ML20206G755

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Oct 1988 for Oyster Creek Nuclear Generating Station
ML20206G755
Person / Time
Site: Oyster Creek
Issue date: 10/31/1988
From: Fitzpatrick E, Sedar J
GENERAL PUBLIC UTILITIES CORP.
To:
NRC
References
NUDOCS 8811220413
Download: ML20206G755 (9)
v • d • e


Text

. .

. o. -

MEI11LY OPERATING REFORT - OCTUBER 1988 Throughout the report period, Oyster Creek remained shut down for the Cycle 12 Refueling Outage.

4 i

d

$jp2ggg(( $$$8 gp ggk R

/

h

t

  • =

i MONTHLY OPERATING REPORT OCTOBER 1988  ;

The following Licensee Event Reports were submitted during the month of October 1988-t LER 88-019 " Tech Spec Violation A & B Condensors Being Inoperable Due To l Mechanical Problems And Procedural Inadequacies."

On September 2,1988, an equipment operator performing a valve line-up verification on Isolation Condensers (ICs) "A" and "B" discovered the "A" IC ,

vent line inboard manual isolation valve (V-14-6) was in the incorrect  ;

position (CLOSED). The "A" IC was declared inoperable due to the closed vent valve and the vent valve was opened. The valve was in the incorrect (CLOSED) position due to inadequate administrative controls in a local leak rate test [

procedure. The "B" IC had been declared inoperable from August 29th to September 2nd due to valve seat leakage past the condensate return isolation i valve, V-14-35. Since both ICs were inoperable, an orderly plant shutdown was  ;

commenced at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> as required by Technical Specifications. The shutdown l was terminated at 1952 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.42736e-4 months <br /> after sufficient time had elapsed to vent the "A" IC tube bundle of non-condensible gases, as determined by engineering l evaluation. The "B" IC was returned to service at 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br /> af ter a second  !

engineering study concluded the IC was operable. Corrective action consists of a review of local leak rate procedures for proper administrative controls ,

on components manipulated, and required reading for appropriate personnel, i LER 88-020 "Isolation Condenser and Emergency Service Water Radiation Monitors  ;

Incapable of Leak Detection."

The Isolation Condenser (IC) vent radiation monitor and the Emergency Service Water (ESW) effluent ractation monitors de not fulfill their design function of radioactive leak detection as stated in the Oyster Creek Final Safety Analysis Report (FSAR). This condition was determined reportable on l September 8,1988, while the plant was operating near full power. The  ;

condition has existed since the plant was originally licensed. The apparent cause of the occurrence is a design deficiency due to a failure to properly ^

evaluate all potential area radiation conditions. The safety significance of this condition relative to the ESW monitors is considered minor because system  :

design minimizes the potential for a radioactive release through this  :

pathway. The safety significance of the current IC vent monitor l configuration, however, is considered significant because there is a potential for a radioactive release through this pathway. Procedures for sampling and surveying the area of the Isolation Condenser after an actuation are already i in place. Corrective action will be taken to determine if any additional monitoring requirements or design changes are appropriate to identify and preclude any releases via the IC vent. The design of the ESW monitor will also be evaluated and the FSAR revised to more accurately describe the ef fluent monitor's function.

MONTHLY OPERATING REPORT OCTOBER 1988 Cont'd LER 88-021 "Plant Shutdown Required Due To Both Isolation Condensers Being In An Unanalyzed Condition."

On September 29, 1988, while operating at 100% reactor power, it was determined that both the "A" and "B" isolation condensers were operating in a mode outside of the system design. Temperature data suggested that the steam lines to the isolation condensers were at least partially filled with water, and a thermo-hydraulic mechanism had been established that resulted in both isolation condensers steaming at a combined rate of about 4 MWth. The temperature data also suggested that condensate flow was reversed through one-half of each condenser.

Due to concerns about potential water hamer in the condensar steam lines and the potential system damage which could result in a loss of safety function, a decision was made to isolate the condensers from the reactor. At 1315 on September 29, 1988, all isolation valves to both isolation condensers were closed and the condensers were declared inoperable. Since the Technical Specifications require a reactor shutdown (cold shutdown) in the event both isolation condensers become inoperable, an orderly reactor shutdown was comenced. The plant reached cold shutdown on September 30, 1988.

The safety significance and corrective actions are being evaluated and will be discussed in a supplemental report.

LER 88-022 "Actuation of Engineered Safeguards Functions Caused By The Loss Of The "lD" Electrical Bus."

On October 2,1988 at 1357 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.163385e-4 months <br />, power to 4160 volt bus 10 wat lost when breaker 10 tripped and locked out due to a ground fault on the bus. The plant had been shutdown since September 30, 1988 for a refueling maintenance outage. One of the "B" phase leads was later found grounded at a point between the 10 bus and Emergency Diesel Generator No 2 output breaker. The loss of the bus led to actuation of Engineered Safeguards functions. At 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, on October 3,1988, as part of the recovery effort following restoration of the 10 bus, power was momentarily lost to Vital AC Power Instrument Panel VACP-1 while restoring its normal power supply. This led to the actuation of some additional Engineered Safeguards Functions powered from YACP-1. The failed Diesel Generator cable will be analyzed to determine the cause of the cable fault. This event is reportabic based on 10CFR50.73(a)(2)(iv).

MONTHLY OPERATING REPORT OCTOBER 1988 Cont'd LER 88-023 "Drywell Airlock Not Leak Rate Tested In Accordance With Appendix J Schedule."

, On September 27, 1988, it was discovered that the plant's drywell airlock door

is not leak rate tested at the frequency or test pressure required by 10CFR50

< Appendix J. The Itcensee comitted to test the drywell airlock every six l months, as required by Appendix J, but has been performing the test on a refueling outage interval as indicated in the Technical Specifications.

Testing artor to reestablishing primary containment has been performed at 10 psig ratier than 35 psig. At the time of discovery, the plant was in the RUN

! mode at approximately full power, but the condition has existed for several operating cycles. The cause of the occurrence is attributed to insufficient administrative controls to ensure that the schedule comitted to and test i pressure required by Appendix J were implemented. This condition could have

! safety significance in that a leak larger than allowed by test acceptance l criteria could have existed for more than a six-month interval. Imediately 1

upon discovery of the condition, the drywell airlock leak rate test schedule i was changed to a six-month interval and proper test pressures were used. A Technical Specification Change Request which complies with 10CFR50 Appendix J

testing frequency and pressures has been submitted and is being reviewed by the NRC. Since the time of the testing frequency comitment (1978), a formal action item system for implementation of regulatory comitments has been instituted.

1 e

i l

l 1

i i

4 AVERAGE DAILY POWER LEVEL NET MWe I t

DOCXET d. . . . . . . . 50219 i UNIT. . . . . . . . . . 0YSTER CREEK #1 REPORT DATE . . . . . . . NOVEMBER 5, 1988 (

COMPILED BY . . . . . . . JOHN H. SEDAR JR.

TELEPHONE # . . . . . . 609-971-4698 ,

i MONTH OCTOBER, 1988 l t

t DAY MW DAY MW

1. 0 17 0 ,

l

2. 0 18 0 '

f 3. 0 19 0  !

4. 0 20 0 l i
5. 0 21 0
6. 0 22 0  !

1 1

7. 0 23 0 I i >
8. 0 24 0 9 0 25 0
10. 0 26 0 i r
11. 0 27 0 [

l

12. 0 28 0 j
13. 0 29 0  :

t i

14. 0 30 0
15. 0 31 0 l
16. 0 i

a 3

[

d i

u 1

I

(

t

. OPERATING DATA REPORT OPERATING STATUS

1. DOCbT: 50-219
2. REPORTING PERIOD: 10/88
3. UTILITY CONTACT: JOHN H. SEDAR, JR. 609-971-4698
4. LICENSED THERMAL POWER (Wc): 1930
5. NAMEPLATE RATING (CROSS MWe): 687.5 X 0.8 - 550
6. DESIGN ELECTRICAL RATING (NET MWe): 650 l
7. HAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 650
8. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 620
9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS NONE t'
10. POWER LEVEL TO kHICH RESTRICTED, IF ANY (NET MWe):
11. REASON FOR RESTRICTION, IF ANY: NONE i MONTH YEAR CUMULATIVE l
12. REPORT PERIOD HRS 744.0 7319.0 165312.0
13. HOURS RX CRITICAL 0.0 5789.0 106245.4 14 RX RESERVE SHTDhH HRS 0.0 0.0 918.2 1
15. HRS GENERATOR ON-LINE 0.0 5750.6 103543.5 f
16. UT RESERVE SHTDhH HRS 0.0 0.0 1208.6
17. GROSS THERM ENER (%H) 0 10873100 173520889 L
18. CROSS ELEC ENER (MhH) 0 3685830 58604184
19. NET ELEC ENER (EH) -3466 3543832 56264828 l
20. UT SERVICE FACTOR 0.0 78.6 62.6
21. UT AVAIL FACTOR 0.0 87.5 63.4 [
22. UT CAP FACTOR (MDC NET) 0.0 78.1 54.9  ;
23. UT CAP FACTOR (DER NET) 0.0 74.5 52.4
24. UT FORCED OUTAGE RATE 0.0 12.5 11.? f
25. FORCED OUTAGE HRS 0.0 824.4 13510.7 f
26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):

REFUELING OUTAGE RESCHEDULED FOR SEPTEM3ER 30,1988 THROUGH DECEMBER 30, t 1988.  !

27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: DECDiBER 30, 1988.

Oyster Creek Station di Docket No. 50-219 REFUELING INFORMATION - OCTOBER, 1988 ,

Name of Facility: Oyster Creek Station di Scheduled date for next refueling shutdown: September 30, 1988 Scheduled date for restart following refueling: Decembe r 30, 1988 Will refueling or re sumption of operation thereafter require a Technical ,

Specif feation change or other license amendment? '

Yes I

Scheduled date(s) for submitting proposed licensing action and supporting  !

information l Technical Specification Change Request No.166 was submitted March 30, 1988 ,

4 L

i Important licensing considerations associated with refueling, e.g., new or ,

i different fuel design or supplier, unterieved design or performance analysis  !

methods, significant changes in fuel design, new operating procedurest '

1. General Electrk Fuel Assemblies -

fuel design and performance analysis methods have been approved by the NRC. [

i

2. Exxon Fuel Assemblies -

no asjor changes have been made nor are there any anticipated.

I I The number of fuel assemblies (a) in the core - 560 (b) in the spent fuel storage pool = 1573 (c) in dry storage = 38 i t

l The pre sent licensed spent fuel pool storsge capacity and the site of any [

increase in licensed storage capacity that has been requested or is planned,  ;

4 in number of fuel assembliest  ;

! i Pre sent licensed capacity: 2600 The projected date of the last refueling that can be discharged to the spent I

fuel pool assusing the present licensed capacityt '

Reracking of the fuel pool is in progress. Nine (9) out of ten (10) f j racks have been installed to date. When reracking is cospleted, !

i discharge capacity to the opent fuel pool will be available until 1994  :

l refueling outage.

I i  !'

l

IMKKliT Nt t 1Q-Zl9 ,

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAMii Oveter Creek ,

DATE hv - 19RR -

{

COMPLETED BY x. Baran .

OCTOBER, 1988 TELlirilONE _371-46t.o .

REPORT MONTil .

RAETHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR S- SCHEDULED (HOURS) REASON 0) REDUCING POWER (2) CORRECTIVE ACTIONS /COamAENTS NO. DAlt 70 9/30/88 F 765.6 '

F 2 Suspected both isolation condender steam lines hhve water in them.

Administrative decision made to shutdown. Declared both isolation condensers inoperable. Subsequent I to the shutdown the decision was made to st t the "12-R" Outage.

l

.+

\

SUMMARY

{1) REASON (2) METil0D '

A: Equipment failure (Explain) E: Operator Training & 1: Manual B: Maint, or Test License Examination 2: Manual Scram C: Refueling F: Administrative

D: Regulatory Restriction H: Other (Explain) l

. _ _ _ _ __ _ _ .. . _ _ ,_ _ _ . _ . . _ , , _ , _ , . . . , - , . . , _ _ . _ . . , , - = _ . . . , , _ _ _ _ . . . - - - - _ - . _ . . _ . . _ . _ _ . _ _ _ -

n. . .

g .. . .

O.*U Nucleer Corporation Nuclear ;o='= 388 Forked River, New Jersey 08731 o388 609 971 4000 Writers Direct D al Number.

Director November 10, 1988 Office of Management Information U.S. Nuclear Regulatory Comission 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) copies of the Monthly Operating Data (gray book infortnation) for the Oyster Creek Huclear Generating Station.

If you should have any questions, please contact Kathy Barnes, Oyster Creek Licensing at (609)971-4390.

Very truly yours, f 'c E. E. Fittphtrick Vice President and Director Oyster Creek EEF:KB:smz (0841 A)

Enclosures cc: Director (10)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission Washington, DC 20555 Mr. William T. Russell, Administrator Region I i U.S. Nuclear Regulatory Comiss.on 475 Allendale Avenue King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Comission Division of Reactor Projects I/I!

Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station i Gru Nuc ear caccrate,is a s t:s a v> ct tne Gerera' Ps Utat es CcTc'at on g

Retrieved from "https://kanterella.com/w/index.php?title=ML20206G755&oldid=3058560"