ML20040A347

Forwards Request for Addl Info Necessary to Complete Review of Reload Safety Analysis for Cycle 5 Operation.Info Should Be Submitted by 820111

ML20040A347
Person / Time
Site:	Millstone
Issue date:	12/24/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
References
TAC-47355, TAC-47389, TAC-47473, NUDOCS 8201200796
Download: ML20040A347 (3)

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g(vf DISIRIBUIlfLN RAClark C0ccket File) Gray File NRC PDR L PDR Docket ?io. 50-336 flSIC TERA t'r. W. G. Counsil, Vice President ORB #3 Rdg liuclear Engineering & Operations DEisenhut

ortheast !!uclear Energy Corpany OELD P. O. Box 270 I&E 3 Hartford, Connecticut 06101 ACRS-10 JHeltemes

Dear Fr. Counsil:

PMKreutzer-3 PM In our review of your Reload Safety Analysis for Cycle 5 operation of Mill-

!itone Unit flo. 2, dated November 17, 1931, we find that the enclosed additional information is necessary to complete our evaluation.

Please provide the requested additional information by January 11, 1982.

This request has been modified from the draft request telecopied to your I:r. Mike Cass on December 22, 1981.

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gg M hunwR\\\\ 5g Robert A. Clark, Chief Operating licactors Branch #3 Division of Licensing Lnclosure: hequest for information cc: See next page e

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

.W WASHINGTON, D. O. 20555

%; w l ADDITIONAL INFORMATION REQUEST OF NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION, UNIT N0. 2.

CYCLE 5 REFUELING-RELOAD SAFETY ANALYSIS DOCKET N0. 50-336 1.

The analyses of a locked reactor coolant pump (RCP) rotor in the RSA assumes the availability of offsite power throughout the event.

In accordance with Standard Review Plan 15.3.3 and GDC 17, we require that this event be analyzed assuming turbine trip and coincident loss of offsite power to the undamaged pumps. Appropriate delay times may be assumed for loss of offsite power if suitably justified. The event should also be analyzed assuming the worst single failure of a safety system active component. Maximum Technical Specification primary system activity and steam generator tube leakage should be assumed. The analyses should demonstrate that offsite doses are less than the 10 CFR 100 guidelines values.

2.

Your responce to our request for additional information on the RSR, dated October 17, 1981, indicates that the broken pump shaft incident l

is bounded by the consequences of a locked RCP rotor event. Our I

analysis, as addressed in SRP sections 15.3.3 and 15.3.4, indicates l

that although the initial rate of reduction in RCS flow is greater for the RCP locked rotor, the RCP shaft break event permits a greater re-verse flow through the affected loop later in the transient. Thus, the resultant RCS flow rate is lower for the RCP shaft break event.

I Confirm that the reference October 17, 1981 statement is correct per l

this consideration.

i 3.

For a loss of normal feedwater event, clarify whether credit is taken for overpressure control by operation of the power operated relief valves.

4.

The staff is presently evaluating the need for all operating PWRs to pro-vide adequate protection against uncontrolled boron dilation events. To evaluate this event at Millstone, Unit No. 2, provide:

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a.

An evaluation of the ability of the installed instrumentation channels to detect and alert the operator of a boron dilution event in Modes 3 through 6; b.

A demonstration of the operator action time available, i.e., the time span between the receipt of an alarm or signal and the time when the shutdown margin is lost.

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Northeast Nuclear Energy Company cc:

William H. Cuddy, Esquire Mr. John Shedlosky Day, Berry & Howard Resident Inspector /Millsb3ne Counselors at Law c/o U.S.N.R.C.

One Constitution Plaza P. O. Drawer KK Hartford, Connecticut 06103 Niantic, CT 06357 1

i Mr. Charles Brinkman s

Manager - Washington Nuclear 1 -

Operations C-E Power Systems q

Combustion Engineering, Inc.

4853 Cordell Aven., Suite A-1 f

Bethesda, MD 20014

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l Mr. Lawrence Bettencourt, First Selectman Town of Waterford i

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Hall of Records - 200 Boston Post Road i

Waterford, Connecticut 06385 Northeast Nuclear Energy Company

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ATTN:

Superintendent Millstone Plant Office of. Policy & Management

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Post Office Box 128 ATTN: Under Secretary Energy, Waterford, Connecticut 06385

. Division

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80 Washington Street.

Waterford Public Library Hartford, Connecticut 06115' '

Rope Ferry Road, Route 156 Waterford, Connecticut 06385 U. S. Environmental Protection Agnecy Region I Office ATTN: Regional Radiation Representative John F. Kennedy Federal Building Boston, Massachusetts 02203 Northeast Utilities Service Company ATTN:

Mr. Richard T. Laudenat, Manager Generation Facilities Licensing P. O. Box 270 Hartford, Connecticut 06101 l

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