ML20236W090
| ML20236W090 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/31/1987 |
| From: | Fiedler P, Sedar J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC |
| References | |
| NUDOCS 8712070269 | |
| Download: ML20236W090 (8) | |
Text
.
OPERATING DATA REPORT OPERATING STATUS 1.
DOCKET:
50-219'
.2.
REPORTING PERIOD: OCTOBER, 1987 3.
UTILITY CONTACT:
JOHN H. SEDAR, JR.
609-971-4698 4..
LICENSED THERMAL POWER (MWt):
1930 5.
NAMEPLATE RATING (GROSS We):
687.5 X 0.8 = 550 6.-
DESIGN ELECTRICAL RATING (NET We):
650 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS We):
650 8.
MAXIMUM DEPENDABLE CAPACITY (NET We):
620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET We):
0 11.
REASON FOR RESTRICTION, IF ANY: NRC IMPOSED SHUTDOWN MONTH YEAR CUMULATIVE-
- 12. REPORT PERIOD HRS 745.0 7296.0 156529.0
- 13. HOURS RX CRITICAL 0.0 4668.3 99504.8 14.
RX RESERVE SHTDWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 0.0 4516.5 96886.5
- 16. [TT RESERVE SHTDWN HRS 0.0 0.0 1208.6
- 17. GROSS W ERM ENER (MWH) 0 7962604 160918989
- 18. GROSS ELEC ENER (MWH) 0 2654600 54322845 19.
NET ELEC ENER (WH)
-2466 2539579 52149656
- 20. (If SERVICE FACTOR 0.0 61.9 61.9 21.
[TT AVAIL FACTOR 0.0 61.9 62.7
- 24. [TT FORCED OUTAGE RATE 0.0 31.1 11.6 25.
FORCED OlTTAGE HRS 0.0 2034.5 12686.3
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
. /Q\\
27 IF CURRENTLY SHUTDOWN ESTDRTED STARTUP TIME:
N/A
/
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9 1965B
L Oyster' Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - OCTOBER,1987 Naine 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 information:
i March 31, 1988 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:
fuel design and performance
- 1. General ' Electric Fuel Assemblies analysis methods have been approved by the NRC.
- 2. Exxon Fuel Assemblies - no major changes have been made nor are there any anticipated.
l 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.
l 1619B
AVERAGE DAILY POWER LEVEL NET MWe DOCKET #........
50-219 UNIT.......... 0YSTER CREEK #1 REPORT DATE....... NOVEMBER 02, 1987 COMPILED BY....... JOHN H. SEDAR, JR.
TELEPHONE #......
609-971-4698 MONTH OCTOBER, 1987 DAY MW DAY MW 1.
0 16.
O e 2.
0 17.
0 3.
0 18.
0 4.
0 19.
0 5.
0 20.
0 6.
0 21.
0 l
l 7.
0 22.
0 8.
0 23.
0 9.
0 24.
0 10.
0 25.
0 l
11.
0 26.
0 12.
0 27.
0 13.
0 28.
0 14.
0 29.
0 15.
0 30.
0 31.
0 1968B
MONTHLY OPERATIE3 REPORT OCTOBER 1987 The following Licensee Event Reports were submitted during the month of October 1987:
LER 87-033 " Safety Limit Violation Caused by Personnel Error While Removing Reactor Recirculation Pumps from Service" i
On Septembar 11,1987, at 0217 hours0.00251 days <br />0.0603 hours <br />3.587963e-4 weeks <br />8.25685e-5 months <br /> a Technical Specification Safety Limit l
requiring at least two recirculation loops to be fully open was violated.
The safety limit was violated while removing reactor recirculation pumps from service in response to a leak from the reactor building closed cooling water system which occurred during maintenance activities.
The plant was shut down with reactor coolant temperature approximately 140*F. The cause of the event was personnel error.
Upon violation of the safety limit, immediate corrective dctions were taked to open other recirculation loops to restore the plant to l
an allowable configuration.
Analysis of the data related to the event indicates that there was minimal reduction in recirculation loop flow area due to intnediate operator responses, thus providing adequate communication between i
the core area and vessel annulus for vessel level instrumentation.
Therefore the event posed no danger to the health and safety of the public, and did not create the potential for core damage to occur. Corrective actions include procedure revisions, additional training for operators, and evaluation of a possible technical specification change request.
LER 87-034 " Inadequate Emergency Lighting Due to Design Deficiency" On September 16, 1987, during a design review of the emergency lighting system, it was discovered that emergercy lighting in the A/B Battery Rosyn and a portion of the access route thereto was inadequate due to a design deficiency.
The existing lighting is inadequate to perform manual actions which are required in the event of a fire in the 'A' 480 volt switchgear room (fire zone 08-FZ-6A).
The safety significance of this condition is minimal since a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> is available to perform this action utilizing readily available portable lighting units.
Modifications to provide the required lighting capability have been completed.
LER 87-035 " Reactor Scram With Reactor Shutdown Due to Degraded Electrical Cable" On September 24,1987 at 1:10 PM with the reactor shutdown a reactor full scram signal occurred.
At the time an instrument surveillance was in progress in the Control Room that causes half scrams during the course of its performance. Coincident with a half scram from the surveillance, an instrument technician opened an instrument drawer in the Control Room on the L __ _ _ _-____ _______-_ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ ___ ___ _ - ____-_ - -_-________-___-____-__- - _-_ _
f
' Licensee Event-Reports Octob2r 1987 Page 2 L
f l
Nuclear -Instrumentation (unrelated to the surveillance) to-replace a calibration sticker. A full scram occurred.
The half scram from the Nuclear 4
Instrumentation is attributed to a poor electrical ground caused by a degraded connection at a remote cable connector joint. The degraded ground caused a spurious spike in an Intermediate Range Monitor (IRM) when its drawer was moved.
All equipment responses and indications were normal during and
-following the scram signal.
The safety significance of this event is considered minimal.
The cause of the degraded connection appears to be due to normal wear and tear'from routine testing aggravated by the short length of the cable attached to the connector.
The connection will be repaired and the cable lengthened to reduce stress at the connection.. Other IRM cables will be l
inspected for similar conditions and repaired as necessary.
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GPU Nuclear Corporation
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Post Othee Box 388 Route 9 South Forked River,New Jersey 08731-0388 609 971-4000 Writers Direct Dial Number:
Director Office of Management Information November 13, 1987 U.S. Nuclear. Regulatory Commission 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 Opgrating 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, N
n -
Pete ied1'er Vice President and Director Oyster Creek PBF:KB:dmd(0841 A)
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 Comission 631 Park Avenue g
3,
~
King of Prussia, PA 19406 g
q l
Mr. Alexander W. Dromerick, Project Manager 7
9@ h U.S. Nuclear Regulatory Comission f
j Division of Reactor Projects I/II l
7920 Norfolk Avenue, Phillips Bldg.
A Bethesda, MD 20014
,8 s's NRC Resident Inspector Oyster Creek Nuclear Generating Station i
GPU Nuclear Corporation is a subsid.ary of the General Pubhc Utihties Corporation
NONDfLY OPBUtTING REPORT - OCTOBER 1987 l
1 i
Throughout the report period, Oyster Creek remained shutdown for the l
11-U-6 Maintenance Outage.
The shutdown, which commenced on September 9, to repair a main flash tank manway leak, was extended due to a Safety Limit Violation which occurred on September 11 while attempting to secure the recirculation. pumps in response to Icakage from a Reactor Building Closed Cooling Water drywell isolation valve.
Approval for restart requested from the NRC was pending at the end of the report period.
j
-.__- - A