ML20127P580
| ML20127P580 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/26/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127P573 | List: |
| References | |
| NUDOCS 9302010336 | |
| Download: ML20127P580 (2) | |
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UNITED STATES (g s..J) [i H
NUCLEAR REGULATORY COMMISSION hE-y WASHINoTON. D C M46 SAlfTL[yALVATION BY THE Of flCE Of _ NUCLEAR REACTOR REGUL ATION REL ATED TO AMLNDRERLF0.189 10 FACILITY OPJRATING LICENSE NO. EPJ-1 PORTLAND GENERAL ELECTRIC COMPAN1 THE C1JY OF EMERL_QRfl0B PAClfl0 POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DRCKET NO. 50-344 1.0 Jh]TfR000CT10B By letter dated November 5,1992, Portland General Electric Company, et al.
(PGE or the licensee) submitted a request for changes to the Technical Specifications (TS) for Trojan Nuclear Plant.
The licensce proposes to modify 1rojan Technical Specification 3/4.3.3.7, " Fire Protection Instrumentation."
lhis amendment request would revise the list of fire detection instruments (Table 3.3-10) and surveillance requirements found within the specification to reflect modifications to the fire detection system, which were made to ensure compliance with the National Fire Protection Association Standard on Automatic fire Detectors (NFPA 72E).
This amendment request is the result of a cammitment made by the licensee to the U.S. Nuclear Regulatory Commission in licensee Event Report No. 92-15, dated July 17, 1992.
2.0 EVALVATION licensee Event Report No. 92-15 discussed a failure by the licensee to follow established procedures in processing a design change package involving a required license change. Modifications to the fire detection system involved replacing smoke (ionization) detectors with heat (thermal) detectors in certain plant areas. Although the modifications to the fire detection system were necessary to bring it into compliance with the NFPA 72E standards, the error led to the implementation of the design change without the required approval of the U.S. Nuclear Regulatory Conmission.
Technical Specification changes for the fire detection system involve primarily administrative and editorial changes, since these changes reflect upgrading the plant to meet NFPA standards, and this may be considered more restrictive.
As such, these changes will enable the Trojan Technical Specifications to match the current plant configuration.
These changes entail instrument locations, types of detectors, surveillance requirement:,, and minimum operability requirements for TS 3/4.3.3.7 for various fire detection zones, as found in Table 3.3-10.
The criterion used to establish the mininum 9302010336 930126 PDR ADOCK 0500 4
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operability iequirements for the detectors in each fire detection zone is that at least 50 percent of the detectors shall be operable.
The staff has teviewed the proposed changes to the Trojan Technical Soecification 3/4.3.3.7, " Fire Protection Instrumentation," as outlined in the licensee's submittal dated November 5, 1992.
The staff has determined that these changes are warranted, may be considered administrative in nature, and may be more restrictive than current requirements. These changes were necessary in order to meet NFPA standards. Therefore, the staff approves the modifications to the Trojan Technical Specification 3/4.3.3.7, " fire Protection Instrumentation."
3.0
$1A,lLQ.QN1QLIAIJ.03 In accordance with the Commission's regulations, the Oregon State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 U EIRONMFETAL CONSIDERATIQ3 The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR
' art 20 and changes rurveillance requirements.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no-significant change in the types, of any eff!uents 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 consi& ration, and thera has been no public comment on such finding (57 rn bbi46). Accordingly, the amencment muets the eligioilitv critoria for cate.orical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CF51 Sl.22(t)) no environmental impa(t statement or envirunmental assessment need be prepared in connection with the issuance of the amendment.
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The Commission has concluded, based on the considerations discussed above, tht' (1) there h reasonable assurance that the health and safety of the put ic will not be endangered by operation in the proposed manner,-(2) such activities will be conducted in compliance with the Commission't regulations, and (3) the issuance uf the amendment will not be inimical to the common defcose and security or to the health and safety of the public.
Principal Contr.M tor:
Lawrence E. Kokajko Date:
January 26, 1993 I