ACCELERATED DI TRIBUTION DEMONSTRATION SYSTEMr

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9204170227 DOC.DATE: 92/03/31 NOTARIZED: NOFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1, Pacific Ga

50-323 Diablo Canyon Nuclear Power Plant, Unit 2, Pacific GaAUTH.NAME AUTHOR AFFILIATION

HELETE,D. Pacific Gas & Electric Co.DAHAN,P.G. Pacific Gas & Electric Co.MAYER,M. L. Pacific Gas & Electric Co.

RECIP.NAME RECIPIENT AFFILIATION

DOCKET N

0500027505000323

SUBJECT: Monthly operating repts for Mar 1992 for Diablo Canyon Units1 & 2.W/920410 ltr.

DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR I ENCL f SIZE:TITLE: Monthly Operating Report (per Tech Specs)

NOTES:

D

RECIPIENTID CODE/NAME

PD5 LAROOD,H

INTERNAL: ACRSAEOD/DS P/TPABNRR/DOEA/OEABRGN5

EXTERNAL: EG&G BRYCE,J.HNSIC

COPIESLTTR ENCL

3 31 1

10 101 11 11 1

1 11 1

RECIPIENTID CODE/NAME

PD5 PD

AEOD/DOANRR/QL - L B10REG - 01

NRC PDR

COPIESLTTR ENCL

1 1

1 11 11 1

1 1

D

D

R

I

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NOTE TO ALL"RIDS" RECIPIENTS:

D

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PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTIONLISIS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24

' '0'1

ti

Pacific Gas and Electric Company

April 10, 1992

Diablo Canyon Power Plant

P.O. Box 56Avila Beach, CA 93424sosls4s-6o'oo

John D. Townsend

Vice President-Diablo Canyon

Operations and Plant Manager

U.S. NUCLEARREGULATORY COMMISSIONAttention: Document Control DeskWashington, DC 20555

RE: Docket No. 50-275 and 50-323License No. DPR-80 and DPR-82Monthly Operating Report for March 1992

GENTLEMEN:

Enclosed are the monthly operating reports for Diablo Canyon Units 1 and 2 forMarch 1992. This report is submitted in accordance with Section 6.9.1.7 of the Units1 and 2 Technical Specifications.

Sincerely,

T:maz

Enclosures

cc Mr. John B. Martin, Regional AdministratorU.S. Nuclear Regulatory CommissionRegion V1450 Maria Lane, Suite 210Walnut Creek, CA 94596-5268

Ms. Liz Hannon, PresidentUtilityData Institute, Inc.1700 K Street, NW, Suite 400Washington, DC 20006

0.00004

9204170227 920331

c

PDR ADOCK 05000275R PDR .

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4

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MON'HK,YNARRATIVEREPORTOF OPERATION

AND MAJOR MAINTENANCEEXPERIENCE

This report describes the operating and major maintenance experience for the month ofMarch 1992. This narrative report was prepared by the Plant Staff and is submitted inaccordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.

rr i fDil i ifi n l E

On March 1, 1992:

On March 6, 1992:

Unit 1 and Unit 2 started the month at 100% power.

A 10 CFR 50.72 (b)(2)(ii) non-emergency 4-hour report wasmade regarding an unplanned Unit 1 automatic reactor tripdue to a low-low steam generator (SG) water level. The SGlevel transient occurred after a main feedwater pump (MFP)overspeed trip due to failure of- the inverter power supply forthe MFP speed probes. For more information see LER 1-92-002.

On March 11, 1992:

On March 14, 1992:

Unit 1 returned to 100% power.

Unit 2 ramped down to 55% to implement a design changethat provides a separate power supply to each of the twospeed probes on each MFP.

On March 15, 1992:

On March 22, 1992:

Unit 2 returned to 100% power.

An Unusual Event (UE) was declared due to an unidentifiedflow restriction in main steam lead no. 2. The turbine stopvalve was declared inoperable and a Unit 2 manual shutdowncommenced as required by Technical Specification 3.3.4.1.The event was reported to the NRC as a non-emergency 1-hour report in accordance with 10 CFR 50.72(b)(1)(i)(A).Unit 2 entered Mode 3 (HOT STANDBY) and the UE wasterminated. For more information see LER 2-92-003, whichwillbe submitted.

On March 27, 1992: Unit 2 entered Mode 2 (STARTUP).

S:>NRCRPTWPVQ'RIL92.MAZ

ilk P

I

On March 28, 1992: Unit 2 entered Mode 1 (POWER GPERATION).A 10 CFR 50.72(b)(2)(ii) non-emergency 4-hour report wasmade regarding a Unit 2 spurious Containment VentilationIsolation (CVI) actuation, a control room ventilation systemshift to the pressurization mode, and a fuel handling buildingventilation system shift to the iodine removal mode. - Theseevents constitute Engineered Safety Feature (ESF) actuations.A voltage transient caused a momentary loss of AC power.The loss of AC power caused the ESF actuations. For moreinformation see LER 2-92-004, which willbe submitted.

On March 29, 1992:

On March 31, 1992:

Unit 2 returned to 100% power.

Unit 1 and Unit 2 ended the month at 100% power.

ni h

Unit 1 operated this month with a unit availability factor of 88.3% and a unit capacityfactor of 84.6%. Unit 1 reduced power once this month due to an automatic reactor trip.

Unit 2 operated this month with a unit availability factor of 82.2% and a unit capacityfactor of77.7%. Unit2 reduced power twice this month, once due to the implementationof a design change to main feedwater pump 2-1 and once due to a manual unit shutdown.

i nifi RI

o The seat to flowUnit 2 control valve (FCV) 144 was weld repaired and machined.The stop valve shaft and disk were replaced.

r f r r

There were no challenges to the steam generator safety valves or the pressurizer poweroperated relief valves.

S:hNRCRPTWP>APRIL92.MAZ

OPERATING DATAREPORT

PERA TA

DOCKET NO. 50-275UNIT 1

DATE 04/01/92COMPLETED BY D. HELETETELEPHONE (805) 545-4696

l.2.

3.

4.

5.

6.

7.

8.

9.

10.

Unit Name:

Reporting Period:

Licensed Thermal Power (MWt):Nameplate Rating (Gross MWe):Design Electrical Rating (Net MWe):Maximum Dependable Capacity (Gross MWe):Maximum Dependable Capacity (Net MWe):Ifchanges occur in capacity ratings (items

3 through 7) since last report, give reasons:

Power level to which restricted, ifany (Net MWe):Reasons for restrictions, ifany:

Diablo Canyon Unit 1

March 1992

3338

1137

1086

1124

1073.4

N/AN/AN/A

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

25.

Qi~ml gii60502.3

50421.6

0.0

49582.3

0.0

155289430

52268532

49551495

82.0

82.0

76.3

75.4

3.7

2184.0

2106.9

0.02096.6

0.0

6940984

2326300

2213335

96.0

96.0

99.4

93.3

4.0

Hours In Reporting Period

Number Of Hours Reactor Was Critical

Reactor Reserve Shutdown Hours

Hours Generator On-Line

Unit Reserve Shutdown Hours

Gross Thermal Energy Generated (MVH)Gross Electrical Energy Generated (MWIQNet Electrical Energy Generated (MWH)Unit Service Factor

Unit AvailabilityFactor

Unit Capacity Factor (Using MDC Net)Unit Capacity Factor (Using DER Net)

Unit Forced Outage Rate

Shutdowns Scheduled Over Next 6 Months

(Type, Date, and Duration of Each): Refueling Outage - September 15, 1991 - 63 days

IfShut Down At End Of Report Period, Estimate Date of Startup: N/A

SANRCRFPYVP>APRIL92.MAZ

AVERAGE DAILYUNIT POWER LEVEL

DOCKET NO.UNITDATECOMPLETED BYTELEPHONE

50-2751

04/01/92D. HELETE(805) 545-4696

MARCH 1992 DAY

1

23456789

1011

1213

1415

16171819202122232425262728293031

AVERAGE DAILYPOWER LEVEL(MWe-Net)

10691065106410651064444-30-38-43193

101910691065106410651069106410691065106510651065106510681065106010641052106510651060

INSTRUCTIONSOn this format, list the average daily unit power level in MWe-Net for each day in the reporting month.Compute to the nearest whole megawatt.The Average Monthly Electrical Power Level for March 1992 = 908 MWe-Net

S:ENRCRPTWPEAPRIL92.MAZ

UNIT SHUTDOWNS AND POWER REDUCTIONS

.DOCKET NO. 50-275UNIT 1

DATE 04/01/92COMPLETED BY P. G. DAHANTELEPHONE (805) 545-4054

REPORT MONTH'ARCH 1992

None

~ 920306

':;:;:=:.DURATION,:'::;:.:;,'.

~,„-'",.:";(HOUR$}'„.:'-,''„"'-'.

87.4

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,:,'-:,:ME'IHOD':OF,,:"",',.-,,::Pi':EVENTIDE~!~SHUTDOWN:,,.::::,„";: '„-'"'~"::REPORT::.-'.",':::;.;

1-92402 SJ

'@COMPQNENF,".,'NVT

,;=::,'CAUSE.'."4"::.CORRECTIVE::.'=:

",.-,'."ACHON,-TO!PREVENT',"-;:."-;:,

'-::;:;:i:',.'",'.'i".::,';":;:"'.RECURRENCE:.'-":;"'„:,";:,.'::'.,'„:"-,.'„."':

Unit 1 reactor tripped dueto MFP speed probe powersupply inverter failure. Aseparate power supply toeach of the two speedprobes on each MFP wasprovided

Type:F-ForcedS-Scheduled

Reason:A-Equipment Failure (Explain)B-Maintenance or TestC-RefuelingD-Regulatory RestrictionE-Operator Training &License ExaminationF- AdministrativeG-Operational Error (Explain)H-Other (Explain)

Method:1-Manual2-Manual Scram3-Automatic Scram4-Continuation from

previous month5-Power reduction6,7,8-N/A9-Other

Exhibit G-Instructionsfor Preparation of DataEntry Sheets for LicenseeEvent Report (LER) File(NUREG-1022)

5Exhibit I - Same Source

S:hNRCRPTWPVQ'RIL92.MAZ

REFUELING INFORMATIONREQUEST

DOCKET NO. 50-275UNIT 1

DATE 04/01/92COMPLETED BY M. L. MayerTELEPHONE (805) 545-4674

1. Name of facility: Diablo Canyon Unit 1

2. Scheduled date for next refueling shutdown: September 15, 1992 (estimated)

4.

Scheduled date for restart following refueling: November 1992 (estimated)F

Will refueling or resumption of operation thereafter require a technical specificationchange or other license amendments Ifanswer is yes, what, in general, will there be2Ifanswer is no, has the reload fuel design and core configuration been reviewed by yourPlant Safety Review Committee to determine whether any unreviewed safety questionsare associated with the core reload (Ref. 10 CFR Section 50.59)2 Ifno such review has

taken place, when is it scheduled2

No. The PSRC is scheduled to review the cycle 6 core reload in September 1992(estimated).

5. Scheduled date(s) for submitting proposed licensing action and supporting information:N/A

6. Important licensing considerations associated with refueling, e.g., new or different fueldesign or supplier, unreviewed design or performance analysis methods, significantchanges in fuel design, new operating procedures: N/A

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

(a) 193 (b) 288

8. The present licensed spent fuel pool storage capacity and the size of any increase inlicensed storage capacity that has been requested or is planned, in number of fuelassemblies:

Present 1324 Increase size by 0

9. The projected date of the last. refueling that can be discharged to the spent fuel poolassuming the present licensed capacity: 2006 (Loss of full core offload capability)

S:)NRCRPTWP)APRIL92.MAZ

c) 4k"

OPERATING DATAREPORT

PERA

DOCKET NO. 50-323UNIT 2DATE 04/01/92COMPLETED BY D. HELETETELEPHONE (805) 545-4696

2.

3.

4,

5.

6.

7.

8.

9.

10.

Unit Name:

Reporting Period:

Licensed Thermal Power (MWt):Nameplate Rating (Gross MWe):Design Electrical Rating (Net MWe):Maximum Dependable Capacity (Gross MWe):Maximum Dependable Capacity (Net MWe):Ifchanges occur in capacity ratings (items

3 through 7) since last report, give reasons:

Power level to which restricted, ifany (Net MWe):Reasons for restrictions, ifany:

Diablo Canyon Unit 2

March 1992

3411

1164

1119

1137

1087

N/AN/AN/A

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

25.

Xbiianfh YTD2184.0

2072.9

0.02051.8

0.0

6855038

2274700

2168293

94.0

94.0

91.3

88.7

6.1

Hours In Reporting Period

Number Of Hours Reactor Was CriticalReactor Reserve Shutdown Hours

Hours Generator On-Line

Unit Reserve Shutdown Hours

Gross Thermal Energy Generated (MWH)Gross Electrical Energy Generated (MWH)Net Electrical Energy .Generated (MWH)Unit Service Factor

Unit AvailabilityFactor

Unit Capacity Factor (Using MDC Net)Unit Capacity Factor (Using DER Net)Unit Forced Outage Rate

Shutdowns Scheduled Over Next 6 Months

(Type, Date, and Duration of Each): None

IfShut Down At End Of Report Period, Estimate Date of Startup: N/A

Qi~i~li~v53061.0

44235.0

0.0

43405.3

0.0

141086017

46938299

44554162

81.8

81.8

77.4'5.0

4.9

S:ENRCRFI WPFAPRIL92.MAZ

~ .

AVERAGE DAILYUNIT POWER LEVEL

DOCKET NO.UNITDATECOMPLETED BYTELEPHONE

50-323204/01/92D. HELETE(805) 545-4696

MARCH 1992 DAY

1011

1213

141516171819

202122232425262728293031

AVERAGE DAILYPOWER LEVEL(MWe-Net)

10841084107910791079107910831079107610701083107510831009566

107010751079107510751071997-24-27-26-30-36108968

10911096

INSTRUCTIONSOn this format, list the average daily unit power level in MWe-Net foi each day in the reporting month. Compute tothe nearest whole megawatt.The Average Monthly Electrical Power Level for March 1992 = 844 MWe-Net

S:>NRCRPPVP>APRIL92.MAZ

JF

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l

UNIT SHVH)OWNS AND POWER REDUCTIONSDOCKET NO. 50-323UNIT 2DATE 04/01/92COMPLETED BY P. G. DAHANTELEPHONE (805) 545-4054

REPORT MONTH'ARCH 1992

920314

''„„;-:TYPE,,::;:;j::-':,;'-;:,;DUR'ATION;~

0

gREASOhP,-'.::

B

::::-":m~HOD,":OFg "';--.,'+im:,:-; SHVmOVg8'.,;=,:;;.-",REPOjT;.::" -.:,::;.COOS',,';.=„.''-:,-

N/A

.Q':,~X'-:,'.-',.',COMPONENT.:,::,:.:

INVT

i,",'CAUSE:"ki;":CORRECTPfE;:'-:!FACTION':T~O'PRBVBRF"

.;,,.:,.';::''".:::.'.-„::-:RECUISBNCEjjl :':

Unit 2 ramped down to55% to implement a

design change thatprovides a separate powersupply for each of the twospeed probes on eachMFP.

920322 132.2 A 2-92403 SB FCV Unit manually shutdowndue to a flow restriction ina turbine stop valve.Turbine stop valve wasrepaired.

Type:F-ForcedS-Scheduled

Reason:A-Equipment Failure (Explain)B-Maintenance or TestC-RefuelingD-Regulatory RestrictionE-Operator Training &License ExaminationF- AdministrativeG-Operational Error (Explain)H-Other (Explain)

Method:1-Manual2-Manual Scram3-Automatic Scram+Continuation from

previous month5-Power reduction6,7,8-N/A9-Other

Exhibit G-Instructionsfor Preparation of DataEntry Sheets for LicenseeEvent Report (LER) File(NUREG-1022)

5Exhibit I - Same Source

S:>NRCRFP1A'>APRIL92.MAZ

D

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REFUELING INFORMATIONREQUEST

DOCKET NO. 50-323UNIT 2DATE 04/01/92COMPLETED BY M. L. MayerTELEPHONE (805) 545-4674

1. Name of facility: Diablo Canyon Unit 2

2. Scheduled date for next refueling shutdown: March 1, 1993 (estimated)

3. Scheduled date for restart following refueling: May 1993 (estimated)

4. Will refueling or resumption of operation thereafter require a technical specificationchange or other license amendments Ifanswer is yes, what, in general, will there beIfanswer is no, has the reload fuel design and core configuration been reviewed by yourPlant Safety Review Committee to determine whether any unreviewed safety questionsare associated with the core reload (Ref. 10 CFR Section 50.59)Y Ifno such review has

taken place, when is it scheduled'

No. The PSRC is scheduled to review the cycle 6 core reload in February 1993(estimated).

5. Scheduled date(s) for submitting proposed licensing action and supporting information:NA

6. Important licensing considerations associated with refueling, e.g., new or different fueldesign or supplier, unreviewed design or performance analysis methods, significantchanges in fuel design, new operating procedures: NA

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

(a) 193 (b) 308

8. The present licensed spent fuel pool storage capacity and the size of any increase inlicensed storage capacity that has been requested or is planned, in number of fuelassemblies:

Present 1324 Increase size by 0

9. The projected date of the last refueling that can be discharged to the spent fuel poolassuming the present licensed capacity: 2006 (Loss of full core offload capability)

S:)NRCRPTWPLAPRIL92.MAZ

I

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