ML20077H665
| ML20077H665 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/15/1983 |
| From: | Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8308110193 | |
| Download: ML20077H665 (6) | |
Text
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4 MONTHLY OPERATIONS REPORT June 1983 Throughout the report period, the Oyster Creek Station remained shutdown for the 1983 Refueling / Maintenance Outage.
Both outboard MSIV's (NSO4A/NSO4B) failed their leak rate test. Bo th I,
MSIV's are being scheduled for rebuilding during the current outage.
Inspection of the Reactor Recirculation System valves was started during the report period with the Reactor Vessel drained. Inspection results at the end of the period revealed cracks in the backseats of "B" loop suction valve and "D" and "E" loop discharge valves. The Technical Functions Division is evaluating the results.
Two Unusual Events occurred during the report period.
On June 6, 1983, an Unusual Event was declared at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> as a result of a chlorine leak in the plant's Chlorination System. The leak was isolated within eleven minutes, and the Unusual Event was terminated following the satisfactory accountability of site personnel. One (1) individual was af fected and transferred to a local hospital for trestment. The individual was hospitalized overnight for observatf er..
The second Unusual Event occurred on June 7,1983. This event involved a potentially contaminated injured person who was struck by a falling bag of insulation material while climbing the ladder in the Drywell. The Unusual Event was terminated approximately an hour and half later when it was i
verified the injured person was not contaminated.
l On June 7 and June 11 the plant experienced a trip of Emergency Bus "C".
j The first trip was due to personnel error. The trip on-June 11 was caused by a i
disconnected undervoltage trip wire while racking in the "lC" breaker. Due to-the rough condition of the 4160 Volt switchgear room floor, racking in the heavy 4160 Volt breakers cannot be done smoothly. On June 29, the plant experienced a trip of Emergency Bus "D" for the same reasons as the trip of "C" Bus on June 11.
A repair of the 4160 Volt switchgear room floor is being evaluated.
f The following outage events were considered noteworthy:
i (1) Maintenance and inspection of Bank 5 and 6 (34.5 KV) was completed.
Bank 6 was returned to service July 1.
(2) The bearings were replaced on Standby Gas Treatment System Fan EF-1-9.
(3) The Appendix "J" modifications were started on the Cleanup System,
'Feedwater. System and the CRD System.
(4) Replacement of Shutdown Cooling System motor-operated valves started at the end of the report period.
(5) Transfer of Control Room alarms to the temporary alarm panel began 1
during the report period.
There 'were no Licensee Event Reports submitted during June 1983.
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50-219 UNIT SilUTDOWNS AND POWER REDUC 110NS DOCKETNO.
UNIT NAA4E vyst.er creek DATE 7-5-83 REPORT HONTil June, 1983 COMPLETED 3Y R.
Baran TELEPil0NE 4640
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Cause & Corrective
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Y Licensee
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Date g
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Event u1 j0" Action to
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- Eu Prevent Recussence 8
31 2-11-83 S
3336 C
1 NA ZZ ZZZZZZ Start of 1983 Refueling Maintenance Outage.
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2-3 4he F: Fosced Reason:-
Method:
S Exhibit G.Instructfuns 3
S: Scheduled
- A Equipnwns Failuse(Explain) 1 Manual 3.For Preparation of Data B-Maintenance of Test 24fanual Scram.
Entry Sheets for Licensee 2
C-Refueling.
- 3. Automatic Scrant.
! Event Report (LER)Fde(NUREG.
D Regulatory Restriction 4 Other(Explain)
J 0161)
E4perator Training & Ucense Exandnation F. Administrative 5~
GOperational Earor (Explain)
Exhibit I-Same Souece (9/77)
II4ther(Explain) m 4
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OPERATING DATA REPORT OPERATING STATUS 1.
DOCKET:
50-219 2.
UTILITY CONTACT:
Joseph R. Molnar 609-971-4699
- 3. _
REPORTING PERIOD:
JUNE, 1983 4.
LICENSED ' THERMAL POWER (MWt):
1930 5.
NAMEPLATE RATING (GROSS MWe):
687.5
- 0.8 = 550 6.
DESIGN ELECTRICAL RATING (NET MUe):
650 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 650 8.
MAXIMUM DEPENDABLE CAPACITY (NET MWe):
620 9.
IF CRANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS: NONE 10.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
N/A 11.
REASON FOR RESTRICTION, IF ANY:
N/A MONTH YEAR CUMULATIVE 12.
REPORT PERIOD HRS 720 4,343.0 118,511.0 13.
HOURS RX CRITICAL 0
1,009.6 84,622.8 14.
RX RESERVE SHUTDOWN HOURS 0
0.0 468.2 15.
HRb GENERATOR ON-LINE O
1,007.8 82,693.5 16.
UT RESERVE SHUTDOWN HOURS 0
0.0 0.0 17.
GROSS THERMAL ENER (MWH) 0 853,300.0 136,224,730.5 18.
GROSS ELEC ENER (MWH) 0 244,630.0 46,056,905.0 19.
NET ELEC ENER (MWH)
-1,847 215,435.0 44,295,963.0 20.
UT SERVICE FACTOR 0
23.2 69.8 21.
UT AVAIL FACTOR 0
23.2 69.8 22.
UT CAP FACTOR (MDC NET) 0 8.0 60.3 23.
Irr CAP FACTOR (DER NET) 0 7.6 57.5 24.
UT FORCED OUTAGE RATE O
0.0 9.7 25.
FORCED OUTAGE HOURS 0
0.0 8,916.8 26.
SHUTDOWNS SCHEDULED OVER NEXT'6 MONTHS (TYPE,'DATE,-DURATION):
N/A 27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:
1/12/84 i
1
i AVERAGE DAILY POWER LEVEL NET MWe DOCKET #...............
50219 UNIT.
0.C. #1
. JULY 2, 1983 REPORT DATE...
COMPILED BY..
. ROBERT J. FRICK TELEPHONE....
. 609-971-4699 MONTH: JUNE, 1983 DAY MW DAY MW 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
'O 11 0
26 0
12 0
27 0
13 0
28 0
14 0
29 0
15 0
30 0
Oyster Cresk Statien #1
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Dncket No. 50-219 MAY 1983 REFUELING INFORMATIO Name of Facility:
Oyster Creek Station #1 Scheduled date for next refueling shutdown: Presently shutdown for Refueling
' Scheduled date for restart following refueling: January 12, 1984 refueling or resumption of operation thereaf ter require a Technical Will Specification change or other license amendment?
Technical Specification Change Request No. 96 was submitted on August 31, 1982 for incorporation of GE fuel assemb3 des into the Cycle 10 core.
Scheduled date(s) for submitting proposed licensing action and supporting in fo rma tion:
September 1983 - The final supplement to the reload analysis, delineating the specific core configuration for Cycle 10 operation, will be submitted.
licensing considerations associated with refueling, e.g., new or Important fuel design or supplier, unreviewed design or performance analysis different methods, significant changes in fuel design, new operating procedures:
i 1.
General Electric fuel assemblies - fuel design and performance analysis
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methods have been approved by the NRC. New operating procedures, if necessary, will be s'ubmitted at a later date.
2.
Exxon Fuel Assemblies - No major c'hanges have been made nor are there any anticipated.
The number of fuel assemblies (a) in the core 0
(b) in the spent fuel storage pool -
1341
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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: 1,800 Planned: 2,600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
De Spring 1987 Outage.*
- NOTE: This is for a normal refueling. Full core off-load, however, can only, be acco=nodated through about 1983 or 1984 with 1,800 licensed locations.
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i GPU Nuclear NggIg{
P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:
Direc t or Of fice of Management Information U.S. Nuclear Regulatory Commission Wa shing ton, D.C.
20555 l
Dear Sir:
i Subj ect: Oyster Creek Nuclear Ger.erating Station i
Do eke t No. 50-219 Monthly Opera ting 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 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. Michael Laggart at (609) 971-4643.
Very truly yours, h
0J Peter n. Fiedler Vice President and Director Oyster Creek PBF:PFC:jal Enclosure s cc: Director (10)
Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission l
Washing ton, D.C.
20555 l
Regional Administrator (1) i Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 L
NRC Resident Inspector (1)
Oyster Creek Nuclear Generating Station Forked River, NJ 053731 l
l
.rE 2.y GPU Nuclear is a part of the General Public Utilities System 1