ML20115D767
| ML20115D767 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/30/1992 |
| From: | J. J. Barton, Bradley E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-92-2286, NUDOCS 9210210130 | |
| Download: ML20115D767 (8) | |
Text
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9 GPU Nuclear Corporation G G' Nuclear
- no;;;388 Forked River, New Jersey 08731-038E 609 971 4000 Wnter's Direct Dial Number
C321-92-2286 Octcoer 16, 1992 U.S. Nuclear Regulatory Commission ATTN: Document Control 01sk Washington, D.C.
20555 Des.r Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operatinc Report In accordance with the Oyster Creek Nuclear Generating Station Operating Lf cense 1
No. DPR-16, Apocndi:,, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Oper& ting Data (gray book information) for the Oyster Creek Nuclear Generating Station.
If you should have any questions, please contac' Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
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i.J. Bar on ice Pres' nt and Director Oyster Creek JJB/BCEM: jc Attachment tape art,Mp?)
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Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager I
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GPU Nuclear Corporation is a subscary of Genera! Pubhc U%t.es Corporahon
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W Monthly Operating Report September-1992 Oyster Creek operated at full power for the ' month of September and had a capacity factor of 99.5%, generating 436,986 megawstts electric net output.
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t MONTHLY OPERATING RE00RT i
The following Licensee Event Reports were submitted during the month of September, 1992:
LER 92-0J3 l
A reactor low water level scram from full power occurred on August 22, 1992, at i
1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br />.
A low-low water level condition occurred immediately after the scram, which resulted in the actuation of several engineered safety features:
Core Spray systerr. initiation, Diesel Generator start, primary containment-isolation, main steam isolation, Isolction Condenser initiation, and Standby Gas Treatmen' system init'ation. Once the Mala Steam Isolation Valves were closed, reactor water level was restored using the Feedwater eystem.
The reactor was i
cooled using the Isolation Condensers.
The cause of t5e event was a failed i
proportional amplifier in the Feedwater Control system, which caused the system to sense a large decrease in steam removed from the reactor vessel. The. system compensated for the apparent steam flow decrease by rapidly reducing Feedwater flow, which caused the low water level and scram. The safety significance of the event is considered minimal. The failed proportional amplifier ns replaced and the plant was restarted.
The feedwater Control-system is scheduled to be replaced in the upcoming refueling outage, j
LER 92-010 I
On August 24, 1992, the reactor was critical in the intermediate range and a plar.t heatup was in progret2.
At 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />, high team flow occurred during warmup of the Main Turbine that resulted in a reactor low water level scram.
This event was caused by a non-conservative drift in the opening adjustment of the #2 Turbine Stop Valve due to the locking screws loosening on its restoring arm. This drift resulted in the premature opening'of-the #2 Turbine Stop Valve after an adjustment wat made to the position of-the #2 Stop Valvt Internal Byphss Valve. The opening of the Stop Valve caused a high steam flow and resultant drop in reactor-pressure, which caused a level increase due to voiding (swell).
Opei Itors wera ccting to control and reduce water level when a second adjustment j
was made to the position of the Internal Bypass Velve that closed the Stop Valve, resulting ia a presure spike that caused void collapse. A rapid reduction in.
reactor water level followed (shrink), which caused a reactor scram. Subsequent to the scram, the plant was cooled down and the #2 Stop Valve operating mechanism
- was inspected.
The operating mechanism was reset, and tha restoring arm adjustment was locked with set screws, lack-nuts and a thread locking compound.
The operating mechanism was tested and the plant was restarted.
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' Monthly Operting Report Licensee Event Reports - Sept';bor (Continued)
LER 92-011 As a result of a review of INPO operating experience report OE 4967, the circuitry of six valves was identified as potentially susceptible to hot shorts during a control room fire that could render the valves inoperable at the remote shutdown panel, Three valves are associated with the "B" Isolation Condenser which is the protected system for maintaining the plant in a hot shutdown condition during a control room fire scenario.
The other three 4
valves are associated with the shutdown cooling and recirculation systems which are used to achieve cold shutdown.
The cause of this occurrence is an oversight in the Appendix R design.
The design did not ' evaluate the effects of s not short on the valve _ circuitry during the interim time it would take to 4
transfer to the remote or local shutdown panels.
The safety significance of.
this condition is minimal based on the low probability of the specific event.
The circuitry for the valves identified to have this problem will be modified in accordance with the Oyster Creek integrated schedule.
In the interim,_
operators will be made aware of the problem and guidance will be provided, i
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OPERATING DATA: REPORT OPERATING STATUS
- 1. DOCKET: 219
- 2. REPORTING PERIOD:
09/92
- 3. UTILITY CONTACT:
CD BRADLEY (609)971-4097
- 4. LICENSED THERMAL POWER (MWt):
-1930
- 5. NAMEPLATE RATING (GROSS MWe):
687.5'x'O.8 = 550
- 6. DESIGN ELECTRICAL RATING (NET MWe):.650
- 7. MAX 1 HUM DEPENDABLE CAPACITY (GROSS MWe):
632 8.~ MAXIMUM DEPENDABLE CAPACITY-(NET MWe):
610
- 9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE
- 10 POWER LEVEL TO WH'CH RESTRICTED, IF ANY (NET MWe):
NONE
- 11. REASON.FOR PESTRICTION, IF ANY:
j NONE 3
l MONTH YEAR CUMULATIVE
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- 12. REPORT PERIOD NNIRS 7h0.0-6575.0 199631.C 1
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- 13. HOURS RX CRITICAL 720.0
'6149.3.
130ft2.0
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- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2-I
- 15. HRS GENERATOR ON-LINE
-720.0 6070.8:
127153.1
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- 17. GROSS THERM ENERGY.(MWH) 1383974 11515079
-215840437-l 1A. GROSS-ELEC ENERGY (MWH) 454111 3832663 72518293-19.-NET ELEC ENERGY (MWH)
.436986-3687372 69;'s4060.
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- 20. UT. SERVICE FACTOR 100.0 92.3 63.7
- 21. UT AVAIL FACTOR 100.0 92.3 64.3
?99.5
- 91.9 56.3.
23.'UT CAP FACTOR (DER NET) 93.4
- B6.3 53.6-f
- 24. UT FORCED OUTAGE RATEE 0.0-4.2-
- 11. 2.-
- 25. FORCED OUTAGE HRS
- 0. 0 266.1 15957.3
- 26. SHUTDObNS SCHEDULED'OVER NEXT 6 MONTHS (TYPE, DATE, D*1 RATION) ;
t-14-R NOVEMBER 27, 1992, 75 DAYS
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
N/A
- NRC_RPT.WPD/65~
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AVERADE DAILY POWER LEVEL NET MWe DOCKET #..
50-219
- UNIT.
. OYSTER CREEK #1 REPORT DATE,
. OCTOBER 8, 1992
- COMPILED BY.
..ED BRADLEY TELEPHO14E #.
.609-971-4097 MONTH:
S2PTEMBER, 1992 DAX M
P.AX M
1.
-608 16.
606 2.
608 17,.
6:7 3.
602 18.
602 4,
601 19.
580 j
5.
605
'20.
605 i
6.
609 21.
606 i
7.
608 22.
604 l
8.
606 23.
GOS 9.
601 24.
617 10.
596 25.
620 11.
602 26.
619 12.
607 27.
617 13.
606 28.
617 14.
606 29.
617 15, 603 30, 618 t-4 i-NRC_RPT.WPD/64 3
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Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - SEPTEMBER, 1992 Name of Facility: Oyster Creek Station #1
{
Scheduled date for next refueling shutdown:
November 27, 1992 Scheduled date for restart following refueling:
February 10, 1993 5
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Will refueling or resumption of operation thereafter require a Technical i
Specification chenge or other license amendment?
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Importar.t licensing considerations associated - with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysie 4
1 methods, significant changes in fuel design, new operating procedures:
4 1.
General Electric Fuel Assemblies Fuel design and performance analysis methods have been approved by the NRC.
5 2.
Exxon Fuel Assemblies - No major changes have b6an made nor t'
are there any anticipated.
The number of fuel assemblies (a) in the core 560
=
(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 cf fuel assemblies:
4 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:
Full core discharge capacity to the spent fuel pool will be available through the 1996 refueling. outage.
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NRC_RPT.WPD/63 r
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4 I" FIT SHUTDOWNS AND POWER REDUOTIONS DOCFP.T NO:
50-219 UNIT NAME:
Oyster Creek DATE:
October 5. 1992 COMPLT*D 3Y: davidEsan TELEPHONE:
971-4818 REPORT MONTH September 1992 TYPE METHOD OF SHUTTING CORRECTIVE No.
DATE Ps Forced DURATION REASON (1)
DOWN TN2 REACTOR OR ACTIONS / COMMENTS i
S: Scheduled
(hours)
REDW ANG POWER (2)
Timre were no shutdowns or signific.st powe red. actions duriv the reporting period 1
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Equipaent Failure (Explain) e.
Operater Training & Lie Exam ~
1.
Manual.
" - b.
Maints**=nce or Test f.
Administrative 2.
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Refueling s.
Operational Error (Explain) 3.
Autoenatic Scram
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Regulatory Restriction h.
Other (Explain) 4.
other (Explain)
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