ML20005D737

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Safety Evaluation Supporting Amend 169 to License DPR-62
ML20005D737
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 11/08/1989
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20005D726 List:
References
NUDOCS 8912140398
Download: ML20005D737 (4)


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p 3AFETYEVALUATIONBYTHEOFFICEOFNUCLEARREj'CTORPEGULATION juPFN, TING AMENDMENT NO. 169 TO FACILITY OPERATING LICE.1SE NO. _0PR-62 CAROLINA POWER & LIGHT COMPANY.

BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 DOCKET NO. 50-324 1.0 IhTRODUCTION By letter cated Jure 9,19B9 from A.L. Cutter (CP&L) to NRC, the licensee submitted a request for the Technical Specification changes for Brunswick Steam Electric Plant (Brunswick), Unit 7, for Cycle 9.

The Cycle 9 reload core wi'l consist of three types of GE ruel BP8x8R, GE8x8EB, and GE8x8NB, of wh5.1 the type GE8x8NB is a new fuel type.

The GE8x8NB fuel was approved for reload in Amendment 18 to GES1 AR-II (NEDE-24011-P-A).

Due to the use of new fuel CE9x8NB, the licensee recalculates the minimum critical power ratio (PCPR),1afety limit and proposes a change in the Technical Specifications ~ We evaluate the changes in the following.

2.0 EVALUATION OF-TECHNICAL fDECIFICATION CHANGES l

(1) Section 2.1.2 THERMAL POWER i

The MCPR safety limit for Cycle 9 with the new GE8x8NB fuel type is changed f run,.14 to 1.06.

The new MCPR limit is based on an approved metnocology w.,:ribed in the approved Amendment 18 to NE0E-24011-P-A.

The i

l-degree of conservatista associatec with the new MCPR limit is the same as that of the old MCPR limit, i.e., there is an adequate margin _to assure l,

that more than 99.9 percent of the fuel rods in the core will not expertence boiling transition during normal operation and anticipated operational occurrences (A00s).

Based on the approved methodology and adequate conserva+. ism, we concluce that the new MCPR limit of 1.061s acceptable for use in Cycle 9.

(2) 5.3.1 FUEL ASSEMBLIES The fuel types in the Cycle 9 reload core are BP8x8R, GE8x8EB, and GE8x6NB.

The fuel types BP8x8R anc GE8xSEB are currently in Cycle 8 core.

The new fuel type GE8x8NB was approvec in Amendment 18 to NEDE-24011-P-A.

We thus conclude that the three fuel types BP8x8R, GE8x6EB, anc GE8x8NB are acceptable for use in Cycle 9.

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3.0 ENVIRONMENTAL CONSIDERATION

S This 'erendment changes a requirement with respect to installetton or use cf a facility component locatec within the restricted area as defined in 10 CFR Part 20 and changes to the surve111ance requirements.. The staff has ceterminec that the annament involves no significant increase in the amounts, ano no significant change 10 the types, of any effiuents that may be releaseo ott site; and that there shoulc be no-significant increase in indivioual or cumulative cccupational radiation exposure.

The Commissicn has previously issued a proposed finding that this amendment involves no 4

significart hazaros consideration, and there has been oc public content on

.such tincing.

for categcr1 cal exclusion set forth in 10 CFR 51.22(c)(9,.Accordi Fursuant to 10 CFR 51.22(b), no environmental impact statenent or environmental assessment need be prepared in connection with the issuance cf the asiencrent.

a.0 _CONCL US ION The Commissier trade. a proposeo determination that this anencrent involves no significant hazards consiceration which was published in the FEDERAL REGISTEP. (54 FR 29401) on July 12, 1989, anc consulted with the State of l

North Carolina.

No public corments or recusts for hearing were received, and the State of horth Carolina did not have any cucrerts.

3 The stuf f has concluded, 'basec on the consideratiers discussed above, that: (1) there is reasonable assurance that the health ano safet) cf the public vili not be encangered by cperation in the proposed nianner, anc (2) such activities will be conducted in ccrpliance with the Commission's l'

regulations, and the issuance of the amendment will not be inimical to the common cefense and security or to the health ano safety of the public.

Principal-Cortributor:

5. Wu-Datec: November 8,1989 l

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACT M

. SUPPORTING AMENDMENT NO.- 169 TO FACILITY OPERA CAROLINA POWE_R & LIGHT COMPANY g.

BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 DOCKET h0. 50-324 1.0 ThTRODUCTION By letter cated Jure-9,1989 from A.B. Cutter (CP&L) to NRC, the licensee submitted a request for the Technical Specification changes for Brunswick Steam Electric Plant (Brunswick), Unit 2, for Cycle 9.

The Cycle 9 reload of which the type GE8x8N8 is a new fuel type. core will consist The GE8x8NB fuel was approved for reload in Amendirent 18 to GESI AR-l! (NEDE-24011-P-A).Due to the use of new fuel GE8x8NB the licensee recalculates the minimum critical pcwer ratio (MCPR), safety limit and proposes a change in the Technical Specificatiens.

We evaluate the changes in the following.

2.0 EVALL'ATION OF TECHNICAL SPECIFICATION CHANGES (1)- Section 2,1.2 THERMAL POWER The MCPR safety limit for Cycle 9 witn the new GE8x8HB fuel type is changec from 1.04 to 1.06.

The new MCPR limit is based on an approved methocology cescribed in the approved Arendment 18 to NEDE-24011-P-A. The degree of censervatist.i associatec with the new MCPR limit is the same as that of tne old MCPR limit, i.e., there is an adequate margin to assure that more than 99.9 percent of the fuel rocs in the core will not experience boi' ling transition during normal cperation anc anticipated operatier.al occurrences (A00s).

Eased on the approved methodology arc adequate conservatism, we concluce that the new MCpR limit of 1.061s acceptacle for use in Cycle 9.

(2) 5.3.1 FUEL ASSEMBLIES The f uel types in the Cycle 9 reload core are 8P8x8R, GE8x8EB, and GE6x6NB.

The fuel types BP8x8R anc GE6x8EB are currently in Cycle 8 core.

The new fuel type GE8x8NB was approvec in Amencment 18 to NEDE-24011-P-A.

We thus conclude that the three fuel types BP8x8R, GE8x6EB, ana GE8x8NB are acceptable for use in Cycle 9.

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3.0 ENVIRONMENTAL CONSIDERATION

S This 'emendnent changes a recuirement with respect to installation or use cf a facility component locateo within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements.

The staff has ceterminec that the arencment involves no significant increase in the be releaseo ott site; and that there shoulc be no sicnifican ind15 toual or cumulative cccupational radiation exposure.

The Commission has previously issued # proposed finding that this amendment in)olves no significart hazarcs consideration, acid there has been tc public comment on such rincitig.

for categcrical exclusion set forth in 10 CFR 51.22(c)(9,.Accord Fursuant to 10 CFR 51.22(b), no environmental impact staten4nt or environmental assessment need-be prepared in connection with the issuance cf the ar.;encrent, a.0 CONCLUSION 7te Commissier rade a proposea cetermination that this anencrent involves no significant bazards consiceration which was published in the FEDERAL REGISTEP (54 FR 294C1) on July 12, 1989, anc consulted with the State of North Carolina.

No public coastnts or rectests for hearing were received, anc the State of herth Carolina did not have any coccerts.

The rthti has ccncluded, basec on the consideratiers aiscussed absve, that: (1) there is reasonable assurance that the health ano safet) ef the public vili not be encengered by cperation in :he proposed raanner, anc (2) such activitie! will be conducted in ccroliance with the Commission's regulaticns, ano the issuance of the amencment will not be inimical to the 1

s cormon ce*ense and security or to the health ano safety of the public.

Francipal Cortributor:

S. Wu Dated: November 8, 1989 e

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