ML20100C236
| ML20100C236 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/18/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100C235 | List: |
| References | |
| NUDOCS 8503280781 | |
| Download: ML20100C236 (2) | |
Text
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UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION D
j WASHINGTON D. C. 20656 4
SAFETY EVALUATION REPORT RELATED TO AMENDMENT NO. 41 TO FACILITY OPERATING LICENSE NPF-9 AND TO AMENDMENT NO. 22 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 I.
INTRODUCTION By letter dated September 28, 1984, the licensee proposed amendments to license Nos. NPF-9 and NPF-17 which would change the Technical Specifica-tions by deleting the surveillance requirements for four Steam Generator Blowdown Valves (BB140, BB141, BB142, B8143) listed in Specification Table 3.6-2, Containment Isolation Valves. The licensee is making modifications to the plant which will make it acceptable to eliminate these valves and replace them with spool pieces.
II.
EVALUATION The purpose of the Steam Generator Blowdown Recycle System (referred to by the licensee as the BB system) is to maintain acceptable steam generator shell-side chemistry and to conserve the blowdown water through recycling.
Each steam generator has one BB line exiting the containment and entering the Auxiliary Building, resulting in four containment penetrations for each unit.
Each of these containment penetrations has containment isola-tion capability provided by valves RBI through BB4 on the Auxiliary Building side and valves BBS through BB8 on the Containment side. These eight valves are included in the leak test program pursuant to Appendix J to 10 CFR 50.
l Steam generator blowdown valves BB140 through BB143, which are located l
inside containment near the steam generators, were originally installed l
to pennit pipe class changes from licensee's Class B to F, which were necessary to accomnodate non-safety related BB subcooling heat exchangers in the lines between the steam generators and the containment wall. The licensee's Class 8 piping is ASME Class 2 or Quality Group B, while their Class F is not safety grade.
In order for the Main Steam System (steam generators, main steam lines, etc.) to be considered a closed system inside containment as required by General Design Criterion 57, the non-safety grade heat exchangers and their Class F piping had to be isolated from the rest of the Main Steam System by valves BB140 through BB143. Hcwever, the licensee has removed the heat exchangers. The piping sr,ools that replaced the heat exchangers and the remaining Class i
F piping are being upgraded to Class B.
Thus, all the BB system inside containment (and that portion to and including valves 881 through BB4 outside containment) will be Class B.
Therefore, the whole Main Steam System qualifies as a closed system inside containment, and the four 8503290781 950318 PDR ADOCK 05000369 P
.2-valves, BB140 through BB143, are no longer necessary to serve the safety (isolation) function for which they were originally installed. They are being removed from the lines and, consequently, must be deleted from the table to maintain consistency between the design and the Technical Specifi-cations.
Based on our review, we conclude that because of the plant modifications discussed above, valves BB140, BB141. 88142, and B8143 are no longer necessary to serve their earlier safety (isolation) function (i.e., the modified Steam Generator Blowdown Recycle System is such that the Main Steam System will satisfy the requirements of General Design Criterion 57 and Appendix J to 10 CFR 50 without these four valves), and their deletion from Specification Table 3.6-2, Containment Isolation Valves, is therefore acceptable.
III. ENVIRONMENTAL CONSIDERATION These amendmants involve a change in use of facility components located within the restricted area as defined in 10 CFR Part
- 0 and change a 2
surveillance requirement. The staff has detennined 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 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, the amendments meet the eligibility) criteria for categorical exclusion set forth in 10 CFR Section 51.22(c (9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepare (inconnectionwiththeissuanceoftheseamendments.
IV.
CONCLUSION The Coinnission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (49 FR 50802) on December 31, 1984, and consulted with the state of North Carolina.
No public comments were received, and the state of North Carolina did not have any. comments.
We have concluded, based on the considerations discussed above, that:
will not be. endangered by operation in the proposed manner, and (2) pub (1) there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Commission's regu-
- ations 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.
Principal Contributors:
D. S. Hood, Licensing Branch No. 4, DL J. Pulsipher, Containment Systems Branch,;DSI Dated: March 18, 1985
.