ML19263C951
| ML19263C951 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/19/1979 |
| From: | Gibbs M ISHAM, LINCOLN & BEALE |
| To: | Cowan F, Kornblith L, Smith I Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 7903200097 | |
| Download: ML19263C951 (1) | |
Text
.
ISHAM, LINCOLN & BEALE WH:D CCRRES?02 D:: 02.
COUNCELCRS AT LAW oNC FIRST NATICNAL PLAZA FORTV-S ECONQ FLCOR CMICAGO, tLLf NCIS 606C3 TELE *MO N C 312 *Te 6-7500
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was mNovoN, o. C. a c ose February 19, 1979 Ivan W.
Smith, Esq.
Mr. Lester Kornblith, Jr.
Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C.
20553 Washington, D.C.
20555 g e.y Dr. Frederick P. Cowan d
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6152 N. Verde Trail N
Apt. B-125
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Re:
Consumers Pcwer Company g
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h (Midland Plant, Units 1 and p'.
Docket Nos. 50-329, 50-330 9
Gentlemen:
W Under the provisions of 10 C.F.R. 550.55 (e), Consumers Power Company is required to notify the Nuclear Regulatory Commission of certain defi-ciencies in the design and construction of the Midland Plant and to submit a written report describing and analyzing each item.
In com-pliance with this regulation, the Company has submitted reports to the appropriate NRC officials at Region III, the Office of Inspection and Enforcement, and the Office of Management.
As counsel for Consumers Power in the operating license proceedings for the Midland Plant, we are providing for the information of the Atomic Safety and Licensing Board and parties copies of reports filed by the Company pursuant to S50.55 (e) since the Notice of Hearing for these proceedings was issued on October 12, 1978.
The only report not being provided is the first one concerning the diesel generator build-ing settlement which was previously transmitted to the Licensing Board and parties by the NRC Staff.
Hereafter, all S50.55(e) reports will be distributed to the Licensing Board and parties as they are submitted by Consumers Power.
Very truly yours, 1
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l hC@ilN c. C)k6 Martha E. Gibbs MEG bc cc:
Service List w/ enclosures 790320009}
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27 Mr J G Keppler, Regional Director Office of Inspection and Enforce =ent l[
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799 Rooseve'.t Reed Glen Ellyn, IL 60137 A
cn MIOLAND NUCLEAR PLA5~' -
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- NO.1, DOC}~C NO. 50-329 UUIT No. 2, DOCKIT N0. 50-330 ELECTRICAL ??3r?>CION ASSHOLY In accordance with the require =ents of 10 CFR 50.55(e), this letter eenstitutes an interi= report en the status of discrepancies found in the inheard ter= int.1 boxes of Unit 1 c.nd 2 electrical penetration asse=blies.
A description of the discrept.ncy, potential safety i=plicaticns, investigation and plany:ed corrective actions are docu=ented in the attach =ents to this letter.
Another repert, eithe: interi= or final, vill be'se,nt en er before I'. arch 31, 1979
-Y v-t Attach =ent:
1.
Quality Assurance Fregram, Manage =ent Corrective Action Report, MCAR-1, Fepcrt 26, dated Dece=ber 19, 1978.
Letter, P. A. Martinen to G. S. Keeley, ELC 6993, MCAR-26, 2.
Interi= Report 11, with attached repert.
CC:
Directer cf Office Inspection end Inforce-: cat Mr. Jchs 9. Eavis, Acting Director, USNRC (15)
Att:
Director of Office of Manage =ent Infor=ation and Progra= centrol, USNRC (1)
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AMUEC2 Hove 16-79 Bechtel Power Corporatior, 7,77 East Eisenhower Parkway
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-y as.auense P.O. Box 1000. Ann Arbor. McNgan 43106 January 10, 1979 BLC-6993 ifr. G. S. Keeley Project. Manager CONSUMERS POWER COMPANY 1945 West Parnall Road Jackson, luchigan 49201 s
Hidland Units 1 and 2 Consu=ars Power Company Bechtel Jeb 7220
_MCAR 76 IIEERIM REPORT 1 Files 2417/2801
... 3;
Dear Mr. Keeley:
. Transmitted for your infor=ation and use.is the first interim report
' submitted for the electrical penetration assembly inadequate wire ter=inations (MCAR 26).
The next interim report is scheduled for March 15, 2.979.
Very truly yours,
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P. A. Martinez Project Manager PA!!/AEB/pp cc:
Mr. R. C. Bauman Mr. W. R. Bird Mr. J. L. Corley Attach =ent (3 pages).
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JANl11979 QiffiliY 1,$SilPM.DE
..e MCAR Report No. 26 f
Page 2 Description (continued) 1.
Teminal bon for 22113 a) Teminals 3-17 and K-4 wires pulled easily out of teminal lugs.
b) Teminals L-3 and L-8 connections were very loose on ter-N1 block.
2.
Ter=inal box for 1"129 a) Ter=inals F-1, L-1 and E-15 wires pulled easily out of teminal lugs.
b) Teminals C-15 and E-19 have uninsulated lugs installed.
3.
Teminal box for 12131
'a)
Ter=inal G-10 wire pulled easily out of ter=inal lug.
b) Teminals J-10 K-1, K-2, K-3, and K connections were very loose on teminal block.
In addition to these discrepancies, approxi=ately 20b of the viring in the three teminal boxes exhibited the following:
1.
Wires not fully penetrating lug barrel 2.
Crf=ps not tight 3.
Cri=ps caught very tip of vire 4.
Barrel of lug collapsed preventing full wire ec=pression.-
Note:
There are no field inspections required to verify vendors worleanship.
After the penetrations are released from the venders and accepted by Bechtel's shop inspectors the penetrations are shipped to the site for installation.
Recormended Action:
(continued) 4.
Detemine if there was a breakdown in the vendor quality control program and/or the Bechtel shop inspection program.
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.A'ITAC!E4EhT 1 QUALilY A55UllAt Ch PituGIIAM Hove 16-79 p,.
. MANAGEMENT CORRECTli/E ACTION REPORT
, gipM k.y Re-typed from telc/ copy received MCAR.1 REPORT NO*
26 12/20/78 signed by E. Smith on 12/19/78 JOB NO. 7MO O NO.
1 m9 OATE nnandne in-in7R l' DESCRIPTION (lac!uding references):
t client inspection of three installed electrieni penetrations revealed inadequate crimping
'This has been docu=ented in of wires located in the penetrations inboard teminal boxes.
'PCo liCR M-01 '4-8-107 issued 12/19/78. These terminations were dor.e by the manufacturer uphenr1 Sa=s/ Dunker R co prior to shipment. This inspection as witnessed by Bechtel Field enc ne Ing and Qa lity Control, identified the following discrepancies:
i (see page two)
' RECOMMENDED ACTION (Optional) l.
Determine what effect these discrepancies, if gone undetected, would have on plant safety.
2.
Investigate the inboard terminal boxes on all penetrations for inadequate teminations cnd corrcet accordingly.
3.
Determine the root cause of the discrepancies and take appropriate corrective action to preclude recurrence.
."(see page two)
REFERRED TO
@ ENGINEERING CONSTRUCTION
-] OA MANAGEMENT C
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] PROCUREMENT ISSUED BY Project Engineer h O*
NOTIFIED CLIENT 12/21/78 il REPORTABLE DEFICIENCY Md.
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CORRECTIVE ACTION TAKEN A
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FORMAL REPORT TO CLIENk g9,)g"g' (if Section ll Applies)
Date stv. trun e xer.
l tt jett tauger N.ti.e,'s.' 7 *" E =" l*r' CORRECTIVE ACTION IMPLEMENTED re ju t r,is wer ri..s.ri/rr.s.c.ut.rar..c rrej.ri m w.n n e r.r.
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1 BCC: JLBacen, M-1085A BW.arguglio, JSC-220A WRBird, JSC-216B PAMartinez, Bechtel AA RLCastleberry, Bechtel AA DBMiller, Midland TCCooke, Midland WGMoring, Bechtel AA JLCorley, Midland JNevgen, Bechtel-Midland eisbach, Bechtel-Midland MJSchaeffer, Midland
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Attachter.t to DLC-6993 Page 1
SUBJECT:
MCAR 26 (Issued 12/19/78)
Electrical Penetration Assembly,' Inadequate Wire Terminations INTERIM REPORT 1
January 8, 1979 DATE:
Consumers Power ~ Company PROJECT:
Midland Plant Units 1,& 2 Bechtel Job 7220 Introduction This report is submitted to advise regarding the' interim status and course 26 and CPCo NCR M-01-4-8-107.
of action required pursuant to MCAR Description of Discrepancy Pield inspection by CPCo of three installed electrical penetration assemblies revealed the following discrepancies associated with wire i l terminations located in the penetration assemblies' inboard term na boxes:
Inadequate crimping of lugs - vires pulled out easily 1.
Inadequate crimping of lugs - cri=ps not tight 2.
Inadequate crimping of lugs - vires not fully penetrating lug 3.
barrel Inadequate crimping of lugs - crimps caught the very tip of wire 4.
Inadequate crimping of lugs - barrel of lug collapsed, preventing 5.
full. wire compression Incorrect type of lug used - insulated lugs specified, but uninsu-6.
lated types found on some terminations Inadequate termination of lug to terminal block - connecticas icose 7.
on terminal blocks O
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Senior Vice Presidens 49201 + (5171788-0453 General oHices: 1945 West Pernell Road, Jeckson, Michigen January 5,1979 Hove h-79 f @ Isc:a
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US Nuclear Regulato:y Co= mission 2-
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.79o Roosevelt Road Glen Ellyn, IL 60137 MIDLAND UUCLEAR PLAS" UNIT NO 1, DOCKET 50 50-329 UNIT NO 2, DOCKET No 50-330 PRESSURIZER HEA m SYS 3 Consumers Power Co=pany informed the NRC on December 7,1978 of. a potentially reportable catter concerning the plant conditions following a S The specific' issue is that no engineering evaluation is available
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which addresses the unavailability of pressuriser heaters during plant het systems.
This letter is an interim 50.55(e) report on this subject.
shutdown.
There are two options available which are being pursued, which should result in the resolution of this issue. They are as follows:
CPCo cnd 3&W are investigating the feasibility of perfor=ing a complete evaluation te define the plant response to unavsilability of 1.
engineering An engineering plan to pressurizer heaters during plant hot shutdown. conduct this or alterna 28, 1979 Also to be option is not viable vill be available by Februa y investigated are specific operating procedures which could be taken It may well be following an SEF to assure acceptable plant cenditions.
possible to de=onstrate that the availabilit/ of heaters is not a requirement.
Consuners has requested B&W to perform an engineerina evaluation to determine if a sufficient nunber of pressurizer heaters vould be operable 2 -.
The methodology to be employed is not finalized at this following an SSE.
time.
As a natter of infernation, CPCo made a decision in Nove=ber, in order to enhance plant licensability, to upCrade to Class 1E pressuriser control and f[
power supply for a portion of the heaters in each pressurizer,
- qOaCP
Bechtel Associates ProfessionalCorporation '
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MCAR 26 U;TERIM REPORT 1 Page 3 January 8, 1979 Attachment to BLC-6993 Safety Implication Most of the discrepancies identified are of a nature that would be suspect to a failure =cdc.
'Ihe failure mode vould most likely be an electrical circuit disruption. The discrepancies were identified in Therefore, a circuit penetration assemblics for Class 1E circuits.
disruption would be classified as a failure of the ciectrical penetration assembly to perform its intended safety function.
Based on the potential failure code and resulting safety i= plication, these deficiencies are considered to-be reportable as stated in the MCAR.
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Forecast Date on Corrective Action 2.
A schedule for the corrective actions will be pr'ovided in Interim Report O
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.r Concurrence by J
JK/j s 1/5/4 e
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Bechtel Associates Pro.fessionalCorporation MCAR 26 INIERIM REPORT 1 Page 2 January 8, 1979 Attachment to BLC-6993 Probable Cause Electrical connections are visually checked at random by Bechtel Supplier Quality Representative (SQR) as part of inprocess inspection.
Electrical connections are subj ected to a 100% electrical check according to the supplicr's acceptance test procedure. Elec:rical tests are randomly witnessed by Bechtel SQR. All verification documents, including the required electrical tests (insulation resistance arc continuity) are checked by Bechtel SQR prior to releasing material for shipment. Further investigation is being made to determine why the random check by tha SQR did not discover any discrepancies.
The cri= ping tools shich were used for the Midland. work were subjected to regu7ar calibration checks and pull tests to verify calibration.
Pull tests were randomly witnessed by Bechtel SQR.
The records for the calibration and pull test were rechecked in late December 1978 by Bechtel SQR and found satisfactory.
The supplier's QA manual and their acceptance test procedures require
' inspection and verification of each =anufacturing operation.
Based on this requirement and in view of the discrepancies identified, it would appear that there was a breakdown in the supplier's quality control program. The supplier (Bunker Ramo-Amphenol Saps Division) vill be requested to provide their own assessmer.t of the p,robable cause of the apparent breakdown in their quality control program.
Corrective Action Although all of Midland's presently known electrical penetration assemblics have been delivered to the jobsite, the supplier will be notified to identify corrective action to be taken to prevent recurrence for potential add-on orders.
With regard to the assemblies on the site, investigate the inboard terminal boxes on all penetrations for inadequate terminations and document the findings.
Each individual nonconforming termination will be dispositioned accordingly.
It is noted that of the total 92 c1ccerieni penetration assemblics (46 per unit), 26 assemblies (13 per unit) are designated for Class 1E circuits.
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2 Hove h-79
'a Another interim 50.55(e) report vill be provided on or before March 16, 1979 at which time we vill provide the status on the above two options.
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CC: Director of Office of Inspection & Enforce =ent Mr John G Davis, Acting Director, USNRC (15)
Att:
Director, Office of Management Information & Progra: Control, USHRC (1) 3CC: JL3acen, M-1085A RC3au=an, Plk hl2 WR3ird, JSC-2163 RLCastleberry, Sechtel AA JLCorley, Midland LADreisbach, Bechtel-Midland GSKeeley, P1h h083 CEMahaney, 3&W Lynchburg EM4arguglio, JSC-220A D3 Miller, Midland WGMoring, Bechtel AA JFNewgen, Bechtel-Midland M ibbs, IL&B File:
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Senior Vice Pressdent General Of fices: 1945 West Parnell ' toad, Jackson, Michigan 49201. (517) 788-0453 January 12, 1979 g\\ EN I J Hove-ll-79 d
,p]J, Mr J G Keppler, Regional Director
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Office of Inspection and Enforcement Regicn III g(.4
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US nuclear Regulatory Cc==ission
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N 799 Roosevelt Reac Glen Ellyn, IL 60137
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MIDL'UD UUCLIAR PLAliI' -
. UNIT I:0 1, DOC m 50 50-329 UNIT EO 2, DOCKET HO 50-330 SMALL 2REAK ANALYSIS
Reference:
S H Howell letters to J G Keppler; Midland Nuclear Plant; Unit No 1, Docket No 50-329; Unit ::o 2, Decket. no 50-330; S=cil Ereak Analysis -
- 1) Serial Hove-Th-78; dated May 12, 1978
- 2) Serial Ecue-12k-78; dated July 18, 1976
- 3) serial neve-182-78; dated september 29, 1978 The referenced letters were interi 50 55(e) rei:crts as is this letter.
The HPI cross-connect =odification, described in References 2 and 3, vill be implemented.
P&.ID's M h03 and M h0h have been revised to incorporate the cross-connect and are currently in drauins: distribution. Isc=etric drawings have been drafted, and preliminary stress analysis has baen ec=gleted for the Unit 1 piping.
'"hese isc=etrics have been trans=itted to and approved by E&W es acceptable routings. Because the Unit 2 piping is identical, no additional engineering is required other than the preparation of the isc=etrics issued for fabrication. It is expectec this will be cc=plete by early February,1979, at which time =aterial procurc=ent vill ec==ence.
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'2 Hove-ll-79 Another report, either interi:n or final, vill be submitted on or before March 12, 1979 a
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L,L C cbCf gD CC: Director, Office of Inspecticn & Enforcement Att: Mr John G Davis, Acting Director, US NRC (15)
Director, Office of Management Infor:cticn end Pr gra= Centrol, US NRC (1)
ECC: JL2scon, M-lC85A RC3auman, Pik hl2 WR31rd, JSC-2163 RLCastleberry, 2echtel AA TCCocke, Midland JLCorley, Midland LADreisbech, 2echtel-Midland GSKeeley, P14 h083 CE ahaney, S&W Lynchburg EGiarguglio, JSC-22CA DEMiller, Midland kUMoring, Eechtel AA JFUevgen, Bechtel-Midland
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.j 1945 West Pernall Road. Jackson, Michi9sn 49201. (5171788-0453 g
General Of fices:
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6 Mr J 't Keppler, Regional Director Off'.cc of Inspection and Enforce =ent
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/,N'i'CD US Nuclear Reguintory C - 4ssion 799 Roosevelt Road Glen Ellyn, IL 60137 MIDL/JO NUCLEAR PLANT -
UNIT NO 1, DCCNET No 50-329 U.TI No 2, DcCKEr No 50-330 CGG01CC QUALIFICATION TEST DOCUGTIATION RE-EIVIEW
Reference:
Letter, S H Howell to J G Keppler; Midland Nuclear Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; Co=ponent qualification Test Docu=entation Re-Review; Serial Hove-252-78, dated November 28, 1978 The referenced letter was an interis 50 55(e) report as is this letter. The attachments provide.a descriptien of the deficiency, the status of corrective actien, and the ad=inistrative procedure which describes the re-review progra=.
Another report, either interim or final, vill be sent on or before March 9, 1979
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Quality Assurance Progrem, Menage =ent Correcti.m Action Attachmento:
A.
Report, MCAR-1, Repor: 25 3.
MCAR-25, Interi Report fl, Seis=1e and Enviree-aatal Co=ponent qualification, dat.ed January 5, 1979 Letter, P A Martine: to G S Keeley, ELC-6934, Cc=ponent C.
qualification Review, dated December 22, 1978 CC: Director, Office of Inspection & Enfo:rement 9g
\\7 Mr John G Davis, Acting Director, USNRC (15)
QD Att:
Director, Office of Management Infor=ation and Program Control, USNRC (1)
2 Hewe-17-79 BCC: JL3 acon, M-1085A WRBird, JSC-2163 RLCastleberry, Bechtel AA
'JLCorley, Midland LADreisbach, Bechtel-Midland GSKeeley, P14 h083 B'EarguG11o, JSC-220A PAMartinez, Bechtel AA DEuller, Midland JWevgen, Bechtel-Midland JAPastor, P14 Lo3 MJSchaeffer, Midland
,,,AGaibbs, H&3 File:
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Attach =ent A
.Hewe-17-79 QUALITY ASSURANCE PROGRAM MANAGEMENT CORRECTIVE ACTION REPORT -
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MCAR.1 REPORT NO.
DATE
- c4 c-1 's. 107 A 7220 O NO. Vi nt**
JOS NO.
i
- CESCRIPT!ON (Inctucing references):
The Midland Project initiated a co=p. nents qualification re-review program in August o
1978 of the seismic and environmental qualification test requirements, procedures and reports which have been proccssed by Bechtel. The purpose of th'is re-review progra=
document-is to provido additional assurance on a comprehensive basis that adequ to re-evaluate such infor=ation systematically to determine if applicable requirements have been satisfied, and to take appropriate corrective action where necessary.
(continued on page 2)
- RECOMMENDED ACTICN (Cetional)
Complete the re-review program.
1)
Resolve component qualifi:ations which are questionable regarding require =ents, 2) test methods and/or evaluation of test results.*l fan 7, inadequacies found during this re-review are and vill be discussed and resolved with the respective vendor Continue to report questionable qualifications.
3)
Investigate and identify the cause of questionable qualifications and take 4) appropriate corrective action to preclude recurrence.
CCNSTRUCTION CA MANAG MENT O
REFERRED TO h ENGINEERING b
a PROCUREMENT ISSUED BY rroi.c(hAEn,n.* i M% L. A. Dernisbn A T'N r Potentially Reoortable 11 l/70 f
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MCAR Report No. 25 Page 2 Description (continued)
The project has identified all Q-components requiring seismic' and env1runnental qualification testing with approximately 267 qualification test docu=ents re-quiring re-review.
Inadequacies identified dieing the course of this re-rennw and program will be identified and docu=ented in att.sch=ents to this report, follow-up action taken and documented. A report c,., the first compocant identi-fled with questionable qualifications is attached.
Attacheent_:
1 7220-J-204 Model E 10 Trans=1tter S a ry
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dunnAux UF FOXBORO MODEL E10 SERIES TRANSMITTER *-QUALIFICATION CONCERNS ATTACIFENT 1 PURCHASE ORDER 7220-J-204 Standard' Requirement Foxboro 2est Document Concerns IEEE 323-1971 Testing shall simulate Test Report No. T3-1068, During irradiation test of 8 units there Sec. 5.2.3.5 DBA environmental con-page 4 were 4 unexplained failures where the out-ditions.
put of the transmitter either went to 0 or went to 0 and returned to 50% value af ter a period of time.
In all cases the rad icvel at time of failure was below the Midland requirement.
Midland spray chemistry Test Report No. T3-1013 8 units were run through LOCA (MCA) environ-requirements consists of Section 6.0 mental testing. Actual testing period of a solution of sodium hy-24 hours, with a spray solution lacking droxide, sodium thio-sodium thiosulfate. Test chamber pressure sulfate and boric acid was 60 psig, whereas Midland LOCA pressure for a 30 day period.
was 70 psig.
IEEE 344-1971 Seismic qualification Test Report No. T3-1091 A crack in the force motor assembly of one Sec. 1.0 shall verify that per-Section 3.0 unit was found after the 10g test. Cause formance requirements of the crack and the effect of the crack are met.
on transmitter function under a LOCA en-vironment were not explained.
IEEE 344-1971 Testing at natural Test Report No. T3-1091 Natural frequencies in the 1-33 Hz range.
Sec. 3.2.2.4 frequencies.
(Action Test Report 10486 were identified during resonant survey.
page 4)
No unique testing at natural frequencies was performed.
Tech Spec Performance shall be de-None Documentation was not available to show that 7220-J-204 monstrated under con-one unit can withstand composite test Sec. 6.0 ditions simulating in-conditions for installed life.
stalled life.
A The supplier has been advised to place these Q-listed items on IIOLD.
Attech=ent 3 Howe-17-79 Bechtel Associates ProfessionalCorporation
SUBJECT:
MCAR 25 (issued 11/20/78)
Sei,smic and Environmental Component Qualification INTERIM REPORT j.,
DATE:
January 5, 1979 Consumers Power Co=pany Hidland Plant Units 1 & 2 Pechtel PROJECT:
Job 7220 O
Descrintion of Potential Discrepancies In response to MCAR 25, investigation by project engineering into the adequacy of data submitted by suppliers to fulfill the applicable requirements confir=ed that there are questions concerning the acceptabil-ity of suppliqrs' environmental and seis=ic equipment qualification test The. investigation has been expanded to include all documentation.
safety-related ite=s which require seismic and/or environmental testing or analysis.
Safety Imolications MCAR 25 was considered potentially reportable because a safety problem could exist if the equipment does not meet the specified seismic and environmental qualification requirements.
Corrective Actions Taken and Inprocess Engineering personnel responsible for reviewing supplier-sub=itted 1.
seismic and environmental qualification documents have attended special training sessions to ensure that adequata reviews to the An applicable requirements are perfor=ed in a timely manner.
i
.dministrative procedure entitled Components Qualification Rev ew has been developed and implemented to reflect the controls and actions being taken by the project.
Seismic and environmental qualification procedures and results 2.
submitted and accepted prior to November 16, 1978, have been additi-onally reviewed by project engineering to ensure that the equipment ll 5 us JAN IS 1979 QUAUiY ASSURANCE
Bechtel Associates ProfessionalCorporation MCAR 25 Interim Report 2 January 5, 1979 Page 2 meets the applicable qualification requirements. Because of problems experienced in obtaining complete packages, these previously accepted documents were additionally reviewed to a greater depth than the original submittal. At this point in time, 58 orders have been found to be indeterminate because they contain questionable areas.
[he following actions have been taken.
The qualification test status report (QTSR) was developed by project engineering to create a status list on all purchase orders requiring seismic or environmental qualification. The report is issued approximately conthly to reflect the current documentation status.
Qualification test review (QTR) formr are completed by engineering when questions arise with regard to previously accepted qualification Currently, engineering's initial review of -previously documents.
accepted documents is 98% complete. At present, coordination meetings are being held to resolve any questionable areas noted from the initial review as documented on the QTR form. When further action is required, engineering is taking action as delineated in the procedure. to the MCAR identified qual'fication problems associated 3.
with the Foxboro Model E10 series transmitter (P.O. 7220-J-204).
The Q-listed transmitters (Model E10) have been placed on hold, pending a decision to convert the Q-listed transmitters to non-Q Services.
Engineering is presently obtaining information on an alternative The final supply of Q-listco transmitters from another supplier.
decision of a source of Q-listed transmitters will.be made af ter the evaluation is completed.
Proj ect engineering is coordinating questionable areas with the respective suppliers for resolution or positive identification of any deficiencies. Deficiencies will be reported in subsequent Attached is a QTR form which is a typical example of the reports.
type of questions and actions completed (see attachment A).
Concur-rently, the fc11owing controls have been initiated:
Bechtel Associates Professional Corporation
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MCAR 25 Interim Report 2 January 5, 1979 Page 3 If the supplier has started shipment of Q-listed material, a.
the site has been notified so that appropriate action can be initiated to identify and control the item (s).
b.
If the supplier has not started shipment of Q-listed material, procurement has been requested to hold release for shipment until either resolution is obtained or a supplier deviation disposition request (SDDR) is initiated by the supplier.
Sub=itted by: /. C A "
Approved by:$ESI/ N-M(4/fr Concurrence by:
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SPECIFICATI0;i REQUIRCIC TS (Include Rev and/or Date)
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Bechtel Power Corporation 777 East Eisenhower Parkway Ann Arbor, Michigan
- . e acesueess: P.O. Box 1000. Ann Arbor. MacNgan 4S106 December 22, 1978 BLC-6934 Mr. G. S. Keeley Project Manager CONSUMERS POWER COMPANY 1945 West Parnall Road Jackson, Michigan 49201 Midland Units 1 and 2 Consurers Power Company Becht;el Job 7220 COMPONEh"IS OUALITICATION REVIET Files 1506/2801
Dear Mr. Keeley:
The attached Conponents Qualification Review, dated Dececher 22, 1978, Revision A, process description is n su==arization of the various procedures used by the Project to review components qualification testing documentation.
Further definition beyond those procedures has beetz added for some actions particularly with regard to timing.
Until the next Midland Project Procedures Manual revision is issued to include this, this docu=ent will be followed by the Project in the Components Qualification Testing Program. Please advise if you have any questions on the attach =cnt.
Very truly yours,
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P. A. Martine:
Project Manager PAM/pp cc: Mr. R. C. Bauman Mr. W. R. Bird lf h*
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Mr. J. L. Corley Mr. B. W. Marguglio Mr. D. B. Miller g{ggojg73
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WIhUTY ASSU,8lJiCE
COMPONENTS QUALIFICATION-REVILV 12/22/78 Rev. A PURPOSE The purpose of this docenent is to describe the prccess for 'the review of qualification require =ents and data for:
- 1) Consistency of the procurc=ent package with the FSAR (Reference EDPI 4.1.).
- 2) Consistency with qualification test requirements in, procurement documents.
~
3)
Consistency with procurement requirements in submitted test procedures.
- 4) Compliance to procurement package require =ents for test data submittal.
5)
The issuance of a Qualification Test Status Report to document the status of the above review.
Initial reviews of procurc=ent package qualification test procedures, and data are perfor=ed in accordance with MED/EDP 4.58.
DEFINITIONS l
2.1.
Qualification Test Status Reoort ?OTER) - Exhibit 1 A status report used to provide pertinent infor=ation conecrning the traceability of the qualification test data such as MR/ Specification nu=bers, original P.O. date, ites and manufacturer, applicable standards, specification reference, test procedure, test results, and review /re-review status.
2.1.1 QTSR (Status Inout)
Input Definition a)
Start ship:
a) '
, Start of shipment of Date (actual or forecast)
Q-listed material that requires qualification.
b)
Turnover:
b)
Scheduled date for turnover Date (actual or forecast) of Q-listed material frem Bechtel to Consumer Power Co.
c)
Re-review status:
Incomplete QE rereview not yet completed.
QE re review completed and cec =ents a
In-process
. awaiting resolution. Site or supplier notified (Date).
Complete QE re-review completed and comments if any, are satisfactorily resolved.
~
Re-review not required by QE Qualification data to be revicacd by cognisant discipline upon initial receipt.
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b
COMPONENTS QUALIFICATION REVIEW -- continued Page 2 2.2 Qualification Test Review (QTRi Form - Exhibit 2 A docunent review form containing pertinent infor=ation such as MR/Speci-fication, date reviewed, document revie0cd, specification requirements, co==ents and resolution from the re-review of qualification test data for input in to the status colu=n of the QTSR.
3.0 CENERAL 3.1 Review of New Ite=s (Not Released for Shie=ent)
Qualification procedures and data are reviewed and evaluated by the cognizant discipline in accordance with EDP 4.58.
The cognirant d'mipline advises the Licensing Engineer of the acceptability of the data and the Licensing Engineer't:akes the appropriate entry into the QTSR at the next conthly issue.
These items vill not be reviewed by Quality Engineering. Copiec of the QTR's which have cocpleted engineering review and indicate further action s
are to be forwarded to CPCo QA. Distribution of the QTSR vill be as follows:
Bechtel CPCo R. Bau=an
.E.' Ru=baugh J. liilandin W. Bird
~
J. Corley L. Dreisbach ~ -
P. Jacobsen W. Moring B. Marguglio R. Castleberry J. Pastor H. O'Mara M. Schaeffer K. Wiedner D. Sc=:ers L. Sokol J. Newgen W. Barclay Group Supervisors Chief Engineers 3.2 Review of Old Ite=s Re-review of all previously sub=itted and accepted qualification data as delineated in Revision 1 of the QTSR dated 10/27/78 is the pri=ary responci-bility of Quality Engineering with input as necessary frcm the ccanizant discipline. The basis of re-review by Quality Engineering is as stated in the purpose and to the latest procurc=ent package revision.
Quality Engineering establishes review priority h2 sed on' difficulty of tracking the ite=s (i.e. bulk items), date of turnover, and supplier delivery dates of Q-List items to mini =1:e any schedule delay. The QTSR is issued =onthly to reficct changes to infor=ation contained therein. Quality Engineering docu= cuts cen=ents generated during re-review on Exhibit 2 and coordinates the co==ents with cognizant engineering discipline for resolution. The cognizant discipline engineer docu=ents the resolution of the co==ents on Exhibit 2 and returns the QTR and any attachc=nts to Quality Engineering. The resolution shall describe or refer to docu=cnts which provide adequate rational for resolution or action taken. These aspects should, as appropriate, address:
...... ~ _
COMPCUT.U S QUALITICATION REVIEW-continued Page 3
- 1) What is to be done
- 2) To what criteria
- 3) Justification of the new criteria When all actions arc completed the Quality Engineer submits a copy of the completed QTR form and attachments. to Licensing for incorporation into the QTSR.
3.3 Corrective Actions When the Quality Engineering review of the documents discloses conditions which are questionable'regarding requirencnt; test methods and/or evaluation of test results the following action vill be. taken by the cognizant engineering discipline:
- 1) If shipment has been =ade, the field vill be notiff d of the QTR cc=nents by the Proj ect Engineer. The notifications will be sent to the field (Construction Superintendent, PFQCE and PQAE) so that appropriate NCR action can be initiated.
The cognizant group supervisor or designee will be responsible for keeping the QTSR updated on actions taken.
- 2) If ship =ent has not been made, the suppiler and PSQR vill be
~
notified that shipment is to be held until questions are resolved.
The cognizant discipline shall obtain resolution from the supplier prior to shipment or an SDDR will be initiated by the supplier requesting a date extension for data submittal so release for shipment can be granted.
In such cases, a copy of the approved SDDR (EDP 4.63) vill be sent to the field in addition to the norcal distribution.
UCR action cay be taken as described in Puragraph 1) above.
Uhen the Quality Engineering review is co=plete, the QTR and attachments will be forwarded to the Licensing Group for QTSR input.
NCRs issued will be closed by site 4C based on receipt of notification by Project Engineering that the Qualification Test Requirements have been satisfied as noted on the completed QTR from.
3.4.
NCR conditional Release When material has been shipped to the jobsite and found to be nonconforming because of unacceptabic qualification test data, an NCR must be initiated.
A conditional release may be implemented if the ites is critical to the installation schedule. NCR and conditional release vill be issued in accordance with SF/ PSP G-3.2.
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M3/
- itication l-Original Item and pgg Specification Reference Test Procedure Test Results_
Status _
.O. C.- t e ) _. Monu f acturer Applicable Standards _
- Startship:03267 A 18/C-18, Field crccted Scismic - ASME Code, Paragrapha 2.2.3, 2.3 Turnovers 1010737 6
tanks (Graver Section III, Sub-(Design Requirements);
25/75)
Tank) ocction lic Articic 4.0 (ASME Code,Section III, Subsection IIC)
Environmental nonc startship:0f.3079?
42/C-42, New and spent Scismic - ASME Code, Subparagraphs 3. 12, j Turnover 092279T 5.3.12, Appendix B,\\/,/
.1 fuel racksSection III (design requirements)
'S/78)
(Wachtcr) c
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Environmental Articic 6.2',\\ Appendik
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M4/C-44, Tucl pool Scismic
- Artfcle
.4 (C,-77 Rev 5 C-44-24, C-44-24, StartShip:01017$F i2 gates (W.J.
IEE Std 344-75 and\\IEEE Std 3r14-75) 7/27/78,
- 7/27/78, Tc nover 0922797 Level 1 Level 1 Re cv Co=plete Wooley)
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C-44-25, C-44-25, v
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7/27/70, 7/27/78, Environmental rticic 5.2 (rad doses) nonc Scismic - [NEd:\\ Code, Articic 7.4 (AstE Code, I. C-50D-12-4, C-50B-12-4, Star'eship:02107tA
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building locks Scction IIf4 Section III, and design 2/26/74, 2/26/7,4, Turnovers 1:01797*
Reactor 0503/C-50,
./5/69) and hatches
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N rcquirements)
Level 2 Level 2
. RerevaI. process
.v 13 (NC?.1033-(W.J. Woolcy).
C-50n-13-6, C-50D-13-6, Cond.T.c14) 1
- 6/14/74, 6/14/74, Lovcl 2 Lcvc1 2 e
C-50D-17-10, C-500-17-10, 5/31/78, 5/31/78, Level 4 Lcvc1 4 gg C-50B-10-6, C-50B-18-6, jy gh, S/31/78, 5/31/78, Level 4 Levcl 4 g
,I C-503-138-4, C-50D-138-4, 6/14/74, 6/14/74, Level 2 Level,2 Revision 1 9/15/78
.1 l*xlilli t t 1
.HR/ SPEC Rev DATE REVIl21 STARTED
. Vendpr Docu=cnts Reviewed Vender Print Number
,,.Titic or Descrintion l
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SPECITICATION REQUIEEIDiTS (Include Rev and/or Date)
REVII'.I BY.
Date RESOLUTION BY
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Co==ent: Reco'Ived
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g (Oh POWBr Stephen H. Howelf
{g Senior Yace Pressdent General Officos: 1945 West Parnell Road. Jackson. M!chigan 49201 * (5171 788 0453 C
January 26, 1979 4
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Mr J G Keppler, Regional Director M
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Office of Inspection and Enforcement
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US Nuclear Regulatory Co= mission 0:
Region III Ci 799 Roosevelt Road f..i-Glen Ellyn, IL 60137 MIDLAI;D NUCLEAR PLANT UNIT NO 1, DOCKER No 50-329 UNIT NO 2, DOCKET NO 50-330 AIR FILTERING UIf1TS In accordance with the requirements of 10 CFR So.55(e), this letter constitutes an interim report on the status of the discrepancy found in the heater virin6 of the air filtering units for the control room.
A description of the discrepancy, potential safety i=plications, investigation and planned corrective actions are documented in the attachments to this letter.-
Another report, either interim or finni, vill be sent on or before March 9,1979
Attachment:
1.
Quality Assurance Program, Manage =ent Corrective Action Report, MCAR-1, Report 27, dated December 28, 1978.
2.
MCAR-27, Interim Report fl, Air Filterin6 Units, dated January 12, 1979 CC: Director of Office of Inspection and Enforcement Att: Mr John G Davis, Acting Director, USNRC (15)
Director of Office of Mana6cment Information and Prog am Control, USNRC (1) 0\\
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Hove-20
- BCC: JLBacon, M-1085A WRBird, J3C-2163 RLCastleberry, Bechtel AA TCCooke, Midland JLCorley, Midland LADreisbach, Bechtel-Midland Mmibbs, II&.3 GSKeeley, P14-408B BWarguglio, JSC-220A PAMartinez, Bechtel AA DEMiller, Midland W,Moring, Bechtel AA JNewgen, Bechtel-Midland MJSchaeffer, Midland File:
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, MANAGEMENT CORRECTIVE ACTION REPORT l
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gJs.f Hove.,20-79 MCAR.1 REPORT NO 3
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- 12/28/78 7
O NO.4 *
. DATE NO.
Itine Saf ety /.ppliance (P.O. 722 H i-150) 3
- DESCRIPTION (Inc!uding reierences):
vendor of the air filtering units advised Ecchtel that they had found a discrepancy in their viring installed for the heaters cf Units OVM-7SA and B & O\\it 94A & B.
}'SA should have provided AUG sizes 10 & 8 (per liEC). Ecvever, AUC size 12 was installed.
Ecchtel initial revicu'did not deter =ine that there was any ir. pact on safety and additional infor=ction uns requested fro: MSA. Af ter review of that infor=stion together Oith project. criteria, project engineering.dctc =ined that the deficiency was reportabic and USA uns so advised.
The deficiency is repertable since the thyroid dose to control roc = operators could exceed the dose limits specified in
RECOMMENDED ACTION (Optional)
Take those steps necessdry to have the discrepant viring replaced. (Give schedule date 1.
2.
State uhat steps the supplier is taking, ter prevent recurrence.
3.
Assure that no other ce=penents supplied by l'SA arc involved.
Prepare an interin report and issue to the Project I!an:ger within fif teen days 4.
containing all available infor=ation together with a state =ent as to when, a complete report vill be issued.
EFERRED TO X ENGINEERING O CONSTRUCTION D OiMA GE.:ENT 5
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Date
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.oayTuA=Acun oivision enocuncuent ucn enoo rnocuns.ur.n? unn PleoCue84.uk t4T SuPf'L IC id ou AbiT Y uG n Ano otV $UPPLagf4 oW ALIT T uG88 VERIF;ED RY
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DESCRIPTION (continued)
Page 2 10CFR50 Appendix A General Design Criteria 19, as referenced in FSAR Section 9.4-1,1.1.
The dose limit could be e.xeceded based on reduced efficiency of the charcoal filters due to high relative hu=idity if the heaters failed to operate. The deficiency in the wire size was due to lack of infor=ation on the vendor's fabrication drawing.
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1 Bove-20-79 Bechtel Associates Professional Corporation Attachment to BLC-7018 Page 1 of 2
SUBJECT:
MCAR 27 (issued 12/28/78)
Air Filtering Units (MR 7220-M-150)
INTERDi REPORT:
1 DATE:
January 12, 1979 l
PROJECT:
Consumers Power Company Midland Plant Units 1 and 2 s
Bechtel Job 7220 Description of Discrepancy Mine Safety Appliances OdSA), vendor of the air filtering units, has advised us by their letter dated November 11, 1978, that they have found in the wiring installed from the control panel to the (See CP Co Note) discrepancy heaters of units OVM-78A and B and OVM-94A and B.
To comply.with the heaters, MSA should have provided minimum AtiG sizes 10 and 8 (per NEC).
MSA informed us in their TLX dated Instead, size 12 wire was installed.
that this discrepancy was the result of a lack of Decenber 19, 1978, information on MSA's internal installation drawings. This type of document is not normally subjected to Bechtel review.
Safety Implications 19, 1978, that if this discrepancy MSA stated in their TLX dated December had not been detected, the heater could fail :o function as a result of This failure could result in the charcoal overloading of the wires.
absorber being subjected to high relative humidity air and thereby This decrease in the absorption efficiency of the charcoal.
decrease charcoal absorption efficiency of units OVM-8A and B (control room makeup air filter units) could result in the control room operator thyroid dose level to be exceeded as specified in 10 CFR 50, Appendix A General Design Criteria 19, as referenced in FSAR Subsection 9.4.1.1.
Failure of the heaters in the fuel handling area exhaust air filter units OVM-94A and B is not considered reportable.
The stated control panel is a local control panel mounted CP Co Note:
directly on the housing of the air filtering unit.
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Bechtel Associates Professional Corporation MCAR 27 DTIERIM REPOKI 1 Attachment to BLC-7018 January 12, 1979 Page 2 of 2 Corrective Action MSA proposes to correct the misapplication of viring by replacing these wires with correct AWG sizes. The re rofit of these units vill be done by Bechtel under MSA's supervision. NCR 1733 has been applied to the equipment at the site, and this will be used to follow up and close this item.
MSA has been requested to confirm what steps have been taken to prevent recurrence and to ensure that no other components supplied by MSA are involved.
Submitted by:
/
'I s
Approved by: O rW Concurrence by:
/
AAns 1/8/5
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H POVier arurro conntm~ scs 5* ""~a C0mpDDy Senior Vice Perndens cen'er,el off:ces: 1945 West Parnell Road, Jackson, uschigen 4o201 + (51717384453 Januaw 31, 1979 Hove-37-79 Mr J G Keppler, Regional Director
' Office of Inspection and Enforce =ent M IejI I.--
Region III US Nuclear Regulatory C d ssion g
799 Roosevelt Road g"
d%7 Glen Ellyn, IL 60137
, 95
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' MIDLAND NUCLEAR PLAIG 9]ky UNIT NO 1, DoCKm No 50-329 g
UNIT NO 2, DOCKE:' NO 50-330
,p CLASS lE STATION BATTERY g
Reference:
- 1) Letter, S H Howell to J G Keppler; Mid na Nuclear Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; Class E Station Battery; Hove-235-78; dated November 17, 1978
- 2) Letter, S H Howell to J G Keppler; Midland Nuclear Plant;,
Unit No 1, Docket go 50-329; Unit No 2, Docket No 50-330; Class lE Station Battery, Hove-3-79; dated January 5,1979 The referenced letters were interi= 50 55(e) reports which described the nonconfor=ance and the proposed part corrective action. ~
This letter is the final report. The reportable design deficiency has been corrected, as proposed, by the release of an e ' roved design change which adds isolation bars to the battery racks. Ths
.n is nov in confor=ance to require =ents.
Specific process corrective action is unnecessary since the anc=aly was identified by the vendor's existing program and there is no reason to suspect deficiencies in their design process. The battery racks were originally tested by Wyle Laboratory for use in four and five foot seg=ents. Cc=puter analysis revealed the inadequacy of the design for ses=ents of greater length.
Aside from the above, the seis=ic qualification testing of Exide's prototype G cell and battery rack asse=bly is expected to be cc=pleted by Jcnuary,1960.
Installation of the battery racks to the new design can ecc:=ence in early March, 1979 h
- /
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Mr Jchn G Davis, Acting Director Director, Office of Management CC:
Office of Inspection &, Enforcement, USNRC (15)
Infor=ati.
and Prcgran Control, USNRC (1)
t 2
Hove-37-79 SCO: JLBacon, M-1085A RC3at=an, Pik hl2
'a~d31rd, JSC-2163 RIrastleberry, Bechtel AA JLCorley, Midland LADrelsbach, 3echtel-Midhnd GSKeeley, Pik 4063 3*nMarguglio, JSC-220A WEoring, Sechte'l AA J7:levgen, Bechtel4tidiand t,MIGibbs, H&3 File:
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E Mr J G Keppler, Regional Director j
d Office of Inspection and Enforeccent De Region III 4
US Nuclear Regulatory Co: mission y,j C 799 Roosevelt Rond Glen Ellyn, IL 60137 MIDLAND KUCLEAR PLANT IRilT NO 1, DOCKET No 50-329 IR{IT NO 2, DOCKET NO 50-330 REACTOR COCLANT PIIG MOTOR FLANGES
Reference:
S H Howell letters to J G Keppler; Midland Nuclear Ple.rt; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; Reactor Coolant Pu=p Motor Flanges -
1 Serial Howe-13-78; dated February 10, 1978 2
Serial Howe-37-78; dated March 30, lW8 3
Serial Howe-108-78; dated June 30,1W8 4
Serial Hove-153-78; dated August 30, 1978 The referenced letters were interim 50 55(e) reports. This is a final report.
The repair design has been completed, approved and released for implemen-tatien in the field. This resolves the design deficiency and the design is now in confor=nnce with requirements.
The field implementation of the design rhange vill be inspected as routinely required by the procedures.
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CC: Mr John G Davis, Acting Director Office of Inspection & Enforcement, USHRC (15)
[
\\7 Director, Office of Management 40 Information & Program control, USHRC (1)
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I BCC: JLBacen, M-1085A RCBau=an, Pik-h12 WEBird, JSC-216B RLCastleberry, Bechtel AA TCCooke, Midland JLCorley, Midland LADreisbach, Bechtel AA GSKeeley, P14 h08B CD4ahaney, B&W Lynchburg BWMarguglio, JSC-220A DH4111er, Midland JFNev6en, Bechtel-Midland A ibbs, IL&3 File:
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a[ C/ e POWOT CDP.SlimBIS C04W S" " * *"' a Senior Vice Pressdent General Officos: 1945 West PernaH Mr..J Jackson, Michigen 49201 e (517) 7384453 February 1, 1979 Hove-36-79 Mr J G Keppler, Regional Director Office of Inspection and Enforcement
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US Nuclear ReEulatory C
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Region III oegg 799 Roosevelt Road Olen Ellyn, IL 60137 g 973 l
HIDLAND NUCLEAR PLANT e fy we
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REACIOR BUILDI:D SPRAY PIPIEG SUPPORTS 4
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Reference:
S E Hovell letters to J G Keppler; Midland Nuclear Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; Reactor Building Spray Pipin6 Supporta -
- 1) Serial Hove-60-78, dated April 19, 1978 2
Serial Hove-92-78, dated June 13, 1978 3
Serial Hove-154-78, dated August 30, 1978 4
Serial Hove-186-78, dated October 13, 1978 5
Serial Hove-231-78, dated November 10, 1978 6
Serial Hove-265-78, dated December 15, 1978 The referenced letters and this letter are interim 50 55(e) reports. In reference 1 it was reported that the local pipe stresses at the point of the anchor attach =ent to the spray piping may exceed Code allowables. In reference 6, it was reported that the expected result of the evaluatica vould be that the reactor buildin6 spray anchors and system piping would be utilized as is in that the allevable stresses vould not be exceeded.
Recent correspondence from I'IT Grinnell revealed that six anchors, for each unit, have been shown to have stresses approximately 6% over Code allevables. This condition cxists at the veld joint between the anchor and the Bechtel supplied structural support extending frem the contain=ent dcce. The previously determined actisi time history vater ha=mer loading curves vill nov be applied to more closely provide the actual loadings that would be experienced by the anchors still in question. As reported in h
references 4 and 5, an analysis in accordance with ASME Section III, g
Appendix F is not being pursued.
O G
9
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4
Hove-36-79 Another report, either interin or final, vill be sent on or before March 23, Igrfg.
%}
Director of Office of Inspection & Enforcement CC:
Mr John G Davis, Acting Director, IRIRC (15)
Att:
Director of Office of Manage =ent Infor=ation&ProgramControl,USNRC(1)
BCC: JLBacon, M-1085A WRBird, JSC-2163 ELCastleberry, Bechtel AA TCCooke, Midland JLCorley, Midland LADreisbach, Bechtel-Midland GSKeeley, P14 kO83 EWMarguglio, JSC-220A PAMartinez, Bechtel AA DEM111er, Midland JFNevgen, Bechtel-Midland M ibbs, IL&B File: 0.4 9 17
Consumers (7Q Power 7-company u
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Hove-231-78
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Mr J G Keppler, Regional Director
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US Nuclear Regulatory C-ission D/-
Region III J
4 799 Roosevelt Road Glen Ellyn, IL 60137 MIDIAND NUCLEAR FIR;T
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~ UNIT No 1, Docr.r:' No 50-329 tmIT ro 2, DOCKET No 50-330 RFACTOR BUILDING SPFAY P H ING SUPPoRIS S E Howell letters to J G Keppler; Midland Nuclear Plant;
Reference:
Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; Reactor Building Spray Pipirs Supports -
(
- 1) Serial Howe-60-78, dated April 19, 1978
- 2) Serial Howe-92-78, dated June 13, 1978
- 3) Serial Howe-15k-78 dated August 30, 1978 h) Serial Hove-186-78, dated october 13, 1978 The referenced letters and this letter are interim reports.
provides the status of the analysis being conducted to resolve the question of the adequacy of the reactor building spray piping supports relative to the AS:E Section III Code allowable stress requirements.
Another report, either interim or final, vill be sent on or before Dece=ber 19, 1978.
k u
(1) MCAR-22, Interim Report f8, dsted Neverler 6,1978 Attach:nent:
CC: Director of office of Inspection & Enforec=ent h
7 Att: Mr John G Davio, Actims Director, 05:2 0.(15)
U Director of Office of Manage =ent O
g\\q0 Infomation & Program Control, USNRC (1)
A
2 nove-231-78 t.
BCC: JLBacon, M-1085A WEBird, JSC-216B RLCastleberry, Bechtel AA TCCocke, Midland JLCorley, Midland LADreisbach, Bechtel-Midland GSKeeley, P14 kO8A EkMarguglio, JSC-220A
~
BAMartinez, Bechtel AA DH4111er, Midland '
vgen, Bechtel-Midland Za=arin, IIAB File:
0.4 9 17 s
9
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Attach =ent 1 Hove-231-78 BECEIEL ASSOCIATES PROFESSIONAL CORPORATION
SUBJECT:
HCAR #
22 (Issued 3/21/78)
INTERIM REPORT #
8 DATE:
November 6, 1978 PROJECT: Consumers Power Conpany Midland Plant Units 1 & 2 Bechtel Job 7220 Status of Corrective Action and Investigation actions in progress for resolution of the subject MCAR The status c:
is updated as follows:
ITT Grinnell has completed their analyses of the 3, 4, and 6-inch 1.
anchors for ther=al, weight, and seismic response. Results indicate that allowable stresses are not exceeded.
ITI Grinnell analyses of anchor d2 sign for the water hammer loads 2.
submitted on Septe=ber 28, 1978, has not yet been completed.
Bechtel is supplying ITT Grinnell actual time-history data for water ha=mer analyses for their use. An analysis in,accordance with Appendix F of Section III of the ASME Boiler and Pressure Vessel Code does not appear to be required because the water hammer loads are not as large as previously anticipated.
Forecast Data for Investigation and Corrective Action The following specific forecast dates are provided:
The results of the analysis of thermal, weight, and seis=ic loads 1.
are now to be included in a final report from ITT Grinnell which Therefore, see vill include results of water hammer load analysis.
Item 2 below for final report completion date.
ITT Grinnell analysis of water hamer loads is scheduled for 2.
19, 1979. This analysis will factor in completion by January time-history data for water hamer condition provided by 3echtel.
These data are scheduisd to be provided to ITT Grinnell by November 13, 1978.
b
MCAR 22 INTERIM REPO R 8 November 6, 1978 b*.E'khenextinterimreportisscheduledforDecember8,1978.
A final report scheduled for February 16, 1979, remains valid as identified previously.
Submitted by:
4 Approved by Concurrence by:
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BECHTELASSOCIATESPROFESpONALCORPORATION 4*s O
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- w. w.- ii C0@any Senior Vice President General Offices: 1948 West Pernell Road, Jecheon. M8thHuan 40201 e (517) 7384463 October 13, 1978 Hove-186-78 g ' L*MJ /,g f
.gNg Mr J G Keppler, Regional Director c@.?"
P Office of Inspection and Enforcement
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US Nuclear Regulatory C - 4ssion
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799 Roosevelt Road Glen Ellyn, IL 60137 MT AC
- I MIDLAND NUCLEAR PLANT UNIT NO 1, DOCKET NO 50-329 UNIT NO 2, DOCKET NO 50-330 REACTOR BUILDING SPRAY PIPING SUPPORTS
Reference:
S H Hovel.L letters to J G Keppler; Midland Nuclear Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; k
Reactor Building Spray Piping Supports -
- 1) Serial Hove-60-78, dated April 19, 1978
- 2) Serial Hove-92-78, dated June 13, 1978
- 3) Serial Hove-154-78, dated August 30, 1978 s
The referenced letters and this letter are interim reports. Attachment 1 j
1 provides the status of the, analysig ht,ing conducted to respe the questica 4 of the status of the analysis being conducted to resolve the question of the adequacy,of the reactor building spray piping supports relative to the ASME Section III Code allavable stress requirements.
Another report. -tther interim or final, vill be sent on or before November 17, 14 'J.
Attach =ent:
(1) MCAR-22, Interim Report f7, dated October 6,1978
%{J CC: Director of Office of Inspection & Enforec=ent O
Att: Mr John G Davis, Acting Director, USHRC (15)
/g D
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Director of Office of Management p
[
Information & Pro 6 ram Control, t.ENRC (1)
2 Hove-186-78
(.
BCC: JIsacon, M-lO85A WRBird, JSC-2163 RLCastleberry, Bechtel AA TCCooke, Midland JLCorley, Midland IADreisbach, Bechtel-Midland GSKeeley, P14-h08A BHMarguglio, JSC-220A PAMartines, Bechtel AA DEMiller, Midland JFNevgen, Bechtel-Midland fuuamarin, II&B
. File:
0.4 9 17 s
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Attach =ent 1 Howe-186-78 Bechtel Associates Professional Corporation
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Attacheent to BLC-6658
SUBJECT:
MCAR #22 (Issued 3/21/78)
INTERIM REPORT #7,
DATE:
October 6, 1978 PkOJECT: Consu=ers Power Company Midland Plant Units 1 and 2 Bechtel Job 7220 Status of Corrective Action and Investigation
.The status of actions in progress for rcsolution of the subject McAR is updated as follows:
1.
' Anchor load sheets including thermal, weight, and seismic response for 3, 4, and 6-inch anchors were formally transmitted to ITT
(
Grinnell on September 28, 1978, 2.
Time-history data for water hammer analysis have been generat d.
The anchor load sheets mentioned above also contained loads incia ing water hammer.
ITT Grinnell is currently analyzing anchor design to determine design adequacy for the loads submitted on September 28, la 8.
An analysis in accordance with Appendix F of Section III of 4 ASME Boiler and Pressure Vessel Code may not be required to verify use of the anchors "as-is" because the water hammer'3'sds are not as large as had been previously anticipated. Curren: ITT Grinnell analysis, therefore, may not include such efforts.
Forecast Data for Investigation and Corrective Action The following specific forecast dates are provided:
1.
.The results of the IT": Crinnell analysis of the thermal, weight, and seismic loads submitted on September 28, 1978, is scheduled to be completed by October 20, 1978.
2.
ITT Grinnell preliminary analysis of anchor design with respect to water hammer loads is scheduled to be completed by October 20, 1978.
If an Appendix F analysis is required, such efforts vould start immediately thereaf ter, and be scheduled for completion by
(..
January 19, 1979.
Bechtel Associates Professional Corporation
~
Attachment to BLC-6658
~
HCAR 22 INTERIM REPORT 7 9
October 6, 1978 Page 2 3.
Since the next corrective action and investigative milestone is scheduled for October 20, 1978, and because no definitive information is expected until that time, the next interim report is scheduled for November 6,1978. A final report will follow thereaf ter if no additional analysis is required to justify use at the anchors "as-If additional analysis is required, the final report scheduled is".
for February 16, 1979, remains valid.
Submitted by:
Approved by:
- 7 N Concurrence by:
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MBP/ cap 10/2/2 O
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u Senaer Vice Presmient Generet Ottleen: 1945 West Pernett Road, Jackson, Mich6 gen 402e1 15171788-0453 December 15, 1978 Hove-265-78 g
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Office of Inspection and Enforcement
..pd ']
Mr J G Keppler, Regional Director
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US Nuclear Regulatory C-4 ssion c.'
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Region III' 799 Roosevelt Road hd
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f Glen Ellyn, IL 60137
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MIDLAND NUCIZAR PLANT UNIT NO 1, DOCKET NO 50-329 UNIT NO 2, DOCKET NO 50-330 REACICR BUILDDI, SPRAY PIPHIG SUPPORIS
Reference:
S H Howell letters to J G Keppler; Midland Nuclear Plant;
(~
Unit No 1, Dochet No 50-329; Unit No 2, Docket No 50-330; Reactor Building Spray Piping Supports.
- 1) Serial Hove-60-78, dated April 19, 1978 2
Serial Hove-92-78, dated June 13, 1978 3
Serial Howe-154-78 dated August 30, 1978 h
Serial Hove-186-78, dated October 13, 1978
- 5) Serial Hove-231-78, dated November 10, 1978 The referenced letters and this letter are interim reports. Attach =ent 1 provides the status of the analysis being conducted to resolve the question of the adequacy of the reactor building spray piping supports relative to the ASME Section III Code allowable stress requirements.
Another report, either interim or final, will be sent en or before February 1, 1979 t
Attachment:
(1)MCAR-22,InterimReport#9, dated Dr tber 11, 1978.
CC: Director of Office of Inspection & Enforcement Att: Mr John G Davis, Acting Director, USNRC (15) 4
\\
Director of Office of Management
!b Information & Program Control, USaBC (1)
\\
O
2 Hove-265-78 l
BCC: JL3 acon M-1085A VRBird, JSC-2163 RLCastleberry, Bechtel AA TCCocke, Midland JLCorley, Midland LADreisbach, Bechtel-Midland GSKeeley, Pik h08B BWMarguglio, JSC-220A PAMartinez, Bechtel AA DEdiller, M'dland Jefevgen, Bechtel-Midland
- ibbs, IIA.B File: 0.4 9 17 O
Attach =ent 1 Howe-265-78 Bechtel Associates ProfessionalCorporation Attachment to BLC-6900
{
SUBJECT:
MCAR #22 (Issued 3/21/78)
INIERIM REPORT #9 DATE:
December 11, 1978 PROJECT:
Consumers Power Company Midland Plant Units 1,& 2 Bechtel Job 7220 On the basis of recent results, it appears that our evaluation vill be that the reactor building spray anchors and system piping can be utilized as-is, without adverse effect upon the nuclear safety of the Midland Plant, Units 1 and 2.
Status of Corrective Action and Investigation Earlier, because of the conservatism in the input data, the stipulation was that if the water hammer loads were calculated to be high, the i
actual time-history water ha=mer loading curves for the piping could be utilized for stress analyses. However, ITI Grinnell has verbally reported that analysis of the piping system anchors has shown that allowable stresses are not exceeded.
Bechtel has completed analysis of the anchor-to-pipe veld for the maximum water hat:=er forces using the stress intensification factor for an unreinforced branch and has found that the stresses in the piping system are below the faulted allowable stresses, in accordance with ASME Sectiot III, Class 2.
Forecast Dats for Investigation and Corrective Action A final report is scheduled for completion by January 19, 1979.
Submitted by:
Approved byr
)Sc Concurrence by:
MBP/js 12/2/4 C
M censumers RF.L.CF.D CCRPISPONL"JCS
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C0mpany u
Stener Vect Prtsmitaf T
Generst Offices: 1945 West PerneH Road, Jackson, Micrt6gan 49201 e (517) 7884453 November 7, 1978 Hove-230-78 2..
k
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p'Ci ll-Mr J G Keppler, Regional Director r'"'i,g/
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2 Office of Inspection and Enforce =ent US Nuclear Regulatory Cc~._.ission s-c.;fpgyk Region III 799 Roosevelt Road b
,g Glen Ellyn, IL 60137
' cat m-MIDLAIID NUCLEAR PLANT -
UNIT NO 1, DOCKET NO 50-329 UNIT NO 2, DOCKET NO 50-330 SEITLDETI CF DIESEL GE iERATOR KUNDATIONS ARD BUILDDG
Reference:
Letter, S H Howell to J G Keppler; Midland Nuclear Plat.':
Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330;
(
Settleme=t of Diesel Generator Foundaticas and Building; Serial Hove-183-78; dated Septe=ber 29, 1978 This letter, as was the referenced letter, is an interim 50 55(e) report en the settlement of the diesel generator foundations and building.
The enclosure provides the status of the acticns being taken to resolve the problem. It is tentatively planned to hold a reviev =eeting during the last two vee'n.n November. The Nuclear Regulatory Cc==issien vill be invited to...,1cipate when the time and place have been finalized.
Another report, either interim or final, vill be sent en or before Dece=ber 29, 1978.
'~
g
Enclosure:
MCAR !24, Settlement of the Diesel Generator Foundations and Building, Interim Report y2, dated November 3,1978 CC: Director, Office of Inspection & Enforcement Att: Mr John G Davis, Acting Director, USHRC (15)
Director, Office of Management
{
Infor=ation and Program Centrol, USNRC (1) h g
D Y
g Howe-230-78 BCC: JLBacon, M-1085A WEBird, "?-2163 RLCastL erry, Bechtel AA TCCoche, Midland JLCorley, Midland LADreisbach, Bechtel-Midland DDiorn, Midland CAHunt, P14-2093 GSKeeley, Pik-kCSB
' ~-
MJKoschik, M-890A
- BWMarguG11o, JSC-220A PAMartinez, Bechtel AA DBMiller, Midland JFNevgen, Bechtel-Midland Me=arin, IIAB File:
0.h.9 20 g
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Hove-230 78
. Becniel Associates Professional Corporation I
SUBJECT:
HCAR #24 (issued 9/7/78)
Settlement of the diesel generator foundations and building INT 5RLH REPORT # 2 DATE:
November 3, 1978 PROJECT:
Consumers Power Company Midland Plant Units 1 & 2' Bechtel Job 7220 Introduction This report is submitted to advise of the interim status of the project's actions relating to the settlement of the diesel generator foundations and building as described in MCAR #24 and NCR 1482.
Genersl Background
(
,.The fill material in this area was placed between 1975 and 1977.
Construc-The tion was started on the diesel generator building in mid-1977.
diesel generator building settlements were noticed to exceed anticipated values in July 1978. One concrete pour was made to finish the structure A
to a common elevation of 662'-0" and to allow removal of formwork.
soil boring progrrm was started on August 25, 1978.* Based on the preliminary soil boring data evaluation, MCAR #24 was issued.
The actions requested by MCAR #24 are being performed as follows:
The Foundation Data Survey Program, Specification 7220-C-76, has 1) been expanded by increasing the number of data locations and the frequency of measurements.
The cause of the settlement and the corrective actions required to 2) preclude the recurrence of this condition will be addressed after the testing and monitoring programs have been evaluated.
The options available to resolve the existing settlement conditions 3) will be discussed in subsequent reports following the complete evaluation of soil conditions.
b
@ 42
~
Bechtel Associates Professional Corporation MCAR #24 Page 2 Description of Deficiency 31, 1978, The general foundation and building settlements as of October
~
and October 27, 1978, respectively, are shown in Figure 1 (attached).
ceivities in Progress The activities are:
The Foundation Data Survey Program.as discussed in the previous 1) report is being continued.
The soil boring prograa has been completed. There were 29 soil 2) borings and 13 dutch cone penetrations made in the area of the diesel ge~nerator building to provide better definition of the fill conditions under the building and to obtain soil samples for laboratory tests.
Laboratory tests for the soil sa=ples obtained from the borings are 3) being perfor=ed by Goldberg-Zonino-Dunniclif f and Associates, Inc.
(
The tests are:
a.
Shear strength tests b.
Consolidation tests Soil classification c.
d.
Mineralogy tests All of the above tests are approximately100% complete except the As the test results mineralogy tests, which have not been started.
are available to Bechtel, they are forwarded to the consultants who The tests are estimated to be completed by have baen retained.
November 15, 1978.
4)
Independent Soils Consultants A team of consultants who specialize in soils has been retained to Provide their independent evaluation and recommendations concerning the soil conditions existing under the diesel generator building.
The consultants, Dr. R.B. Peck, previously with the University of 1111ncis, and Dr. A.J. Hendron, presently with the University of Illinois, have visited the site and. reviewed the existing conditions.
Based on Dr. Peck's consultation, the following resulted:
C.:
Bechtel Associates Professional Corporation MCAR #24 Page 3 t
t Dr. R.D. Woods of the University of liichigan will provide an a.
interpretation of the dutch cone penetration tests.
Mr. J. Dunni 1.if f (Goldberg-Zoino-Dunniclif f & Associates,
' - b.
Inc.), who specializes in soils instrumentation, reviewed the building and site to assist in developing a soil monitoring program.
5)
Ifelated Activities s
Based on preliminary evaluation of the soil borings, soil test the consultants com=ents, and the construction schedule,
- results, several activities common to any corrective actions may be started before the next interim ceport.
Placement of the soil and underground utility instru=entation a.
vill be done.
Separate the electrical duct banks penetrating or otherwise b.
restricting the equalized settlement of the building from the i
Grout any footing to allow unrestricted settlements to occur.
Any remaining separations between the building footings.
separations between bu11 ding footing and supporting fill vill
~
be grouted.
Raise the cooling pond vater level from elevation 622'-0" to its design height of elevation 627'-0," which vill bring the c.
water table in the building area to its operation level.
Visual monitoring and a survey of the diesel generator building d.
and appropiate utilities under the building vill be performed before, during, and after Item b above.
6)
Other Areas _
Soil Soils borings have been made in the other plant fill areas.
sar.ples from the borings have been sent to the laboratory for The same group of tests vill be performed for these testing.
samples as described in item 3 above.
(.
Bechtel Associates ProfessionalCorporation
, m,,,
Page 4
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Potential Safety Implications This item is considered reportable under 10 CFR 50.55 e, 1, iii because of the magnitude of the investigative tests and analysis of test results to support the corrective actions.
4 Submitted by:
c /d
%DE Approved by:-
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3 Concurrence by:
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g, Senior Vice Preskient General offices: 1945 West Pernall Road, Jackson. MicNgan 49201 * (517) 788-0453 November 28, 1978 Hove-252-78
, /. O, Mr J G Keppler, Regional Director
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Office of Inspection and Enforcement Re61cn III y'\\
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US Nuclear Regulatory Co==ission f
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(/ td 799 Roosevelt Road "a
Glen Ellyn, IL 60137 e
MIDLAND NUCLEAR PLANT -
UNIT NO 1, DOCKET NO 50-329 UNIT NO 2, DOCKET NO 50-330 CCMPCNENT QUALIFICATION TEST DOCU M ATION RE-REVIEW In accordance with the requirements of 10 CFR 50 55(e), this letter constitutes an interi= report on the status of the potentially reportable condition concerning
(,
the qualification test documentation review.
We initiated a limited effort in early 1978 to review selected co=ponent seismic and environmental qualification docu=entation. This resulted in a question as to the adequacy of existing docu=entation to demonstrate co=ponent qualification.
In August, a co=ponent qualification re-review progra= vas initiated for the seis=ic and environ = ental qualification test requirs=ents,- procedures and reports for the procure =ents processed by Bechtel. Additicnsi questions have been raised as to the adequacy of the qualification records. The potential that a co=penent
=ay not be capable of being qualified exists; however, to date, no co=ponent has been put in this category.
The purpose of the re-review is to provide assurance, on a comprehensive basis, that adequate docu=entation has been submitted by the vendors regarding their qualification test progre=s, to syste'::stic. ally determine if applicable require-
=ents have been satisfied, and to take appropriate corrective action when The review vill provide assurance that the FSAR require =ents have necessary.
been adequately reflected in the procurement packages and that there is consis-tency between the W.AR and procure =ent package require =ents, qualification test A Qualification Test Status Report is being generated procedures and test dcta.
by Bechtel to document the status of the re-review and its results on an individual material requisition basis for all Q-co:nponents requiring seismic and environ = ental qualification testin6-E$e e
2 Hove-252-78 I
Consu=ers Pover has taken steps to i=plement a similar effort with the NSSS Supplier.
Another report vill be sent en or before January 17, 1979
[yMk CC: Director, Office of Inspecticn & Enforcement Att: Mr Jchn G Davis, Acting Director, US'mC (15)
Director, Office of Management Infomstion and Program Control, USIEC (1)
BCC: J13acen, M-1085A WEDird, JSC-216B RLCastleberry, Eechtel AA JLCorley, Midland I
LADreisbach, Bechtel-Midland GSKeeley, P14 LO83 BWMarguglio, JSC-22CA PAMartinez, Bechtel AA D34111er, Midland JFHevgen, Bechtel-Midland JAPastor, P1h ho3 P Schaeffer, Midland MEibbs, IIL3 File:
0.h.9 22 (i
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$asphen H.Howell k,.
pnmneitig g,,jer yice tvesident u
uulilpulIJ General Cffices: 1945 West Pernell Road. Jackson. MicMosa 49201 * (517) 788 4453 November 17, 1978 Ecue-235-78
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Mr J G Keppler, Regional Director l't Office of Inspection and Enforcement
.p
.C
Region III 6
c/yJ41T D/
US Nuclear Regulatory Co==ission
./
f 799 Roosevelt Road
%, jc.a. s t _.
Glen Ellyn, IL 60137
~
MIDLAND NUCLEAR PLANT UNIT NO 1, DOCKET NO 50-329 UNIT E0 P, DOCIGT No 50-330 CLASS 1E STATION EA1 M Exide Indust:ial Eattery Divisien made a report to the NRC in accordance with
(,
the requirements of Title 10 CFR, Part 21 concerning the need for an isolation bar to isolate, in two cell increments, the buildup of horizontal me=entum The Attach =ent provides a copy of the Part 21 report.
durin6 a seismic event.
This letter is an interim 50 55(e) report for the condition as it applies to Four Class lE 125 volt station batteries (Material Requisition and Midland.
Specification No 7220-E-12(Q); equi; rent numbers 1D01,1D02, 2 Dol, and 2DO2) are involved. The present equipment status is as follows:
The battery racks for batteries 1D02 and 2D02 are in crates at the a.
installation location at elevation 614 in the aurif f ary building.
The battery racks for batteries 1D01 and 2D01 are assembled but not b.
installed at the installation location at elevation 614 in the auxiliary building.
Thebatterycells(60perset)havebeenreceivedandvarehoused.
c.
Exide has been asked to provide additional infon::ation describing the condition, the failure mode of the battery racks if the condition had not been detected, an analysis which defines why the condition was reportable, and any subsequent corrective actions taken or planned.
Corrective action has been initiated by Ezide to add an isolation bar to each The isointion bar is currently being designed by Exide and is expected rack.
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to be available for retrofit by December 10, 1978.
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2
- Howe-235-78
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Another report, either interim or final, vill be supplie'd-by Janusry 15, 1979 D
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Mailgram, Exide Industrial Battery Division to USNRC Office of
~
Inspection and Enforcement, dated 10/11/78
Attachment:
Director of Office of Inspection & EnforcementMr John G Davis CC:
Att:
Director, Office of Mans 6e=ent Information and Program Centrol, US1!RC (1)
JLBacon, M-1085A ECC:
RCBauman, Plk-412
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VRBird, JSC-2163 RLCastleberry, Bechtel AA JLCorley, Midland LADreisbach, Midland GSKeeley, P14 h08B BWMarauglio, JSC-220A WMoring, Bechtel AA JFNevgen, Bechtel4tidland IUZamarin, IIAB
.Affnibbs,IIAR File: 0.4 9 21 t
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3 J gif_JM nAI(GR' SER.C E (;ENT'~3 Dr?.,gdrg.c.!M
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HJDDLETOLh, VA, 22645 NfR Attach =ent to
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Hae-235-78 I-013141 A284002 10/11/78 TkX ESB OATA B PGHA SPESSARD - REGION III 01 MORSHAM, PA OCTOBER 11 HAYNES - RECION V
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USNRC 0FFICE OF I ASPFCTION AND ENFORCEMENT C.*
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631 P ARK AVENUE CI h'G OF PRUSSI A, PA 16400
'fD E-IIL.
N OF Esu INCORPORATED BELIEvi.S EXIDE INDuSTRI AL 6ATTERY DIVISIONwITH PkODUCT IT HAS SUPPLIED R
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THERE IS A POTENTIAL PROBLEM TU SOUTHERN CALIFORNIA EDISDN FOR TnEIR S.A.N..ONt0FR.E UHI.TS 2 AND 3 1 AND 4,
wbICH MAY DETERPINED BY E21DE7 ~,/
AND CONSUMERS POWERTO. FOR THEIR HIOLAND UNITS BE,iEP04T AaLE UNDER 10CFR 21, IT HAS BEEN St.ISMIC AN ALYSIS.CSSULTANT THAT AN ADDITIOtt.L ISOLATION BAR IS REGU!dE010 6E ADDED TO THE CLASS 1E BATTkRY RACMS 10 ISOLATE, IN Two-CELL INCREHE. TS, TPE BUILD UP 01-H0HI20NT/,L HOMENTUM IN A N
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{~ 7IN3 0F CELLS ON A BATTEPY.. RACK'. STEP DURING A SEISHIC EVEN blS ADQITIONAL PIEC'E IS t<0T REGUIRED FOR THE STHUCTudAL INTEGRITY SUY FU,9 THE ISOL ATId4 DP MOMENTUM AND WILL HOT AFFECT THE STRUCTURAL
~
INTE GilIT Y OF T HE CL[A,,S S 1E BATTERY RACKS, EXIDE Id CURRENTLY WORkJNG UN THE DESIGN OF SUCH AN ACCESSORY FO THE ADDITION 10 TME PR000CT SUPPLIED FOR THE AFOREMENTIDAED. CON-STRUCTION PbASE NUCLEAR GENERATING STATIONS. EXIDE SHOULD HAVE TnI5 ITEM AVAILABLE F0d HETRO-FIT wITHIN 60 DAYS.
THE NEED FOR SUCH ITEM WAS DETERMINLD 10/10/78.
THIS N011FIC ATION IS APPLICABLE TO THE FOLLOWING CLASS 1E B ATTERY RACAS FOR THE SodTHERN CALIFGHNIA EDISON SAN UNUFRE NUCLEAR CE TING STATIONr UNIT 3 UNIT d 26009, 2S010, 2o007, 28008 30009, 38010, 33007, 30008 CONSUMERS POWER FIDLAND NUCLEAR GENERATING STATIONS 1 & 2 UNIT 2 UNIT 1 2001, 2002 1001, 1002 THIS POTENTI AL PROBLEM HAS uEEN REALIZED BY EXIDE kHO IS ACTIhG T DECTUY THE PRooLEH AT.THIS WIHE.
THE PERSON TO C07. TACT FOR ADDITION-AL INFORMATION HELATIVE TO THIS WIRE IS MR.
C. K. MC MANUS AT ErIDE, A%AILABLE AT TELEPHuNE (21S) 674-9500.
THIS NOTIFIC ATION IS oEING HADE IN ACCCRDANCE WITH THE REQU PART 21, OF TITLE 10 0F THE CODE OF FEDERAL HEGULATIONS, FOR EXIDE INDUSTRIAL BATTERY DIVISION
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CHA4LES 6 MC MANUS g,
,/[.* W 852 EST 59 HonCorte ac"
TED COnBESP03pF NCS
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censumers r,
<tr M power m\\,M Stephen H. Howell y
sraser Vice Prrsidras
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I tb J Generet Offices: 1945 West Parneff Road, Jackson. Micn# gen 4 201 * (517) 788 0453 I ',, %.g,d Dece:her 21, 1978
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Hove ' 67-78 s
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%g \\D Mr J G Keppler, Regional Director 99 j d (5?
ml Office of Inspection and Enforce =ent N
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IL Nuclear Regulatory Cdssion C[# 9 C /
Region III' 799 Roosevelt Road
"# / cy i H Glen Ellyn, IL 60137 MIDIAND NUCLEAR PLALT -
U:iIT NO 1, DCCKET NO 50-329 UNIT NO 2, DOCKET NO 50-330 SEIT1EELT OF DIESEL GENERATOR FOUNDATICNS AND EUILDI;G S H Howell Letters to J G Keppler; Midland Nuclear Plant;
Reference:
Unit No 1, Dccket No 50-329; Unit No 2, Docket No 50-330; Settlement of Diesel Generator Foundations and Building;
(
a) Seria Howe-183-78; dated September 29, 1978 b) Serial Howe-230-78; dated November 7,19T8 This letter, as vere the referenced letters, is an interim 50 55(e) report The use on the settlement of the diesel generator foundations and building.
of a preload to densify the existing fill =sterial in place has been selected as the majer corrective action plan. Activities necessary to accomplish this plan vere discussed with NRC personnel during their visit to the Midland jobsite on December 3 and 4,1978.
Bechtel Associates Professional Corporation's Interim Report f3 to NCAR 24 Their vill detaiJ. the acec=plished and planned corrective action tasks.
Report 93 vill be trans=itted to you the first veck in January.
Q
$_5 ' 02 a"( ~
~1 Director, Office of Inspection and Enforcement CC:
Mr John G Davis, Acting Director, USNRC (15)
Att:
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Director, Cffice of Management Infor::ation and Pregram Control, USNRC (1) g Q
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g Howe-267-78 i'
BCC: JL3 acon, M-1085A Faird, JSC-216B RLCastleberry, 3echtel AA TCCooke, Midland JLCorley, Midland LADreisbach, Bechtel-Midland DDiorn, Midland CAHunt, P1h-2093 GSKeeley, P1h hCS3 MJKoschik, M-890A 3Giarguglio, JSC-220A PAMartinez, Bechtel AA DEiiller, Midland JH:cagen, rechte1411dland p fm ibbs, II&B File:
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