ML20045H015

Monthly Operating Rept for June 1993 for Pilgrim Nuclear Power Station.W/930712 Ltr

ML20045H015
Person / Time
Site:	Pilgrim
Issue date:	06/30/1993
From:	Gay R, Kraft E BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-087, 93-87, NUDOCS 9307160244
Download: ML20045H015 (8)

Text

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BOSTON EDISON Pilgorn Nuclear Power Staton Rocky Hdi Road Plyrnouth, Massachusetts 02360 E, S. Kraft, Jr.

Vce Prevdent Nuclear Operations and staten crecto' July 12, 1993 i BECo Ltr. #93-087 l

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U.S. Nuclear Regulatory Commission Attention: Document Control Desk  !

Washington, DC 20555 ]

License No. DPR-35 l Docket No. 50-293 June 1993 Monthly Repor_t 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.

N . kCC t, E. S. Kraf r.

RAG /bal Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road l King of Prussia, PA 19406 l

l Mr. R. B. Eaton Div. of Reactor Projects I/II Office of NRR - USNRC One White Flint North - Mail Stop 1401

, 11555 Rockville Pike i Rockville, MD 20852 Senior Resident Inspector 7 y )

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9307160244 930630 E3 PDR. ADOCK 05000293 N /lU b R PDR &

,y . i OPERATING DATA REPORT =

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DOCKET NO. 50-293 DATE July 12. 1993 .

COMPLETED BY: R.~ Gay-TELEPHONE- (508) 747-8047 OPERATING STATUS e

NOTES t

1. Unit Name Pilgrim I I

2. Reporting Period June-1993

.3, Licensed Thermal Power (MWt) 1998 .

4. ' Nameplate Rating (Gross MWe) 121

5. Design Electrical Rating (Net MWe) f51

6. . Maximum Dependable Capacity (Gross MWe) f25f  ;

7. Maximum Dependable Capacity (Net MWe) 670 -

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

None

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

10. Reasons For Restrictions, If Any: N/A

'i This Month Yr-to-Date- Cumulative 'i t

-11. Hours In' Reporting Period 720.0 4343.0- 180215.0 ,

12. Number of Hours Reactor Was Critical 670.6 2890.8 108749.4 (

13. Reactor Reserve Shutdown Hours 0.0 0'0

. 0.0 *

24. Hours Generator On-Line 648.6 2803'2.. 104709.6-  !

-15. Unit Reserve Shutdown Hours 0.0- 0.0 0.0

16. Gross - Thermal Energy Generated (MMH) 1144128.0 ~ 5287272.0 '183296088.0 17 Gross Electrical. Energy Generated (15m) 389450.0 1820330.0 61954324.0

18. Net Electrical' Energy Generated (tom) 374097.0- 1750445.0 '59543361.0c

19. Unit Service Factor 90.1 64.5 58.1'

'20. -Unit Availablility Factor 90.1 64.5 58.1-  !

21. Unit Capacity Factor (Using MDC . Net) 77.5 60.2 49.3

22. Unit Capacity Factor (Using DER Net) 79.3 __ 61.5 50.4.

23. Unit Forced Outage Rate 9.9- 5.4 12.1

24. Shutdown Scheduled Over Next 6 Months (Type, Date, and Duration of Each) : None- ,

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25. If Shut Down At End of Report Period, Estimated Date of Startup. Unit Doeratino. ] ,

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AVERAGE DAILY UNIT POWER LEVEL l

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DOCKET NO. 50-293' .:

UNIT Pilorim I .

DATE July 12. 1993 COMPLETED BY: R. Gav TELEPHO!TE (508) 747-8047 - ;i MONTH dyne 1993 l l

DAY AVERAGE DAILY POWER LEVEL. DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net) ,

1 0 17 661 l 2 0 18 661 .

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3 2 19 661 i i

4 99 20 660 i h

5 106 21 660 '

6 244 22 661 t

7 322 23 637.

i B 446 24 623- ,

9 659 25 657 +

10 -659 26 658 11 661 27 573  !

12 659 28 661 [

13 659 29 661 14 659 30 660 ,

15 660 '

16 659

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This format lists the average daily unit power level in MWe-Net for each day in the  :

l reporting month, computed to the nearest whole megawatt. '

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l BOSTON EDISON COMPANY l

. PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 OPERATIONAL

SUMMARY

FOR JUNE 1993 I l

The unit started the reporting period in a forced outage condition, while l investigation continued as to the cause of the unit scram that occurred on May 31, 1993. On June 2, 1993, all requirements for placing the Reactor Mode Switch to i "STARTUP" were satisfied and the reactor was made critical at 0121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br /> on 6/3/93.

, On 6/3/93 with reactor pressure at approximately 135 psig, Reactor Core Isolation Cooling (RCIC) flow rate test at 150 psig was successfully performed. At 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br /> on 6/3/93 the mode switch was placed in "RUN" and the unit was synchronized to the 'l grid at 2322 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.83521e-4 months <br />. At J331 hours reactor power was being increased to approximately 25 percent Core Thermal Power (CTP). During recovery from the unit scram, the plant performed s regular and a thermal backwash of the Main Condenser and experienced feedwater robulating valve oscillations. On 6/4/93 the RCIC 1000 psig pump operability and flos rate surveillance test was successfully performed.  ;

On 6/9/93 at 0136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br /> the unit power level was increased to 100 percent (CTP) and maintained that level until 6/23/93. On 6/23/93 at 2305 hours0.0267 days <br />0.64 hours <br />0.00381 weeks <br />8.770525e-4 months <br /> reactor power was  !

being reduced to approximately 70 percent (CTP) in response to HCU 42-39 scram outlet valve diaphragm failure causing a control rod scram. On 6/24/93, following i replacement of the diaphragm, power was increased 100 percent (CTP). On 6/27/93 the- f unit power level was reduced to approximately 50 percent (CTP) to facilitate a 'I backwash of the Main Condenser. Following the backwash, 100 percent (CTP) was l achieved on 6/27/93. On 6/30/93 during the HPCI system pump and valve j monthly / quarterly operability test, the minimum flow rating was not achieved. {

Therefore, the HPCI System was secured and declared inoperable. Subsequent .

investigation demonstrated the injection function was not affected. The unit ended  !

the reporting period with reactor power at 100 percent (CTP).  ;

SAFETY RELIEF VALVE CHALLENGES MONTH OF JUNE 1993 l

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

There were no safety relief valve challenges during the reporting period. i 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 date 01/05/81.

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RWFUELING INFORMATXON

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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 1, 1995 B

3. Scheduled date for restart following next refueling: June 1, 1995

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 1993 refueling outage was of the same design as i loaded in the previous refueling outage and consisted of 140 assemblies,

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

1' (b) There are 1629 fuel assemblies in the spent fuel pool.

B. (a) The station is presently licensed to store 2320 spent fuel assemblies. i The actual usable spent fuel storage capacity is 2320 fuel assemblies. >

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

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

to accommodate an additional 691 fuel assemblies.

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MONTH JUdE. 1993 PILGPI'4 NUCLEAR POWER STATION M% TOR SAFETY RELATED MAINTEWANCE . .

CORRECTIVE ACTION TO ASSOCIATED SYSTEM COMPONENT' MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER ..

' Low- AC, Circuit Circuit Breaker Circuit break- Replaced lug and (Refer to associated .93-009-00 Voltage Breaker did not close er did not reterminated LER)

Power (52-102) during automatically wire.

System transfer. close due to (PR93.9215) loose wire-to-lug connection in breaker control circuit.

' Main' Relief valve Setpoint of The out-of- Remove valves Valves sent to Target 93-011-00 Steam (S/N 1040, Target Rock tolerance pop- S/N 1040, 1025, Rock for rework, ma-System 1025, 1207) relief valves ping pressure 1207 and chining and reassembly.

found out of of the valves installed three tolerance. was due to previously refur-(PR93.0420, setpoint bished spares. '

93.0421, drift.

93.0422) 4 Reactor Speed Reactor Core Turbine oscil- Speed control (Refer to associated 93-013-00 Core control Isolation Cool- lations were hydraulic -LER)

Isolation (EG-R). ing System de- due to failure actuator (EG-R)

. Cooling clared inoper- of the EG-R. was replaced.

(RCIC) able due to Failure of the Samples of EG-R System turbine speed EG-R was most oil were taken and oscillations. likely due to sent for testing.

(PR93.9282)' grit found in-side the EG-F.

which caused mech-anical binding and wear of the pilot plunger assembly.-

- Engineer- Differential Automatic Scram Scram was Phase 'B' and (Refer to associated 93-014-00 ed Protective resulting from due'to the 'C' relays LER)

Safety Relay malfunction of closing of (187-3) were Features (187-3)* Unit Auxiliary Turbine Stop . interchanged for

-Actuation Transformer Valves investigative Syste:m differential with Turbine- purposes. Relays (PCIS, relay.* first stage . will remain inter-

.RBIS, RPS) (PR93.9283) pressure at - changed as a future approx. 110 investigative' aid.

.psig.

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~ . ; , -,.-- - s, MONTH JUNE. 1993 PILGRIM NUCLEAR POWER STATION , ,

MAJOR SAFETY RELATED MAIETTEFANCE .

CORRECTIVE ACTION TO- ASSOCIATED, SYSTEM- COMPONENT MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER-L. Control Scram outlet Control rod Diaphragm Rseplaced failed Perform future pre- None Rod _. valve (42-39) _ fully. failure in diaphragm. ventive maintenance

' Drive ~ (CV-305-127) ' inserted and the air oper- as scheduled.

(CRD)- isolated. ator of the (PR93.9303) scram cutlet valve.

o Non-safety related but caused reduction of power.

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.ss v UNIT SHUTDOWNS AND POWER REDUCTIONS' DOCKET NO: 53-293 .,.

NN .

DOCKET NO: 50-293.

NAME: Pilcrim I ' '

DATE. July 12, 1993 -

COMPLETED BY: R. Gav TELEP!IONE : (508 ) 747-8047 RET + MONTH June 1993 J

METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVEITT SYSTEM COMPONENT ACTION TO PREVENT ~

NO. DATE TYPE 1 (HOURS) REASON DOWN REACTOR REPORT # CODE 4 CODES RECURRENCE 06 5/31/93 .F 71.4 A 3 93-014-00 EA XFMR UAT. lockout-turb trip-scram.

(continuation) 1- 2 2 '3 4&5 F-FORCED A-Equip Failure F-Admin 1-Manual

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Exhibit F & H-

-S-SCHED -B-Main or Test .G-Oper Error 2-Manual Scram l ~ Instructions for

'C-Refueling- .H-Other .3-Auto Scram' Preparations of D-Regulatory Restriction 4-Continued Data Entry Sheet.

-E-Operator Training l5-Reduced Load Licensee Event Report

-.& Licence Examination' 9-Other. ' { LER) File (NUREG-1022)

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