ML20135F820

Summary of 970110 Meeting W/Combustion Engineering Owners Re Status of Draft Shutdown & Fuel Storage Pool Operations Rule.List of Attendees Encl

ML20135F820
Person / Time
Issue date:	03/07/1997
From:	Stewart Magruder NRC (Affiliation Not Assigned)
To:	Matthews D NRC (Affiliation Not Assigned)
References
PROJECT-692 NUDOCS 9703140151
Download: ML20135F820 (5)

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,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 7, 1997 i

MEMORANDUM T0:

David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:

Stewart L. Magruder, Project Manager Generic Issues and Environmental AM b

Projects Branch Division of Reactor Program Management 1

Office of Nuclear Reactor Regulation

SUMMARY

OF JANUARY 10, 1997, MEETING WITH COMBUSTION ENGINEERING OWNERS GROUP OUTAGE MANAGEMENT WORKING GROUP The Nuclear Regulatory Commission (NRC) staff conducted a conference call with representatives of the Combustion Engineerir.g Owners Group (CE0G) Outage Management Working Group on January 10, 1997.

The purpose of the call was to discuss the status of the draft shutdown and fuel storage pool operations rule.

The call participants are listed in attachment 1.

The call opened with the NRC representative providing a description of the task force that had been recently formed to help expedite the development of the shutdown rule. The NRC representative stated that tha group comprises mehlbers from several different technical branches within the Office of Nuclear Reactor Regulation as well as a representative from the Office of the General Counsel. The task force's goal is to complete the rulemaking package for a risk-informed rule with performance elements by May 1997.

(The task force is scheduled to provide the package to the Commission by July 31, 1997.)

The CE0G representatives stated that they had several questions regarding specific requirements in the rule. The NRC representative noted that the rule was still subject to change but that he would answer the questions as best he i

could with the qualifications that the answers did not represent staff I

positions and would be based on the status (November,1996) prior to formation of the task force The first question from the CE0G was related to the pressure bearing

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requirements of containment. They asked whether, when containment is required to be set, the maximum pressure that the containment must be able to withstand j

is that due to steam following an accident or whether a hydrogen burn must be

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The NRC representative stated thattif you are in a condition where you may have significant damage to the fuel cladding' then you should address hydrogen.

Therefore, you should be able to ensure that temporary closures do not represent weak points in the containment or that they are capable of withstanding the pressure generated by a hydrogen burn.

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1 D. Matthews The CE0G representatives then asked whether the industry could propose prevention of hydrogen burns instead of trying to mitigate their consequences, They suggested that one method may be to show that the core remains covered under all accident conditions in modes 5 and 6.

The CE0G representatives suggested that it may be possible to increase safety injection capability and i

reliability to a point where the. likelihood of core uncovery is very low. The NRC representative stated that it is important to be able to maintain i

containment in all modes when required. He also stated that he would reconsnend acceptance of lower pressure requirements for containment when the refueling cavity is not filled only if the industry could show that hydro.

generation and burning is not of concern.

1 The CE0G representatives next asked about whether the term " containment integrity"-would be used in the rule. The NRC staff representative stated that the term should not be in the rule and that there should not be any references to technical specification leakage requirements.

The CE0G representatives then asked about temporary containment hatches. They stated that the temporary hatches do not always have the same pressure l

capability as primary containment and they questioned whether they needed to have the same capability. The NRC representative stated that the temporary hatch covers should have the same pressure capability as the containment when i

the refueling cavity is not filled unless licensees can establish that temporary covers provide comparable protection and satisfactory defense-in-depth.

l The CE0G representatives noted that there is a difference of opinion between the industry and the NRC representative regarding temporary hatches. The NRC staff representative agreed.

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CEOG OMWG/NRC CONFERENCE CALL LIST OF ATTENDEES January 10, 1997 N8Mk ORGANIZATION L'. Auterino APS J. Scott APS P. Kriningan

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S. Waro,

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M. Bourgeois Entergy-ANO i.

D. Shipman Entergy-WSES-J. Herman 0 PPD'

'SCE-F D. Optiz L. Wild t- >- 'ABB-CE's.

W. Dove ABB-CE' P. Hijeck ABB-CE T. Timmons Westinghouse J. Osborne BGE' e

N. Chapman SERCH/Bechtel W. Lyon NRC/NRR.-

S. Magruder NRC NRR

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D. Matthews March 7, 1997 The CEOG representatives then asked'whether the industry could propose prevention of hydrogen burns instead of trying to mitigate their consequences.

They suggested that one method may be to show that the core remains covered under all accident conditions in modes 5 and 6._ The CE0G representatives-suggested that it may be possible to increase safety injection capability and

. reliability to a point where the likelihood of core uncovery is very low.

The NRC-representative stated that it is important to.be able to maintain containment in all modes when required. He also stated that he would-recommend acceptance of lower pressure requirements for containment when the refueling cavity is not filled only if the industry could show that hydrogen generation and burning is not of concern.

The CE0G representatives next asked about whether the term " containment integrity" would be used in the. rule. The NRC staff representative stated that the term should not be in the rule and that there should not be any references to technical specification leakage requirements.

The CEOG representatives then. asked about temporary containment hatches.

They stated that the temporary hatches do not always have the same pressure capability as. primary containment and they questioned whether they needed to have the same capability.

The NRC representative stated that the temporary hatch covers should have the same pressure capability as the containment when the refueling cavity is not filled unless licensees.can e::tablish that temporary covers provide comparable protection and satisfactory defense-in-depth.

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The CE0G representatives noted that there-is a difference of opinion between j

the industry and the NRC representative.regarding temporary. hatches..The NRC staff representative agreed. g

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Mr. Charles B. Brinkman. Director i

Nuclear Systems Licensing ABB-Combustion Engineering, Inc.

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i Mr. Charles B. Brinkman, Manager Washington Nuclear Operations i

ABB-Combustion Engineering, Inc.

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