ML19225B820

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Responds to IE Bulletins 79-04 & 79-07.Correct Velan Valve Weights Used in Piping Analyses.All Computer Codes Used in Seismic Stress Analysis of safety-related Piping Verified
ML19225B820
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 05/29/1979
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 7907260079
Download: ML19225B820 (3)


Text

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. s m bM Q' , KANSAS GAS AND ELECTRIC COMPANY Ma;r 23, 1979 stes~ t. not st c a v<t eettiot=t-oes=4' oma Mr Karl V Seyfrit, Director Of fice of Inspection and Enforcement U S Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlir.g ton, Texas 76011 Re: RIV Docket No. STN 50-482/IE Bulletin No. 79-04 RIV Docket No. STN 50-482/IE Bulletin No. 79-07 Ref: 1) Letter of 3/30/79 from Of fice of Inspection and Enforcement, NRC to KG&E

2) Letter of 4/14/79 from Of fice of Inspection and Enforcement, NRC to KG&E

Dear Sir:

The referenced letters required action from KG&E in rcgard to IE Bulletins 79-04 and 79-07. The responses to both bulletins are provided below:

s-IE Bulletin 79-04 IE Bulletin 79-04 concerned inccrrect weights for swing check valves. manu-factured by the velan Engineering Corporation and requested certain actions by licensees and permit holders. The following information is provided in response to your letter. The items below are numbered to match the bulletin action items.

?) The following seismic Category I piping systems will utilize 3, 4 or 6 inch Velan swing check valves:

a) Component Cooling Water System b) Essential Service Water System c) Reactor Coolant System d) Auxiliary Feedwater System e) Feedwater System f) Compressed Air System g) Auxiliary Turbines System

2) The correct valve weights were used in piping analysis. On April 20, 1979, the Velan Engineering Corporation informed the SNUPPS architect engineer, Bechtel, that the weight of all swing check valves as shown on project engineering drawings were acceptable. Bechtel reviewed relevant piping stress analyses to verify that weights used were equal to or greater than those shown on the Velan Drawings. This review was completed by May 2, 1979.

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201 N. Market - Wichda, Kansas - Mail Address: P. O. B x 208 / Wichita, Kansas 67:31 - Telechone Area Code (316) 264-1111

Mr Seyfrit Page Two May 29, 1979

3) Incorrect valve weights were rot used.
4) No modifications are required because the correct valve weights were used.
5) This item is not applicable because modificatir,as and/or stress re-analysis w<tre not required.
6) This item is applicable to holders of operating licenses only.
7) No outstanding matters in Items 1 through 5 above have been identified.

Documentation of our actions in regard *o this IE Bulletin are avail-ablve for NRC inspection.

IE Bulletin 74-07 IE Bulletin 79-07 concerned seismic stress analysis of safety-related piping.

The following information is provided in response to your letter. The items below are numbered to natch the bulletin action items.

1) None of the methods specified in the IE Bulletin were used for the aismic analysis of safety-related piping.
2. 2his item is not applicable because of the response to Item 1 above.
3) All computer codes used in the seismic analysis of safety-related piring have beco verified as shown below:

a) ME 632: Verified using PISOL (EDS Muclear Irc), PIPMO (UPS/ John A Blum and Associates, Engineers) and TPIPE (PMD Systems Engineering Inc) b) n' 101: Verified using RE 632, TPIPE and SUPERPIPE (EDS Nuclear Inc) c) TPIPE: Verified using PISOL (EDS Nuclear Inc) and ME G32 d) BSAP: Verified using FE 101 e) WESTDYN: Refer to WCAP 8252, Rev 1, ' Documentation of Selected Westinghouse Structural Analysis computer Codes",

May 1977, which is currently under NRC review.

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Mr Seyfrit Page Three May 29, 1979

4) This item is not applicable because of the response to Item 1 above.

Sincerely,

,fs g' ,, '? g'd(f.,

o aa GLK/ ash cc-Mr Norman C Moseley NRC Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D C 20555

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