ML20217A626

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Revised Monthly Operating Rept for Jul 1997 for Hope Creek Generating Station,Unit 1
ML20217A626
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 07/31/1997
From: Ritzman R
Public Service Enterprise Group
To:
Shared Package
ML20217A146 List:
References
NUDOCS 9709190250
Download: ML20217A626 (3)


Text

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DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 09/04/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH AUGUST 1997 The following items completed during July 1997 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.

Desian Chanaes Su===ry of Safety EvaluaticDA SEC-0008, Pkg. 1, Hand Geometry Access Project. This design change installs a hand geometry reader system in the Security Center, enables the elimination of the badge issue and retrieval from the Security Center, and relocates the accountability computer terminals.

This design change was reviewed with regard to the Design Basis Security Threat. This design change was determined not to contribute to an increased vulnerability to a design basis threat. The use of hand ceometry is a program enhancement in that it reduces the possibility of human error in badge issuance and improves Security Center lebby management.

9709190250 970915 PDR ADOCK 05000354-R PDR

This design change does not negatively impact any accident response. This design change does not create or increase the probability or consequences of either an accident or a malfunction of equipment important to safety, or reduce the margin of safety as defined in the basis for any Technical Specification. Therefore, this design change does not involve an Unreviewed Safety Question.

Temporary Modifications S"==srv of Safety Evaluations TNR 97-008, Temporary Removal of Low Flow Switch from Control Circuit for the Feedwater Heater Room Unit Cooler (1A-VH133).

This temporary change disables the low flow trip signal by de-terminating wires to a flow switch. The low flow signal trips the unit cooler for the 3A, 4A, and 5A feedwater heaters. The unit cooler's function le to maintain ambient room temperature below 120 degrees F. The unit cooler is not safety related.

The turbine building ventilation system, including the feedwater heater room unit coolers, is not safety related. This temporary modification allows the unit cooler to perform its design function of maintaining ambient room temperature below 120 degrees F. There are no design basis accidents or credible failures associated with the failure of the feedwater heater room unit coolers. This temporary modification does not create or increase the probability or consequences of either an accident or a malfunction of equipment important to safety, or reduce the margin of safety as defined in the basis for any Technical Specification. Therefore, this temporary modification does not involve an Unreviewed Safety Question.

MFSAR Changp___ Notices Summary of Safety Eygly_alLgna There were no changes in this category implemented during July 1997 Erocedures Summary of Safety Evaluations HC.CH SO.AK-0005(Q), Rev. 1B, Condensate Domineralizer System Niscellaneous Operations. This procedure revision changes the normal position of a valve that provides isolation for the water that is supplied from the condensate Storage and Transfer system to the Condensate Demineralizer system. The valve position is being changed from normally open to closed. The valve is being closed to isolate the Condensate Storage and Transfer system from the polisher vessels and the regeneration cell subsystem.

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The Condensate Demineralizer system has no safety related functions and is not required to be operable following an accident. The failure of the Condensate Demineralizer system does not compromise any safety related system or component, or prevent the safe shutdown of the plant. There are no automatic or manual functions of the condensate Polisher system that affect the systems and failures analyzed in the Accident Analysis portion of the UFSAR. Therefore, this procedure revision does not involve an Unreviewed Safety Question.

PLeliciency Reports Summary of Safety Evaluati_qng There were no changes in this category implemented during July 1997.

Other Summary of Safety Evaluation There were no changes in this category implemented during July 1997.

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