ML20079C135

Monthly Operating Rept for May 1991 for Pilgrim Unit 1

ML20079C135
Person / Time
Site:	Pilgrim
Issue date:	05/31/1991
From:	Richard Anderson, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-91-80, NUDOCS 9106180457
Download: ML20079C135 (7)

Text

ROSTON EDISON tv anm Nuotar Naer staten nDCI V Hill nO8d Plymouth, Manathusetts o2300 e sde$tY I!v'$1S78.7,on, June 14, 1991 BECo Ltr. #91- so U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 D.ocket No. 50_2.93._

Subject:

Hay 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.

/

R.A. Anderson (N/

HJH/bal Attachment cc: Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 47S Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector gicQ.180457 910531 _,

I;DR ADOCK 09.'O){

h',

, . AyJJBGE DAILY UNIT POWER LEVIL j DOCKET NO. 50 233 Pilagig 1 UNIT DATE hae 1* 1991 .

i COMPLETED BY .H. Munro ,

TELEPHONE E .0fD 747-8474 HONTH Hav 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (HWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 ,

4 0 20 0 5 0 21 0 6 0 22 0  ;

I 7 0 23 0 8 0 , 24 0 9 0 25 ___ 0 10 0 26 0 ,

11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 This format lists the average daily unit power level in HWe-Net for each day in the reporting month, computed to the nearest whole megawatt, e s

. --, . - _ - , , . . . . - , . . , . . _ _ , , . . . _ .._.---..-,-~,,.....m__- ~ . , . . , - - - _ - - . ,- . ~ . - - -

... .. OPERATING DATA REPORT DOCKET NO. _ 50-293 l DATE _ June it. 1991 COMPLETED BY _ K Hunro TELEPHONE _(508) 747-8474 QPERATING STATUS Notes

1. Unit Name Pilarim 1

2. Reporting Period Hav 1991

3. Licensed Thermal Power (MHt) 1993

4. Nameplate Rating (Gross HHe) _ 678

5. Design Electrical Rating (Net HHe) 655

6. Maximum Dependable Capacity (Gross HHe) 616

7. Maximum Dependable Capacity (Net HHe) 670 _

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

, None

9. Power Level To Hhich Restricted, If Any (Net MHe) None l

10. Reasons for Restrictions, If Any N/A 1his Month 1r-12-Q312 Gymulative

> 11. Hours In Reporting Period ___ 744,0 __..362310 161951.0

12. Number Of Hours Reactor Has Critical 00 285Q22 95450,9

13. Reactor Reserve Shutdown Hours 00 0.0 Q10

14. Hours Generator On-Line 00 2 285022 91766.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (HHH) 0.0 _521E522J) 15861BDaE10

17. Gross Electrical Energy Generated (HHH) 0.0 _la121E0 V _5.3459694.0

18. Net Electrical Energy Generated (HHH) 0.0 _]743822.0 _5137023Q10

19. Unit Service factor 0.0 78.7 56.7

20. Unit Availability factor 0.0 78.7 _ 56.7

21. Unit Capacity factor (Using HDC Net) 0.0 71.8 47.3

22. Unit Capacity factor (Using DER Net) O0 t 73.5 48.4

23. Unit forced Outage Rate 100.0 3.6 12.5

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

Refuelino Outace No. 8. aooroximately 70 days

25. If Shut Down At End Of Report Period. Estimated Date of Startup 7/13/91 l

l

. .. BOSTON EDISON COMPANY PILGRIH NUCLEAR P0HER STATION DQCXLl_l@. ED-293 Onentiefuti Sunrnary for Hay 1991_

The unit started the reporting period in cold shutdown. Refueling outage Number 8 commenced at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on May 4, 1991.

Safety Relief Valve Challenges Month of liav 1991 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during this reporting period.

An SRV challenge is defined as anytime an SRV has rectived a signal to operate via reactor pressure, auto signal (ADS) or control switch (r'anual). Ref. BECo Itr. #81-01 dated 01/05/81.

(

REuu1HG_1HEORM110H 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 $Upplied has been enumerated so tiat, 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: On or about April 1, 1993

3. Scheduled date 'or restart following present refueling: Third Quarter 1991

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

5. See #6.

6. The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.

7. (a) There are no fuel assemblies in the core.

(b) There are 2068' fuel assemblies in the spcnt fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies. The actual usable spent fuel storage c6pacity is 2320 fuel assemblies.

(b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 832 fuel assemblies.

• Includes 168 new fuel assemblies to support current refuel outage.

580 fuel assemblies in the spent fuel pool will be returned to the core for Cycle 9.

Honth May 1991 PILGRIM NUCLEAR POWER STATION

~

MAJOR SAFETY RELATED MAINTENANCE .

~

MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED SYSTEM COMPONENT MALFUNCTION CAUSE PREVENT RECURRENCE- LER Seals to be replaced Frequency of seal LER 91-007-00 Recirc- Loop "B" Pump Increase in End of useful in both A and B replacement under U1ation P2018 Drywell floor life of the sump leakage inner seal of Recirculation System review.

System pumps during RFO-8. Refer to associated LER.

(RECIRC) rate to great- Recirculation er than 5 gpm pump "B".

(F&MR 91-122)

Following the first To be determined. LER 91-006-00 Primary N/A False high re- Root Cause Contain- actor water investigation two isolations, the signal caused ongoing. isolation signal was ment three auto- reset and the main steam ,

I Isolat-ion Con- matic PCIS line (MSL) drain valve Group 1 Isola- and the main steam trol System tions. (F&MRs isolation (MSIV) valves91-124, 91-125 were reopened, to facil-(PCIS) itate decay heat removal.

and 91-127)

Following the third 1:01-ation, the isolation signal was reset and the MSL drain valve and the HSIVs were left closed, using the Res-idual Heat Removal System for plant cooldown.

-. _ _ _ _ _. . - - _. ._ _ = . _ ___

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCui NO. 50-293 -

NAME Pilcrio 1 .

DATE June 14 1991 ,

COMPLETED BY W. Munro .

TELEPHONE (508) 747-8474 -

REPORT MONTH May 1991 .

NETH00 0F LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM ENT ACTION TO PREVENT NO. DATE TYPE I (E00RS) REASON 2 DONN REACTOR 3 P.EPORT # C00E 4 gODE C RECURRENCE 8 05/01/91 F 79.0 D 4 91-007-00 AD P Seal Seal failure on (continuation) "B" Recirculation Pump.

Seal to be replaced.

8 05/04/91 S 665.0 C 4 N/A N/A N/A Refueling outage No. 8 (continuation) 1 2 2 3 4&5 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint 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 Sheet E-Operator Training 5-Reduced Load Licensee Event Report

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

_ _ . - . . - _ _ - . . _ . . _ . _ . .- . . - - - _ _ .