ML19351D734
| ML19351D734 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/02/1977 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WYR-77-43, NUDOCS 8011170694 | |
| Download: ML19351D734 (3) | |
Text
Propo;cd Chang No. 145
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f,3upplem;nt IIo. 3 Tct: phone 617 366-901l rwx 7s0 390-0739 YANKEE ATOMIC ELECTRIC COMPANY
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May 2,1977
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Attention: Office of Nuclear Reactor Regulation O
Subject:
Core XIII Loss of Coolant Accident Analysis Reference (1)
License No. DPR-3 (Docket No. 50-29)
(2)
Proposed Change No. 145, Supplement No. 1, April 13, 1977.
(3)
Proposed Change No. 145, January 6, 1977.
(4)
Antonopoulos, P.T.,
Husain, A. " Method for Calculating End-of-Bypass Time for Yankee Rowe Lors-of-Coolant Accident Analysir,, YAEC-1125, March, 1977.
Dear Sir:
Pursuant to Section 50.59 of the Commission's Rules and Regulations, Yankee Atomic Electric Company hereby requests the authorization to make the following changes:
PROPOSED CHANGE: Reference is made to the Technical Specifications of License No. DPR-3 and Attachment B, " Yankee Nuclear Power Station Core XIII Performance Analysis", of Reference (2) above.
It is proposed that:
(1)
The attached Figure 3.2-1 replace the corresponding figure in the Technical Specifications, (2) the attached Table of Contents replace the corresponding page in Reference (2), and (3) the attached Appendix A be included as part of the Core XIII Performance Analysis submitted in Reference (2).
REASCM FOR CHANGE: Yankee Nuclear Power Station Core XIII large break loss-of-coolant accident
- slysis has been completed for beginning of cycle conditions. This
- sis is attached to this letter as Appendix A.
Figure 3.2-1 of the b nical Specifications has been c*anged to reflect the results of this analysis. This analysis has been conducted with assumptions appropriate to the proposed d-'ign changes to the current ECC Systems as outlined in Reference (?) and to changes in our approved ECCS Evaluation Model as presented in Reference (4).
F 8011170 [
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Unitcd Statas Nucl6tr R39ulatory Comiscion May 2, 1977 Atta Offico_of Nuclear Reactor Regulation Page Two SAFETY CONS'[DERATIONS : Appendix A " Yankee Nuclear Power Station Core XIII Large Break Loss-of-Coolant Accident Analysis" attached hereto addresses the safety aspect of this change with respect to large break loss-of-coolant accident analysis. Small break loss-of-coolant accident analysis must be addressed in a future supplement to this change.
Based on the considerations herein, it is concluded that there is reasonable assurance that Core XIII operation within the proposed specifications will not endanger the health and safety of the public.
This proposed change has been reviewed by the Nuclear Safety Audit and Review Comittee.
SCHEDULE OF CHANGE: The Core XII-XIII refueling is scheduled to commence June 3, 1977. We respectfully request review of this Proposed Change by the Commission as soon as practical.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY D. E. Vandenburgh Senior Vice President COMMONWEALTH OF MASSACHUSETTS)
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COUNTY OF WORCESTER
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Then personally appeared before, D. E. Vandenburgh, who being duly sworn, did stato that he is Senior Vice President of Yankee Atomic' Electric Company and that he is duly authorized to execute and file the foregoing request in the name snd on the behalf of Yankee Atomic Electric Company, and that the statements therein are true to the best of his knowledge and belief.
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Armand R. Soucy Notary Public My Commission Expires September 9, 1977
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