ML19317F734
| ML19317F734 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/08/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317F721 | List: |
| References | |
| NUDOCS 8001230621 | |
| Download: ML19317F734 (2) | |
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3AFETY EVALUAIIGi_af T3E O?FICE OP ?TUCI.ESR PEACIOR arMULVIGN SUy.:ORTIE.VCEOT 20. 4 'IG LIC'2:30 40. teF-3 ICIIDG CLI.iG4 CO'G.WI ig } kid
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my Actter datea June 24, 1977, taa Toledo Edicen Oc:cany recuested enanges in tne technical spoeifications accenced to Facility 0;erating Licenae,.idf-3, for tne Oavis ::esde :4uclear cower Statica, Unit 1.
?ae requested caanges ta tne tecnnical soecificatieru are recuired to reflect ti.e procer allowacia v21eca and surveillence rec,uirements for ::u cecan generator level transo.ittera unica nave tren i.utalled in lieu uf the steam generatcr level switenes in tne facility steam and feessater rupture control systas.
LI5CJS51ai Ine Tcledo Eaison Cc:=any scecifiec tnat the following enangea are required to,erocerlf acdress tne a110vaale values and curve 111ance requireitents for tne newly inctalls: steam generator 1cvel trans.aitters:
(1) Tacle 3.3-11 cn Page 3/4 3-15 and Page 3/4 3-25 ce enanged to scow cne nes 1svel witch nu. tera, (2) Iacle 3.3-12 on Page 3/4 3-23 ce cnanged to snow t.at ene allowccle value :or Functional Unit 2 is greater tnen er equal to (3') 10 incnes of water and greater tnan cr ocual to (2:) la.J7 incnes water for tne Cnannel calicratien, 2na (3) Taalc 4.3-11 ca Fage 3/4 3-30 oe cacnJod to snew a Cnannel aliaratica frequency for Itein lo of once every Id sentna (P) instead of once every
- 12 days (2).
The Toledo Edison Conpany states tnat the requested enangec to the tecnnical scecifications are required prior to facility operation in Mode 3 (not stanccy) since tne steam generator level switenes w.icn have ccen reclaced are nct presently functional j
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{ @ ATIC41, item E.1, to Facility Operating License, NPF-3, stipulates that the four steam generator level switches in each steam gererator insice centainment be replaced with four steam generator level transaitters prior to proceeding to facility operation in Me 2 (startup).
ne allcwaole value for channel calibration of greater than or equal to 18.37 inenes of water instead of the greater than or equal to 20.0 inches of water is based on an allowance of 1.13 inches for transmitter drift over an 18 oonth period as determined by cualifIcation teating of the steam generator level tranmitters. Basad en our review of the aodified system, we have concluded that the allevance for tran=itter drif t is accectable.
The change in the frequency of channel calibration to ence per 13 acnths instead of once cer 92 days is ::ased en recamendations contained in IEEE 279-1371, and is acceptacle.
Inerefore, based on cur evaluation as set forth in this report and on our evaluation and firdings as della.eatad in our safety Cvaluat ion Escort ard Sepplement Uo.1, Section 7.4.l(4), we find the TolMo F.dison Ccr.r.cany's request for technical specification charges, as discussed accve and specifically relating to the recently installed steam genarator lavel tran.r:itters, to be acceptacle.
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be have deterr.ined that the amend ent dces net authorize a enange in effluent types or total mounts nor an increase in powr level and will not result in any significant environmental !=nct. "daving made this determination, va have further concluded that the amener.ent involves an action which is insignificant from tne standccint of envirencental imcact and, cursuant to 10 CFR 351.5(J)(4),
tnat an anvircrantal 1.nact statment or negative declaration and envircreental izact aceraisal need not be preparM in cennection with the issuance of this acer.ctent.
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"We have cencluded, based on the considerations discussed abcrie, that (1) because the isnenchent dces not involve a significant increase in the cro-bability or consequences of acciaents previously considered or a significant decrease in any safety rargin, it does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of tne public will not be endangered by operation in the proposed canner, and (3) such activities will be conducted in camliance with the Comission's regulations and the issuance of this amendment will not be inimical to the cccurcn oefense and security or to the health aM safety of the public. Also, we reaffirm our corclusions as othervi=* etM in our %ty Evaluation Peccrt.
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NRC POAM 328 (P 76) NRCM 0240
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