ML20043A367

Monthly Operating Rept for Apr 1990 for Pilgrim Nuclear Power Station.W/900514 Ltr

ML20043A367
Person / Time
Site:	Pilgrim
Issue date:	04/30/1990
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-068, 90-68, NUDOCS 9005210260
Download: ML20043A367 (8)

Text

..y ' i*

• 006MEM Pilgrim Nuclear Power Statiori Rocky Hill Road Plymouth, Massachusetts o2360 ia En or a ve. er. xi.nt, wuci.6, oper ix,n.

May 14,1990 BECo Ltr. #90- 068 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. OPR-35 Qgeket No. 50-293

Subject:

April 1990 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.

,[ p, K.L. Highfil V HJH:bal Attachment cc: Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector Y pg$

n.

wa -a R

- 5<14 \ l 1

m

7:

AVERAGE DAILY Uh1T POWER LEVEL

'O

+

, DOCKET NO. 50-293 UNIT Pilorim 1 DATE May 14. 1990 COMPLETED BY W. Munro TELEPHONE (508) 747-8474 MONTH April 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Net) (MHe-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 28 123 13 0 29 381 14 0 30 -574  ;

15 0 31 N/A 16 0 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.

I

., ... OPERATING DATA REPORT- i (l .

DOCKET NO. 50-293 i DATE  %, u ,mme i COMPLETED BY _ H. Atinro""

. TELEPHONE- -(508) 747-8474 OPERATING STATUS

. Notes.

1. Unit Name Pilarim 1

2. Reporting Period Acril 1990

3. Licensed Thermal. Power (MHt) 1998

4. Nameplate Rating-(Gross MHe) 678

5. Design Electrical Rating (Net MWe) 655 6.- Maximum Dependable Capacity (Gross MWe). . 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 Which Restricted, If Any (Net MHe) None-

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

11. Hours In Reporting Period 719.0 2879.0 152447.0 1

12. Number Of Hours Reactor Was Critical 164.8 1831.1_ 8723h,3

13. Reactor Reserve Shutdown Hours 0.0 0.0 - 0.0

14. Hours Generator On-Line 65.5 1726.4 83855.7

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (HHH) 82392.0

17. Gross Electrical Energy Generated (MHH)-

3341256.0 143826168.0 -

27130.0 1152930.0 ,_48.389754.0 l 18. Net Electrical Energy Generated (MHH) 25874.0

19. Unit Service Factor *1109586.0 _*46492770.0

[

9.1 60.0 55.0

20. Unit Availability Factor 60.0

21. Unit Capacity Factor (Using HDC Net)

__ 9 .1_ 55.0 l 5.4 57-5 45.5 22.- Unit Capacity Factor (Using DER Net) 5.5 i

23. Unit Forced Outage Rate 58 4 46 5 l 0.0 0.0 12 1

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

25. If Shut Down At End Of Report Period. Estimated Date of Startup -

26. Units In Test Status (Prior to Commercial Operation): N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

Includes adjustment from March 1990 Report i

i

. ,' GOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION-

. DOCKET NO. 50-293 Onerational Summary for Anril 1990

.The unit started the reporting period with the mid cycle outage in progress.

On 4-24-90 the reactor was made critical at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />. During the increase to power the NPCI and RCIC operability tests were successfully performed at both 150 psig and 1000 psig. The power increase continued, and at 0633 hours0.00733 days <br />0.176 hours <br />0.00105 weeks <br />2.408565e-4 months <br /> on 4-28-90 the unit was synchronized to the grid and remained on line for the remainder of the reporting period.

Safety Relief Valve Challenges Month of Anril-1990 Requirement: NUREG-0737 T.A.P. II.K.3.3 Date: April 25, 1990 Valve # 203-3A, 3B, 3C and 3D Reason: Startup Testing (ref. Procedure 8.5.6.2)

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 dated 01/05/81. j l

S

Month April 1990 .

PILGRIM NUCLEAR PONER STATION- . ,

MAJOR SAFETY RELATED MAINTENANCE C

SYSTEM COMPONENT MALFUNCTION [AQSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED ~

PREVENT RECURRENCE LER R:circula- Recirc. E Set Instability in Aging of the Recirculation Speed N/A N/A~

tion System "A" the speed control electronic Control Modification Motor function loop. components PDC 90-14 has been Generator (F&MR 90-49) of the E incorporated into Set (E) Set. "A" Recirc. E Set.

Electric Circuit Breaker 3reaker 52-202 Latch prop Breaker sent to G.E. Inspection, overhaul' LER 90-005-00 Power 52-202 (G.E. failed to trip misalignment for inspection and and testing of similar System type AK-2A-50) (open) automat- due to miss- overhaul. Breaker (480V) breakers perf . ,

Ica11y during ing retaining re-installed and ormed. (Refer to Assoc- '

bus transfer. ring result- post work tested lated LER).  !

(F&MR 90-64) ing in fail- satisfactorily. i ure of its trip coll. i R:sidual RHR Injection Check valve Misalignment Valve disassembled- To be deternined. N/A Heat Check Valve CK-1001-68B of the valve and inspected. Repl- .i Removal CK-1001-688. failed hydro- seat and disc. aced hinge pin bush-System dynamic leakage Root cause ings, hinge pins, ,

(RHR) test. Under invest- and machined disc (F&MR 90-68). igation. and seat surfaces.

Performed hydro 'j dynamic' leakage test successfully.

R:sidual LPCI Manual Leakage developed Normal wear. Furmanite injected Pressure seals to be N/A Heat Isolation Valve through pressure per PDC 89-49 and repaired during RFO-8.

Removal 1001-HO-33A. seal. FRN 89-49-11.

System (RHR)

Residual Reactor Head Developed external Normal wear. Furninate injected. Valve to be replaced N/A Hat Spray Vent body to bonnet per PDC 90-031, to during RFO-8.

Removal Valve 1001- leakage. seal valve in its System HO-177.- normally dosed -

(RHR) position.

UNIT SHUTDONNS AND POWER REDUCTIONS DOCKET NO. 50-293 f' '

NAME Pilgri ,1 ..

DATE m ir. toon

~

COMPLETfD Bf M. Munro TELEPHONE (508) 747-8474 .

REPORT MONTH Anril 1990- ,

METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM ENT ACTION TO PREVENTIVE.

TYPE I NO. DATE (HOURS) REASON 2 DONN REACTOR 3 REPORT # CODE' RE N ENCE 02 04/01/90 S 653.5 B 1 N/A N/A N/A- Continuation of.sbut-down for midcycle maintenance outage.

E' 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

. Preparation of C-Refueling H-Other .3-Auto Scram 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) r y b .______._________m_ _ _ . ~ - . , ~ ~ . . . . - . . . . ~ . - .,/.., _...--~.--.-a..-m.. . _ ,. a.: -- . _ . . - - . ~ , . . - . . . . ~ ..,__._.._,._-..__m _ _ _ _ . _ . . .

Month Anril 199J

~~

PILGRIM NUCLEAR POWER STATION - . _

~

MAJOR SAFETY RELATED MAINTENANCE

^

SYSTEM COMPONENT MALFUNCTION CAUSE MAINTEE NCE CORRECTIVE' ACTION TO - ASSOCIATED

. - ' PREVENT RECURREwCE LER R:sidual RNR Contain- Valve failed Under invest- Disassembly and insp- To be determined N/A Heat ment Isola- Local Leak Rate igation tion of valve. Lapped Removal tion Valve. Test (LLRT) the body, seal, and-System MG-1001-29B (F8MR 90-73) seats. Replaced valve-(RHR) stem. Performed LLRT successfully.

.w' FWWIY* 'e*fV'T i~b~ s'f**(9 4N*'t'M@ .O' I D 4' F'% 8 "F'1N* eT

• P M F " 'T'Tf"IN 'W"% *MW

_iMS 42 1 __m+m __ _'*^se__'-'T' T' * WF'PieC" W4 '4P'N8 N '9"9'W e"'teM E'D*i# Li.i' WNad' t

I

.- REFUELING INFORMATION

, ,. r ; -

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: Second Quarter 1991

3. Scheduled date for restart following refueling: Second Quarter'1991  !

4'. Due to their similarity, requests 4, 5, & 6 are responded to collectively ,

under #6.

t

5. See #6.

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

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

(b) There are 1320 fuel assemblies in the spent fuel pool.,  !

6. (a) The station is presently licensed to store 2320 spent fuel '

assemblies. The actual usable spent fuel storage capacity is 2320 l

f!iel assemblies.

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

9. With present spent fuel in storage, ~hec spent fuel pool now has the  ;

capacity to accommodate an additional 1000 fuel assemblies.

l l

i l

l

^2