ML20057E192

Safety Evaluation Supporting Amend 166 to License DPR-61

ML20057E192
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/04/1993
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20057E190	List: ML20057E189 ML20057E191 ML20057E192
References
NUDOCS 9310080081
Download: ML20057E192 (2)

Text

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UNITED STATES j

j NUCLEAR REGULATORY COMMISSION-a WASHINGTON, D.C. 2058H001

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1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 166 TO FACILITY GPERATING LICENSE NO. DPR-61~

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAN NECK PLANT DOCKET NO. 50-213

1.0 INTRODUCTION

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By letter dated July 21, 1993, the Connecticut. Yankee Atomic Power Company (the licensee) submitted a request for changes to the Haddam Neck Plant' Technical Specifications'~(TS).- The amendment would modify the-Haddam Neck TS Tables 3.3-9 and 4.3-7. by deleting an obsolete footnote' and replacing it with a clarification as to when the steam generator blowdown radioactivity monitors 1

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are required to be operable.

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2.0 EVALUATION JJ Tables 3.3-9 and' 4.3-7 each contain an entry for the steam generator blowdown line under the title " gross. radioactivity monitors providing automatic termination of release." These entries each reference"a footnote"which states:

" Automatic termination of blowdown requirement'will become effective l

upon completion of proposed modification to provide. automatic-termination."

The referenced modification has been completed. ' Plant Design Change Number -

1146, entitled " Implementation of Service Water Modifications on SW-TV-2356' A-

& B and Installation of Hi Radiation Trip of the Steam Generator Blowdown Trip Valves," installed control equ11 ment.to provide an: automatic ~ steam generator blowdown isolation function on' sigh steam generator blowdown line' radiation.

A summary of this plant design change and its 10 CFR 50.59 evaluation was transmitted to'the NRC by letter dated February 26, 1993,-via-the: annual report for the Haddam Neck Plant;and Millstone Unit Nos. 1, 2, and.3. The completion of this modification makes the footnote' obsolete. Based on'thet above, the staff concludes that the modification has~been completed and the removal of this footnote is an editorial; change and is acceptable,to the -

staff..

=l The licensee proposes to replace the existing footnote with a new footnote to-TS Tables 3.3-9 and 4.3-7 which will state that the operability requirements-for the steam generator blowdown radioactivity monitors are not~ applicable 4

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' during Modes 5 or 6. ~ Currently TS 3.3.3.7: specifies that each of the.

radioactive liquid effluent monitoring instrumentation ~ channels delineated in:

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Table 3.3-9 must be operable in the quantity specified "at all times" andithatl the appropriate surveillance requirements of Table 4.3-7tshould be performed "j

4 for.all Modes. The' pressure in the' steam generator blowdown lines 1s-the head' of water. in the ~ steam generator, which is insufficient to cause flow or water through the blowdown monitors.: Because these lines are' in:a'no' flow '

i condition, the steam ' generator blowdown radioactivity monitors provide'no:

=j meaningful radioactivity. indications during Modes 5' or 6.OThe'refore,1the.

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licensee proposes to add a footnote to Tables 3.3-9 and 4.3-7 which will' state:

1 that the operability requirements for the steam generator. blowdown-j

- radioactivity monitors are.not applicable during. Modes 5 or 6.; This.changei 1

accurately. reflects plant conditions during Modes 5 or. 6L and will(reduce 1the H

licensee burden by eliminating the requirement to enter.TS action statement-1 for a normal evolution in plant-operation.

Based on=the:above, the staff

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agrees that the steam generator blowdown radioactivity monitors need not bei 1

operable during Modes 5 or 6~ and'the.TS change isl acceptable..

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3.0 STATE CONSULTATION

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In accordance'with the Commission's regulations', the Connecticut ^ State.

official was notified of the proposed issuance of the amendment.. The State; j

official had no comments.

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4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with~ respect:to ' installation or use of a:

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facility component located within the restricted area as defined. in 10.CFR i

Part 20. The NRC-staff has' determined that the' amendment involves no.

significant increase in the amounts, and no significant change in:the types,

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of any effluents that may.be: released offsite,:and that there.is no >

a significant increase in individual or cumulative occupational radiation

- exposure. The Commission has.previously issued a ~ proposed finding: that' the amendment involves no significant hazards-consideration, and there has been no-public comment on such finding (58 FR 46225).' ' Accordingly, the amendmenti meets the eligibility criteria for categoricalinxclusion~ set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmentalt impact statement.or environmental assessment need be. prepared in connection with the issuance:of the amendment.

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5.0 CONCLUSION

i The Commission has concluded, based on the considerations. discussed above, that: '(1) there is~ reasonable assurance that-the~ health and safetyJof the public will not'be endangered by operation in. the proposed manner, (2) such

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activities will be' conducted in. compliance with the Commission's regulations,

- and (3) the-issuance.of the' amendment will.not be inimicairto the~ common defense and security orL to the health"and" safety of the public.

Principal Contributor:. A. Wang x

Date:

October 4, 1993 d

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