ML20071D318

From kanterella
Jump to navigation Jump to search
Requests License Condition 2.C.(24) Be Revised W/Respect to Rev 2 of Reg Guide 1.97, Instrumentation for Light Water Cooled Nuclear Power Plants to Access Plant Conditions During & Following Accident
ML20071D318
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 03/04/1983
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Adensam E
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8303090343
Download: ML20071D318 (3)


Text

r_ .

TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ol 400 Chestnut Street Tower II March 4, 1983 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dea." Ms. Adensam:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority ) 50-328 As required by the Sequoyah Nuclear Plant unit 1 operating license condition 2.C.(24), we provided tentative schedules for compliance with Regulatory Guide 197 in my April 18, 1981 letter to A. Schwencer and in my July 1, 1981 letter to you. A subsequent similar license condition was imposed in the unit 2 operating license, 2.C.(14).

By my March 15, 1982 letter to you, we provided information to satisfy the unit 1 operating license condition 2.C(24). The information provided included the final Post Accident Monitoring (PAM) instrumentation list and

, design criteria as well as TVA plans for upgrading of specific plant

! instrumentation. Based on the new guidelines of SECY-82-111B (NRC Generic l Letter 82-33), we consider the unit 1 operating license condition 2.C.(24) satis fied.

The unit 2 operating license condition 2.C.(14) requires implementation of

" modifications necessary to comply with Revision 2 of Regulatory Guide 1.97 by June 1983." SECY-82-111B, issued as Supplement 1 to NUREG-0737, allows compliance with Regulatory Guide 1.97 on a schedule consistent with an integrated approach for implementation of all the requirements of i Supplement 1 to NUREG-0737. We therefore request the license condition be revised as provided in the Enclosure. In accordance with the provisions of 10 CFR Part 170, because this proposed change is administrative in nature and results' from revised NRC requirements and guidelines, no fees are being forwarded at this time.

8303090343 830304 1 PDR ADOCK 05000327 P PDR An Equal Opportunity Employer j

4 Director of Nuclear Reactor Regulation March II,1983 If you have any questions concerning this matter, please get in touch with J. E. Wills at FTS 858-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, llanager Nuclear Licensing Sworn,go d subscr before me thi W . day of ( M 1983 d'/24ff fa <

n-&tN2V /

Rob'ar ublii My Co ssion Expires -

/ /

Enclosure cc: U.S. Nuclear Regulatory Commission (Enclosure)

Region II Attn: Mr. James P. O'Reilly Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

j. 2 ENCLOSURE LICENSING CONDITION 2.C.14 - COMPLIANCE WITH REGULATORY GUIDE 1 97 Existing Condition TVA shall implement modifications necessary to comply with Revision 2 of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"

dated December 1980, by June 1983 Proposed Condition TVA shall comply with the intent of SECY-82-111B (issued as Supplement 1 to NUREG-0737) with respect to Revision 2 of Regulatory Guide 1.97,

" Instrumentation for Light Water Cooled Nuclear Power Plants to Access Plant Conditions During and Following an Accident," dated December 1980.

Basis for the Proposed Change SECY-82-111B, which revises the requirements for Regulatory Guide 1 97, does not require compliance with the regulatory guide by June 1983 TVA plans to provide a schedule for compliance with SECY-82-111B in April 1983 as required by NRC. The revised license condition will allow TVA to comply with the regulatory guide on a schedule consistent with the requirements of SECY-82-111B for an integrated approach to implementation. The schedule for implementation will be plant specific and determined by the NRC licensing project manager, as required by SECY-82-111B.

.