ML20147F611

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Revised MOR for Jan 1997 for Hope Creek Generating Station
ML20147F611
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 01/31/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML20147F602 List:
References
NUDOCS 9703260274
Download: ML20147F611 (4)
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DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 03/07/97 COMPLETED BY: L. Keplev TELEPHONE: (609) 339-1106

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE IIOPE CREEK GENERATING STATION MONTH FEBRUARY 1997 The following items completed during January 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 I 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 efe shutdown of the reactor. These items did not change the plant efIluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Desien Channes Summary of Safety Evaluations Replacement of Air-Operated Valves in the Safety Auxiliary Cooling System (SACS),4EC-03612 Pkg. 5. The Standby Diesel Generator (SDG) room cooler water supply valves in the SACS were replacul. The previous valves were carbon steel air actuated flexible wedge gate valves. The replacement valves are stainless steel air actuated ball valves which are more suitable to the application. UFSAR Figure 9.2-5 was changed to show the type and material of the replacement valves and actuators. UFSAR Table 3.9-18 was changed to show the valve / actuator replacement type. This replacement ,

does not change the function of the valves or the function of the affected systems. The change does not alter the ability of the SACS, the SDG Room Recirculation System, or the SDGs to perform their intended safety function. The affected systems will function in accordance with the original design and licensing basis of the plant.

Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

Replacement of Air-Operated Valves in the Safety Auxiliaries Cooling System (SACS),4EC-3612, Pkgs 10 and 12. The Residual Heat Removal (RHR) pump room cooler water supply valves in the SACS were replaced. The previous valves were carbon stect air actuated flexible-wedge gate valves. The replacement valves are stainless steel air actuated ball valves which are more suitable to the application. UFSAR Figure 9.2-4 was changed to show the type and material of the replacement valves / actuators. UFSAR Table

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3.9-18 was changed to show the valve / actuator replacement type. This replacement does '

. not change the fimction of the valves or the function of the affected systems. The change does not alter the ability of the SACS, the Equipment Area Cooling System (EACS), or i the RHR pump room unit coolers to perform their intended safety functions. The affected systems will function in accordance with the original design and licensing basis of the plant.

t L Therefore, this design change does not increase the probability or consequences of an i

accident previously described in the UFSAR and does not involve an Unreviewed Safety

Question.

Replacement of Air-Operated Valves in the Safety Auxiliaries Cooling System  ;

(SACS), 4EC-3612, Pkg 26. The Core Spray (CS) pump room cooler water supply

. valves in the SACS were replaced. The previous valves were carbon steel air actuated j flexible-wedge gate valves. The replacement valves are stainless steel air actuated ball valves which are more suitable to the application. UFSAR Figure 9.2-4 was changed to show the type and material of the replacement valves / actuators. UFSAR Table 3.9-18
was changed to show the valve / actuator replacement type. This replacement does not
change the function of the valves or the function of the affected systems. The change does not altes the ability of the SACS, the Equipment Area Cooling System (EACS), or the CS pump room unit coolers to perform their mtended safety functions. The affected systems will function in accordance with the original design and licensing basis of the plant. 1 I

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Therefore, this design change does not increase the probability or consequences of an
_ accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

i Replacement of Moisture Separators on Primary Containment Instrument Gas

. (PCIG) Compressor Skid 1A-S-934,4EC-03274 Pkg 4. Four (4) moisture separators i were replaced on the PCIG skids (two separators per sk'd). The new separators were i fabricated to meet PSE&G's Design / Detail Specification for moisture separators in the

! PCIG system, but could not be purchased with the appropriata ASME Section III N-symbol affixed as originally supphed. The installation of a 'honJN-stamped" component j to replace an 'N-stamped" component is a change to the facility as originally licensed as

described in Sections 3.2.2 and 9.3.6.3 of the UFSAR. The change in size, material and l
internal configuration of the moisture separators does not alter the design bases of the PCIG system, nor are the design parameters or the description of the PCIG system altered.

However, the PCIG skid is listed as a safety related system in the UFSAR. The 2 compliance with the ASME 'N" stamped components ensures design margin. The intent i of the 'N" stamp safety related designation will be satisfied by compliance with NRC i Generic Letter 89-09 requirements, and ASME design criteria in both Section III and i l VIII. The new replacement separators are superior in design and fabrication to the 1 original components. This replacement does not impact the design basis requirements for  ;

j the Main Steam Isolation Valve Sealing system or the 10CFR100 offsite dose. l Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety

[ Question.

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. UFSAR Change Notices Summary of Safety Evaluations

" UFSAR Change Notice 96-141, Process Sampling System. This change revised or removed information pertaining to the Process Sampling System. This system is not safety related. This change does not affect any information pertaining to the Post Accident Sampling System (PASS). This change does not reduce the required sampling or analysis of any sample governed by a)plicable Technical Specifications, Standard Review Plans, NUREGs, or Regulatory Guic.es. This changes does not alter the ability to obtain PASS samples for the purpose of evaluating core damage or offsite dose calculations.

i Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety

! Question.

UFSAR Change Notice 96-142, Hope Creek UFSAR Organization Update -

Chemistry and Projects to Operations. These changes enhance the existing Hope Creek organization, but do not affect the programs described in the UFSAR. Specifically, ,

the changes streamline the organization. The Chemistry Superintendent is matnxed under  !

the 0 3erations Manager, the Chemistry and Water Management functions are combined, and tie function of the Hope Creek Projects Supervisor is part of the Operations Department. The changes conform to appropriate regulatory requirements in the Technical Specifications, Regulatory Guides, and ANSI Standards. The changes do not alter the plant and do not affect any initiating conditions described in the SAR.

Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety )

Question.

Temporary Modifications Summary of Safety Evaluations Remove the Diesel Room Recirculation (DRR) Fire Protection System Trip of the  ;

DRR Fans, Temporary Modification 97-001. This temporary modification removed the i DRR fan automatic shutdown initiated by the carbon dioxide system. The automatic fan  !

shutdown was implemented previously since the fire dampers would not close against l system design air flow. Since the automatic trip of the DRR fan from the carbon dioxide system was removed, the carbon dioxide system no longer functions as described in the UFSAR. However, the fire suppression system (FSS) circuit will still operate per design with the exception of the DRR fan trip. Appropriate compensatory actions have been taken in accordance with the Fire Protection Program. This modification involves portions of safety systems that are required to mitigate the consequences of an accident. '

However, there are no modifications to safety systems which would be used to control plant operations and which would be considered in an accident analysis. This modification  !

removes the oossibility of an inadvenent shutdown of the DRR fans. The potential for this i type of shutc own is considerec' a design deficiency. Removing this deficiency will ensure that the SDGs will be able to perform as required to mitigate the consequences of an accident. This temporary modification does not degrade the performance of the DRR or the SDG. The temporary modification does inhibit the automatic FSS. However, compensatory actions have been taken in accordance with the Fire Protection Plan.

, Therefore, implementation of this temporr.ry modification does not increase the probability or conseguences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

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- Other Summary of Safety Evaluation 1996 Emergency Plan Annual Review. The Nuclear Business Unit (NBU) Emergency Plan for Hope Creek Nuclear Generating Station was changed as a result of the annual review required by Section 17, Part 4.0 of the Emergency Plan. The following changes were made: 1) reduced the Radiological Assessment Suppoit Team from five to four members, 2) added two positions to the Emergency Response Organization (ERO), 3) revised the Emergency Offsite Facility (EOF), and 4) removed references to the counting room and counting equipment available at the Nuclear Training Center for EOF. These l changes to the Emergency Plan will not impact any plant systems, structures, equipment or plant parameters. They do not change parameters used for post-accident monitoring of ,

4 vanables and systems as required by Regu atory Guide 1.97. Physical changes at the EOF ,

do not alter the Heating, Ventilation, and Air Conditioning system or EOF habitability.

No significant electrical loads were added to the EOF and eqm,pment electrical loads in the  !

EOF do not impact any plant safety-related power sources. These changes do not reduce the capability to prevent or mitigate consequences of accidents that result in offsite <

4 exposures comparable to 10CFR100 guidelines. These changes do not affect the ERO

. positions involved in plant operations; corrective maintenance and direct support of operation; and plant emergency direction and control. The changes do not change the design basis of any systems. No plant systems, structures or components were changed by the revisions. l 1

Therefore, implementation of this change does not increase the probability or )

conseguences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

1 Salem and Hope Creek Event Classification Guide and Emergency Plan - Section 5. ]

The Salem and Hope Creek Event Classification Guides were revised to provide an  ;

improved set of Emergency Action Levels (EALs) and Reporting Action Levels (RALs) l which are consistent with the revised NUMARC methodology on emergency classification. In addition to revising the EALs, a new document titled " Emergency Classification Guide Technical Basis" (ECGTB) was provided for each ECG which provides the ECG user with a basis and discussion for each EAL. The ECGTB also provides the calculations and assumptions used to support the EAL threshold values. This .

change did not include or effect any systems, structures or components. The ECG is only l used after an accident or event has occurred to properly classify the event. j l

Therefore, implementation of this change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

Deficiency Reports Summary of Safety Evaluations Procedures Summary of Safety Evaluations There were no changes in these categories implemented during January 1997.

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