ML20206A964
| ML20206A964 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/21/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206A962 | List: |
| References | |
| NUDOCS 9904290108 | |
| Download: ML20206A964 (3) | |
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UNITED STATES s
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 1
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO,150 TO i
FACILITY OPERATING LICENSE NO. NPF-38 i
ENTERGY OPERATIONS. INC.
j 1
WATERFORD STEAM ELECTRIC STATION. UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
I By application dated November 13,1997, Entergy Operations, Inc. (the licensee), submitted a request for changes to the Waterford Steam Electric Station, Unit 3 (Waterford 3), Technical Specifications (TSs). The requested changes would revise TS 6.8.4.a, Primary Coolant Sources Outside Containment, by adding portions of the containment vacuum relief (CVR) and primary sampling systems to the list of systems included in the Primary Coolant Sources Outside Containment Program.
2.0 EVALUATION Current TS 6.8.4.a requires a program to reduce leakage from those portions of the systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the containment spray, safety injection, hydrogen analyzer, and the post-accident sarr wig system. The program requires the following:
1.
Preventive maintenance and periodic visual inspection requirements, and
- 2. Integrated leak test requirements for earn system at refueling cycle intervals or less.
The proposed change will add portions of the CVR a id the primary sampling systems in the list of systems included in the Primary Coolant Sources C utside Containment Program. The CVR system is being added to correct a design error made during the initial licensing phase of Waterford 3 and the primary sampling system is being added based on a plant modification.
Both of these systems have the potential to produce leakage from containment to outside containment during a serious transient or accident. Therefore, by adding both of these systems to TS 6.8.4.a, the licensee will ensure that these systems will comply with the requirements of the program.
9904290108 990421 PDR ADOCK 05000382 P
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.a The licensee stated that the addition of the CVR system and the primary sampling system to the Primary Coolant Sources Outside Containment Program in the TSs will ensure that any leakage
. associated with these potential bypass leakage paths will not exceed the limits used in the Waterford 3 safety analysis or result in a significant increase in the analyzed dose consequences. The leak rate testing on appropriate portions of these systems during each refueling cycle will keep any leakage from this systems to a minimum and the licensee will perform required preventive maintenance on these systems.
The Nuclear Regulatory Commission (NRC) staff has reviewed the proposed changes and concludes that these systems should be irscluded in the Primary Coolant Sources Outside Containment Program because there is a potential that these systems could contain highly radioactive fluids outside containment. The proposed changes will minimize the leakage of primary coolant outside the containment and limit the dose consequences during a serious transient or accident to as low as practical levels. Therefore, these changes are accepteble to the staff.
3.0 STATE CONSULTATION
in accordance witn the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 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 signi-ficant 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 the amendment involves no significant hazards consideration and there has been no public comment on such finding (63 FR 9601). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(g). Pursuant to 10 CFR 51.22(b), no environmentalimpact statement or environmental assessment need be prepared in connection with the issuance of the amendment
5.0 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 the common defense and security or to the health and safety of the public.
Principal Contributor: C. Patel A ril 21, 1999 Date:
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