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" GOVERHMEHT ACCOUHTADILITYPROJECTins(i(use for Policy 5tudies1901 Que 5(reei. N.%'.. Noshington. D.C. 20009,, (202) 234-9382

Mr. Hans SchierlingU.S. Nuclear Regulatory CommissionWashington, D.C.

May 31, 1984

Dear Mr. Schierling:Enclosed are copies of two affidavits which were

promised at our meeting. Please excuse myoversight in not meeting you at the airport before yourdeparture from San Luis Obispo, California.

Also enclosed .is the list of additional referencematerials which Mr. Stokes needs to complete his evalu-ation of the licensee's corrective action on Mr. Yin'sfindin'gs. As you will recall, the May 9, i984 transcriptidentifies this information, which is part of the trans-cript and available upon public request. As you willalso recall, on Mr.',Stokes requested the data.You asked that he put the specifics in writing. We de-layed sending this list until a legal intern forwardedadditional materials available at the Public Document,Room, which reduced the numbex of items in the attachedenclosure.

Third, have you obtained approval from counsel forMr. Stokes to review necessary non-public materials, underMr. Yin's supervision, as he offered at the meeting?You will recall that Mr. Yin explained that he has fol-lowed this procedure successfully in other cases. Fur-ther, the Office of Investigations already has made anidentical agreement for GAP witnesses at Diablo Canyon.As a result, I assume that counsel's approval is a for-mality. But it should be obtained before Mr. Yin's re-turn, so that Mr. Stokes can complete his research.

Fourth, the witness from wants to receiveand review his transcript as soon as possible. He alsorequests the opportunity to swear under oath to the ac-curacy of his statements and to receive a copy of histranscript.

Finally, I have nearly completed extensive pre-parations with the witness, and several others,to organize data on Unit, I Quick Fives that raise sicpificantengineering concerns. An this was Mr. Vollmer'srequest. The ",.'"n '...:-;..". request the opportunity to meet

8406250316 8406 |'5 ' 'I" ~.PDR ADOCK 05000275 ',''.' -"'DR'>'

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with Nr. Yin and any other team members to continue thedisclosures. On you estimated that the team wouldreturn in approximately two'eeks.. I will call your of-fice tomorrow to follow up on this letter.

Sine rely,

Thomas DevineLegal Director

Enclosures

AFFIDAVIT

Hy name is Thomas Devine. am the Legal Director of the

Government Accountability project (GAP) . I am submitting this af-f idavit to provide a record of allegations received by GAP from

anonymous whistleblowers over the last two weeks. The allegationsconcern stresses on the concrete from Hilti Quick Bolts which may

result in failures of the bolts themselves. The alleged conditionsinclude —1) deep embedment; and 2; failure to consider the possibledesign ef fects when bolts are installed too close to the back of otherbolts from opposite sides of concrete walls.

The particular examples are on safety related work,

specif ically in the GE area, 85 foot level elevation in the AuxiliaryBuilding just outside the containment wall. They help support an

anchor-type hanger in Component Cooling Water (CCW) system 14. The

witnesses descr ibed these specif ic examples as illustrative of a

generic condition. The problems have been reported on quick FixI

process sheets and recently on a Deficient Condition Notice (DCN) .

There still has not been effective corrective action, although one

witness estimated that the problem should have been reported to the+Q

NRC with in 24 hours under 10 CFR part 21 due to it s potential to cause

failure in a safety-related system. The witness was deeply concerned

with the potential for the bolts to shake right out of the wall duringh

an earthquake, unless there is a full review and any necessary cor-rective action.

Beyond technical significance, if true the accounts below

of the two major bolting issues demonstrate the ineffectiveness of the

page -1- of Five pages

E

Quick Fix and Quality Control (QC) reporting systems to identify,disclose and correct all related deficient conditions. They alsodemonstrate a pattern of management non-response to a signif icantissue that has been raised repeatedly over the last year. Both the

effects -- bolting -- and the cause -- mismanagement

should be corrected before Diablo Canyon goes commercial.

The first alleged problem is that bolts were embedded a

minimum of 10.5 inches into concrete that was only 12 inches thick.Although the witnesses were not aware of specific calculations tode'monstrate whether this condition'were acceptable, I was informed

that unacceptable residual stresses can result if bolts are embeaded

too deeply into the concrete. Allegedly an inspector on-site has

requested relevant back-up data to see if the problem were consideredbut has not received any response. Mr. Stokes informed me that atmost nuclear plants in his experience the concrete is 24 inches thickwhen embedment is that deep.

4

I was told that the origin of the problem was instructionson design drawings to achieve a minimum of 10.5 inches embecment.

Allegedly the deep embedment had been considered necessary to achieve

the required strength for the structural loads —the hangers. The

potential problem

descends

on whether the consequences from excessiveembedment also were taken into account. As one witness said, "Itdoesn' do much good to f ix one problem by creating another that may be

worse."

The nature of management.'s response may be as signif icant as

the bolting problem itself. Last June a QC inspector identified the

issue to Pullman Power Products (Ppp) engineers. Despite recog-

Page -2- of Five Pages

(

nition of specif ic problems and individual corrective action--the a e

of "thru-bolts"—the generic condition was never addressed.

Last June 28 a different inspector allegedly also iaent-(ified a similar problem, but in this instance a Pullman engineer

disregarded the warning and responded that structural integer ity would

not be ef fected.

Un for tunately, the eng ineer was mistaken. Dur in'nstal-1'ation, concrete cones directly beneath three relevant bolts suf fered

a structural failure: the concrete popped out. The allegers were

concerned that the concrete failure could cause the bolts to fail asV

well.They also were concerned that the corrective action at the

time was ineffective. The "solution" was to "dry pack" the voids leftwhen the concrete fell out. "Dry packing" means applying filler to

the void that does not have any structural value. 'In other words, tne

corrective action was ineffective from a design perspective.and was

only applied to a'ew examples for a potentially generic condition.In 1983 Pacific Gas and Electric (PG&E) engineers also were

alerted to this problem and instructed the relevant Pullman engineer

to resolve it. As seen by the recent DCN, however, the problem wasn'

resolved. The new DCN allegedly was filed several weeks ago but

Pullman management has not responded. The witnesses inquiredwhether Pullman is violating the NRC 24 hour reporting requirements

for significant conditions. They told me that for all practicalpurposes the embedment problem is the same as last year, and the

quality of the bolting remains indeterminate after three attempts to

work within the system.

Page -3- of F ive Pages

t tAllegedly the DCN author raised an ancillary question

whether there was any design consideration for the structural ef fects

when Hilti Quick Bolts are embedded too closely to each other from

opposite sides of the concrete. In that circumstance the zones ofstructural influence from the bolts might conflict, leading to the

possibility of structural failure such as crackinc and resultingvoids on the concrete. As with the embedment problem, the witnesses

were concerned that this could cause failure of the bolts themselves,

and compromise the hangers and the lines being supported.

The anonymous witnesses stated that in fact there have been

instances when bolts from one side had been hit during the drilling anc

installation of bolts from the opposite side. Those tvoes r F mr Hi-

tions were found as late as last fall.. The occurrences suggestea to

the witnesses that design control had been inade<,uate to prevent the

conflicts.The witnesses told me that both technical tissues were

identified on Quick Fix process sheets. In fact, the bolting embed-

ment was verified by QC inspectors and placed on the back of Quick Fix

sheets. But the relevant as-built drawings do not reflect thisspecific information.. They only reference the 10.5 inch minimum

requirement. As a result, specif ic information on the Quick Fix

sheets was factored out of 'the as-built review's.

The witnesses emphasized that the specific examples may be

generic because so many other instances of voids, cracks, buried drain

pipe, forms lef t in concrete and dry packed knock outs are still being

identif ied in the field.Several of the witnesses requested the opportunity to

Page -4- of Five Pages 'Z3

conf identially disclose Quick Fix ~roble1«s wi"h NPC Inspector: 'I a

Yen, during his next visit.I have read the above -5- page statement and swear under

penalty of perjury, that this statement is true ana accurate to the

best of my belief.

Thomas Devine

Subscribed and sworn to before me'his ~2 th day of &lay, 1984.

s t

s

~

4f fTR« ~-'it";~-'~.1 I,.:; 1

.'1."- CBIGFO COUN1YMy Ge~. Expires h'.ay 9, 1986}-~~

t f.,I 'l''t'ai.

I-J

Notary Public in and forthe County of San LuisObispo, State ofCalifornia

Page -5- of Five Pages

~f

AFFIDAVIT

My name is Richard D. Parks. I work as an investing ator fvrthe Government Accountability project (GAP) in the Diablo Canyon

power Plant (DCpp) Investigation. I am providing this sworn state-ment to evidence concerns over a problem at DCPP.

Recently a packet of documents came into my possession rom

a ser ies of anomyous sources. These documents included Design Change

FrDC 2 E P 10544 Def icient Condition Notice (DCN) '31350 011 g PSA

Snubber Checklist, Field Support Process Sheets, Pipe Supr ort Design

Tolerance Clarification Forms (Quick Fixes) gQF-2-6916, QF-2-5168,

QF 2-5156, QF-2-2011], Minor Var iation Rector t IM-4490, PGS E DCPP-

Environmental Qualif ication (EQ) Maintenance Training Course St'tA050,

and HP Foley Valve Maintenance Report N1845. They are enclosed in a

packet identified as Attachment l.These documents relate to Residual Heat Removal (RHR) Pump

gl Recirculation Valve (FCV-641A- Unit 2), and its associated hanger

1413-143 SL. On page 40 of Attachment 1, this valve is listed as being

Environmentally Qualif ied. Attachment 1, pages 37-41 ex~lain the

siqnif icance of this qualif ication.After receiving and reviewing this packet of cocuments, I

reviewed the documents with several past/present Quality Control (QC)

inspectors from DCPP. Each of these individuals are aware of the

problem contained in the DCN and confirmed that the problem stillexists in the plant. I also reviewed NUREG-0588 to complete my

familiarization with the Qualification requirements.

page -1- of Four Pages

A review of the attached aocuments reveals the i:ollowing

problems with the Environmental Qualification program practices at

DCPP:

problem 41: During the "As-built Inspection", the responsible QCInspector identified that the 5/8" studs holding the valve motor tothe seismic valve support plate (piece 0 1, Attachment 1 page 9) naonever been replaced. These studs were requirea to be changeo by theoriginal Design Change./DC-2-E-P-10544, (refer tv Note "2 Attachmentgl, page 7) . This deficient condition was documented cn a DCN(Attachment 1 page 16) and iaentified that a Deviation Report shouldbe submitted to PG&E. This should have resolveo the problem;however, the original inspector was over r'dden and his DCN changed byA. Neinstein on 2/27/84. A. Weinstein's justif ication for his actionis describeo on page 17 of Attachment 1,.

The inoividuals that I reviewed this problem with informed me that the.. reason the studs had to be replaced was 1) due to the adoition of a 1/2"

support plate being bolted to the motor housing, it was necessary toensure sufficient projection of threads, and 2) the existing old stuashad visible indication of oamaged threads. Apparently the craft,when disassembling the valve to make the modification, had useo vise-grips to back the studs out of the motor. Thus to ensure adequatestrength with respect to fastening/tore;ue re<;uirements the stuasshoulo have been replaced. They were not.

'I

Conclusion: If the threads on the studs in c;uestion w'ere in factaamaged, they should have been replaced. Paragraph 3 on page 38,Attachment 1 identifies that if any doubt existed on the studs, "poor.maintenance practice" would have been to replace them. Unfortu-nately, they were not.problem j2: The uncontrolled disassembly of an EQ Nuclear SafetyRelateo Valve without use of a controlled procedure esulteo in damageto the valve and discharge of personnel involved. This is aocumentedon pages 35 and 36 of Attachment 1. 'his incident resulted in thegeneration of an MVR; that was deemed to be only a violation of pro3ectInstruction 58 (Takeout procedure) and a "ppp in-house Non-ComplianceReport". However, the MVR was markeo as "not reportable" and "not aNon-Conformance", despite its relevance for NUREG-0588 compliance.

Conclusion: Due to the significance of the valve and the conflictingstatements on reportability, it should have been deemed "reportable"and reported to the NRC.

problem 43: Attachment 1 page 38, "EQ Effects On Maintenance" statesin part "...provide detailed descriptions of maintenance work per-formed as input for failure analysis (trend) stuay."

page -2- of Four pages

However, a review of Valve Maintenance Ressort (jMVR-1845), Attachment1 page 41, does not include a listing of "what damaged oarts wererepaired or how they were repaireo."

problem j4: A letter from D.A ~ Rockwell to P. Stieqer (Attachment 1page,34) identif ies that the practice of installing seismic valvesupports to EQ valves could be violating EQ requirements. The letterrequires pullman power products (ppp) to respond and provice "a '~tof all seismic valve supports completed or presently being workec" byMarch 5, 1984. This is a ~rob em because valves that have alreadybeen disassembled to in tall the seismic supports may have alreadyviolated EQ Nuclear Safety Related Requirements and have gone unre-ported. In the instance of FCV-641A, the violation occurred 10months before the problem was officially "flagged" to ppp for EQcompliance.

Conclusion: There is an apparent deficiency in PG&E 's trainingprogram to acquaint personnel with the requirements of EQ and NuclearSafety Related Equipment.

The problems identified in the review of the attached

documents reveal significant deficiencies in the QA/QC and EQ com-

pliance requirement practices of the Nuclear Safety Related Equipment

at Oiablo Canyon Unit 2,. Even theugh the documents are restricted co

Unit 2, the witnesse" informed me that the problems they, aodpess are

generic to both Units with respect to training ana familiarity withspecialized requirements. The same people perform the same type ofwork in both units. If the practices discussea in this statement

exist in Unit 1 or Unit 2, the reliability of any EQ valve similarlydisassembled is indeterminate. Unfortunately, the reliability of

these valves is taken for granted by both the NRC and the operators ofthe plant.

I. will further discuss these issues with NRC good faithefforts to address these issues.

I have read the above -4- page statement and attached

documents, and swear under penalty of perjury, this statement is true

Page -3- of Four Pages

and accurate to the best of my belief.

Rxchara D. park

QF1:i'( -'~L S~~Mi!'.-'. R. VIE)WEB

' i<'~ - i ( Pr 'suQ Q~uPORN1A-i:!I LU1"- O81SPO COUNTY

pAy Co.am Expites Muy 9, 1986

of

Subscribed and sworn to before me this ~~ th day of Nay, 1984.r

1

Notary pub ic in ano forthe County of San LuisObispo, State

" California

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NQ. OF ASSEMBLES REQUIRED)MATERIALS PER ~HdBt Y

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@SAN /5 J 4 WJ W[~i'ki<6iViQW iUM Ks a. C.~ = 1~i

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HANGS SY)ASOIGP 2,Z2.V!~~~M ~!t.OC ON OmG +»+~—

APPROVA1

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P KC 7~EC GAS AND ~LZC J. RZC CO2<~9NY'IABLO

CANYON PROJECT ~ GENFRAL CONS RUC IONP 0. BOX 117 ~ AVILABEA:H. CALIFGRNtA 93424 ~ <ac5) 59

February 29, 1984

P. StiegerPullman Power ProductsP.Q. Box 367Avila Beach, California 93424

Oear Mr. Stieger:

Pullman Power Products is presently installing seismic'valve supports pervarious OCH's. However, no notification is being .given to J . Arnold,

.Mechanical Oepartment - Attention: Valve Maintenance, prior to ins a'llationof the supports. This could cause violation of valve EnvironmentalQualification Procedures.

Mlitten notification for each seismic valve suppor shall be given toMiscellaneous Mechanical prior to start o" work.

Valve Maintenance will issue a Valve Maintenance Report and order par s asrequired, to allow ins.allation oi the support. In this manner all. valvegA/gC and »:nvironmental gualification Procedures can be complied with.

Please supoly a lis oi all Unit 2 seismic valvepr sently being worked.,

rts ccmoleteh or

ORlGINALSlGN) D SYOA. ROCK'v="~ ~

O. A. RockwellPropre"t Field ~ng>neer

Re„iy Request d: YesOue Oate: March. c, 1984Jhrnold/RT:cb

cc: G.R.H.

J.G.

R.J.R.

V. CranstonO. Etzl er8. FriendB. HochR. ManningH. Moore

Roset aLieberMaciasToomire

FOR J@FO@B~R 8 =~pa p,y~~~

DCC

"titd ="I -'.-U!:...'Il I 0'r a PYRIC'lCI:tI Wt 0 I iIO,I'i i Gil i'I"r:'=7 . I QCJCI.„=

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lt WQt ReCOttdO'0't .htat a Nor ~ant-t.—..dna

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1 POlf~r

h»f'. P . 0. ac 1 1'cated t~ie fifoco'I

)<CCC'='4 i ) se I < avag:. fig cafe

1, con!:act. er..gir.eer'ngi al led .o ~ 0;:lls.

Cta, f 'S.. Ql i

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1 rvr. « ~ ' 1nrf «) f it%1 Q~ ~ ( )i

sl';"'s al-.d a ciia,n

L j .i:ose hangers "'.'.;at '~il,'ek scnedufa.

req i f e cl earaaces cf.' f e si.11 n red, 'n

r d cn cover fl"'.recess:-'.", et'ra ~ r ul I- N ~ l oe stan< ed

iii«lil

va.ed not ng that I;nit 2 will be t1 r<i f)(Itu'i 'red ~

,,< telf i C. ~ C ~ 1 «t« ~

r<>f'f simi f -. o Jn>., w.. r =. i n s

:r nirg bessicns

opera ci< AG S jstHSf 0 0 ~ i Ql ~ r~ .ec ss i "'c ~ T c f care..ces Qn

~'-- e OCS wl 1 I 3e Gl'Cen cij cl ~ ~ ~ > ~ S~ i if«v b4 ~ 1

"":l s:ane i

sat.e<f vi slofl.

C.ntrac".or suoer vi s ion.cover i.-e «1'. i be ir.creased in c;,e ='~'d b" P.f.=.C. ara ~ n . =

i~Ai

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Qnng g4 g~lstgwgge-"«r]amIg g'~a'hrd Qh

The Durpose of this training outline is to amiiiarize Maintenance Oepar-.mentpersonnel with requirements and responsibilit es o the "=nvircnmentai qua!ifi-ca" icn P, ogram.

I'NTRQOUCTION

A major catagoiy addressed in assuring safe operation of nuclear oower oi«ntsdeals wIth equipment operation under var"Qus envirnnmentaI conditions. Simplystated, if the equicment is required to operate, during and after a worst case«cciden"., wo - v that the ecuiom nt an ocerate in .an environfi'Ien simiilar- Q 'h .one aused -b asuch.. an ace~gent,. To verlfy Qperabl 1iy qulpme'It iocn=-

'fied as oeing potential y exposed to accident nv.'ronments - =nvironmentaI Iyual if'.ed throunh 'laboratory tests and/or enginee. ing analysis.

OKF!NITION OF ~NVIRONHENTAL OUALIFTCAT1GN

Knvironm ntally qualified (=.g.) eqvipment is' special cataoorv of ~af -v R !

V t«e~uiomen.. Th«;:5 equ piiient is not only required for safe control of tneplant but may also be requir d to operate in extreme environmenzs of adversetemperature, pressure, humidity, chemistry and radiation that could oc ur durino

-«nd fol!owing a Loss of Coolant Accident (LOCA) or a Hain Steam 'ne Sr ak (.".: ).~asicaliy, this means that the equipn>eni must not fail under severe envi Qnmen -"!"Qr di-ions resul"ing «rem a major pTant accicent. Another =.g. "Qns;cere-.:cr<scen-ifies equi"men- which mus- fail in a safe -Qd during an ac"ident Qr munich-ust survive for only a short period after an acc;dent. I(ge ui!I ene'r«ll.'/ address-.ne first reouirement since i is most demand;ng. Currently, =.g. has beendirac=ad -,award eiecarical equicmenc; however, in -h -,wn;re "hi.expand to IIIost. othe? -~QI io! I nt incIudlnQ 52'5« I'Ic considera'ons ~ n for. al esc. Ip-ion of : , taken from NRC . equirements ard used as the 'as-is for ur Acm-nis-.-.;--

Proc dur 0-/.=a stat s that,

"...electricaI equioment shall nave been environmentall/ "uaiifieo -or"he environment in ~hich it nas to operate and for the nviron-ent :n '.vh c. i-.would operate during or =ollowing an accident."

"...measures are required to ensure that the envircnmen-.ai ualification.of his eauipment be maint.ined as it ages =-."" after I 29air or ":- i emen-.."

. ~ .. ~ r r'r 3 rlrlr(gr «: «rlr( +t ~ ( rnqv + +gg (/( ~ „,, v '~ I'nac vvnd w iC v s law; ~-r ii I(picj a IIer«! > / a ~ 'rl da - -I

~ t ~ ~

.O. AFF""CTS ON PAINT"NPNC-

nce dccurientation "reo«provide detai«ed descr

ur nalysis (-~e,o-'ng;on o-. E.q. come~i en=5

insur that res!= e.:enmen-. Qr-ginai Iy -;es"ed

:n addii-'icn to 'he maint na:(e ."..ust, on E.g. equipment,"erfQr™ed as input, or ai I5 i cn5 of aaina or degradatii:enarce or"cedure. Sec"nd,=.ar=s as"ambled In the

«qu'«r«iotions o5 tuc'/

~ rI ~ I

V IV ~

and/or =

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I+ ga< I Q

r I« I '~

tQI c

a v

(ol '(rec /'

~/ I a/

sua ln-

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PACIFIC GAS 5 ELEC'RIC COMPANYOEPARTMEHT OF NUCLEAR PLANI OP"=pTIONS

OIABLO t.ANYON PO'rlcR P nNT

GCPP MAIiNTKHANCE TRAINING MANUAL

COURSE NO. MA050 . „

ENVIRONMENTAL QUA'F:CATIONMAINTENANCE TRAINING

RK'/ISION 0JUNE i le~2

PRRRRRFD BY)

APPROVE~ BY

J~ ~

1

4

<„:m araoie -ar: numbers:Ii ii usuaiiv sa-.;siy:.". - "==;:-=;.-=-;- - ":.

a manu=ac-.ure. s suooeszed "aoual r placement" is llOT acceo-.a '=- :n :.'", = .-

uniess E.g. is'pec.-,ically addressed. :,')RC reouiremen ~~"latefiai chanc n -: o =" ordance with the orioinal desicn reouiremeni-s environmental ouali='-'

'

. o'n-.=- and

Yiaierials considered susc pt ble to postulated worst case environment r ailrrom non-metal iic groups. Examples wh ch we will encounter are: motor and ableinsuiazions, luoric nts, seals, molded switch mat r als, ask t ma'.. iais andspeci'al conductor t rminations.

Beyond .he addition mainten-nce doc men-.ation need anc ""~ ~~-ra ca~~ n"-c~ -arv'n oar";s identirication and reolacemen -1 "oood, i ~nance orac-.ices"shouio ensure ooerao e eouicment under. ai ~environmental conditions. Attention'o suooi>er assembly instruc:ions wher. provided = ~-ui aaske- oreoarat;onano o acemenz, proper connec=or torauino and strict adherence to the aopiicaoiemaintenance proceoure ws I guarantee a succ'es I orooram.

REQUIRB1Ei'ITS FOR E.O.

:hiiI, -, Etl. g~8 1' i IC.'.

=.'d. program was issued as Adeinistrative Proc dure ~N ao -s and ;he de='tiledmethods and instruc ions by which ue actually accomoiish -".g. are shown in -"~

~0-75 iiuestions not answer d in this E.ii. trainino outline should ha coveredin the latter procedure.

eoiAp

'ilhen you repairi l ke thl s:

or maintain eauipmenz iden@i=ied wish a brien- orance ".ias: c 'ag,

s a ehe

as

or are assigned APPR's, Snoo

I

Vork Followers or any work dir'ec=ing =or;„s-amped

~ ~~, r'ai

a "."-- r=vie:i - o a""iicabie main-enan"= ."r"cedur . "=ive O'J rarts w'i zh s cen

was per 07 ..-"

eSZ1nc.

;= :.".=- soec;ai =.g. comiooner..s, r piac c.g. paand caresully document what "s,aintenance or . epa.-a~erisal apoearances and ir =.g. components 'ai

~ IvU I ~ ~I wC: ~ .0

,io ~

x-.. ~ i ~- . ' '-

~

~ ~ \ ~

~ ~

~ ~ ~ t ~ $ t t% ~ tQt'~ ~ Ig ~ m I

=".vironrrentaiiy guaI ivied Qu'Q,ien- he! ps "s;„ainormai opera-.icns and in accident conditions.

2. The c nv ironm nza I qua I i=ication P rooraa providesnecessary to;.,ainzain quaii-.ied equipment in des

~ o= the pianz.

"he orcan zation a..d "uidanceign ccndi-:ion =or the Ii-.e

3. "- herence to the c..g.reauiataons.

Program assures comaliance uith iRC cuiceiines and

I»

» ~ ~ ~

~ \

»ttY [p(s ~ ~ zrlt t ~ ( y rILtpL!.» + rjU wa ~ r»+i~

L1s includes only those currently designated E.q. devices assigned as='l4c ricai/l!echanical Maintenance l 4sponsibll lay. '.KC associatec detl3c4s arelisted separately. Refer to "contro'lied listing" of E.Q. devices if uo--;o-dateaccuracy is required.

e.'.",'RS -1E;";RS-2FCV-350FCV-363FCV-357."CV-440FFCV-641AFCV-0418FCV-749FCV-750LCV-'06LCV-107LCV-108LCV-'09LC /-110Lct( 1

'llI l»YLCV-1SGOOA

BOO QB.

SQOOC

807c.'0788

8078C80780SLQ5810581078112870I87028716A87168

II 1HII

FiLE NO.

c02028

1516161616iaTa

12121Z1414t

147bibib

L"L»'I

5L»16'l 010

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I or

16

Rotork NOV -————-—II II

Llm1toraue i410V ———--

ill Gen. Cntls. EHOV—II II

II II

II II

Limitoraue HQY

Targ - Rock SOV ——-—II II Il

Llmitorque '10V --—---

OM H, Recombiner --'----II ll

II flgll

FILE NO

8801A880.1888GZA880288803A880388804A880488805A880 88807A880788809A880988821A8S21888358976808Q9G03A90038

Limitorque,'iOV

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Rl-'R Pur o 1-1CC PumaC one. c ert P nSpecial.Cables-inside Cont.-LOCA Seals - QZ "=edney —-—-LGCA Soi'ces - ~=vc.'".em ---—-

~ ocedures, /PPR ', Shoo; ork Foi i o,vers, er=idocuments, HKS action documents and/or o-.her ceca. ent should be stamoed "K.g." and forward d -.o thal 0 .vith a comoleted Recora Nanarement System?3':S ( 1 gib I e cool es acceptao l "-

rds relat14 On-S I t=nous -cr,.

nc :0 aoov4 acuI I)arrl J I»

-~y -. 1)I 4»I)

6/82

4 ve I 5+~A.-/

«e', ~

~ ar e ~ r«e s« ~ ~ e.e«W ~ . e «~o e«e« -«1»

V~esses g S «qr«mee ~ Sesr«~ ee s~

'Cq' 'g~»st ~~ /~~ 4m

V~«e

l J C s. maes mmseeee «ss~

«aw. iP ~5" 34:c 010

V've ~ .5 Vaj:se g~e . s800 '7~>ee ~CV-i4 lA

P~l~~ ~ fjjT~'0+fT

Tread me \e «m.4a8 m

-- 'c'~T - R ~%M.. ~M QR >~4 - ~

G HANG~~ ZNSTALLATXON BY .; .P,, Sr= ..W 4 4490

:OR P~~cIC-.

ROKKVZAL QUALZ~CATTON OF ~< VALVE SaALL 3E PR~MER~ AS OU.-

~.r ~G~Z OF AC~ FLAN'PWrONS ~ROCZURZ O-7:-6 ANO ~-SS.S.

re

t ~

~ ~

~gg «ee»

ALL '«ORK P~ KF QCM-5.

R:--D )0 L QTCROU:" ~fkiWAL DC"1i32~9-629-L.

DTSASS~c.BL= ACiiATOR 5 QfS2ECT Li5ALS FOR OA.-(GZ. OC ~M '-PT-S~./ ~ +r lZVi~i:A~ ~ Do~. S~c. ~ VALVc. t."IVV'C

.=~.~mZ:...." ~~ DAi~CCZD P42. S 70 A~ATOR, S~ 5 VALVE AS '..=wB. 1Cc

k,~~gC=~ w="ie

.-'ZD KZON:PAUL~ ~O GZ=-'eSE AS '.F c3 O .AZ.Z'Z.". A~PROX.

:C ~W ~C'Z=--P~~ e ~ r e ~ ~

kC- aA . ~PKGc3 GaSc = S 4/ANC-ORx.c.;4(. A~i=... - 3e =O'.ca.ri'~ P~r.g/0 CH~+~ fW r '~/WQc...e&t i- =-zS

".C (1 e~~

I

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e

s e ~ ss««~ i

e%

a~~ /1

~ \I !'

~~ ) 1 II» ~ ~ i 11«\ )I»w ~ 1)I ~

e II «I')~ ~ q»

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W0 0» %014)»

~ ~

~~~/ g) ~ /g» /~ g) /

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&g+ I-Lg

fg N ~ Pg)$)fI)~) t) I)IIIjj g

~ ~4C «e

e m~le~

urn firrg.'P)C 7 /~A n~ B<c ~zZ» rR rr~-''~~=~i 7 AN 1 ~

),W~IP I

CW~lr~P gCe re ~~=c~8W r' >Pi- - ~

I ~ ~:w8 r'rFN Her 7 = ~

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~ pggl rr r rr g \

Enclosure 3

DOCUMENTS LIST REFERENCED AT MAY 9 g 1 9 8 4 NRC PG &E MEETING

The May9, 1984 transcript pages where these doc-ments are referenced are in parentheses after each item.

1. Criterion M-9. (p.52)

2. Project engineering construction procedure PEI-12.(p.201)

3. "Last three procedures written for control of DP'swithin engineering." (p.217)

4. ESD-223. (p.218)

5. GC-PI-17. (p.220)

6. I-37. (p.220)

7. I-40. (p. 220)

8.

9.

D-16. (p.220)

All of the procedures referenced by Mr. Tressler onp. 227 for items already referenced in Sl-8 above.

10. The 18-24 inches of procedures referenced by Mr.Knight pages 247-248, except for items already referencedin 51-9 above.

I

lrIf

I