ML19208A624
| ML19208A624 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/06/1979 |
| From: | Chaudhary S, Mccaughy R, Toth A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19208A607 | List: |
| References | |
| 50-322-79-04, 50-322-79-4, NUDOCS 7909170091 | |
| Download: ML19208A624 (18) | |
See also: IR 05000322/1979004
Text
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U.S. NUCLEAR REGULATORY C0FDiISSION
OFFICE OF INSPECTION AND ENFORCEMENT
Region I
Report No. 50-322/79-04
Docket No. 50-322
License No. CPPR-95
Priority --
Category A
Licensee: Long Island Lighting Company
175 East Old Country Road
Hicksville, New York 11801
Facility Name:
Shoreham Nuclear Power Station, Unit No. 1
Inspection at:
Shoreham, New York
Inspection conducted: March 27-30, 1979, and April 2-4, 1979
Inspectors:
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A. D. Toth, Reactor Inspector
date signed
m
b ' f 55 Y s
S.K.Chaudhary,ReactorI/spector
date signed
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A. E. Finkel, Redctor Inspector
date signed
Approved by:
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R.W.McGaughy,piefpProjectsSection
y dqs6 signed'
Reactor Construction a Engineering Support Branch
Inspection Summary:
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Inspection on March 27-30 and April 2-4, 1979 (Report No. 50-322/79-04)
Areas Inspected:
Routine, unannounced inspection by three regional
based inspectors of work activities for electrical cable installation
and quality verification records for electrical cable installation,
control of verbally authorized design changes.
The inspectors also
performed plant tour-inspections, reviewed licensee action on previous
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inspection findings, and performed follow-up action as necessary to
resolve questions which arose during the course of inspection of the
above areas.
Such follow-up included an unannounced return to the
site on April 2, subsequent to the exit meeting March 30, to review
QA inspector qualifications.
The inspection involved 78 inspector-
hours onsite by 3 NRC regional office based inspectors.
On April 2,
1979, the inspection commenced 8:30 p.m. outside the normal dayshift
working hours at the site.
Results: Of the three arcas inspected, no items of noncompliance were
identified in two areas; one apparent item of noncompliance was
identified in one area.
(Infraction - failure to control thermal-
cutting on RHR heat exchanger, Paragraph 3.)
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DETAILS
1.
Persons Contacted
Long Island Lighting Company
- D. Bednarczyk, QA Supervisor
T. Catchpole, QA Engineer
- R. V. DeRocher, QA Engineer
- T. F. Cerecke, QA Banager
- M. A. Ciannattasio, Assistant Project Engineer
- R. Cutmann, Startup Manager
T. Joos, QA Engineer
- J. M. Kelly, Field QA Manager
- L. C. Lilly, Site Manager
- E.
J. Nicholas, QA Specialist
- J. P. Novarro, Project Manager
- J. H. Taylor, Startup Manager
_
Stone and Webster Engineerine
- T. T. Arrington, Superintendent, FQC
J. Berthoty, FQC Inspector
J. Beverage, FQC Inspector
- J. A. Burgess, Project QA Engineer
J. Carey, FQC Inspector
D. Cooke, FQC Inspector
E. Cooper, FQC Inspector
- C. A. Fonseca, Assistant Project Engineer
- T.
C. Gray, Construction Turnover Coordinator
E. Hall, FQC Inspector Supervisor
- J. W. Hassett, Senior FQC Inspector
- K. A. Howe, General Superintendent of Construction
W. Moody, FQC Inspector
B. O'Donnell, FQC Inspector
R. Perra, FQC Chief Inspection Supervisor
R. Perry, FQC Inspector Supervisor
M. Staggs, FQC Inspector
Comstock Jackson
R. Troff, Reactor Area Manager
Hartford Steam Boiler I & I Company
- G. F. Cocuzzo, Authorized Nuclear Inspector
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- Denotes those present at March 30, 1979, exit interview.
- Denotes those present at April 4, 1979, exit interview.
- Denotes those present at both exit interviews.
In addition to the above, the inspectors interviewed various
contractor supervisory, administrative and craft personnel during
the course of the inspection, relative to records retrieval,
status of work, and general site activities.
Long Island Lighting Company (LILCO) and Stone and Webster (S&W)
personnel participate in the joint UNICO construction management
organization mentioned in this report.
NRC inspectors at this inspection included:
S. K. Chaudhary
March 27-30, 1979
A. E. Finkel
April 2-4, 1979
A. D. Toth
March 27-30 and April 2-4, 1979
2.
Plant Tour
Shortly after arrival onsite, the inspectors visited various parts
of the plant to observe work activities in-progress, completed
work and plant status.
Observations made during this general
inspection of the plant were considered as warranted during later
inspection of the construction quality assurance program imple-
mentation in specific areas.
Additional plant tour inspections
were also conducted at other periods over the duration of the
inspection.
The inspectors examined work for any obvious defects
or noncompliance with regulatory requirements.
Particular note
was taken of presence and/or availability of quality control
inspectors, and quality contrcl evidence such as inspection
records, material identification, nonconforming material status,
inspection / process hold-point status, housekeeping and equipment
p rese rva tirn.
The inspectors interviewed craft personnel, super-
vision and quality inspection personnel as such personnel were
available in the work areas.
No items of noncompliance were identified during this general
tour-inspection.
3.
Licensee action on Previous Inspection Findings
3gg[7();
(Noncompliance) Unresolved Item (78-11-04):
Temporary weld
attachment removed on the RHR heat exchanger.
The inspector
examined documents relating to removal of pressure / shipping caps
f rom the RHR heat exchangers, and interviewed responsible quality
control personnel, regarding the thermal cutting of welds.
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GE Specification No. 21A9227AK, Paragraph 2.4, establishes the
RHR heat exchangers as ASME Section III, Class C.
Paragraph
4.8.1 requires " Preheat requirements for thermal cutting shall
be the same as those specified for welding (Paragraph 4.8.2.4)."
The Paragraph 4.8.2.4 requires " Preheat requirements of Appendix R
of Section VIII of the ASME code are mandatory.
The minimum pre-
heat temperature shall be obtained through the full thickness
of the joint."
Appendix R requires that a minimum preheat of
175 be obtained if the wall thickness of the part is greater
than 1-inch, and the specified maximum carbon content of the
material exceeds 0.3%.
This is consistent with the 1971 ASME
Code Section III, Paragraph NB-4231.2(f) and referenced NB-4211.
The Perfex Company supplied material certifications for the N3
and N4 nozzles of RHR heat exchangers 034A and 034B show com-
pliance with ASTM SA 105 Crade II, which has specified maximum
carbon content of 0.35%.
The material certifications show nozzle
N3 and N4 wall thickness of 3 5/16" and 2 1/2" respectively.
Accordingly, the minimum required preheat for thermal cutting is
175 F.
The inspector had previously requested evidence that the required
heat treatment had been accomplished; such records were not
available, nor were records available that the required NDE had
been performed.
Plans to perform required NDE have since been
suggested in a Courter Nonconformance Report dated March 9,
1979. However, no data was yet available to affirm that
required heat treatment had been accomplished.
This is contrary
to Criterion IX of Appendix B of 10 CFR 50, " Control of Special
Processes," and related Criterion X and XII requirements relative
to inspection and documentation.
(322/79-04-01)
The inspector reviewed the following syecific documents relative
to the above:
Material Certifications for nozzles N3 and N4 (showing
ASME-SA-105-2, 3 5/16" and 2 1/2" respectively)
GE Specification No. 21A9227AK, Revision 4
Courter QA Procedure 10.1, Revision 1
7.1, Revision 2
Courter Nuclear QA Manual Sections 6 and 10
Courter Nonconformance Report No. 607 dated March 8, 1979
(14 pages).
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S&W QC Instruction No. FSI-F13.1-03D dated May 4, 1976
Component Checklist (weld history record) for welds:
No. 1E11-1C028-FW-3 (October 8, 1976, weld rod slip)
No. 1E11-1C029-FW-1 (October 19, 1976, weld rod slip)
No. 1E11-1C030-FW-1 (October 18, 1976, weld rod slip)
No. 1E11-1C028-FW-2
S&W QA and QC Manual - ASME Section III - Sections 9, 10 and 12
Section 9, Revision B, Fabrication and Installation Control
Section 10, Revision F, Welding and Brazing Control
Section 12, Revision B, Heat Treatment
4.
Quality Records Review of Electrical Cable and Terminations
The inspector selected the listed power and control cable records
to ascertain whether these records were in conformance with
established procedures and whether these records reflect work
accomplishment consistent with applicable requirements in the
following areas:
--Receipt inspection
--Installation records
--Nondestructive Examination
--Nonconforming / Deviation Records
(a) The control and power cable records selected by the inspector
for review are as listed:
Cable No.
System
Service
Size
1F11 ARC 701
Control Cable
14AWG
1F11 ARC 700
Control Cable
14AWG
1F11 ARC 538
Control Cable
14AWG
1E11 ARC 537
Control' Cable
14AWG
1E11 ARC 708
Control Cable
14AWG
1E11 ARC 707
Control Cable
14AWG
1B21 ARC 505
Nuclear Boiler
Control Cable
14AWG
1B21 ARC 506
Nuclear Boiler
Control Cable
14AWG
1E51 ARC 408
Reactor Core Isolation Cooling
Control Cable
14AWG
1E51 ARC 403
Reactor Core Isolation Cooling
Control Cable
14AWG
1E51 ARC 409
Reactor Core Isolation Cooling
Control Cable
14AWG
1E21 ARC 336
Control Cable
14AWG
1E41 ARC 407
High Pressure Coolant Injection Control Cable
14AWG
1R23ARH001
Unit Substation
4160V to 601V
500 MCM
1P41DOH061
4160V to 601V
4/0
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1P41C0H041
4160V to 601V
4/0
1P41BBH021
4160V to 601V
4/0
1P41ARH001
4160V to 601V
4/0
1M50DOH061
RBSVS and Control Room AC
4160V to 601V
350 MCM
Chilled Water
1M50C0H041
RBSVS sad Control Room AC
4160V to 601V
350 MCM
Chilled Water
1E11C0H041
4160V to 601V
500 MCM
1E11ARH001
4160V to 601V
500 MCM
1E11BBH021
4160V to 601V
500 MCM
The records for the above listed control and power cables were
inspected in accordance with the following licensee's procedures:
--Cable Installation Acceptance Criteria, Procedure QCI
FS1-F12.1-10E and 10F
--Cable Termination Procedure, QCI FSI-F12.1-13B
--Electrical Installation Specification SH1-159, Revision 3,
dated April 1, 1978
(b) The inspector reviewed the quality records for the above
control and power cables which included the Cable Pull
Tickets, Cable Termination Quality Control Inspection Report
(QCIR) Records, Cable Installation Acceptance (QCIRs) and
referenced Engineering and Design Coordination Reports (E&DCRs).
(1)
Cable Pull Tickets
The cable pull tickets list the cable identification
reel number, QC receiving inspection number, size, type,
raceways, from/to location, and esticated cable length.
The bottom part of the cable pull ticket has space for
the actual cable length salue to be recorded, continuity
and megger values to be recorded and a quality control
signature block.
(2)
Cable Installation (QCIR)
The cable installation (QCIR) requires that the quality
control inspector verify; the cable pull ticket attri-
bute against the microfiche data, in-process cable
installation, nondestructive testing of installed
cable, cable pull tension and method used to pull cable.
Cable bending radius requirements per SH1-159 are docu-
mented and record control numbers on pulling and
testing equipment if used during cable installation,
are recorded on the individual QCIR form.
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(3) Cable Termination (QCIR)
The attributes of the cable termination (QCIR) requires
inspection verification of the cable surface and wire
condition, correct lug / sleeve size and type, proper
crimping tool size and type, condition of wire crimp,
location to drawing verification, separation and
segregation verification, and cable verification back
to first raceway for routing separation and support.
If the cable is aluminum, the above conditions are followed
with additional inspection criteria as defined in SH1-159.
In reviewing the quality control records for the above listed
control and power cables, no items of noncompliance were
identified.
5.
Nonconformance/ Deviation Records
The inspector reviewed the listed Deficiency Corrective Orders
(DCO)
relative to cables, cable installation and termination,
and related electrical equipments.
The records were readily
retrievable by the licensee, they were current and legible, and
it appeared that the description and resolution, where completed,
was adequately described in the disposition.
Status
DC0 No.
Subj ect
Open Closed
Date
12793
1E41NBX002
X
January 19, 1979
12949
1E11 ARC 706
X
March 24, 1979
12943
Cable Tray ITC905B
March 22, 1979
IIC900B
X
March 22, 1979
ITC904B
X
March 22, 1979
12813
1E11*PS-134A
X
March 28, 1979
2785
1FX404R02
X
April 2, 1979
2951
1E11*MOV-032B
X
March 27, 1979
12946
1DX915B07
X
March 27, 1979
12950
1H11XPNL-MVP
X
March 27, 1979
1H11XPNL-608
X
March 27, 1979
12652
ITX621R
X
March 24, 1979
12644
1TX621
X
December 8, 1978
12643
ITX622R
X
December 8, 1978
No items of noncompliance were identified by the inspector.
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6.
Surveillance and Audit Reports
The inspector reviewed the listed surveillance and audit reports
associated with ele'irical cable installation, termination, and
electrical equipme - short term storage and stored in place
documentation.
(a) Electrical Cable Installation Surveillance Reports
Surveillance
Report
No.
Date
054
March 1, 1979
053
February 26, 1979
052
February 23, 1979
051
February 16, 1979
050
February 13, 1979
049
January 31, 1979
048
' January 17, 1979
047
January 17, 1979
046
January 12, 1979
045
January 6, 1979
044
December 18, 1978
043
December 6, 1978
042
November 14, 1978
041
November 13, 1978
040
October 25, 1978
039
October 19, 1978
038
September 18, 1978
037
September 13, 1973
(b)
Electrical Cable Termination Surveillance Reports
Surveillance
Report
No.
Date
059
dbrch 5, 1979
058
February 26, 1979
057
February 5, 1979
056
February 2, 1979
055
January 30, 1979
054
January 29, 1979
053
January 23, 1979
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052
January 5, 1979
051
January 3, 1979
050
December 26, 1978
049
December 26, 1978
048
December 20, 1978
047
December 7, 1978
046
November 14, 1978
045
November 13, 1978
044
October 23, 1978
043
October 19, 1978
042
September 18, 1978
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041
September 12, 1978
(c)
Electrical Equipment in Short Term Storage or Stored _
in Place Reports
Surveillance
Report
No.
Date
March 1, 1979
March 1, 1979
February 2, 1979
February 2, 1979
February 2, 1979
February 2,1979
December 15, 1978
December 15, 1978
November 16, 1978
November 21, 1978
October 31, 1978
October 31, 1978
September 26, 1978
September 26, 1978
(d)
Field Audits (FAs)
FA 846, dated November 10, 1978, entitled " Audit of
Instrumentation Stored in Place."
FA 826, dated October 13, 1978, entitled " Audit of
Instrumentation Installation and Records."
FA 823, dated October 10, 1978, entitled " Audit of
Electrical Cable and Raceway."
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FA 895, dated February 16, 1979, entitled " Audit af
Electrical Equipment Stored in Place."
FA 822, dated October 13, 1978, entitled " Audit of
Electrical Equipment Installation and Records."
FA 836, dated October 5,1978, entitled " Audit of
Measuring and Test Equipment
The inspector reviewed the Corrective Action Requests (CARS) and
the Engineering and Design Coordination Reports (E&DCRs) issued
from findings identified in the above reports.
It appears that the
corrective action to correct the identified findings listed in
the reports were such that repetition of the deficiency should
be precluded.
No items of noncompliance were identified.
7.
Installation of Power and Control Cable
The inspector examined the installation and termination of the
listed power and control cables associated with the 101 and 102
diesel and switchgear rooms and selected equipment installations.
The electrical cables were examined in accordance with the cable
pull ticket for both installation and termination and the equip-
ment was examined in accordance with the requirements of
specification SH1-159.
(a) Diesel P.coms:
--1JB*306 Junction Box
--1CL545RA5 Conduit
--1R43ARL001 Power Cable
--1JB*623C Generator End
(b)
CO2 Panels
--1M43*PNG C0-5
--1M43*PNL C0-7
--1M43*PNL CO-6
(c)
Switchgear Room (102)
--Cable fray ITCt-13B
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--Vertical Trough _1TC442B
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(d)
Screen Well Building
--lX41BBC526 Control Cable
-lCK352RM1 Conduit
--1CH305RA Conduit
--lJB323 Junction Box
(e)
Randomly Selected Cables and Conduits
--lDC902R64
--lX60C0X600
--lCH3600A
--lTK671R
--lTL663R
No items of noncompliance were identified.
8.
Cable Terminations in Control Room Cabinets
The inspector examined the installation and termination of control
cables in randomly selected contro? room equipment cabinets.
Cable Nos. 1C11 ARC 003, IC41 ARC 003 and IC41BBC013 which are
14A'G 5/C Rockbestos Cables appeared to have dents on the terminated
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cables insulation just behind the cable termination lugs.
It appears
that when using the mechanical wire stripping tool, before the insulation
is stripped from the stranded conductors, the mechanical stripping tool
vill lock-on to the conductor insulation material and then the cutting
part of the stripping tool strips the insulation from the stranded conductor
wire. The indents on the conductor insulation is made during the wire
stripping action of the stripping tool. The inspector randomly selected
three wire stripping tools with strip Nos. 10, 18, 16, and 14AWG sizet
wire for three different electrical personnel. The inspector using these
three tools performed three separate wire stripping actions on a
5 stranded No. 14AWG 5/C Rockbestos cable similar to the cables in the
cabinets of the control room 1H11*PNL. The incidents on the cable insulation
varied in depth among the three cable stripping tools.
The licensee stated that the cable stripping tools are not controlled and
do not come under the equipment calibration program that is presently used
at the site.
The significance of the indents on the cable insulation caused by the action
of the stripping tools, is considered to be an unresolved item, pending its
evaluation by the licensee and the review of the evaluation by an NRC
inspector during a subsequent inspection. (322/79-04-02)
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9.
Training and Qualification of OC Electrical Inspectors
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During a March 29, 1979, examination of records of electrical
cable work, the inspector interviewed a S&W level II quality
control (QC) inspector who had been recently hired from another
site, and who had been assigned responsibilities for inspection
of electrical cable pulling and terminations.
The QC inspector
could not respond to questions regarding acceptance criteria.for
his terminations inspection checklist to the satisfaction of the
NRC inspector. The QC inspector could not describe the acceptable
" size and type" of cable termination, nor where he might obtain
such information, although the QC inspector was preparing to
perform inspection of terminations.
The S&W QC management stated
that this individual was experienced at another project and had
been personally known by his supervisor to be capable; his
ability
to respond to the NRC inspectors questions was attributed
to personality considerations.
The QC inspector had been onsite
in an orientation status for about only a month, and had just
recently been released to perform inspections on his own.
The
NRC inspector identified the matter of QC electrical inspector
training as unresolved at a Friday, March 30, 1979, exit meeting.
On Monday, April 2, 1979, two NRC inspectors arrived onsite,
unannounced, at 8:30 p.m.
No safety related electrical cable
work was in-progress, but a second shift QC electrical inspector
was available onsite.
The NRC inspectors interviewed this indi-
vidual relative to acceptance criteria for inspection checklists
previously signed by him for electric cable inspections.
During
the next day, the NRC inspectors similarly interviewed eight
other QC electrical inspectors, including the individual previously
interviewed on Friday. With the exception of that individual,
the NRC inspectors found the QC electrical inspectors knowledge-
able in the criteria for electrical cable pulling and termination
activities for which they were authorized to perform, as posted
on the qualification status board in the QC Chief Inspection
Supervisor's office. A training qualification program appeared
to be established and implemented.
As a result of the NRC interviews, the S&W QC supervision obtained
the questionable QC inspector's log-book and initiated re-inspec-
tion of each termination inspected by the individual.
(These were
all control cable terminations, subject only to post-installation
inspection.
A re-inspection at this time thus appears to be a
valid verification technique.)
In addition to further training
of this individual, the S&W Chief Inspection Supervisor stated
that training sessions will now incorporate written quizzes to
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verify inspector familiarity with inspection criteria. Also, the
supervisor plans to participate in the weekly training sessions
to further assure proper flow of information regarding acceptance
criteria and QC inspector responsibilities.
The NRC inspectors concluded that the individual in question was
an isolated example of premature release of a QC inspector to
perform independent work activities in an area in which he was
not fully prepared.
The NRC did not find a general deficiency
in this area, and had no further questions at this time, in view
of the QC Inspection Supervisor's actions.
During the above review, the inspectors examined the following
documents:
S&W Procedures:
QCP-12.1
QCI-FSI-F12.1-10E and 10F
QCI-FSI-F12.1-13B
S&W Specification:
SH1-159 Revision 3, and manual of
E&DCRs (changes).
Cable Pull and Termination Inspection Reports:
1X-60C0X602 (Pull)
E21BBC023 (Pull)
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E11 ARC 202 (Term)
1DX911026 (Pull)
1X60C0X600 (Term)
1E11BRC593 (Pull)
1E51NRC075 (Term)
1E11ANC911 (Pull)
1R43BBC001 (Pull)
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QC Inspector Orientation / Training Status Board - April 2, 1979
No items of noncompliance were identified.
10.
Records of Electrical Deficiency Corrective Orders
On March 27-30, the inspector examined quality assurance records
for three power cables (1R22NRK346, 1E21BBK233, 1E41NBK132)
relative to receipt inspection, materials certification, installa-
tion, and nondestructive tests.
The inspector ascertained that
certifications reflected conformance to Purchase Order specifi-
cations No. SH1-127, 128, or 129 for the reels from which the
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cables were drawn.
The inspector ascertained that the physical
test report for cable IE41NBK132 showed test values within the
prescribed acceptance criteria.
The inspector also reviewed the
electrical QC list of open deficiency corrective orders.
The inspector selected seven open DCOs relating to cables; of
these, five related to failures in protection of the cable
(from damage) in accordance with specification requirements
(resting on sharp edges, lack of coverings, debris):
No. 12218, dated July 11, 1978
No. 12651, dated December 5, 1978
No. 12798, dated January 25, 1979
No. 12862, dated March 12, 1979
No. 12942, dated March 16, 1979
Upon inquiry by the NRC inspector, the S&W quality control staff
ascertained that none of these DCOs are yet closed, although work
was reportedly in progress relative to No. 12218, and QC inspec-
tion was pending for work completed for No. 12651.
The NRC
inspector expressed concern for lack of Lnmediate corrective
action, for conditions which could lead to increasing deterior-
ation or increasing probability of damage with time.
This item
is unresolved pending review of licensee action to ascertain the
status of DCOs involving such considerations.
(322/79-04-03)
11.
Control of Verbally Authorized Design Changes
During the plant tour inspection, the inspector observed personnel
referring to details of an interoffice memorandum which documented
previous verbal design change instructions regarding a ventilation
duct support.
The inspector reviewed procedures which control
the issuance of such verbal instructions, and records of delega-
tion of authority for issuance and receipt of such changes.
The
procedures limit such verbal changes to the duct support and
pipe support disciplines only, limit the origin and channels of
connunication for such changes, and require immediate informal
documentation and later formal documentation within three months.
The licensee site QA organization has audited this area to verify
the timely formal documentation of such changes.
The constructor had not formally designated specific individuals
for requesting and issuing verbal design change instructions for
duct supports work.
However, the inspector determined that there
were specific individuals assigned to the task who were following
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the procedure. This was properly documented by the constructor
on March 29, while the inspector was still onsite.
Formal desig-
nation of individuals for requesting and giving out " verbal"
design change instruction was documented and existed for the pipe
support discipline.
The inspector reviewed the following documents relative to the
above:
S&W EAP-5.1, Rev. 3; EAP-5. 7, Rev. 2; EAP-6. 3, Rev. 3
S&W Inter Office Memoranda, SEO 55 and 55A
S&W Project General Instruction, Addendum 62, Rev. 1
S&W E&DCRs F-5854-Z
F-7668-S
F-11725
F-16741-A
F-17113
F-14936
S&W " Verbal" design change instructions - IG33-PSSH024
IB21-HA3
IB21-SB2
lEll-PSSH261
IM50-PSR622
lE41-PSR054
LlLCo Field Audit FA-905 dated March 20, 1979
No items of noncompliance were ioentified.
12.
Service Water Building Equipment Supports
During a plant tour-inspection of the service water building,
the inspectors observed pump supports which appeared to have
questionable welds at the wall anchorage, and anchor bolts located
too close to an embedded unistrut, relative to jobsite specifi-
cations.
The inspectors later interviewed responsible S&W QC
inspectors to determine the extent of inspections completed in
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the service water building.
The questionable items observed by
the NRC inspectors had not yet been inspected by S&W, but would
eventually be inspected under the S&W program.
However, since
the items were questionable, the NRC inspectors requested appli-
cable drawings and specifications and requested that the S&W
-
QC inspector perform an inspection of the welds and bolts to his
acceptance criteria.
The S&W QC inspector was generally familiar
with the applicable acceptance criteria and rejected the 11/4"
spacing of the 1"-bolt as not meeting the 3-bolt-diameter minimum
spacing criteria.
He stated that he will issue a nonconformance
report regarding this item.
For the welding, there appeared to
be a conflict between the S&W drawing and the corresponding Cives
drawing relative to required fillet weld size and corner wrap-
around requirements, such that acceptibility of the welds could
not be determined.
The QC inspector stated that this item would
be referred to S&W engineering for clarification of applicable
requirements.
This item is unresolved pending completion of the engineering
dispo si tion.
(322/79-04-04)
The inspectors examined the following documents relative to the
above:
Weld Procedure Specification W-200, Section A, Part 8.3,
Revision 5, E&DCR-P2940C
Inspection Reports QCIR " Structural Steel" dated
November 2,1978, and November 3,1978, file W22.
Drawings: M-10017-9 (FM-4A)
M-12972-2
9.22-170A (Cives)
FS-38-8
9.30-001E
13.
Unresolved Items
Unresolved items are matters about which more information is
required in order to ascertain whether they are acceptable items,
items of noncompliance, or deviations.
Unresolved items disclosed
during the inspection are discussed in Paragraphs 8,10, and 12.
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e
.
.
.
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14.
Management Interview
%
At the conclusion of the inspection on March ?O, 1979, a meeting
was held at the Shoreham site with representatives of the
licensee and contractor organizations. Attendees at this meeting
included personnel whose names are indicated by notation (*) or
(***)
in Paragraph 1.
The inspectors summarized the results
of the inspection as described in this report, including identi-
fication of an unresolved item regarding qualification of QC
electrical inspectors.
This item was resolved during the following
week.
At the conclusion of the unannounced continued inspection on
April 4, 1979, a second meeting was held at the Shoreham site.
Attendees at this meeting included personnel whose names are
indicated by notation (**) or (***)
in Paragraph 1.
The inspectors
su=marized the results of the continued inspection, including
the conclusion that the additional inspection shgwed that QC
electrical inspector training was acceptable (resolved).
351215