ML20237G689

Safety Evaluation Supporting Amend 9 to License NPF-49

ML20237G689
Person / Time
Site:	Millstone
Issue date:	08/21/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237G658	List: ML20237G656 ML20237G670 ML20237G689
References
NUDOCS 8709020370
Download: ML20237G689 (2)

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g UNITED STATES y g NUCLEAR REGULATORY COMMISSION 5i :j WASHINGTON, D. C. 20555 i

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, SAFETY EVALUATI0'l BY THE OFFICE OF NUCLEAR REAC9R REGULATION

, RELATED TO AMENDMENT NO. 9 t ' '

, TO FACILITY OPEPATING LICENSE NO. NPF-49 NORTHEAST NUCLEAR ENERGY COMPANY, ET AL. I MILLSTONE. NUCLEAR POWER STATION, UNIT N0. 3 DOCKET NO. 50-423 1.0 ' INTRODUCTION -_

By letter dated December 18,1986, . Northeast Nuclear Energy Company proposed changes to the Millstone Unit 3 Technical Specifications to eliminate redundancy of operational and surveillance requirements on the control room air intake radioactivity moMitor. The changes will delete reference-to the control room air intake radiation monitor in Technical Specification Table

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33.3-6, Radioactive Monitoring Instrumentation for Plant Operations, and the associated Surysillance Table 4.3-3. The reason for this deletion is that all orcrational, testing and surveillance,requireri,ents are. duplicated for thi,s nxnitor in ESF Instrumentation Tables 3.3-3, 3.3-4 and 4.3-2.

2.0 EVALVATIO The control building inlet ventilation radiation monitor is listed as both Engineered Safety Feature Actuation System Instre:nentation (Item 7e, Tables 3.3-3, 3.3-4 and 4.3 2) and Radioactive Monitoring Instrumentation for Plant Operations (Item 3a Tables 3.3-6 and 4.3-31

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The control building inlet. ventilation radiation monitor is mora '

logically associated with the Engineered Safety Feature Actuation  !

Instrumentation because it initiates a control building isolation i signal. The proposed change retains the operational testing and  !

surveillance requirements for this monitor and eliminates unnecessary duplication in the Technical Specifications. We find these changes  ;

acceptable. ~

8709020370 870821 PDR ADOCK 05000423 P PDR

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3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves changes which are administrative in nature.

Accordingly, the amendment meets the elig):sility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10 . Pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

4.0 CONCLUSION

We have concluded, based on the considerations discussed above, that (1) there is reasonable acsurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

I Dated: August 21, 1987 l Principal Contributors:

R. Ferguson l R. Fell l

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