ML20035C514

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Summary of 930404 Meeting W/Util in Rockville,Md Re Discussions on Various Aspects of Standard Tss.List of Attendees Encl
ML20035C514
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/02/1993
From: Shiraki C
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9304080055
Download: ML20035C514 (5)


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-4 UNITED STATES

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- NUCLEAR REGULATORY COMMISSION j

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WASHINGTON. D.C. 20666-0001 a

April 2, 1993-Docket Nos. 50-295 and 50-304-LICENSEE:

Commonwealth Edison Company

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FACILITY:

Zion Nuclear Power Station

SUBJECT:

' MEETING

SUMMARY

- ISSUES CENTERED AROUND THE STANDARD TECHNICAL ~

f SPECIFICATIONS

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On March 4,1993, a' meeting _ was held at NRC Headquarters in Rockville, j

Maryland, to discuss various aspects of the. standard technical specifications

-(STS). Meeting participants -included representatives of Commonwealth Edison-Company (CECO, or the licensee) and its contractor, and employees of the NRC's 1

Office of Nuclear Reactor Regulation (the staff). A list of attendees is j

enclosed.

Licensina Basis for Atmospheric Dumo Valves Zion's licensing basis for steam generator tube rupture events relies on the condenser as the heat sink, as it does for.some older pressurized water.

reactors, while later plants were required to. assume a coincident ^ loss-of-offsite power (LOOP) such that the design basis' relies on the atmospheric dump q

valves ~ (ADV). Commonwealth Edison Company believes that. it is' appropriate to include the ADV heat removal function in the technical-specifications, but.

Criterion 3 does not apply unless Ceco redoes its safety analysis. They are l

concerned that redoing the safety analysis would lead the staff to require' the ADV to be upgraded to safety related,' although Zion was licensed with-non-safety related requirements on the valves.

The staff indicated that the STS improvement program is not the appropriate

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vehicle by which to accomplish changes to the design basis.

Nevertheless, the.

j staff expects a licensee to determine the adequacy of its licensing basis when -

evaluated against that in the STS.

In the specific situation: involving the ADV, the licensee concluded that although it would be appropriate to include l

the ADV function in the technical specifications because of risk considera- _

tions, redoing the safety analysis or upgrading the valves would not _be cost

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effective.

Further, CECO proposed an alternate limiting condition-for operation which gives credit for the condenser heat removal function when ADVs-are inoperable. Their proposal will be discussed further at a meeting with.

the Owners' Groups on March 18, 1993. The staff-suggested that the Owners' Groups should consider developing a common Bases option that would explain the requirements-for plants that were licensed in a fashion similar to Zion.

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Shared Systems l

Commonwealth' Edison Company indicated that it did.not clearly understand the acceptance criteria for shared systems, as they are described in-General Design Criterion 5.

The staff suggested that Ceco consult the Standard.

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PDR g

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Review Plan. - Commonwealth Edison Company. described its primary concern asi l

being with the action requirements for combinations of inoperable equipment'

related to diesel operability
and design basis accident assumptions.i They.

have a simihr concern with inconsistencies related to;the sharEJ service:

water s.vstem. The staff suggested that the resolution may depend on the form l

of %o requirement, i.e.,. combined specifications for multiple units,. or unit-

-i mcific specifications.

In either case, a common approach should be i

developed by the Owners' Groups which considers the best.way to communicate-i the requirements to the plant operators (human factors considerations).

commonwealth Edison Company asked about the accepted practi_ceL regarding LOOP

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assumptions for multiple unit-sites; the staff agreed to research the' question and provide an answer.

l Reportability j

In reply to CECO's question of.whether the reportability practice described

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for design basis reconstitution could be applied for STS conversion and similar activities, the staff replied in the affirmative; This. issue was also' discussed in the operability workshops as it relates to other programs which identify potentially non-conforming conditions. The staff. suggested'that if clarification of this point was a generic concern, NUMARC or another industry group could mak.e a specific request for clarification, and the staff would establish a definitive position.

.l 4

v original signed by:

j Clyde Y. Shiraki, Sr. Project. Manager

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Project Directorate III-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Enclosure-List of Attendees cc w/ enclosure:

See next page j

.plSTRIBUTION Docket File NRC & Local PDRs PDIII-2 r/f

~j TMurley/FMiraglia JPartlow JRoe-

-l JZwolinski JDyer CShiraki

't CMoore OGC EJordan ACRS(IO)

GGrant, EDO BClayton, RIII CGrimes ETomlinson j

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III-2 PM/PDIII-D/PDII

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-CShiraki:rc Jper

/93 y/2_l93-7/fr DOCUMENT NAME: ZI3_4_93.MTG 1

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e Zion Nuclear Power Station Unit Nos. 1 and.2-1 cc:

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Michael I. Miller, Esquire 1

Sidley and Austin.

One First National Plaza Chicago, Illinois 60690 t

Dr.' Cecil Lue-Hing~

l Director of Research and Development

-Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Phillip Steptoe, Esquire Sidley and Austin 3

One First National Plaza Chicago, Illinois 60603 i

Mayor of Zion

. Zion, Illinois 60099 Illinois Department of Nuclear' Safety Office of Nuclear Facility' Safety l

1035 Outer Park Drive Springfield, Illinois 62704 s

^

U. S. Nuclear Regulatory Commission Resident Inspectors Office i

105 Shiloh Blvd.

i Zion, Illinois 60099 Regional Administrator, Region III l

U. S. Nuclear Regulatory Commission f

799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Robert Neumann-Office of Public Counsel State of Illinois Center-t

'100 W. Randolph Suite 11-300 Chicago', Illinois 60601 Mr. D. L. Farrar, Manager.

Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 l

1400 OPUS Place Downers Grove, Illinois.60515 j

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-, + - -

ENCLOSURE c..

.I LIST OF ATTENDEES' ISSUES CENTERED AROUND THE STANDARD TECHNICAL SPECIFICATIONS MARCH 4. 1993 Name Affiliation Clyde Shiraki NRC/ Zion project Manager Chris Grimes NRC/ Technical Specifications Branch Edward Tomlinson NRC/ Technical Specifications Branch

. Lee Bush.

Commonwealth Edison / Westinghouse Owners' Gro:p Stephen Stimac Commonwealth Edison Company, Nuclear Licensing Administrator Don Hoffman

-Boiling Water Reactor Owners' Group and C.ambustion Engineering Owners' Group Mark Bittmann NUS Corporation

Review Plan.

Commonwealth Edison Company described its primary concern as being with the action requirements for combinations of inoperable equipment related to diesel operability and design basis accident assumptions. They have a similar concern with inconsistencies related to the shared service water system. The staff suggested that the resolution may depend on the form of the requirement, i.e., combined specifications for multiple units, or unit-specific specifications.

In either case, a common approach should be developed by the Owners' Groups which considers the best way to communicate-the requirements to the plant operators (human factors considerations).

I Commonwealth Edison Company asked about the accepted practice regarding LOOP assumptions for multiple unit sites; the staff agreed to research the question and provide an answer.

Reportability In reply to CECO's question of whether the reportability practice described ~

for design basis reconstitution could be applied for STS conversion and similar activities, the staff replied in the affirmative.

This issue was also l

discussed in the operability workshops as it relates to other programs which identify potentially non-conforming conditions. The staff suggested that if clarification of-this point was a generic concern, NUMARC or another industry group could make a specific request for clarification, and the. staff would establish a definitive position.

original signed by:

Clyde Y. Shiraki, Sr. Project Manager Project Directorate III-2 i

Division of Reactor Projects'III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

List of Attendees cc w/ enclosure:

See next page DISTRIBUTION Docket File NRC & Local PDRs PDIII-2 r/f TMurley/FMiraglia JPartlow JRoe JZwolinski JDyer CShiraki CMoore OGC EJordan ACRS(IO)

GGrant, EDO BClayton, RIII CGrimes ETomlinson CShiraki:r@ CPM /PDIII-2!

D/PDII

_A ' 1111-2 Utoo Jper

$/f8/93 y/1/93 y/7, DOCUMENT NAME: ZI3_4_93.MTG