ML20205D433
| ML20205D433 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/31/1986 |
| From: | Fiedler P, Notigan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 0170A, 170A, NUDOCS 8608180014 | |
| Download: ML20205D433 (7) | |
Text
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Monthly Operating Report The following Licensee Event Reports were submitted during the month of May 1986:
Licensee Event Report 50-219/86-005 - An inadvertent Core Spray System and Emergency Diesel Generator automatic initiation occurred on April 7,
1986 during a surveillance of reactor low water level scram sensors while the plant was operating at 1650 MWt.
The event occurred when a step in the test procedure was performed requiring valving one of the low level sensors, RE05/19A1, into service after being connected to a test gauge to verify consnunication of the sensor with the reactor.
The test gauge and line were not filled with water and caused a pressure drop in the common sensing line shared by reactor low-low level sensor RE02A when RE05/19Al was valved into service.
The pressure drop caused RE02A to sense lov-low reactor water level and Core Spray System operation was initiated.
After approximately one minute, Core Spray System operation was terminated.
Licensee Event Report 50-219/86-008 - During the performance of local leak rate testing in accordance with 10CFR50 Appendix J, two penetrations were located where one of two redundant valves exceeded the acceptance criteria for leak rate.
Immediate corrective action was taken to tighten the packing on the valves.
Subsequent testing indicated that satisfactory reductions in leak rates had been accomplished.
This is a voluntary report being submitted for informational purposes.
Licensee Event Report 50-219/86-009 - On May 1,1986, a full scram signal was received.
The cause of the scram signal was electronic noise induced spikes on the Intermediate Range Monitors (IRMs) of the nuclear instrumentation.
Prior to this event, the reactor was in the refuel mode with all control rods fully inserted, or at the full out position with the drive unit valved out and control cell unloaded.
A post trip review was performed l
on this event with the following outcome; all plant systems responded as expected for signals received and control room personnel responded properly and in accordance with appropriate procedures.
The cause of the noise spikes on the IRMs is not known at this time.
Noise spikes on the IRMs have been a problem in the past and are more frequent and severe when shutdown with increased maintenance activities.
An investigation which was underway prior I
to this event will continue to identify the sources of the noise problem so l
appropriate corrective action can be taken.
i dam:(0841A)
V B600100014 060531 PDR ADOCK 05000219
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MON'niLY OPERATING REPORT - MAY 1986 Throughout the report riod, Oyster Creek remained in cold shutdown for the Cycle 11 Refueling. intenance/ Modifications Outage.
On May 1 and again on May 13, full scram signals were received due to spurious output signals on IRM channels 11 and 15.
These events were somewhat unusual in that the spikes were of a magnitude higher than recently experienced and are possibly a result of outage work activities in the area of nuclear instrumentation equipment.
Spurious noise spikes affecting electronic circuitry has been a recurring problem with Oyster Creek's nuclear instrtmentation and is currently being evaluated.
On May 29, while moving fuel in the vicinity of the fuel pool gates, several local and remote high radiation alarms actuated.
An investigation concluded that the alarms actuated due to inadequate shielding in the vicinity of the fuel pool gates.
With the reactor cavity drained and only one (1) of six (6) fuel pool shield blocks installed, shleiding was inadequate to prevent " shine" through the fuel pool gates.
Installation of the remaining fuel pool shield blocks was subsequently completed and appropriate precautions and procedural changes identified to prevent recurrence.
0890g
OPERATING DATA REPORT OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTING PERIOD:
- MAY,1986 3.
(TTILITY CONTACT:
DONALD V. NOT]GAN 609-971-4695 4.
LICENSED THERMAL POWER ( W t):
1930 5.
NAMEPLATE RATING (20SS We):
687.5 X 0.8 = 550 6.
DESIGN ELECTRICAL RATING (NET We):
650 7.
MAXIMlM DEPENDABLE CAPACITY (20SS We):
650 8.
MAXIMLN DEPENDABLE CAPACITY (NET We):
620 9.
IF CHANGES OCQJR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE 10.
POWER LEVEL TV WilIO! RESTRICTED, IF ANY (NET We):
N/A 11.
REASON FOR RES1RICTION, IF ANY:
NONE MON 111 YEAR ClMJLATIVE 12.
REPORT PIRIOD IRS 744.0 3623.0 144096.0
- 13. Il00RS RX G ITICAL
- 0. 0 2311.5 94758.9
- 14. RX RESERVE SifrDWN IRS 0.0 448.5 91 8. 2 15.
IPS GENERA 1DR ON-LINE
- 0. 0 2273.9 92333.0 16.
Ifr RESERVE SifrDWN IRS
- 0. 0 452.8 1208.6 17.
GROSS 111ERM ENER (Wil) 0 4074338 152951807
- 18. GROSS ELEC ENER (Wil) 0 1371480 51662165
- 19. NET ELEC ENER (Wil)
-2377 1314776 49623377 20.
(fr SERVICE FACIDR
- 0. 0 62.8 64.1
- 21. (fr AVAIL FAC1DR
- 0. 0 75.3 64.9
- 0. 0 58.5 55.5
- 23. (Tr CAP FACIDR (DER NLT)
- 0. 0 55.8 53.0 24.
(TT FORCED OtfrAGE RATE
- 0. 0
- 6. 3 10.3 25.
FORCED OUTAGE 1RS 0.0 152.3 10587.9
- 26. SlHTDOWNS SQlEDULED OVIR NEXT 6 M0.Vilt3 (TYPE, DATE, DURATION):
REIVELING/ MAINTENANCE OtfrAGE BEGAN 4/12/86 - 6 MONTilS 27.
IF WRRENTLY SiljTDOWN ESTIMATED STARTUP TIME:
10/12/86 1965B
AVERAGE DAILY POWER LEVEL NET We DOCKET #........
50-219 UNIT.......... 0YSTER G EEK #1 REIORT DATE
...... JUNE 4,1986 COMPILED BY,...... DONALD V. NOTIGAN TELEPHDNE #......
609-971-4695 MONTH MAY, 1986 DAY W
DAY W
1.
0 16.
0 2.
0 17.
0 3.
0 18.
0 4.
0 19.
0 5.
0 20.
0 6.
0 21.
0 7.
0 22.
0 8.
0 23.
0 9.
0 24.
0 10.
0 25.
0 11.
0 26.
0 12.
0 27.
0 13.
0 28.
0 14.
0 29.
0 15.
0 30.
0 31.
0 1968B
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Oystsr Cre;k Stcticn #1 Docket No. 50-219 REFUELING INFORMATION - MAY, 1986 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:
Scheduled date for restart following refueling: October 12, 1986 Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?
Yes Scheduled date(s) for submitting proposed licensing action and supporting infonnation:
June, 1986 Important licensing considerations associated with refueling, e.g., new or different fuel desigt or supplier, unreviewed design or perfomance analysis methods, significant changes in fuel design, new operating procedures:
- 1. General Electric Fuel Assemblies - fuel design and perfomance 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.
Tim number of fuel assemblies (a) in the core 0
=
(b) in the spent fuel storage pool = 1824 148 (c) in the dry storage
=
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 Itcensed capacity:
2600
'the projected date of the last refueling that can be discharged to the spent fuel pool assuming tim present licensed capacity:
Reracking of the fuel pool is in progress. Six (6) 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 1990 refueling outage.
1619B
- T8k u..
50-219 DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS Uyster Creek UNIT NAME DATE June 1986 COMPLETED Sy R.
Baran REPORT MONTig May 1986 TELEPHONE 971-4640 o
E
$E "g }I5 Cause & Conredive Licensee Eg No.
Date g
3g
,s&
Event g'g i
Action to ju Prevent Recurrence E
$5 5
jiRg Report
- mu 8
46 4/12/86 S
1197.8 C
1 N/A N/A N/A llR Outage 1
2 3
4 F: Forced Reason:
Method:
Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain)
I-Manual for Preparation of Dasa B-Maintenance of Test 2-Manual Scrain.
Entry Sheets for tiensee C-Refueling 3 Automatic Scram.
Event Repost (LER) File (NUREG-D-Regulatany Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Exandnation F-Administrative 5
G. Operational Error (Explain)
Extiibit I-Same Source (9/77) iIOhcr(Explain)
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GPU Nuclear Corporation Nuclear
- fn:r388 Forked River,New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number:
Director June 13, 1986 Office of Management Information 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 Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
If you should have any questions, please contact the Oyster Creek Licensing Manager at (609) 971-4643.
Very truly yours, Vice President and Director Oyster Creek PDF:ED: dam (0170A)
Enclosures 1
cc: Director (10)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. Thomas E. Murley, Administrator Region I 1
U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Comission 7920 Norfolk Avenue, Phillips Bldg.
Bethesda, MD 20014 O
NRC Resident Inspector 9
Oyster Creek Nuclear Generating Station r
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GPU Nuclear Corporation is a subsubary of the General Public Utilities Corporation
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