ML20235E917
| ML20235E917 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/23/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235E870 | List: |
| References | |
| NUDOCS 8707130138 | |
| Download: ML20235E917 (2) | |
Text
7 b
i I.
s.n stop 1
o UNITED STATES 8"
1 NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555
..... p$
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.105 TO FACILITY OPERATING LICENSE NO. DPR-39 AND AMENDMENT N0. 95 TO FACILITY OPERATING LICENSE NO. DPR-48 COMMONWEALTH EDISON COMPANY ZION NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-295 AND 50-304 i
1.0 INTRODUCTION
By letter dated April 9,1987, the licensee (Commonwealth Edison) for Zion Nuclear Power Station, Units 1 and 2, proposed changes to Sections 3.9 and i
4.9 of the Zion Technical Specifications (TS) with regard to containment isolation valves. These proposed TS changes expand the containment isolation valve listing based on information contained in the Zion FSAR to conform with the guidance described in NUREG-0452, Rev. 4, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors." In addition, the proposed changes will eliminate the existing conflict in requirements addressed in Section 3.9.4.c for 3-loop operation.
2.0 EVALUATION We have reviewed the licensee's submittal and find that the expanded valve listing will include the appropriate containment isolation valves for containment penetrations. The proposed changes do not affect the design and operation of the containment isolation capability which was previously found acceptable (as stated in the Zion SER issued on October 6,1972) by the staff.
The proposed TS changes will also delete the guidance in Section 3.9.4.c that provided for the option of 3-loop operation following the failure of a main steam isolation valve. The licensee indicated that Section 2.c.4 of the Zion Composite License prohibits operation with less than 4 reactor coolant loops above approximately 10% of full reactor power. Thus, the guidance previously described in Section 3.9.4.c conflicted with this license requirement and is not applicable.
3.0 TECHNICAL FINDINGS Based on the staff's review, we find that the licensee's proposed TS changes are acceptable. We further conclude that deletion of the option of 3-loop operation from TS Section 3.9.4.c is an acceptable clarification based on existing license constraints.
e707130138 e70623 DR ADOCK 050 5
i a
3 4
1 I ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of the facilities, components located within the restricted areas as defined in 10 CFR 20. The staff has determined that these amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR Sec 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
5.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance 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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated: June 23,1987 PRINCIPAL CONTRIBUTOR:
D. Shum j