ML20206U157

Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With

ML20206U157
Person / Time
Site:	Hope Creek
Issue date:	04/30/1999
From:	Bezilla M, Ritzman R, Todd F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99233, NUDOCS 9905250073
Download: ML20206U157 (8)

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OPSEG Public Service , Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit ENf171999 LR-N99233 U. S. Nuclear Regulatory Commission' Document Control Desk Washington, DC 20555 Gentlemen:

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 April 1999 are being forwarded. Also being forwarded to you, pursuant to the requirements of 10CFR50.59(b), is the summary of changes, tests, and experiments that were implemented during April 1999.

Sincerely, Mark B. Bezilla General Manager -

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Hope Creek Operations RAR Attachments I

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INDEX NUMBER SECTION OF PAGES Operating Data R epo rt. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Month ly Ope rating S u m m a ry. . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . 1 Summary of Changes, Tests, and Experiments...... ...... ... ... ... ... ...... ... .. 4 1

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e DATE: 05/10/99

. COMPLETED BY: F.Todd TELEPHONE: (609) 339-1316 Reporting Period April 1999 OPERATING DATA REPORT Design Electrical Rating (MWe-Net)

Maximum Dependable Capacity (MWe-Net) 1031 Month Year-to-date Cumulative No. of hours reactor was critical 719 l1798 l 90927 l No. of hours generator was on line (service 719 1757 89367 hours) l Unit reserve shutdown hours 0 l0 l0 l l Not Electrical Enprgy (MWH) 696242 l1770839 l 90368360 l 2

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UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF OORRECTIVE ACTION /

F= FORCED (HOURS) (1)_ SHUTTING COMMENT S= SCHEDULED DOWN THE i REACTOR (2) i (1) Reason (2) Method A- Equipment Failure (Explain) 1 - Manual  !

B - Maintenance or Test 2 - Manual Trip / Scram l C - Refueling 3 - Automatic Trip / Scram )

D - Regulatory Restriction 4 - Continuation l E - Operator Training / License Examination 5 - Other (Explain) j F - Administrative  ;

G - Operational Error (Explain)  !

H - Other l

DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 05/10/99 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445 i

Summary Of Monthly Operating Experience

. At the beginning of the month of April, Hope Creek was increasing power subsequent to the refueling outage. Hope Creek reached 100% power on April 6.

. At the end of the month, Hope Creek had been online for 30 days.

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. DOCKET NO.:50-354 UNIT: Hope Creek DATE:05/10/99 COMPLETED BY:R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE liOPE CREEK GENERATING STATION MONTH April 1999 The following items completed during April 1999 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

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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.

Design Changes Summary of Safety Evaluations There were no repostable changes in this category implemented during April 1999.

Temporary Modifications Summary of Safety Evaluations There were no reportable changes in this category implemented during April 1999.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS .

FOR THE HOPE CREEK GENERATING STATION - Cont'd Procedures Summary of Safety Evaluations There were no reportable changes in this category implemented during April 1999.

UFSAR Change Notices Summary of Safety Evaluations UFSAR Change Notice 98-35, Safety and Turbine Auxiliaries Cooling System  ;

Required Flow Rates and Heat Loads. This UFSAR change notice revised the heat i loads and the minimum flow requirements for Safety Auxiliaries cooling system  !

components. These changes were based on a revised calculation and do not impact j the nominal design flow rates or any operation or maintenance procedures.  !

The Loss of Coolant Accident and the Loss of Power Accident are the initiating events j associated with this proposal. This change notice does not adversely impact either the consequences or the probability of these accidents, but ensures that sufficient flow is delivered to the components to ensure that the required heat loads can be removed.  ;

The calculation evaluates system and component response during normal and

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abnormal system operation to ensure that the operating parameters of the interfacing components would not exceed the vendor recommended limits. This UFSAR change does not increase the possibility or consequences of any accident or malfunction, does ,

not reduce the margin of safety, and; therefore, does not involve an Unreviewed Safety  !

Question. j i

UFSAR Change Notice 99-07, Radiation Monitoring System Transfer Calibration Sources. This UFSAR change notice revises the description of the Radiation Monitoring System radiation detector calibration methods. The UFSAR change notice allows the use of transfer calibration' sources that were not supplied by the vendor. The use of these transfer calibration sources did not affect the radiation monitor setpoints, logic, automatic actions, or any other function. This UFSAR change does not increase '

the possibility or consequences of any accident or malfunction, does not reduce the ,

margin of safety, and; therefore, does not involve an Unreviewed Safety Question.

UFSAR Change Notice 99-09, Procurement Assessment Manager's Change in Reporting Relationship. This UFSR change notice is an administrative change that revises the reporting chain for the Procurement Assessment Manager. The Procurement Assessment Manager reported to the Manager- Nuclear Procurement and Materials Management. The Procurement Assessment Manager will now report to the Director- Nuclear Business Support. This change will give the quality functions performed by. Procurement Assessment increased visibility. The existing functions and responsibilities will be maintained; only the reporting relationships changed. This change is administrative in nature, and does not introduce any new elements to the Procurement Assessment departmeret

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION - Cent'd Because the change is administrative in nature, this UFSAR change does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and; therefore, does not involve an Unreviewed Safety Question.

UFSAR Change Notice 99-19, Feedwater Zinc and Iron Injection to Control Radiation Field Buildup. This UFSAR change notice revises the Reactor Coolant System target value for zinc injection. These target values are consistent with EPRI recommendations. The change notice also revises the description of feedwater iron injection as a method to control ex-core radiation fields.

This change notice allows for the control of fuel performance within guidelines based on industry experience and will not affect the assumptions and conclusions of the design basis accident evaluations. Controlling the injection rates for iron and zinc as described in this UFSAR change notice and 10CFR50.59 Safety Evaluation does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and; therefore, does not involve an Unreviewed Safety Question.

UFSA.R Change Notice 99-23, Controlling Condenser Vacuum for Low Pressure Turbine Rotor Warm-Up. This UFSAR change notice allows for the controlling of condenser vacuum for Low Pressure Turbine Rotor warm-up. The purpose of this pre-warming is to achieve and maintain a minimum temperature of 100 degrees F at the wheel keyways. This lessens the probability of turbine wheel burst due to brittle fracture.

Neither the mechanical vacuum pumps, nor any other components in the Condenser Air .

Removal system are important to safety. In addition, during the pre-warming, the operation of the mechanical vacuum pump will be under the control of the operators.

Therefore, this UFSAR change notice and 10CFR50.59 Safety Evaluation does not

. increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and; therefore, does not involve an Unreviewed Safety Question.

Other Summary of Safety Evaluations PIRS 981223156, incorrect Relay in Fuel Oil Transfer Control Circuit. This safety evaluation was written to address an operable but degraded resolution for an incorrect relay in the fuel oil transfer control circuit. The Diesel Fuel Oil Storage and Transfer system consists of a day tank, two storage tanks, tow dedicated transfer pumps, and the associated controls and alarms. During normal operation, a pump starts on a low level signal. As the tank level increases,'a high level signal is received, and the pump stops. As tank level decrease, the other pump cycles to make up the level. If the low l

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION - Cant'd l

I low level se'tpoint is reached, both pumps operate until the high high setpoint is l reached. 4 This safety evaluation was written to address a situation where, due to the installation of an incorrect relay, neither pump started when the low setpoint was reached, but both pumps operated between the low low setpoint and the high high setpoint. This dual pump operation did not affect the ability to transfer oil from the storage tanks to the day tank under any postulated accident or system demand. Therefore, this operable but degraded resolution does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and; therefore, does not involve an Unreviewed Safety Question.

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