ML20011D872

Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor-Darling S350W.... Review of Sys Drawings Determined That No Subj Valves Installed at Facilities

ML20011D872
Person / Time
Site:	Hatch
Issue date:	12/21/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HL-734, IEB-89-002, IEB-89-2, NUDOCS 9001020211
Download: ML20011D872 (2)

Text

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Georg a Power Company 333 Pawnont Aenue 1 o 4 5(3d5 Ma4ing Adtess P O ce L x 5 Birmingham Alabama 3f231 itkonone 20$ 668 $581 t'vmuvn t*cPK wem W. G. Haltston, Hi Senior Vce Presdont Naclear Operations HL-734 0290V December 21, 1989 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 RESPONSE TO NRC BULLETIN 89-02 i Gentlemen:

! NRC Bulletin 89-02, " Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350H Swing Check Valves or Valves of Similar Design," was issued on July 19, 1989 to all holders of operating licenses or construction-permits for nuclear power reactors. The purpose of the subject bulletin was to request that addressees identify, disassenible and insprct certain types of swing check valves including Anchor Darling. Model S350H swing check valves or valves of similar design which may contain Type 410 stainless steel (SS) bolting material. Should the Type 410 SS bolting material be of sufficiently high hardness that is susceptible to stress corrosion cracking, or has failed, addressees were requested to ' take certain actions as outlined in NRC Bulletin 89-02.

Georgia Power Company has determined through a- review of applicable vendor drawings, instruction manuals, Purchase Orders (P0s), system

! drawings, and in some cases plant walk-downs, that there are no Anchor Darling Medel S350H swing check valves' with Type 410 SS. bolts subject tc, NRC Bulletin 89-02 it Plant Hatch Units 1. and 2. In addition, we-identified no valves of similar design with preloaded Type 410 SS bolt material in use at the Hatch facility.

In accordance with the reporting requirements of NRC Bulletin 89-02, a copy of 'this submittal is being provided to the NRC Region II l Administrator.

This' submittal completes the reporting _ requirements of NRC Bulletin 89-02 for Plant Hatch Units 1 and 2. Should there be any questions, please contact this office.

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U.S. Nuclear Regulatory Commission

December 21, 1989 Page Two l~  ;

I Mr. H. G. Hairston, III states that he is a Senior Vice President of ,

Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company and that, to the best of his knowledge and belief, '

l the facts set forth in this letter are true, r ,

GEORGIA POWER COMPANY i

L By: IM M+ E

! H. G. Hairston, III Sworn to and subscribed before me this JI" day of b e e < ,,1 l, c v 1989.

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c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS U.S. Nuclear Regulatory Commission. Hashinaton. D.C.

Mr. L. P. Crocker, Licensing Project Manager - Hatch ,

U.S. Nuclear Regulatory Commission. Region II Mr. S. D. Ebneter, Regional t.iministrator Mr. 1. E. Menning, Senior Resident Inspector - Hatch ,

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