ML20034A849
| ML20034A849 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/31/1990 |
| From: | Baran R, Fitzpatrick E, Yeager J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9004240431 | |
| Download: ML20034A849 (7) | |
Text
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ENuolear
?== r-Route 9 South Forked River.New.lersey 08731-0388 -
l 609 971 4000 Writer's Direct Dial Number:
April 16,1990
. U.S. Nuclear Regulatory Commission l
ATTN Document Control Desk Washington, D.C.
20555 j
r Dear Sirs i
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly operating Report
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In accordance with the Oyster Creek Nnclear Generating Station operating I.icense 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.
l If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing at (609) 971-4642.
i f-Very truly yours, ee ytrickrf E. E. Fitz Vice President and Director
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Oyster Creek EEF KFBadmd (MOR)
Enclosures i
ces Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Avenue King of Prussia, PA 19406 l
Mr. Alexander W. Dromerick, Project Manager i
U.S. Nuclear Regulatory Commission Washington, DC 20555 l
t NRC Resident Inspector Oyster Creek Nuclear Generating Station 9004240431 900331 PDR ADOCK 05000219 R
.GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation
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s MONTHLY OPERATING REPORT - MARCH 1990 t
l At the beginning of the report period, Oyster Creek was operating at a gross generator load of 656 MWe.
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Commencing on March 9, the plant began experiencing condenser vacuum abnormalities.
In accordance with procedure, plant load was reduced to approximately 50% to stabilise vacuum and to determine potential causes. An I
outage plan was developed and plant shutdown commenced on March 26 to effect j
repairs. The plant remained out of service for the remainder of the report j
period.
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MONTHLY OPERATING REPORT MARCH, 1990 The following Licensee Event Report was submitted during the month of March, 1990:
LER 90-04 MANUAL RX SCRAM INITIATED DUE TO SPURIOUS ACTUATION OF ALTERNATE ROD INJECTION SYSTEM RESULTING FROM PERSONNEL ERROR IN OPERATING HAND-HELD RADIOS IN RESTRICTED AREA On February 20, 1990, while performing a surveillance on a reactor vessel level instrument, an Instrument & Controls (I&C) technician keyed a hand-held radio near the analog trip units for the Alternate Rod Injection (ARI) System causing the system to actuate due to radio frequency interference (RFI).
Control room operators noted that air operated valves supplied from the Scram Air System were repositioning and that control rods were drifting into the core. The operators initiated a manual reactor scram as required by procedure due to the drifting control rods. The cause of this occurrence has been attributed to personnel error by the technician performing the surveillance procedure. The access door to the area where the ARI System components are located is well marked with reference to the restriction on the use of radios in the area.
This event is determined to have minimal safety significance because a manual scram was initiated by the operators within 5 seconds of rod movement.
Chemistry samples indicate that no fuel damage resulted from this event. The use of radios by I&c technicians must now be approved by the technician's supervisor. Appropriate site personnel will receive training on this event and an investigation will be conducted into minimizing the ARI System's sensitivity to RFI.
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CPERATING DATA REPORT g
OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTING PERIOD:
03/90 3.
UTILITY CONTACT: JEFF YEAGER 609-971-4585 4.
LICENSED THERMAL POWER (MWt):
1930 5.
NAMEPLATE RATING (GROSS MWe):
687.5 X 0.8 = 550 6.
DESIGN ELECTRICAL RATING (NET MWe):
650 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
642 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): March 9 to March 27 limited to 325 MWe Net 11.
REASON FOR RESTRICTION, IF ANY: Condenser Vacuum Abnormalities 140 NTH XEAR CUMULATIVE 12.
REPORT PERIOD HRS 744.0 2160.0 177696.0 13.
HOURS RX CRITICAL 628.8 1780.7 113041.3 14.
RX RESERVE CHTDWN HRS 0.0 0.0 918.2 15.
HRS GENERATOR ON-LINE 623.6 1730.2 109962.0 16.
UT RESERVE SHTDWN HRS 0.0 0.0 1208.6 17.
GROSS THERM ENER (MWH) 841300 2839100 184112159 18.
GROSS ELEC ENER (MWH) 266800 936390 62059130 19.
NET ELEC ENER (MWH) 254407 897119 59552097 20.
UT SERVICE FACTOR 83.8 80.1 61.9 l
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UT AVAIL FACTOR 83.8 80.1 62.6 22.
UT CAP FACTOR (MDC NET) 55.2 67.0 54.1 23.
UT CAP FACTOR (DER NET) 52.6 63.9 51.6 24.
UT FORCED OUTAGE RATE 0.0 2.8 11.6 25.
FORCED OUTAGE HRS 0.0 49.1 14459.2 26.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NONE l
27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: April 3, 1990 l
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1 1619B/20 l
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-f AVERAGE DAILY. POWER LEVEL-
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MET MWe t
l DOCKET #........
50219 l
UNIT.
. OYSTER CREEK #1
. APRIL 3, 1990
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REPORT.DATE.
COMPILED BY.
.JEFF YEAGER i
TELEPHONE #.-......609-971-4585 b
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HONTH MARCH, 1990 i
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tDi M-191 1.
634 17.
304 2.
633 18.
306 j
3.
635 19.
248 4.
635 20.
292-5.
634 21.
307.
6.
635 22.
304 7.
634 23.
303 f
8.
633
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305 9.
582 25.
-307-10.
358 2 6. -
292 t
11.
238
-27.
0-1 12. -
256 28.
0 i
13.
258-29.
O 14.
276
- 30..
O i
.l 15.
314 31.
0 i
16.
306-
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.i 1619B/19 3
4 OyctOr Creek St;tiCn #1 Docket No. 50-219 REFUELING INFORMATION - MARCH, 1990 Name of Facility:
Oyster Creek Station #1 Scheduled date for next refueling shutdown: January 11, 1991 pending necessary state approval.
Scheduled date for restart following refueling: May 19, 1991 Will refueling or resumption of operation t\\ereafter require a Technical Specification change or other license amendment?
Yes Scheduled date(s) for submitting proposed licensing action and supporting information:
July 15, 1990 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.
The number of fuel assemblies (a) in the core 560
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(b) in the spent fuel storage pool 1595
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(c) in dry storage 37
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The present licensed spent fuel pool storage capacity and the size of any increaso 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.
1619B/18
s UNIT SEUTDOWPS AND POWER REDUCTIONS 3
DOCRET NO.
50-219 UNIT NABE Ovster Creek DATE April. 1990 COIN'LETED BY R. Baran TEI2PEONE 971-4640 REPORT NONTE NARCE 1990 TYPE BETHOD OF SEUTTING F: Forced DURATIOpi DOWN TER REACTOR OR NO.
DATE 8: Scheduled (Bours)
REASON (1)
REDUCING POWER (2)
(XMtRBCTIVE ACTIONS /rvinamnerg 97 3/9 F
410.4 A
1 Load reduction to 57% Rx Power due to vacuum problems 12-U-J Staintemence Outage 98 3/26 8
120.4 B
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SUOWEARY:
(1) R5ASON (2) IETBOD A.
Equipment Failure (Explain)
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Operator Training & License Exam 1.
Desanal B..
Maintenance or Test F.
Administrative 2.
Mammal Scram i
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Refueling G.
Operational Error (Explain)-
3.
Autonnatic Scram
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Regulatory Restriction E.
Other (Explain) 4.
Other (Explain)
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