ML20082A011
| ML20082A011 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/30/1983 |
| From: | Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8311170439 | |
| Download: ML20082A011 (8) | |
Text
1 4
MONTHLY OPERATIONS REPORT SEPTEMBER 1983 Throughout the report period, the Oyster Creek Station remained shutdown for the 1983 Refueling / Maintenance Outage.
Processing of new reactor fuel commenced during the report period.
On September 20, 1983, Reactor Building Ventilation System isolation valve V-28-12 failed to fully close during routine testing. V-28-12 was repaired and returned to an operable status on September 28.
The problem was attributed to leaking piston seal rings in the valve actuator. Consequently, the Operations Department has requested that all Reactor Building Ventilation System valves be inspected for this problem and repaired as necessary. These repairs should reduce the demand on the plant's Control Air System and thus reduce the number of times the air compressors cycle to maintain system pressure.
The only problem experienced with plant air compressors during the report period was with No. 2 air compressor.
It was out of service for a two day period due to a starting and loading problem.
Repairs were started on several leaks in Condensate Transfer System piping.
These repairs are expected to be completed and the system made available by October 1, 1983.
On September 7 and 8, outage work in the drywell and torus was temporarily stopped due to personnel experiencing heat distress as a result of high ambient air temperature.
Plant Engineering is addressing this problem with assistance from the Plant Operations and Maintenance and Construction Departments.
A scram signal (half scram) was received in Reactor Protection System No. 2 due to the failure of one of the associated high dryuell pressure sensor y
(RE 048) relays (2k9). The relay was replaced.
P3 N a.
$8 A half scram was received due to a detector failure on "D" main steam lir.c g
radiation sensor. A new detector will be installed.
o b
The following items were also considered noteworthy:
1.
Dilution pump No. I tripped due to a failed seal water pressure switch.
Ca:
2.
Faulty contacts in the Rotary Inverter for Continuous Instrument Panel No.
$$a:
3 caused a voltage regulator problem which made its associated auto-but-transfer switch (IT-3) transfer periodically between the normal and alternate power supply. The Rotary Inverter was placed back in service after the contacts were replaced.
It is presently being monitored for satisfactory operation.
d YN
September 1983 Monthly Op3 rations Report Page 2 3.
Fire diesel pump No. 2 was out of service for a two day period due to an oil leak.
4.
The bearings on "D" Augmented Fuel Pool Cooling pump were replaced.
5.
The Stack Gas Sample System isokinetic probe was removed for decon, inspection, and modification. A temporary probe has been installed.
6.
Reactor Building Closed Cooling Water (RBCCW) pump No.1 was out of service for a one day period due to a breaker tripping problem.
7.- On September 21, the fuel pool water spilled into the ventilation system while backwashing the fuel pool filter. The cause of the event was duc W a combination of procedure deficiencies, equipment malfunction and operator error. The procedure will be revised, and the critique discussed with operators.
8.
As a result of work activities in the 460 Volt Switchgear Room and Cable Spreading Room, two fire barriers, which had been breached, were repaired. Fire watches were posted in the interim.
9.
Inspection of main steam reheaters (RHTR) 1-2 and 1-3 was completed. One tube leak in RHTR l-2 was identified.
f
September 1983 Monthly Operations Report
.Page 3 The following Licensee Event Report was submitted during September 1983:
Reportable Occurrence No. 50-219/83-17/0lT:
On August 16, 1983, Diesel Generater (DG) No. 1 tripped during a fasi, stalt test. DG No. I was then declared inoperable. After a thorough review of the test data, it was determined on August 26, 1983 that DG No. 2 might have the potential for the same problem. At that time, DG No. 2 was also taken out of service. The cause of the occurrence was attributed to close timing between the Main Circuit Breaker Auxiliary Relay and the DG's undervoltage sensing protective relay.
Following a change in the time delay setpoint (from 4 seconds to 7 seconds) both DGs were returned to service on August 27,' 1983.
l
50-219 UNITSHUTDOWNS AND POWER REDUCTIONS DOCKETNO. Oyster Creek UNIT NAME DAst Oct.
1.
1983 COMPLETED BY R.
Baran REPORTMONT11 Sentomber 1983 TELEPHONE 4640 i
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I Licent:?
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Cause & Corrective g
No.
Date k
3g
,, g oc Event u7 Action to j 65 g Repori#
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rrevent Recurrence E
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t 31 2-11-83 S
5544 C
1 NA ZZ ZZZZZZ Start of the 1983 Refuel /
Maintenance Outage.
A I
2 3
4 F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A Equipment Failure ('ixplain) 1 Manual for Preparation of Data B-Maintenance of Test 2 Marmal Scram.
Entry Sheets for Licensee C Refueling 3 Automalic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restricii. n 4-Other (Explain) 0161)
E-Operator Training & dcense Exandnation F-Administrative 5
G-Operational Errur (Explain)
Exhibit I-Same 3ource (9/7 )
ll 01her (Explain) l
/'
OPERATING DATA REPORP
'-4 OPERATING STATUS 1.
DOGET:
50-219 2.
IEPORPING PERIOD:
September, 1983 3.
UrILITY 009EACT:
JOSEPH R. MOIJ&R 609-971-4699 4.
LICENSED THEINAL POER. (Mt) :
1930 5.
NAMEPIATE RATING (GROSS We):
687.5 X 0.8 = 550 6.
DESIGN ELECIRICAL RATING (NET We):
650 7.
MAXIMM DEPENDABLE CAPACITY (GROSS We):
650 8.
MAXIMLM DEPENDABLE CAPACITY (NET We):
620 9.
IF CHANGES OCQR ABOVE SINCE LAST REPORP, GIVE REASONS:
NONE 10.
POWER LEVEL TO WHICH RESTRICIED, IF ANY (IEF We):
- 11..
REASON M R RESTRICTION, IF ANY: NONE MONIH YEAR O.NULATIVE 12.
REPORP PERIOD HRS
~720.0 6,551.0 120,719.0 13.
IOURS RX CRITICAL 0.0 1,009.6 84,622.8 14.
RX RESERVE Slfluti HRS 0.0 0.0 468.2 15.
HRS GENERA'1DR ON-LINE 0.0 1,007.8 82,693.6 16.
Uf RESERVE SHID W HRS 0.0 0.0 0.0 17.
GROSS THEIN ENER (WH) 0.0 853,300.0 136,224,730.5
' 18.
GROSS EIEC ENER (MWH) 0.0 244,630.0 46,056,905.0 19.
NET ELEC ENER (21H)
-1,461.0 210,583.0 44,291,111.0 20.
UP SERVICE FACIDR 0.0 15.4 68.5 21.
UP AVAIL FAC10R 0.0 15.4 68.5 i
l 22.
Ur CAP FACIOR (MQ NOT) 0.0 5.2 59.2 i
23.-
Ur CAP FACIOR (DER NET) 0.0 4.9 56.4 24.
Ur maced OurAGE RATE 0.0 0.0 9.7-25.
FORCED OUfAGE HRS 0.0 0.0 8,916.8 f-L 26.
SHUIDOWS SCHEDULED OVER NEXT 6 MNfHS (TYPE, DATE, DURATION): N/A 1
l 27.
IF CURRENTLY SHUIDOW ESTIMATFD STARFUP TIME:
02/10/84 f
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AVERAGE DAILY PO6ER LEWL NET M4e DOCKET 4........ 50-219 UNIT.......... Oyster Creek #1 REPORP DATE.......OCIOBER O3,1983 CEMPILED BY-....... JOSEPH R. MOW AR
'IELEP10NE 9...... 609-971-4699 MONIH SEPTDEER,1983 DAY g
DAY g
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0 18.
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0 19.
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0 23.
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0 25.
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Oyster Creek Station #1 Dockst No. 50-219 RE2UELING INFORMATION - September,1983 Name of Facility: Oyster Creek Station il Scheduled date for next refueling shutdown: Presently shutdown for Refueling Scheduled date for restart following refueling: February 10, 1984 Will refueling or resumption of operation thereafter require.a Technical Specification change or other license amendment?
Technical Specification Omnge Request No. 96 was submitted on August 31, 1982 for incorporation of GE assemblies into the Cycle 10 core.
Scheduled date(s) for submitting proposed licensing action and supporting information:
October 30, 1983 - W e final supplement to the reload analysis, delineating the specific core configuration for Cycle 10 operation, will be sutaitted.
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:
- l. General Electric Fuel Assemblies - fuel design and performance analysis methods have been approved by the NBC. % operating procedures, if necessary, will be submitted at a tte.
- 2. Fxxon Fuel Assemblies - no major changes have bet nor are there any anticipated.
0 We number of fuel assemblies (a) in the core
=
(b) in the spent fuel storage pool = 1361 h e 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 he projected date of the last refueling that can be discharged to the spent
-fuel pool assuming the present licensed capapcity:
Full core offload capability will be lost after the 1985 outage. Batch discharge capability will be lost after the 1987 outage. Expanded spent fuel pool rack capacity (2,600) is scheduled for 1984.
/
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0 GPU Nuclear Corporation l
g gf Post Office Box 388 j
Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
October 14, 1983 Director Office of Management Information U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Subject:
Dyster 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) 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, er e
^)
Pet 6r B. Fiedler Vice President and Director Oyster Creek PBF:PFC: dam Enclosures cc: Director (10)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Regional Administrator (1)
Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 IEC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 9,
GPU Nuclear Corporation is a sul;sidiary of the General Pubhc Utihties Corporation