line Preaaure-Low

TOTAL NO. or CHANNELS

2/steam line

2***

4

2/steam line

1 T /loop avg

1 pressure/ loop

CHANNELS TO TRIP

l/ateam line

1

2

l/steam line any 2 steam lines

1 T in anya~gloopa

1 preaaure any 2 loop•

MINIMUM CHANNELS OPERABLE

1/operating ste8JI! line

2

3

l/steam line

1 T in anya°Jgloops

1 pressure any J loops

,•

APPLICABLE ~ Act ION

1,2,J 23

1,2,J 20

1,2,l 16

1,2,l##

1,2,l## 14* l'f~

1,2,3## 14*

w ......... -~

w I

N 0

f-J w 00

TABLE 3.3-3 (Continued) ~NGINEEBED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

FUNCTIONAL UNXT

5. TURBINE TRIP & l'SSO~TBR ISOLATION

6.

. a. Steam Generator Water level-High-High

SAFEGUARDS EQUIPMENT CONTROL SYSTBll (SBC)

7. UNDERVOLTAGE, VITAL BUS

a. LOBB 9f Voltage

b. Sustained Degraded Voltage

TOTAL NO. OF CUANNELS

l/loop

3

1/bua

3/bua

CHANNELS TO TRIP

2/loop in any operating loop

2

2

2/bua


APPLICABLE HQJ2I.§ -

2/loop in 1,2,3 each operating loop

3 1,2,3,4

3 1,2,3

3/bua 1,2,3

ACTION

13

14*

14*

G

·~ H "'i ....

w

' .e. w I

"" a Ill

f I:'

~ ID ~ rt

z 0

....... w OJ

TABLE 3.J-3 «eontinuedl ENGINEERED SAFETY FEATURE ACTUAIION SYSTEM INSTRUffENfATION

FUNCIIOftAL UNIT

8. AUXILIARY FEB~"'

a. Automatic Actuation Logic **

b. Manual Initiation

TOTAL NO. OF ClfANNELS

2

l/pua,p

c. steam Gen•r•tor Water Level--Low-Low

i. Start Motor Driven Pumps

ii. Start Turbine Driven Pumps

d. Undervoltage - RCP Start Turbine - Driven Pump

3/stm. gen.

3/etm. gen. generator

4-1/bue

CHANNELS TO TRIP

1

l/pump

2/stm. gen. any stm. gen.

2/etm. gen. any 2 etm. gen.

1/2 x 2


2

l/pump

2/stm. gen.

2/etm. gen.

3

APPLICABLE HQD.U

1,2,3

1,2,J

1,2,3

1,2,3

1,2

,,

ACTION

20

22

-H- tq*

-i:-4-*- I q ~

19

e. S.I. Start Motor-Driven Pumps See 1 above (All S.I. initiating functions and requirements)

f. Trip of Main Peedwater Pumpa Start Motor Driven Pumps

g. Station Blackout

2/pump l/pump l/pump

See 6 and 7 above (SEC and U/V Vital Bus)

1,2 21*

e I.

e

TABLE 3.3-3 <Continued)

TABLE NOTATION

# Trip function may be bypassed in this MODE below P-11.

## Trip function may be bypassed in this MODE below P-12.

* The provi•ion• of Specification 3.0.4 are not applicable.

** Applie• to Functional Unit 8 item• c and d.

*** Th• automatic actuation logic include• two redundant •olenoid operated vent valve• for each Main steam I•olation Valve. One vent valve on any one Main Steam I•olation Valve may be isolated without affecting the function of the automatic actuation logic provided the remaining seven solenoid vent valve• remain operable. The isolated MSIV vent valve shall be returned to OPERABLE status upon the fir•t @ntry into MODE 5 following determination that the vent valve is inoperable. For any condition where more than on• of the eight solenoid vent valve• are inoperable, entry into ACTION 20 is required.

f<.fSTt>flf.. WI£.. 1µop,<;.Jl.Ae,l£ C..tANN''- TO o.PU.Al.31..IL ACTION STATEMENTS "'~TVS w1-ru1;.J (;;, H0\.1£S o.R 7H£ /l.){.)c.T .,,/ I \, ' ~

ACTION 13 - With the number of\OPERABLE Channel• one l•••\than the Total Number of Channels,~be in HOT STAHDBY withinf6 hours and in

ACTION 14 -

ACTION 15

COLD SHUTDOWN within the following 30 houra1 however, one channel may be bypassed for up to~hour• for •urveillance te•ting per Specification 4.3.2.1.li P.<.ov1M.J> 114-4... o~ C1v.i.11.1ML

f S 0 Pt;fiAI!; Uf ... •

With the number of OPERABLE Channel• one le•• than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the

inoperable channel is placed in th• tripped condition w~t~~n l hour.

NOT USED

ACTION 16 - With the number of OPERABLE Channel• on• l••• than the 7;tal Number of Channels, operation may proceed provided th• inoperable channel ia placed in th• bypaaaed condition .,. . .:i th• Minimum Channels OPERABLE requirement i• demonstrated

6'1' CHA.Wtv6.L C/.lftK within ~hou;_i- on~ ad~itional channel may be bypassed t n .. p to ,2"hour• for surveillance teating per Specification 4.~.L.r. l. 4

ACTION 17 -

ACTION 18 -

SALEM - UNIT 1

With l••• than the Minimum Channel• OPERABLE, operation ~Y continu= provided the containment purge and exhaust valv•• are maintained closed.

With th• number of OPERABLE Channel• one l••• than th• ~~t•l Number of Channels, restore the inoperable channel to OPERABLE •tatua within 48 hours or be in at leaat HOT STANDBY w1t~1n the next 6 hours and in COLD SHUTDOWN within the foll°"'•nQ 30. hour•.


ACTION 19 -

ACTION 20 -

tJE.-:.<fjJ'JE.. 17-k_ IAJOf~ C#A-f.-JIV~L 10 o/aA&A... S~n..JS i,y;/f.11,.J 6 l-lov£S

ol? >

ACTION 21 -

ACTION 22 -

ACTION 23 -

SALEM - UNIT 1

TABLE 3.3-3 (Continued)

With the number of OPERABLE Channels one lea• than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within ;l' hour ...

ce. 's The Minimum Channel• OPERABLE requirement• is met; however, ·eAa al!itienal channel may be bypassed for up to A4hour• for aurveillanc• te•ting/\ per Specification 4. 3. 2 .1. l OF orn,t;,e Cl+NVNit-LJ;.

With the number of OPERABLE channels one le•• than the Total Number of Channel•,4be.in at lea•t HOT STANDBY within~6 ho~re and in at least HOT SHUTDOWN within the following 6 hours; 711€ I.Ji.XI

however, one channel may be bypa•••d for up to~hour for surveillance testing provided the other channel ~• OPERABLE. A .

PU- s/J.6,c.11=tc.A770.J 1..1.3,z. f. t With the number of OPERABLE channel• one l••• than the Minimum Number of Channels, operation may proceed· provided that either:

a. The inoperable channel is re•tored to OPERABLE within 72 hours, or

b. If the affected Main Feedwater Pump i• expected to be out of service for more than 72 hour•, the inoperable channel i• jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pump• upon the lo•• of th• other Main Feedwater Pump.

With the number of OPERABLE channel• relating directly with th• number of OPERABLE auxiliary feedwater pumps, the ACTIONs of L.c.o. 3.7.1.2 apply.

With the number of OPERABLE channel• one l••• than the Total Number of Channels, restore the inoperable channel to OPERABLE •tatus .within 48 hour• or be in HOT STANDBY within th• 6 hour• and in at leaat HOT SHUTDOWN within the following 6 hour•.


w ........ .co. w I

w ..... Ill

i

' :i rt .

z 0

TABLE 4.3-2

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUffENTATION SURVEILLANCE '·RIOUIBEMENTS

FUNCTIONAL UNJ;T CHANNEL

CHECK CHANNEL

CALIBBATION

1. SAFETY INJTBCTIOH, TUQINB.TRIP ARD FEEDWATER ISOLATION

2.

a. Manual Initiation

b. Automatic Actuaticm Logic

c. Containment Preaaure-High

d. Pressurizer Presaure--Low

e. Differential Pressure Between Steam Lines--High

f. Steam Flow in Two Steam Linea--High coincident with T --Low-Low or s@:im I.in• Pre•aure-LoW

CONTAINMINT SPRAY

a. Manual Initiation


c. Containment Preaeure--High-High

N.A. N.A.

N.A. N.A.

s R

s R

s R

s R

N.A. N.A.

N.A. N.A.

s R

CHANNEL FUNCTIONAL

.D.§I

R

M(2)

Q ,,.H13)

Q -M--

Q -ft-

Q ~

R

M(2)

MODES IN WHICH SURVEILLANCE

REOUIRIQ

1,2,3,4

1,2,3,4

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3,4

1,2,3,4

1,2,3

e

w ....... .c. w I

w l\J

IABLE 4.3-2 <Continued)

ENGINEERED SAFETY FEATURE AC'l'UAIION SYSTEM INSTRUMENTATION SURVEILLANCE JgjOUI8EM§NTS

FUNC'l'IONAL UNIT

3. CONTAINMENT ISOLaTIOll

a. Phase •A• Ieolation

1. Manual

2. From S~fety Injection Automatic Actuation Logic

b. Phase "8" Isolation

1. Manual

2. Automatic Actuation Logic

3. Containment Pressure-High-High

c. Containment Ventilation I•olation

1. Manual

2. Automatic Actuation Logic

'CHANNEL £Hlg

N.A.

N.A.

N.A.

N.A.

s

N.A.

N.A.

3. Containment Atmosphere Gaseoua Radioactivity - High

CHANNEL CALIBBATION

N.A.

N.A.

N.A.

N.A.

R

N.A.

N.A.

Per table 4.3-3

CHANNEL FUNCTIONAL

Dll

R

M(2)

R

M(2)

Q ;i((l)

R

M(2)


R£0UI8ED

1,2,3,4

1,2,3,4.

1,2,3,4

1,2,J,4

1,2,;3

1,2,3,4

1,2,3,4

w I w

. N ..

i ft CD ::I rt'

z 0

,._. w ())


EN9INEER£D SA[ETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLAtfCB 8EOUl8EMENTS

FUNCIIONAL UNIT

4. STEAM LINE ISOLATION

a. Manual


c. Containment Pre••ure-High-High

d. Steam Flow in Two Steam Lines--High Coincident with T --Low-Low or Steam Line P~~Hsure--Low

5. TURBINE TRIP AND FEEDWATER ISOLATION

a •. Steam Generator Water Level--High-High

CHANNEL £BGI

N.A.

N.A.

s

s

s

6. SAFEGUARDS EQUIPMENT COHTROL SYSTEM (SEC) LOGIC

a. Inputs N.A.

b~ Logic, Timing and output• * N.A.

7. UHDERVOLTAGE, VITAL BUS

a. Loss of Voltage s

b. Sustained Deqraded Voltaqe s

CHAHNEL CALIBRM'ION

N.A.

N.A.

R

R

R

N.A.

N.A.

R

R

CHANHEL FUNCTIONAL

.till

R

M(2)

Q AC3)

M(6)

M(l)

M

M


REOU18ED

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3,4

1,2,3,4

1,2,3

1,2,3

I

w

' .so. w I

w w

f r ::s rt

z 0

...... w 00

TABLE 4.3-2 IContinued)

ENGINEER£D SAFETY FEATURE ACTUATION SY§TEM INSTRUMENtATION SURVEILI.ANCB RIOUIRIMIN1S

FUNCTIONAL UNIT

8. AUXILIARY FBGDWA'J.'SR

a. Automatic Actu•tion Logic

b, Manual Initiation

c. Steam Generator Water Level--Low-Low

d. Undervoltage - RCP

CHANNEL gfl£K

N.A.

N.A.

s

s

CHANNEL CALIBRATION

N.A.

N.A.

R

R

CHANNEL FUNCTIONAL

Dll

M(2)

M(S)

q -M--

Q H(2)


REOUIRIQ

1,2,J

1,2,J

1,2,J

1,2

e. s. I. See 1 above (All S,J, surveillance requirements)

f. Trip of Kain Feedwater Pumps N.A. N.A. R 1

g. Station Blackout See 6b and 7 above (SEC and U/V Vital Bus)

.. ' ...

ATTACHMENT B3

Markup of Salem Unit 1 Technical Specification 3/4.3.1 and 3/4.3.2 Bases

ATTACHMENT B3

INSERT 1:

New Bases Paragraph #1 (Add to the existing paragraph)

and sufficient redundancy is maintained to permit a channel to be out of service for testing or ~aintenance consistent with maintaining an appropriate level .of reliability of the Reactor Protection and Engineered Safety Features instrumentation and, 3) sufficient system functions capability is available from diverse parameters.

INSERT 2:


Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, "Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," and Supplements to that report •. Surveillance intervals and out of service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection System and. Engineered Safety Features instrumentation.

(

ADD tJG.V

JNSUT ~I

3/4.3 INSTRUMENTATION

BASES

3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) I NSTRDMENTAT !ON

The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its set oint, 2) the s ecified coincidence lo ic ·

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent_with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed w1thin the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either l) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

3/4.3.3 MONITORING INSTRUMENTATION

3/4.3.3.l RADIATION MONITORING INSTRUMENTATION

The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served

SALEM - UNIT 1 B 3/4 3-1

.. • ATTACHMENT Cl

Markup of Salem Unit 2 Technical Specification 3/4.3.1 -Reactor Trip System Instrumentation

'• •

ATTACHMENT Cl

Technical Specification 3.3.1 insert.

INSERT 1: -

ACTION 10 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours or be in at least HOT STANDBY in the next 6 hours; however, one channel may be bypassed for up to 4 hours for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

JAILI J,J aillaliia11aa IQG1'pl DIP 11•·4' llQ"""'DITHll

"' ... -.. 9 MIHIMUll

~AL llUllBSR CHAllHSU atAIOllU APPL I CAIL. c fUllCTIOIAJ, VIII or QINlllLI IO DI' QPIMILI :I llOQIS ICJIOll .. .. ,,,. . 11. Pr•••urlaer Mator a.vel J 2 2 1,2 -·Hl9h

6 .,

12. Lo•• of Plow - 0"'91• Laop J/loop 2/loop ln 2/ll.oop ln 1 --ff- C:, 'It f Above P-IJ •nr oper- each oper-

atlftl loop atJl.IUJ loop

13. Lo•• of Plow - Ywo Loop11 J/loop 2/loop ln 2/Roop in 1 -ff-- ~-ti: e fAbove P-7 and INlow P•IJ two oper- each oper-

atlnt 100119 atllng loop

lt. It• .. Generator llat.er l/loop 2/loop in 2/'J.oop in 1,2 -Tl-Gd .. v•l--Law-Low anr oper- each oper-

w atlnt loop• at!n9 loop ...... -·<t n. St• .. /Feedwater Flow 2/loop-level 1/loop-level 1/loop-level 1,2 -ff-- G,.. w

Ml ... tch and i.o.. Ste .. and eolncldent and Generator Water .. vel 2/loop-flow with 2/loop-f low

•1-tch l/loop-flow •l1111atch or •l ... tcb ln 2/loop-level .- loop and

1/loop-flow •1 ... tcb

11. Undenolt..,.-a.aotor •-1/bu• 1/2 twlc• l 1 6

coolant ......

17. Underf ref1Uenor•i..actor •-1/bu• 1/2 twlce l / 1 6

COOlMt .....

f >

'.j ·• > .. • ')

. _. ,_ .. i..-

en .. • ... • c :I -... N

w ..... . ... w I ...

( I .. .. 0

......

...... w

fYNCTIONAL UBll

18. Turbin• Trip a. Low Auto•top 011 Pr•••ur• b. Turbin• Stop Val•• Clo•ure

19. Safety Injection Input from ESF

20. Reactor cooiant Puap Breaker Po•ition Trip Cabove P-71

21. Reactor Trip Breaker•

22 • Automatic Trip Logic

DILi ~.~-I (~Dt1DY!!!U BIACTOR IB12 lllilll IBIIBUlllB?al'.1211

MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE or CffANNII.S TO TBl2 OPERABLE HODES ft!d'.IO!'.!

3 2 2 1 .,.,_. (o 1:J.

4 4 l 1 ...:i#- (prJ:

2 1 2 1,2 -+- /0

1/breaker 2 !/breaker 1 11 e per opera-ting loop

2 1 2 1,2 1111, 14 J•,4•,s• 13

2 1 2 1,2 --i- /0 J•,4•,s• 13

..

*

##

###

TABLE 3.3-1 !Continued\ TABLE NOTATION

With the reactor trip system breakers in the closed poaition and the control rod drive system capable_of rod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

High voltage to detector may be de-energized above P-6.

If ACTION Statement l is entered a• a r••ult of Reactor Trip Breaker (RTB) or Reactor Trip Bypaa• Breaker (RTBB) maintenance t••ting r••ult• exceeding the following acceptance criteria, NRC reporting •hall be made within 30 day• in accordance with Specification 6.9.2:

l. A RTB or RTBB trip failure during any •urveillance t••t with les• than or equal to 300 grams of weight added to the breaker trip bar.

2. A RTB or RTBB time response failure that r••ult• in th• overall reactor trip •yutem time respon•• exceeding the Technical Specification limit.

ACIION STATEHENTS

ACTION 1 With the number of channel• OPERABLE one l••• than required by th• Minimum Channel• OPERABLJ: requirement, be in HOT STANDBY within 6 hour•; however, one channel may be byp••••d for up to 2 hour• for •urveillance te•tin9 per Specification 4.3.1.l provided th• other channel i• OPERABLE.

ACTION 2

a.

b.

c.

4."3,i,J.\ . With th• number of OPERABLE channel• one l••• than the Total Number of Channel•, STARTUP and/or POWER OPERATION may proceed provided th• followin9 condition• are •ati•fied:

Th• inoperable channel i• placed in the tripped condition within ¥hour.

(p ~ Th• Minimum Channel• OPERABLE requirement i• met; however, one additienal channel may be bypa••ed for up to.% hour• for •urveillanc• t••tinqA per Spec;f ication 4. 3 .1.1. 4

OF onia,L. CN.-1.Mv.U.s '{. 73,1,j. I Either, THERMAL POWER ill rtit•i;rictttd to " 75, of RATED THERMAL POWER and th• Power Range, lfeutron Flux trip ••tpoint i• reduced to ~ 85\ of RATED THERMAL POWER within 4 hour•; or, the QUADRANT POWER TILT RATIO i• monitored at lea•t once per l~ hcn!~8.

d. Th• QUADRAh"T POWER TILT RA'i'IO, a• indicated by th•

SALEM. - UNIT 2

remainin9 thr•• detector1, i• verified con•i•t•nt with the normalized •ymm•tric power di•tribution obtained by u•ing the movable in-core detector• in the four pair• of 1ymmetric thimble location• at lea1t once per 12 hour• when THERMAL. ~OWER ii greater than 75\ of RATED THERMAL POWER.

3/4 3-5 Amendment No • 113

' ( e IbBLE ~ J,J•l IC ~ ODljl.DUedl

ACTIOll l -

ACTIOll 4 -

ACTICll I •

ACl'lCll ' -

With th• number of channel• OPIRABLZ one le•• than r~ired by th• Minimum Channel• OPERAaLZ requirtllD9nt and with the THZJUCAL POWER levels

•· Below P-6, re•tore the inoperabl• channel to OPl1'AILI •tatu• prior to incr•a•in9 THEIUCAL fOMSll aboT• the P-6 setpoint.

b. Above P~6, but below 5' of RATSD 'l'UIUIAL PONSJt, r••tore th• inoperable channel to OflJtAaLI •tatu• prior to increaain9 THERMAL ~ Uo•• 5' of M'flD ~ POND.

c:. AbOft Hof U.'flD TDJtllAL POWat, l'OllD.OPDA'f?Oll uy continue.

d. Above 10' of RAftD TDIUIAL llOWD, tlw prcw1a1on• of specificction 3.0.l ara not applieable.

With the number of ch•nnel• OPs.AILS one l••• tb&D r9qQirecl by the ICinimum Channel• OnMILS r8qUU--Dt and witb the ~At JlONS!! levels

a. ..low ,_,, r••tore the 1noparu1a· cbulnal to o~ •tatu• prior to inere••iDI '1'mJIU. IOllD ...._ tbe P-6 'setpoint.

b. Allon ,_,, operation .. , contJ.aae.

With the nuaber of channel• OPDYLS ocw 1••• tban Hq\aired by tu IU.nJ.mum Channel• OPSUILI r-.u-nt, nrify eompliann with the IBUfDOMI ICAIGI• nqui.rwnta of lpacification J.1.1.1 or J.1.1.2, .. applicatale, witbin 1 hour aacl at l•••t on1:a par 12 lloun tbenat~u.

WiU tu number of OPDAILI ebawl• w 1... tban tu ~al llullbar of Cbannal•, ftaat'Uf .. ,. IOllD O.DATIOll My BP&e•M prniclecl the followiJMJ CODdit!W an nt1•f1ech

•· n. iaoperabl• channel· 1• placed 1a ~ ~ri.ppacl coadition vithin 6 ~ours. . . -

11. fte ICiniaNm Ch•M•l OflMll.I r-.uu-nt 18 mn1 bowever, the inoperable cbannel.•J m bfp&aHCI for ~P ~ 4 boar• for •uneilluce t•ft.i.al of other ch1nne ls per Spec1f1cat1cn 4.3.1.1. 4,3,1.1.1

AC'flOll 7 - If~ •• nmtel' af GPIM&e etaana.1• one 1•• ~ tha '

SALIN • UlllT' 2

~otal 111 NZ' of Channel•, ftMlUI 8fll41'"• fOllD °'IM'f?Clll 411a7 p&'OCl••cl u•U perfozwanca of tbii ... , zaqabwd CJUUC1IZL 'PVllGl'JelfAL 'flS'I pro•id•d etae i:nopacal:al• cban ... 1 ~· placed in "tba tzr1ppa- comhocion witb 1 bour.

/VOT U~£Q

l/4 l-6 ~ndr1at ll0.114

' ' ACTION 8 .. ACTION 9

ACTION lO -

ACTION ll -

ACTION 12 -

ACTION 13 -

ACTION 14 -

QISIQNATION

P-6

P-7

SALEH - UNIT 2

NOT USED

NOT USED

With less than the Minimum Number of Channel• OPERABLE, operation· may continue provided the inoperable channel i• placed in the tripped condition within ,.Yhcur..

G:. ~ With the number of channels OPERABLE one le•• than required by the Minimum Channels OPERABLE requirement, reatcr• th• inoperable channel to OPERABLE atatu• within 48 hour• or_be in HOT STANDBY within the next 6 hour• and/er open the reactor trip break•r•·

With th• number cf OPERABLE channel• en• l••• than the Minimum Channel• OPERABLE requirement, r••tcr• th• inoperablti channel eo.OPERABLE •tatu• within 48 hour• or open the reactor trip breaker• within the next hour.

With en• of th• divers• trip feature• (Undervclta9e or •hunt trip ~ttachmant) inop•rabl~, r88to~• it to OPERABLE •tatua within 48 hour• or declare the breaker inoperable and be in at l•a•t HOT STANDBY within 6 hour•. The breaker •hall net be bypa•••d while one of the diver•• trip feature• i• inoperable except fer th• time required fer performing maintenance to r••tcre th• breaker to OPERA!ILZ •tatu•.

REACTOR TRIP SYSTEM INTJjBLOCJ)S

CQNPITION ANC SETPOINT

With 2 cf 2 Intermediate Rani!i Neutron Flux Channel• < 6x10 ampe.

With 2 of 4 Power Range Neutron Chann•l• ~ ll\ Of RATED TDRHAL POWER er l cf 2 Turbin• impul•• chamber pre Hur• . : · · channel• ~ a pr•••ur• •quivalent to 11\ of RATEO THERMAL POWER.

3/4 3-7

nmCTION

P-6 prevent• er dafeat• the manual block of •ource ran9• reactor trip.

P-7 prevent• er defeat• Flux th• autcm&tic block of

reactor trip ens Low flow in more than on• primary coolant loop,

reactor coolant pump undervolta9• and under-frequency, pr•••urizer low pr•••ure, pre••urizer high level, and th• opening of more than en• reactor coolant pump breaker.

Amendment No. 1~3

.

VI ~ ,...

Tl\Bl.E 4.3-1 111 .:iC

·= REACTOR lHIP S.YSTEH IJ4SlRUMENTATION SURVEILLANC[ HEQUIREHCNlS

~ .. -4

-i Clll\NNEL MOOES IN WlllCll N CHANNEL FUNCTIONAL SUHVE llll\NCE

f UNC 11 OtlAL _lllfil CllCCK CALIBRATION TEST REQUIR[O ---I. Manual Me1ct1Dr Trip Swttch N.A. N.A. . S/U(9) N.A.

2. Power R1nge, Neutron Flux s 0(2), M(J) ind Q(6)

Q --*""-- 1, 2 e' J. Power Range, Neutron Flux,

Htgh Positive Rite' . N.A. R(6) Q -M- 1. 2

4. Power Range, Neutron Flux, llt~h Nc!Jal he Rate N.A. R(6) Q __..__ •• 2

w ......... ~ s. lnter11edtate Ranye, l•I Neutron Flux · s R(6) S/U(l) I, 2 and* • -- 6.' Source R~nge, Neutrqn flux 5(7) R(6) Q -M-1nd S/U( 1) 2. 3, 4, 5 and •I

1. Overtaper•ture AT s R Q -M- 1 • 2 I

r 8. Overpower 6 T s R <Q -K- 1, 2 91 a I

~ 9. Pressurtzer Pressure--Low s R --*'-- 1, 2

I :I 10. rressurher Pressure--lltgh s R Q --M- 1. 2 rt

z Q 0 ll . Pl'essur6zer W•ter Level--Htyh s R 1. 2 • .... .... s R Q -M- 1 1:- ••• loss ur fl'*' - Si n9 le Loop Lo

en

ti 1111.1 t.iJ-1 llifilo~io11•5la • ;a BllCJpR IRIP 811111 llSDlJMIUUIQI IVBQil.LNICI UOUIRIMINTS ... ...

CHAHNllL HODES IN WHICH N CllAllN&L PUNCTIOllAL SURVEILLANCI llJllCTIQIAL Ullt RllCI CAl.IIQTIQI llST Bl!2UllWI! 1J. Lo•• of Flow - ii.a Loopl • • M.A. 1 lt. ate .. Generator .. ter a.w.1-- • • --- Q 1, 2 le Low-Low

15. ate .. /Feedwater •law Ml ... tcb • •• • --H- Q 1, 2 I Low •team Cleaerfltor ••tu a.wel

16. Undenoltage - Daaator _Coolant •• A. • -H- Q 1 w ...... ....... .. w 17. Underfraquencr - a.actor Coolant M.A. R -- Q 1 • .... N Pump•

18. Turbine Trip a. Low AutNitop Oil Pr~••11r• •• A. •.A • 8/U(l) N.A. b. t'Urblae atop Valwe cloaua-e •.a. •.A. 8/U(lt II.A.

11. ••f•tr lnjec~lOlll Input f ra11 ur •.a. N.A. .. , •• (51 1, 2

I 20. a.actor CDolont l'ump k•abr •• A. I.A • R N.A.

I ..,.ltlon Trlp

21 • ... ctor Trlp 8rHker •• A. M.A • 8/U(lO) a 1, 2 and * .. f 11(11,llj, • 8A(12, ll) - and R(U) D w

H(S) 1, 2 and • • 22. A&itomatlc Tl"lp .Lo9lc •• A. II. A.

' ' *

(1)

(2)

TABLE 4.J-1 (Continued)

NOTATION

With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous;r'days. .31

Heat balance only, above 157. of RATED THERMAL POWER.

(3) Compare incore to excore axial offset above 157. of RATED THERMAL POWER. Recalibrate if absolute difference ~ 3 percent.

(4) Manual SSPS functional input check every 18 months.

(5) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(6) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8) Deleted

(9) If not performed in the previous 24 hours, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and shunt trip wiring.

(10) -

( 11) -

(12) -

If not performed in the previous 24 hours, conduct a functional test of:

Reactor Trip Breaker independent operation of U.V. dnd Shunt Trip (via SSPS)

Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

Perform a functional test of:

Reac.tor Trip Breaker independent operation of U. V. "'.' :- ~ p and Shunt Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip/Breakers (event recorjers)

Reactor Trip Breaker Shunt Trip (via manual.pushbut:~n controls)

Perform periodic maintenance on Reactor Trip Breakers and Ra•c:Jr Trip Bypass Breakers semiannually as follows:

a. response time testing, (3 times) (visicorder) trend dat.u b. trip bar lift force measurements c. U.V. output force measurement d. dropout voltage check

SALEM - UNIT 2 ;j/ 4 3-13 Amendment No. 7 4

I

... • • ATTACHMENT C2

Markup of Salem Unit 2 Technical Specification 3/4.3.2 -Engineered Safety Features Actuation.system Instrumentation

f ft ID ::i rt

z 0

OR, COINCIDENT WITH

Steam Line Pressure-Low l pressure/ loop

l pressure any 2 loops

l pressure 1,2,3## any 3 loops

14*

-- w

' ,,,. w I ,_. '°

~-.

m.


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

FUNCTIONAL UNIT

4. STEAM LINE ISOLATION

a. Manual


c. Containment Pressure-High-High

d. Steam Flow in Two Steam Lines--High

COINCIDENT WITH EITHER

T --Low-Low avg

OR, COINCIDENT WITH

steam Line Pressure-Low

TOTAL NO. OF CHANNELS

2/steam line

2 ***

4

:Z/steam line

1 T /loop avg

I pressure/ loop

CHANNELS TO TRIP

I/steam line

I

2

I/steam line any 2 steam lines

I T in anya~gloops

I pressure any 2 loops


I/operating steam line

2

3

l/steam line

I T in anyalgloops

I pressure any 3 loops

APPLICABLE MODES

I,2,3

I,2,3

I,2,3

I,2,3##

I,2,3##

1,2,3##

ACTION

23

20

I6

~ l t.) *'

w I

"" 0

TABLE 3.3-3 (Continued>

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUffENTAIION

FUNCTIONAL UNIT TOTAL NO.

·OF CHANNELS

5. TURBINE TRIP AHO FEEDWATER ISOLATION

a. Steam Generator Water level--High-High

6. SAFEGUARDS EQUIPMENT CONTROL SYSTEM (SEC)

7. UNDERVOLTAGE, VITAL BUS

a. Loss of Voltage

b. Sustained Degraded Voltage

3/loop

3

1/bus

3/bus

CHANNELS TO TRIP

2/loop in any operating loop

2

2

2/bus


2/loop in each operating loop

3

3

3/bue

APPLICABLE MODES

1,2,3

1,2,3,4

1,2,3

1,2,3

ACTION

13

14*

14*

w ........ ~

w I ....,

.....


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

FUNCTIONAL UNIT

8. AUXILIARY FEEDWATER

a~ Automat'ic Actuation Logic **


c. Stm. Gen. Water Level-Low-Low

i. Start Motor.Driven Pumps

TOTAL NO. OF CHANNELS

2

l/pump

3/atm. gen.

ii. Start Turbine Driven Pumps 3/atm. gen.

d. Unde.rvol tage - RCP Start Turbine - Driven Pump

4-1/bus

CHANNELS TO TRIP

1

l/pump

2/atm. gen. any atm. gen.

2/atm gen. any 2·atm • gen.

1/2 x 2


2

l/pump

2/atm. gen.

2/atm. gen.

3

APPLICABLE .MODES

1,2,3

1,2,3

1,2,3

1,2,J

1,2

ACTION

20

22

19

e. S.I. Start Motor-Driven Pumps See 1 above (All S.I. initiating functions and requirements)

f •. Trip of Mmin Feedwater Pumps Start Motor-Driven Pumps

2/pump l/pump l/pump

g. Station Blackout See 6 and 7 above (SEC and UV Vital Bua)

9. SEMIAUTOMATIC TRANSFER TO RECIRCULATION

a. RWST Level Low 4 2 3

b. Automatic Actuation Logic 2 1 2

1,2 21*

1,2,3 16

1,2,3 -Tr 2o

' t e TABLE 3.3-3 I Cont in.

TABLE NOTATION

# Trip function may be bypassed in this MODE below P-11.

## Trip function may be bypassed in this MODE below P-12.

* The provisions of Specification 3.0.4 are not applicable.

** Applies to Functional Unit 8 items c and d.

*** The automatic actuation 'logic includes two redundant solenoid operated · vent valves for each Main Steam Isolation Valve. one vent valve on

any one Main Steam Isolation Valve may be iaolated without affecting the function of the automatic actuation logic provided the remaining seven solenoid vent val ve.s remain operable. The isolated MSIV vent · valve shall be returned to OPERABLE statu• upon the first entry into MODE 5 following determination that the vent valve is inoperable. For any condition where more than one of the eight solenoid vent valves are inoperable, entry into ACTION 20 is required.

~£Srol!.<.. TI#i- /No/¥....lfl&l.Ji.. .. OwuNJi;,'- -ro oP~L£ S"l1f'TVS" ACTION STATEMENTS WITHIN '° .Hovll!:i. o,e I ' /M /Ve)CT

ACTION 13 - With the n~OPERABLE Channel• one le•• than the\Total Number of ·~~~~~e~;,\be in at least HOT STANOBY,within~ hours and in COLD SHUTDOWN within the following 30 hours; however,

ACTION 14 -

ACTION 15 -

ACTION 16 -

ACTION 17 -

ACTION 18 -

SALEM - UNIT 2

one channei' may be bypassed for up to~hour11 for . surveillance testing per Specification 4.3.2.l.l provided the other channel is OPERABLE.

With the number of OPERABLE Channels one less than the Total Number of Channels,, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within l hour.

NOT USED

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypaaaed condition and th• Minimum Channels OPERABLE requirement i• demonstrated by

CHANNEL CHECK within~hou~; one additional channel may be

bypaased for up to~hours.Sfor surveillance testing per Specification 4.3.2.1.1.

With lass than the Minimum Channel• OPERABLE, operation may continue provided the containment purg~ and exhaust valves are maintained closed.

With the number of OPERABLE Channels one lesa than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and .in COLD SHUTDOWN within the following 30 hours.


' . ~

ACTION 19 -

TABLE 3.3-3 (Cantin~

With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within X hour.

6, ll s b. The Minimum Channels OPERABLE requirements is met;

711£ l.JU;P~6'-'i... however, ealt &ddi'eieaal channel may be bypassed for up I . · to~hours for surveillance testingA per Specification 4. 3. 2 .1.1. OF omlU CHA<NN-Et..S

T~ IJE->cl ACTION 20 - With the number of OPERABLE channels one less than the)Total

/ Number of Channels~be in at least HOT STANDBY withinT6 hours f!.E'f;,TOIU ~ " 1·•ofoU'.A&'.-£and in at least HOT SHUTDOWN within the following 6 hours;

C#AAJAJ6-'- 70 ol'~ · STJ<17LIS WffJl'-..:J c,, however, one channel may be bypassed for up to ~hour for /70~~~ oL> surveillance testing provided the other channel is OPERABLE.

A PU. SP~c.1/=-IU\TloAJ t./.'3, 2. 'I, I ACTION 21 -

ACTION 22 -

ACTION 23·-

SALEM - UNIT 2

With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either:

a. The inoperable channel is restored to OPERABLE within 12 hours.

b. If the affected Main Feedwater Pump is expected to be out of service for more than 72 hours, the inoperable channel is jumpered so-as to enable the Start Circuit of the Auxiliary Feedwater Pumpa upon loss of the other Main Feedwater Pump •.

With the Number of OPERABLE channels relating directly ~~t~ . the number of OPERABLE auxiliary feedwater pumps, the AC7:0NS

of L.C.O. 3.7.1.2 apply.

With the number of OPERABLE channels one less than the :~ta~ Number of Channels, restore the inoperable channel to o?~?A3~E status within 48 hours or be in at leaat HOT STANDBY w ~ t ~. ~ ~.

6 hours and in HOT SHUTDOWN within the following 6 hou~s.


TABLE 4.3-2 V> ::S-0 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION r-~ ~DRVEl[LAN~E IEQOllEMENT~

c CHANNEL :z CHANNEL CHANNEL FUNCTIONAL ...... ..... FUNCTIONAL UNIT CHECK CALIBRATION TEST N

1. SAFETY INJIECTION. TURBINE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation N.A. N.A. R

b. Autoaatic Actuation Logic N.A. N.A. M(2)

c. Containment Pressure--High s R Q .Jf{3)

d. Pressurizer Pressure--Low s R Q ~ w -~ e. D1fferent~al Pressure s R CQ -H-w Between Stea11 Lines--High I w (.>

Stea11 Flow in Two Stea. . f. s R Q -H-Lines--High Coincident with T --Low-Low or Stea11 Ltne PfXVsure--Low

2. CONTAINMENT SPRAY

a. Manual Initiation N.A. N.A. R

b. Auto.attc Actuation Logic N.A. N.A. M(2)

c. Contailllllent Pressure--H1gh- s R Q Aft3) HiQh


REQUIRED

1. 2, 3. 4

1. 2. 3. 4

1. 2, 3

1, 2, 3

1, 2, 3

1, 2. 3

1, 2, 3, 4

1,2,3,4

1, 2 I 3

. ~

e

e

w ........ ,,.. w I w ,,..

" TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIR£MENTS

FUNCTIONAL UNIT

3. CONTAINMENT ISOLATIOB

a. Phase ~A" Iaolation

l) Manual

2) From Safety Injection Automatic Actuation Logic

b. Phase "B" Isolation

l) Manual

2) Automatic Actuation Logic

3) Containment Pressure-High-High

CHANNEL ~

N.A.

N.A.

N.A.

N.A.

s

c. Containment Ventilation Isolation

1) Manual

2) Automatic Actuation Logic

3) Containment Atmoaphere Gaseous Radioactivity - High

N.A.

M.A.

CHANNEL CALIBRATION

N.A.

N.A.

N.A.

N.A.

R

N.A.

N.A.

CHANNEL FUNCTIONAL

TEST

R

M(2)

R

M(2)

R

M(2)

Per table 4.3-3


REQUIRED

1,2,3,4

1,2,3,4

1,2,3,4

1,2,3,4

1,2,3

1,2,3,4

1,2,3,4

w I


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

FUNCTIONAL UNIT

4. STEAM. LINE ISOLATION

a. Manual


c. Containment Pressure-High-High

d. Steam Flow in Two Steam Linea--High Coincident with T --Low-Low or s@~~ Line Preasure--Low

CHANNEL CHECK

N.A.

N.A.

s

s

CHANNEL. CALIBRATION

N.A.

N.A.

R

R

CHANNEL FUNCTIONAL

TEST

R

M(2)

~ 5. TURBINE TRIP AND FEEDWATER ISOLATION

z 0

a. steam Generator Water Level--High-High

s

6. SAFEGUARDS EQUIPMENT CONTROL SYSTEM (SEC) LOGIC

a. Inputs N.A.

b. Logic, Timing and Outputs * N.A.

7. UNDERVOLTAGB, VITAL BUS

a. Losa of Voltage s

b. Suatained Degraded Voltage s

R

N.A. M(6)

N.A. M(l)

R M

R M


REQUIRED

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3,4

1,2,3,4

1,2,3

1,2,3

w I

w O'I


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

FUNCTIONAL UNIT

8. AUXILIARY FEEDWATBR

a. Automatic Actuation Logic


c. Steam Generator Water Level--Low-Low

d. Undervoltage - RCP

CHANNEL CHECK

N.A.

N.A.

s

s

CHANNEL CALIBRATION

N.A.

N.A.

R

R

CHANNEL FUNCTIONAL

TEST

M(2)

M(5)

Q -M-

Q -M-


REQUIRED

1,2,3

1,2,3

1,2,3

1,2

e. s. I. See 1 above (All s. I. surveillance requirements)

t. Trip of Main N.A. N.A. S/U(4) 1,2 Feedwater Pumps

g. station Blackout See 6 and 7 above (SEC and U/V.Vital Bus)

9. SEMIAUTOMATIC TRANSFER TO RECIRCULATION

a. RWST Low Level s R 1,2,3

b. Automatic Initiation Logic N.A. N.A. N.A. 1,2,3,4

-,

1e

,\ ...

___ , .... • ATTACHMENT C3

Markup of Salem Unit 2 Technical Specification 3/4.3.1 and 3/4.3.2 Bases

"',s :.· ... ~\ .,

.,>.-·' •

ATTACHMENT CJ

INSERT 1:


and sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features instrumentation and, 3) sufficient system functions capability is available from diverse parameters.

INSERT 2:


Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, "Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation system," and Supplements to that report. Surveillance intervals and out of. service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection System and Engineered Safety Features instrumentation.

I

A-DD- Nl.w

JAJ S lf.L T ~ I

• 3/4.3 INSTRUMENTATION

BASES

3/4.3. l and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION

The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination -thereof reaches its setpoint, 2) the specified coincidence logic1 is maiAtaiRee, J) suff;eient redundancy ;s mainta;ned to perm;t a ehannel to be- out of serviee for testing or maintenance, and 4) suffi ei eAt sy·stem fuAeti eAal eapaei li ty is available feP pPeteetive aAd ESF puppeses fPem aivePse paPametePs.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility de-sign for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the originaJ design standards. The periodic surveillance tests performed-at the minimum frequencies are sufficient to demonstrate this capability._,.,..

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the .analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements- provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either l) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

3/4.3.3 MONITORING INSTRUMENTATION

3/4.3.3. 1 RADIATION MONITORING INSTRUMENTATION

The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels, and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

SALEM - UNIT 2

proposed tech specs revising rts & esfas instrumentation ... · technical specification·3.3.1...

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