ML20206G181

Forwards SE Approving Three of 25 Relief Requests Submitted by for Third 10-year ISI Program.Remaining Reliefs Will Be Evaluated in Separate SEs

ML20206G181
Person / Time
Site:	Brunswick
Issue date:	05/04/1999
From:	Peterson S NRC (Affiliation Not Assigned)
To:	Keenan J CAROLINA POWER & LIGHT CO.
Shared Package
ML20206G185	List: ML20206G181 ML20206G187
References
TAC-MA2108, TAC-MA2109, NUDOCS 9905070110
Download: ML20206G181 (3)

Text

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% May 4, 1999 Mr. J. S. Keenan, Vice President Carolina Power & Light Company Brunswick Steam Electric Plant Post Office Box 10429

. Southport, North Carolina 28461

SUBJECT:

APPROVAL FOR THIRD 10-YEAR INTERVAL INSERVICE INSPECTION

~ PROGRAM REQUEST FOR RELIEF FOR THE BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 (TAC NOS. MA2108 AND MA2109)

Dear Mr. Keenan:

By letter dated April 23,1998 (Serial: BSEP 98-0087), Carolina Power & Light (CP&L)

. Company submitted the third 10 year Inservice Inspection (ISI) Program for the Brunswick Steam Electric Plant (BSEP), Unit Nos.1 and 2. The ISI Program submittal included 25 relief requests. Subsequently, by letters dated February 18,1999, and April 26,1999, CP&L supplemented 12 of the 25 relief requests based on telephone discussions on November 10, 1998, with the NRC and the NRC's contractor, Idaho National Engineering and Environmental Laboratory (INEEL).' This letter addr_ esses three of the relief requests submitted by CP&L.

The remaining reliefs will be evaluated in separate safety evaluations.

In accordance with Generic Letter (GL) 90-09, Attematiw Requirements for Snubber Visual Inspection Intervals and Correctim Actions, CP&L submitted a request for relief for snubbers (Relief Request RR-8, Revision 0) from the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel (B&PV) Code,Section XI, requirements for the Brunswick Steam Electric Plant, Unit Nos.1 and 2, third 10-year interval ISI Program Plan.

ASME Code,Section XI, Paragraphs IWB-2420(a) and IWC-2420(a) require the sequence of component examinations established during the first inspection interval be repeated during

- each successive inspection interval, to the extent practical. Pursuant to 10 CFR 50.55a(a)(3)(i), the licensee submitted RR-15 to request relief from the Code-required sequence of component examinations as specified in IWB-2420(a) and IWC-2420(a).

The third 10-year ISI Program is based on the 1989 Edition of the ASME B&PV Code,Section XI. The second 10 year ISI Program was based on the 1980 Edition of the Code. Due to differences in the requirements of IWA-5250 contained in these two Code editions, CP&L submitted Relief Request RR-17, " Leakage at Bolted Connections," for the BSEP, Unit 2 Refueling Outage 13, only, as an attemative to the requirements of IWA-5250(a)(2), CP&L proposes to follow the requirements of ASME Code Case N-566-1. Following BSEP, Unit 2 Refueling Outage 13, CP&L plans to continue discussions with the NRC regarding the use of using Code Case N-566-1 as the basis for a permanent attemative to the requirements of IWA-5250(a)(2).

The Code of FederalRegulations,10 CFR 50.55a, requires that ISI of certain ASME Code Class 1,2, and 3 components be performed in accordance with Section XI of the ASME B&PV i 9905070110 990504

• PDR-G ADOCK 05000324 PDR

• J.S.Keenin May 4, 1999 a

epplicabla Edition cnd Addenda, excspt wh:ra specific writt:n reli;f his br:n r:questad by the licensee and granted by the Commission pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (g)(6)(i) of 10 CFR 50.55a The NRC Staff has reviewed your request and concluded that the proposed altematives proposed in the three requests mentioned above provide an acceptable level of quality and safety at the Brunswick Steam Electric Plant, Unit Nos.1 and 2. The proposed changes to the CP&L commitment for Code relief will ensure that these inspections are completed in accordance with Section XI, " Rules for Inservice inspection of Nuclear Power Plant Components," of the ASME B&PV Code applicable Edition and Addenda. Therefore, the proposed alternative,s are authorized pursuant to 10 CFR 50.55a(a)(3).

Sincerely Original signed by:

Sheri R. Peterson, Chief, Section 2 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 i

Enclosure:

Safety Evaluation cc w/ enclosure: See next page DISTRIBUTION:

' Docket File :

PUBLIC Brunswick R/F i JZwolinski/SBlack OGC SPeterson MBoyle EDunnington KCotton AHansen CNorsworthy (e-mail SE only)

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MSatorius, EDO BBonser, Rll DOCUMENT NAME: G:\ BRUNSWICK \ RELA 2108.WPD *see previous concurrence To rec 4ve a cop 1 nf thle document, lnd cate in the bon 'C' = Copy without attachment / enclosure "E" = Copy with anachment/ enclosure *N" = No copy OFFICE PDil-2/PM C PDll-2/PM lE PDil-2:LA ( PDil-2/SC

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• NAME KCotton 4fE_ AHansen Atlk As' EDunnington b6 SPeterson RBachmann 05/4/99 sus gis aussas ==== - _{5/3/99 _

OFFICE NRR/DE/EMCB

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• NAME KManoly ESullivan DATE 04/30/99 05/3/99 05/ /99 05/ /99 05/ /99 OFFICIAL RECORD COPY 070019 u

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1 J.S.Keenan )

i applicable Edition and Addenda, except where specific written relief has been requested by the  ;

licensee and granted by the Commission pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (g)(6)(i) !

of 10 CFR 50.55a.

The NRC Staff has reviewed your request and concluded that the proposed alternatives l proposed in the three requests mentioned above provide an acceptable level of quality and I safety at the Brunswick Steam Electric Plant, Unit Nos.1 and 2. The' proposed changes to the  !

CP&L commitment for Code relief will ensure that these inspections are completed in )

accordance with Section XI, " Rules for Inservice inspection of Nuclear Power Plant  ;

Components," of the ASME B&PV Code applicable Edition and Addenda. Therefore, the l proposed alternatives are authorized pursuant to 10 CFR 50.55a(a)(3). .

l Sincerely, S6 R, PL Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Licensing Project Management l Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324

Enclosure:

Safety Evaluation cc w/ enclosure: See next page

,