ML20005B964

Forwards Revised Draft Evaluation, SEP Review of Safe Shutdown Sys. Revision Based on SEP Topics V-10.B,V-11.B & VII-3.Differences Between as-built Facility & Licensing Basis Assumed in Assessments Requested within 30 Days

ML20005B964
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/09/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
Shared Package
ML20005B965	List: ML20005B964 ML20005B968
References
TASK-05-10.B, TASK-05-11.B, TASK-07-03, TASK-5-10.B, TASK-5-11.B, TASK-7-3, TASK-RR LSO5-81-09-026, LSO5-81-9-26, NUDOCS 8109160206
Download: ML20005B964 (4)

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NUCLEAR REGULATORY COMMISSION g

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Docket No. 50-213 LS05-81-09-026

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2 SEPl5198;w Mr. W. G. Counsil, Vice President CJ u.a.uucun eD,QD 1

Nuclear Engineering and Operations m

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"'5 Northeast Nuclear Energy Company j

Post Office Box 270 g

Hartford, Connecticut 06101

SUBJECT:

HADDAM NECK - SEP TOPIC V-10.B RHR Reliability, V-11.B RHR Interlock Requirements, VII-3 Systems Required for Safe Shutdown (Safe Shutdown Systems Report) l The SEP draf t evaluation of Safe Shutdown Systems for Haddan Neck was trans-mitted to you on June 7,1979. Your comments were provided in a letter dated September 28, 1979.

The draft Safe Shutdown Systems Report has been revised by contractor person-nel to resolve your comments, to establish the minimum set of systemsneeded to satisfy the staff's functional criterir. and to determine the water requir-

.ed to perfonn the coaldown in accordance w'th these criteria.

The revised evaluation is enclosed. You are requested to inform us if your as-built facility differs from the licensing basis assumed in the assessment within 30 days of receipt of this letter.

This topic evaluation will be a basic input to the integrated saf ety assess-ment unless you identify changes needed to reflect the as-built conditions of your facility. This topic assessment may be revised in the future if your fac'iity design is changed or if NRC criteria relating to this topic are modi-fied before the integrated assessment is complete.

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--9 Also enclosed are the conclusions the staff has formulated as a result of these topic evaluations and identification'of concerns for resolution in~the integrated assessment. You arc encouraged to supply for the docke' any other material related to these concerns that may affect the staff's ev.':uation and conclusions, to enable us to resolve these deviations prior'to ti e integrated assessment.

Sincerely, 1

Dennis M. Crutchfield, Chief Operating Reactors 3 ranch No. 5 Division of Licensing

Enclosures:

As stated cc w/ enclosures:

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HADDAM NECK Docket No. 50-213 Mr. W. G. Coun'.1 cc Day, Berry & Howard Counselors at Law One Const'tution Plaza Hartford, Connecticut 06103 Superintendent Haddam Neck Plant RFD #1 Post Of fice Box 127E East Hampton, Conneccicut 06424 Mr. Richard R. Laudenat Manager, Generation Facilities Licensing Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 Board of Selectmen Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency ATTN: Assistant Director Research and Policy Development Departnent of Planning and Energy Policy 20 Grand Street Hartford, Connecticut 06106 U. S. Environmental Protection Agency Region I Office ATTN: EIS COOP.DINATOR JFK Federal Building Boston, Massachusetts 02203 Resident Inspector Haddam Neck Nuclear Power Station c/o U. S. NRC East Haddam Post Office East Haddam, Connecticut 06423

ENCLOSURE 1 Conclusions 1.

Because of the potential for Residual Heat Removal (RHR) overpressur-ization, the staff has determined that the following modifications J

should be considered for backfit during the integrated plant safety assessment:

a.

Interlocks on the RHR-to-core deluge motor-operated valves to prevent opening until RCS pressure is below design pressure.

b.

Independent diverse interlocks on the RHR-to RCS isolation valves to prevent opening until RCS pressure is below RHR design pressure.

c.

Modification of the technical specifications to reauire placing the overpressure protection system in operation whenever RHR cooling is in progress.

j 2.

The staff cancludes that the Haddam Neck systems fulfill the safety objective of reliable plant shutdown capability using safety-grade equipment provided that plant operating procedures are modified to in-struct operators how to perform shutdown and cooldown functions with the systems identified in the minimum systems list.

3.

The staff noted during the safe shutdown evaluation that no Technical Specification requirement governs the allowed outage time of an ECCS train. The need for this requirement will be evaluated ur. der SEP Topic XVI, " Technical Specifications".

4.

Based on our review, the staff concludes that procedural shortcomings exist with respect to shutdown from cutside the control room in the areas of maintenance of batteries for portable instruments, the assign-ment of shutdown duties for shift personnel and emergency communications l

methods. The licensee should modify his procedures to alleviate these

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s hortcomings.

1i 5.

A passive failure of the common pump suction header, discharge header, or the non-essential condensate service line, to which the AFS suction line is attached, would prevent the AFS from. supplying feedwater to the steam generators even without an assumed concurrent single active failure. The low probability of a passive failure in the low pressure suction line or in the discharge line, which is periodically tested under the Licensee's inservice inspection program, alleviates the need for any immediate cor-rective measures. The staff intends to exanine the need for a long-term l>

improvement in the redundancy of the AFS at the Haddam Neck plant. This will be considered separate from the SEP as part of the TMI Task Action Pla~n (NUR[G-0737), Unresolved Safety Issues A-45 and A-46, and Multi-plant Action Plan issue C-14.

We note that the licensee has committed to pro-vide an isolation valve in the common cross connect line and a bypass r

valve around the suction line isolation valve by January 1,1982. These

. modifications will enhance the reliability of the auxiliary feedwater systems.

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