ML20083B646
| ML20083B646 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/31/1991 |
| From: | J. J. Barton, Bradley E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-91-2251, NUDOCS 9109250149 | |
| Download: ML20083B646 (7) | |
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GPU Nuclear Corporation G a Nuclear
":=:r 88 Forked Ryer, New Jersey 087310388 609 971-4000 Wnter's Direct Dial Number; September 13, 1991 C321-91-2251 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
Attached is a page listing the correct numbers for generator on line hours (year to date and cumulative) for June and July.
If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
Sincerely, M cM M
J.J. Barton Vice President and Director Oyster Creek JJB/BDEM: jc Attachment (MOR*RPT) cc:
Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager 91o9250149 910831 PDR (iDOCK 0500 9
p G 'C V a V V GPU Nuclear Corporation is a subsdary of General PutAc Uttties Corpora::on
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MONTHLY OPERATING REPORT - AUGUST 1991 At the beginning of August. Oyster Creek was increasing power following repairs to a leak in the condensate transfer system underground piping.
Power was limited due to failure of a seal on a reactor feedwater pump.
Following repair of the feedwater pump, full power was achieved on August 6.
On August 22, the "A" condensate pump tripped due to an electrical fault. An automatic scram due to a low-low water level containment isolation occurred and the plant cooled down using the isolation condensers and shutdown cooling
- systems, An " Unusual Event" was declared as required by emergency procedures.
Repairs to the condensate pump proceeded in parallel with a reactor start-up which was conducted on August 24th. The generator was placed "on-line" on August 25 and the plant remained at approximately 70% power through the end of August.
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MONTHLY OPERATING REPCRT, AUGUST 1991 The following Licensee Reports were submitted during the month of August, 1991.
LER 91-001 An area designated as a locked high radiation area was found enlocked. This condition is prohibited by Plant Technical Specification 6.13.2 and is being reported voluntarily.
A critique of this event was conducted and concluded that procedure controls, General Erployee Training, and Radiation Control Technician Training with respect to High Radiation Areas are all adequate and did not contribute to this event. This event was caused by several personnel errors all of which were contrary to an approved plant procedure.
During the past two years at least ten thousand entries have been made to locked high radiation areas without incident.
The personnel directly responsible for this event were contractor personnel and were determined to be negligent in performing their duties.
LER 91-004 On August 3,1991 a trouble alarm was received for a fire zone on the 51' elevation of the Reactor Building. The cause of the trouble alarm could not be determined, but failure of a detector circuit was recognized as a potential problem. An hourly fire watch was set, although a continuous watch is required for detector circuit failure which results in the inoperability of the associated fire suppresion system. On August 5th, troubleshooting determined that detectors for the affected circuit were disabled and that the deluge system for this area would not have automatically initiated, rendering it inoperable.
The failure to set the appropriate fire watch is attributed to personnel error, inadequate guidance, and the failure to take prompt action in evaluating the problem. This event is considered to have minimal safety significance because the other fire detection circuit in this area would have alarmed in the event of a fire and operators would still have been able to initiate the associated deluge system manually. Once it was recognized that the area deluge system was incperable, a continuous f_ ire watch was established.
Guidance has been given to the operators via memo that a delugo l
system in a fire area is to be considered inoperable when a detection system trouble alarm is received, until it can be proven otherwise.
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AVERAGE DAILY POWER L,EVEL NET MWo DOCKET #.
50219 j
UNIT.
. OYSTER CREEK #1 j
REPORT CATE.
.. SEPTEMBER-1, 1991 l
COMP! LED BY.
. ED BRADLEY TELEPHONE #.
.609-971-4097 HONTH:
AUGUST, 1991 Eh!
M QA1 W
l 1.
263 16, 601 2.
398 17.
588 t-3, 409 18, 576 4.
407 19.
593 5,
410 20, 561 6.
434 21.
599 7.
597 22.
71 8.
598 23.
0 9.
597 24.
O 10.
599 25, 136 11.
603 26, 388 12, 601 27, 407 13.
598 28.
462 14.
598 29.
547 15.
599 30.
386 31, 413 NRC_RPT.WPD/23
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r Oyster Creek Station #1 Docket No. $0 419 4
REFUELING INFORMATION - AUGUST, 1991 Name of Facility: Oyster Creek S&.ation #1 Scheduled date for next refueling shutdown:
November 27, 1992 Scheduled date for restart following refueling February 9, 1993 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures 1.
General Electric Fuel Assemblies Fuel design and performance analysis methods have been approved by the NRC.
2.
Exxon Fuel assemblies - No major changes have been made nor are there any anticipated.
The number of fuel assemblies (a) in the core 560
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(b) in the spent fuel storage pool = 1708 (c) in dry storage 44
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The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present Licensed capacity:
2600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
The reracking of the fuel pool is now complete.
All ten (10) racks are now installed.
Discharge capacity to the spent fuel pool will be available through the 1994 refueling outage.
NRC_RPT.WPD/22
OPERATING DATA REPORT OPERATING STATUS
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
8/91
- 3. UTILITY CONTACT:
ED BRADLEY (609)971-4097
- 4. LICENSED THERMAL POWER (MWt):
1930
- 5. NAMEPLATE RATING (GROSS MWe):
687.5x0.8=550
- 6. DESIGN ELECTRICAL RATING (NET MWe):
650 7.' MAXIMUM DEPENDABLE CAPACITY (GROSS KWe):
642
- 8. MAXIMUM DEPENDABLE CAP). CITY (NET MWe):
620
- 9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
NONE
- 11. REASON FOR RESTRICTION, 7F ANY:
NONE MONTH XEAB CUMULATIVE
- 12. REPORT PERIOD HOURS 744,0 5831.0 190127.0
- 13. HOURS RX CRITICAL 678.3 2444.8 121509.9
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 662.4 2354.5 118267.5
- 17. GROSS THERM ENERGY (MWH) 1105018.3 4121379.3 199016335.3
- 18. GROSS ELEC ENERGY (MWH) 350910 1341990 66947913 19.' NET ELEC ENERGY (MWH) 336597 1274119 64234151
- 20. UT SERVICE FACTOR 89.0 40.4 62.2
- 21. UT AVAIL FACTOR 89.0 40.4 62.8
- 24. UT FORCED OUTAGE RATE 11.0 11.6 11.6
- 25. FORCED OUTAGE HRS 81.6 309.6 15580.5 l
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,.DATE, DURATION):
NONE
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
N/A NRC_RPT.WPD/24 L
There has been some confusion as to the generator on-line hours cince the generator was taken of f-line in June of 1991 for 0.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> for a test during the Beginning of Cycle start-up.
This time was corrected on the June report, however, the 0.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> was not subtracted from the Year-to-Datt and Cumulative columns.
All correct values are listed below.
The values for August have already been adjusted.
QIN ON-LINE HOURS YEAR-TO-DATE CUMULATIVE May 0.0 1109.2 117022.2 June 67.8 1177.0 117090.0 July 515.1 1692.1 117605.1 Augusc 662.4 2354.5 118267.5 NRC_RPT.WPD/25
t U25IT SHUTDOWitS AND POWER REDUCTIONS DOCKET NO.-
50-219 f
UNIT NAME-Ovster Creek
l DATE-Sept. 1991 l
COMPLETED BYL R.
Baran
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TELEPHONE 971-4640 REPORT MONTil Aucust. 1991'-
1 TYPE METHOD OF S!!UTTING Ll F: Forced DURATION DOWN THE REACTOR OR i
NO.
DATE S: Scheduled
'(Hours)
REASON (1)
. REDUCING PO=ER (2)
CORRECTIVE ACTIONS / COMMENTS i
107 910722 F
2.1 A
2 13-U-l Outage to repair-
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Condensate Storage Tank.
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108 910822 F
'79.5 A
3 13-U-2 outage. Full scram due I
4 to trip of
'A' Condensate Pump.
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109 910830 S
O A
1
'A' Condensate Pump removed from i
service for Engineering evaluation (load reduction to 50% power) l l
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Summary :
(1) REASON MET!!OD a.
Equipenent Failure (Explain; e.
Operator Training & License Exam 1.
Manual b.
Maintenance or Test f.
Administrative 2.
Manual Scram c.
Refueling g.
Operational Error (Explain) 3.
Regulatory Restriction h.
Other (Explain) 4.
Other (Explain) i 1
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