ML20150B637
| ML20150B637 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/20/1978 |
| From: | Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20150B640 | List: |
| References | |
| 50-364-78-12, NUDOCS 7811020360 | |
| Download: ML20150B637 (5) | |
See also: IR 05000364/1978012
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UNITED STATES
NUCLE AR REGULATORY COMMISSION
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Rem rt No.:
50-364/78-12
' Docket No.:
50-364
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License No.:
CPPR-86
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Category:
A-2
Licensee: Alabama Power Company
Post Office Box 2641
Birmingham, Alabama 35291
Facility Name- Joseph M. Farley Plant, Unit 2
Inspection at:
Ashford, Alabama
Inspection conducted:
September 5-8, 1978
Inspector:
P. K. VanDoorn
Reviewed try:-
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T. E. Conlon, Chief
Date
Engineering Support Section No. 2
Reactor Construction and Engineering
Support Branch
Inspection Summary
Inspect ion on September 5-8, 1978 (Report No. 50-364/78-12)
Areas inspected:
Routine unannounced inspection of safety related piping
work activities and quality records; reactor coolant pressure boundary piping
quality records; safety related structures quality records.
The inspection
involved 25 inspector-hours on site by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
781102o36o
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R11 Report No. 50-364/78-12
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DETAILS I
Prepared hy: '/
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P. K. VanDoorn, tietallurgical Engineer
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Engineering Support Section No. 2
Reactor Construction and Engineering
Support Branch
Dates of Inspection:
September 5-8, 1978
Reviewed by _ -8
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T. E. Conlon, Chief
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Engineering Support Section No. 2
Reactor Construction and Engineering
Support Branch
1.
Persons Contacted
a.
Alabama Power Company (APCO)
- J. A. Mooney, Project rianager, Const ruction
- R. E. Hollands , QA Supervisor
- J. C. Payson, QA Staff Engineer
- R. S. Fucich, QA Engineer
- J. G. llegi, Project QC Engineer
hD. B. Hartline, QA Engineer
b.
Cont.ractor Orjaniztion
Dainel Construction Company (DCC)
kl. F. Warrick, Construction Manager
hL, C. Easterwood, QC Manager
kF. L. Thomas, QA Engineer
B. B. Marchman, QCDS Supervisor
S. King, QCDS Engineer
L. T. Chandler, QCDS Engineer
hDenotes those present at the exit interview.
2.
Licensee Action on Previous Inspe_ction Findi_ngs
(0 pen) Unresolved Item (364/78-09-01):
Verification of Anchor Bolt
Lengths.
This item was originally iaentified en June 23, 1978.
It
concerned establishment of a measurement based system to provide
verification of the proper length of anchor bolts.
The inspector
reviewed actions which had been completed to date
DCC has randomly
ultrasoncially tested 104 previously installed anchor bolts and has
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Rll Report No. 50-364/78-12
1-2
identified four bolts of improper length, all associated with large
hangers.
Statistical analysis is sti]] in progress to determine the
number of additional bolts to be tested.
In addition to the above a program for testing of all newly installed
anchor holts was initiated on July 17, 1978.
No lengt h deviations
have been identified to date as a result of this program.
This item
will be reviewed in detail at a later date.
3.
Unresloved items
No unresolved items were identi fied during this inspection.
4.
Independent inspection Effort
The inspector conducted a general walk-through inspection of the
a.
containment and auxiliary buildings to observe construction pro-
gress and general construction activities such as welding, material
handling, housekeeping and storage,
b.
The applicable code for installation of safety related piping is
the ASME Boiler and Pressure Vessel Code, 1971 Edition plus
addenda through the summer of 1971. The inspector observed
safety related piping installation activities to determine if
Code, NRC and SAR requirements were being met.
Activities observed
included weld preparation of steam generator No. 2 outlet, heat
treatment of main steam system weld numbers FW 50571 and FW
50572, and fit up of auxiliary feedwater syster weld number 2F
and 7F.
No items of noncompliance or deviations were identified.
5.
Re actor Coolant Pressure Boundarv Pip _ing,_ Review of Quality Records
The applicable Code for reactor coolant pressure boundary piping is
the ASME Boiler and Pressure Vessel Code, Section 111, 1971 Edition
plus addenda thrcugh the summer of 1971 for installation, and various
editions and addenda for the purchase of material dependent upon the
purchase date
The inspector re"iewed quality records to determine if
Code, NRC and SAR requirements were met.
Installatica records were
reviewed for the following spools:
Spool No.
Size
System
E21-CCA-27-4
6"
Safety injection
E21-CCA-27-6
6"
Safety injection
E21-CCA-27-9
6"
Safety injection
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Ril Report No. 50-364/78-12
1-3
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Ell-CC-22-5R
8"
B13-CCA-10
27.5"
B13-CCA-12
31"
B13-CCA-11
29"
E11-CCA-22-5
8"
. . .
E21-CCA-26
3/4" and 2"
Safety injection
Additional records were reviewed for the first six spools listed above
and included, as applicable, material test reports / certification
records, vendor shop manufacturing and NDE records NSSS quality release
'
forms, and receiving inspection reports.
General Class 1 piping
,
,
storage recerds were reviewed for January through July of 1978.
APCO
QA audits of October 14, 1977 concerning piping storage and November 11,
1977 concerning; pipe cleaning were also reviewed.
No items of noncompliance or deviations were identified.
6.
Reactor Coolant Pressure Boundary Piping (Welding) - Review of Quality
Records
^
The applicable Code for installation of reactor coolant pressure
..
boundary piping is delineated in paragraph 5.
The inspector reviewed
welding quality records to determine if Code, NRC and SAR requirements
were met.
Records were reviewed for the following welds:
Weld No.
Size
'
FW-5
6"
.
FW-6
6"
FW-10
8"
FW-11
8"
7F
27.5"
8F
27.5"
Areas reviewed included inspection records covering visual and dimen-
sional inspections, weld hist.cy records, NDE records, weld repair
records, welding material cont rol records, welder qualification records,
and inspector qualification records.
The inspector also reviewed six
noncomformance reports relative to reactor coolant pipe
No items of noncompliance or deviations were identified.
7.
Safety Related St ructures (Welding) - Review Of _quali_ty_ Rec.ords
, ,
The inspector reviewed QA audits and nonconformance report s (NCR'S) in
the area of welding of saf et y related st ructures to determine if
records were complete, legible, retrievable, properly closed out and
that adequate and timely corrective actions had been taken.
Specifscally
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Rll Report No. 50-364/78-12
1-4
reviewed were the APC0 audit of April 21, 1978 concerning modifications
to the Reactor Makeup Water Tank and Condensate Storage Tank, the APCO
audit of June 30, 1978 concerning MT inspection of whip restraint
welds, and 12 NCR's numbered Q2W-14, 16, 31, 33-35, 39-43, and 70.
No items of noncompiance or deviations were identified.
8.
Safety Related Piping - Review of Quality Records
The applicable Code is delineated in paragraph 4.b.
Installation
records such as checklists, isometrics, inspection, records cleanliness
records, and records of qualification of inspection personnel were
reviewed for 10 pipe spools to determine if Code, NRC and SAR requirements
were met.
Specific pipe spools reviewed were E11-ECB-28-1, -2M1,
-3,
and -4; E13-HCB-53-4,
-5,
-6, and -7; and E13-HCB-78-1 and
-2.
No items of noncompiance or deviations were identfied.
9.
Safety Related Piping - Observation of Work and Work Activities
The applicable Code is delineated in paragraph 4.b.
The inspector
observed handling of feedwater system spool No. N21-DBB-1-1 for confor-
mance with work performance procedures and construction specifications.
No items of noncompliance or deviations were identified.
10.
Exit Interview
The inspector met with license representatives (denoted in paragraph 1)
at the conclusion of the inspection.
The inspector summarized the
scope and findings of the inspection.
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