ML20006F109

Monthly Operating Rept for Jan 1990 for Hope Creek Generating Station,Unit 1.W/900215 Ltr

ML20006F109
Person / Time
Site:	Hope Creek
Issue date:	01/31/1990
From:	Hagan J, Loeper S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HSE-90-027, HSE-90-27, NUDOCS 9002270169
Download: ML20006F109 (13)

Text

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6 O PSEG i Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 l

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l' February 15, 1990 HSE-90-027 j p

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.U. S. Nuclear Regulatory Commission i Document control Desk .t

. Washington, DC 20555

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 January are being forwarded to you with the summary of changes, tests, and experiments for January 1990 t pursuant to the requirements of 10CFR50.59(b). .

Sincerehy yours, j

' Hagbnj hM 'i J. "J Geberal Manager - "

Hope Creek Operations

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. . , .Monthly l. Opera ting Summary . . . . . . . . . . . . . '. . . . . . . . . . . . . . . . .

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"~t Summary of.LCh'ahges,!Terts, and Experiments........'..... .

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _50-354 UNIT - Hope Creek __

DATE 2/15/90 4

COMPLETED BY __S._LLoeper TELEPHONE __(609) 339-5257 MONTH- _ January 1990 +

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 4 1 0 17 1033 2: 0 18 1049  !

3 13 __ 19 897 4 -944 20 1.041 5 1019 21 1004  ;

6 23 22 1_067 7 ~0 23 996

-8' O 24 __1001 9 0 25 1008  ;

10 ~ 312 26 1049 ,

11 984 27 1003 12 942 28 979 13' 1010 29 1019 -

14' 1052 13 0 1011 -

15- -1028 31 1008 16 995

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C C l p , OPERATING DATA REPORT' DOCKET No.- 50-354 '

UNIT. _ Hope Creek ,

t' DATE _2/15/90 __

COMPLETED BY S.__Loeper TELEPHONE _(609) 339-5257 3 OPERATING STATUS ,

1. , REPORTING PERIOD January _._1990_ GROSS HOURS IN REPORTING PERIOD 744_

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'2.: . CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEPEND;-CAPACITY (MWe-Net) 1031 ,

DESIGN ELECTRICAL RATING (MWe-Net) 1067-  ;

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3. POWERELEVEL"TO WHICH RESTRICTED (IF ANY)'(MWe-Net) None

'4. REASONS'FOR RESTRICTION (IF ANY)  !

THIS YR TO _

MONTH DATE CUMULATIV3, 5.- NO. OF HOURS REACTOR WAS CRITICAL 606.2 _ 606.2 __22,'367.7 l..

> '6 REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

, '7. HOURS GENERATOR ON LINE 585.5 585.5 _21,936.7 8 UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0  ;

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9. GROSS THERMAL ENERGY GENERATED .

(MWH) _1,797,350 1~797,350

, 68,753,726 q

10. : GROSS ELECTRICAL ENERGY

GENERATED-(MWH) 588,220 588.220_ _22,744,483_

11. NET ELECTRICAL ENERGY GENERATED

.(MWH) 560,891 1150,891___ -__21,717,440

12. REACTOR SERVICE FACTOR 81.5 81.5 81.8

13. ~ REACTOR AVAILABILITY FACTOR 81.5 81.5 81.8

14. UNIT SERVICE FACTOR 78.7 78.7 80.u2

15. ' UNIT AVAILABILITY FACTOR 78.7 78.7 80.2 ,

11 6 . UNIT CAPACITY FACTOR (Using MDC) 73.1 73.1 77.1-17; UNIT CAPACITY FACTOR

.(Using Design MWe) 70.7 70.7 74.5 1

18. UNIT FORCED OUTAGE RATE 21.3 21.3 6,1 L "19 . ' SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):

None Scheduled

20. .IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP: 1/3/90 N/A

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, OPERATING DATA REPORT UNIT' SHUTDOWNS AND POWER REDUCTIONF {

. DOCKET NO. _50-354 UNIT _ Hope Creek _

f DATE __2/15/90 _,

COMPLETED BY S.Loeper REPORT HONTH January. 1990 TELEPHONE (609) '339-5257  :

NETHOD OF SHUTTING ,

DOWN THE TYPE REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) (1) ' POWER (2) COMMENTS 1- 12/30 F 62.5 A 3 FAILURE OF LIMIT' l SWITCH DURING TESTING'OF THE MAIN TURBINE THRUST BEARING WEAR DETECTOR -

(LER 89-026) ]

2 1/6 F 96~.0 A/G 3 TURBINE TRIP'FROM y MOISTURE SEPERATOR HIGH LEVEL DURING TURBINE TESTING (LER 90-001) '

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SUMMARY

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, REFUELING INFORMATION COMPLETED BY: _Chris Brennan DOCKET NO: 50-354 UNIT NAME: Hope Creek Unit 1 f DATE: _2/15/90 TELEPHONE: (609) 339-3193 s, EXTENSION: N/A Month February _._19 90 i

- 1. ' Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: 01/19/91 t

3. Scheduled date for restart following refueling _03/05/91_  !

4. A) Will Technical. Specification changes or other license 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? 02/01/91

5. Scheduled date(s) for submitting proposed licensing netion: N/A 6.. Important licensing considerations associated with refueling:

-Amendment 34 to the Hope Creek Tech Specs allows the.. cycle

-specific operatina limits to be incorporated into the CORE

-OPERATING LIMITS REPORT; a submittal is therefore not required.

7. Number of Fuel Assemblies:

Al-Incore 764 3):I0 Mpent Fuel Storage (prior to refueling) _496 '

C) In Sper.t Fuel Storage (after refueling) 744

- 8. Present licensontspent fuel storage c, capacity: 1290

' i- Future.epent fuel storage capacity: 4006

9. Dste of last refueling that can be discharged to spent f741 pool assuming

the present licensed c.apacity

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, HOPE CREEK GENERATING STATION o , MONTHLY OPERATING

SUMMARY

JANUARY 1990 e

i Hope Creek entered the month of January in cold shutdown repairing a weld defect on a recirculation instrument line. On January 2 preparations were made to restart the reactor and on January 3 the reactor achieved criticality. On January 4 the plant reached 100%

power. On January 5 power was reduced to 95% of generator cepacity because the 2C Drain Cooler was out of service. On January 6 during a Main Turbine Combined Intermediate Valve (CIV) l- Surveillance Test, the plant automatically shutdown due to a high level in the Moisture Separator. The high level was caused by a conbination of the Moisture Separator Level Controllers not being optimally tuned and the cycling of a CIV prior to the stabilization i of moisture separator level after cycling a previous CIV. The high level caused a turbine trip which in turn caused a reactor scram.

On January 9, the reactor achieved criticality and on January 11, the plant reached 95% of generator capacity (2C Drain Cooler out of service). On January 31, the plant remained at 95% and completed l sts 21st day of continuous power operation.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS.

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,T.he following Design Change Packages (DCP's) 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 evai.uated 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 DCP's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. The DCP's 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.

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Description:

__of_Desian_ Chance Packace

'A 4HC-0123 This DCP installed a radiation shielding door at the entrance to the Transversing In-core Probe Room,.inside the existing door. Lifting lugs were also added-to facilitate.the installation and maintenance of the door. The radiation shielding' door will maintain radiation at an acceptable level outside of the Transversing In-core Probe Room Door.

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4HM-0219 This DCP replaced a flow meter and a' flow 3

w transducer.in the Oily Waste System with a magnetic inductive flowmeter and signal p converter. This changeout'will reduce the f , failure rate previously caused by blockage and binding in the original impeller driven

, transducer.

4HM-0376. This DCP iristalled piping from the Steam Supply of the Solid Radwaste Electric Auxiliary Boiler to the Nitrogen Vaporizer in.the Containment Atmosphere control System. This will enable the Plant Heating Auxiliary Boiler to be removed from service to allow for summer lay-up and outage maintenance.

4HM-0524 This DCP removed the Chlorine Analyzer and installed the new analyzer in a, temperature controlled cabinet-adjacent to the Service i Water Chlorination Building. .The analyzer will allow for better control and monitoring of-the Service Water Hypochlorination Injection!

System, k%i i

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,, . The following Temporary Modification Requests'(THR's) have been  ;

. - evaluated to determine: i 1

- 1) (if the. probability of: occurrence'or the consequences of an I W, 4 ~ accident or malfunction of equipment important to safety previously evaluated in thefsafety analysis report may be increased; or- f z

2)- if-a possibility for'an accident or malfunction of a l different type than any. evaluated previously in the safety l D "' 1 analysis-report may be created; or  !

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..3) -if the': margin of safety as defined in the basis for any '

, cv " technical spacification is reduced. ,

t LThe-TMR's did not create a new safety hazard to the plant nor did-  !

."' i they. affect theisafe shutdown of the reactor. The TMR's did not.  !

'i 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.  :

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1 i :Refety Evgluation Description o[ Tenporary Modi (1 cation Request

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89-173 This THR nodified the indicating circuit for a computer point to change it from an average temperature of the Cooling Tower Basin to the temperature indicated by the "A" Cooling Tower ,

Basin Water _ Temperature Element. This THR was ;

required because the averaging circuit was not indicating correctly due to different. lengths ,

-of cable leading from each of the temperature elements.

• 90-001 This TMR removed the overload heaters from a breaker for the Residual Heat Removal Outboard .

Shutdown Cooling Isolation Valve.- This will prevent the valve from opening during an

• Appendix R fire.  !

^90-002 This,THR temoved the overload heaters from breakers associated with the Reactor Water ,

Cleanup Discharge to Condenser Valve and the  !

Reactor-Water Cleanup' Discharge to Equipment Drain-Valve. The overload heaters were removed to prevent the valves from opening during an .

Appendix R fire.

'90-003' This TMR jumpered the High/High Level Trip from l the #2 "A", "B", and "C" Feedwater Heaters.

Spurious High Level signals have been observed at low power levels due to inleakage in the -

reference legs. .This THR was installed only.

1 until the level signals stabilized.

i L 006 This THR removed the input sign 11 from a  ;

L defective reed switch for Coc'.rol Rod 84-11.

• The input signal was removed by modifying the i Rod Position Information System Probe  ;

Multiplexer Card to electrically disconnect the input.90-008 This TMR jumpered the High/High Level Trip from ,

the #2 "A", "B", and "C" Feedwater Heaters. '

Spurious High Level signals have been observed

, at low power levels due to inleakage in the

,,: reference legs. This TMR was installed only -

/ until the level signals stabilized.90-009 This TMR removed the input signals from 6 defective reed switches for Control Rod 34-2".

The input signal was removed by modifying the i Red Position Information System Probe

, Multiplexer Card to electrically disconnect the input.

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Et[9h Evaluation ~ Descripjjon p.f Temporary Hodification Request 90-010 This TM7c xemoved the overload heaters. f rom breakers associated,with the Reactor Water Cleanup Discharge to Condenser Valve and the Reactor Water Cleanup Discharge to Equipment Drain Valve. The overload heaters were removed to prevent the valves from opening during an Appendix R fire.90-013 ThisLTMR installed a jumper in the Breath-Air Compressor Control Panel. The jumper bypasses the Breathing Air System abnormal condition inputs to the Breathing Air System Trouble Annunciator in the Control Room. Annunciator is still available at the local panel.

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