IR 05000325/1973006
| ML20044C491 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/26/1973 |
| From: | Crossman W, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20044C467 | List: |
| References | |
| FOIA-92-569 50-325-73-06, 50-325-73-6, NUDOCS 9303230130 | |
| Download: ML20044C491 (5) | |
Text
..
,...
.
.
.
. -..-
~.
...
-
.-
.3-
~
.f
' e'*
%
UNITED STATES
!
+
9 #g ATOMIC ENERGY COMMISSION
! i.gh *
!
DIRECTORATE OF REGUIATORY OPERATIONS-l g'$
/,, -
.y REGION ti - SutT E 818 t
l
2M PE ACHT R EE-ST RE ET. NORT MwEST
- 147gs 0%
,
g,.
ATL4NTA.GEoRGaa 30303
)
i
!
i
!
RO Irspection Report No. 50-325/73-6
'
.,
t
Licensee: Carolina Power and Light Company
336 Fayetteville Street
Raleigh, North Carolina 27602
.i Facility Name:. Brunswick 1 l
Docket No.:
50-325
'
License No.:
CPPR-68 Category :
A2 l
t i
Location: Southport, North Carolina
(
)'
Type of License:- 821 Mwe, BWR, G-E j
l Type of Inspection: Routine, Unannounced, Construction i
>
'
t Dates of Inspection: October 2-5, 1973
!
!
Dates of Previous Inspection: September 11-13, 1973 Inspector-in-Charge:
W. D. Kelley, Reactor Inspector-i Engineering Section, Facilities.. Construction Branch
Acconpanying Inspectors: None i
-!
Other Accompanying Personnel:
.J.
C. Bryant, Senior Inspector
!
Engineering Section, Facilities i
Construction Branch, October 4,5 only i
.
Principal Inspector:
-
I]
A#-l(97
.-
C. R. McFarland, Reactor Inspector Date i
Facilities Section,' Facilities Construction Branch.
..
i
!
Reviewed'6y:s
- T W
/d
-
'
'
g W. A'~ Grossman, Senior Inspector, Facilities Section
'Dats i
.
Facilities Construction Branch t
i
- !
!
I r
'
i'I e
--
t i
'
t O'fEALI92-569 '. PDR I
'
..
.
... _
-
,
,
.,, - ~. <,
. -.,.,
-
. _.,,
-
... "
'
.
_ -. _ _.
_
.:
.
,
,
RO Rpt. No. 50-325/73-6-2-i
,
SUlt4ARY OF FINDINGS
,
1.
Enforcement Action A.
Violations j
None B.
Safety Items
!
None II.
Licensee Action on Previous 1v Identified Enforcement Matters A.
Violations None
'
B, Safety Items t
None
,
.
'
III. New Unresolved Items None IV.
Status of Previous 1v Reported Unresolved Items At the conclusion of this inspection, three items remain unresolved.
73-3/2 Piping Documentation
?
The licensee and Brown and Root, Inc. (B&R) are auditing all completed weld joints to insure that complete documentation
,
exists for each weld joint. The licensee has revised quality j
control procedure F-33, " Control of Welding and Associated -
Procedures," to insure closer control and to prevent lost
documentation. This item remains open.
!
- l 73-3/5 NDT Personnel Oualification Procedures
!
B&R has issued NDT procedures, " Personnel Qualification and Certification Policy" and " Personnel-. Training, Qualification.
!
and Certification Procedure No.1".
This item is closed.
'
t 73-1/1 Verification of Nuclear Valves to Design Specifications (RO:11
'
Letters Dated June 30, 1972 and February 16, 1973)
t The licensee has not completed his program of measurement of all-
.
valves.
Item remains open.
(Details 1)
,
".
4,
.
...
._=
-
.
.
-
.
...
RO Rpt. No. 50-325/73-6-3-
,
f 73-1/2 Limitorque valve Operator Failure (RO:II Letter Dated December 4, 1972)
'
t Site corrective work by Limitorque and Carolina Power and Light Company (CP&L) continues.
Item remains open.
V.
Design Changes I
None VI. Unusual Occurrences None
VII. ' Other Significant Findings N. J. Chiangi has been employed by CP&L as QA Manager, Construction.
VIII. Management Interview The inspectors met with G. M. Simpson, CP&L QC Specialist, Raleigh, to appraise him of the general areas of inspection and findings as noted in this report.
,
I J
a f
.
k
k
9 I
.
',
b
-
i
.!
-
'
i
'
e,
-,
.
...
.
. -
.
_
.
.
. -
-
.
-
.
RO Report No. 50-325/73-6 I-1 DETAILS I Prepared by:
J
./
/
- ' /
/6"/f'[3 W.
D.' Kelley, Reactor Ipspector Date Engineering Section Facilities Construction Branch
Dates of Inspection: October 2-5, 1973 Reviewed by:
56_b
///MN I J. t. Brysnt, Senior Inspector Date
, Engineering Section Facilities Construction Branch 1.
Persons Contacted a.
Carolina Power and Light Company (CP&L)
F. R. Coburn - Project QC Specialist R. G. Strickland - QC Specialist (Mechanical)
b.
Contractor Organizations
Brown and Root, Inc. (B&R)
i W. L. West - QA Manager R. A. Slater - QA Receiving and Release Inspector 2.
Verification of Nuclear Valves to Design Specifications CP&L has not completed preparation of their valve wall thickness verification program for Brunswick Units 1 and 2.
The inspector reviewed with CP&L the valve wall thickness verification requirements of RO:Il letters of June 30, 1972, and February 16, 1973.
The license stated that the program would be completed and made
-
available to the inspector on a subsequent inspection.
The program will include the following steps.
t a.
The list of valves requiring wall thickness verification will be
'
sent to CP&L-Engineering for review and verification that it contains all reactor coolant pressure boundary valves greater than 1 1/4 inches in size in water lines and greater than 2 1/2 inches in steam lines.
t b.
The ultrasonic wall thickness verification procedure vill be revised to include inaccuracy of measurements of nonparallel
i.
!
i e
i
.
-
.
.
.
._
.
'
.
. -
.
..
,
RO Report No. 50-325/73-6 I-2
,
surfaces plus a more detailed description of number and location
,
of wall thickness verification measurements to be made based on
!
minimum wall thickness as well as valve size.
!
c.
The method and accuracy of valve wall thickness verification by mechanical means will be described and included in a procedure.
d.
The documentation of the thickness verification measurements will be reviewed by a person knowledgeable in valve manufacturing i
to determine that it is adequate for verifying that the valve
,
meets the purchase specification as amended by 10 CFR 50,
paragraph 50.55(a), " Codes and Standards."
,
h
!
i
,
,
D f
t
!
i
I
l
,