ML20147E241

Monthly Operating Rept for Dec 1987

ML20147E241
Person / Time
Site:	Hope Creek
Issue date:	12/31/1987
From:	Jensen H, Labruna S, Ritzman R Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8801210050
Download: ML20147E241 (12)

Text

e

's

• j AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.86-354 UNIT Hope Creek

'DATE 1/15/88 COhPLETED BY H. Jensen __

TELEPHONE (609) 339-5261 MONTH December 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1026 17 1015 2 1007 18 1000 3 1014 19 952 4 1031 20 978 5 991 21 1099 6 1023 22 994 7 1013 23 966 8 588 24 1003 9 0 25 1002 10 868 26 955 11 1017 27 __

1012 12 1003 28 1029 13 1009 29 1023 14 1017 30 1018 15 1007 31 1026 16 1006 t

p'/

8801210050 871231 l PDR ADOCK 05000354 R DCD

OPERATING DATA' REPORT DOCKET NO.86-354 UNIT Hope Creek DATE 1/15/88 COMPLET3D BY H. Jensen ___

TELEPHONE (609) 339-5261 OPERATING STATUS

1. REPOP. TING PERIOD Dec 1987 GROSS HOURS Id REPORTING PERIOD '/44

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEPEND. CAPACITY (MWe-Net) 1067

• DESIGN ELECTRICAL RATING (MWe-Net) 1067

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net) None

4. REASONS FOR RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE

5. NO. OF HOURS REACTOR WAS CRITICAL 713.9 7570.1 7858.1 i

6. REACTOR RESERVE SHUTDOWN HOURS 0 0 0

7. HOURS GENERATOR ON LINS 709.4 7457.1 7745.1

8. UNIT RESERVE SHUTDOWN HOURS 0 _0 0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2,309,491 _22t 878,159 23,808,567

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 770,718 7,614,058 7,911,698

11.  !!ET ELECTRICAL ENERGY GENERATED (MWH) 739,066 7,279,214 7,565,038

12. REACTOR SERVICE FACTOR 96.0 86.4 86.8

13. REACTOR AVAILABILITY FACTOR 96.0 86.4 86.8

14. UNIT SERVICE FACTOR 95.3 85.1 85.6

15. UNIT AVAILABILITY FACTOR 95.3 85.1 85.6

16. UNIT CAPACITY FACTOR (Using Design HDC) 93.1 77.9 78.4

17. UNIT CAPACITY FACTOR (Usina Desian MWe) 93.1 77.9 78.4 __

18. UNIT FORCED OUTAGE RATE 4.7 9.3 9.0

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):

Refueling 2/12/88, 55 days

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

• Data obtained in August is under management review.

l OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.86-354 UNIT Hoce Creek DATE 1/15/88 COMPLETED BY R. Ritzman REPORT MONTH Dec. 1987 TELEPHONE (609) 339-3737 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) (1) POWER (2) COMMENTS 21 12/8 F 34.6 A 3 Reactor Scram caused by a spurious signal in the Main Steam Line Radiation Monitoring

> cabinets LER 87-051 1/6/88 l

1 i

SUMMARY

j l

i

. . -_ . - . . . - .. - - = .. - -_ - _ .

HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

DECEMBER 1987 Hope Creek entered the month of December operating at approximately 100% power. At 2:05 pm on December 8, the reactor automatically scrammed due to a spurious signal in the Main Steam Line Radiation Monitoring cabinets. The unit had been on-line for 41 consecutive days. The reactor went critical at 8:12 pm on December 9 and the generator was synchronized with the grid at 12:43 am on December 10. At months end the plant completed its 21st day of continuous power operation.

R-005 RAR:tib l

l 1

. _ _ _ ___ . _ __ _.___ _ _ . . _ . ~ . . _ _ _ . _ . _ _ - - - _ _ .._ . _ . _ _ _ _ _ _ _ _ . . _ . . _ _ _ . _ . _ _ - . . _ _ _ _ _ _ _

t

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION DECEMBER 1987 f

v 4

,n,- +,, , - - - - - - . . . , , - --=ye-+-----, y-,-y,-,--%, -, , --,=.--,,,.,-m,--a w,,,w-.m,--n-e--w--.e--v<----w,-< ,,w,-,,.,-e,e,-.=-w,,-,w,-v-v+, --e-,--,wg-e-wew--,w,-,rs, +- m- w we

.]

l l

The'following' Design Change Packages (DCPs) have been evaluated to-

. determine:  ;

1) if the probability ao f ' occurrence or- the . consequences of an accident or -malfunction ~ of equipment. important to safety previously evaluated in the safety analysis report may be

. increased; or

2) if a possibility for. an accident or malfunction of a different type than any evaluated-previously in'the safety analysis . report may be-created; or

3) if the. margin of' safety as defir.ed in the basis-for any technical

, specification is reduced.

None of the DCPs created a new safety hazard to'thel plant nor did they affect the safe shutdown of the reactor. These DCPs did not change the plant effluent releases: and did not. alter the existing environmental impact. The Safety Evaluations determined thatf no.

unreviewed safety or environmental questions are-involved.

l l

1 l

l I

l J

ECE Description of Desian Chance Packace 4-HC-0019/1 This DCP rewired Control Room Overhead Annunciator Windows to allow the annunciator to clear when the corresponding remote panel alarm has been y acknowledged. .This will eliminate nuisance alarms i in the Control Room and reduce confusion by l clearing alarms when they are no longer required.

to be displayed.

I 4-HC-0019/2 This DCP rewired Control Room Overhead Annunciator Windows to allow the annunciator to clear when the corresponding remote panel alarm has been  ;

acknowledged. This will eliminate nuisance alarms  !

in the Control Room and reduce confusion by clearing alarms when they are no longer required to be displayed.

4-HH-0147 This DCP installed terminals in the Radiation Protection offices and the Operational Support Center to allow personnel to expeditiously obtain radiological and meteorological data during emergency conditions.

4-HM-0214 This DCP replaced a Reactor Protection System Scram Reset Relay with a functionally equivalent relay. The original style relay is no longer available.

4-HM-0216 This DCP modified the ICD cards and applicable drawings to allow the use of either of two logic cards for the Service Water Pump Lubricating Water Low Pressure Switch and the valve which allows Head Tank flow in the event of Low Lubricating Water Pressure. This change eliminates a Temporary Hodification and allows for more flexibility when replacement parts are required.

4-HM-0252 This DCP- changed-the Main Steam Line Radiation Monitor Alarm and Trip Setpoints to be consistent with the measured full power backgroand radiation monitor readings. The "B" and "C" Main Steam Line Radiation Monitors have been changed, "A" and "D" I will be changed at a later date. )

4-HM-0255 This DCP installed stiffeners on the flow distribution vanes in the transition duct between the Filtration, Recirculation and Ventilation System recirculation fan and its filter housing. l Adding the stiffeners will eliminate the pressure I pulsations which fatigued the duct, causing cracking at the area where the vane is welded to the duct. ,

The following Temporary Modification Requests (THRs) have been evaluated to determine:

1) if the . probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3) if the margin of safety as defined in the_ basis for any technical specification is reduced.

None of the THRs created a new safety hazard to the plant nor did they affect the safe shutdown of_the reactor. These THRs did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

4 Safety Evaluation Description of Temporary Modification Reauest (THR) 87-0197 This TMR replaced resistors in the Filtration, Recirculation and Ventilation Radiation Monitoring System. This THR was necessitated by the failure of a flow sensor in the Filtration, Recirculation and Ventilation System. Normally, the Radiation Monitors average 2 signals, however, with 1 of the signals inoperable this is not possible.- This THR allows the use of the valid signal rather than the average.

H-1-GUXX-MSE-0722 This THR temporarily provides for the adequate filtration, recirculation, and ventilation of the Reactor Building. The THR is required while ductwork in the Reactor Building Ventilation System is being replaced. The Filtration, Recirculation and Ventilation System will be able to provide Reactor Building cooling and be able to maintain negative pressure there during this time frame, i

I 1

I

9 The following Deficiency Requests (DRs)' have been evaluated to determine:

1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3) if.the margin of safety as defined in the basis for any technical specification is reduced.

None of the DRs created a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These DRs did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Safety' Evaluation Description of Deficiency Report (DR) 87-0110 The insulation on Emergency Diesel Generator Combustion Air High Temperature Switch Alarm wire leads was discovered to be damaged. Repairing the insulation via the Raychem process will restore the insulation to its original integrity and allow the switch to operate as designed.

87-0194 Inter-step connection cables installed on the 125 VDC Class lE Battery Bank were discovered to be out of compliance with the design documents.

Additionally, they were not certified to the applicable standard. However, the cables are capable of performina their required function until they can be replaced.

87-0199 Emergency Diesel Generator Exhaust Silencer Inlet Expansion Joints show signs of distortion and possible leakage. The extent of leakage will be evaluated. The expansion joints may be used "as is" until the evaluations are comp 1cte and the required parts are available.

87-0201 A two inch wye pattern globe valve branching from the "C" Main Steam Line developed a packing leak.

Drilling a small hole in the packing gland and injecting sealant to stop the leak will allow the valve to be used "as is" until it can be repaired.

i i

)

l l

l

.s' D PSEG I Public Service Electric and Gas Compary P.O. Box L Hancocks Bridge New Jersey 08038 Hope Creek Operations January 15, 1988 U. S. Nuclear Regulatory Commission Document Control Desk ,

Washington, DC 20555 l

Dear Sir:

MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for December are being forwarded to yo" In addition, the summary of changes, tests, and experiments for December 1987 are included '

pursuant to the requirements of 10CFR50.59(b).

Sincerely yours, l 6sw S. LaBruna General Manager -

Hope Creek Operations W Attachment C Distribution 1

/g')

2 i\

The Energy People 95-2173 0 1 % 12 85

, . - ._ __ , _ _ _ _