ML20246P923

Forwards Safety Evaluation Accepting Plant Second 10-yr Interval Inservice Insp Program,Per 10CFR50.55a(g).Relief Request RR-2 Re Reactor Pressure Vessel Circumferential Shell Weld Not Granted

ML20246P923
Person / Time
Site:	Brunswick
Issue date:	05/10/1989
From:	Le N Office of Nuclear Reactor Regulation
To:	Eury L CAROLINA POWER & LIGHT CO.
Shared Package
ML20246P927	List: ML20246P923 ML20246P940 ML20246P967
References
TAC-63786, TAC-63787, NUDOCS 8905220310
Download: ML20246P923 (4)

Text

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~ May 10, 1989

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DISTRIBUTION FLitton b

1 6"&^L~o'c~al NRC PDRs PD21 r/f Docket Nos. 50-325 TMurley/JSniezek (12G18).

and . 50-324 CRossi (11E4)

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t' GLainas Mr. Lynn . W. Eury ' EAdensam- NLe Executive Vice. President PAnderson Support Groups _

OGC Carolina Power & Light Company EJordan(MNBB3302)

H Post 'fice Box 1551 BGrimes(9A2).

Raleigh, North Carolina 27602 li4eeks (8).

GPA/PA

Dear Mr. Eury:

ARM /LFMB ACRS(10)

SUBJECT:

SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM, BRUNSWICK p STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. 63786 AND 63787)

By letter dated November 10, 1986, CarolinaPower&LightCompany(CP&L) submitted the Second Ten-Year Interval Inservice Inspection (ISI) Program,

,i Revision.0 for the Brunswick Steam Electric Plant, Units 1 and 2, for staff review. The staff, with assistance from its contractor, Idaho National Engineering Laberatory, reviewed the program, and the requests for relief from the ASME Code Section XI' requirements which CP&L has determined to be o impractical. 'As.a result of.this review, a Request for Additional Information (RAI) was. prepared describing the information and/or clarification required {

from CP&L in order for the staff to complete the review, this.RAI was sent to CP&L on April 2, 1987. Revision I of the 151 Program Plan was submitted in the CP&L's-responses to the NRC's RAI, dated August 19, 1987.

The' Brunswick. Steam Electric Plant, Unit I and Unit 2, Second Ten-Year Interval ISI Program Plan,-Revision 1, was evaluated for compliance with: a)the requirements of the 1980 Edition, Winter 1981 Addenda (80W81) of the ASME Code Section XI except that the' extent of examination for Code Class 2 piping welds has been determined by ASME Code Case N-408, b) acceptability of examination sample, c) exclusion criteria, and d) compliance with ISI-related commitments identified during the NRC's previous PSI and ISI reviews. The requests for relief from the ASME Code requirements which the licensee has determined to be impractical for the second 10-year inspection interval were also evaluated.

In accordance with the requirements of 10 CFR 50.55a(g), the staff concludes  !

that the Brunswick Units 1 and 2's Second Ten-Year Interval ISI program is f acceptable. The second 10-year interval began July 10, 1986 and ends July 10, i 1996. The relief request RR-1 and relief requests RR-3 through RR-7 are ,

, granted. The staff has determined, pursuant to 10 CFR Part 50.55a(g)(6)(1), l that the granting of these reliefs is authorized by law and will not endanger life or property or the connon defense and security and is otherwise in the public interest. In making this determination, the staff has given due consideration to the burden that could result if these requirements were imposed on the facility. The relief request RR-2, RPV Circumferential Shell o Weld, is not granted, howeur.

M 8905220310 890510 4 I

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Mr. L. W.' Eury -2 May 10, 1989 Enclosure I contains the staff's Safety Evaluation for the ISI program, the relief requests RR-1 through RR_7; and the detailed evaluation for the program and relief requests from the NRC contractor, Idaho National Engineering Laboratory.

Relief request RR.8. functional testing of snubbers, was addressed previously in our letter to Mr. Utley dated March 2,1988.

Sincerely, No ." Le ofe Manager Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulaticn

Enclosures:

As stated cc w/ enclosures:

See next page

[ BRUNSWICK 10-YR ISI PROGRAM]

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Mr. L. W. Eury Brunt; wick Steam Electric Plant I Carolina Power & Light Company Units 1 and 2 l l

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Mr. Russell B. Starkey, Jr. Mr. J. L. Harness l Project Manager Plant General Manager ]

Brunswick Nuclear Project Brunswick Steam Electric Plant '

Box 10429 P. O. Box 10429 Southport, North Carolina 28461 Southport, North Carolina 28461 Mr. R. E. Jones, General Counsel Mr. H. A. Cole Carolina Power & Light Company Special Deputy Attorney General P. O. Box 1551 State of North Carolina Raleigh, North Carolina 27602 Post Office Box 629 ,

Raleigh, North Carolina 27602 Mr. Mark S. Calvert Associate General Counsel Mr. Robert P. Gruber Carolina Power & Light Company Executive Director Post Office Box 1551 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Ms. Grace Beasley Board of Commissioners Post Office Box 249 Bolivia, North Carolina 28422 Mrs. Chrys Baggett State Clearinghouse Budget and Management 116 West Jones Street Raleigh, North Carolina 27603 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 Post Office Box 208 Southport, North Carolina 28461 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr. Dayne H. Brown, Chief Radiation Protection Branch #

Division of Facility Services N. C. Department of Human Resources 701 Barbour Drive l Raleigh, North Carolina 27603-2008 i

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TABLE 1 STATUS OF RELIEF FROM ASME CODE REQUIREMENTS.

Request Evaluation Number Category Description Status RR-2 B-A RPV Circumferential Shell Not granted Item Bl.11 Weld RR-1 B-J Pressure Retaining Class 1 Granted Item B9.11 Circumferential RR-4 B-L-2 Internal Surfaces of Class Gronted Item B12.20 1 Pumps Casings RR-3 B-M-2 Internal Surface of Class 1 Granted Item B12.50- Valve Bodies '

RR-7 Subarticle Hydrostatic Test of the Granted IWC-5222(a) Class 2 Portion of the Main Steam System RR-6 Subarticle Hydrostatic Test of the - -Granted IWD-5223(a) Class 3 High Pressur'e Por-tion of the HPC1 System RR-5 Table IWF-2500-1 Component Supports on the Granted Figure-JWF-1300-1 Service Water Piping for the Four Diesql. Fuel Storage Chambers ' .

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