ML20205R590

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

ML20205R590
Person / Time
Site:	Hope Creek
Issue date:	03/31/1999
From:	Bezilla M, Ritzman R, Todd F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99198, NUDOCS 9904230141
Download: ML20205R590 (8)

Text

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.OPSEG Pubhc Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nucisar Business Unit l

APR151999  ;

LR-N99198 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

MONTHLY OPERATING REPORT I 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 March 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 March 1999.

Sinperely, l TcLin.BfElLLA Ma B. Bezilla General Manager -

Hope Creek Operations RAR Attachments l t l C Distribution ib l

9904230141 99033134 PDR ADOCK O a

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95 2168 REV 694

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I NUMBER SECTION OF PAGES O pe rati n g D a ta Repo rt. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Monthly Operating S u mma ry.. . . .. .... . . . .. . . . .... .. ... .. .. .. . . . . ... . . ... . .. . .. .. . . . . . . . ... . 1 Summary of Changes, Tests, and Experiments... ............................... 4

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DATE: 04/12/99 COMPLETED BY: F.Todd i -

TELEPHONE: (609) 339-1316 i

l Reporting Period March 1999 l

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 45 l1079 l 90208 l No. of hours generator was on line (service 7 1038 88648 hours)

Unit reserve shutdown hours 0 l0 l0 l Net Electrical Energy (MWH) 49 l 1074597 l 89672118 l UNIT SHUTOOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE ACTION /

F= FORCED (HOURS) (1) SHUTTING COMMENT S= SCHEDULED DOWN THE REACTOR (2) 1 3/1/99 S 737 C 1 Refuel Outage 3/31/99 (1) Reason (2) Method A- Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip / Scram C - Refueling 3 - Automatic Trip / Scram D - Regulatory Restriction 4 - Continuation E - Operator Training / License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain) l H - Other r

r DOCKET NO.: 50-354 <

l UNIT: Hope Creek l DATE: 04/12/99 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445 Summary Of Monthly Operating Experience

. Hope Creek entered the month of March in the refueling outage.

. The reactor went critical on March 31, and the plant was placed on line for 7 l hours to conduct turbine testing. l l

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DOCKET NO.:50-354 UNIT: Hope Creek DATE:04/12/99 COMPLETED BY:R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH March 1999 I The following items completed during March 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 l

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 i reduced.

i 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 l environmentalimpact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

l Design Changes Summary of Safety Evaluations 4EC-3449, Packages 9 and 10, Replace Selected Carbon Steel Piping and Fittings l- with Chromium Alloy Due to Flow Accelerated Corrosion. This design change replaces various carbon steel piping and fittings with a chromium alloy. The safety evaluation address this replacement in the following systems / components: Feedwater, Condensate, Sealing Steam, Main Steam, Extraction Steam, Condenser Air Removal, Reactor Feed Pump Turbine steam, Moisture Separator Drains, Heater Drains, and Plant Heating.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS

,, FOR THE HOPE CREEK GENERATING STATION - Cont'd

. The design requirements for the replacement piping are not changed and the upgraded piping material meets or exceeds the design requirements of the original piping material specifications. Pipe stresses and support loeds will remain in conformance with their applicable code or design basis allowables.

The safety evaluation is required to update design drawings to reflect the new piping material. This design change will result in increased reliability of the affected piping and 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.

4EC-3538, Packages 1,5,6,7, and 8 WR and CORE Spray Suction Strainers.

This design change installs Emergency Core Cooling System suction strainers in the suppression pool with new strainers for the Residual Heat Removal (RHR) and Core Spray (CS) pumps.

This design change replaces the existing bolt-on Zurn strainers with larger Performance Contracting, Inc. (PCI) stacked disk strainers. The new larger PCI suction strainer provides increased surface area and thus increases the flow area of the strainer. The new strainers meet the same function and flow capacity of the plant systems. This design 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.

4EC-3675, Underwater Light Replacement for Spent Fuel Pool, Reactor Cavity, and Reactor Vessel. This design change modifies six underwater lights in the Spent Fuel Pool by adding ballast and replacing the halogen bulbs with high pressure sodium bulbs. This design change also provides four new high pressure sodium light fixtures in the Reactor Cavity and four in the Reactor Vessel. These lights will only be installed during refueling.

The underwater lights are non-safety related and do not affect the function of any other equipment. This design change does not affect any assumptions previously made in evaluating the radiological consequences of accidents identified in the SAR, does not affect any fission product barriers, and odes not restrict access to vital areas or otherwise impede actions to mitigate the consequences of an accident. Therefore, this

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

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS

,, FOR THE HOPE CREEK GENERATING STATION - Cont'd

, Temporary Modifications Summary of Safety Evaluations TMR 99-04, Defeat Condensate Transfer Flow Switch. This temporary modification lifted leads to defeat the Condensate Transfer Flow Switch. This prevented the flow switch from automatically stopping the Condensate Transfer Pumps on low flow conditions. The pumps were protected from damage due to dead head operation by minimum flow recirculation line back to the Condensate Storage Tank. The low low flow trip is controlled by another switch and remained in service.

The Condensate Transfer Pumps are non-safety related and do not provide accident mitigation functions. Compensatory measures were in place for the operators to trip the pumps, if needed. Therefore, this temporary modification did not increase the possibility or consequences of any accident or malfunction, did not reduce the margin of safety, and did not involve an Unreviewed Safety Question.

TMR 99-06, "A" and "B" Control Rod Drive Pump Monitoring for Low Suction Pressure. This temporary modification installed two pressure transmitters on the suction side of each of the "A" and "B" Control Rod Drive Pumps. The temporary modification also installed a pressure transmitter on the high side of a differential pressure switch located at the common suction side of the pump suction filters. These pressure transmitters are being installed to gather data to assist in determining the l l cause of spurious Control Rod Drive Pump trips. ,

The Control Rod Drive Pumps and associated instrumentation are non-safety related.

The installation of this temporary modification does not impact the ability to safely shutdown the plant. The installation of these pressure transmitters 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.

Procedures Summary of Safety Evaluations There were no reportable changes in this category implemented during March 1999.

I UFSAR Change Notices Summary of Safety Evaluations UFSAR Change Notice HCN 99-006, Chemistry Department Functional Organization. This UFSAR change notice addresses the functional reorganization of the Salem and Hope Creek Chemistry departments. The existing functions and responsibilities will be maintained; however, the organization titles and reporting relationships changed. This change is administrative in nature, and does not introduce any new elements to the Chemistry department.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS

,, FOR THE HOPE CREEK GENERATING STATION - Cont'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 HCN 99-015, Mechanical Vacuum Pump Operation and' Control Rod Drop Accident Analysis Reconstitution. The safety evaluation associated with this UFSAR change notice provides a radiological assessment for a control rod drop accident while using of the mechanical vacuum pumps during startup at power levels up to 5%. The mechanical vacuum pump trip function is non-safety related; therefore, this safety evaluation assumed that the vacuum pumps would not trip. The radiological assessment updated the accident analysis section and corrected an internal inconsistency within the UFSAR.

The design calculation referenced in the safety evaluation demonstrates that the radiological consequences of a control rod drop accident while the mechanical vacuum pumps are in service at power levels up to 5% are well within the 10CFR100 guidelines.

Additionally, the design calculation demonstrated that the radiological consequences of the postulated event are within the GDC 19 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.

4 UFSAR Change Notice HCN 99-016, Elimination of Loose Parts Monitoring l System Reporting Requirements. This UFSAR change notice deletes the NRC )

reporting requirements associated with the Loose Parts Monitoring System. This  !

change is limiting to the reporting requirements, and does not impact the way in which the Loose Parts Monitoring System, or any of its support or supported systerns are ,

operated, tested, or maintained.

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.