ML20035C274

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Requests Review of Neutron Flux Monitoring Instrumentation Against NEDO-31558 Criteria to Determine Whether Criteria Met & Provide Ltr to NRC Documenting Results of Review
ML20035C274
Person / Time
Site: Millstone 
Issue date: 04/01/1993
From: Andersen J
Office of Nuclear Reactor Regulation
To: Opeka J
NORTHEAST NUCLEAR ENERGY CO.
Shared Package
ML20035C275 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-M51106, NUDOCS 9304060428
Download: ML20035C274 (3)


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UNITED STATES

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NUCLEAR REGULATORY COMMISSION -

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April 1, 1993-Docket No. 50-245 Mr. John F. Opeka Executive Vice President, Nuclear Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141-0270

Dear Mr. Opeka:

SUBJECT:

REGULATORY GUIDE 1.97 - BOILING WATER REACTOR NEUTRON FLUX MONITORING (TAC M51106)

Section 6.2 of Generic Letter 82-33 requested that applicants and licensees-provide a report on their implementation of Regulatory Guide (RG) 1.97, Revision 2, and methods for complying with the Commission's regulations including supporting technical justification of any proposed deviations-or-alternatives. A large number of deviation requests were received from Boiling Water Reactor (BWR) applicants and licensees concerning neutron flux monitoring' instrumentation.

These requests were initially-denied.

In support of these requests, the BWR Owners Group submitted NED0-31558,

" Position on NRC Regulatory Guide 1.97,' Revision 3, Requirements for Post-Accident Neutron Monitoring System." NED0-31558 proposed alternate criteria for neutron flux monitoring instrumentation in lieu of the Category I criteria stated in RG 1.97.

The staff has completed its evaluation of NED0-31558, and by letter dated -

January 13, 1993, to the BWR Owners Group, issued a safety evaluation (enclosed). The safety evaluation concluded that, for current BWR operating license and construction permit holders, the-criteria of NED0-31558 are acceptable.

However, for new license applications for both conventional and advanced BWR designs, the RG 1.97 criteria must be met for neutron flux monitoring instrumentation. The staff further concluded that Category'1 neutron flux monitoring instrumentation is not needed for existing BWRs to cope with a loss-of-Coolant Accident, Anticipated Transient Without Scram, or other accidents that'do not result in severe core damage conditions.

Instrumentation to monitor the progression of core melt accidents -is best addressed by the current severe accident management program.

You are requested to review your neutron flux monitoring instrumentation against the criteria of NED0-31558 to determine whether you meet these criteria, and provide a letter to the NRC documenting the results of your review.

If you do not meet the criteria, you should either make a commitment to meet the criteria and state when this commitment will be fulfilled, or.-

explicitly state any deviations from the criteria and provide supporting-justification.

MRC MI C8HEi COM 9304060428 930401

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PDR ADOCK-05000245; P

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Hr. John F. Opeka

  • The criteria of NED0-31558 include the use of uninterruptible and reliable power sources. The BWR Owners Group and the staff agree that redundant neutron flux monitoring channels should be powered from different uninterruptible power supplies (UPS), so that loss of a single UPS would not cause the loss of all channels. You are, therefore, requested to perform a plant-specific evaluation to review the power supplies to neutron flux i

monitoring instrumentation, including recorders. This review should verify that power would not be lost during design basis events by load shedding logics or similar schemes, and that a single power supply _ failure would not cause the loss of all channels. The results of this review should be indicated in your response to the staff concerning this issue.

Since neutron flux monitoring instrumentation for BWRs is no longer considered to be Category 1 instrumentation, you may request the removal of neutron flux monitoring instrumentation from your post-accident monitoring technical specifications.

If you wish to maintain a post-accident monitoring technical specification on this instrumentation, you may do so.

Please notify the NRC, within 60 days of receipt of this letter, of the actions you plan to take and your schedule for implementation.

If you have any questions regarding this issue, please do not hesitate to contact me at (301) 504-1437.

This request for information was approved by the Office of Management and Budget under clearance number 3150-0011 which expires June 30, 1994.

Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D. C. 20503.

Sincerely, Original signed by James W. Andersen, Acting Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Distribution:

1.

Safety Evaluation Docket File JAndersen dated 1/13/93 NRC & Local PDRs OGC PD I-4 Plant ACRS (10) cc w/ enclosure:

SVarga LTDoerflein, RI See next page JCalvo AHansen SNorris BMarcus D:PDIk DFFICE LA:PDI-4 PM:PDI-4

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OFFICIAL RECORD COPY Document Name: G:\\ANDERSEN\\51106LET y

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I Mr. John F. Opeka-

Millstone Nuclear Power Station.

1 Northeast. Nuclear Energy Company Unit 1 CC:

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' Gerald Garfield, Esquire R. M. Kacich,' Director l

Day, Berry and Howard

-Nuclear Licensing'.

Counselors at Law Northeast Utilities Service Company-l City Place Post Office Box 270-1 Hartford, Connecticut 06103-3499-Hartford, Connecticut 06141-0270 I

W. D. Romberg, Vice President D. 0.-Nordquist Nuclear, Operations Services Director of Quality' Services Northeast Utilities Service Company Northeast Utilities Service Company Post Office Box 270 Post Office Box 270 i

Hartford, Connecticut 06141-0270 Hartford,:ConnecticutL06141'0270--

l Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region I j

Department of Environmental Protection U.S. Nuclear Regulatory Commission:

State Office Building 475 Allendale Road-a Hartford, Connecticut-06106-

~ King of Prussia, Pennsylvania 19406 j

i Allan Johanson, Assistant Director First Selectmen Office of Policy and Management Town of Waterford l

Policy Development and Planning Division Hall of Records j

SO Washington Street 200 Boston Post ~ Road j

Hartford, Connecticut 06106

-Waterford, Connecticut 06385-j I

S. E. Scace, Vice President P. D. Swetland, Resident Inspector Millstone Nuclear Power Station.

Millstone Nuclear' Power Station.

Northeast Nuclear Energy Company c/o U.S. Nuclear Regulatory Commission

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Post Office Box 128

-Post Office Box 513 Waterford, Connecticut 06385 Niantic, Connecticut 06357

.j H. F. Haynes, Nuclear Unit Director

.i Millstone Unit No. I Northeast Nuclear Energy Company l

Post' Office Box 128 l

hierford, Connecticut 06385 Nicholas S. Reynolds Winston & Strawn i

1400 L Street, NW Washington, DC 20005-3502 i

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