ML20147B874

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Forwards SER Opposing Basis for Conclusion That Util Reported Values of Copper & Nickel Content of Reactor Vessel Beltline Welds,Per 870918 Submittal
ML20147B874
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 02/26/1988
From: Muller D
Office of Nuclear Reactor Regulation
To: Butterfield L
COMMONWEALTH EDISON CO.
Shared Package
ML20147B879 List:
References
TAC-60777, TAC-60778, NUDOCS 8803020231
Download: ML20147B874 (3)


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LMr.~ L.iD. Gutterfield, Jr. 43PD3:2 Rdg File - :JPartire

. Nuclear LicensingiManager-

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GHolahan- # .ACRS410)c w . Connonwea.1th Edison Company -

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DearMr.dutterfield:

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SUBJECT:

/ ZION STATION LNIT 1 AND 2L ; CCPPEL CONTENT OF REACTCP VES$a.

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  • RELTLINE WEl.DWR PTS EVAU!ATION (TAC NO3, 60777 AND 60778) .

6 ,q . .i W he'enclo's'ed Safety EvaluatioI: Re ort is a. review of tho third submittal from

' (qtionwealth , Edison Company,(CECO L giving the bdsis for Ceco's position with g%. $E l regard to thocopper and n1cici contents 4f the control!ing beltline material

'g~e for Zion Station' Units 1 and 2, submitted ii? response to the Pl3 rule,10 CFR

50.61.

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The first PTS. sub.nittal 'fot fion i and 2 tyCECo on January.17,1986 wa: t3 sed i= on t report by Westingnouse elm?ric Ccepora'f. ton. WCAP-10962. The control M y

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. reactor vessel material from the stand /oint of kassurized thermal shock

< evaluations was torrectlyidentifiedis the circumferential beltline weld in

- ' the Zioni reactor vessel-and the lower shell. longitudinal welds in the Zion 2 O reactor vusel.1 :Soth critical welds were made 'with weld wire heat number

'* 72105. .To arriveht the best estimate copper = and nickel contents for. these vessel' welds, Westinghouse averaged 87;neasurenent; give in WCAP-10962 that had been reportta for several weldments made with Wire 72105. All but 30 of these came from studies made by B&W and repcrted in'BAW l/99. The unusually

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large number of measurements of copper and nickel sontents for heat 72105, was

& the risult of some special-studies conducted by B&W to Otermine throughwall N variability in a nozzle dropout, rnd other studies on pieces of weld material '

from the archives. ,

19 45 . lov themical composition given in BAW 1799 was 0.35% Cu mnd 0.59% N1. How-evter, in WCAP-10962, Westthghouse added about 30 neasurements taken mainly

- from two surveillance rgports by Southwest Research Institute (SWRI) which gave the results of X-ray fluoretcirnce rea:;urements on irradiated broken Charpy

~ . bars. When these 30 measurements are included, WCAP-10962 reported an average E

of 87 values of 0.32% Cu and 0.56% N1.

In tits review of the first ".ECo submittal for Zion 1,'the staff conclud64 that W*

< soif of-the 30 measurements included in the list in WCAP-10962 were not appro-

. priate, and the copper and nickel contents should be 0.35% and 0.59%, respec-4 4 tiy% f, as reported .in BAW 1799. The finding was transmitted to CECO by letter pp -n y6 4

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% 8803020231 880226 j PDR ADOCK 0500029" p PDR l

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r-L. D.- Butterfield, Jr. February 26, 1988 -

2 of August- 14, 1986. At a meeting on October 3,1986, representatives of CECO and Westinghouse presented additional data and arguments in support of their position, but their arguments were not persuasive to the staff. The CECO position was put in writing in another submittal dated December 29, 1986, which referenced WCAP-11350, a compilation of the technical information presented at the meeting. The staff again did not support the CECO position in an SER transmitted to CECO on May 7, 1987. A third submittal by CECO, dated September 18, 1987, commented on the staff SER and restated the contents of their December 29, 1986 submittal in the form of attachments to the letter.

The enclosed SER is a review of the September 18, 1987 submittal.

The staff has reviewed the Ceco submittal of September 18, 1987. Our

conclusion is unchanged from the one transmitted to Ceco on August 14, 1986, and again on May 7, 1987. We find that the CECO submittal provides no new information. Our enclosed SER gives the basis for the conclusion that the Ceco's reported values of copper and nickel content are not acceptable and that when "RT " is evaluated using values the staff finds appropriate, the Zion Unit 1 p15N will reach the screening criterion before the end of licensed Itfe. Ceco, therefore, sheuld submit plans for further flux reduction. The Zion Unit 2 plant has the same controlling material, bt;t the reported fluence  !

is low enough to prevent reaching the screening criterion before the end of  :

licensed life.

The staff believes that further discussion of the statistical treatment of the data would be productive only if Ceco were to present new information with regard to the copper and nickel content of the weld material.

Sincerely.

Original Signed by/

Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

As stated cc: See next page

(*See Previous Concurrence)

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Mr. L. D. Butterfield, Jr.

Connonwealth Edison Company Zion Station cc:

Robert J. Vollen. Esq. Mr. Michael C. Parker, Chief 109 N. Dearborn Street Division of Engineering Chicago, Illinois 60602 Illinois Department of Nuclear Safety Dr. Cecil Lue-Hing 1035 Outer Park Drive, 5th Floor Director of Research and Development Springfield, Illinois 62704 Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Mr. P. Steptoe, Esq.

Isham, Lincoln and Beale Three First National Plaza Suite 5200 Chicago, Illinois 60602 Mayor of Zion Zion, Illinois 60099 Illinois Department of Nuclear Safety ATTN: Manager, Nuclear Facility Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 U.S. Nuclear Regulatory Commission Resident Inspectors Office 105 Shiloh Blvd.

Zion, Illinois 60099 Regional Administrator, Region III U.S. Nuclear Regulatory Connission 799 Roosevelt Road Glen Ellyn, Illinois 60137

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