ML19259A576
| ML19259A576 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/20/1978 |
| From: | Hayes D, Naidu K, Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19259A572 | List: |
| References | |
| 50-483-78-10, NUDOCS 7901080076 | |
| Download: ML19259A576 (17) | |
See also: IR 05000483/1978010
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-483/78-10
Docket No. 50-483
License No. CPPR-139
Licensee: Union Electric Company
P. O. Box 149
St. Louis, MO 63166
Facility Name:
Callaway, Unit 1
Inspection At:
Callaway site, Callaway County, MO
Inspection Conducted:
October 2-4, 1978
[, S. h5w&E
Inspectors:
E. R nSchweibinz
//-/7~28
\\ j,
N
g j
3 c )$'
K. R. Na\\ td
,
idu
E. O.
[+<- J. C. Mattia (Regi6n I)
// ~/ 2 ~ N
r. r. 4L
h C. R. Oberg %(Region IV)
/ ', ~ / , ~ ,8
Approved By:, D. W.
ay s
er
//
Oj!M
Projects Section
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Inspection Summary
Inspection on October 2-4, 1978 (Report No. 50-483/78-10)
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Areas Inspected:
Reactor Pressure Vessel movement act ivities; Site tour;
Cable Tray support installation; Cable Tray support welding activities;
Cable Tray support welding records; Containment structural steel welding
records; Safety-related structures; Reactor building interior concrete
structures; Licensee site audits; and safety-related components. The
inspection involved a total of 78 inspector hours on site by four NRC
inspectors.
Results: Of the ten areas inspected no items of noncompliance or
deviations were found in eight areas; two apparent items of noncompliance
were identified in two areas (infraction - failure to follow procedures
for weld rod control - Section I, paragraph 2; infraction - failure to
follow procedures for timely response to audit findings - Section III).
7soiwso76
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DETAILS
Persons Contacted
Union Electric Company (UE)
- W.
H. Weber, Manager, Nuclear Construction
- R. L. Powers, Site Quality Assurance Group Leader
- W.
H. "'nhl, Ouality Assurance Engineer
- S. M. Ho,an, Quality Assurance Assistant Engineer
M. I. Do i.e, General Superintendent, Callaway Construction
J. R. Vcatch, Quality Assurance Assistant Engineer
J. V. Laux, Quality Assurance Assistant Engineer
J. C. Gearhart, Quality Assurance Assistant Engineer
J. Baker, Construction Supervisor
Daniel International Company (Daniel)
- H.
J. Starr, Project Manager
- E.
D. McFarland, Construction Engineering Manager
- W.
C. Westhoff, Quality Control Manager
- J. A. Holland, Project Quality Assurance Manager
- W.
L. Sykora, Assistant Project Manager
- J.
N. Kaelin, Project Audit Response Coordinator
S. R. Farwell, Rigging Consultant
The inspectors also contacted and interviewed other licensee and contractor
personnel, including Craf tsmen, QA/QC, Technical and Engineering staff
members.
- denotes those attending the exit meeting.
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Licensee Action on Previous Inspection Findings
(Closed) Unresolved item (50-483/78-01-08, 50-483/78-03); The QA/QC system
implemented by the licensee does not require that nonconforming items
in storage be tagged or otherwise identified relative to their status.
Administrative Procedure number AP-IV-09, Revision 0, dated September 18,
1978, has been issued. This procedure requires that items found to be in
nonconformance of the storage requirements that have deteriorated or
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are suspected to have deteriorated will have a nonconformance report
initiated against them.
It further requires that if equipment is found
to be in adverse storage conditions but not nonconforming, a notation
will be made on the preventive maintenance work order, and a copy placed
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in a pending file. The pending rile will be reviewed weekly to insure
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that correttive action is taken to resolve the discrepancy. This item
is closed.
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(0 pen) Unresolved (50-483/78-06-01)'
QA Engineering procedure QE-301
did not address what is to be done with comments generated from
reviewing documents received from o ganizations. The licensee stated
that their QA procedure, QE-303 is the procedure for disposition of
comments and they will revise QE-301 to reference QE-303.
This item
remains open.
(Closed) Noncompliance (50-483/78-06-02):
Failure to provide objective
evidence that Alpha Portland Cement Company's QC program (Revisions 1,
2 and 4) were reviewed and approved. The inspector reviewed documenta-
tion dated August 24 and September 15, 1978, indicating that the
Alpha Portland Cement Company's QC program (Revisions 1, 2 and 4) had
been reviewed and approved. In addition to this program the licensee's
constructor performed a 100% audit of all their safety related purchase
orders to verify that all QA programs have been reviewed and approved.
The Daniel International letter dated September 13, 1978, stated that
this 100% audit had been completed and all QA programs have been ~eviewed
and approved. This item is closed.
(Closed) Noncompliance (50-483/78-06-03):
Failure to provide objective
evidence that Pittsburgh Testing Laboratory's QC procedures No. A-SL
(Revision 2) and No. S l (Revision 2) had been reviewed and approved.
The inspector reviewed licensee's documents dated August 22, ar.d
October 4, 1978, indicating that the above Pittsburgh Testing
Laboratory procedures had been reviewed and approved.
This item is
closed.
(Closed) Noncompliance (50-483/ 8-06-04):
The licensee's QA proccdure
f ailed to provide several of the requirements in ANSI N45.2.11 for
design external interface control. The licensee issued a QA procedure
No. QE-3.8 Revision 0, dated September 15, 1978, which addressed
design-external interface control. The inspector reviewed this
document and found it to meet requirements.
This item is closed.
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(Closed) Noncompliance (50-483/78-06-05):
Engineering Change Notices
(ECN) issued by the site A/E are now approved by the licensee in
accordance with QE-319, Review of Engineering Change Notices prepared
by the Site Architect Engineer, Revision 0 (9/15/78).
This item
is closed.
(Closed) Noncompliance (50-483/78-06-06): QE-303 Review of Design
Documents, Revision 7 (9/15/78) now defines the requirements for
document review and comment.
Internal procedures for Bechtel and
SNUPPS Staff Procedures are in agreement with QE-303.
This item is
closed.
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(Closed) Noncompliance (50-483/78-06-09): QE-303, paragraph 2.0,
Scope, has been changed to define responsibility for review. See Item
50-453/78-06-06 above . This item is closed.
(Closed) Unresolved (50-483/70-06-08):
This item is closed based on the
clarification of review requirements in QE-303.
(Open) Noncompliance (50-483/78-06-10):
This item remains open pending
a change to QE-314, paragraph 5.2, for an appropriate reference to QE-301.
(0 pen) Noncompliance (50-483/78-07-07 and 50-483/78-07-08):
Changes to
AP-IV-04 and AP-IV-05 are still in the review stage and have not been
issued. The licensee representative stated that the changes will be
issued by October 31, 1978. This item remains cpen.
(Open) Unresolved (50-483/78-06-07):
This item refers to adequacy of
distrubution and filing control system. After discussion with the licensee
representative it was determined that this item vill need to be reviewed
further during a future inspection.
The licensee will also review this
matter internally. The IE inspector determined that the review of
safety-related items by personnel outside of the Q,A program was satisfied
by a change to paragraph 5.1.3 of QEC-303, which rer
es final
evaluation to be done by Nuclear Engineering. Thi, item remains open.
(open) Unresolved item (50-483/78-07-04):
Resurvey of the safety-related
columns in the Auxilary Building. Some columns in the Auxilary Building
were determined to be out of plum during a resurvey. The contractor
provided some additional information to the inspector during the current
inspection however, this item remains open pending further review.
(0 pen) Unresolved item (50-483/78-07-05):
Inadequate provisions to control
welding process.
It was previously reported that the contractor agreed to
develop suitable provisions to establish that welding is performed within
the parameters specified in the Welding Procedures specification.
The con-
tractor has developed an interim instruction, Welding Equipment Voltage
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Surveillance, Procedure number 11-030, dated October 4, 1978.
This item
remains open pending review of the implementation of this procedure.
(Closed) Followup Item (50-483/78-02-05): Welding procedure implemen-
tation for cable tray supports. This item is addressed in Section II,
paragraphs 1, 2, and 3 of this report. This item is closed.
Functional or Progran Areas Inspected
Details of Functional or Prog am areas inspected are documented in Sections
1, 2, 3, and 4 as follow..
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Section I
Prepared ty E. R. Schweibinz
Reviewed '2y D. W. Hayes, Chief
Reactor Projects 4ection
1.
Reactor Pressure Vessel and Upper Internals Removal from a Barge,
Hauling and Placing in Storage - Review of Implementing Procedures
The following procedures were received from the licensee for Region
III office review on September 14, 1978.
Procedure
Revision
Approval
Number ___
Number
Date
Description
101
2
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Unloading a Reactor
Vessel from a berge, haul-
ing and placing in storage.
103
1
9/11/78
Cantilever gantry
crane.
105
1
Unloading the upper
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internals from a barge,
hauling and placing
in storage.
106
1
Unloading the Reactor
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head from a barge, hauling
and placing in storage.
107
2
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Load test of haul road
and transport trailer.
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108
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420 ton load test.
Procedur- specification numbers 1, 2, 3, 4, and 5 all Revision 0
approved on September 5, 1978, titled Prequalified Joint Welding
Procedure were also supplied for review.
The RIII review of the above procedures was completed on September 15,
1978.
Comments regarding the above procedures were telep? ned to
the UE Qaulity Assurance Group Leader on the same day.
One of
the comments provided to Union Electric suggested that the results
of inspections performed at the site should be available to the
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licensee, this was not clear as written in the Procedures.
The
Procedures were revised an' addendum I was added to include a statement
that "All inspection documentation will be forwarded to Daniel Inter-
national Corporation for their review and Quality Assurance documentation."
The addition of the above sentence to the Procedures satisfied the RIII
concern. The following list of approved Procedures were provided to the
RIII inspector on October 3, 1978.
Procedure
Revision
Approval
Number
Number
Date
Description
101
2
9/21/78
Unloading a Reactor Pressure
Vessel from a barge, hauling
and placing in storage. With
Addendum 1 and 2.
103
1
9/11/78
Cantilever gantry crane. With
Addendum 1, dated September 27,
1978.
105
2
9/15/78
Unloading the upper internals
from a barge, hauling and
placing in storage. With
Addendum 1.
106
1
9/21/78
Unioading the reactor head
from a barge, hauling and
placing in storage. With
Addendum 1 and 2.
107
2
9/15/78
Load test of haul road and
transport trailer.
108
1
9/15/78
420 ton load test.
With
Addendum 1.
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109
0
9/26/78
Upending the upper internals,
removing them from shipping
stand and setting them in
storage. With Addendum 1.
110
0
9/19/78
Mobile crane test.
With
Addendum 1.
The above Procedures were reviewed and appeared to be consistent with
requirements.
During this inspection the RIII inspector did witness part of the load
test of the haul road and the transport trailer.
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The 420 ton load test occurred on September 25, 1978, when 859,986 pounds
were lif ted, which is approximately 430 tons.
430 tons is approximately
115% greater than the heaviest lif t that will be made which is the lif t
of the Steam Generators which weigh approximately 373.4 tons including
all of their rigging. The Reactor Pressure Vessel (RFV) and its
associsted rigging weigh approximately 356 tons.
The Reactor Pressure
Vessel was lifted from the barge and placed on the transporter on
October 9, 1978. The RPV was then transported from the barge area to
the storage area on October 10, 1978.
No items of noncompliance or deviations were identified.
(483/78-10-01)
2.
Site Tour
During the site tour the following item we; identified.
A large quantity
of E7018 weld rod stubs were found in the stiffener channels that are
attached to the liner plate ir the area of the 14th lift of the contain-
r rt exterior wall. Weld rod stubs should be put in stub containers
and not left in the area where the welding is occurring, which would
leave the possibility that they could be reused.
Paragraph number 3.16 of Work Procedure number WP-503, Control of
welding consumables, dated May 5, 1978, Revision 6 states in part
" Loose electrodes and filler wire shall not be lef t lying around but
shall be contained in a portable container or a weld pouch."
Inner
office memo CM-450 dated June 9, 1977, from the Welding Superintendent
to All Superintendents and Welders on the subject of Rules for
Welding Control states in part " Weld rod stubs shall be put in stub
cont iners and emptied in a trash container at the end of the st'ft."
This is an item of noncompliance with 10 CFR 50, Appendix B,
Criterion V.
(483/78-10-02)
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Section II
Prepared by K. R. Naidu
Reviewed by R. L. Spessard, Chief
Engineering Support Section 1
1.
Observation of Installation of Cable Tray Supports
The inspector observed work performance on partially completed work
and completed work on the cable tray supports identified as 4J1D20,
IU1B22 and 4JLA13-1 in the control room building at elevations
1984'-0", 2000'-0" and 2016'-0" respectively and determined that
work and inspection requirements were met in the following areas.
a.
Specified materials were used.
b.
Installation of the cable tray supports were in accordance
with Raceway Plan Control Room Building drawing - E-0R3211(Q),
E-0R3311(Q) and E-OR-3411(Q) for elevations 1984'-0", 2000'-0"
and 2016'-0" respectively.
c.
Qualified inspectors perfort'd the inspections.
d.
Records were legible and retrievable.
e.
Visual inspections were being performed.
No items of noncompliance or deviations were identified in the
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above areas.
2.
Observation of Cable Tray Support Welding Activities
The inspector selected the following cable tray supports to ascertain
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whether the attachment welds were in conformance with the relevant
drawings:
At Elevation 1984'-0"
Cable Tray Support
Drawing
Detail
4J1A 13-1
C-0401
9
4J1A 13-2
C-0401
11
C-0402
8
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At Elevation 2000'-0"
Cable Tray Support
Drawing
Detail
IUlB22
C-0409
9
C-0401
10
IJ1C35A
C-0401
19
C-0402
8
IJ1C35B
C-0401
19
C-0402
8
At Elevation 2016'-0"
Cable Tray Support
Drawing
Detail
4J1D20
C-0401
12
C-0401
4
2J1A10
C-0405
10
C-0401
12
IJ1Dll
C-0401
4
C-0401
12
1J1D20
C-041s
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The inspector determined that size and location of the welds
conformed to the drawings. The length of the weld on one side
was longer than specified by 2 inches. For example, drawing
C-0404(Q) titled " Typical Details Cable Tray Supports". Sheet
No. 4 in detail 16 requires a Unistrut type P1357 bracket to
be welded with a 3/16" size weld 1 1/2" long r.a three sides.
The dimensions of the bracket sides are 1 1/2" X 1 1/2" X 3 1/2".
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The licensee agreed with the inspector that althe .rh the additional
reinforcement on one side is not detrimental, the we:d should con-
form to the drawing requirements. The licensee stated they had
verbally appraised the A/E of this apparent discrepancy but had not
received any clarification to date
The inspector informed the
licensee that this matter is con 4 ered an unresolved item until
the clarification provided by the A/E is reviewed and determined
acceptable.
(483/78-10-03).
No items of noncompliance or deviations were identified in the
above areas.
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3.
Review of Cable Tray Supports Welding Quality Records
The inspector reviewed the Quality Records documenting the inspec-
tions on Cable Tray Supports welds listed in paragraph 2 and
determined that the applicable inspection requirements were met in
the following areas
a.
Weld Procedure Specifications (WPS) #N-1-1-A-12 dated June 10,
1978, Revision 1 and N-1-1-A-13 dated June 10, 1978, Revision
1, were used where applicable,
b.
Electrodes type E7018 were used.
c.
The welds were visually inspected by qualified inspectors to
AWS D1.1-75 requirements,
d.
Periodic checks of the current were made to determine that the
current was within the range specified in the WPS.
e.
Surveillances documented the serial number of the portable
weldrod even used to establish that only approved weldrod was
used to perform welding.
f.
Inspections were documented on Welding Surveillance reports
instead of separate welding inspection reports, as described in
t'.e procedure QCP 507. The licensee agreed to review this
matter in order to resolve this inconsistency.
The inspector
informed the licensee that this matter is considered an
unresolved item and that action taken will be reviewed during
a subsequent inspection (483/78-10-04).
No items of noncompliance or deviations were identified in the
above areas.
4.
Review of Containment Structural Steel Welding Records
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The inspector observed welding activities relative to the installation
of Reactor Refuelling Canal (RRC) Liner plates. Discussions with the
licensee and DI personnel indicate that the installation of the
Stainless Steel Liner plates to the seismic Category 1 RRC concrete
structure was not considered 'Q'
listed, and thus safety related only in
those sections where the liner plate is attached to the seismic
Category 1 embedcent by welding. Horizontal and vertical seam
welds attaching liner plata to liner plate were not considered
safety related and were being performed by Alberici, a subcontractor
without a QA program. Further discussions with Alberici personnel
indicate that the liner plates are welded by automatic machines.
The final welds are subjected to Penetrant Examination by an
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independent testing agency, namely Pittsburgh Testing Laboratories
(PTL). The inspector did not review the records generated by Alberici
since the work performed was not considered safety related by the
A/E. This matter is considered unresolved and is being forwarded to
IE:
Headquarters for resolution.
(483/78-10-05).
The inspector selected Field Welds (FW) #1, 2, 3 and 4, identified
on drawings C-0L-2922(Q) Revision 7 and C-OL-2931, and reviewed the
relevant documentation.
These welds attach liner plate cut-out
sections, to which embeds identified as 64PSA and 64PSB were welded,
to the liner plates installed in the RRC.
The inspector determined
that the records reflect work accomplishment consistent with applicable
requirements in the following areas:
a.
Inspections were documented in the Weld Control Record.
b.
Preheat temperature was specified as 60 F and was verified.
c.
Fit up was checked.
d.
Weldrod withdrawal was identified.
e.
Welding Procedure #N-8-8-A6 was specified,
f.
Weldors were identified; qualification records indicate that
they were qualified.
g.
Visual inspections were performed on the completed welds,
h.
The welds were subjected to Liquid Penetrant (PT) examination.
Records indicate that the welds FW2, FW6, FW4 were examined
according to DI Magnetic Particle procedure 7.3C Revision 1,
utilizing dye penetrant type SKL-5, developer type SKD-5 and
cleaner type SKC-5 all manuf actured by Magnaflux.
The dwell
,
time was ten minutes, drying time was five minutes, and developing
time was seven minutes. The weld was sprayed and wiped clean.
No unacceptable indications were identified.
1.
Records of the Level II NDE inspectors indicate that they are
qualified.
j.
Records were legible end retrievable.
No items of noncompliance ce deviations were identified in the above
areas.
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5.
Observation of Safety Related Structures Work Activities
The inspector observed steel columns 3C2AD and SC4AD, identified
on A:oerican Bridge drawing #K6726E2, in the Emergency Diesel
Generator Building. The columns had been erected, and during a survey,
it was determined that the base plates of the column was 3/8" lower
than specified in the drawing. Corrective action recommended
and approved was to raise the base plate 3/8" by placing grout
underneath it.
The inspector determined that inspection require-
ments were met in the following areas:
a.
Material Control Report (MRC) 02574 identifies that the material
was received without shipping damage.
Bechtel C 321-D Form
indicates that the necessary shop inspections were performed.
b.
Installation was to Bechtel drawing #COS 5211 Revision 1.
c.
Specified materials were used.
d.
Inspections of the instellation were documented in Structural
Steel report dated July 20, 1978.
The inspector observed that the splices between columns 727C7J1A and
614C7J1A and 702C6JA and 601C6JA had been identified with a noncon-
formance report (NCR) tag 2-3772-C-A.
The columns are installed in
the auxiliary building at elevation 2002'0".
Review of NCR 2-3772-C-A
dated September 6, 1978, indicates that the columns do not have
bearing contact on milled surfaces at the splice connection due to
misfabrication.
Corrective action recommended was to enlarge the bolt holes on columns
727C7J1A by 3/32" and column 702C6JA by 1/8" utilizing a magnetic drill.
Corrective action had not been completed.
The NCR was legible and
retrievable. The inspector has no further questions on this matter
at this time.
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No items of noncompliance or deviations were identified in the above
areas.
6.
Observation of Reactor Building Interior Concrete Structures
The inspector observed several areas on the Reactor Building interior
walls which exhibited inadequate consolidation. The licensee informed
the inspector that NCR 2-3950-C-A documents these areas as non-
conforming. The NCR identifies voids in pour Nos. 2C231W32, 2C231W24,
2C231W27, 2C231W34, 2C231W31 and 2C231W35. Corrective action
recommended to repair the voids appeared to be adequate.
Supervision
was informed of the contents of the NCR to prevent recurrence. The
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inspector stated that it was not clear whether the supervision in
turn passed the coments to the craf t personnel who use the vibrators.
The DI personnel stated that when the trend persists they indoctrinate
the craft personnel and agreed to document in the NCR the instances
when training sessions were held. The inspector has no further
questions on this matter at this time.
No items of noncompliance or deviations were identified in the above
areas.
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Section III
Prepared by J. C. Mattia (Region I)
Reviewed by R. W. McCaughy (Region I)
Licensee Site Audits
The inspector reviewed various licensee's audits of the site constructor
to verify the following:
Audits were scheduled and conducted.
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Scope of Audits were consistent with the purpose stated.
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Appropriate standards were referenced for measuring performance.
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Audited organizations received copies of audit reports.
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Audited organizations provided timely response to audit findings.
Appropriate corrective action was taken and timely followup
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action, including re-audit of deficient areas.
The licensee's audit schedule and the following audit files, which included
audit reports, checklists, audit plans, action letters, response letters,
response evaluation letters, pre and post audit conference documents for
a specific audit were reviewed:
Audit Date
Type of Audit
.
June 22-28, 1977
Material, Receiving, Storage and
Processing
April 20-20, 1977
Material Processing Facility
- May 12-13, 1977
Field Engineering (Survey)
- September 7-13, 197~
Records Management System
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- April 13, 1977
Civil Laboratory
- June 19-23, 1978
Appendix B Critaria II, XVI,
c.nd XVII
- July 17-21, 1978
Appendix B Criteria IV, VIII,
XIII and XV
September 11-12, 1978
Subcontractor for Reactor
Pressure Vessel Lift
The inspector did determine from his review of the above eight audits and
associated dccuments that the licensee was complying with the audit require-
.
ments, except in one area. For five of the eight audits reviewed the
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inspector determined that the constructor (Audited Organization) did
not respond within the required time.
The IE inspector pointed out that
ANSI N45.2.12 paragraph 4.5.1 requires that the Audited Organization review
and investigate adverse audit findings and respond to the audit report
within thirty days after receipt, giving results of the review and investi-
gation. Also, UE QA Procedure QA-106 Revision 5, paragraph 5.3.4 requires
that responses to audits, where corrective action is indicated are to be
submitted within thirty days after receipt of the audit report.
The
audits denoted above with an asterick are the audits that have exceeded
the thirty day requirement by ten to thirty-four days.
This item is considered an item of noncompliance with 10 CFR 50,
Appendix B, Criteria V (483/78-10-06).
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Section IV
Prepared by C. R. Oberg (Region IV)
Reviewed by W. A. Crossman (Region IV)
Safety Related Components - Review of Quality Assurance Implementing Procedures
The IE inspector reviewed the procedures listed below as they pertain to
safety related components and their inspection, installation, and maintenance.
The following procedures were reviewed:
AP-IV-01
Material Control Functions, Revision 3 (August 9,1978)
AP-IV-09
Storage and Maintenance, Revision 0 (September 18, 1978)
AP-VII-07
Material and Equipment Receiving and Inspection,
Revision 1
(December 5, 1977)
AP-VII-09
Material and Equipment Storage and Handling, Revision 1,
(January 11, 1978)
AP-IX-05
Material Storage and Control, Revision 5 (March 24, 1978)
WP-114
Rigging, Revision 3 (June 6, 1978)
WP-210
Installation of Mechanical Equipment
QCP-210
Inspection of Installation of yechanicalEquipment,
Revision 2 (October 10, 1978)
WP-305
Installation of Electrical Equipment, Revision 1
(June 26, 1978)
QCP-ll4
Inspection of Material / Equipment Rigging and Handling,
Revision 0 (July 25,1977)
QCP-305
Inspection of Electrical Equipment Installation,
Revision 1 (July 14,1978)
Interim Changes:
AP-VII-09
ICP-1
Revision 0
September 18, 1978
AP-IX-05
ICP-1
Revision 0
September 18, 1978
AP-IV-09
ICP-1
Revision 0
September 29, 1978
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AP-IV-09
ICP-2
Revision 0
October 3, 1978
AP-IV-01
ICP-1
Revision 0
September 18, 1978
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The inspector determined that the requirements of ASNI N45.2.2 - 1972, and
the referenced standards therein, have been included in the above procedures.
Specifically,
1.
Receipt inspections determine that components are undamaged, are in
conformance with purchase specifications, and are properly identified.
Receipt inspection reports are required.
1/ Issued October 2, 1978.
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2.
Installation, testing and inspection activities are in accordance
with specifications and are to be done in accordance with written
procedures. Storage levels are determined in accordance with speci-
fication and procedure requirements.
3,
Handling equipment and crane lifting requirements have been established
and appropriate tests are required prior to special lifts.
4.
Post installation (storage in place) inspect *on and preservation
requirements are established prior to need and are adequately controlled
by procedures.
No items of noncompliance or deviations were identified.
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 Section II, paragraphs 2, 3 and 4 of the
Details Section of this report.
Exit Meeting
.
The inspectors met with site staff representatives (denoted in the
Persons Contacted paragraph) at the conclusion of the inspection on
October 4, 1978. The inspectors summarized the scope and findings of
the inspection, including the two apparent items of noncompliance
identified in Section I, paragraph 2 and Section III of the Details
Section of this report.
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