ML20096E769

Monthly Operating Rept for Apr 1992 for Hope Creek Generation Station,Unit 1

ML20096E769
Person / Time
Site:	Hope Creek
Issue date:	04/30/1992
From:	Hagan J, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9205200001
Download: ML20096E769 (12)

Text

_ _ _

fO PSIBG Public Service Doctric and Gas Company P.O. Box 230 Hancockt, Bridge. New Jett.ey 08030 Hope C eek Generating Station May 15, 1992 U. S. Nuc'Sar Regulatory Commission Document control Desk Washington, DC 20555 Dear S'rs MONTHLY OPERATING REPORT HOPE CREEK GENERATION 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 April are being forwarded to you along with the summary of changes, tests, and experiments for April 1992 persuant to the requirements of_10CFR50.59(b).-

Sincer ly yours, d'

.J.}faga.

Genera]. -

ager.-

Hope Cree Operations QF RAR 1d Attachments C Distribution 2000_09 The Energy People

[/

9205200001 920430 ,s myuy, ,n, PDR ADOCK'05000354 R . P DR _ '

.i INDEX NUMBER SI.CTION OF PAGES Average rally Unit Power Level. . . . . . . . . . . 1 Operating Data Report . . . . . . . . . . . . . . . 2 Refueling Information . . . . . . . . . . . . . . 1 Monthly Operating Summary . . . . . . . . . . . . . 1 Summary of changes, Tests, and Experiments. . . . . 5 2

e h

• /

' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.59-354 ..

UNIT- U p_n_e _C r e e k  ;

DATE 5/15/92 COMPLETED BY V. Zabielski_  ;

TELEPHONE- (609) 339-3506 MONTH April 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWo-Net) - (MWe-Net )'

1. 1060 17. 10!,2

2. 1061 1 ', 1064

3. 1951 19, 1053

4. 1061 20. 1053

5. 1009 -21. 32d '

6. 1050 22. 486

7. 104E 23. 967

8. 10 ER 24, 987

9. 19.49 25. #51

10. 1061* 26. ~s55

11. 1059* 27. 1QE1; 12, 1037- 2 8. - -1056 l

13. 1068* 29. 3059

14. lqlR* 30.- J049

15. 1059* '31. HZA i 16. 1054 o A calculated value was - used on April 10 through 15 due :to the -failure -

of the 'A' phase potential-transformer, which.was returned to service on the 15th.

L I

, - . , - - , y

OPERATING DATA REPORT DOCKET NO. 5D-) 5 4 UNIT Hope Creek DATE E jli/_9 2 COMPLETED BY V. Z.pbielski7lf-h TELEPHONE 1609) 339-350s OPERATING STATUS

1. Reporting Period Apri) 1991 Gross Hours in Report Period 21R

2. Currently Authorized Power Level (MWt) 3222 May Depend. Capacity (MWe-Het) 1021 Decign Electrical Rating (MWe-Net) 1067

3. Power Level to which restricted (if any) (MWe-Net) }Lqua

4. Reasons for restriction (if any)

This Yr To lioltth para cumulative

5. No. of hours reactor was critical 719.0 1581.8 31d41d 1

6. Reactor reserve shutdown hours L,Q L_Q hQ

7. Hours generator on line 719.0 2f5.4,_1 22J28tB

8. Unit reserve shutdown hours 0.0 0.0 hQ

9. Gross thermal energy generated 2.238.772 L493&q23 124.491.0~35 (MWH) jo .oss electrical energy 747.44Q 2.843.02Q AJ.195,514

tneratad (MWH)

! ' . t eleccrical energy generated 21Llfg 2_,718.091 JL J69.640 1 t.Jactor service factor 100.0 12,d 84.7

13. Reactor availability factor 100.0 22 d Ei,d

14. Unit service factor 100J 21d 83.4

15. Unit availability factor 10,0._q 21d _83 4,

16. Unit capacity factor (using MDC) 2M 90.8 FL2

17. Unit capacity factor iba 87.8 7_8.5 (Using Design MWe)

18. Unit torced outage latu L_Q L_Q 4.9

19. Shutdowns scheduled over next 6 months (type, date, & duration):

Refueling outage, 9/12/92, 60 days

20. If shutdown at end of report period, estimated date of start-up:

N/A l

l l

OPERATIt!G DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. iQ-JJ,i4 __

t UNIT lipAq__Qrag3 DATE 5/15/92 COMPLETED BY V. Zabi_olaki TELEPHONE L(LQc)1 3 39-3 606 s MONTil ApJl.1J 1992

- 1 METilOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE- S= SCHEDULED (HOURS) (1) POWER (2) ACTION / COMMENTS 2 4/21 F 0 A S 'B' Recirculation Pump Trip 3 4/25 F 0 A 5 Repairs made to 'B' Recirculation Motor / Generator Set I _.

Summary 1

.s REFUELING INFORMATION DOCKET NO. 50-354 UNIT Hone Crqek DATE 5/15/92 COMPLETED BY E. Hollinasworth TELEPHONE (609) 339-1051 MONTH April 1992

1. Refueling information has changed from last month:

Yes No X

2. Scheduled date for next refueling: 1412/12

3. Scheduled date for restart following refueling: 11/11/92

4. A. Will Technical Specification changes or other licenso amendments be required?

Yes No X B. Has the reload fuel design been reviewed by the Station Operating Review Committee?

Yes No X ,

If no, when is it scheduled? not scheduled (on or prior to 7/24/92)

5. Scheduled date(s) for submitting proposed licensing action: EfA

6. Important licensing considerations associated with refueling:

- Same fresh fuel as current cycle: no new considerations

7. Number of Fuel Assemblies:

A. Tncore 764 B. in Spent Fuel Storage (prior to refueling) 253 C. In Spent Fuel Storage (after refueling) 1008

8. Present licensed' spent. fuel storage capacity: 4006 Future spent fuel storage capacity: 3006

9. Date of last refueling that can be discharged 11/4, 2013 to spent fuel pool assuming the present. (EOC16) licensed capacity:

(does not allow for full-core offload).

.. -.. -...., . . - . . - - - - . . . , , , . . . . - - . . - - . . . ~

4 (*

,~

HOPE CREEK GENERATING: STATION  :

MONTHLY OPERATING

SUMMARY

April 1992 Hope Creek entored-the month of April at'approximately 100% power.

On April 21, the 'B' Recirculation Pump tripped, causing a runback. The 'B' Recirculation Motor / Generator Set was repaired on April 25 and power wan then returned to'approximately-100%-

power. On April 30,-the plant completed its 44th day of continuous power operation.. .

+

F t

b

, , , , 4 - , . . . , ,, N y

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION APRIL 1992 3

.~

Thc following items 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.

The 10CFR50.59 Safety Evaluations showed that these-items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations-

, determined that no unreviewed safety or_ environmental questions are involved.

k 1

- =____:_.-.-.- - --

.- 1 1

QCE Descriotion of Safety, Evaluation 4EC-3224 This DCP added three 30 amp single pole circuit  !

breakers in a 120 volt AC power distribution panel and re arranged branch circuits feeding space i heaters in a motor control center. This allows the power feed for the Ultrasonic Rosin Cleaner Panel to be-re-routed to improve the voltage at the panel and enhance the efficiency of the Ultraconic Rosin Cleaner.

No Unreviewed Safety Questions were involved because this DCP involves only systems,-nquipment, and components that are non-safety related. Also, all of the materials that were used are compatible with previously used materials.

4EC-3251 This DCP installed two diodes, in series, parallel to the coils of the Intermediate Range Monitor /-

Source Range Monitor alarm relays.. The diodes were installed for noise-suppression.

The diodes do not have any controlling functionn nor do they affect the alarms or the Intermediate

-or Source Range Monitors. Therefore, no Unroviewed Safety Caestions are involved with this DCP.

4EC-3341/02 This DCP provided-permanent' rigging points'to allow the removal and reinstallation of Filtration, Recirculation, and Ventilation System backdraft isolation dampers in the Reactor Building.

This DCP does not involve work on-egalpment important to safety or items interfacing with equipment important to safety. - Therefore, no Unreviewed Safety Question are involved with this DCP.

l

l DGE Qescription pf Safety Evalustignj .

4EC-3342 During_the Electrical Distribution Systems Functional Inspection, it-was' determined that the slow-bus transfer' scheme for the Class 1E'4KV buses -'

could possibly~ transfer the loads'from the normal infeed to the-alternate _infeed'without stripping.

the loads. _This could subject the motors on=the-4KV-buses to_overvoltage_ transients.- In addition, loads that had been sequenced-onto a.4KV bus-by the Loss of Coolant Accident sequencer and'were then.

stripped during a-bus transfer might not be ,

resequenced onto the bus:after the alternate infeed closed. This DCP adds,a time delay-into-the closing circuit of thecalternate.infeed breaker'in:

the slow and dead bus-transfer-schemes to prevent the alternate infeed from closing too soon and to enable the sequencer to reset after;a bus transfer.

The additional dead bus' time ensures that the motors-are notroubjected to=overvoltage transients. .

when the alternato infeedEcloses. The additional:

dead bus time also ensures that:the sequencer:

renate, allowingLthe loads to be re-sequenced onto-the bus. The time delay also,increasescthe reliability of the syetem. .Therefore, no Unreviewed Safety-Question are involved with--this  ;

DCP.

l l

Procedure Revision DAqqrintipn of Safety EvalMt1RD NC.NA-AP.ZZ-0002(Q) This new procedure reflects title changes Rev 0 and reporting relationships within the Nuclear Department.

The scope of tai 9 new procedure is limited to describing .* oles, responsibilities, and reporting relationships of key Nuclear Department personnel. This procedure-does not change the design, function, or operacion of any structures, ayutems,'or components; therefore, there are no Unreviewed Safety Questions ana>ciated with this ncy procedure.

NC.NA-AP.ZZ-0013(Q) This procedure revision identifies that Rev 1 temporary modifications made to operable components, systems, or structures-to support the-implementation of design changes, tests, and experiments are controlled by this procedure. It also states that space heaters and ventilation eguipment is to be controlled by this procedure. Additionally, this revision r:hangea some forms and part of the flowpath process.

This administrative procedure provides specific guidance for the implementation of the programs and processes described in the SAR. The proposed revision is in compliance with the SAR;_therefore, there are no Unreviewed Safety Questions associated with this new procedure.

NC.NA-AP.ZZ-0055(Q) This revision makes several changes to Rev 1 clarify the procedure as well as changes-that arc grammatical or editorial in nature.

This administrative procedure. enhances the administrative control of outage management. The implementation of this procedure provides cor.trols to ensure that .

outage activities are performed in l compliance with licercing requirements and suggested industry guidelines. 'rhe proposed revision is in compliance with the SAR; therefore, there are no Unreviewed Safety Questions associated with thir procedure revision.

- _ - _ - _ _ _ - _ _ _ _ - _ _ _ _ _ _ _