ML20077A139
| ML20077A139 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/06/1983 |
| From: | Harrington W, Whitney G BOSTON EDISON CO. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 83-147, NUDOCS 8307220197 | |
| Download: ML20077A139 (7) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL 50-293 DOCKET NO.
UNIT Pilgrim 1 06/06/83 DATE G.G. Whitney COMPL*.TED BY TELEPHONE (6171746-7900 MAY, 1983 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWeNet)
(MWe Net 1 662.
649.
g7 g
665.
Ig' 665.
2 664.
665.
39 3
~~
664.
666.
20 4
ss2.
666.
23 5
664.
664.
3 6
664.
534.
23 7
663.
664.
24 3
A6L 665.
23 p
661.
666.
26 10 659.
665.
y g;
An6.
663.
3 g3 664.
663.
29 g3 664.
660.
30 p
662.
603.
33 15 663.
INSTRUCTIONS On this format. list the averup dasy unis power te,et in MWe. Net for each day in the reporting m the nearest whole rnecurt.
~T) 8307220197 830606 DR ADOCK 05000293 PDR
OPERATI G DATA REPORT
~
DOCKET NO. 50-293 DATE 06/06/83 COMPLETED BY G.C. Whitney TELEPHONE (A1747 tin-7900 s
OPERATING STATUS Pilgrim 1 Notes
- 1. Unit Name:
May, 1983
- 2. Reporting Period:
1998.
- 3. LicensedThermalPower(MWt):
678.
- 4. Nameplate Rating (Gross MWe):
655.
' 5. Design Electrica! Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): 690.
- 7. Maximum Dependable Capacity (Net MWe): 67n
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
NONE N'ONE
- 9. Power LevelTo Wluch Restricted,if Any (Net MWe):
- 10. Reasons For Restrictions,If Any:
N/A This Month Yr.-to.Dete Cumulative i
'744.0' 3623.0 91823.0
- 11. Hours la Reporting Period 744.0 3568.3 65513.6 l
- 12. Number Of Hours Reactor Was Critical 0.0 0.0 0.0
- 13. Reactar Reserve ShutdownHours 744.0 3542.1 63421.3
- 14. Hours Generstor On-Line 0.0 0.0 0.0
- 15. Unit Reserve Shutdown Hours
'1454136.0 6862464.0 109576056.0
- 16. Gross Thermal Energy Generated (MWH) 503730.0 2385640.0 36712464.0
- 17. Gross Electrical Energy Generated (MWH) 484795.0 2295774.0 35277285.0
- 18. Net Electrical Energy Generated (MWH) 100.0 97.8 69.1 100.0 97.8 69.1
- 19. Unit Service Factor
- 20. Unit Availability Factor 97.3 94.6 57.3
- 21. Unit Capacity Factor (Using MDC Net) 96.7 58.7 99.5 l
- 22. Unit Capacity Factor (Using DER Net) 2.2 9.3 t'
0.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6.Weaths (Type. Dete,and Duration of Each t:
06/10/83 and end on 06/15/83.
Maintenance Outane scheduled to start on I
Unit operating
- 25. If Shut Down At End Of Report Period.Estansted Date of Startup:
Forecast Achieved
- 26. Units in Test Status (Prior to Commercial Operation):
l INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Y
REFUELING INFORMATION The following refueling information is included in the Monthly Report as 18, 1978:
requested in an NRC letter to BECo dated January For your. convenience, the information supplied has been enumerated so that each number curresponds to equivalent notation utilized in the request.
The name of this facility is Pilgrim Nuclear Power Station, Docket 1.
Number 50-293.
January, 1984 Scheduled date for next Refueling Shutdown:
2.
April, 1984 Scheduled date for restart following refueling:
3.
4.
D.2c to their similarity, requests 4, 5, & 6 are responded to collectively:
5.
The fuel, which had been loaded during the 1981 scheduled refueling f
outage, is of the same P8x8R design, as loaded the previous outage 6.
consisting of 112 P8DRB282 assemblies and 60 P8DRB265 assemblies.
There are 580 fuel assemblies in the core.
7.
(a)
There are 936 fuel assemblies in the spent fuel pool.
-(b)
The station is presently licensed to store 2320 spent fuel assemblies.
The actual spent fuel storage capacity is 1770 fuel assemblies at 8.
(a) present.
The planned spent fuel storage capacity is 2320 fuel assemblies.
.(b)
With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 834 fuel assemblies.
9.
i n
-. -.. ~... -., _.,,
.,,-,.,,-v-,-,..
,-.,,.-..,~n
,.,-,,---,-_,,,,---,+--,,--e-,,
6 si.uiu tt tmt.i.s.an rinn.n u ni ""
MONTH May. 1983 HAJOR SAFETY RELATED HAINTENANCE CORRECTIVE ACTION SYSTEH COMPONENT I
HALFUNCTION CAUSE MAINTENANCE TO PREVENT RECURRENCE ASSOCIATED LER None-Ro"tinae Maintenance N/A Original Replaced Switch INOP SBLC TIC 1154 u
Unit Faileil SBLC P207 A & B Packing Leak
, Normal Repacked
.None-Routine Maintenance N/A (SLC)
RCIC RCIC Controlle r Reading 60 GPM Unknown Checked calibra-None-Routine Maintenance N/A l
tions, flushed
' lines RCIC AD1301-71~
Steam Leak N/A Reinjected Fur-MR Written for permanent repair N/A manite.
IIPCI PS-II Leaking
. Unknown Replaced Switch None-Routine Maintenance N/A IIPCI Discharge Pres - Reading liigh Unknown liecalibrated None-Routine Maintenance N/A sure Trans-Transmitter mitter llPCI IIPCI Stop Viv Packing Leak N/A Repacked Will investigate valve inter '
To be issued A02301-31 nal condition IIPCI R02301-62E Steam Leak-Age Replaced Casket None-Routine Maintenance N/A IIPCI R02301-62 A&B Steam' Leak Age Re"placed Casket None-Routine Maintenance N/A SSW E209B Drain Valves Cor - Age Replaced Valves None-Routine Maintenance N/A roded y
SSW E209A Drain Valves Cor Age Replaced Valves None-Routine Maintenance N/A roded FIRE Fire Door Cab-Cable loolsened N/A Readjusted Cable None-Routine Maintenance 83-027/03L-D le SGTS SBGT B Control Failed Flow test Dirty -pre-Clean pre-filter New pre-filters ordered N/A '
Room Environ-filter mental EDG
'B' Diesol Broken fuel pump Fastener Replaced with new New type fastener used, de-83-023/03L-0('A')
.ator belt failure alligator fastene tailed instructions provided 83-028/03L-0('B')
i
BOSTON EDISON COMPANY I
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for May, 1983 The unit was operating at 100% power at the start of the month.
.On May.4th, the "A" SGTS was made inoperable for maintenance and the "A" i
- emergency diesel generator fuel booster pump belt broke during surveillance and was returned to service the same day. (Ref: LER 83-23/03L-0). The "A" SGTS was made operable on May 6th, the "B" SSW loop was made inoperable for maintenance and power was reduced to 50% for a short period for a condenser backwash. On May 7th, the "B" SSW loop was made operable. On May 8th, the RCIC was taken out of service for a short period to check calibration of a flow indicator. The unit was operated at 100% until May 15th when power was reduced for a. condenser backwash with a return to 100% the same day.
r On May 18th, the "B" diesel generator fuel booster pump belt broke during scheduled surveillance (Ref: LER 83-028/03L-0). A crack was found in an ex-pansion joint on the "B" train 5th point heater.
On May 20th, power was reduced to backwash the condensers. The "A" SSW loop was taken.out of service on May 26th to replace a drain valve and was placed back in service the same day. On May 27th, power u s reduced for a condenser backwash with a return to 100%'the same day. The HPCI system was taken out of service on May 28th to repack A0-2301-31 valve, because of a steam leak.
The system was returned to service the next day. The unit ended the month at 100% power.
NOTES:
1.
The condansers were required to be backwashed every weekend because of an influx of horseshoe crabs.
2.
Reactor pressure is limited to 1025 psig because of safety /
relief valve simmer margin considerations.-
A.
i SAFETY / RELIEF VALVE CHALLENGES MONTH OF MAY, 1983 Requirement:
T.A.P.
II.K.3.3 There were no challenges to the safety / relief valves during the month of May, 1983.
l y_
~ _ _,.. _ -.
y
j DOCKET NO.
50-293 UNIT SilUT1) OWNS ANI) POWER REIPUCTIONS UNIT NAME Pilarrim 1 DATE 06/n6/at COMPLETED BY G.G. Whitney MAY* 1983 REPORTlWONT11 TELEPflONE (617)746-7900 q
"k w
o Cause & Corrective
] Y ">gd Event E,
k" Acthm to 3E 3
Lkensee E*
{
No.
Ihle h
gg g
7 j di g Report #
iku O
Prevent Recunence oE at 6
NONE s
i 1
i t
?
s I
i b
3 4
I 2
Meshed:
Exhibit G Instructkms I:: Forced Reason:
I 5: Schedided A Equipment Fallme(Explain) 1-Manual for Prepsesehm of Data II. Maintenance of Test 2-Manuel Scram.
Entry Sheets for I.kensee 3-Automalle Scrsm.
Event Report (LER) File INUREG.,
i C-Refueling D Regulatory Resielction 44)ther IEmpialn) 0161)
E-Operator Trainhis A License Emandnathm 5
F-Adudnistrailve Exhible I Same Simrce
)
04)perational Ersur (Emplain)
!i (9/11)
Il-Other (Explain)
Ef BDETON EpisON COMPANY B00 BOvLaTON STREET BOSTON, MASSACHUSETTS 02199 WILLIAM D. HARRINGTON e& ween wees ensososest June 14,1983 BECo. Ltr. #83-147 Director Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket No. 50-293 License DPR-35
Subject:
May 1983 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.
Respectful,1y submitted, William D. Harringtan WDH/mg cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue Kinf of Prussia, PA 19406
- ;i,
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