ML20149L162
| ML20149L162 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/12/1988 |
| From: | NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20149L135 | List: |
| References | |
| GL-84-09, GL-84-9, TAC-R00098, TAC-R00099, TAC-R00100, TAC-R100, TAC-R98, TAC-R99, NUDOCS 8802240136 | |
| Download: ML20149L162 (2) | |
Text
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UNITED STATES
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SAFETY EVALUATION BY THE OFFICE OF SPECIAL PROJECTS SUPPORTING AMEN 0 MENT NO.142 TO FACILITY OPERATING LICENSE NO. OPR-33 AMEN'DMENT NO.138 TO FACILITY OPERATING LICENSE NO. DPR-52 AMENDMENT NO.113 TO FACILITY OPERATING LICENSE NO. OPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 DOCKETS NOS. 50-259, 50-260 AND 50-296 1.0 INTPODUCTION The proposad amendments would impose a limit on reactor operation when nitrogen is not beino used to supply the pneumatic control system inside containment.
The amendrent request is in response to Generic letter 84-09, Hydrogen Recombiner Capability. The proposed amer.dments also delete an obsolete reference to the fire-related startup retesting progran.
2.0 EVALUATION The proposed amerdments would add new technical specification requirements in response to Generic Letter (GL) 84-09, Hydrogen Recombiner Capability.
Ti;e purpose of these technical spacifications is to limit the possibility cf the pneurotic control system being an oxygen source inside primary containment during resctor power operation.
The primary pneumatic supply to the containment is provided by compressors I
wHch take suction from the nitrogen inerted containment atmosphere itself.
The system is also provided with a backup supply of compressed air from the plant control air system anc prior to restart of Unit 2 modifications will be completed so that there will be an external supply of compressed nitrogen from the Containmnt Atmospheric Cilution System.
The air supply is normally isolated by a lock closed manucl control valve which is closed during tires when the containment is inerted by nitrocen. Once the above modifi ation is cocplete ane; the air supply control valve is locked closed, this systen ber.omes the ritrogen containment atrospheric dilution system which satisfias the requirements of GL 84-09.
This proposed change would linit operation of the reactor with the air supply i
valves open by requiring the plant to be in the cold shutdown condition witHn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of opening the locked closed air supply v&lves, it would reduce the possibility of the contairrent becoming dainerted in a post-accident situation while at thi same tire allowinq for A more orderly shutdewn on loss of ncr-nl preuratic suoply.
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This proposed change would add more stringent technical specification requirements in accordance with Generic Letter 84-09. Therefore, the staff has concluded that the proposed technical specification changes will not reduce the margin of nuclear safety.
The proposed amendments would also delete the first phrase of technical specification 3.7.A.5.a which is purely administrative and is not related to the other changes except that it' is in the same technical specification section. The deleted phrase makes this requirement effective after the completion of the fire-related startup retesting program.
Since this program has been completed, the recuire-ment is effective and deleting this phrase will only remove extraneous information.
No technical specification requirements are changed.
Based on the above evaluation the staff finds the proposed changes will enhance the safe operation of the plant or are administrative in nature and, therefore, the proposed changes to the technical specifications are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
The amendments Nolve a change to a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements. The 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 increase in individual or cumulative occupational radiation exposure. The Comission has creviously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public coment on such finding. 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 nor environmental assessment need be prepared in connection with the issuance of these amendments.
4.0 CONCLUSION
The staff 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, and (2) such activities will be conducted in compliance with the Comission's re-gulations, &nd the issuance of the amendments will not be inimical to the ccmon defense and security nor to the health and safety of the public.
l Principal Contributor: Jchn Stang IMted: February 12. D83 1