ML20236D553

Resubmits Proposed Tech Spec Changes Needed to Support Cycle 15 Reload,Incorporating Pagination,Correcting Typo & Terminology Clarifications & change-out Instruction Table. Description of Changes Made from Original Submittal Encl

ML20236D553
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/22/1987
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20236D556	List: B12604, Proposed Tech Spec Changes Supporting Cycle 15 Operation ML20236D553
References
B12604, NUDOCS 8707300522
Download: ML20236D553 (4)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY BERLIN. CO N N ECTIC U T P.O. BOA 270 H ARTFORD. CONNECTICUT C6101 July 22,1987 nu===

203-6MS 6 911 Docket No. 50-213 B12604 Re: 10CFR50.36 I

1 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Reference:

(1)

E. 3. Mroczka letter to U.S.

Nuclear Regulatory 1

Commission, Cycle 15 Reload, Technical Specification l

Requests and Reload Report, dated June 1,1987.

Gentlemen:

Haddam Neck Plant Cycle 15 Reload Technical Specifications in Reference (1), Connecticut Yankee Atomic Power Company (CYAPCO) provided a set of proposed Technical Specification changes needed to support Cycle 15 operation. After a preliminary review by your Staff and a meeting with CYAPCO representatives, it was agre.ed that the submittal would be resubmitted to incorporate pagination, correct some typographical and terminology clarifica-tions, and include a change-out instruction table with notes providing a compar-ison between current and proposed Technical Specifications.

Attachments included are as follows:

o provides a description of changes made from the Reference 1 proposed changes, o provides a resubmittal of the proposed Technical Specification changes.

o provides the change-out instruction table.

We trust that you find this information satisf actory.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY g%hm. >g /

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p E. 3.'M czka g/

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Senior ice President i

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L U.S. Nuclear Regulatory Commission

= B12604/Page '2

- Joly.;22,11987

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W.'T. Russell, Region I Administrator'

F. M.' Akstulewicz, NRC Project Manager, Haddam Neck Plant--

3.' T. Shediosky,' Resident Inspector, Haddam Neck Plant -

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l STATE 'OF CONNECTICUT)-

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- COUNTY OF HARTFORD )~'

- Then ' personally appeared' before me, E. 3. Mroczka, who being ' duly cworn did

' state that: his ~ is' Senior Vicel President of Connecticut Yankee Atynic Power

Company, = a Licensee herein, f that' he is authorized to execute and. file the.

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foregoing information in the name and on behalf of the Licenseer herein, and.that the statements contained inL said information are true and correct to the best of his knowledge and belief.-

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AhAtthes Y

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c-My Commiss on Expires March 31,1988 f

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Docket No. 50-213 B12604 1

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Haddam Neck Plant j

Description of Changes Made Since the Original Submittal 1

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July 1987

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Description of Changes Made Since the Original Submittal (Reference 1) o_ -

Table 1-1, Operational Modes--a change bar has been added to MODES 2-5 to acknowledge a change in the " Reactivity Condition" made.

o Section 2.2.1, Safety Limits--Reactor Core, " Table 2.1-1 and 2.1-2" havc been renumbered to " Table 2.2-1 and 2.2-2." (Tables have been renumbered also.)

o Section 2.4, Maximum Safety Setthgs--Protective Instrumentation item 7--

the basis for the high steam flow trip set point has been further modified to de'.ete a reference to lowering the trip point near no-load conditions. The trip set point is not lowered during plant operation, nor is credit. taken for the lower set point in the accident analysis.

Section 3.3.1.8, RCS-Idle Loop Start-Up--replaced RTP" with " RATED o

THERMAL POWER."

Section 3.3.3, RCS--Pressurizer--capitalized " THERMAL POWER" in LCO o

.and in Action Statement b, " restore the pressurizer to OPERABLE. status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or."

o Section 3.10.2.),

Movable Control Assemblies--Bank

Height, Sections 3.17.3.1 and 2, $H Power Distribution Limits--Nuclear Enthalpy Rise Hot Channel Factor--F for four and three loops, respectively, and Section 3.17.4, Quadrant Power Tilt Ratio- " Power Range Neutron Flux--

High" was changed to " nuclear overpower" to be consistent with Section 2.0.

Section 3.10.2.2, Reactivity Control Systems--Position Indication Systems--

o-Operating--an additional Action Statement has been added for the conuition where more than one rod position indicator is inoperable.

Section 3.11, Containment--under item B(1) the shutdown margin require-o ment was changed from 2500 pcm to 2600 pcm to correct a typo.

o Section 3.17.4, Power Distribution Limits--Quadrant Power Tilt Ratio, Action Item C.2--the word " power" has been deleted from the second line just prior to Nuclear Overpower Trip.

01eral--page numbers have been added and change bars have been added o

for : vised Specifications 3.3, 3.10, 3.17, and 3.24.

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