ML20149B767
| ML20149B767 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 07/10/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20149B760 | List: |
| References | |
| NUDOCS 9707150036 | |
| Download: ML20149B767 (3) | |
Text
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UNITED STATES p-j NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.C. Samma -1
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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 4
RELATED TO AMENDMENT NO. 91 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 90 TO FACILITY OPERATING LICENSE NO. NPF-66, j
AMENDMENT NO. 84 TO FACILITY OPERATING LICENSE NO. NPF-72, i
i AND AMENDMENT NO. 83 TO FACILITY OPERATING LICENSE NO. NPF-77 COMMONWEALTH EDISON COMPANY BYRON STATION. UNIT NOS. I AND 2 BRAIDWOOD STATION. UNIT NOS. I AND 2 DOCKET NOS. STN 50-454. STN 50-455. STN 50-456 AND STN 50-457
1.0 INTRODUCTION
By application dated January 20, 1997, Commonwealth Edison Company (Comed, the licensee), requested changes to Technical Specification (TS) 3.6.3, l
" Containment Isolation Valves," for the Byron and Braidwood Nuclear Power l
Stations, Unit I and 2.
The proposed changes would reflect modifications associated with steam generator (SG) replacements at Byron, Unit I and Braidwood, Unit 1.
The TSs Table of Isolation Valves would be revised to reflect (a) the deletion of feedwater isolation bypass valves for the replaced i
SGs, and (b) the reassignment of certain isolation valves to different containment penetrations; consistent with the modifications described below.
TS pages for Unit 2 of each station are affected because Units 1 and 2 share common TS pages.
2.0 EVALUATION Comed is replacing the original Westinghouse Model D4 SGs at Byron, Unit 1, and Braidwood, Unit 1, with Babcock & Wilcox International (BWI) SGs. As part of the project, parts of the main feedwater and auxiliary feedwater piping will be modified. Feedwater bypass isolation valves will be deleted and different containment penetrations will be used for main feedwater piping.
' More specifically:
Single feedwater nozzle delivery will replace dual nozzle delivery. The original SGs have two nozzles (one for main feedwater and one for feedwater tempering), whereas the replacement SGs each have a single main feedwater nozzle.
The 4
existing Feedwater Tempering containment penetrations will be used for chemical feed and the new wet layup system.
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1 j The feedwater isolation valve bypass line required for the original preheater SGs, as part of the Water Hammer Prevention System for limiting preheater vibration, is no longer required.
Piping and associated valves will be removed.
Existing Auxiliary Feedwater lines which discharge into the existing Feedwater Tempering lines outside containment will be rerouted to join the Main Feedwater Lines outside containment.
The use of single feedwater nozzle delivery (shared by main and auxiliary feedwater systems) is acceptable under Standard Review Plan (SRP)
Section 10.4.9, which specifically indicates that auxiliary feedwater may be delivered to a SG by a separate line or by joining the main feedwater line.
4 The new wet layup system will facilitate maintenance operations and is not j
i anticipated to have any adverse safety consequences or any adverse affects on SG chemistry.
The licensee's application states that the existing isolation provisions conform to General Design Criteria 54 and 57 and that such conformance will not be affected by the modifications nor will isolation instrumentation be changed.
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3.0
SUMMARY
Based on the information provided in the application and its finding that the proposed changes are consistent with standard acceptance criteria for l
feedwater systems and isolation capability, the staff concludes that the i
proposed TS changes are acceptable.
4.0 SJAJE CONSULTATION In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the 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 incrr :e in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the i
amendments involve no significant hazards consideration, and there has been no public comment on such finding (62 FR 11489). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 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 the amendments.
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6.0 CONCLUSION
The Commission has 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, -(2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: W. Long Date:
July 10, 1997 I
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