ML20024E146

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Revised Monthly Operating Rept for June 1983.W/830804 Ltr
ML20024E146
Person / Time
Site: Pilgrim
Issue date: 08/04/1983
From: Harrington W, Whitney G
BOSTON EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
83-206, NUDOCS 8308090284
Download: ML20024E146 (8)


Text

. _ _ _ _ .__ _ . ~ ._. . . . _ _ _ . ._

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OPERATING DATA REPORT DOCKET NO. 50-293 DATE 8/4/83

' s COMPLETED BY G.G. Whitney

    • TELEPHONE 617-746-7900

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OPEFATING STATUS Pilgrim 1 Notes

l. UWt h June, 1983
2. Reporting Period:

1998.

3. Licensed Thennal Power (MWt):

i

4. Namep:ste Raths (Gross MWe): 678. -
5. Design Electrical Rating (Net MWe): 6ss.
6. Maximum Dependable Capacity (Gross MWe): 690.

. 7. Mr.ximum Dependable capacity (Net MWe):

670.

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

4 None 1

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9. Power Level To Which Restricted,if Any (Net MWe): None
10. Reasons For Restrictions. If Any: ,

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' !his Month Yr.-to.Dete Cumulative

11. Hours In Reporting Period 720.0' 4343.0 92543.0
12. Number Of Hours R'esetor Was Critical -

540.6 4108.9 66054.2 d 0.0 0.0 0.0

13. Rescre Reserve Shutdow[Mours k

1

14. Hour:GeneratoronW
  • 521.5 4063.6 63942.8
15. Unit Rese:ve Shutdown Hours 0.0 0.0 0.0
16. Gross Therrnal Energy Generated (MWH) 972120.0 7834584.0 110548176.0 *
17. Gross Electrical Energy Generated (MWH) 332350.0 _,

2717990.0 37044814.0 2615220.0 35596731.0

18. Net Electncal Energy Genersted (MWH) 319446.0 f,
19. Unit Semce Factor 72.4 93.6 69.1
20. Unit Availability Factor ~72.4 93.6 69.1
21. Unit Capacity Factor (Using MDC Net)

. 66.2 89.9 57.4 l

22. Unit Capacity Factor (Using DER Net) 67.7 91.9 58.7
23. Unit Forced Ourage Rate 15.6 4.2 9.4
24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

Refuel Outage to commence January, 1984

25. If Shut Down At End Of Report Period. Estimated Date of Startup: Startup consnenced on July 2,1983 ,
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved  ;

INITIAL CRITICALITY INITIAL ELECTRICITY

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COMMERCIAL OPERATION .

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l 8309090294 830804 PDR ADOCK 05000293 I R PDR (0/771 1 3

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)

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- - - AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 f

UNIT Pilgrim I DATE 8/4/83

  • G.G. Whitney COMPETED BY TELEPHONE 617-746-7900 JUNE. 1983 MONTE DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net) t _

660. 17 607.

2 661. -13' 509.

659. 617.

3 39

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4 598. 20 612.

662. 21 607.

5 663. ,, 599.

6 _

661. 23 598.

7 660. 24

  • 589.

S 659. 547.

9 23 10 658. 26 653.

29. 7 419.

11

0. ;g 0.

12 0.

g 0. 3 0.

g4 0. 30 15 324. 33 16 61.

INSTRUCTIONS -

On this format. !ist the average f. by mit power level in MWe Net for each day in the reportin5 month. Compute to the nearest whole mepwart.

to/~71

i DOCKET NO. 50-293 5

. UNIT SilUT1)OWN ANI) POWER RElitM:TIONS UNIT NAME Pi1Rrim 1 .

DATE 8/4/83 ~

JUNE, 1983 COMPl.ETED BY G.c whienov

' REPORT MONT11 TELEPHONE 617-746-790d _ .

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4 Ik'ic

.!g ~I $ }Y'gM

( kensee Event Eg g3 k

ki Cause & Gutective Acthm tu

' No. h $

P ok E jdig Repent # vi U fU Prevent Recurrence 6

+ .

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8 83/06/11 S 102.2 B 2 N/A HH HTEXCH Repair Feedwater heaters and investi-gate and repair drywell leakage i 9 83/06/16 F 18.5 A 3 N/A HA INSTRU Erratic turbine controls 10 83/06/27 F 77.8 B 2 N/A CD VALVEX MSIV Stem packing found Icaking in drywell. Repack stem k

i 1

j 4 .

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3 I 3 3 4 k Exhible G. Instructhms F: Forced Ressim: Methool:

i 5: Scheduled A Equipment Fellnee(Esplain) 1-Manuel fin roersesehm of Dass 2-Manuel Scism. Entry Sheets few l.icensee B-Melntenance of Tesl 1

C. Refueling 3 Automatic Scism. Event Repent (LFR) File INURLG ,

! 0161)

D Reguistewy Resielction 44)tiu e (Esplein) 4 E4)perator T sinheg & License Emendnsilim 5

F. Adminislistive G4)pesselonel Essin (Esplein) Exhible l .Same Source i

I l'8/77) il Other (Esplain) *

, , , BOSTON EDISON COMPANY j PILCRIM NUCLEAR POWER STATION l

Summary of Operations for June, 1983 The unit was operating at.100% power at the start of the month.

4

~ On June 1, the "B" emergency diesel generator was declared inoperable because I of a loss of speed control. (Ref: LER 83-33/03L-0). A power reduction was made on June 4 to backwash the condensers, returning to full load the same day.

On June 5. the "C" SSW pump was made inoperable to correct vibration problems.

and perform preventive maintenance. On June 6 the A0 5033B nitrogen purge .

j_ valve was made inoperable when it could not pass the required timing sur-1-

veillance test (Ref: LER 83-34/03L-0). The "B" D/G was returned to service the same day.

h On June 10..the RWCU System was removed from service in an attempt to identify the source of increasing drywell leakage. A scheduled feedwater heater maintenance outage and drywell entry was started on June 11. Drywell inspection found a leaking hinge pin cover on a feedwater check valve. The 1400-4A MOV, core spray test valve was found with 3~out of 4 operator mounting cap screws-missing (Ref: LER 83-35/03L-0). Various steam leaks were also repaired in the condenser area. Anodes were changed in the water boxes and a ground was b

repaired on the "B" 125 VDC battery system. Two drywell air flow dampers l were found malfunctioning ; an air flow balance was performed after their repair. A seismic hanger was found with loose bolts on the "A" RHR loop. The ,

bolts were tightened and the reactor made critical on June 14 at 2000 hrs.

and the unit placed on line at 0808 hrs. on June 15. On June 16, while reducing 4 power for a rod pattern change the unit tripped at 0030 hrs, because of erratic EPR control. The "C" S/RV was used for pressure control during this scram.

After adjustment, the reactor was made critical at 1157 hrs, the unit placed on line at 1900 hrs. and 100% power was achieved on June 17. Later the same-day, PNPS Was notified by BECo Engineering Dept. that the "A" spent fuel pool heat exchanger support did not meet the required seismic loading criteria. (Ref:

LER 83-29/01T-0). The "A" & "B" SFP loops were isolated with the "B" loop used only as required until the support was returned to original design on June 25.

i On June 18, power was reduced for a condenser backwash and control rod exercises.

t Control rod 10-31 could not be withdrawn and the symmetric rods were inserted.

The maximum power available with this pattern was approximately 96%. The "C" i SSW pump was returned to service on this day. ,

On June 25, power was reduced for a condenser backwash and returned to full available power the same day.

On June 27, the unit was taken off-line because of increasing drywell leakage.

Drywell entry and investigation found MO 202-4B and 202-5A recirculation valves leaking. 'MSlV "B" stem packing was also found to be leaking. Repairs to the

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"B" 5th point heater. condenser tube cleaning and seal weld leaks in the drywell were also made during this outage. The unit remained off-line until the end of the month.

page 1 of 2

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NOTES: ,

1. The condensers were backwashed every weekend because of horseshoe crab intrusion.
2. The annual emergency preparedness drill was held on June 29.

SAFETY / RELIEF VALVE CHALLENCES MONTH OF JUNE, 1983 Requirement: T.A.P. II.K.3.3 Date: June 16, 1983 Valve #: 203-3C Reactor Pressure: 980 psi Reason: Manual actuation of the valve to control reactor pressure following a scram which was caused by MSIV initiation.

page 2 of 2

PILGRIM NUCLEAR POWER STATION. Month JUNE, 1983

^

MAJOR SAFETY RELATED MAINTENANCE .

CORRECTIVE ACTION ASSOCIATED LER SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT RECURRENCE CAC' A0 5033B Failed time test Oil in viv. Replace solenoid PDCR to replace solenoid'with 83-034/03L-0 /fi another model.

RWCU MO 1201-2 Packing leak Packing Inspected.MO.and None-routine maintenance N/A replaced valve 1 e 2 SSW 'C' SSW pump Vibration Rebuilt . Balance None-routine maintenance ~N/A pump & motor

, I&C 1RM 'A' switch Would not select misalign- Readjusted switch Will overhaul during refuel N/A ment outage Elec. pwr 'B' 125 VDC Ground Battery Cleaned battery Establish schedule to clean N/A

- system tracking periodically I

Elec pwr 'A' Battery Ground Steam leak Replaced MSIV 'B' None-routine maintenance (and N/A system Inboard limit installed plug in junction -

switch & repacked box) valve i Standby A0 95 No indication Limit switcl HReadjusted limit Inspected every three months N/A Gas switch D/G A'ux. 'B' D/G Would not take Governor Replaced governor Not servicable at site-will 83-033/03L-0 full load ship to vendor for overhaul.

i Cora Rep' lace bolts MOV 1400-4A Mounting bolts Vibration Applied thread locking com- 83-035/03L-0 -/fi Spray missing . pound and torqued to a higher ,

i Ft/lbs. l 1

l RBCCW Spent fuel Initial constru- Unknown Return to origi- None - isolated incident 83-029/01T-0

pool Ex.E206-A ction error nal design i E

e d

i

, l' . . .

REFUELING INFORMATION The following refueling information is included in the Monthly leport 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: January, 1984
3. Scheduled date for restart following refueling: April, 19E4 4.
5. Due to their similarity, requests 4, 5, & 6 are responded to collectively:
6. The fuel, which had been loaded during the 1981 scheduled refueling outage, is of the same P8x8R design, as loaded the previous outage consisting of 112 P8DRB282 assemblies and 60 P8DRB265 assenblies.
7. sa) There are 530 fuel assemblies-in the core.

(b) There are 936 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies.

The actual spent fuel storage capacity is 1770 fuel as semblies at present.

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

9.- kith present spent fuel in storage, the spent fuel pool nou has the capacity to accommodate an additional 834 fuel assemblies.

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BDETON EDISON COMPANY 500 50VLETON STREET 50sTON, MASSADHUSETTE D2199 WILLIAM D. H ARRINSTDN w .... .... ..... .,

August 4, 1983 BECo.83-206 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk Docket No. 50-293 License DPR-35

Subject:

June 1983 Monthly Report (Revised)

Dear Sir:

In accordance with PNPS Technical Specification 6.9.A.2, a copy of the revised Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.

This revision is provided to correct errors discovered in the June 1983 report. Please replace the original report now in your files with this copy.

Respectfully submitted, fk)

William D. Harri ton WDH/mg cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Standard BEco. Monthly Report distribution I