ML20128Q003
| ML20128Q003 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/17/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128Q000 | List: |
| References | |
| NUDOCS 8506040040 | |
| Download: ML20128Q003 (2) | |
Text
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c UNITED STATES
[.I jy k NUCLEAR REGULATORY COMMISSION 3
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WASHWGTON, D. C. 20555 h,/
SAFETY EVALUATION BY THE OFFICE OF fiUCLEAR REACTOR REGULATION RELATEC TO AMEtiDMENT N0. 34
~? FACILITY-0PERATIt(G LICENSE NO. DPR-75 PUBLIC SERVICE ELECTRIC AND GAS COM?ANY PhlLADELPnlA tLELiRiL COMPANY DELIGRV/, POWER AND LiGni COMPAfn, AND AILANTIC CliY tLECTRIC COMPAIO SALEM NUCLEAR GENERATION STATION, UNIT N0. 2 00CKET NO. 50-311 Introduction in a letter dated January 11, 1985, Public Service Electric and Gas Comoany (PSE&G) requestec changes to the Power Deper4 dent Insertion Limit-(PDIL) of the Technical Specification (Figure 3.1-1) for Sale.T Unit 2.
This change would' match the Unit 2 PDIL curves with those of Unit 1.
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This change is requested in order to gain operational flexibility which was Icst due to reduction of rod insertion limits for Cycle 2 of Unit 2.
The
' Cycle 3 reload design has been based on the proposed PDIL and a revised centrol roc pattern (bank grouping).
The previous control rot pattern for Salem Units' I and 2 differed considerably.
The revised control rod patterr for Unit 2 would make the control rod patterns for Units 1 and 2 identical for control bank D, which is the most important control bank and almost id,entical for control bank C which is the next most important cnntrol bank.
Bank 3, the only other bank allowed in the core during power operation, must be fully v:ithdrawn prior to 20% full power.
The revision to the control rod patterns which was implemented during the Cycle 2-3 refueling outage was mace
'under tne provision of 10CFR50.59.
Evaluation and Sumary The Reload. Safety Evaluation (RSE) for Cycle 3 was performed by Westinghouse and reviewed by PSE&G.
The results of the RSE showed that the proposed PDIL do not cause the previ.ously acceptable safety limits for any incident 'tb be i
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Fur:herat e'it was sheer :La: the current cere safe:3 Iimits 3r..
-s'i ' asqiicas}e ar.d :nt: :ha change ir ~no way crea:es the pessiotii 3 cf a
-nee 'r ci :erent accident' frcr'any accident previousiy evaluatec *cr Sa:em.
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Er.vir nren:a1 Censicera:icr, This.arer.dment involves a ' change in the installaticn' cr use of a facility
.:ct :nsr.: i ds:ec witrir :ne restricted area as definea in 10 -CFR-Far: 2C.
ne staff has de erminec tnat-the amencment invcives no significant increase
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in-the amounts,_and no significant change in the tyces, of any effluents' that'may_-be releasec effsite,?and that:there is no significant increase in incividual or cumulative occupational radiation exposure.
The Commission has
-previously issuec'a pr'oposec finding that this amendment involves no
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sicnificart ha: arcs consiceration and there has been.no public ccmment en su:"-#indirg.
Accc-dingly thislamencment meets the eligibility criterie
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for cateccrical exclusion set fortn in 10 CFR Sec 51.22(c';(9).
Pu rsuant ::c-10'CFR151.22(b) ne ervironmental impact statement or environmental assessment need be precarec in connection with the issuance of this areacment.
h Ccnclusion
.le'have ccr.cluded. based cr, the considerations discussed above, that:
- l3.} there 'is reasonable assurance that the-health and safety of ne cutlic will not be'encangerec by ope. ration in the proposed manner, and (2't such activities will be conducted in compliance with-the D
Commission's' regulations and the issuance of this amendment will not be= inimical Lto,the common defense and security or to the health;and safety of the public.
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. Dated: May_17, 1985 Princical Contributor:
f
. Chatterton L
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