ML17320A564

Application for Amend to Licenses DPR-58 & DPR-74 Changing Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements

ML17320A564
Person / Time
Site:	Cook
Issue date:	07/08/1983
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17320A566	List: ML17320A564 ML17320A569
References
AEP:NRC:0591A, AEP:NRC:591A, NUDOCS 8307120400
Download: ML17320A564 (10)

Text

REGULA'Y INFORMATION OISTRISUTI(YSTEM (RIOS)

I ACCESSION NBR:8307120400 DOC.DATE: 83/07/08 NOTARIZED: YES DOCKET FACIL:50 315 Donald C. Cook Nuclear Power Plants Unj t ls "Indiana 8 05000315 50 316 Donald C. Cook Nuclear Power P ant F Unit 2s Indi ana 1 8 05000316 AUTH NAME, AUTHOR AFFILIATION ALEXICH~ M.P. Indiana 8 Michiaan Electt ic Co RECIP. NAME REC IP IENT AFFILIATION DENTONsH R Of f ice of Nuclear Reactor Reaul ation. Director S UBJECT: Aoolication for amend to Licenses DPR 58 8.DPR 74 changing Tech Soec Table 4,3 1 re reactor trio svs instrumentation surveillance reauirements.

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INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 July 8, 1983 AEP:NRC:0591A Donald C.'Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 AMENDMENT TO TECHNICAL SPECIFICATION CHANGE REQUEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Reference:

Letter No. AEP:NRCc0591 dated January 22, 1982

Dear Mr. Denton:

This letter and its Attachments amend the above referenced January 22, 1982 letter as a result of discussions with members of your staff. The subject matter attached is identical to that associated with the January 22, 1982, letter; the only items we are proposing to change are:

1) the content of the individual Technical Specifications associated with Change No. 1, and

2) we are hereby withdrawing the Technical Specification change request contained in Change No. 3.

Change No. 2 remains as proposed in the referenced January 22, 1982/

letter. Change No. 4 has already been incorporated in Technical Specification Amendment Nos. 59 and 42> for Units Nos. 1 and 2 respectively.

Attachment No. 1 to this letter contains a description of the proposed changes and our justification. Attachment No. 2 to this letter contains the proposed changes to Unit Nos. 1 and 2 Technical Specifications.

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Our evaluation of the content of this amended Technical Specification change request shows that no significant hazards considerations are involved, since the amended response does not involve a significant increase in the probability or consequences of an accident previously evaluated> does not create the possibility of a new accident, or one different from any previously evaluatedt and does not involve a significant reduction in the margin of safety.

These proposed changes have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee at its next meeting.

Since this license amendment change proposal is made at the request of your staff to simplify and clarify our original request of January 22, 1982, we interpret that, in accordance with the provisions of 10 CFR Part 170, this change does not require any fee.

This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, M. P. Alex ch MPA/os Vice President cc: John E. Dolan - Columbus R. S. Hunter R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen State Representative G. Charnoff NRC Resident, Inspector at Cook Plant - Bridgman

'I Attachment No. 1 to AEP:NRC:0591A Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Justificatio'n of the Proposed Technical Specification Changes

Discussed below are two groups of proposed Technical Specification (T/S) changes. For convenience, each change is discussed as a separate part. The first group of proposed changes is to Table 4.3-1 'of the Unit No. 1 T/S; the second is to Table 4.3-1 of the Unit

.No. 2 T/S. As stated in the cover letter, these changes are being

proposed to mnend our previous T/S change proposal contained in Change No. 1 of Attachment No. 1 to the January 22, 1982 letter (AEP:NRC:0591). In addition, when the proposed changes are issued, the yT/S for Unit Nos. 1 and 2 will be the same with regard to these particular T/S.

GROUP 1: Obanges to Table 4.3-1 of Unit Ro. 1 Tecbnical Specifications:

PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels (Item 6), so that the surveillances are required in NODES 2 and 3 only when the plant is below the P-6 permissive setpoint. As previously discussed with members of your staff, this change will make, our surveillance requirements closer to those presented in the Standard Technical Specifications f'r Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4.

PART 2 The second proposed change is the addition of a 12-hour (Shiftly) CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6)

This change will make the T/S closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4.

PART 3 The third proposed change is the addition of a requirement to perform a CHANNEL CALIBRATION on the Intermediate Range and Source Range, Neutron Flux Channels (Items 5 and 6) at, least once per 549 days.

This change will make the Unit No. 1 T/S the same as the Unit No. 2 T/S and closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4.

'PART 4 The fourth proposed change is the addition of a requirement to perform a CHANNEL FUNCTIONAL TEST on the Source Range, Neutron Flux Channels (Item 6) at least once per month.

This change will make the Unit No. 1 T/S the same as the Unit No. 2 T/S and closer to the

Standard Technical Specifications for Westinghouse Pressurized Water ReactorsJ NUREG-0452, Revision No. 4.

PART 3 The fifth proposed change is the modification of the surveillance requirements for the High Positive Rate and High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that'the neutron detectors may be excluded from CHANNEL CALIBRATION.

This change will make our surveillance requirements consistent with those presen'ted in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revisions No. 4.

GROUP 2: Changes to Table 4,3-1 of the Unit No. 2 Technical Specifications:

PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels so that the surveillances are required in MODES 2 and 3 only when the plant is below the P-6 permissive setpoint. The justification for this change is the same as that proposed for Unit No.

1.

PART 2 The second proposed change is the addition of a 12-hour (Shiftly) CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6) . The justification for this change is the same as that proposed for Unit No. 1,

'PART 3 The third proposed change is the deletion of the requirement to perform surveillances of the Source Range, Neutron Flux Channel (Item

6) while in Mode 6. As per previous discussions with your staff, it has been agreed upon that the justification submitted in our January 22, 1982 letter is adequate.

'PART 4 The fourth proposed change is the modification of the surveillance requirements for the High Positive Rate anQ High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that. the neutron detectors may be excluded from CHANNEL CALIBRATION.

This change will make our surveillance requirements consistent with those presented in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors, NUREG-0452, Revision No. 4.