ML20059L630
| ML20059L630 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/31/1993 |
| From: | J. J. Barton, Egan D, Krall J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-93-2296, NUDOCS 9311170239 | |
| Download: ML20059L630 (7) | |
Text
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g GPU Nuclear Corporation
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Post Office Box 388 J
-i Route 9 South Forked River, New Jersey 08731-0388 609 971 4000 Wnter's Direct Dial Number:
C321-93-2296 November 11, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject:
Dyster 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.
If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
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- incerely,
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l Jj Barton V
i President and Director ter Creek 1
JJB/BDEM: jc Attachment (MoR-RPT.oCT) cc:
Administrator, Region 1 i
Senior NRC Resident Inspector Oyster Creek NRC Project Manager s
F 9311170239 931031 PDR ADDCK 05000219 d l
R PDR 1IUU d GPU Nuclear Cordorat:on is a subsdag of Genera! Pubhc UNmes Corporation l
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Monthly Doeratina Report October 1993 Oyster creek entered October operating at full power and generated 463,798 net electric megawatt hours during the month.
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HONTHLY OPERATING REPORT LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of October, 1993:
LER 92-013 R1 On November 30, 1992 local leak rate testing results indicated that NSO4B, the i
outside containment main steam isolation valve, exceeded the leak rate limit of 12.08 SCFH at 20 psig as specified in plant Technical Specification 4.5.F.2.
As the leak rate was not quantifiable, the.6 L, leakage limit for the combined type B and C leak rate tests as specified in Technical Specification 4.5.F.1 was also exceeded. On December 24, 1992, local leak rate testing results indicated that NS03B, the inside containment main steam isolation valve, also exceeded the leak rate limit of 12.08 SCFH at 20 psig.
The leak rate was measured to be 17.12 SCFH at 20 psig.
i The cause of these occurrences was component aging. The seating surfaces of NSO4B were degraded, and the actuator springs on NS03B were in a weakened condition. The safety significance of these events is considered minimal as the total penetration leakage would have been limited by the NS03B leakrate.
The internals of NSO4B were replaced with modified components. The actuator springs were replaced on NS03B. To minimize the possibility of a recurrence of the relaxed spring phenomenon, a maintenance activity will be implemented to replace the actuator springs on a routine basis. Satisfactory leak rate tests were performed on both valves prior to startup.
LER 93-005 During a recent review of the Limiting System Setpoints in the Oyster Creek Nuclear Generating Station Technical Specifications, it was determined that Technical Specification 2.3.P.(2) could not be proven to adequately protect loads on the 4160 volt AC buses as designed. This setpoint,3671 VAC 21%,
protected Oyster Creek from a degraded grid undervoltage condition and was approved by the USNRC on October 16, 1981.
During the month of August 1993, it was discovered that the possibility existed that certain loads downstream of the 4160 VAC buses may not be able to perform their intended safety functions if: 1) a worst case design basis LOCA occurreo; 2) the grid voltage degraded to slightly above the trip setpoint;
- 3) the Station Voltage Regulators were inoperable; and 4) one of the Station Startup Transformers was lost. This occurrence is of minimal safety significance as a degraded grid condition is highly unstable and would be of limited duration, and the probability of all four conditions occurring l
simultaneously is extremely remote. Additionally, calculations and testing l
have demonstrated for the worst case AC control circuit, the electrical l
contactors will function based on the existing undervoltage relay settings and their tolerances. Appropriate corrective action will be included in a revision to this LER which will be submitted when the evaluation of the undervoltage conditions is complete.
i Dycter Crosk Station #1 Docket No. 50-219 i
REFUELING INFORMATION - OCTOBER, 1993 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: Currently projected for September,1994 Scheduled date for restart following refueling: Currently projected for December, 1994 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 f
methods, significant changes in furs' design, new operating procedures:
l 1.
General Electric Fuel Assemblies - Fuel design and performance analysis methods have been approved by the NRC.
The number of fuel assemblies (a) in the core 560
=
(b) in the spent fuel storage pool 1878 1
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(c) in dry storage 8
=
l The present licensed spent fuel pool storage capacity and the size of any j
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:
l Full core discharge capacity to the spent fuel pool will be available through the 1996 refueling outage.
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NRC_RPT.WPD/102
AVERAGE DAZLY POWER LEVEL NET MWe DOCKET #.
.50-219 UNIT.
. OYSTER CREEK #1 REPORT DATE.
. 11-04-93 COMPILED BY.
. JIM KRALL l
TELEPHONE #...
.609-971-4115
{
MONTH:
OCTOBER, 1993 M
M M
M 1.
621 16.
625 2.
619 17.
624 l
l 3.
619 18.
623 i
i 4.
621 19.
622 5.
619 20, 622 6.
623 21.
621 7.
621 22.
623 8.
618 23.
617 9.
618 24.
625 10.
621 25.
624 11.
624 26.
624 12.
624 27.
625 13.
626 28.
625 14.
625 29.
625 15.
624 30.
624 31.
627 NRC_RPT.WPD/103
t OPERAT2NG DATA REPORT OPERATING STATUS I
I
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
10/93 l
- 3. UTILITY CONTACT:
.IIM KRALL (609)971-4115 t
- 4. LICENSED THERMAL POWKA (MWt):
1930
- 5. NAMEPLATE RATING (GROSR MWe):
687.5 x 0.8 = 550 l
- 6. DESIGN ELECTRICAL RATING (NET MWe):
650 i
- 7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
632
{
- 8. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
610
- 9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
f NONE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
NONE i
i
- 11. REASON FOR RESTRICTION, IF ANY:
NONE MONTH YEAR CUMULATIVE
- 12. REPORT PERIOD HOURS 745.0 7296.0 209136.0
)
- 13. HOURS RX CRITICAL 745.0 6226.6 138135.0
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 745.0 6190.4 134737.7
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- 17. GROSS THERM ENERGY (MWH) 1435532 11797411 230306165 I
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- 18. GROSS ELEC ENERGY (MWH) 481358 3901711 77297849 l
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- 19. NET ELEC ENERGY (MWH) 463798 3751618 74135242
- 20. UT SERVICE FACTOR 100.0 84.8 64.4 j
- 21. UT AVAIL FACTOR 100.0 84.8 64.4
- 24. UT FORCED OUTAGE RATE 0.0 0.0 10.6
- 25. FORCED OUTAGE HRS 0.0 0.0 15957.3
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NONE
- 1
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
N/A j
NRC_RPT.WPD/104 i
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-._-.,._,,m..
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UNIT SIPJTDOWNS AND POWER REDUCTIONS a
DOCKET NO:
30-21'1 UNIT NAME:
A ter Creek DATE:
Nosember 5. 1993 COMPLT'D BY Dav h lgan TELEPHONE:
E -4818 REPORT MONTH:
October 1993
".YPE METHOD OF SRUTTING CORRECTIVE No.
DATE F: Forera D'JRATION REASON (1)
DOWN TEE REACTOR OR ACTIONS / COMMENTS St Sche..uted (hours)
REDUCING POWER (2)
There were no shutdowns or major power reductions during this reporting period.
SUMMARY
(1) REASON (2) METHOD a.
Equipment Failure (Explain) e.
Operator Training & Lie Eass 1.
Manumi b.
Maintenance or Test f.
Administrative 2.
Manual Scrata c.
Refueling g.
Operational Error (Explain) 3.
Automatic Scrars d.
Regulatory Restriction h.
Other (Explain) 4.
Other (Emplain).
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