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- Dean L Quemme Sise Manager
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Midland Proper C.
Mdand Project PO Boa 1963. Mdand. MI 48640. ($17) 6318650 February 23, 1984 t
Mr J J Harrison Chief, Midland Section Region III Nuclear Regulatory Comission 799 Roosevelt Road
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Glen Ellyn, IL 60137 MIDLAND ENERGY CENTER CWO 7020 NCR'S FROM TliE FCR/FCN REVIEW FOR SWO'S File: 0505.2 UFI: 03*05*06 Serial: CSC-7367 0460.3 73*10*03 0250 99*04 Per your request, attached is a sumary of the NCR's identified as a result of the recent FCR/FCN review.
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cc JEKarr, CIO RAWells, MPQAD BHPeck, MEC NIReichel, MEC RJCook, NRC Site l
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To Distribution (See below)
Faos DATaggart, Midland gggg Darc February 21, 1984 h0E$I company Suescer MIDLAND ENERGY CENTER PROJECT - IDENTIFIED t
NCR's FROM THE FCR/FCN REVIEW FOR SWO's Comacsponotwoc DAh21-84.")
cc KJGill, Midland PDMilano, Midland SMPalmer, Midland Attached for. your_information please find n* sn=ra=> y nf' tha Mt'R'= uhi r h ue e_
identified as a result of the recent FCR/FCN review. Should you have any specific questions regarding these items please feel free to contact Pat Milano.
t sw DISTRIBUTION:
RAWells, Midland JLWood, Midland DLQuamme, Midland GEParker, Midland HPLeonard, Midland RCSember, Midland JKMsisenheimer, Midland NReichal, Midisnd WRBird, P-14-418A DPerry, Midland i
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'"O NCRs From FCR/FCN Review For SW0s NCR#
Discipline Nonconformance 1.
C-00913 Mechanical Penetrations drilled and rebar cut in isolation valve pit wall and Turbine Building wall w/o prior Project appro-
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val, as required by Spec C-231.
1 2.
C-00024 I&C Contrary to nots on Drawing J-3150(Q)
Instrument Support, RLT-3976BB2, lo-cated 4" east ofirequired location.
Tolerance was only 22"..
3 C-00933 Electrical Wire number change to blue conductor' of cable OBB6601B proposed by FCN E-5298.
FCN was not clearly dis-approved by Project Engineering and thus, the disapproved change was 1
incorporated into Drawing E-900.
E-900 calls for wir.e tag now to be "6".
Drawing E-37 identifies wire number as "5G1".
4.
C-00934 Electrical FCN E-5744 re7ised sizes of terminal (Replaced by NCR C-01012 boxes 2J1109 and 2J1110 from 30"x20"x8" to 30"x30"x8".
However, FCN not attached to Drawing E-46 at time of installation and thus, wrong box size could be installed. NCR C-01012 written on the same problem which superceded this NCR.
5.
C-00935 Electrical Drawing E-791 provides dimensions 1 plans for raceway supports. E-748 provides dimension sections for raceway supports. FCR E-639 was not incorporated into Drawings E-748(Q),
4 Sheets 1 & 2.
Dimensions on E-741(Q) do not agree with E-748(Q) sht 1.
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Proposed connection details on FCR-E-639 for E748, Sh. 2, were disapproved 4
Status of supports indeterminate.
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6 P nntit-77 civil FCR C-3618 written against detail 7.'"
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(HVAC) 902 at one specific location. The FCR was dispositioned to be a revision for i
all locations. However, the FCR was not attached to Drawing C-902.
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a NCR Discipline Nonconformance i
7.
H-00134-ZZ Civil Same as H-00133-ZZ but for dirrerent (HVAC) hanger.
8.
H-00135-ZZ Civil Same as H-00133-ZZ but for dirrerent (HVAC) hanger.
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9.
H-00175-ZZ Civil FCN C924 never incorporated into (HVAC)
Drawing C-953(Q) as so stated in dis-position.
10.
H-00176-ZZ Civil FCN C-878 never incorporated into (HVAC)
Drawing C-935(Q) as'so stated in disposition.
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UNITED STATES
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FEB 0 2 1S84 b.
Docket Nos.:
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and 50-330 OM, OL MEMORANDUM FOR: Atomic Safety and Licensing Board for the Midland Plant, Units 1 and 2 (C. Bechhoefer, J. Harbour, F. Cowan)
FROM:
Thomas M. Novak, Assistant Director for Licensing Division of Licensing
SUBJECT:
MIOLAND ISSUES, BOARD NOTIFICATION 84-019 (1) Lif ting of Soils Remedial Stop Work Order (2) Potential 50.55(e) Involving Differential Settlement of Diesel Pedestals and Diesel Building (3) Crack Monitoring This Notification is provided in accordance with NRC procedures regarding Board Notifications and is deemed to provide new information material and relevant to issues in the Midland OM-OL proceeding. This information concerns the licensee's January 19, 1984, lif ting of the sofis remedial stop work order; the 'icensee's December.14,1983, reporting of a potential 50.55(e) condition involving differential settlement between the diesel pedestals and the diesel building itself; and a follow-up of the crack monitoring issue. Details of these items are provided in Enclosure 1.
The staf f will provide follow-up to the Board on these issues when available.
Tromas M. Novak, Assistant Director for Licensing Division of Licensing
Enclosure:
As stated 1
i SECY (2)
OPE
'3101100018-CGC EDO i
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4 DISTRIBUTION LIST FOR BOARD NOTIFICATION Midland Units 182, Occket Nos. 50-329/330 ACRS Members Charles Bechhoefer, Esq.
Dr. Robert C. Axt:tann p
Ms. Lynne Bernabei Mr. Myer Bender James E. Brunner, Esq.
Dr. Max W. Carbon Mr. Jesse C. Ebersole Dr. John H. Buck Mr. Ronald C. Callen Mr. Harold Etherington Gerald Charnoff, Esq.
Dr. William Xerr Dr. Harold W. Lewis Myron M. Cherry, P.C.
Dr. Frederick P. Cowan Dr. J. Carson Mar's Barton Z. Ccwan, Esq.
Mr. William M. Mathis T. J. Creswell Dr. Dade W. Moeller Dr. Milton S. Plesset Gary J. Edles, Esq.
Steve J. Galder, P.E.
Mr. Jeremiah J. Ray Dr. David Okrent Dr. Jerry Harbour Samuel A. Haubold, Esq.
Dr. Paul C. Shee:an Mr. Wayne Hearn Or,Chester P. Siess m
Dr. W. Reed Johnson Mr. David A. Ward Mr. James R. Kates Frank J. Kelley, Esq.
Christine N. Kool, Esq.
Dr. J. Venn Leeds, Jr.
Mr. Mcward A. Levin Steven Lewis, Esq.
J. G. Xeppler Dr. Emeth A. Luebke Geotechnical Engineers, Inc Mr. Wendell H. Marshall
- 8. P. Garde Marshall E. Miller, Esq.
P. C. Huang Michael I. Miller, Esq.
L. J. Auge Thomas S. Moore, Esq.
H. Gehring William C. Potter, Jr.
I. Charak Mr. Paul Rau C. Herrick Harold F. Reis. Esq.
P. Bassett Ms. Mary Sinclair Ms. Barbara Stamiris' Frederick C. Willir ns, Esq.
i Atomic Safety and Licensing j
Board Panel j
Atomic Safety and Licensing 4
1 Appeal Panel Occketing and Service Section Document Management Branch i
J. W. Cook S. H. Freeman J. Morrisen i
R. 8. Borstm
- 0. Van Farrc.a l
U.S. NUCl!1r Sigui1Mry C;T f 5 3 i D1
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?. A. Perry 1
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NUCLEAR REGULATORY COMMISSION
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'h.....I January 25, 1984 V
MIMORANDUM FOR:
D. G. Eisenhut, Director, Division of Licensing, FROM:
R. F. Warnick, Director, Office of Special Cases
SUBJECT:
RECOMMINDATION FOR NOTIFICATION OF LICENSING 30ARD In accordance with present NRC peccedures regarding Board Notifications, the following information is being provided as constituting new information relevant and =aterial to the Midland CM/0L proceedings. This infor=ation deals vi:h the licensee's January 19, 1984 lifting of the soils re=edial stop work order; :he licensee's Decenber 14, 1983 reporting of a potential 50.55(e) condition involving differential settlement between-the diesel pedestals and the diesel building itself; and a follovup of the crack monitoring issue.
A.
The pertinent facts that relate to the lifting of the soils stop work are as follows:
1.
On October 22, 1983, the licensee issued stop work number FSV-38 on all remedial soils work because of problems with referencing of drawings and specifications in the Bechtel FCR/FCN process. This created an indeterminate condition with respect to work that has been or could be performed.
2.
This stop work was one of nine stop work orders which halted all safety-related activities at the Midland site. They were issued as the result of a quality assurance audit of the design document control system (Board Notification dated October 25, 1983).
3.
The licensee reviewed potential impact of hardware and plant equip-ent to ensure it was built to the proper drawings. No significant construction problems vere found in the review and the drsving change and review process has been changed to improve the processing of the engineering documents.
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4.
Project correctiva actions were revieved by Stone & Webster, the independent assess:ent organization, and were found to be acceptable.
3.
Stop vork vas lifted in the soils tras on January 19, 1984.
6.
Mer; intine 2nd Spencer, White & Prin:is vill begin rehire of cr:scr2c: ion verkats as work rean=23.
7.
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a :n :his issue as a na::er of l
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The pertinent facts that relate to the 50.f5(e) are as follows:
9 1.
On October 14, 1983, RIII received c allegation by the way of a C/J affidavit that Sechtel had not tcken inte account the effect that the i
anticipated differential settlecent between the diesel pedestals and 1
the diesel building itself would have en associated connecting equip =ent.
I 2.
On November 3, 1983, RIII requested NRR assistance in pursuing this allegation.
3.
On December 2, 1983, CPCo was notified of the allegation for the purposes of obtaining design information for NRR's review of the allegation.
4.
On December 14, 1983, CPCo notified RITT nf-a potential 50.55(e) on this matter.
5.
On January 13, 1984, the licensee issued the official 50.55(e) report to the NRC.
6.
The 50.55(e) report states that Bechtel discovered this deficiency during a system review of the diesel generator on November 21, 1983.
7.
A meeting is tentatively scheduled for February,1984, to pursue this issue.
8.
Furthermore, the licensee's 50.54(f) response to Question 18, Revision 5, date'd* February 2, 1980, states, " Piping will be designed to accesedate the expected future differential settlement", between the diesel pedestals and the building structure.. In the 50.55(e) report the licensee states, " requirements for differential settlecent between the Diesel Generator Building Structure and Diesel Generator Pedestals were not accounted for in the design of the piping equipment conduits, and pipe supports."
9.
The Region III staff plans to follow up on this matter he a routine inspection item.
C.
The pertinent facts that relate to the crack monitoring issue are as follows:
I-1.
The NRC staff during the Stone & Webster public meeting on November 10, 1983, imposed a hold point on resuming soils remedial under-pinning until the crack ~ monitoring issue was resolved. This resulted from the NRC's review of Stone & Webster's weekly reports which indicated some problems in the crack monitoring area.
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D. G. Eisenhut 3
January 25. 1984 2.
On November 30, 1983, the licensee provided RIII with an updata of the crack monitoring issue.
In summary, the licensee in'dicated that QA/QC ' inspections and overviews were incomplete for crack mapping.
i This resulted in.the issuance of 59 NCR's and 11 QAR's that included a magnitude of problems for example:
a.
Inadequate specification, procedures and Project Quality Ocntrol Instructions (PQCI's) b." ' ' Some cracks were not being monitored c.
Some cracks were not identified d'.
QA/QC inspection functions not completed Crack mapping issues were not being resolved in a timely :anner e.
3.
During an ASLB hearing session on December 3, 1983, Mr. D. Hood, NRR Project Manager', verbally notified the ASLB of'this condition.
4.
On December 6,1983, RIII documented this as a formal hold point in a letter to CPCo.
5.
On December 23, 1983, corrective actions taken on crack-mapping vere reviewed by Stone & Webster and were found to be acceptable.
6.
On December 29, 1983, a letter to CPCo from RIII documented the
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completi~on of the review of the corrective actions taken, found c5em to be acceptable, and rel' eased the NRC hold,oint.
7.
The NRC Hold Point was released prior the licensee releasing its step work of October 22, 1983, and therefore, the NRC hold point had no impact on the licensee's schedule.
If you have any questions or desire further information regarding this matter, please call me.
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I? JNt.)Ms<.Eh R. F. Warnick Director Office of Special C2ses
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