ML20107G729
See also: IR 05000219/1975015
Text
-
,.
,
,
~
a
,,
.
IE'1' Fora 12
-
(Jan 75) (Rev)
'
,
.
I
U.S. NUCLEAR REGULATORY COMMISS. ION
OFFICE OF INSPECTION AND ENFORCEMENT
..
. REGION I
Q
.
,
50-219/75-15
Docket No: 50-219
IE Inspection Report No:
Licensee:
Jersey Central Power & Light Company
License No: DPR-16
Madison Avenue at Punch Bowl Road
Priority:
N/A
C
Morristown, New Jersey 07960
Category:
'
_
.
Location:
Forked River, New Jersey
(Oyster Creek)
Safeguards
!A
Group:
,,
Type of License:
.
.
Type of Inspection:
SPecial - Announced
$$
Dates of Inspection: May 21-22, 1975
$N
May 5-9, 1975
Dates of Previous Inspection:
'b
. d rdtecke% edacIst d% J,.,_
% to _ i c,7g-
. Reporting Inspector:
4 Date
'
E. P. Jerniga'n,' Reactor Inspector
Accompanying Inspectors:
nnn,
Date
.
Date
-
.
Date
-
-
.
Date
,
Other Accompanying Personnel: None
Date
M b /WT
Reviewed By:
- ~
.
'
/ Date
'R. C. Haynes,
eactor Inspector
.
,
,
'
/
f
9604230322 960213
4
DEKOK95-258
i
e
. , . - - . - .
. .. .
. - - - . . - .. -. -. .- .
. _ _ _ . - - . . ,-
. . .
_
' '
. . .
.
.
- -
!
'
.
t
. .
,
T
v
~
SUMMARY OF FINDINGS
'
,
Enforcement Action.
A. . Items of Noncompliance
,
,
None
B.
Deviations
None
-
Licensee Action on Previously Identified Enforcement Nhtters
.
Not inspected.
<
,
Design Changes
,
!
- Not inspected.
- Unusual Occurrences
,
None' reported.-
1
)
(2Ai
Other Significant Findings
A.
Current Findings
1.
Acceptable Areas
,
a.
Valve Wall Thickness Verification Program
'
i
The valve wall thickness verification program required by the
RO:I letter of June 22,-1972 is approximately 52% complete.
'
The documentation for that part of the program which has been
.
completed was inspected and was found to be acceptable. The
documentation reviewed by the inspector included the following:
1.
Procedure NSD-V-3-010, Rev. O, dated February 1, 1973.
'
2.
Personnel Qualifications.
i
3..
Data of Completed Valves.
'
<-
4.
Wall Thickness Data of.22 Safety Relief Valves.
~
~
(Details, Paragraph 2)
'
.
S
t
!
\\
r +,
'1
.
'
\\' t '
,
,
,.
.
,
,
.
.
-2-
2.
Unresolved Item
- 9-
a.
Scope of Valve Wall Thickness Verification' Program
.C
The scope of valve wall thickness verification program established
by the licensee is based on a sample number of valves. The in-
spector informed the licensee that all of the valves designated in
the RO:I letter of June 22, 1972 were to be inspected. This item
is considered to be unresolved.
(Details, Paragraph 3)
B.
Status of Previous Unresolved Items
The unresolved item listed below has been resolved.
1.
Ultrasonic and eddy current inspection data as originally reported for
,
repairs to in-core housing weld No. 28-05.
(Ref. IE:I Inspection Report 50-219/74-12)
(Details, Paragraph 4)
Management Interview
A management interview was held at the site on May 23, 1975 with the following
(;gg
attendees:
Jersey Central Power & Light Company
D. Ross, Manager, Generating Stations-Nuclear (telephone contact only)
D. Reeves, Chief Engineer
R. Swift, Maintenance. Engineer
~
J. Carroll, Plant Superintendent
Items discussed are summarized below:
A.
Purpose of Inspection
The inspector stated that the purpose of this inspection was to audit the
licensee's compliance with valve wall verification requirements outlined
in the RO:I letter dated June 22, 1972.
In addition, this inspection included a review of test data and the licensee's
evaluation of this data with respect to repaArs performed on in-core housing
28-05 as previously reported in RO:I Inspection Report No. 50-219/74-12.
B.
Valve Wall Thickness Verification Program and Scope of Program
The items discussed are as identified under Current Findings in the Summary
'
'
'i
of Findings of this report.
(Details, Paragraphs 2 and 3)
-
- -
. -
- -
-
. -
-
.-.
-
.
-
..
-
.
.
,.
.
.
,
-3-
C.
Review of Previous Unresolved Items
.
'f j
The item discussed concerned the review of certain nondestructive
%g@
examination data and the licensee's evaluation'thereof of tests
associated with repairs to in-core housing 28-05. This item is
"'
considered to be resolved.
(Details, Paragraph 4)
,
g f.+
'-.g
't
kN!,!
W:::
.M*
.
i
l
, . ;,;.
b '
q
t
WF $
- n <n
s
.
4
'
-
__
. ._
.
' ' '
. . .
%
.
.
,
DETAILS
k
.
1.
Persons Contacted
- ,
,
7,
'
Jersey Central Power & Light Company
J. Carroll, Plant Superintendent
D.
Reeves, Chief Engineer
R. Jacobstein, Project Engineer
R. Swift, Maintenance Engineer
2.
Valve Wall Thickness Verification Program
a.
Procedure Review
.
The inspector reviewed the licensee contractor's procedure,
NSD-V-3-010, Rev. O, dated February 1, 1973.
The procedure,
Ultrasonic Wall Thickness Measurement of Nuclear Piping System
Valves, reflected those parameters necessary to obtain required
<
results.
b.
Personnel Qualifications
The inspector reviewed the contractor's personnel certificates of
qualifications of all inspectors making valve wall thickness measure-
.
OE6N
ments and were in compliance with the requirements of referenced
standard, SNT-TC-1A.
c .- Data Review
The inspector audited the valve wall thickness measurement data of
the 43 completed valves.
All data had been evaluated and accepted
by the licensee.
,
The data supplied and evaluation results appeared to be sufficient in
content and detail.
d.
Reactor Safety Valves
The inspector reviewed the mechanical wall thickness measurement data
4
of the 22 safety valves, including 6 spare valves.
Valve design precludes the possibility of ultrasonically measuring the
wall thickness of the pressure boundary portion of the valve. The
i
pressure boundary of these valves are machined nozzles which are
,
fabricated to closely controlled tolerances to permit assembly. After
disassembly, nozzles of 5 valves were checked by the licensee for
compliance to detail design requirements and were found to be within
drawing tolerances. The remaining 17 valve nozzles were checked
assembled and they were deemed to meet design requirements.
The
,
. -
- . .
-
.
_ - . ..
.
'
-
.
.
'
e
.
.
,
-5-
inspector reviewed the nozzle measurement data and found the data
met specification requirements.
,
fj
3.
Scope of Valve Wall Thickness Verification' Program
The licensee's valve wall thickness verification program is comprised of
a total of 73 valves, exclusive of the reactor safety valves. The scope
of the licensee's program was to inspect a representative sample of each
type of valve as stated in their letter to the Regional Office, dated
July 21, 1972. The licensee was informed by the inspector that.all of-
the valves designated in the RO:I letter, dated June 22, 1972 were to
be inspected to meet the intent of this verification program.
This item is considered to be unresolved pending completion of the_ wall
thickness verification program for the remaining valves. The licensee's
program for the verification of the wall thickness of the 22 reactor
safety valves is considered to be complete and meets the intent of the
R0:1 letter.
,
4.
In-Core Housing 28-05 Repairs
.
1
The inspector reviewed the licensee's letter of September 10, 1974, which
i
clarified the previous ultrasonic report for in-core housing weld No. 28-05.
In addition, a pressure test of this weld was performed during the May 1975
outage and no leakage was observed.
$
The inspector also reviewed the licensee's inspection contractor's formal
evaluation report dated July 30, 1974 with respect to certain indications
found during eddy current tests of the housing. The report stated that
during eddy current testing of the housing tube material, slight pitting
was detected in the tube's I.D. which was less than 5 percent of the tube
wall thickness. The pitting was within acceptable limits according to the
contractor's evaluation report to the licensee.
j
This item is considered to be resolved.
,
9
0
0