ML20012G695
| ML20012G695 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/08/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012G694 | List: |
| References | |
| NUDOCS 9303110371 | |
| Download: ML20012G695 (2) | |
Text
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UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 7
y WASHINGTON. D. C. 20555
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENuMENT NO. 97 TO FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 89 TO FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY. INC.
JOSEPH M. FARLEY NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated October 13, 1992, the Southern Nuclear Operating Company, Inc.
(the licensee), sube.itted a request for changes to the Joseph M. Farley Nuclear Plant, Units 1 and 2 (Farley), Technical Specifications (TS).
The requested changes would revise Technical Specification 3/4.4.5 and Bases Section 3/4.4.5 to include new requirements with respect to operability and surveillance of power-operated relief valves (PORVs) and block valves.
The changes are based on the guidance contained in Generic Letter (GL) 90-06 and are intended to enhance the reliability of the PORVs and block valves.
2.0 BACKGROUND
On June 25, 1990, the staff issued GL 90-06, " Resolution Of Generic Issue 70,
' Additional Low-Temperature Overpressure Protection for Light-Water Reactors,'
Pursuant to 10 CFR 50.54(f)." The GL represented the technical resolution of the above-mentioned generic issues.
Generic Issue 70, " Power-0perated Relief Valve and Block Valve Reliability,"
involves the evaluation of the reliability of power-operated relief valves (PORVs) and block valves and their safety significance in PWR plants The GL discussed how PORVs are increasingly being relied on to perform safety-related functions and the corresponding need to improve the reliability of both PORVs and their associated block valves.
Proposed staff positions and improvements to the plant's TS were recommended to be implemented at all affected facilities.
This issue is applicable to all Westinghouse, Babcock & Wilcox, and Combustion Engineering designed facilities with PORVs.
Generic Issue 90, " Additional Low-Temperature Overpressure Protection for Light-Water Reactors," addresses concerns with the implementation of the requirements set forth in the resolution of Unresolved Safety Issue (USI) A-26, " Reactor Vessel Pressure Trans:'nt Protection (Overpressure Protection)."
The GL discussed the continuing occurrence of overpressure events and the need to further restrict the allowed outage time for a low-temperature overpressure protection channel in operating modes 4, 5, and 6.
This issue is only applicable to Westinghouse and Combustion Engineering facilities.
9303110371 930308 PDR ADOCK 05000348 P
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, By letter dated October 13, 1992, the licensee proposed changes to the Farley TS in response to GL 90-06.
3.0 EVALUATION The actions proposed by the NRC staff to improve the reliability of PORVs and block valves represent a substantial increase in overall protection of the public health and safety and a determination has been made that the attendant costs are justified in view of this increased protection. The technical findings and the regulatory analysis related to Generic Issue 70 are discussed in NUREG-1316, " Technical Findings and Regulatory Analysis Related to Generic Issue 70 - Evaluation of Power-0perated Relief Valve Reliability in PWR Nuclear Power Plants."
The proposed changes to the Farley TS included in the licensee's letter of October 13, 1992, are consistent with that proposed in the staff's GL (Example: One of the proposed changes involves plant operations with the block valves closed due to leaking PORVs. The licensee has adopted the staff position by stipulating that power be maintained to the block valve during such conditions so that they can be readily opened from the control room upon demand....)
The staff has reviewed the licensee's proposed modifications to the Farley TS.
Since the proposed modifications are consistent with the staff's position previously stated in the GL and found to be justif.T9d in the above-mentioned regulatory analysis, the staff finds the proposed modifications to be acceptable.
4.0 STATE CONSULTATION
l In accordance with the Commission's regulations, the State of Alabama official was notified of the proposed issuance of the amendment.
The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to 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 amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that m.y be released offsite, and that there is no significant increase in individual or cumulative occupational-radiation i
exposure. The Commission has previously issued a proposed finding that the.
amendment involves no significant hazards consideration, and there has been no public comment on such finding (58 FR 7005). _ Accordingly, the amendment meets 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 amendment.
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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 amendment will not be inimical to t' a common defense and security or to the health and safety of the public.
Principal Contributors:
R. Kirkwood S. Hoffman Date:
March 8, 1993 I
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