ML19318A997

Advises That Util Intends to Respond to 800507 Request Re TMI-2 Requirements within Schedule.Util Presently Evaluating Alternatives within Framework of GE BWR Owners Group

ML19318A997
Person / Time
Site:	Cooper
Issue date:	06/18/1980
From:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
LQA8000310, NUDOCS 8006240500
Download: ML19318A997 (2)

Text

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LQA8000310 GENERAL OFFICE P. c. box 499, col'>MBUS NES R ASKA 68601 Nebraska Publ.ic Power Distr. ic t TE'E~c~E sou se4 asei June; 18, 1980 Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 Subj ect: Five Additional TMI-2 Related Requirements to Operating Reactors

Reference:

1) Letter from NRC to All Operating Reactor Licensees Dated May 7,1980, Same Subject

2) " Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-Term Operating License Applications", NUREG-0626 dated January,1980

3) Letter from S. J. Stark (GE) to C. O. Thomas (NRC)

Dated December 7,1979, "B&O Prospective Safety Evaluation Report Requirements for BWR's"

Dear Mr. Eisenhut:

In Reference 1 Nebraska Public Power District was requested to provide a commitment to implement certain requirements per the implementation schedule provided.

Nebraska Public Power District intends to be fully responsive to these requirements; however, well-defined acceptance criteria for many of the recommendations are needed in order to assure timely implementation.

These acceptance criteria, when fully developed, may impact implementation 4

schedules due to the availability of hardware and resources for conducting the required studies and developing the required design.

Section 4.2.B.15 of Reference 2 stated the following:

"The B&OTF has recommended substantial changes which will af fect system design, system actuation or isolation logic, operator actions, and ar.alysis techniques. GE should review all of the recommendations of the B&OTF and provide an assessment of the collective impact of these recom-mendations on _ system safety and reliability."

Following this collective assessment of the impact by GE, the District may wish to discuss with the NRC alternatives to the strict interpretation of some requirements. The District is presently evaluating such alternatives -

within the framework of the General Electric Boiling Water Reactors Owners A Group. Such alternatives may include:

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Darrell G. Eisenhut.

June 18, 1980 Page 2 .

1) Modifications other than those suggested by the requirement which provide equal or better safety improvement;

2) Design and test of hardware modifications on a single typical plant followed by implementation on remaining plants;

3) Exception to some recommendations whose implementation is believed unnecessary for reasons similar to those discussed in Reference 3.

- Within the constraints described above, it is the District's intent to meet the requirements and schedule of Reference 1.

The implementation date for Item II.K.3.30 and II.K.3.31 are assumed to be the dates given.in Enciasure 3, Part 1 of Reference 1.

EIf additional clarification is necessary, please do not hesitate to contact me.

Sincerely,

\hA Jay M. Pilant Director of Licensing and Quality Assurance JMP:JDW:cmk 1

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