ML19248D005
| ML19248D005 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 05/07/1979 |
| From: | Cook R, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19248D001 | List: |
| References | |
| 50-329-79-09, 50-329-79-9, 50-330-79-09, 50-330-79-9, NUDOCS 7907300096 | |
| Download: ML19248D005 (6) | |
See also: IR 05000329/1979009
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-329/79-09; 50-330/79-09
Docket No. 50-329; 50-330
License No. CPPR-81; CPPR-82
Licensee:
Consumers Power Company
1945 West Parnall Road
Jackson, M1 49201
Facility Name:
Midland Nuclear Power Plant, Units 1 and 2
Inspection At:
Midland Site, Midland, Michigan
Inspection Conducted:
February 1 - !brch 29,1979
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Inspector:
R. J. Cook
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Approved By:
R.C.
Knop, Chief
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Projects Section
Inspection Summary
Inspection on February 1
.'brch 29, 1979 (Report No. 50-329/79-09;
50-330/79-09)
Areas Inspected:
Examination of the site conditions, tensioning of
steam generator and reactor vessel hold down bolting, settlement of
diesel generator foundations and structures and associated settlement
monitoring program, inadequate crimping in vendor supplied electrical
penetrations, Unit 2 reactor vessel internals storage, adequacy of
decay heat removal pump technical maintenance information, fire in the
solid radwaste building, management meetings betweer. agional principa!
staf f members and licensee corporate personnel, welding of Unit 2 reactor
coolant system seismic supports / restraints, base line inservice inspection
preparations, safety practices of site radiographers, hydrostatic tesing
of Unit 2 incore instrument tank 2T-87, cable tray and wire installation
in the spreading rooms, and violations of QC Hold Tags.
This inspection
effort involved a total of 96 inspection hours by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
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7907300096
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DETAILS
Persons Contacted
- D. Miller, Site Manager
- J.
Corley, Quality Assurance Section Head IE and TV
- B.
Peck, Construction Supervisor
- P.
Kyner, Field Quality Assurance Engineer
D. Horn, Quality Assurance Engineer
- L. Drei sbach, Bechtel Corporation Quality Assurance Engineer
- E.
Smith, Bechtel Corporation Quality Assurance Engineer
- D.
Hollar, Bechtel Corporation Quality Assurance Engineer
- R.
Shope,
B6'..' Proj ec t Engineer
W.
Lee, B&W Construction Site Consultant
Numerous other principal staff and personnel were contacted during the
reporting period.
- Denotes those present during at least one of the four exit interviews
conducted during the report period.
Licensee Action on Previous Inspection Findings
(Closed) Item of Noncompliance (329/78-13-02; 330/78-13-02):
B&W field
Procedure FCp No. 11 was developed to allow hydraulic tensioners to be
used for setting the steam generator and reactor holddown bolts at the
pretension level established by Drawing No. 376Q, Revision 8.
During
the reporting period, tensioning of Unit 2.
North Steam Generator
holddown bolts were v2*i.ossed.
The above referenced procedure was being
applied at this time.
Reportable Deficiencies - 50. 55 (e ) Items
Settlement of Diesel Generator Foundations and Structures
(open) Item of Noncompliance (329/78-13-03; 330/78-13-03):
During the
reporting period the licensee has informed the Resident Inspection of
additional soil borings and data which have been taken pertinent to
monitoring the settlement of the diesel generator building.
The prelim-
inary qualitative results of this data were subsequently relayed to
Regional Office Personnel. A Regional Based Inspector performed an
inspection onsite on March 28 and 29, 1979, to perform a quantitative
review of the settlement monitoring program (NRC Inspection Report No.
50-329/79-06; 50-330/79-06).
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Inadequate Crimpling '.n Vendor Supplied Electrical Penetrationg
During the reporting period, vendor representatives performed a visual
examination of six contamination electrical penetrations which had
exhibited discrepancies in the crimpling of terminations.
Their examin-
ation confirmed the results of previous inspections of the electrical
penetrations. Tae vendor has agreed to perform extended examinations of
all penetrations and to replace defective crimps.
The Resident
inspector was invited and attended a meeting between the licensee and
vendor to discuss the condition of the penetration.
Functional ar.d Program Areas Inspected
1.
Site Tours
At periodic intervals generalized site tours were conducted by the
Resident Inspector.
During the reporting period, these tours
particularly covered Units 1 and 2 containments, upper and lower
spreading rooms, safety related motor control centers, battery
rooms, penetration rooms, solid radwaste storage building, and
diesel generator building.
The se tours were intended to assess the
cleanliness of the site, storage condition of equipment and piping
being used in site construction; the potential f r fire or other
hazards which might have a dilatorious affect on pe sonnel and
equipment and to witness construction activities 1a progress.
2.
Unit 2 Reactor Vessel Internals Storage
The final storage condition of the partially assembled Unit 2
core barrel was examined.
The core barrel is positioned on the
st: age stand which is being supported by polyethylene covered
wood located on the floor of the fuel pool.
The core barrel is
drapped with polyethylene and has remained plum within the
required 0.010 inches per foot.
The licensee is constructing
temporary " clean room" with controlled access around the core
a
' arrel for continued assembly of the core barrel.
3.
Decay Heat Removal Pump Technical Literature
During a review of technical literature and drawings associated
with the assembly of impellers on the shaft of the decay heat
removal pumps, ambiquity was noted which relied heavily on the
experience of maintenance personnel to correctly assemble the
pumps.
T.ie licensee has agreed to insert clarifying information
and/or drawings to remove any uncertainties in future maintenance
work performed on these pumps.
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4.
Fire in the Solid Radwaste Building
At about 4:00 a.m., on February 4,
1979, the licensee experienced
a fire at the roof elevation (approximately 648 ft elevation) at
the south face of the westend of the solid radwaste building.
The
is attributed to a temporary gas operated unit heater being
cause
close to wood formers which ignited the formers and adjacent
The Midland City Fire Department responded to the
fire alarm and brought assistance to fire fighters onsite.
Minimal
damage to the building and no serious personnel injuries were
sustained.
5.
Manaaement Meetincs
On February 7, 1979, principal NRC Region III staff met with
representatives of Consumer Power Company senior corporate staff
and senior Bechtel Corporation Midland Staff members at the
Midland Site.
The Resident Inspector attended these meetings.
Details pertinent to these meetings are discussed in NRC
Inspection Reports No 50-329/79-04; 50-330/79-04.
6.
Welding of Unit 2 Reactor Coolant System (RCS) Seismic Supports /
Restraints
During the installation of seismic support / restraints for the RCS
in Unit 2 containment, linear indications of cracking of inbeds has
been experienced.
This cracking has been taued in B&W Nonconform-
ance Report No. 459 and subsequent repairs of linear indications
are documented in the B&W Minor Repair Procedure file.
On
February 6-8, 1979, a Regional Based Inspector performed an
inspection and reviewed the licensee's activities pertinent to
repair of these linear indications.
7.
Base Line Inservice Inspection
During the reporting period the Resident Inspector was informed
that the licensee was developing scheduling plans and procedural
details for performance of the base line inservice inspection.
The licensee stated that actual NDE is scheduled to start in May,
1979.
8.
Site Radiographers
During the reporting period, radiographers from X-Ray Engineering,
Company were observed working on the night shift.
Radiation areas
were marked, personnel were in attendance, and survey meters
appeared to be in use.
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Du. ing the reporting period B&W has experienced some personnel
changes in the night shift radiography crews.
Some discrepancies
have been noted by the licensee pertinent to safe operation.
has attempted to rectify these discrepancies by procuring addi-
tional experienced radiographers.
The licensee was observed
performing an overview inspection of the B&W radiographers.
The
Resident Inspector was informed that minor discrepancies were noted
in posting of radiation areas.
9.
Hvdrostatic Test of Unit 2 Incore Instrument Tank 2T-87
The licensee performed a hydrostatic test of Unit 2 Incore
Instrument Tank 2T-87.
However, it appeared that portions of two
vertical welds which penetrate the floor area at about the 626 foot
elevation could not be physically examined to e ablish zero
leakage using the techniques employed.
This was subsequently
established to be a potential item of noncompliance during the next
reporting period.
10.
Cable Tray and Wire Installation
During the report period cable pan and wire installation in the
spreading rooms was inspected.
Sharp edges were noted at the
inside surface of cable pan IBFB01 into 1RJG01 located in the upper
spreading room.
These sharp edges were pointed out to the
licensee. At the time frame that these " sharp edges" were noted
the licensee had identified weakness in the program which allowed
personal judgement to determine if a need exists for placing edge
protectors on sharp edges based on how the sharp edge might tend to
affect a given cable pull.
The affects of sharp edges on indi-
vidual cables, once the cable pan was filled, was not necessarily
considered for the need and placement of edge protectors.
The
licensee has added additional edge protectors to those locations
addressed in the Nonconformance Reports; instructed Electrical QC
Engineers in cable installation with emphasis on the use of edge
protectors; and modified QC Instructions to include those locations
where a cable presses against a sharp edge.
11.
QC Hold Tac Violations
During the inspection of cable pan and wire installation in the
upper spreading room (referenced above), a QC Hold Tag No. NCR 1727
was noted on cable pans designated IBGB, IBFB, IBFA, and IBGA. The
hold tags were placed because of pan identification markings not
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being in agreement with Drawing No. E-642(Q) SH.
1, Revision 6.
It
was noted that the hold tags were inconspicuous 1y placed at the
opposite end of the cable can from where cable was being installed
and cables were pulled into these pans without a conditional
release from the NCR placing the hold tags.
The licensee had previously identified that violations of hold tags
had occurred and was able to demonstrate this by letters which had
been exchanged among management personnel, NCR's written addressing
violations of Hold Tags, and the existance of a Hold Tag Violation
File.
The licensee has given additional instructions to QC
Engineers in the use of Hold Tags with emphasis on placing Hold
Tags in such a manner as to be recognized by construction per-
sonnel; issued a strong letter from the Bechtel Power Corporation
Project Superintendent ir.sisting that procedura! requirements
concerning hold tags are strictly adhered to; and demonstrated
strong management reaction to violations of QC Hold Tags.
Because the licensee has taken dramatic action to curb violations
of QC Hold Tags, and because this action appeared to be in progress
prior to the Resident Inspector noting a violation of Hold Tags and
these actions have emphatically continued, violations of QC Hold
Tags is considered an unresolved item.
This item shall remain
unresolved until such times that it has been demonstrated (or
cannot be demonstrated) that the licensee's actions have become
effective in curbing violations of QC Hold Tags and is able to
adequately adJress isolated intances should they occur with good
reason. Unresolved Item (329/79-09-01; 330/79-09-01).
Unresolved Matters
Unresolved items are matters about which more information is required in
order to ascertain whether they are acceptable items, items of noncom-
pliance or deviations.
One unresolved item disclosed during the
inspection is discussed in Paragraph 11.
Exit Interview
The Resident Inspector attended the Exit Interview conducted by 1. Yin,
P. Ba r re t t , and E. Gallagher, RIII Reactor Inspectors on February 8 and
9; and March 29, 1979, respectively.
The Resident Inspector met with licensee representatives (denoted under
Persons Contacted) on February 2, February 15, February 21, and March 20,
1979.
The inspector summarized the scope and findings of the inspection
effert to date.
The licensee acknowledged the findings reported herein.
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