ML20090H780

Monthly Operating Rept for Feb 1992 for Pilgrim Nuclear Power Station

ML20090H780
Person / Time
Site:	Pilgrim
Issue date:	02/29/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-029, 92-29, NUDOCS 9203160247
Download: ML20090H780 (7)

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BOSTON EDISON PflgttfTI NUCi&8f rOMf bl81 ton Rocky Hdi Poad Plymouth, Massachusetts 02360 E. Thomas Boulette. PhD Vce Predent Nuclear Opersions and Statran Duector March 13, 1992 BECo Ltr. #92-029 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293

Subject:

February 1992 Honthly Report In accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilg.im Nuclear Power Station is attached for your information and planning. Should you have any questions concerning this report please contact me directly.

/ XLbb L L. Thomas Boulette HJH/bal Attachment cc: Mr. Thomas T. Hartin Regional Administrator, Region i U.S._ Nuclear Regtlatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Mr. R. B. Eaton Div. of Reactor Projects I/II Office of NRR - USNRC l One White Flint North - Hall Stop 14D1 11555 Rockville Pike Rockville, HD 20852 Senior Resident Inspector l- ,

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'- by1MGL(1AILY UNIT P0HER 1,Ey1L j DOCKET NO. 50-293 UNIT Pilarim 1 l

. DATE March 13. 1992 l ib8 -8474 HONTH February 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (HWe-Not) 1 667 17 667 2 665 18 667 l 3 666 19 667 l

4 666 20 _16L.  !

5 666 21 666 6 667 22 666 7 666 23 667 8 665 24 666 9 667 25 666 10 666 26 666 11 _

667 27 666 12 667 28 666 13 666 29 665 14 ,

665 30 N/A 15 665 31 N/A 16 667 This format lists the average daily unit power level in HWe-Net for each day j in the reporting month, computed to the nearest whole megawatt.

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t OPERATING DATA REPORT

, DOCKET NO. 50-1 93--

DATE March 13, 1992

. COMPLETED BY H. Munro

. TELEPHONE (508) 747-8474 OPERATING STATUS Notes

1. Unit Name Pilorim 1

2. Reporting Period _[ebruary 1992

3. Licensed Thermal Power (MHt) 1998

4. Nameplate Rating (Gross HHe) 678

5. Design Electrical Rating (Net MHe) Hji

6. Maximum Dependable Capacity (Gross MHe) 696

7. Maximum Dependable Capacity (Net MHe) 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

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10. Reasons for Restrictions, If Any N/A This Month ,Yr-to-Date Gmulative

11. Hours In Reporting Period _

696.0 1440.0 16352AJ

12. Number Of Hours Reactor Has Critical 696.0 1440.0 99800.6

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 696.0 1440.0 95942 2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (HHH) _1389816.0 _.ZDJBIL4J 166541064.;

17. Gross Electrical Eriergy Generated (MHH) _481420.0 981550.0 _ 561870M

18. Net Electrical Energy Generated (MHH) 463695J 945197.0 ,J3996145.0

19. Unit Service factor . 100.0 100.0 56.9

20. Unit Availability Factor 100.0 100J ~56.9

21. Unit Capacity Factor (Using HDC Net) 99.4 ,, _9BJ 47.8

22. Unit Capacity Factor (Using DER Net) 101 1 100.2 48 9

23. Unit Forced C'itage Rate 0.0 0.0 12Ji

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 N/A

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BOSTON EDISON COMPANY

. PILGRIH NUCLEAR POWER STATION

. __ DOCKET NO. 50-293 Operational Summary for February _]) R The unit started tne reporting period at approximately 100 percent core thermal power (CTP) and maintained that level throughout the reporting period. Minor power reductions were initiated on February 8, 15, 22 and 29 to perform weekly control rod exercises.

Safety Relief Valve Challenges

-Month of Febryarv 1992 Requirement: NUREG-0737 T.A.P. II.K.3.3 Thert were no safety relief valve challenges during this reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reacte-r pressure, auto signal (ADS) or control switch (manual). Ref. BECo Itr. #81 J1 dated 01/05/81.

BEFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC 1etter to 8Eco, 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 shutdoen: April 3, 1993

3. Scheduled date'for restart following next refuelina: June 8, 1993

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 cnd 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.

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

9. With present spent fuel in storage, the spent fuel pool now nas the capacity to accommodate an additional 831 fuel assemblies.

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Month February 1992 .

PILGRIM NUCLEAR PONER STATION MAJOR SAFETY RELATED MAINTENANCE ODRRECTIVE ACTION TO ASSOCIATED MALFUNCTION CAUSE MAINTENANCE SYSTEM COMPONENT PREVENT RECURRENCE _ LER PDC 91-61 " Diesel None "B" Emergency Durinq :00 '"te Rust and Check valves dis-Die:e1 t, assembled and Generator Air Start Genera- Diesel Generator of Survc'i tam - moisture buildup in cleaned. Temporary Piping" implementation tors and (EDG) X-1078 turbo 8.9.1 air p . e check valve;. Modification TM91-59 date being Aux 111- assist air rec- couldn't be main-elver tank piping tained in air start installed on the "B" considered.

artes EDG air system to receivers due to leakage past air remove moisture from start receiver inlet the lires. (This mod-check valves 47-CK- ification was previous-101B and 47-CK-1010. ly installed on the "A" EDG). l (F&MR 92-48) 1 Under Discennected cable Initiated Engineering None Reactor RCIC EGR cable 125 volt DC connector plug. ground alarm on investigation and cleaned oil from Service Request ESR Ccre plug. Procedure 91-364 to investigate ,

Isola- D-4 received in 8.5.5.1 was success- grounding of RCIC and tion Control Room.

fully performed to HPCI EGR cable connector Cooling declare RCIC plugs.

(RCIC) operable.

System Replaced seven '/> Engineering Service None Salt SSH Pump P-208A High vibration Spider and low discharge bearing spider bearings in- Request ESR 91-742

( Service degradation stalled rebuilt bowl initiated to evaluate Hater flow. and upgrade line shaft l

assembly, stuffiaS (SSW) box bushing and one hearings and suction System (1) line shaft coup- head.

ling. Also, replaced two (2) intermediate columns damaged during pump removal due to a misaligned restraint arm assembly wall bracket.

Installed new twelve (12) inch expansion joint on discharge side of pump.

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l DOCKET !LO. 50-293 .

UNIT SHUTD0HNS AND P0HER REDUCTIONS NAME Piloria V-DATE__ March 13. 1992' '*

COMPLETED BY H. Munro "

TELEPHONE (508) 747-8474 REPORT MONTH February 1992 NETHOD OF LICENSE CAUSE & CORRECTIVE SHUTTING EVENT 7NENT ACTION TO PREVENT DURATION SYSTEg COHgE 3 RECURRENCE NO. DATE TYPE I (HOURS) REASON 2 DOWN REACTOR REPORT # CODE COD No Unit Shutdowns or significant power reductions during the reporting period.

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2 3 4&5 1 2 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 Sheet E-Operator Training 5-Reduced Load Licensee Event Report

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

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