ML20096D256

Monthly Operating Rept for Apr 1992 for Pilgrim Nuclear Power Station,Unit 1

ML20096D256
Person / Time
Site:	Pilgrim
Issue date:	04/30/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-#92-59, NUDOCS 9205150173
Download: ML20096D256 (8)

Text

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BOS TON EDISON

, P.igf un Nutivat Poe.tt Staton j

. Rocky HW Ho;4d Phmouth, MMLuchusetts 023f>0 E, Thomas Boutette, PhD Vice President Nuclear Operatons and Staton Di'et'.or  !

May 13 , 1992 l BECo Ltr. #92-.59 I U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashingto;, DC 20555 License No. OPR-35  ;

Docket No. 50-293_. I

Subject:

April 1992 Honthly neport 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, h7/bbLob 4 E. Thomas Boulette HJH/bal Attachment cc: Mr. Thomas T. Hartin Recional Administrator, Region i U.S. Nuclear-Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19405 Hr. R. B. Eaton Div. of Reactor Projects I/II Office of NRR - USNRC One White flint North - Hail Stop 14D1 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector 9205150173 920430 PLR ADCCK 05000293 /

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oyfjLAGLDAll,Y UNIT POWER LEVEL I

- DOCKET NO, 50-293 UNIT __ Pilarim 1 DATE May 13. 1992

- COMPLETED Bf W. Hunro TELiPHONE (508) 741-8474 HONTH Aoril 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEEL (HWe-Net) (MHe-Net) 1 0 17 _

667 2 0 10 _

666 3 0 19 666 4 0 20 666 ___. _

5 0 21 6f15 6 0 22 665 7 O_ 23 666 _

8 0 _

24 556 9 __ _0 25 6 61 _

10 0 26 667 11 0 27 59L 12 0 28 649 13 ,_

83 29 ,_ 667 14 _223 30 f67 2

15 527 31 N/A 16 655 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.

. OPERATING DATA REPORY DOCKET NO. 50-293 DATE May 13, 1992 COMPLETED BY W. Munro TELEPHONE (508) 747-8474 OPERATING STATUS Notes

1. Unit Name Pilorim 1

2. Reporting Period April ' 992_ .

3. Licensed Thermal Power (MWt) 199.8

4. Nameplate Rating-(Gross MWe) 673

5. Design Electrical Rating (Net MWe) 60

6. Maximum Dependable Capacity (Gross MWe)..__. H6

7. Maximum Cependable Capacity (Net MWe) 670 __

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

None

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

10. Reasons For Restrictions, If Any N/A J.t's Month yr-19-J.ite Cumuletive

11. Hours In Reporting Period 719.Q .2101J) 169991.0

12. Number Of Hours Reactor Was Critical 471.0 252E.6 100886.2  !

13. Reactor Reserve. Shutdown Hours 00 00 0.0

14. Hours Generator On-Line ___ 422.9 2473.!i 969))J l

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 ,

16.. Gross Thermal Energy Generated (MWH) 777744.0 - 4817736.0.168522216.D l

17. Gross Electrical _ Energy Generated (MWH) _267650.0 _1665150.0 _56871564.0 l

18. het Flectrical Energy Generated (MWH)- 257485 0 1603258dl _ji4613205J j

19. Unit Service factor SBJ 85.R 57.0

20. Unit Availability Factor 58_.8 85.2 57.0 {

21. Unit Capacity Factc,r (Using MDC Net) 53 5 Pld 48J 22.. Unit Capacity Factor (Using DER Net) 54 2 84.J 49.1 '

23. Unit Forced Outage Rate 41 J _

14.8 12.7

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

Midcycle_cutaae - October 1992 Acoroximately 35 days ,,

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25. If Shut-Down At End.0f Report Period, Estimated Date of Startup _tyA u

'A

BOSTON EDISON COMPAt4Y PILGRIM NUCLEAR POWER STATIO!4

, DOCKET I40. 50-293_

Operational Summuy for April 1992 The unit started the reporting period in cold shutdown with outage activities in progress. On April 9 at 0859 hours0.00994 days <br />0.239 hours <br />0.00142 weeks <br />3.268495e-4 months <br /> the reactor was declared critical and power was increased to approximately 15 percent r. ore thermal power (CTP) to perform post work testing (Temporary Procedure TP 92-021) for the Reactor Hater Level Temporary Hodification TH 92-13. Reactor shutdown commenced on April 10 at 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br /> with cold shutdown achieved on April 11 at 0335 hours0.00388 days <br />0.0931 hours <br />5.539021e-4 weeks <br />1.274675e-4 months <br />.

On April 12 at 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br /> the Reactor Mode Selector Switch was taken to STARTUP and the reactor was declared critical at 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br />. On April 13 at 0904 hours0.0105 days <br />0.251 hours <br />0.00149 weeks <br />3.43972e-4 months <br /> the generator was synchronized to the grid at approximately 20 percent core thermal power (CTP). Power ascension continued, and at approximately 28 percent CTP a backwash of the main condenser was performed.

Following the backwash power ascension continued and the unit attained 100 percent CTP on April 16. This power level was maintained until April 27 when at approximately 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, power was reduced to approximately 50 percent CTP -

to perform a backwash of the main condenser. The unit was returned to 100 percent CTP on April 28 at approximately 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> and remained at that level for the remainder of the reporting period. Hinor power reductions were initiated on April 18 and 25 to perform control rod exercises.

Safety Relief Valve Challenges Month of AndL,]S]2 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 received a signal to aperate via reactor pressure, auto signal (ADS) or control switch (manual). Ref. 8ECo ltr. #81-01 dated 01/05/81.

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, , Bif1lfd.15.INFORMATIQM The following- refueling information i s 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 collectf vely under #6.

E. Set #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) 1here arc- 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 has the capacity to accomiaodate an additional 831 fuel assemblies.

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Month Aoril 1992 PILGRIM NUCLEAR P0HE't STATION .,

MAJOR SAFETY RELATED MAINTENANCE

SISE1 COMPONENI MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ' ASSOCIATED

PREVENT RECURRENCE __ LER Reactor

EGR 125 volt DC ground Under EGR replaced with new To be determined. None Core Actuator alarm received in investigation replacement in kind.

-13c)ation Control Room. .i Cooling (RCIC)

System Reactor Inboard MO-1301 16 indic- Valve actuator Valve actuator was Actuator to yoke cap- LER 92-003-00  :

Core Steam Isolation ed closv but was to yoke cap- overhauled and re- screws were torqued to a l Isolation valve actually open. screws backed attached. Valve was higher value. Motor Cooling MO-1301-16 out and the op- diagnostica11y test- operated valve fasteners (RCIC) erator Decame ed with satisfact- were either torque checked [

System detached from ory results. or visually inspected.to the valve. verify the fasteners were  !

not loose.

Reactor Outboard Steam Steam leak Seal ring MO-1301-17 seal ring N/A None

-Core Isolation in Traversing leakage replaced and actuator Isolation -Valve 'In-core Probe rebuilt. Valve was

.Looling M0-1301-17 (TIP) room. diagnostically testeo 3 (RCIC) with satisfactory System results.

Reactor Pump P202D Seal leakage Seal wear. Seal was replaced N/A None [

Building (F&MR 92-84) and P202D wa.s satis-Closed factorily tes'ced using r Cooling using Pme:aure 8.S.3.1.

j Hater  !

'(RBCCH) i System

~

Month April 1992 PILGRIM NUCLEAR P0HER STATION ,

MAJOR' SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER

.Co ntrol CRDs 38-23'and Leakage under Faulty CR0 CRDs 33-23 and 38-31 N/A None Rod 38-31 vessel. flange 'O' removed 'O' rings Drive rings replaced, and CRDs

-(CRD)' reinstalled. Leak System tested satisfactory.

Reactor Relay 16A-K5A Relay contacts Contacts 3&4 Contacts were cleaned N/A None Protect- Low water level / would not energ- dirty. anj Procedure tion High drywell- ize to cause "B" 8.M.2-1.5.8.2 was System ' pressure side reactor performed (RPS) PCIS relay. building Isolation satisfactorly.

during Procedure

~8.M.2-1.5.8.2 (F&MR 92-72)

Primary Reactor. water False high Improper Equalizing line insu- Data to be collected LER 92-004-00 Contain- level transmit- reactor water performance of lation removed to weekly to analyze ment ters LT-263-588. level signals reference leg prevent vaporization reference leg chamber Isolation caused Group I chamber and in line. Tested via performance.

System isolations of equalizing line. Temporary Procedure (PCIS) Main Steam (TP) 92-21.

isolation valves.

Neutron Intermediate When inserted on Detector failure IRM detector replaced N/A None Monitoring Range Monitor SHUTDOHN. IRM "C" and satisfactorily System (IRM) "C" remained down- post work tested via scale'(F&MR 92-77) Procedure 8.M.1-1.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCrIT NO. 50-293 NAME Pilorin 1 ,

l DATE May 13, 1992 -

l 00MPLETED BY W. Munro ' ,

. TELEPHONE (508) 747-8474 '

REPORT MONTH'Aoril 1992 METHOD OF LICENSE CAUSE & CORRECTIVE i

DURATION SHUTTING EVENT SYSTg- ENT ACTION TO PREVENT NO. DATE- TYPEI (HOURS) REASON 2 DOWN REACTOR 3 REPORT # CODE COMyE COD RECURRENCE I

03 3/26/92 F- 296.1 A i 92-003-00, BN ISV Continuation of forced

l. maintenance outage.

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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-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)

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