ML20197D343
| ML20197D343 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/28/1986 |
| From: | Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 0841A, 841A, NUDOCS 8605140238 | |
| Download: ML20197D343 (7) | |
Text
.
MONTHLY 0 PIRATING REIORT - FEBRUARY 1986 At the beginning of the report period, Oyster Creek was operating at approximately 650 FMe.
On February 2, Standby Gas Treatment System (SGTS) I was declared inoperable after routine testing identified a failed inlet tempera ture transmitter which prevented system heaters from energizing.
B11owing repairs, the system was retested and i
declared operable on February 4.
& February 4, the reactor Cleanup System was rmoved from service to facilitate sealant injection retnirs to valves V-16-22C and V-16-233.
Power was reduced to 602 FWe prior to returning the Cleanup System to service to minimize the effects of a flux increase due to cold water addition.
The Cleanup System was returned to service later that day and power was subsequently increased to approximately 650 hMe.
Permanent repairs are planned for the next refueling outage.
On February 4, Core Spray System II was removed from service to repair two minor piping leaks.
As a target of opportunity, associated booster pump breaker undervoltage devices were inspected.
Following completion of repairs and inspections, the system was retested and declared operable on February 5.
On February 6, Trunnion Room temperature increased due to failure of recirculation fan RF 1-6.
RF 1-7 was placed in service and temperatures returned to normal.
l Inspection of RF 1-6 revealed a defective drive belt.
Power was decreased to approximtely 495 hMe to reduce radiation exposure during belt replacment. RF 1-6 was returned to service and RF 1-7 secured.
RF 1-7 is only used as backup, due to
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its degraded condition, and is scheduled for repair during the next refueling cuta ge. Plant load was returned to 650 hMe cn February 7.
m February 11, all power rods were essentially withdrawn and end of fuel cycle
'toastdown" began.
On February 20, during a rcutine surveillance test, reactor low level sensors RID 5A1 and RE05B1 setpoints were found to be out of specification.
The sensors were subsequently adjusted and the test completed satisfactorily.
He evmt required a one (1) hour notification to the NIC.
On February 21, a high conductivity alarm for "A"
North condenser annunciated accompanied by increasing conductivity indication.
"A" North section of the condenser was rmoved from service following a load reduction to approximately 475 hMe.
A leaking tthe (1) was identified on February 22 and plugged.
The condenser was returned to service and load increased to 560 AMe later that day. Maximum plant load was achieved on February 23.
Power stabilized at 612 MWe on February 25 after establishing Xenon equilibrium.
On February 27, reactor low level sensor RID 5A1 failed surveillance testing and was determined to be inoperable. This action required entering a technical specification "IID" action sta tement and necessary notifications were made.
He sensor was stbsequently replaced, calibrated, tested satisfactorily and returned to operable status the same day.
Plant load at the md of the report period was 602 MWe.
N se2 R
h
Monthly Opzrating Repsrt The following Licensee Event Reports were submitted during the month of February 1986:
i Licensee Event Report 50-219/85-026 - On December 18, 1985 a recirculation 4
pump tripped and its discharge valve could not be immediately closed.
Reverse i
flow occurred in the idle loop and was electronically added to the flow in the i
other four recirculation loops.
This resulted in the flow biased Average Power Range Monitor ( APRM) setpoints for the scram and rod block functions to be less conservative than those allowed by Technical Specifications.
Licensee Event Report 50-219/86-001 - On January 17, 1986, three out of four reactor low level scram sensors were found out of specification during 4
the monthly surveillance.
Upon discovery, the setpoints were immediately adjusted within acceptable ranges.
On January 20, two of the sensors were i
retested and both were found in specification, but one failed to reset when valved back into service.
The switch was determined to have failed and was replaced.
During the additional testing of the failed sensor, its monthly i
out-of-service limit of 60 minutes was exceeded, and a shutdown was comenced. The shutdown was terminated at 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> on January 21 when a new sensor was placed in service. The cause of the occurrence has been attributed to instrument drift, and the cause of the sensor failure is being investigated at the vendor's facilities.
Licensee Event Report 50-219/86-002 - On January 24, 1986 at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, a l
Safety Related Hydraulic Snubber (NQ-2-S7) was disconnected from the i
Containment Spray piping rendering this snubber inoperable.
This action placed the plant in the Limiting Condition for Operation (LCO).
The snubber j
was disconnected during execution of a Short Form generated to exchange the i
front paddle on the snubber.
The snubber was then reconnected to the pipe, making it operable.
The removed paddle was used to repair a feedwater snubber.
The cause of the event is attributed to personnel error when the Group Shift Supervisor (GSS) approved a maintenance short form which approved maintenance reordering a safety related snubber inoperable.
i
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(0841A)
OPERATING DATA REPORT t
OPERATING STATUS 1.
DOCKET:
50-219
~
2.
REPORTING PERIOD:
FEBRUARY, 1986 3.
UTILITY CONTACT:
JOSEPH R. MOLNAR 609-971-4699 4.
LICENSED THERMAL POWER (MWt):
1930 5.
NAMEPLATE RATING (GROSS MWe):
687.5 X 0.8 = 550 6.
DESIGN ELECTRICAL RATING (NET MWe):
650 i
7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
650 8.
MAXIMUM DEPENDABLE CAPACITY (NET MWe):
620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE 10.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
COASTDOWN -
2 APPROXIMATELY 2 NET MWe PER DAY 11.
REASON FOR RESTRICTION, IF ANY:
NONE MONTH YEAR CUMULATIVE 12.
REPORT PERIOD HRS 672.0 1416.0 141889.0 13.
HOURS RX CRITICAL 672.0 1416.0 93863.4 I
14.
RX RESERVE SHTDWN HRS 0.0 0.0 469.7 15.
HRS GENERATOR ON-LINE 672.0 1416.0 91475.1 1
16.
UT RESERVE SHTDWN HRS 0.0 0.0 755.8 4
17.
CROSS THERM ENER (MWH) 1242000 2648000 151525469 i
j 18.
GROSS ELEC ENER (MWH) 420780 899170
- 51189855 19.
NET ELEC ENER (MWH) 405019 865876 49174477 j
20.
UT SERVICE FACTOR 100.0 100.0 64.5 i
21.
UT AVAIL FACTOR 100.0 100.0 65.0 22.
UT CAP FACTOR (MDC NET) 97.2 98.6 55.9 l
23.
UT CAP FACTOR (DER NET) 92.7 94.1 53.3 24.
UT FORCED OUTAGE RATE 0.0 0.0 10.2 25.
FORCED OUTAGE HRS 0.0 0.0 10435.6 26.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
I REFUELING, APRIL 12, 1986, 6 MONTHS 27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:
N/A 1
19658 4
1 r,
r-
,-,n.,.,m
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r--,~.
AVERAGE DAILY POWER LEVEL i
NET MWe DOCKET t...
.50-219 UNIT.
. OYSTER CREEK #1 REPORT DATE.
. MARCH 4, 1936 v
i COMPILED BY,
. ANTHONY V. SAVINO TELEPHONE i
.609-971-4456 i
]
MONTH FEBRUARY, 1986 1
1.
625 16.
607 2.
624 17.
603 4
3.
624 18.
602
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4.
621 19.
599 j
5.
624 20.
597 6.
608 21.
575-f 7.
624 22.
485 8.
625 23.
591 l
9.
620 24.
595 10.
620 25.
587 11.
619 26.
-586 12.
616 27.
584 13.
613 28.
583 14.
611 15, 609
'I 1
.I i
1 I
i 1968B i
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Oyster Creek Station il Docket No. 50-219 REFUELING INFORMATION - February, 1986 Name of Facility: Oyster Creek Station il Scheduled date for next refueling shutdown: April 12, 1986 Scheduled date for restart following refueling: October 12, 1986 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:
April, 1986 Important licensing considerations associated with refueling, e.g., new or different f uel design or supplier, unreviewed design or performance analysis methods, significant changes in f uel design, new operating procedures:
- 1. General Electric Fuel Assemblies - fuel design and performance analysis methods have been approved by the NRC.
New operating p r oc edu res, if necessary, will be submitted at a later date.
- 2. Exxon Fuel Assemblies - no major changes have been made n(r'are there any anticipated.
560 The number of fuel assemblies (a) in the core
=
(b) in the spent fuel storage pool = 1204 148 (c) in the dry storage
=
60 (d) in temporary 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 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 installed to date. When reracking is completed, discharge capacity to the spent fuel pool will be available until 1990 refueling outage.
1619B
e P.
00CKETNO.
50-219 11 NIT SirIJTDOWNS AND POWErt REDUCTIONS UN!TNAME Oyster Creek DATE March 1986 OMPt.ETED By R han REPORT MONT11 Pohnnyv 1986 TEl.EPfl0NE 971-4640 I
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C2v.:1"ctreciive Licensee 3
3 i at Event 3,3 No.
Date
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Ar6 :o F
j_
E jijjg Report #
ui U n
8 N/A N/A N/A A
N/A N/A N/A N/A Feb. 21: Beduced plant load frcm 620 me to 473 Mie (23.7%
load reduction) to repair a tube leak in "A" North condenser.
li 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Emplain) 1-Manual for I'veparation of Data B..'.!;: int: nance of Test 2-Manual Scram.
Entry Sh:ets for Licensee 0-Refu: ling 3 AutunaticScram.
Event R: port (LER) File (NUREG.
D-Regulatory Restriction 4 Ot!':, (Explain) 016!)
E. Operator Training & License Examination G4perational Ermr (Explain) 5 F-Aarninistrative (9/77)
Il-Oth:r (Explala)
Exr.ibii ! - S2::.e F. v. ire -
.O GPU Nuclear Corporation Nuclear
- g== 388 Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
March 11, 1986 Director 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 Aprt 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. George Busch at (609) 971-4643.
Very truly yours, A.A/
ya r
s P
riedler Vice President and Director Oyster Creek PBF:KB: dam (0170A)
Enclosures cc: Director (10) i Office of Inspection and Enforce;aent U.S. Nuclear Regulatory Comission Washington, DC 20555 Dr. Thomas E. Murley, Administrator Region I 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
[
NRC Resident Inspector r {
Oyster Creek Nuclear Generating Station k
GPU Nuclear Corporation is a subsidiary of the General Pubhc Utikties Corporation