ML20085N503

Monthly Operating Rept for Oct 1991 for Pilgrim Nuclear Power Station

ML20085N503
Person / Time
Site:	Pilgrim
Issue date:	10/31/1991
From:	Richard Anderson, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9111150191
Download: ML20085N503 (8)

Text

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

e BOSTON EDISON Pilgenn Nuclear Power Station Rocky Hill Road Plymouth, idanachusetts 02360 b.^hUaIn7E November 14, 1991 UU"S7 fin.

BECo Ltr. #91-138 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Hashington, DC 20555 License No. OPR-35 Docket No. 50-293.

Subject:

October 1991 Monthly Report

Dear Sir:

In accordance with PNPS Technical Specification 6.9.A.2, :psopy of the Operational Status Summary for Pilgrim Nuclear Power Station

. attached for your information and planning. Should you have any ciestieris concerning this report please cc,atact me directly.

lA

.Q

',A. Ar1erson R

HJH/bal 1,

Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region i U.S. Nuclear Regulatory Commission 47S Allendale Rd.

King of Prussia, PA 19406 Mr. R. B. Eaton Div. of Reactor Projects I/II Office of Pt>R - USNRC One White Fl u t North - Hail Stop 14D1 11555 Rockville 'ike Rockville, MD 20852 Senior Resident Inspectw i

m m m m _ou

[Ae 7iO e.m PD,

/

et

&ViR&GE_ DAILY UNIT POWER LEVEL DOCKET NO... 50-293 UNIT Pilarim 1 DATE nee nimr COMPLETED BY H. Munro TELEPHONE

_11Q0 747-8474 HONTH Octohor 1991 DAY A'JERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Net)

(MHe-Net) 1 664 17 665 2

664 18 666 3

665 19 E65 4

_665 20 665 5

664 21 665 6

664 22 666 7

J5f5 23 664 8

667 24 664 9

666 25 664 10 666 26 663 11 EE.5 27 664 12 666 28 663 13 666 29 661 14 666 30 404 15 666 31 0

16 667 This format lists the average daily unit power level in MHe-Net for each day in the reporting month, computed to the nearest whole megawatt.

OPERATING DATA REPORT DOCKEY NO.

50-293 DATE orennor COMPLETED BY H. Munro TELEPHONE

._1108) 747-3474 QP AATING STATid Notes 1.

Un'.t Name.

Pilarim 1 Retorting /eriod October 1991 3.

Licensed T.iermal Power (MHt) 1998 Name/ ate fiating (Gross MHe) __

62B l

4.

5.

Design Clettrical Rating (Net MHe) 655 6.

Maximum Dependable Capacity (Gross MWe) 615 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 is Which Restricted, If Any (Net MHe)

None

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

11. Hours In Reporting Period 745.D 72.1510 17292DjD

12. Number Of Hours Reactor Has Critical 71412 4777.4 973781.9

13. Reactor Reserve Shutdown Hours 0.10 0.0 0.0

14. Hours Generator On-Line 714.2 4637 4 98190u2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) 1.412280.0

_155045110 161891952 0

17. Gross Electrical Energy Generated (MHH)

_4185D010

_2931682<0 54579394.0

18. Net Electrical Energy Generated (MHH) 470369.0

.2820917.0 _324473?5.0

19. Unit Service Factor 95.9 63.6 56 5 1

20. Unit Availability Factor-95.9 63.6 56.5

21. Unit Capacity Factor (Using MDC Net) 94.2 57.7 47.3

22. Unit Capacity Factor (Using DER Net) 96.4 59 0 48.3 1

23. Unit Forced Outage Ratt 4.1 2.9 _

12.3

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 11/19121

~.

r BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION DOCKEI NO. 50-293 Operation 1 Summary for October 1911 The unit started the reporting period at 100 percent power and maintained this power level until October 30 when at 0521 hours0.00603 days <br />0.145 hours <br />8.614418e-4 weeks <br />1.982405e-4 months <br /> Recirculation Pump Hotor "B" Lower Bearing Low 011 alarm was received in the Control Room.

At 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> reactor power was reduced to approximately 47 percent, a decision was made to proceed to cold shutdown, and Recirculation Pump "B"

was secured at 1154 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.39097e-4 months <br />.

Due to conditions resulting from a severe ocean storm, numerous men condenser backwashes were performed to clear low vacuum alarms.

Vacuum conditions continued to degrade and necessitated further reduction of reactor power to approximately 30 percent.

Repeated tripping of Air Circuit Breakers (ACB) 103 and 104 occurred with manual resetting from the Control Room.

With vacuum continuing to degrade, the Mode Switch was placed in SHUTDOWN and the unit was scrammed at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />.

At 1942 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.38931e-4 months <br /> the plant experienced a loss of the startup transformer and a full reactor scram signal was received due to loss of power to the Reactor Protection System (RPS) busses.

Primary Containment Isolation System (PCIS) Group 1,

2 and 6 isolations occurred, followed by an Emergency Diesel GenJrator start signal.

High Pressure Coolant Injection (HPC1) was placed in full flow test (pressure control) and Reactor Core Isolation Cooling (RCIC) in makeup / injection (level control).

Residual Heat Removal (RHR) loop "A" was placed into suppression pool cooling.

Upon the initial start of RCIC, the trip and throttle valve tripped and was immediately reset.

Experiencing a voltage transient on the 125 volt DC Bus "A", the RCIC inverter also tripped.

At 1953 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.431165e-4 months <br /> the plant experienced loss of the Shutdown Transformer and an Unusual Event was declared due to the loss of all offsite power.

At 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> HPCI and RCIC were isolated due to high water level, and at 2031 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.727955e-4 months <br /> manual opening of Relief Valve SRV-203-3B momentarily was required due to increasing pressure.

HPCI and RCIC systems were reset at 2032 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.73176e-4 months <br />.

The Startup Transformer was returned to service at 2142 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.15031e-4 months <br /> and the Shutdown Transformer was restored to service shortly thereafter at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br />.

The Unusual Event was terminated at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br />.

At 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> both RHR loops "A"

and "B" were in suppression pool cooling.

At the end of the reporting period the unit was in cold shutdown.

Power reductions to 95 percent were performed on October 5,

12, 19 and 26 for control rod exercising.

Safety Relief Valve Challenges Month of October 1991 Requirement:

NUREG-0737 T.A.P. II.K.3.3 Date: October 30, 1991.

Valve: # 203-3B Reason:

Hanual opening of SRV 203-38 momentarily was required due to increasing pressure.

An SRV challenge is defined as 2nytime an SRV has receiv::d a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual).

Ref. BECo ltr. #81-01 dated 01/05/81.

r 1

EEFUELING INFORMATIQN Thh 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 next refueling:

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 and consisted of 168 as a mblies.

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.

Hith present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an aditional 831 fuel assemblies.

M nth Octobar 1991 FILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE HAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURR2NCE LER H 0, Panel Analyzer Low Faulty Replaced temperature None None Post 2

Accident HealerTempera-Temperature Alarm temperature swtich.

Sampling ture Controls received in switch TSH 1/3 and Hydro-Control Room.

gen /0xygen (F&MR 91-426)

Analyzer (H 0 )

22 System Structu-Switch Gear and Operability of Original As a compensatory Permanent solution to None ral Battery Room safety related analysin not measure modifications this problem is System Heating, Vent-equipment available.

were made to duct under investigation.

11ation Air located in the Design liasis supports, battery Conditioning Switchgear or cannot le room fans, B-19 load (HVAC) System Battery Room, verified.

center and Panel 60; fcilowing loss plus the addition of of non-safety a portable generator.

related HVAC These modifications system due to a were implemented design basis under PDC 91-01, accident is Field Revision indeterminate.

Notices 91-01-55, 56, 58, 59, and 60.

1

---

a

Honth Ontober 1991 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED HAINTENANCE SLSTEM COMPONENT HAEFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER Diesel "B" Emergency Check valves 47-Rust and moist-Check valves disass-This temporary mod-None Generators Diesel Generator CK-301 A,B and C ure buildup in embled, cleaned and ification will be rem-and (EDG) turbo failed in closed the check valves inspected. Temporary oved when Plant Design Auxiliar-assist air rec-position.

Modification 91-59 change (PDC) 91-61 ies elver tanks (F&MR 91-430) was implemented.

Diesel Generator Air System sucply piping.

Installed "Y" stral-Start System Piping ners and water traps is implemented.

(moisture separators) to preclude rust and water buildup on the upstream side of the inlet check valves to receiver tanks. Postwork test performed satis-factorily.

I I

6 1

UNIT SHUTDOHNS AND P0HER REDUCTIONS DOCKET NO. 50-293 NAME Pilorin 1 DATE November 14. 1991 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 REPORT MONTH October 1991 ME1HCD OF LICENSE CAUSE & CORRECTIVE COM NENT ACTION TO PREVENT DURATION SHUTTING EVENT SYSTEM CODgE NO.

GATE TYPE (HOURS)

REASON 2 DOHN REACTOR 3 REPORT #

CODE 4 I

RECURRENCE 10 10/30/91 F

30.8 8

2 N/A N/A N/A Severe storm, unable to maintain vacuum.

B" Recirculation Pump Motor Lower Bearing Low Level alarm received in tne Control Room.

91-24-00 FK INS Loss of offsite power 91-25-00 BN INV RCIC tripped / inverter tripped.

91-26-00 CE PDIS RHCU Isolations.

1 1

2 2

3 4&S F-Forced A-Equip Failure F-Admir:

1-Manual Eyhibit 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) y-_

-