ML20212P149
| ML20212P149 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1986 |
| From: | Baran R, Fiedler P, Notigan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8703160004 | |
| Download: ML20212P149 (7) | |
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M W mLY OPERATING REPORT - DECEMBER:1986 At the beginning of the report period, Oyster Creek was shut down for the Cycle 11 Refueling / Maintenance / Modifications Outage.
- Reactor. 'startup connenced on December 21.
Drywell inspections were performed on _ December 22 and December 23 at reactor pressures of 500 psig and L.1000 psig, crespectively.
The inspections revealed no-major
~
discrepancies.
Onl December 24, an automatic reactor scram occurred at approximately 3.5%
power while reducing power and reactor pressure. The reactor scrammed on high neutron flux in the IRM range due to cold feedwater being injected
[
into the reactor-vessel.
A plant shutdown was in progress to repair a manway leak-on 1-1 steam reheater.
Following - completion of repairs and a critique of the event, reactor startup commenced on December 26.
Criticality was achieved and plant heatup continued to normal operating pressure.
b Operability and calibration problems were experienced with the Intermediate Range Monitors '(IRMs),
which delayed placing the turbine-generator on-line until December 28.
Drywell inerting comenced on December 27.
. The reactor mode switch was placed.in the "Run" mode on December 28; the turbine-generator was placed "on-line" at a load of approximately 110 me.
Reactor power was slowly increased to a maximum generator load of approximately 234 m e, which was reached on December 29.
On December 29, a significant steam leak developed in the expansion bellows downstream of a reheater supply line relief valve, which had lifted.
Efforts to
" gag" the relief valve were unsuccessful.
Consequently, a power reduction was initiated and the generator was taken off-line.
While reducing steam chest pressure in an attempt to repair the steam leak, condenser vacuta deteriorated.
A decision was made to
- manually scram the reactor.
Cooldown continued and the plant was placed in a cold shutdown condition.
At the end of the report period, the plant was in an outage planned for a 7-day duration to facilitate replacement of the failed expansion bellows and two (2) additional bellows, replacement of the reheater supply line relief' valve, modifications to Average Power Range Monitor (APRM) electronics, IRM and CRD position indication repairs in the drywell and other target-of-opportunity maintenance activities.
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MONTHLY OPERATING REPORT-DECEMBER-1986 The following -Licensee Event Reports were submitted -during the month of December 1986:
Licensee Event Report 50-219/86-023 - As a result of design reviews for modiffcations.to be implemented during the llR refueling outage, an existing design deficiency was identified.
A single failure of either 125 VDC power panel D or F would render the automatic initiation of both containment spray l
systems. inoperable.
The safety significance of ~the single failure is considered minimal as containment spray is not needed immediately during a loss of. coolant accident and both containment spray systems can be manually actuated even with the postulated single failure.
GPUN had previously initiated the ~ research and technical justification to remove the automatic start feature associated-with the containment spray system. - In the interim, to assure all operators are aware of the potential for the single failure mode discussed in this report, this Licensee Event Report will be issued as required reading for all licensed operators.
Licensee Event Report 50-219/86-028 0n November 10, 1986 ft was discovered that all -reactor low-low water level (RE02) initiation signals to the Standby Gas Treatment System had been jumpered out on November 3.
The l
RE02 sensors were being replaced and jumpers had been installed to prevent spurious trips caused by de-energizing the instrument channels for replacement or from work being performed at the instrument racks.
The condition was discovered on November 10, 1986 during modification test activities.
The i
order was given to place the plant in a condition in which secondary containment was not required, isolate reactor building ventilation (EIIS System Code VA), initiate the SGTS, and teminate all work activities which could lower vessel level or release radioactive material.
Control room i
personnel inadvertently did not secure reactor building ventilation.
This was discovered on November 11, 1986 at approximately 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br /> and reactor building ventilation was immediately secured.
The cause of the event is I
attributed to personnel error.
The equipment control procedure will be revised to require procedural control of installations using a large quantity of temporary variations or when the sequencing of temporary variations is important. Additionally, this report will be distributed as required reading for all personnel involved in the temporary variation process.
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'd Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - DECEMBER,1986 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: N/A Scheduled date for restart following refueling:
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No Scheduled date(s) for submitting proposed licensing action arri supporting information:
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. New operating procedures, if necessary, will be submitted at a later date.
- 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
=
(b) in the spent fuel storage pool = 1392 (c) in dry storage 20
=
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:
Reracking of the fuel pool is in progress. Six (6) out of ten (10) racks have been inste'. led to date. When reracking is completed, discharge capacity to the spent fuel pool will be available until 1990 refueling outage.
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OPERATING DAIA REPORT OPERATING SIATUS 1.
DOCKET:
50-219 2.
REPORTING PERIOD:
DECEMBER, 1986 3.
UIILITY CONTACT:
DONALD V. NorIGAN 609-971-4695 4.
LICENSED THERMAL POWER (MWt):
1930 5.
FAMEPLATE RATING (GROSS MWe):
687.5 X 0.8 = 550 6.
DESIGN ELECTRICAL RATING (NET MWe):
650 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS Mde):
650 8.
MAXIMUM DEPENDABLE CAPACITY (NET MWe):
620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
t0NE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
N/A
- 11. REASON EOR RESTRICTION, IF ANY:
NONE MORTH YEAR CUMULATIVE
- 12. REPORT PERIOD HRS 744.0 8760.0 149233.0
- 13. HOURS RX CRITICAL 77.6 2389.1 94836.5
- 14. RX RESERVE SHTDWN HRS 0.0 448.5 918.2
- 15. HRS GENERATOR ON-LINE 37.0 2310.9 92370.0
- 16. Ur RESERVE SHrDWN HRS 0.0 452.8 1208.6
- 17. GROSS THERM ENER (MWFi) 44666 4119004 152996473
- 18. GROSS ELEC ENER (MWH) 6080 1377560 51668245
- 19. NET ELEC ENER (MWH) 535 1301476 49610077
- 20. UT SERVICE FACTOR 5.0 26.4 61.9
- 21. UT AVAIL FACTOR 5.0 31.5 62.7
- 24. Ur FORCED OUTAGE RATE 63.3 8.6 10.3
- 25. FORCED OUTAGE HRS 63.9 216.2 10651.8
- 26. SWrDOWNS SCHEDULED OVER NEXT 6 MORDIS (TYPE, DATE, DURATION):
N/A
- 27. IF CURRENTLY SHUrDOWN ESTIMATED STARTUP TIME:
1/6/87 19658
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AVERAGE DAILY POWER LEVEL NET MWe DOCKET 4........ 50-219 UNIT.. >......... 0YSTER CREEK #1 REPORT DATE....... JANUARY 8,1986 COMPILED BY....... DONALD V. NorIGAN '
TELEPHONE #...... 609-971-4695 MONril DECEMBER,1986 DAY W
DAY M_W.
1.
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0 18.
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0 22.
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82 14.
0 29.
145 15.
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UNITSituTDOWNS AND POWER REDUCDONS er Creek T
E DATE December 1986 COMPLETED 3Y R.
Baran REPORT MONHI December 971-4640 TELErtlONE
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%'8 Cause & Corrective No.
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46 4/12/86 S
6243.4 C
1 N/A N/A N/A llR Outage.
47 12/28/86 S
1.6 B
4 N/A N/A N/A Turbine trip testing.
Reactor remained critical.
48 12/29/86 F
51.9 A
1 N/A N/A N/A Manual scram during shutdown process due to vacuum decreasing.
Required repairs of the cross-around relief valve expansion joints.
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4 1
2 3
4 F: Forced Reason:
Method:
Exhibit G. instructions 5: Scheduled A-Equipment Failurs(Emplain) l-blanual for Pseparation of Dasa 3-Maintenance of Test 244anual Scram.
Entry Sheets for L4:ensee C-Refu: ling 3-Antosnatic Scrain.
Event Report (LER) File (NUREG.
D-Regulatosy Restricilan 4-Other (Explain) 0161)
E-Op:ratos Training & License Examination s
F-Administrative 5
G-Operational E o:IExpl.:ial Exhibit 1-S.une Sousee 19f77)
It Oth: (Explai.O e
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GPU Nuclear Corporation NggIgf Post Office Box 388 Route 9 South Forked River, New Jersey 08731-o388 609 971-4000 Wnter's Direct Dial Number:
Director January 16, 1987 Office of Management Information U.S. Nuclear Regulatory Comission Washington, DC 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 p
Nuclear Generating Station.
t If you should have any questions, please contact Mr. Joseph D. Kowalski, Oyster Creek Licensing Manager at (609)971-4643.
Very truly yours,
- s P e Fedler Vice President and Director Oyster Creek PBF:KB: dam (0841 A)
Enclosures cc: Director (10)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Commission Q
7920 Norfolk Avenue, Phillips Bldg.
Bethesda, MD 20014 NRC Resident Inspector Oyster Creek Nuclear Generating Station GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation L
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