ML20246G233
| ML20246G233 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/06/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246G215 | List: |
| References | |
| GL-88-16, NUDOCS 8907140198 | |
| Download: ML20246G233 (3) | |
Text
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l l-i MIET Y EVALL'! TION EY TUE OFFICE OF I;bCLEAR REACTC+ REGULAT:Cf PEL ATED TC AMENDMENT NC.150 TO FACILITY 0FERATlhC LICENSE PC. FDR-50 1:ETROPOLITAt: EDISON CCMPANY JEPSEY CFl THAL PCLEh & LIGHT COMPANY FEhhSYLV ANI A ELECTRIC C0l',PANY GPU NUCLE /.F CORPORATION TFFEE MILE ISLt.ND NUCLEAR ST ATION, Uf;IT NO.1 00ChET NO. 50-289 INTROPl'CTI0f4 E3 htter catcd /pril 76, ISLE, as supplemented on May 18, 1985 crc' June 19,'ISE9, GPL ISclear Ccrporatior proposeo changes to the Technical Specificaticr.s (TS) for Three t.ile Islar.c l' nit 1.
The proposed changes would i.odify specificatier:s hcving cycle-specific parameter:. limits by replacing the values of thcsc limits with a reference to the corc cperating lin.its by replacing the values of those liritt with e reference to tFc Core Operatirg Limits report (CCLR) for the values:cf those l'r.its.
The proposed ' charges also include the add' tion of tbc CCLR to the Ecf:liitions section and to the reporting requirements of the tcn.inistrt.five Controls section cf TS. Guidsrce on the preposed char.ses was chelopec t,3 Nr.C on the basis of the review of a leed-plant propcsal subrdtted en the Occ+ce plant doctet that wcs endorsed by the Babcock ar.d Wilcox Cv rers Group.
The Cconet license amerdr.ut and Safety Evaluation were issued on Jarica ry 26,15EC. The generic gpicance v:ts providcd to all pcwcr reactor licensees ar.c applicants by Generic Letter 86-16, dated Octcber 4,19ES.
The supplerrrtal submittals dated Pay 18 and June 19, 1989 clarified the wording cf, and added additional references tc the proposed TS consistent with Ceneric letter SE-10. These submittals oid nct alter the action noticed ir the Fcdenci Reg. ster on May 17, 1989 or affect the initial determination.
EVALL!/.TICh The licensee's proposed changes to the TS are in accordance with the guidance provided by Generic Letter 88-16 and are addressed belcw.
(1) The Definitions section of the TS was modified to include a definition cf the COLR that requires cycic/ reload-specific parameter limits to be established on a unit-specific basis in accordance with an KRC-approved it.ethooology that mair. thins the lireits of the sr.fety analysis. The dcfinitio:. r.otes that phei operation within thcse limits is addressed by indivic' cal specifications.
(2) The followirp specifications were revised te replace the s clues of cycle-speciTsc parameter liraits with c reference to the COLL that provides these liraits.
890714019e 890706 PDR ADOCK 05000289 4
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3.5.2.4 ' C;uadrarit Tilt 3.5.2.5' Ccntrol Lc4 Positions 2.5.2.7 Axial Power 1rtalance 3.5.2.8 Power l'apping (3) Specificatier C.9.5, Core Operating Liriits Report, vias added to the rticrting requirements of the Administrative Centrols section cf the TS.
This specifitttien recuires that the COLR be submitted, upon issuance, tc the NCC Cccument Cor.trel Desk with copies to the Regional Administrator and Per4 dent inspector.
The report provides the values of cycle-specific paren.eter lim't! that are cpp11 cable fcr the current fuel cycle.
Furt hernor e,
this spctification requires tret the values of thest limits be estet lished ui'rt NFC-cpprcved methotelogy ar.d col.sistent with all applicable limits rf tLe sefety hr.rlysis.
The tiRC-approved docurnetts constituting this sporevec etnodology trd to be listed in the is ere as fo11ths:
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B AV 101:2A Res. :, "Herrnal 0 rating Cor.trols," Pty 1984.
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LAW-10116-A, "Asscrti) Calculations and Fittcd Nuclear hte,"
May 1977.
(3) L AL-10117P-A, "Eebcock L LM 'ecx Versier, cf TDQ User's Panual,"
Jertary 1977.
(4) eat -IC118A, "Corc Calculation.a1 Technir,ues and Procecures,"
Lecerter 197F.
(5) EAh-10124A, "FLAf*E 3 - A Thret-timensicnal'Lodal Coce for Caict ieting Core Reactivity and Power Distributions," August 1976.
(6) CAL;-1C125A, "terificatich of Three-Cirnensional FLAME Code,'
lucust 197f.
(7) BAK-10152A, "N00CLE - A Multi-Cirensional Two-Group Reacter Sir.:ulator," June 1985.
(C} CIW-10119, "Pewer Pea kir4 huclear I;eliability Factors," June 1977.
fir,elly, the specification requires that all changes in cycle-specific paraiaeter limits be cccumented in the COLR before each relred cycle or renaining part cf a relcac cycle and retuitted upon issuance to likC, pricr to cperatien with the neh paraueter limits.
On the basis of the review of the above iteus, the NRC staff concludes that the licensce provided er; acceptable response to those items as addressec in the tir.C suidance in Ceneric Letter 88-16 on r..odifying cycle-specific parameter limits ir the TS. Because plant operation continues to be limited in accordance with the values e f cycle-specific parareter limits thet are estellished using NRC-approved methodologies end the calculational r:ethodology and acceptance criteria are specified ir, the TS, the change is in conforrrer.ce with IC CFR 50.36. Thus, the NFC staff cer.cluces thct this change is administrative and does not impcet on plant safety. Accordir. gly, the staff finds the proposed chcnges acceptable.
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rjT:00NMENTAL CONSIDERATION.
The amenonent changes a requirement with respect to installation or use of a f acility comporent located within the restricted drea as defined in 10 CFR Part 20 and also changes reporting requirements. We have determined that the emendment involves me significant increase in the amounts and no significant change in the types of an effluents that may be released off site, and that there is no significant increase in individual or cumulative occupational radiation exposure. The staff has previously issued a proposed finding that the omendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9)
.and (10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of its amendment, CONCLUSION Cn the besis cf the considerations discussed above, the NRC staff concludes that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations and (3) the issuance of the amencment will not be inimical to the common oefense and security or to the health and safety of the public.
Principal Contributors: Daniel B. Fieno Thomas G.-Dunning Ronald W. Hernan Dated: July 6, 1989 l
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