ML20033F912
| ML20033F912 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/19/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033F905 | List: |
| References | |
| NUDOCS 9004040067 | |
| Download: ML20033F912 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR' REGULATION f
RELATED TO AMENDMENT NO.125 TO FACILITY _ _0PERAT,1N,G,,L,1,CEN,SE _NO. DPR-40 OMAHA PUB,L,1,C,p0WER DISTRICT FORT _CALHOUN STATION. UNIT NO. 1
. DOCKET N,0 _50-285
1.0 INTRODUCTION
On October 27 1989 Omaha public Power District scbmitted proposed fort CalhounTechnIcalSp,ecificationchangeswhichincludeadditionsto Limiting Conditions for Operation (L.C.O.) 2.16 and Table 3 3a.
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The change to L.C.0 2.15 added the instrumentation contained in Alternate Shutdorn Panels,(Al-179) to that contained in L.C 0 2.15.(/$1-185 and A1-212), a feedwater Panel These instren,ents include those identified as necessary to attain Hot Shutdown i
in the Updated Safety Analysis Resort (USAR) Sections 7.3.6 ThestaffwasconcernedtiettheadditiontoL.C.0E.7.6.4and 7.6.8.
15 did not include operebility requirenents for pump, valve and other controls which eppar on these panels. On January 11, 1990, the licensee, in response to our telephone request of December 21, 1989, clarified that these controls circuits would be included in the operability requirements of L.C.O. 2.15. This change was within the scope of the notice published in the Federal Register on N9yember 29, 1989 and did not affect the initial deter minafion.
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2.0 DISCUSS,1,0N The physical configuration of these panels was investigated by the staff l
trd it was found that panels AI-179, 185 and 212 are located next to each cther in the electrical penetration room at elevation 1013 ft which facilitates control of the process of shutting down the reactor.
Communication between this area and other plant locations is by means of the GAI-tronics Consnunication System, a sound powered phone system, or a UHF radio system.
The Bases for L.C.O. 2.15 were modified to identify the panels which cociprise the facilities for shutting down the reactor in case the main conttol room is rendered unusable and to state that sufficient capability is available to permit entry into and maintenance of the Hot Shutdown Mode from locations outside the main control room.
In addition, the Allowed Outage Times for the identified equipnent appears to be consistent with those for components in similar systems.
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. j In Table 3-3a of the Suryt111ance Requirenent Section of the Technical Specifications, modifications were made to provide surveillance, i
calibration and test requirenents for the instrunentation and control l
equipn.ent located on panels AI-179, 185 and 212 which together form the l
euxiliary shutdown facilities for Fort Calhoun.
Eased on our review of the information submitted by the licensee, the USAR, the Fort Calhoun Technical Specifications, and information obtained in response to our December 21, 1989 conference call with the licensee, wehaveconcludedthatthelicensee'sproposedTechnicalSpecification changes are acceptable.
l 3.0 EliV1F,0! MENTAL CONSIDERATION The amendment '.nvolvt5 a change in a requirement with retpect to the installation or use of a facility comoonent locateo within the tcstricted area as defined in 10 CFR part 20 and' changes in surveillance requirenents.
The staff has determined that the amendment involves no significant increass in the amounts, cod no significant change in the types, of any l
effluents that v.ay be released offsite, and that there is no significant increase in individual or cumulative occupational radiation ex>osures.
t The Contaission has previously issued a proposed finding that tie anendnent involves no significant hazards consideration and there has been to public cortaent on such finding.
Accordingly, the amendment meets the eligibility criterie foi categorical exclusion set forth in 10 CFR Section 51.22(c)(?)).
rursuant to 10 CFR 51.22(b), no environn. ental in. pact statement or environ-rnental assessment need be prepared in connection with the issuance of the ame ndirent.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) ttore is reasonable assurance that tne health and safety of the public i
will ret te endangered by operation in the prososed o.anner, and (2) such ectivities will be conducted in compliance wit 1 the Coraission's regulations, and the issuance of the amer.dment will not be inimical to the cottnen defense and security or to the health and safety of the public.
Date:
March 19, 1990 Principal Contributor: Don R. Lasher (SICB) a 9
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