ML20237D495

Forwards SER Approving Code Case N-389-1, Alternative Rules for Repairs,Replacements or Mods,Section Xi,Div 1, Per 10CFR50.55a(a)(3)(i) &

ML20237D495
Person / Time
Site:	Millstone
Issue date:	08/20/1998
From:	Bill Dean NRC (Affiliation Not Assigned)
To:	Bowling M, Loftus P NORTHEAST NUCLEAR ENERGY CO.
Shared Package
ML20237D497	List: ML20237D495 ML20237D500
References
RTR-REGGD-01.147, RTR-REGGD-1.147 TAC-M94498, NUDOCS 9808260236
Download: ML20237D495 (3)

Text

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y j NUCLEAR RESULATORY COMMISSION

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WASHINGTON, D.C. 30e064001 1 August 20, 1998 j Mr. Martin L. Bowling, Jr.

Recovery Officer - Technical Services Northout Nuclear Energy Company c/o Ms. Patricia A. Loftus -

Director- Regulatory Affairs l P. O. Box 128 Waterford, Connecticut 06385

SUBJECT:

MILLSTONE NUCLEAR POWER STATION, UNIT 3 - REQUEST FOR RELIEF FROM ASME CODE REQUIREMENTS (TAC NO. M94498)

Dear Mr. Bowling:

By letter dated December 15,1995, Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) (the licensee), submitted to the NRC certain requests for relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI requirements. Specifically, pursuant to Title 10 of the Ggde of Federal Regulations (10 CFR) Section 50.55a(g)(5)(iii), the licensee requested (1) relief from using the rules of Article IWA-4000, " Repair Procedures," for repairs on piping, valves, fittings, nominal pipe size 1 inch and smaller, and their associated supports; (2) relief from using the rules of Article IWA-4000 and Article IWA-7000, " Replacements," for repair or replacement activities performed on seal welds; and (3) relief from the rules of Articles IWA-4000 and IWA-7000 for repair or replacement activities performed on valve discs and other nonstructural valve intemals that are constructed to a Construction Code or a Code Case for cll four plants (Haddam Neck, Millstone Units 1,2, and 3). In addition, the licensee requested, pursuant to 10 CFR 50.55a(a)(3)(i). that Code Case N-389-1, "Altemative Rules for Repairs, Replacements, or Modifications,Section XI, Division 1," be approved for use by all four plants.

By letter dated June 7,1996, the licensee revised its requests for relief and withdrew its previously requested reliefs pertaining to the rules of Articles IWA-4000 and IWA-7000 for repair or replacement activities performed on valve discs and other nonstructural valve intemals i that are constructed to a Construction Code or a Code Case. In a letter dateu February 18, 1997, CYAPCO withdrew the remaining requests for relief for Haddam Neck based on an p earlier decision by the CYAPCO joint owners to permanently cease power operations at the facility, in a letter dated August 14,1998, NNECO withdrew allits remaining requests except i for Code Case N-389-1 at Millstone Unit 3. Therefore, this letter only applies to Millstone

, Unit 3.

L The staff has completed its review of Code Case N-389-1 at Millstone Unit 3. The Code Case J

l has been reviewed by the NRC staff and is currently in process of being incorporated into the j3i j

[ forthcoming revision of Regulator; Guide 1.147. The staff finds that the altemative provided in Code Case N-289-1 would provide an acceptable level of quality and safety. t 29 l'

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2' j M. L. Bowling Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the altemative requested by the licensee is authorized. The staffs evaluation and conclusions are contained in the enclosed Safety Evaluation.

Sincerely, 1

liiam M. Dean f Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation Docket No. 50-423

Enclosure:

Safety Evaluation cc w/ encl: See next page L- _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - - _ _ _ - _ _

l M. L. Bowling -2 August 20, 1998 Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the attemative requested by the licensee is authorized. The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation.

Sincerely, i

Original signed by D. Mcdonald for:

William M. Dean l Deputy Director for Licensing i l Special Projects Office i l Office of Nuclear Reactor Regulation i f

Docket No. 50-423

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Enclosure:

Safety Evaluation i

i cc w/ encl: See next page l

DISTRIBUTION:

EDonket fi6mg, I PUBLIC l SPO-L Reading i WDean LBerry SDembek i THarris (E-mail SE only) l OGC ACRS JDurr, RI DScrenci, RI l

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l DOCUMENT NAME: G:\DEMBEK\M94498.LTR

• See previous concurrence To receive copy of document, indicate in >ox: "C" = copy w/o enci "E" = copy w/enci "N" = no copy OFFICE SPO-L:PM ,, E SPO-L:W E ECGB:BC OGC j JPO-JdD ,f(N NAME SDembek ffT LBerry $ GBagchi* RBachmanri"lWD6M DATE f /% /9F "[) /410 /98 7/23/98 7/31/98 oT/ d /98 OFFICIAL RECORD COPY l

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