ML20141H290
| ML20141H290 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/31/1986 |
| From: | Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8604240284 | |
| Download: ML20141H290 (7) | |
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MNFFLY 0 PIRATING REIORT - JANUARY 1986 a
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i At the beginning of the report period, Oyster Creek was operating at approximately 650 MWe, j
On January 10, a brief power reduction to 590 MWe was required to perform core flux shaping.
On January 14, the Reactor Ibilding 23' elevation automatic sprinkler i
system actuated due to exhaust ftnes from a truck unloading new fuel canisters inside the Reactor Ibilding access airlock.
Following sprinkler system actuation, Core Spray System II was declared inoperable until tests could determine the affects of the water spray.
System II j
was returned to service later that, dwy after test results verified the j
system was unaffected by the event.
The deluge system was valved out on the 23' elevaticn and a fire watch posted until provisicos are provided to route truck exhaust to the Reactor Ibilding Ventilation System.
On January 17, during a routine surveillance test, reactor low level i
sensors RE05/19A1, RE05A1 and RE05/19D1 setpoints were found to be out of I
specification and were subsequently adjusted.
The event required a ene (1) hour notification to the NIC.
On January 20, the surveillance test was repeated.
During testing of i
smsor RE05A1, a half-scram signal received as part of the test did not l
clear.
Reactor shutdown commenced at 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br />.
De event required a j
one (1) hour noti fication to the NR C.
The smsor ms valved out-of-service in order to repeat the surveillance test.
He half-scram
,I signal cleared, but the smsor was not returned to service within the sixty (60) minute time limita tion in accordance with technical speci fications.
Following completion of the surveillance test, the i
sensor was returned to service and reactor shutdown was interrupted until further evaluation could be conducted.
The smsor ms determined to be j
inoperable and reactor shutdown recommenced at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />.
Following
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replacment, the sensor was tested and declared operable at 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> on January 21. Reactor shutdown was terminated with plant load at 500 MWe.
hhile at reduced power, core flux shaping was performed.
On January 22, power was increased to approximately 650 MWe and maintained for the balanm of the report period.
On January 24, Containment Sprav System II was declared inoperable due to insuf ficimt flow indication on FSW pump 52D. The cause was attributed to a mal functioning flow instrtment.
%e system was retested and declared operable on January 25 following flow instrument repairs.
In l
I addit ion,
revised ptop 52D flow accepta nce criteria was provided l
following Fngineering evaluation.
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8604240284 e60131 652E PDR ADOCK 05000219 R
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Monthly Operating Report f
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j The following Licensee Event Reports were submitted during the month of January 1986:
j Licensee Event Report 50-219/85-023 - Separate analyses of the ESW System piping revealed that non-seismic system tie-ins and 2 containment spray heat 1
excnanger relief valve lines could fail during a seismic event.
- Also, I
deficiencies in the ESW piping supports could render the system inoperable j
during a design basis seismic event.
This condition has existed since i
origfaal plant startup, and is attributed to original design error.
ESW Surveillance Test acceptance criteria was raised to a level assuring adequate flow for all required plant conditions.
Licensee Event Report 50-219/85-024 - On 12/15/85 at 0743 hours0.0086 days <br />0.206 hours <br />0.00123 weeks <br />2.827115e-4 months <br />, a reactor j
trip occurred due to a high neutron flux condition.
At 0756 hours0.00875 days <br />0.21 hours <br />0.00125 weeks <br />2.87658e-4 months <br />, all trip signals were reset and the plant was stablized and maintained in a hot standby 1
condition.
The increase in flux was due to the collapse of voids in the core.
A post trip review revealed that Reactor pressure had increased 12 psi due to a failure of the Turbine Generator Electric Pressure Regulator caused i
by a loose wire connection.
Licensee Event Report 50-219/85-025 On 12/16/85 at 2126 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.08943e-4 months <br /> an inadvertent automatic main steam line isolation occt:rred during startup activities.
During startup, a Control Room operator moved the reactor mode, switch from REFUEL to STARTUP and noted the presence'of a refuel control rod 1
withdrawal block.
The operator jiggled the mode switch to ensure he was in STARTUP, but in doing so momentarily picked up a RUN mode contact which initiated a MSIV closure, but reactor scram did not occur because the mode l
switch was in STARTUP before the MSIVs went 10% closed.
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(0841A)
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Oyster Creek Station il Docket No. 50-219 l
REFUELING INFORMATION - January, 1986 i
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 1
l Scheduled date(s) for submitting proposed licensing action and supporting information:
April, 1986 Important licensing considecations associated with refueling, e.g., new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
- 1. General Electric Fuel Assemblies - fuel design and performance 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.
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
=
l The present licensed spent fuel pool storage capacity and the size of any i
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.
Four out of ten (10) racks have been installed to date.
When reracking is completed, discharge j
capacity to the spent fuel pool will be available until 1990 refteling outage.
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16198 1
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OPERATING DATA REPORT I
OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTING PERIOD:
JANUARY, 1986 I
I 3.
UTILITY CONTACT:
DONALD V. NOTICAN 609-971-4695 4.
LICENSED THERMAL POWER (MWt):
1930 i
d 5.
NAMEPLATE RATING (GROSS MWe):
687.5 X 0.8 = 550 i
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DESIGN ELECTRICAL RATING (NET MWe):
650 i
7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
650 8.
MAXIMUM DFPENDABLE CAPACITY (NET MWe):
620 i
l 9.
IF CHANGES OCCUR ABOVE STNCE LAST REPORT, GI,VE REASONS:
NONE 10.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
NONS 11.
REASON FOR RESTRICTION, IF ANY:
NONE MONTH YEAR CUMULATIVE 12.
REPORT PERIOD HRS 744.0 744.0 141217.0 13.
HOURS RX CRITICAL
.744.0 744.0 93191.4 1
14.
RX RESERVE SHTDWN HRS N~s,
- 0. 0 0.0 469.7 I
15.
HRS GENERATOR ON-LINE 744.0 744.0 90803.1 16.
UT RESERVE SHTDWN HRS 0.0 0.0 755.8 17.
GROSS THERM ENER (MWH) 1406000 1406000 150283469 18.
GROSS ELEC ENER (MWH) 478390 478390 50769075 i
19.
NET ELEC ENER (MWH) 460857 460857 48769458 l
I 20.
UT SERVICE FACTOR 100.0 100.0 64.3 l
21.
UT AVAIL FACTOR 100.0 100.0 64.8 22.
UT CAP FACTOR (MDC NET) 99.9 99.9 55.7 23.
UT CAP PACTOR (DER NET) 95.3 95.3 53.1 24.
UT FORCED OUTAGE RATE 0.0 0.0 10.3 I
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FORCED OUTAGE HRS 0.0 0.0 10435.6 26.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
REFUELING, APRIL 12, 1986, 6 MONTHS e
27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:
N/A l
1965B
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AVERAGE DAILY POWER LEVEL NET MWe s
DOCKET 4.
.50-219 UNIT.
. OYSTER CEEEK #1 REPORT DATE.
. FEBRUARY 4, 1986 COMPILED BY.
. DONALD V. NOTIGAN TELEPHONE t.
.609-971-4695 MONTH JANUARY, 1986 C
624 16.
624 2.
624 17.
o22 3.
624 18, 622 4.
627 19.
624 5.
625 20.
596 6.
622 21.
546 7.
623 22.
613 8.
626 23.
623 9.
624 24 620 10.
619 25.
623 11.
607 26.
626 12.
625 27.
624 13.
623 28.
625 14.
625 29.
623 15.
625 30.
624 31.
624 1968B
50-219 I
KFT NO.
UNITSilUTDOWNS AND FOWER REDUCTIONS Feb. 4, 1986 DATE COMPLETED BY R. Ibran REPORT MON nt January, 1986 TELEPilONE 971-4640 "Lo c
5g "g
Y3 Licensee Eg cg Cause & CorreclNe 3g5 Event g3 Action to No.
Date
{
~g e-gI j;2g Report
- mo u
p, event Recurrence g
N/A 1-20-86 N/A N/A A
N/A N/A N/A N/A January 20 - Ommenced a shutdown frtri a plant load of 650 Mt due to failun :
of reactor low water level sensor REO Al.
Sensor was repla d and tested satis-factorily. The shutdown was terminated at a plant load of 500 Me (23% load reduction). Increased load back to 6f 0 M b by January 22.
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F: Forced Reasen:
Method:
Exhibit G-Instructions S: Scheduled A-Equiprnent Failure (Explain)
I-Manual for Preparation of Da:a B-Maintenance of Test 2 Manual Scram.
Entry Sheets for 1.icensee C Refueling 3 Ausomatic Scram.
Event Report (LER) File INUREG-D-Regulatory Restriction 4 Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
Goperational Error (Explain)
Exhibit I-Same Source 19/77)
Ilother(Explain)
3 p
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Route 9 South Forked River, New Jersey 08731-o388 609 971-4000 Writer's Direct D6al Numtier:
February 14, 1986 Office of Management Information U.S. Nuclear Regulatory Conmission 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) cooles of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
i If you should have any questions, please contact Mr. Drew Holland at (609) 971-4643.
/
Y t(0lyy s
et e B Fiedler Vic esident and Director te Creek PBF:KB: dam (0170A)
Enclosures cc: Director (10)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.
Bethesda, MD 20014 NRC Resident Inspector
$>N Oyster Creek Nuclear Generating Station i
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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation l