ML20082R514
| ML20082R514 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/05/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082R512 | List: |
| References | |
| NUDOCS 9109160129 | |
| Download: ML20082R514 (2) | |
Text
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ATt MM fJ.'.Y. f!!cLRJ.C..EPr?!!d.Y S!.L f P. !W.t Lf!?. P! !!f.T J !:f. 5.Tb.TJ.C!L.f!').T)J. bFP_ f 00C K E T t.05 !.O..?.7.?..A.t,D. 50..311 1.0 jp,TRppVCTION By letter dated June 20, 1991, the Public Service Electric & Gas Company, Philadelphia Electric Conpany, Celt:arva Tower and Light Company, and Atlantic City Electric Conpany (the licensees) submitted a request for changes to tht.
Salem Nuclear Power Generating Station, Units 1 and 2, Technical Specifications (TS). The requested changes would modify Technical Specification Section 3.5.1, Surycillance Fequirement 4.5.1.c.
The current su..'eillance requires verification that power to the safety injection accumulator isolation salves is disconnected by renoval of tht breater f t om the circuit.
The control power loclout switches were recently rcdified to provide the necessary protection against a single active f ailure, thus ren. oval of the brealer f rom the circuit is u0necessary.
The proposed amendnent also modifies tre applicability of Surveillence I
Feovirement 4.5.1.c to agree with the applicability of the specification. The specification is applicable when plant pressure is above 1000 psig and the i
surveillance requirement is applicable whenever plant pressure is above 2000 i
psig. This change will male the surveillance requirement applicalle whenever plant pressure is above 1000 rsig.
2.0 EVALUATION To protect against inadvertent closure of the accumulator isolation valves, Surveillance pequirement 4.5.1.c, requires the valves to be open and power to the motor operators removed by rocking out the circuit breakers for the four valves.
The circuit brealers are physically located in the Auxiliary Evilding which is rer.ote f rom the control room.
An equipment operator would have to be sent to the Avriliary Building to rack in the circuit breakers and then operation of the push button switches on the contro', console, if closure of the t
salves betones necessary.
9109160129 910905 PDR ADOCM 05000272 l
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-2 p5Et.G has contpleted a nodificatien that protects against a single active failure, to the installed pcwer lotleut switches (totary snar switches) in the control power circuits fot (ach of the c umulator isolation valves. These lockout switches will allow the breater to renain installed, but will remcyc control power from the valyc5. With thcse switches installed, two positive operator actions are reruired to close the valvest the power lockout switctes must be operatcd (located on the backranel in the control room) and the push button switches on the control console trust be operated. Tttse provisions prevent the inadvertent opcratior of the valves by a single operator action.
Also, the design of the power loc 60ut switches neets the single failure criteria as described in the Updated final Safety Analysis Report (UFSAR),
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Section 7.3.74, and does not alt (r the interlock functions as described in the USFAR, Section 7.3.T.7.
The staff fitds the ptoposed charge to be acceptable.
Technical Specification 3.5.1 is epplicable whenever reactor coolant systera pressure is above 1000 psig.
Powever, Survci11ance Fcquirement 4.0.1.c is applicable whenever reactor cooler t sy5 tem ptessure is at cve 000 psig. The 2000 psig in the survcillance rec;uirenent wou'.d be changed to 1000 psig.
Because this in: teases the pressure range over which the surveillance requirenient is applirable, the staff finds the proposed change to be acceptable.
3.0 STATE CO),5DLTAT1,0p in accordance with the Coteission's regulations, the tiew Jersey State official was notified of the proposed issuance of the aniendnents. The State official had no cor.rnents.
4.0 t PV 1 R 0titiEp,T,A,L,,00p,$J D,f,P,A TJ 0p The amendments chor.re a recuirerent with respect to installation or use of a facility component located within the restricted area as defined in 10 CFP part 20 and changes to the surveillerce.requirerients.
The f4C staff has determined that the amendnents involve no significant increase in the amounts, and no significant' change in the types, of etiy effluents that imy Le released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Consission has previously issued a proposed finding that the anendnents involve no significant hazards considera-tion, and there has been no public coran.ent on such finding (56 FR 33900).
Accordingly, the amendnents meet the eligibility criteria for catep?(b) no rical exclusion set forth in 10 CFR 51.PNc)(9). Pursuant to 10 CFR 51.<
environmental in. pact staten.ent or envirorstotel' assessrent need bt prepared in
. connection with the issuance of the amendnents.
5.0. CONCLUSION ine Commission has concluded, based on the considerations discussed above, that:,(1) there is reasonable essurance that the health and safety of the public will not be endangered by operation in'the proposed manrer, (E) such activities will be conducted in con:pliance with the Comnission's regulations, end (2) the issuance of the amendnents nill rict be inimical to i
the common defense and security or to the health and safety of the public.
Principal Contributors:
D. !;guyen J. Stone Date:
beptember 5, 1991
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