ML19290C161

Forwards 791114,19,1205,06,10 & 14 Deficiency Repts

ML19290C161
Person / Time
Site:	Midland
Issue date:	12/17/1979
From:	Gibbs M ISHAM, LINCOLN & BEALE
To:	Cowan F, Linenberger G, Smith I Atomic Safety and Licensing Board Panel
References
NUDOCS 8001100178
Download: ML19290C161 (1)

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ISHAM, LINCOLN & BEALEj DE.C '

COUNSELORS AT LAS gM ONE FIPST NATIONAL PLAZA FORTY *SCCONO FLC h CNICAOC, f LLINCIS 60603 TcLcPNONc 3:a sse-,sOO TcL x: a-sese CD y

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SCvCNTN FLOOR WA S NIN 37CN. C. C.2 OO 3 G 2C2=633 9730 December 17, 1979 Ivan W. Smith, Esq. Mr. Gustave A. Linenberger Atomic Safety and Licensing Board Atomic Safety and Licensing Bd. Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Frederick P. Cowan Apt. B-125 6152 North Verde Trail Boca Raton, Florida 33433 Re: Consumers Fower Company (Midland Plant, Units 1 and 2)

Docket Nos. 50-329, 50-330 Gentlemen:

Enclosed are three S 50.55(e) reports which have recently been submitted by Consumers Power Company to the Nuclear Regulatory Commission.

Very truly y rs,

?uL6 4 Martha E. ibbs MEG:cem Enclosure cc: Service List w/

Enclosures me 3p 8001100 / 7/ 6

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RELATED CORRESPONDENCE CORSumBTS.

@f[i k- POWBr u CDsin ,98DY Stephen H. Howell

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General Offices: 1945 West Pernali Road. Jackson. Michigan 4920f e (5171783-0453 Dece=ber 6, 1979 Ecve-303-79 o- o D'q s

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h 'h Mr J G Keppler, Regional Directer Office of Inspection and Enforcement US Naclear Regulatcry C* ssion I[ [d Region III ~

799 Recsevelt Road h. Qh gG y

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MIDLAND NUCLEAR PLA'!?  % 4 UNIT NO 1, DOCKEI : 0 50-329 UNIT UO 2, DOCKET 30 50-330 SAFE SiiUTDO*ni 30PjCII' CAPA3!LIS

Reference:

Letter SEEcvell to JGKeppler; Midland Nuclear Plant; Unit Uc 1, Docket No 50-329; Unit Uc 2, Docket No 50-330; Safe Shutdcrn Beration Capability; Serial Hove-233-79; dated Octcber 31, 1979 This lette*, as was the referenced letter, is an interi= 50.55(e) repert regarding safe shutdevn capability assuming a = cst restrictive core ecnditien and the control red of highest worth stuck cut cf the core. The referenced letter was not sufficiently specific vith regard to the ste.tement that '

"...present 6 k /k . . . . " .

Midland design does no: permit achieving and =aintaining e.15 In fact, the present design can achieve the 15 6 h/k shutdo ~:

=a.rgin as required by General Design Criterion 26 un rods alene with the ecnditic=s ctated. Eevever, under these conditicas and also with the assumption that non-safety grade syste=s cannot be utilized, the 15 4 h/h shutdowncapability heration =argin cannet that benew maintained exists. as the xenen decays with the safety grade On October 15, 1979, CPCo directed 3echtel, the Architect-Engineer, to prepare a syste= design which increases the safety grade beration capability.

Sechtel's preliminary syste= design is presently undergoing review by CPCo and 3Fa', the RSSS supplier.

by the end of Farc.1, 1930. Finalization of the syste= design is anticipated 1726.333 q#

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Hove-308-79 Another report, either interin or final, vill te sent on or before April 11, 1980.

% 0% 0 k'RB/1r CC: Director of Office of Inspection & Enfu cenent Att: Z'r Victor Stello, US iRC (15)

Director of Office of Manasenent Infomation & Progrc= Control, USITEC (1) 3CC: JL3 acon, M-1085A WR31rd, JSC-2163 JLCorley, Midland LECurtis, 3echtel AA LADreisbach, 3echtel-Midland G3Keeley, Plk-h083 CEMahaney, 3&W-Lynchburg BWMarguglio, JSC-220A DBMiller, Midland WGMoring, Bechtel AA -

JARutgers, Eechtel AA MJSalerno, P2L-619 MEGibbs, IL&B Great Lakes QA Managers File: 0.k.9 36 e

1726 336

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Stephen H. Howell senior Vice President General offices: 1945 West Parnell Road. Jackson. MicNgen 49201 e (5171788-0453 Dece=ber 10, 1979 Hove-310-T9 Mr J G Keppler, Regional Directer Office of Inspection and Enforce =ent Region III US Nuclear Regulatory Cec =ission T99 Roosevelt Road Glen Ellyn, IL 60137 MIDLAND NUCLEAR PLAIIT UNIT NO 1, DOC *C No 50-329 UNIT No 2, DOC:G No 50-330 IIGACT TISu J - ITT GRIICIELL SUPPLIED MAIN FEED PIPE

Reference:

S E Ecvell letters to J G Keppler; Midland Nuclear Flant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; I= pact Tested - ITT Grinnell Supplier Main Feed Pipe;

1) Serial Hove-lT5-79, dated June 20, 1979

2) Serial Hove-215-79, dated August 1,1979

3) Serial Hove-2k2-79, dated Septe=ber T,19T9 h) Serial Ecve-275-79, dated October 26, 1979 The referenced letters were interi: 50 55(e) reperts on the Main Feed Pipe Spcols which had questionable impact test results.

report. .

This letter is the final The Midland Plant is now in confor=ance in that the pipe spcols supplied, or being supplied, for the =ain feed lines meet the physical i= pact requirements Code Criteria. for the =aterial in accordance with AS:G Section III, Class 2, .

fer i= pact properties Thereatis aone miniheat

=u:which did not =eet the Codg require =ents service te=perature of 30 F. There is another heat which had a questionable basis for code cc=pliance based en a subsequent heat treat =ent used to i=preve i= pact properties of SA-106

=sterials.

These heats have been shown to meet er exceed the code require-

=ents for a =ini=u service te=perature of TO F, which is the revised specified te=perature for the spec 1s associated with theae heats.

For Heat N-32T62, there was a single spool which vent through a het bend process and for which impact property tests were taken (at 30 F) after all heat treatment processes were completed. These i=pu:t property test 1726 337 ]d((

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2 Hove-310-79 results were not acceptable. It has been shown that the lov test results were not related to the hot-bend process. This spool piece has been scrapped at the vendor and a replace ent spool vill be provided.

The attachment provides a more complete su= mary of the actions taken to resolve the reported cendition.

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h3B/lr Attach =ent: MCAR-29, Final Report, Dated Novemb'er 19, 1979 CC: Director of Office of Inspecticn & Enforce =ent Att: Mr Victor Stello, USNRC (15)

Director, Office of Manasement Infermation and Prcgram Control, USNRC (1) s BCC: JL3 acon, M-1085A RCEau=an, P1h h12 bR31rd, JSC-2163 ,

AJEirkle, P2h-511 -

JLCorley, Midland LHCurtis, Eechtel AA LADreisbach, Bechtel-Midland GSKeeley, Plh-hC83 SW.arguglio, JSC-220A DBMiller, Midland RLRixford, Eechtel AA LEDavis, Bechtel-Midland RLTeuteberg, Plk h18 d ibbs, IL&B File: 0.k.9 27 e

a 1726 338

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Bechtel Associates ProfessionalCorporation Attachment to

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Howe-310-79

SUBJECT:

HCAR 29 (issued 5/22/79, revised 5/25/79) .

Impact Testing of ! bin Feedwater Pipe FINAL REPORT

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DATE: November 19, 1979 .

PROJECT: Consuuers. Power Company Kidland Plant Units 1 & 2 Bechtel Job 7220 Introduction This final ' report is prepared in response to Midland project management Corrective Action Report 29. This consludes and summarizes our actiens as previously reported in Interim Reports 1 through.4.

Description of Discrepancy During a review of Crinnell documents, the NRC identified nine pipe spools f abricated f rom ASME SA 106 Grade B pipe, Heat N-32762, which f ailed to meet the physical impact requirement for the material in acccordance with ASME Section III Class 2 Code criteria. Crinnell subsequently notified Bechtel of the potentially reportable discrcpsney.

Potential Safety Implication A potential safety problem would exist if inadequate material impact toughness properties at low feedwater temperatures resulted in, or contributed to, a main f eedwater line break.

Summary of Investigation and Historical Background Bechte5, af ter being informed by Grinnell that a discrepancy with poten-tial saf,ety i=plications existed, reviewed at Grinnell 70 spool data packages for impact test properties. This review covered all material requiring Charpy impact testing. This review was done to determine whether additional material, other than that identified during the NRC audit, ce specifications and ASHE Section III, Class 2 Code require-ments.

• The specific Code requirements are as follows: .

In accordance with NB 2332(1) of ASME Section III, test three CV (Charpy

. V-notch test) specimens at a temper lowest service temperature. All th ments of Ta ble HB 2332-1.

DUPLICATE DOCUMENT According to Table NH 2332-1, the r Entire document previously f ollows : entered into system under:

1726 339 ^no 7?/N3ddY No. of pages:

1. C011SumBIS J

(D ",M POW gggy8f Stephen H.Howell r I Senior Vice Presutent General Offices: 1945 West Pernell Road, Jackson, Michigen 49201 e ($171788-0453 December lb, 1979 Hove-311 -79 Mr J G Keppler, Regional Director Office of Inspection and Enforcenent US Nuclear Regulatory C - 4ssion Region III 799 Roosevelt Road Glen Ellyn, IL 60137 MIDLAND NUCLEAR PLANT UNIT NO 1, DOCKET No 50-329 UNIT NO 2, DOCKET No 50-330 UNIT NO 1, REACTOR VESSEL 330KI~i ANCHOR SOLT

Reference:

Letter SEEovell to JGKeppler; Midland Nuclear Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket Ho 50-330; Unit No 1 Reactor Vessel Broken Anchor Solt; Hove-267-79; dated October 12, 1979 This letter, as was the referenced letter, is as interi= 50 55(e) report concerning the broken anchor bolt in the Unit 1 reactor vessel support skirt flange. The attach =ent to this letter provides a status of the actichs bein5 taken to resolve this condition.

Another report, either interim or final, vill be sent on or before March 3, 1980.

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WRS/lr Attachnent : 3rohen Eeactor Vessel Anchor 301t in Unit 1 Status Report, dated Dece=ber 5, 1979 CC: Director of Office of Inspection & Enforcement Att: Mr Victor Stello, USNRC (15) 1726 340 Director, Office of Manage =ent Infcr=ation and Progra= Control, USNRC (1) ',

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• Hove-311-79 BCC: JLBacon, M-1085A RCBaunan, Plk k12 WRBird, JSC-216B JLCorley, Midland LHCurtis, Bechtel AA LADreisbach, Bechtel-Midland GSKeeley, P1h h08A B4farguglio, JSC-220A .

DBMiller, Midland RRicksford, Bechtel AA BBPeck, Midland JARutgers, Bechtel AA Erdhitcher, Mid1cnd MEGibbs, IL&B File: 0.k.9 35 O

1726 341 s

Date: 12/5/79

SUBJECT:

BROKEN REACTOR VESSEL ANCHOR STUD IN UNIT 1 STATUS REPORT Introduction This report s-arizes the additional action taken to date to dete. ine the failure mechanism of the subject anchor stud and corrects the identity of the procure =ent source for the stud that failed.

History of Failed Stud The anchor stud that failed was identified as stud number 35, and was in-correctly located on Figure 1 of the previous status report. More correctly, the stud has no specific numerical identifier, the cited nunber 35 being enly the Babcock and Wilcox tensioning sequence identifier. The revised Figure 1 attached clarifies the identified position of the stud.

This stud was purchased from Mississippi Valley Structural Steel Cc=pany who procured the material frc= Southern Bolt and Fastener Corporatien. The material originated frc= 3ethlehem Steel, was heat treated by J W Rex Cc=pany of Lansdale, Pennsylvania, for Southern Bolt and Fastener Corporation, and co=pleted and shipped by Southern Bolt and Fastener Corporation directly to Bechtel.

Investigation Plan Bechtel, as agents for Consumers Power Cc=pany, has entered into a Technical Services Agreement with Teledyne Engineering Services of Waltha=,

Massachusetts, for testing and censultant services to dete. ine the cause cf the failure. 7he progra= fer planned testing re=ains as described in the previous statut report.

The testing con =enced en Nove=ber 15, 1979 with Non-restructive Examinatien.

The expected ce=pletion late for the planned series of tests is mid-January, 1980, with results available by =id-February,1980. After the results are received frc= Teledyne and reviewed, a course of acticn to ccrrect this deficiency vill be deter =ined.

Safety I=rlicatiens 3ased en preli=ina y analysis, it is judged that the failure of a single anchor stud does not represent an i= pediment to the safety-related support requirements for the reactor vessel. Overall safety implicatiens vill be further evaluated upon receipt of test data.

Revertability This condition remains in the pctentially reportable category pending the results of the currently in progress testing progra=.

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