ML17326A518

Application to Amend App a Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirements,Rcs Heatup & Cooldown Curves, Reporting Requirements & Undervoltage Protection & Monitoring Scheme.Fee Encl

ML17326A518
Person / Time
Site:	Cook
Issue date:	02/22/1980
From:	Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17326A519	List: ML17326A518 ML17326A520 ML17326A522
References
NUDOCS 8002270323
Download: ML17326A518 (7)

Text

INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 18 Bo WL IN G G R E EN ST ATION NEW YORK, N. Y. 10004 February 22, 1980 AEP:NRC:00313 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License No.s DPR-58 and DPR-74 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This letter and its attachments request changes in several of the Appendix 'A'echnical Specifications for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2. Attachment 'A'o this letter contains the description and review of each change. Attachment the appropriate revised pages. A number of these changes 'B'ontains are editorial in nature and are noted as such. Attachment supporting information for change No. 2. We request that 'C'rovides the NRC file and process this technical specification change package as a single amendment.

All of the proposed technical specification changes contained her'ein have been reviewed and approved by the Plant Nuclear Safety Committee. The result of these reviews indicates that in no instance will the proposed technical specification change adversely affect the health and safety of the public.

This appli'cation for technical specification revision is considered to be a Class II License Amendment as per the provisions of 10 CFR 170.22.

As required by Part 170 Subsection 22 a check for $ 1,600.00 accompanies this submittal.

Very truly yours, John E. Dolan ~lP ~o Vice President Dool~etu~=>~>

CQIItI'0l tOPXg-/PE

+ gg Date EA=RC of DOCaIIIenh IFGUMTORY DOCAH F)1.E 80 CD "70 Dz.g

t1r. Harold R. Denton, Director AEP:NRC:00313 cc: R. S. Hunter R. M. Jurgensen G. Charnoff R. C. Callen D. V. Shaller

ATTACHMENT 'A'O AEP:NRC:00313.

PROPOSED TECHNICAL SPECIFICATION REVISIONS DONALD C. COOK NUCLEAR PLANT UNIT NOS. 1 AND 2

~ I ~

7

~CN 2 . 1 - U it N . 1 d 2 Unit No. 2 Technical Specification No. 4.7.1.2.a.2 - Page 3/4 7-5 Unit No. 1 Technical Specification No. 4.7.1.2.a.5 - Page 3/4 7-6 This change deletes the 'exemption'f positively controlled valves (those valves which are locked, sealed, or otherwise secured in position) from the Auxiliary Feedwater System surveillance requirement of a monthly verification of valve position. This change, performed in accordance with NRC Recommendation GS-2, as detailed in the attachment to Mr. D. G.- Eisenhut's letter of October 30, 1979, does not represent any additional surveillance requirement and fulfills the committment contained in our response letter of December 11, 1979, AEP:NRC:00300.

Technical Specification 6.8.1.c requires that "written procedures shall be established, implemented and maintained..." "...for the surveillance and test activities of safety related equipment."

N.2-012N.idly

'02 The Technical Specification RCS Heatup and Cooldown curves, Figures 3.4-2 and 3.4-3, are being revised to reflect the results of the analysis of the first material surveillance capsule removed from the Unit No. 1 reactor pressure vessel. A report prepared by Southwest Research Inc. is submitted in support of this change (Attachment 'C').

~Ch N. 2 Ui N. 10ly (Edit Specification 6.9.2.f incorrectly references Specification 4.7.9.1.3.

The correct reference is Specification 4.7.7.1.3, "Seal Source Leakage".

The revised page reflects the correct reference.

~Ch N . t - U 1 N . 2 0 1 (Edi Specifications 6.9.2.b - "Seismic Monitoring Instrumentation" and 6.9.2.c - "Meteorological Monitoring Instrumentation", should refer to Unit No. 1 Specifications 3.3.3.3 and 3.3.3.4, respectively. The revised NTT Ny 1 t UN 21 t th f

~Ch N. 2-Ui N .1 d2 Technical Specification Tables 2.2-1 and 3.3-4 have been amended to reflect the 6/ (of narrow-range instrument span) increase in the "SG Hater Level Low-Low" trip and ESF actuation setpoint due to reference leg heatup following a hypothetical high energy line rupture inside containment. The revised setpoints, 15% and 215 for Unit Nos. 1 and 2 respectively, were forwarded to the NRC via our response to IE Bulletin No. 79-21, AEP:NRC:00271, dated November 5, 1979.

~ChN.6 II'N.l d2 The undervoltage protection and monitoring scheme will be modified as per the proposed modifications detailed in Attachment No. 7 to our AEP:NRC:00268 submittal dated December 17, 1979. The required modifications will be completed prior to startup from the next regularly scheduled refueling outage for each Unit. Subsequent to these modifications, the 'degraded voltage'unction will be monitored on the 4 kv safety buses; Unit No. 1 buses TllA,"and T11D and Unit No. 2 buses T21A and T21D. As shown on revised Table 3.3-3, the 'degraded voltage'unction will be monitored by three channels per bus, with a two out of three actuation lgglc.

Unit No. 1 Technical Specification Table Nos. 3.3-3, 3.3-4, and 4.3-2 have been revised to incorporate the changes discussed in (5) and (6) above. The surveillance requirements of Table 4.3-2, Item Nos. 7 and 8, have been revised to reflect the requirements of Table 3.3-3 for both Units.