ML20059B863
| ML20059B863 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/25/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059B858 | List: |
| References | |
| GL-86-10, GL-88-12, NUDOCS 9310290122 | |
| Download: ML20059B863 (4) | |
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UNITED STATES
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 84 TO FACILITY OPERATING LICENSE NO. NPF-49 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
MILLSTONE NUCLEAR POWER STATION. UNIT N0. 3 DOCKET NO. 50-423
1.0 INTRODUCTION
By letter dated July 31, 1992, the Northeast Nuclear Energy Company (the licensee), submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 3 Facility Operating License No. NPF-49 and the attached Technical Specifications (TS) and operating licensee. The requested changes would remove requirements from the license and Technical Specifications pertaining to the Fire Protection Program, and place these same requirements in operating procedures.
2.0 EVAtVATION The proposed changes would relocate the Millstone 3 fire protection requirements from Millstone 3 TS to the Millstone 3 fire protection program in accordance with the guidance provided in Generic Letter (GL) 86-10,
" Implementation of Fire Protection Requirements," April 24, 1986, and GL-88-12, " Removal of Fire Protection Requirements from Technical Specifications," August 2, 1988. The following evaluation is based on the staff's review of the letter of July 31, 1992, and the rupporting materials provided with the letter.
The TS changes proposed by NNEC0 are as follows:
1.
Delete the definition of fire protection operational test from TS 1.14 and incorporate into Operating Procedure OP-3273, Revision 0, " Technical Requirement Manual" (TRM).
2.
Delete TS 3.3.3.7 for fire detection instrumentation and Table 3.3-11 and its associated bases and incorporate into OP-3273.
3.
Delete TSs 3.7.12.1, 3.7.12.2, 3.7.12.3, 3.7.12.4, 3.7.12.5, and 3.7.12.6 and their associated bases for fire suppression water system, spray and/or sprinkler systems, carbon dioxide systems, halon systems, fire hose stations, and yard fire hydrants and incorporate into OP-3273.
9310290122 931025 PDR ADOCK 05000423 p
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Delete TS 3.7.13 and its associated bases for fire rated assemblies and incorporate into OP-3273.
5.
Delete TS 6.2.2.F for the site fire brigade and incorporate into OP-3273.
6.
Delete TS 6.4.2 requirements celated to the fire brigade training program and incorporate into OP-3273.
7.
Add TS 6.5.1.6 (k) to include the. review of the fire protection program and implementing procedures as n additional responsibility of the Plant Operations Review Comittee (PORC).
8.
Add TS 6.5.2.6 (i) to include responsibility for the review of the comon site fire protection program and implementing procedures by the Site Operations Review Comittee (SORC).
The licensee also proposed the following fire protection license condition:
i Northeast Nuclear Energy Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER (NUREG-1031) issued July 1984 and Supplements Nos. 2, 4, and 5 issued i
September 1985, November 1985, and January 1986, respectively, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Comission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
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i The licensee retained the TS related to the capability for safe shutdown following a fire in the TS.
j The NRC staff reviewed the license amendment request for Millstone 3 against the guidance provided in GLs 86-10 and 88-12. Generic Letter 86-10 requested that licensees incorporate the NRC-approved fire protection program in their Final Safety Analysis Report (FSAR). Generic Letter 88-12 addressed the elements a licensee should include in a license amendment request to remove fire protection requirements from TS. These elements are (1) the NRC-approved fire protection program must be incorporated into the FSAR; (2) the Limiting Conditions of Operations and Surveillance Requirements associated with fire j
detection systems, fire suppression systems, fire barriers, and the administrative controls that address fire brigade staffing would be deleted from the TS (the existing administrative controls related to fire protection audits would be retained in the TS); (3) all operational conditions, remedial actions, and test requirements presently included in the TS for these systems, as well as the fire brigade staffing requirements, shall be incorporated into the fire protection program; (4) the standard fire protection license condition in GL 86-10 must be included in the license; (5) the Unit Review Group (Onsite Review Group) shall be given responsibility for the review of
, the fire protection program and implementing procedures and for the submittal of recommended changes to the Company Nuclear Review and Audit group (Off-site or Corporate Review Group); and (6) fire protection program implementation shall be added to the list of elements for which written procedures shall be 7
established, implemented, and maintained.
The licensee incorporated the Millstone 3 fire protection program into its FSAR in January 1986. The current TS operability and rurveillance requirements for the detection systems, fire suppression systems, fire rated assemblies, and the fire brigade staffing requirements will be incorporated into the operating procedures and the FSAR. TS 6.5.2.6 (i) will be added to include the responsibility for review of the common site fire protection.
program and implementing procedures by the 50RC. Therefore, the licensee has satisfied elements 1 through 3 of GL 88-12. The licensee proposed the standard fire protection license condition specified in GL 86-10 for Millstone 3.
Therefore, the licensee has met element 4 of GL 88-12.
Elements 5 and 6 of GL 88-12 addressed changes to the administrative controls section of the TS. To satisfy these elements, the licensee proposed to add TS 6.5.1.6 (k) to include the review of the fire protection program and implementing procedures as an additional responsibility of the PORC and TS 6.5.2.6 (i) to include the responsibility for the review of the common site fire protection program and implementing procedures by the 50RC.
Element 6 of GL 88-12 also addressed adding fire protection program implementation'to the list of elements for which written procedures shall be established, implemented, and maintained. TS 6.8.1 (g) already addresses the fire protection program, therefore, no changes are required.
Therefore, the licensee has satisfied elements 5 and 6 GL 88-12.
The licensee's TS amendment request for Millstone 3 is in accordance with NRC guidance provided in GLs 86-10 and 88-12 and is, therefore, acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut 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 amendment also relates to changes in recordkeeping or adminstrative procedures or requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no
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. 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 the amendment involves no significant hazards consideration, and there has been no public comment on such finding (57 FR 40217).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
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.
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:
A. Singh Date:
October 25, 1993