ML20082G313

Monthly Operating Rept for Jul 1991 for Pilgrim Nuclear Power Station

ML20082G313
Person / Time
Site:	Pilgrim
Issue date:	07/31/1991
From:	Richard Anderson, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-105, NUDOCS 9108190022
Download: ML20082G313 (8)

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BOSTON EDISON l Pilgnm Nuclear Power Station '

Rocky He Road l

Plymouth, Massachusetts o236o '

hbe Pr s ent August 13, 1991

['u'Na"r o"[Er'atons BECo Ltr. #91-105 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293

Subject:

July 1991 Monthly Report

Dear Sir:

In accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. Should you have any questions concerning this report please contact me directly.

M R/A. Anderson (J

HJM/bal Attachment cc: Regional Administrator, Region 1 U.S. Nuclear Regulatory Conalission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector pi 91081900'22 910731 PDR ADOCK 05000293 "

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., - AVERAGE DAILY tjNIT POWER LEVIL DOCKET NO. 50-293 UNIT Pilarim 1 i DATE Auaust 13 1991 ,

b8 7 -8474 HONTH July 1991 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  ;

(HHe-Net) (MWe-Net) 1 0 17 0 7 i

2 0 18 0 l 3 ._,

0 19 0 4 0 20 0 5 0 21 0 l' 6 0 22 0 l

7 0 23 0 l 8 0 24 0 .

i 9 0 25 0 10 0 26 0  :

i 11 0 27 0 i

12 0 28 0 13 0 29 0  !

14 0 30 0 l i l 15 0 31 0 l

16 0 l This format lists the average daily unit power level in HHe-Net for each day l in the reporting month, computed to the nearest whole megawatt. l i

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BOSTON EDISON COMPANY

. PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Qp_erational Summarv for Ju_}v 1991 Continued refueling outage number 8.

Safety Relief Valve Challenges .

Month of July 1991 1

i Requirement: NUREG-0737 T.A P. II.K.3.3 l

l There were no sa'ety relief valve challenges during this reporting period.

L An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo ,

ltr. #81-01 dated 01/05/81. ,

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' - *l OPERATING DATA REPORT DOCKET N0. EO-293 DATE _6Maustl3. 1991 COMPLETED BY W. Munro TELEPHONE (508) 747-8474 OPERATING STATUS Notes

1. Unit Name Pilarim 1

2. Reporting Period July 1991

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678

5. Design Electrical Rating (Net MWe) 655

6. Maximum Dependable Capacity (Gross MWe). 696

7. . Maximum Dependable Capacity (Net HWe) 670

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To Which Restricted, If Any (Net MWe) None

10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumyld!u

11. Hours In Reporting Period 744,0 5087.0 163415.0

12. Numbcr Of Hours Reactor Has Critical 0Q1 2850.2 95450.9

13. Reactor Reserve Shutdown Hours 0.2D 0.0 0.0

14. Hours Generator On-Line 0.0 285Q12 91766.3

15. Unit Reserve Shutdown Hour, 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0.0 _E276592.0 158618088.0

17. Gross Electrical Energy Generated (MWH) 0.0 1812180.0 53459694.0

18. Net Electrical Energy Generated (MWH) 0.0 17438222 Q _11370230.0

19. Unit Service Factor 0.0 56.0 56.2

20. Unit Availability Factor 0.0 56 tQ 56.2

21. Unit Capacity Factor (Using MDC Net) 0.0 51.2 15.2

22. Unit Capacity Factor (Using DER Net) 0.0 52.3 48.0

23. Unit Forced Outage Rate 0.0 3.6 12.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None 25.'If Shut _Down At End Of Report Period, Estimated Date of Startup 8/11/91 lJ l

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REftJELING INFORM &IlQt!

'The following refueling information is included in the Monthly Report ~ as requested in an NRC letter to BECo, dated January 18, 1978:

For your convenience, the information supplied has been enumerated so that, each number corresponds to equivalent notation utilized in the request.

1. The name of this facility is Pilgrim Nuclear Power Station Docket Number 50-293.

2.- Scheduled date for next Refueling Shutdown: April 3, 1993

3. Scheduled date for restart following present' refueling: August 11, 1991

4. Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6.

5. See #6.

6. The new fuel loaded during the 1991 refueling outage was of the same ,

design as loaded in the previous outage, and consisted of 168 assemblies.

7. (a) There are 580 fuel assemblies in the core.

(b) There are 1489* fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel .

assemblies. The actual usable spent fuel storage capacity is 2320 fuel assemblies. 5 (b) The planned :: pent fuel storage capacity is 2320 fuel assemblies.

9. Hith present spent fuel in storage, the spent fuel pool now has the ,

capacity to accommodate an additional 831 fuel assemblies.

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Month July-1991 PILGRIM NUCLEAR P0HER STATION

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MAJOR SAFETY RELATED MAINTENANCE SXSIEH COMPONENT' RALEQNCTION CAUSE -MAINTENANCE CORRECTIVE ACTION TO: ' ASSOCIATED .

PREVENT RECURRENCE LER Reactor Heat Exchanger Hairline cracks Metal fatigue Repaired welds and Perform inspection- N/A Building E-2098. on partition installed (6)= stiff- during RF0 9.

Closed plate-to-shell ener plates to each Cooling welds. partition plate per Hater FRN 91-03-30, prov-(RBCCH) iding greater resistance System to fatigue failure. ~i Leaking tubes Corrosion and one (1) tube required inlet end plugging, and ninety-erosion. eight (98) other tubes required replugging.

There were also 1593 sleeves installed on inlet end.

Main Reactor vessel False high Undersized Implementation of Plant N/A LER 91-008-00

• Steam water level . reactor level . equalizing line Design Change PDC.91-40 l (MS) instrumentation. signals from vessel to to replace the one (1)

System caused Group 1 condensing inch equalizing line l 1solations. chambers. with a two (2) inch line between the reactor vessel and the condensing chambers. ,

Reactor Loop "B" Pump cart- Pump seal End of useful Replaced seal cartridges Refer to associated LER 91-007-00 i Recirc- ridge type dual failure. life. in both A and B pumps LER. ,.

ulation mechanical seal during RF0 8.  !

System (Byron Jackson pur.,is Inc.)

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Month July'1 FJ J PILGRlH NUCLEAR P0HER' STATION MAJOR SAFETY RELATED MAINTENANCE -

SYSTEM COMPONENT MALFUNCTIQN CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE . .

LER Salt Loop 'B' piping Identified Excessive corro- Removed and replaced Unlined spool piece N/A Service within the intake wall thinning. sion and delami- various rubber lined will be replaced during Hater structure. nation of rubber spool pieces within midcycle outage. (1992)

(SSH) lining within the intake structure.

System spool pieces. Temporary Modification 91-32 implemented, replacing one (1) rubber lined spool piece with an unlined spool piece.

Salt Pump P205A air Ball cup ears To be Temporary Modifica- Inspect pumps P-208 B N/A Service vent valve (2 of 4) determined implemented to rep- thru E air vent valves Hater broken. lace Crispin brand and replace as necess-(SSH) SSW pump air vent ary. Vent valves for System valve (bronze) with P-208 A thru E to be cast iron Val-matic replaced with Crispin model 102HS. brand (bronze) valves when available.

Mair. Main steam safety As found pop- Setpoint drift. Valves disassembled. Prior to restarting LER 91-014-00 Steam valve (Dresser) S/N ping press- inspected, reworked, from RF0 8, all valves (MS) BK6262. Pilot ure outside and reassembled by installed in the System valves for main Tech Spec applicable pressure relief system steam relief valves limits. manufacturers.Certi- will have been refur-(Target Rock) fication testing by bished, tested, and S/N 1049 and 1054. by Hyle Labs. certified to be within Tech. Spec. Refer to associated LER.

UNIT SHUTD0HNS AND 'OWER P REDUCTIONS DOCKET NO. 50-2 H -

NAME Pilar *m 1 .  ;

DATE Aucust 13.1911. ', .

COMPLETED BY H. Munro -

TELEPHONE (508) 747-8474 -

REPORT MONTH July 1991 l

METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEg 4ENT ACTION'TO PREVENT NO. DATE TYPEI (HOURS) REASON 2 DOHN REACT 0n3 REPORT # CODE COMyE COD RECURRENCE 8 05/04/91 S 744.0 C 4' N/A N/A N/A Refueling outage No. 8 (continuation) i I

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1 2 2 3 4&5 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Haint or Test G-Oper Error 2-Manual' Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheat E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-1022)

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