ML20066G884
| ML20066G884 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/31/1991 |
| From: | Baran R, J. J. Barton, Sedar J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-91-2039, NUDOCS 9102200073 | |
| Download: ML20066G884 (7) | |
Text
O i
g GPU Nuclear Corporation ggg7 Post Office Box 388 z
Route 9 South Forked River, New Jersey 087310388 609 971 4000 Writer's Direct Dial Number:
C321-91-2039 February 12, 1991 U.S. Nuclear Regulatory Concission ATTN Document Control Desk Washington, D.C.
20555 Dear Sir Subject Cyster. 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 t'io '(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 Brenda DeMerchant, oyster.
Creek Licensing Engineer at (609) 971-4642.
Ve t ly yours,
/
a ton D r-tor, Oyster Creek IJB/BDEM: je l'nclosures cc -
Administrator, Region 1 Senior NRC Inspector Oyster Creek NRC Project Manager (MoR)
-l l l 9102200073 910131 PDR ADOCK 05000219 i
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'y Ith ener I Pubhc U'tilities Corporation pf)0tiO8
e MONTHLY OPERATING REPORT - JANUARY 1991 At the beginning of January, Oyster Creek was. operating at full power.
Power was reduced for about 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to problems with emcrgency diesel generators. While #2 emergency diesel generator (EDG) was out of service for repair, #1 EDG failed its daily surveillance test which required declaratien of an " Unusual Event" and commencement of a plant shutdown.
EDG #2 was returned to service ending the " Unusual Event" and the requirement for a plant shutdown. At the end of January, oyster Creek was operating at full power.
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goNTHLY OPTRAT2NG REPORT JANUARY _l 3
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The following Licensee Event Reports were submitted during the month of 4
j January, 19912 1
Two Iso 1 tion Condenser Piro Break Sensors Found Out of Spec Due LER 90-015 4
ip Excessive Driftj]
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During a surveillance test on December 21,;1990'at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />,
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both of the'"B" Isolation condenrer condensate return line pipe-i l
break sensors were found to trip ~at-a differential prewsure_
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greater than the maximum allowable trip setpoint specified in the j
technical specifications.: At the ' time fo? the occurrence the-plant was in the RUN mode at $5% power. The cause of the vent' is excessive component drif t experienced since a 198t e.'leid
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modification ~on the switches, The ' safety significanco -is.
minimal due to the operability. of 'the pipe break sensory =t. st j
slightly higher setpoint.
Immediate corrective action was takan to adjust the switches'to trip;within Technical' Specification j
limits.-.Long term corrective action will be to. replace'these j-sensors as presently committed in the-Integrated Schedule.-
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LER 90-016 hkyence of.an-SRO in the centrol' Room caused bv' Personnel Error
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1990 at 0326 hours0.00377 days <br />0.0906 hours <br />5.390212e-4 weeks <br />1.24043e-4 months <br />, the SRO licensed Group Sh.ft On December 20, Supervisor.(CSS) left the GSS office,after informing the SRO.
I licensed Group Operating Supervisor (GOS).
At 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br /> the GOS l_
lef t the control room without en suring that the GSS had returned l
to the control room..As a result, there was no SRO in the.
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control room for a f6ur minute period, until approximately 0353 hours0.00409 days <br />0.0981 hours <br />5.83664e-4 weeks <br />1.343165e-4 months <br />.
Thic is a.vl31ation of Technical Specification 6.2.2.c
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which requires that an SRO be present in the control, room under the plant conditions which exieted at-the time of the -
occurrence. Corrective actions included tho-immediate return of
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the GOS and-GSS to the control room when it was discovered that i
there was no SRO in the control roomi Plant Operations-l Management counseled the individual involved about the i
occurrence.
l LER 90-017 Both Standby Gas Treatment Systems Declared Inocerable Due to j
Common Duct Failure On December 20, 1990 at approximately 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> a; degradation'in i
ductwork was discovered that' caused both Standby Gas' Treatment'
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Systems to become inoperable. This condition is considered i:
reportable in accordance with 10CFR50.73(a)(2)(v)..
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The duct is constructed of 1/8 inch sheet aluminum'and hasial cross sectional-measurement of 14 inches by 14 inches..Thef x
-degradation consisted of a side panel separating.from the top.and
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bottom corners for a span of approximately three-feet..The cause of the duct failure is still under investigation.
.The, l
degradation-of the duct is a potentially significant condition as i
it could'have affected the operation of both trains of the'SGTS.
Immediate corrective action consisted of declaring both Standby Gas: Treatment Systems inoperable and commencing an orderly 1 shutdown.in accordancelwith Technical Specifications. -concurrent
=with the plant shutdown, temporary repairs:were made to. restore the integrity of.the ductwork.
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AVERAGE DAILY POWER LEVEL NET MWe' I
-DOCKET #...
..... ~....50219.
UNIT.
.:.; OYSTER CREEK #1-REPORT DATE.
.. JANUARY 1, 1991
. JOHN H.-SEDAR COMPILED BY.
TELEPHONE #_.
.......609-971-4698-
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l' MONTH JANtiARY, 1991' t
DM E
DE E'
i 1.
626 16.-
625 2.
626 17.
624 3.
62" 18, 624 4.
62J 19. -
614 5.
625-2t.
'616 F
6.
596 21.
624 s
7.
S55 22.
624-i 8.
625 23.
623 9.
61'7 24.
624 10.
627' 25, 625-11.
627 26.
625-P 12.
625
- 27..
624..
13.
624 28.
625 14.-
626 29.
619-15.
625 30.
'626-
-31.
620
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'l NRC_RPT.WPD/2
OPERhTING' DATA REPORT CPERATING STATUS
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
1/91
- 3. UTILITY CONTACT:
JOHN SEDAR (609)971-4698
- 4. LICENSED THERMAL POWER.(MWt):
19.',0
- 5. NT.MEPLATE RATING (GROSS MWe):
687.5x0.8=550
- 6. DESIGN ELECTRICAL RATING (NET MWe):
650 7.' MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
642
- 8. KAXIMUM Dl?ENDABLE CAPACITY (NET MWe):
.620
- 9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, OIVE REASONS:
NONE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET'139):
NONE
- 11. R:sASON FOR RESTRICTION, IF ANY:
NONE MONTH XEAR CUMULATIVE
- 12. REPORT PERIOD HOURS 744.0 744.0 185040.0
- 13. HOURS RX CRITICAL 744.0 744.0 130809.2
.14. RX RESERVE SHUTDOWN HRS C.0 0.0
?%2
- 15. HRS GENERATOR ON-LINE 744.0 744.0 1166.
s
- 17. GROSS THERM ENERGY (MWH) 1421611 1421611 196316567'
- 18. GROSS ELEC ENERGY (MWH) 480460 480460
'66086383
- 19. NET ELEC ENERGY ( *iviH )
461575 461576 63421607'
"%', TOR 100.0 100.0 63.0 i
- 21. L'T AVAIL FACTOR 100.0 100.0 63.7
55.3
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- 24. UT FORCED OUTAGE RATE 0.0 0.0 11.6
- 25. FORCED OUTAGE HR5 0.0 0.0 15270.0
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
CYCLE 13 REFUELING OUTAGE SCHEDULED TO EEGIN ON FED. 15, 1991, SCHEDULED l
TO END ON MAY 31, 1991.
27.'IF CURRENTLY SHUTDOWN, ESTIMA'9D STARTUP DATE:
i N/A l
NRC_RPT.WPD/7 l
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Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - JANUARY, 1991 f
Name of Facility:
Oyster Creek Station #1 Scheduled date for next refueling shutdowns February 15, 1991 Scheduled date for restart following refuelings.May 31, 1991 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes Technical Specification Change Request 180 was submitted to 'ehe NRC en 5-07-90.
This submittal wac made in accordance with GL 38-16 to incorporate cycle specific parameters in a core operating l'mits report.
.:portant 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 Assemblica P.41 design and performance analysis tethods have been a; roved by the NRC.
I 2.
Exxon Fuel Aesemblies - No major changes have been made nor l
are there any anticipated.
The number of fuel assemblies (a) in the core 560
=
(b) in the spent. fuel storage pool = 1708 (c) in dry storage.
44
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-The preaea, licensed spent fuel pool storage capacity and the size of any increaae 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:
The reracking of the fuel pool is now complete.
All ten (10) racks are no. Installed.
Discharga cr.pacity to the epent fuel pool will be available until 1994 refueling outage.
NRC_RPT.WPD/1 4
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-219-UNIT NAME
_Ovster Creek DATE.
Febmarv, 1991 COMPLETED BY R.
Barart TELEPHONE-971-4640 REPORT MONTH Janno 1991 9
TYPE METHOD 7F SHUTTING Ti Forced DURATION DOWN THE REACTOR OR NO.
' DATE S Scheduled (Hours)
REASON (1)
REDUCING POWER (2)
CORRECTIVE ACTIONS / COMMENTS No unit shutdowns or power reductiens completed during this
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report period.
f dummary :
{1) REASON METHOD a.
Equipment Failure (Explain) a.
Operator Training & License-Er.a 1.
Manual b.
Maintenance or Test f.
Administrative 2.
-. Manual Scram.
c.
Refueling g.
Operational Error (Explain)
- 3.. Automatic Scram d.
Regulatory Restriction h.
Other (Explain) 4..
Other.(Explain) w.
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