ML20065D633
| ML20065D633 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/31/1990 |
| From: | Fitzpatrick E, Sharma H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9009260031 | |
| Download: ML20065D633 (9) | |
Text
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g3 Post Office Box 388 ' r s u -- - Route 9 South n" Forked River, New Jersey 08731-0388 - _ ,
, 609 971 4000 - -
Writer's Direct Dial Number: , September 15, 1990 . l 4
~U.S. Nuclear Regulatory Commission ATTN - Document Control Desk-sWashington,'D.C. 20505 .
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Dear Sir:
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Subject:
Oyster Creek Nuclear Generating Station ' Docket No. 50-219 ?! h Monthly Operating Report
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'In acchrdance w3th'the Oyster Creek' Nuclear Generating Station
< , ._ Operating. License No.' DPR-16, Appendix A, Section 6.9.1.C, enclosed are two ;
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,, l(2) copies o1 the Monthly Operating Data'(gray book information)?for the Ji
- K. . Oyster. Creek N.1 lear.. Generating Station. -f '
'If you should hava any questions,+please contact Brenda DeMerchant, .'
Loyster Creek Licensing Engineer at (609) 971-4642. Very.truly yours, ( q' '
.E. E. Fit;spatrick.
y Vice President,and Director , 1 Oyster _ Creek l Li
, -EEF:BDEM:jc (MOR),
Enclosuresi e ces; Mr. Thomas: Martin, Administrator 3 Region I ; U;S. Nuclear Regulatory Commission
-475'Allendale Road ;
. King of: Prussia, PA 19406 e
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- Mr. Alexander W.-Dromerick, Project. Manager b 5 X- U.S. Nuclear Regulatory Commission
.W ashington, DC- 20555 at e
NRC Resident Inspector q
.OysterfCreek Nuclear Generating Station -{
9009260031 900831 PDR ADOCK 05000219 4
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~ ,; .l MONTHLY OPERATING REPORT ~- AUGUST 1990 .
At the beginning of August,-Oyster Creek was operating at full power. Power reductions were required for maintenance, as specified by the Technical specifications, to perform condenser backwashing and due to discharge canal l temperature limitations. : i on' August 25-26, 1990, power was reduced to isolate and clear the south half of' j '
'C' main condenser. The plant was returned to full power on August 27, 1990.
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o MONTHLY OPERATING REPORT AUGUdT 1990 \ The following Licensee Event Reports were submitted during the month of August 1990s i LEB_90-010: Electromatic Relief Valve Hich Pressure Relief Setooints Exceeded , Technical Specification Limit Due to Drift j On July 18, 1990 while performing an Electromatic Relief Valve (EMRV) Pressure
~ Sensor surveillance, the "As Found" trip setpoint for the high pressure relief- ,
y function on three out of five EMRVs was above that specified in the Technical l L Specifications. Additionally, a review of records for this. surveillance j H revealed that on April 14, 1988-and June 13, 1990, one EMRV had a high pressure i
- setpoint that was above the limit. The cause of these occurrences is
[, attributed to.setpoint repeatability and instrument drift. The design setpoint '~ repeatability can tolerate instrument drift within 2.5 peig of the Technical- ' Specification limit. Previous surveillance records indicate that these instruments frequentiv undergo additional drift within Technical Specification limits due to chang'ig plant and environmental conditions. This occurrence is considered to have m: i21 safety significance as the automatic y . depreasurization fen c of the EMRVs is not. affected by these pressure switchos, all five LMRVs would have actuated to relieve pressure, and the Isolation condenser System and turbine bypass valveo were fully operable. The 4 pressure switches were adjusted to actuate within the Technical Specification limit. A new pressure sensing system is included in the Oyster Creek 3g Integrated Schedule. - I' LER 90-011: Uncualified ooerators on shift Due to Inadecuacies in' Exam Process Results in Violation of Tech Spec Shift Mannino Recuirements In June.and July of 1990, as a result of an NRC audit of the operator ttaining I N - program, 1989 biennial requalification exams were found to have been I : incorrectly graded. A regrading effort resulted in the failure of two licensed-operators. The operators were immediately removed from licensed duties and ; entered into an accelerated tequalification program. These operators had been performing licensed duties during the period from the requal exam up to the regrading of.the exam. Since these two operators were retroactively disqualified, there were 89 shifts during this period with less than two f W control room operators as required.by technical specifications. The cause of this occurrence is attributed to personnel error as a result of programmatic inadequacies in the exam process. An investigation and critique of this incident revealed that these inadequacies led to errors in the preparation, , administration and gra/ cg of the 1989 written requalification exam. These inadequacles caused the grading-anomalies identified. To prevent recurrence, an examination procedure will be developed to provide guidance for the Er preparation, administration and grading of exams. f w P L=:___-.- _ _ _ . - _ _ _ _ _ _ - . - - . . _ . ,
- l. - . ..:.
e t 'O i LER 90-012t An Error in a Feedwater Flow Calculation Ecuation May Have
- Resulted in Operation of the Reactor in Excess of the License Limit-A decrease in plant performance had been noted for the current operating cycle. - A leak in the high pressure feedwater reheaters was postulated and investigated. Visual' inspections revealed no leaks. A detailed review of plant data was initiated on July-11, 1990 to locate the source of the s performance decrease.
On August 1, 1990, it was noted that a procedure revision (approved on February.9, 1987) to the feedwater flow calibration calculation had resulted in
. approximately a 21 correction in indicated feedwater flow. This change resulted in a. decrease in allowed plant power. Therefore, although indicated .l reactor power has been correct since February 9, 1987, prior to that date the reactor may have been operated slightly in excess of its license limit of 1930' megewatts thermal. The magnitude of the power anomaly and any resultant-effects on safety significance are presently being reviewed. A supplemer.tal-Licensee Event Report will be submitted when the ongoing review'is completed.
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, s J f/ AVERAGE DAILY POWER LEVEL
,, . NET MWe 19/ ,
s;- 'e I - DOCKET #... . . . . .. .50219
.jf 3; UNIT. . . . . . . . . . . OYSTER CREEK #1 REPORT DATE . . .~. . . . SEPTEMBER 7,-1990 COMPILED BY . . . - . . . .HARI S. SHARMA TELEPHONE #'. ... . . . .609-971-4638 s
MONTH- AUGUST, 1990' DAX E DAX E .
- 1. 602 16 549
- 1,-
- 2. 602 1 +a
- 3. 594 16, 505
- 4. 594 19. 518
, 5. 566 20. 585
- 6. 520 21. 606
- 7. 510 22. 609 g
- 8. 595 23, 611 u 9. 585 24. 609 10, 588 25. 268
- 11. 511 26. 295
- 12. .559 27. 563
- 13. 528 28. 586
- 14. 520 29. 572
- 15. 553 30. 526
- 31. 597 4
-1619B/34
m-11 . Oystor Creek' Station #1 Docket No. 50-219 REFUELING INFORMATION - AUGUST, 1990-Name of Facility: _ Oyster Creek Station #1 Scheduled date for next refueling shutdowns February 15, 1991 pending necessary state app; oval. Scheduled date for restart following refueling: May 31, 1991-
= Will - refu111ng or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes
' Technical Specification Change Request 180. was submitted to the NRC on 5-07-90. This submittal was made in accordance with GL 88-16 to incorporate cycle specific parameters in a core operating limits report.
Important licensing considerations associated with refueling,'e.g., new or 1different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating' procedures:
- 1. General Electric Fuel Assemblies - fuel desigt- end performance 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 (b) in the spent fuel storage pool = 1595 (c) in dry storage = 37 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 licensed capacity: 2600 The' projected date of the last refueling that can be discharged to the sper 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. 1619D/33 i
OPERATING DATA REPORT OPERATING STATUS
- 1. DOCKET: 50-219
.2. REPORTING PERIOD: 08/90 a- 3. UTILITY CONTACT: HARI S. SHARMA 609-971-4638
- 4. LICENSED THERMAL POWER (MWt): 1930 5.- NAMEPLATE RATING (GROSS MWe): 687.5 X 0.8 = 550
,6. DESIGN ELECTRICAL RATING (HET 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): None
. 11. REASON FOR RESTRICTION, IF ANY: None MONTH XIAB CUMULATIVE
- 12. REPORT PERIOD HRS 744,0 5831.0 181367.0
- 13. HOURS RX CRITICAL 744.0 4875.6 116136.2
- 14. RX~ RESERVE SHTDWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 744.0 4752.2 112984.0
- 16. UT RESERVE SHTDWN HRS 0.0 0.0 1208.6
'17. ' GROSS THERM ENER (MWH) 1328933 8375394 189648453 423850 2746500 63859240
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-18. GROSS JLEC-ENER-(MWH)
- 19. NET ELEC ENER (MWH)' 407070 2634148 61289126
- 20. UT SERVICE FACTOR- 100.0 81.5 'G2.3
- 21. UT AVAIL FACTOR 100.0 81.5 63.0 f 22.. UT. CAP FACTOR (MDC NET) 88.2 72.9 54.5
~ 23. UT CAP FACTOR (DER NET) 84.2 69.5 52.0 24.' UT FORCED OUTAGE RATE 0.0 15.3 11.9
- 25. FORCED OUTAGE HRS 0.0 859.9 15270,0
- 26. SHUTDOWNS SCHEDULED OVER'NEXT 6 MONTHS (TYPE, DATE, DURATION):
Refueling outage 13R commencing February 15, 1991, scheduled to end May 31, 1991.
- 27. IF CURRENTLY SMitTDOWN SjSTIKWED STARTUP DATE: N/A
;1619B/3S i
i . .i o . UNIT CHUTDOWNS AND POWER FEDUCTIONS DOCRET MO. 50-219 UNIT MAME Oyster Creek . DATE- Seo+ Wr. 1990 - COMPLETED BY R. Baron TELEP90NE _971-4640 REPORT MONTH August. 1990 TYPE METHOD ~OF SHUTTING ra Irorced DURATION DOWN THE REACTOR OR REDUCING M (2) CORRECTIVE ACTIONS /CnemarWTS 740 . DATE St Scheduisd (Nours) REASON (1) E 1 Load Reduction required to backwash 1 110 8/06 F 0 main condensers (416 MWe Gross). E 1 Plant shutdwn commenced due to high 111 8/06 F 0 drywell unidentified leak rate follow-ing the inadvertent spray down of the drywell during Containment Spray surveillance testing. Shutdown termin-ated on August 6, 1990 at a plant load of 520 stWe when leak rate returned to normal. On August 7, 1990, load re-duced to 203 MWe to facilitate MSIY-testing. Returned to full load on August 7, 1990. F 0 E 1 Load reduction to backwash main 112 8/11 condensers (411.MWe Gross) St* amary METHOD (1) REASON Operator. Training & License Exam 1. Manual
- a. Equipment Failure (Explain) e.
- 2. Manual Scram
- b. Maintenance or Test f. Administrative Operational Error (Explain) 3. Automatic Scram
- c. Refueling g.
Other (Explain) 4. Other (Explain)
- d. Regulatory Restriction h.
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' UNIT SHUTDOWNS AND POWER REDUCTIONS -.
50-219 DOCKET NO.- . Oyster Creek UNIT NAME - , . DATE September. 1990 - COMPLETED BY R. Baron TELEPHONE 971-4640 REPORT MONTE August, 1990 (continued) TYPE METHOD OF SEUTTING - F: Forced DURATION DOWN THE REACTOR OR REDUCING POWER (2) CORRECTIVE ACTIONS /COBBEENTS NO. DATE St Scheduled (Hours) REASON (1) E 1 Load' Reduction required to backwash 113 6/14 F 0 main condensers (374 MWe Gross). E 1 Load reduction requzred to backwash 114 8/19 F 0 main condensers (336 MWe Gross). S O E 1 Load Reduction to isolate and clean 'C' 115 8/25 South Main condenser (274 MWe Gross). Returned to full load on August 27, 1990. 0 A 1 Commenced plant shutdown due to loss of 116 8/29 F ADS logic input upon isolation of Core Spray System 2. Isolation required to replace V-20-24. Shutdown terminated when ADS logic input was returned to operability at a plant load of 389 Mue. Returned to full load on August 30, 1990. t Sunmary : (1) REASON Operator Training & License Exam 1. Manual
- a. Equipment Failure (Explain) e.
- 2. Manur.1 Scram
- b. Maintenkitce'or Test f. Administrative Refueling g. Operational Error (Explain)- '3. . Automatic Scram
- c. 4. Other (Explain)
Regulatory Restriction h. Other (Explain)- d.}}