Text

Final Deficiency Rept Re 600-psig ASA-rated 1-inch Hancock Valves.Wall Thickness on Remaining Accessible Valves Installed in Unit 3 & Valves to Be Installed Verified
	ML20084H776
Person / Time
Site:	Browns Ferry
Issue date:	06/12/1974
From:	Gilleland J; TENNESSEE VALLEY AUTHORITY
To:	Moore V; US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084H779	List: ML20084H776; ML20084H781; ML20084H786; ML20084H791;
References
	10CFR-050.55E, 10CFR-50.55E, NUDOCS 8305050048
	Download: ML20084H776 (9)
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o CHATTANOOGA, TENNESSEE i s

TENNESSEE VALLEY AUTHO-3740'l L AITY E""JK't '

/J June 12, 1974

$NESSE$$

PARTNEASHIP

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O Mr. Voss A. Moore, Assistant Director W for Light Water Reactors, Group 2 Directorate of Licensing -

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C U.S. Atomic Energy Cem:21ssion i,gNy 6 Washington, DC 20545 .g '4 S

. 'O p Dear Mr. Moore. D 6 In the Matter of the ) Docket Nos. 50-259 ,

Tennescee Valley Authority ) 50-260 50-296 Your letter dated May 17, 1974, concerning the 600 psig ASA-rated one-inch Hancock valves at the Browns Ferry Nuclear Plant required a final report on the survey and recertification results for the unit 3 valves and, if necessary, a reanalysis for unit 1. Forty copies,of that report are submitted herewith.

Ints(eport, togerner witn ene report on ene unic E valves, dated May 31, 1974, which was enclosed with our letter dated June 3, 1974, cons.itutes e the documentation required by 10 CFR 50.55(e).

Very truly yours, N

J. E. Gilleland f

V)

Assistant to the Manager of Power i

l Enclosure (40)

CC:

Mr. R. R. Barris Mr. Norman C. Moseley, Director (enc) '

General Electric Company - Attention: W. S. Little l 832 Georgia Avenue Directorate of Regulatory Operations Chattanooga, Tennessee 37402 U.S. Atomic Energy Commission Region II - Suite 818 230 Peachtree Street, NW.

! Atlanta, Georgia 30303 Mr. R. B. Beers Mr. K. L. Sessions TVA Projects ' General Electric Company.

General Electric co=pany , 9040 Executive Park Drive Atomic Power Equipment Department Knoxvill , Tennesseel 3{919 San Jose, California 95125 ,{/

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8305050048 740612 i (,C1f.h,LM 77 t-PDR ADOCK 05000259 $

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o Report Date: June 11, 1974 BROWNS FERRY NUCLEAR PLANT UNIT 3 FINAL REPORT ON HANCOCK 600 LB. STAINLESS STEEL VALVES Introduction TVA Abnormal Occurrence Report No. BFAO-7427W describes the occurrence and corrective acti,on taken concerning the fifty-eight Hancock one-inch 600 lb.

forged stainless steel globe valves installed in high pressure systems in unit 1. TVA final report dated May 31, 1974, on the one-inch valves of unit 2 and the 3/4-inch valves installed in units 1 and 2 includes a valve wall verification of 50% of the affected valves as well as vendor certifi-cation that these valves are suitable for design conditions of 1326 psi at 562 F.

A report including wall thickness verification on the remaining accessible valves already installed in unit 3 as well as those valves that are to be installed in the future follows. .

VALVE WALL THICKNESS MEASUREMENTS Submitted in Appendix A of this report is a tabulation of the wall thickness measurements of all of the accessible one-inch valves that have been installed in unit 3 Since this unit is still in the construction phase, these valves have not yet been assigned pemanent valve marker tags. The description and location of the thickness measurements is presented in Appendix B of this report.

Based on the sampling of the unit i valves in TVA Abnorinal Occurrence Report No. BFAO-7427W, only two measurements were taken (P2 and P4 positions).

o 70 ,

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Sutanitted in Appendix C 'of this report is a tabulation of the wall thickness

! . measurements of the remaining valves that will be installed in unit 3 or will

, . be utilized as spares. .No3/4-inchvalvesarepresentlyavailablefor installation in unit 3 1

4 The minimum wall thickness measurerent of these valves is equal to or greater than 0.287 inches. . Assuming 0.015' inch as an absolute maximum depth of marking, the minimum wall thickness is: 0.287"- 0.015"= 0.272" which 'is .in excess of the calculated required minimum wall thickness of tm

0.243" (reference sheet 2 of Appendix D, TVA report No. BFOA 7427W).

Conclusions Based on the . data presented in this report and the calcul"tions presented in TVA report No. BFOA 7427W, TVA takes the position that these nLives are fully qualified for the higher design conditions in unit 3 and request acceptance of this positf.on by the AH:. The data presented in this report and the above referenced reports on units 1 and 2 completes TVA'n reporting

.i reqairements.

New tags are being ordered from the manufacturer which will be marked 1326 psi at 5620F. These tags will be attached to all valves i.n units 2 and 3 as soon as possible, and on unit 1 as the valves become accessible.

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ML20084H776

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