ML17334A889

Forwards Westinghouse Providing Details on Reactor Vessel Beltline Region Weld Chemistry,Including as-deposited Copper,Nickel & Phosphorus Weight Percentages for Weld Wire & Flux Used for Weld Seams

ML17334A889
Person / Time
Site:	Cook
Issue date:	07/03/1985
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0894C, AEP:NRC:894C, NUDOCS 8507090185
Download: ML17334A889 (7)

Text

REGULATOR INFORMATION DISTRIBUTION S TEM (RIDS)

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S ACCESSION NBR;8507090185 DOC',DATE: 85/07/03 NOTARIZED:

NO DOCKET ¹ FACIL:50 315 Donald C,

Cook Nuclear Power Planti Unit iE Indiana 8

05000315 AUTH BYNAME AUTI/OR AFFILIATION ALEXICH,M~ P ~

Indiana 8 Michigan Electric Co, RECIP ~NAME'ECIPIENT AFFILIATION DENTONiH ~ R ~

Office of Nuclear Reactor Regulationi Director

SUBJECT:

Forwards Westinghouse 850610 ltr providing details on reactor" vessel beltline region weld chemistryiincluding as-deposited copper<nickel 8, phosphorus weight percentages for weld wire 8 flux used for weld seams, DISTRIBUTION CODE:

AOOID COPIES RECEIVED:LTR 2 ENCLI SiZe:

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INDIANA 8 MICHIGAN ELECTRIC CONPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 July 3, 1985 AEP:NRC:0894C Donald C. Cook Nuclear Plant Unit No.

1 Docket No. 50-315 License No. DPR-58 DATA FOR REACTOR VESSEL BELTLINE REGION WELD CHEMISTRY Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

The purpose of this letter is to transmit the Westinghouse letter which provides details on the Donald C.

Cook Unit 1 reactor vessel beltline region weld chemistry (Attachment 1).

Pursuant to our discussion with your staff on June 5, 1985, enclosed are the as-deposited copper, nickel, and phosphorus weight percentages for the weld wire and flux used to fabricate the weld seams in the core beltline region of the Donald C.

Cook Unit 1 reactor vessel.

This data will provide the basis for forthcoming Technical Specification revisions pertaining to the Donald C. Cook Nuclear Plant operating curves.

This document supersedes any others provided on this subject.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, M. P. Al xich i Vice President lt'I~~

MPA/rjn cc:

John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman G. Bruchmann algol 8507090185 850703 PDR ADOCK 05000315 P

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ATTACHMENT 1 TO AEP:NRC:0894C

'" Attachment AEP:NRC:0894C Sigh oQ$8 ggg gag)g aecffk Cogcratlfw

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Hr. H. P. Alexfch, Yfce President and Ofrector Nuclear Operat1ons American Electric Power Service Corporation One Riverside Plaza

Columbus, Ohio 43216 Muc)ex Sennces lAghtks GMsiN 55 2724

~>4W ~81vm~1523O.2r28 AEP-&5-641 June 14, 1985 AHERICMI ELECTRIC POHER SERVICE CORPORATION 0.

C.

COOK UNIT 1

Reactor Vessel

&eltl fne Re fon Held Cheafstr Oear Hr. Alexfch:

A review of the weld wire and flux used to fabricate the weld seams in the core belt\\inc region of the 0. C. Cook Unit 1 reactor vessel was conducted per the request of 0. Hafer of American Electric Power Serv1ce Corporation to determine the as deposited

copper, n1ckel and phosphorous content of the as deposited weld seams.

The cfrculferentfal girth seam between the fntermedfate and lower shell is considered to be. the limiting weld seam fn the vessel.

This seam was fabricated w1th weld wire heat number 1P3571 and Linde 1092 flux lot number 3958.

E1ght separate chemical analyses are known to have been performed on this combination of the wire and flux and the results are presented below:

Source CE Held Qualification Test (Single Hire)

CE Held Qualification Test (Tandem Hire)

Kevaunee Uni rradiated Surveillance Held Haine'ankee Unfrradiated Surveillance Held Haine Yankee Irradiated Charpy Specimen Hafne Yankee Irradiated Charpy Specimen Haine Yankee Irradfated Charpy Specimen Halne Yankee Irradiated Charpy Specimen

.40

.37

.20

.36

.25

.25

.33

.33

.82

.75

.77

.78

.70

.66

.71

.70

. 017

. 017

. 016

.015

. 030

.020

.040

.040 Average

,31

.74

.024 Sased upon the above data, it fs Hestfnghouse's recawendatfon that the average of the above data points be used for the Cu and Ni content, since this would be more realistic than using any single data point.

This approach has been accepted by the NRC on other applications.

IO'd NOIDSH NHSHLflOS SLDS008d QISN SSAOHONIZSSN L P: 7 7 58

3ktacbment AEP:NRC:0894C Mr. H..P. Alexfch AEP 85 64)

June 14, 198g The phosphorous content reported for the frradfated specfoens fs considered tg, be highly suspect.

Hestfnghouse consfders the average of the four unfrradfated values

<.016 HTI) to be a realfstfc phosphorous content for the weld.

The longitudinal veld seams fn the beltlfne region of the vessel vere made with a tandem submerged arc process using veld wire heats 12008 and 13253 with Linde 1092 flux lot 3791.

No as deposited veld chemfstry exists for this comb}natfon of wires and flux.

Four other tandem ve1ds whfch contained wire heat number 12008 showed as deposited copper contents of 0.19 to 27'X.

The surveillance weld whfch was made from xfre 13253 and Lfnde 1092 flux lot 3791 and which has a copper content of 0.27K is consfdered to be highly representative of the lonqf tudtnal weld seams and the use of fts chemistry for the longitudinal weld seaes appears appropriate.

The applicatfon of new copper and nickel values to the beltline region girth veld seam of the D.

C.

Cook reactor vessel will not result fn the vessel exceeding the PTS screening limits imposed by the HRC.

Please call should you require more fnformatfon Very truly yours, APS/debf 4496f:I2 cc:

H. P. Alexfch, lL

0. Hafer, lL H. G. SmIth, 1L

a. Fefnstefn, lL A: P.

Suda, Manager Great Lakes Area Pro]ects Oepartment NOZOZH NHZHZAOS SZDZC'08d GZSN ZSAOHQNZZSZM Y 5 'T 58 '

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