ML20079D612
| ML20079D612 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/30/1991 |
| From: | Richard Anderson, Munro W BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-088, 91-88, NUDOCS 9107180316 | |
| Download: ML20079D612 (7) | |
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BOSTON EDISON Pilgnm Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts o2360 R. A. Anderson Vice President &
Uu"Ie"EE$t,ons July 11,1991 BECo Ltr. #9'-088 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-2]EL
Subject:
June 1991 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.
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'4 (RA. Anderson HJH/bal Attachment cc: Regional Administrator, Region i U.S. Nuclear Regulatory Commiss bn 475 Allendale Rd.
King of Prussia, PA 19406 Senior Resident Inspector 9107160316 910630 PDR ADOCK 050002f3 R
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' AVERAGE DAILY LINIT POWER LEVfL DOCKET NO.
50-293 UNIT Pilarim 1 i
DATE July
- 11. 1991 COMPLETED BY W. Munro TELEPHONE (508) 747-8474 MONTH June 1991 DAY AVERAGE. DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)
(HWe-Net) j 1
0 17 0
2 0
18 0
3 0
19 0
4 0
20 0
l 5
0 21 0
l l-6 0
22 0
1 7
0 23 0
1 8
0 24 0
9 0
25 0
10 0
26 0
11 0
27 0
l 12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 N/A 16 0
(
This format lists the average daily unit power level in HWe-Net for each day l.
In the reporting month, computed to the nearest whole megawatt.
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DOCKET NO.
50-293 DATE July ii. 1991 COMPLETED BY
__H. Hunro TELEPHONE
,_(508) 747-8474 OPERATING STATUS Notes 1.
Unit Name Pilarim 1 2.
Reporting Period. lune 1991 3.
Licensed Thermal Power (HHt) 1998 4.
Nameplate Rating (Gross HWe) 676 5.
Design Electrical Rating (Not HWe) 655 6.
Maximum Dependable Capacity (Gross HWe) 696 7.
Maximum Dependable Capacity (Net HWe)
(1Q 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 HHe)
None
- 10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 720.0 4343.0 162671.0
- 12. Number Of Hours Reactor Has Critical 0.0 2850.2 95450.9
- 13. Reactor Reserve Shutdown Hours 0.Q 0.0 0.0
- 14. Hours Generator On-Line 0.0 2B1(LZ 91766.3
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (HHH) 0.0 5276592.0 158618088.0
- 17. Gross Electrical Energy Generated (MHH) 0.0 1812180.0 53459694.0
- 18. Net Electrical Energy Generated (HWH) 0.0 1743822.0 51370230.0
- 19. Unit Service Factor 0.0 65.6 56.4
- 20. Unit Availability Factor 0.0 65.6 56.4
- 21. Unit Capacity Factor (Using HDC Net) 0.0 59.9 47.1
- 22. Unit Capacity Factor (Using DER Net) 0.0 61.3 48.2
- 23. Unit Forced Outage Rate 00 3.6 12.5
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
Refuelina Outaae No. 8. aoorodmatelv 85 days
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup 7/23/91 l
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r BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATf0N 1
DOCKET NO. 50-293 Operational Summary for June 1991 Continued refueling outage number 8.
l Safety Relief Valve Challenges Month of June 1991 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 operate via reactor pressure, auto signal (ADS) or control switch (manual).
Ref. BECo ltr. #81-01 dated 01/05/81.
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REFUELING INFORMATION 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 3,1993 3.
Scheduled date for restart following present refueling:
July 23, 1991 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 1991 refueling outage was of the same design as loaded in the previous outage, and consisted of 168 assemblies.
7.
(a) There are 429 fuel assemblies in the core.
(b) There are 1640* 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 accommodate an additional 831 fuel assemblies.
Includes 151 fuel assemblies in the spent fuel pool which will be returned to the core for Cycle 9.
Also includes one (1) reconstituted fuel bundle in the spent fuel pool containing i failed fuel rod discovered during sipping procedure.
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EU Honth June 1991 PILGRIM NUCLEAR POWER STATION HAJOR SAFETY RELATED HAINTENANCE SYSTEM COMPONENT HALFUNCTION CAUSE HAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER Salt Loop "A" piping Identified wall Excessive cor-Removed and replaced Unlined spool pieces N/A Service within the intake thinning.
rosion and del-various rubber lined will be replaced during Water structure.
amination of spool pieces within mid-cycle outage (1992).
rubber lining the intake structure System within spool Temporary Hodification (SSH) pieces.
TH 91-32 installed replacing two rubber lined spool pieces with two unlined spool pieces.
Reactor Heat Exchanger Cracks on heat Metal fatigue Installation of six Perform inspection N/A Building E-209 "A".
exchanger (6) stiffener plates during RFO-9.
Closed partition to each partition plate Cooling plates.
per FRN 91-03-20, provi-ding greater resistance Hater to fatigue failure.
System)
(RBCCH)
Tubes leaking Corrosion, and Thirteen (13) tubes inlet end ero-required plugging and sion.
twenty nine (29) other tubes required replugging.
Feed-Check Valves Failed LLRT Hinge pin mis-Replaced disks, installed Refer to associa-LER 90-013-00 l
water 6 CK-58A and B surveillance alignment new ninge pin configu-ted LER.
("To be issued) l System and 6 CK-62 A and B procedure.
causing disks ration and replaced soft to seat in-seat material.
(FH) correctly.
- UNIT..SHUTDONNS AND POWER REDUCTIONS ~
' DOCKET NO. 501293-NAME.
Pilarin 1
.DATE July 11.1991' COMPLETED.BY H. Munro' 2*!
TELEPHONE' -(508)'747-8474L REPORT. MONTH-June 1991-
-METHOD OF
. LICENSE CAUSE & 00RRECTIVE ENT.
ACTION'TO PREVENT DURATION
. SHUTTING l EVENT SYSTEg'.
- 00MyE-RECURRENCE-l NO.
DATE TYPEI (HOURS)
REASON :
'DOWN REACTOR.
REPORT # -
2 3
CODE COD 8 05/04/91 S
720.0 C
4' N/A N/A N/A Refueling outage No. 8 (continuation)
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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 Auto Scram Preparation of 2
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) 4 1
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