ML20148L197
| ML20148L197 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1987 |
| From: | Baran R, Fiedler P, Notigan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC |
| References | |
| NUDOCS 8801280106 | |
| Download: ML20148L197 (7) | |
Text
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30h'HILY OPERATING REPORT - DECFJiBER 1987 At the beginning of the report period, Oyster Creek was operating at approximately 670 hMe.
Maximum generator load was maintained throughout the report period except for two (2) brief power reductions of approximately 20 FMe to perform turbine valve testing.
1 8801280106 871231
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MONTHLY OPERATING REPORT DECEMBER 1987 The following Licensee Event Reports were submitted during the month of December 1987:
LER 87-047: Reactor Scram Signal While Moving Reactor Mode Switch for Testing On November 15,1987 at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />, a reactor scram signal occurred while moving the reactor mode switch from SHUTDOWN to REFUEL to support testing of the Rod Worth Minimizer system. At the time, the plant was shutdown for maintenance. The scram was reset and operators ensured the plant was in a stable condition.
The apparent cause of the occurrence is equipment malfunction. The mode switch was not completely in REFUEL, causing time delay relays to drop out, which resulted in a scram signal.
The safety significance is minimal, representing only an unnecessary operation of the reactor protection system.
An investigation revealed no defective relays or contacts.
Future replacement of the mode switch will be evaluated.
LER 87-045:
SGTS Initiation Due to Water Accumulation in the A0G System On December 1,1987 at 0933 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.550065e-4 months <br /> a Reactor Building isolation and.itandby Gas Treatment System (SGTS) auto initiation occurred.
At the time the' reactor was operating at full power.
The cause of this event is attributed to Main Condenser offgas pressure oscillations causing offgas flow through a water seal in a drain line.
The drain involved is normally open to allow water accumulated in the offgas line piping to exit to a sump located under the plant vent stack.
Due to pressure oscillations in the offgas system, the offgas line became momentarily pressurized above the static head of the water seal pot.
Hydrogen gas and radioactive gas were released.
The reactor building vent monitor located near the sump alarmed causing the safety system actuation.
Plant Emergency Operating Procedures were entered.
All safety equipment functioned normally.
The safety significance is considered minimal since only a small quantity of offgas was released to the area.
The four (4) inch offgas line causing the pressure oscillations was drained and maintenance is scheduled to verify clear passage of the drain line.
Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - DECEMBER, 1987 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?
Yes Scheduled date(s) for submitting proposed licensing action and supporting infonnation:
March 31, 1988 Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant chaliges 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
=
(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. Nine (9) out of ten (10) racks have been installed to date. When reracking is completed, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.
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OPERATING DATA REPORT OPERATING STATUS 1.
DOCKET: 50-219 2.
REIORTING PERIOD:
12/87 3.
UTILITY CONTACT: DONALD V. NOTIGAN 609-971-4695 4.
LICENSED THERMAL POWER (bMt):
1930 5.
NAMEPLATE RATING (Gross hWe):
687.5 X 0.8 = 550 6;
DESIGN ELECTRICAL RATING (NET FMe):
650 7.
MAXIhtAl DEPENDABLE CAPACITY (GROSS FMe): 650 8.
MAXDihl DEPENDABLE CAPACITY (NET hMe): 620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE 10; POWER LEVEL 10 hBICH RESTRICTED, IF ANY (Net hMe):
- 11. REASON FOR RESTRICTION, IF ANY:
NONE MONTH YEAR CUMULATIVE
- 12. REPORT PERIOD 1RS.
744.0 8760.0 157993.0
- 13. HOURS RX CRITICAL 744,0 5619.9 100456.4
- 14. RX RESERVE SiffDhH HRS.
0.0 0.0 918.2
- 15. HRS. GENERATOR ON-LINE 744.0 5422.9 97792.9
- 16. UT RESERVE SifTDhH 1RS.
O0 0.0 1208.6
- 17. GROSS THERM ENER (hhH) 1431000 9691404 162647789
- 18. GROSS ELEC ENIR (MhB) 497569 3250109 54918354 19; NET ELEC ENER (hhH) 480060 3110919 52720996
- 20. IIT SERVICE FACIOR 100.0 61.9 61.9
- 21. (Jr AVAIL FACFOR 100.0 61.9 62.7
- 24. UT FORCED OUTAGE RATE 0.0 27.3 11.5
- 25. FORCED OUTAGE IRS.
0.0 2034.5 12686.3
- 26. SHUTD0hWS SOED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
27; IF CURRENTLY SIRTfD0hH ESTIMATED STARTUP TIhE: N/A
AVIRAGE DAILY POWER LEVEL NET We DOCKET #....... 50219 UNIT............ 0.C. #1 REPORT DATE...... JANUARY 4, 1988 COMPILED BY...... DONALD V. NOTIGAN.
TELEPHONE........ 609-971-4695 M0.Vni: DECEMBER, 1987 DAY W
DAY MW 1
645 17 646 2
648 18 646 3
646 19 647 0
4 650 20 646 5
645 21 647
-6 645 22 645 L
7 646 23 645 8
644 24 644 9
646 25 645 10 647 26 645 11 645 27 644 12 642 28 645 13 645 29 642 f
l 14 647 30 644 15 645 31 642 1
16 647 i
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Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Diai Number:
Director January 15, 1988 Office of Management Information U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
Subj ect: 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.
If you should have any questions, please contact Mr. Joseph D. Kowalski, Oyster Creek Licensing Manager at (609)971-4643.
Very truly yours, Ai'n=4 Vice President and Director Oyster Creek PBF:KB: dad (0841A)
Enclosures cc: Director (10)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Division of Reactor Projects I/II 7920 Norfolk Avenue, Phillips Bldg.
Bethesda, MD 20014 NRC Resident Inspector I
l Oyster Creek Nuclear Generating Station p
GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corpcration