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{{#Wiki_filter: | {{#Wiki_filter:g>n paco. | ||
UNITED STATES | |||
* * | |||
* | |||
f | |||
[o NUCLEAR REGULATORY COMMISSION g | |||
!'. | |||
REGION n n | |||
,$ | |||
101 M ARIETTA STRE ET, N.W. | |||
k | |||
ATLANTA, GEORGI A 30303 s... / | |||
} | |||
I f | I f | ||
( | |||
Report Nos. 50-388/82-23, 50-339/82-23 | Report Nos. 50-388/82-23, 50-339/82-23 | ||
: | |||
Licensee: Virginia Electric and Power Company | Licensee: | ||
Virginia Electric and Power Company | |||
P. O. Box 26666 | , | ||
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P. O. Box 26666 i | |||
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Richmond, VA 23262 Facility Name: North Anna Units 1 and 2 Docket Nos. 50-338, 50-339 | Richmond, VA 23262 Facility Name: North Anna Units 1 and 2 Docket Nos. 50-338, 50-339 | ||
! | |||
License Nos. NPF-4 and NPF-7 Inspection at North Anna site near Mineral, Virginia | License Nos. NPF-4 and NPF-7 Inspection at North Anna site near Mineral, Virginia i | ||
' | ' | ||
Inspector: | Inspector: | ||
l | 7 - / 9 - 8 2.-- | ||
F. Jape, Section hief / F | l E. H. Brooks Date Signed l | ||
Approved by u.4dc{ [ | |||
#/d 7/ | |||
F. Jape, Section hief / F Date Signed Engineering Inspection [ Branch | |||
' | ' | ||
Division of Engineering and Technical Programs i | |||
, | SUMMARY Inspection on June 28 - July 2,1982 Areas Inspected | ||
Results Within the scope of this inspection no violations or deviations were | , | ||
This routine, unannounced inspection involved 31 inspector-hours on site in the areas of pipe supports and directional restraints, and types B and C leakage rate j | |||
testing. | |||
; | |||
Results Within the scope of this inspection no violations or deviations were identified. | |||
, | |||
$ | $ | ||
i l | i l | ||
8208160151 820723 PDR ADOCK 05000338 PDR | 8208160151 820723 PDR ADOCK 05000338 G | ||
PDR | |||
-_. _., | |||
__. | |||
_ | |||
_ | |||
., | |||
, | |||
REPORT DETAILS 1. | |||
Persons Contacted Licensee Employees W. R. Cartwright, Station Manager | |||
*E. W. Harrell, Assistant Station Manager | |||
*D. L. Benson, Superintendent Operations | |||
*R. T. Johnson, Quality Assurance | |||
*J. A. Hanson, Jr., Superintendent Technical Services | |||
*J. C. Smith, Engineer Supervisor Performance & Test J. Roth, Engineer, Performance & Test J. Masticone, Operations Coordinator F. Timpano, Engineer Performance & Test | |||
*M. E. Fellows, Staff Assistant | |||
' | ' | ||
NRC Resident Inspector | NRC Resident Inspector | ||
*D. Johnson M. Shymlock | |||
* Attended exit interview 2. | |||
Exit Interview The inspection scope and findings were summarized on July 2,1982, with those persons indicated in paragraph 1 above. | |||
Licensee acknowledged the findings without significant comment. | |||
3. | |||
Licensee Action on Previous Inspection Findings Not inspected. | |||
4. | |||
Unresolved Items Unresolved items were not identified during this inspection. | |||
5. | |||
Inspection of Pipe Support and Restraint Systems The inspector and licensee representative performed an inspection of snubbers installed in both Units 1 and 2. | |||
Approximately 75 snubbers in the main steam valve house, service building, safeguards building and auxiliary feedwater pump house were inspected. | |||
All snubbers appeared to be well maintained, properly installed, and free from " lockup." One snubber in the Unit 2 mechanical equipment room was exposed to high temperature feedwater leaking from feedwater value 2-FW-196. | |||
The water was impinging on the snubber piston rod and seal. | |||
Licensee management was advised of the potential for snubber damage. The licensee was in the process of performing | |||
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. | |||
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_ | |||
. | |||
-. - - | |||
. | |||
-. | |||
_ | |||
.. | |||
. | |||
, | |||
, | |||
' | ' | ||
, | |||
inspection | , | ||
f scheduled snubber inspection and functional testing on Unit 1. | |||
The previous inspection. and functional testing of Unit 1 snubbers was performed during the 1981 spring outage. | |||
The licensee has received an exemption from the requirement to functionally | |||
The most recent inspection and functional testing of Unit 2 snubbers was performed during the 1982 spring outage. | |||
; | |||
Based on technical specifications requirements for augmented inservice | |||
' | |||
inspection, both Units I and 2 are presently on a 12 months 25% subsequent visual inspection period. | |||
Also, the licensee has properly selected for functional testing a representative sample in accordance with the technical | |||
, | |||
specifications requirements for both Units 1 and 2. | |||
l The licensee has received an exemption from the requirement to functionally i | |||
' | |||
test large snubbers greater than 50 KIP around the steam generators and reactor coolant pumps, during the current outage only. These snubbers will be included in representative samples selected for tes *,ing during future outages. Open Items (79-04-02 and 79-04-06) concerning this subject are | |||
- | |||
considered closed. | considered closed. | ||
. | . | ||
Bulletin 81-01 concerns surveillance of mechanical snubbers. The licensee l | |||
has responded to the bulletin, stating that no mechanical snubbers are | |||
' | ' | ||
installed in North Anna Unit 1. | |||
In the area of pipe support and restraint systems no violations or devia-tions were | Four mechanical snubbers installed in Unit 2 will be sent to Wyle Laboratories for testing and the NRC will be advised of the test results. This item remains open pending receipt of test results. | ||
The inspector reviewed the documentation of local leakage rate testing for | ' | ||
, | |||
In the area of pipe support and restraint systems no violations or devia-tions were identifed. | |||
6. | |||
Type B and C Local Leakage Rate Testing | |||
' | |||
The inspector reviewed the documentation of local leakage rate testing for containment penetrations (Type B) and containment isolation valves (Type C) | |||
L | |||
, | , | ||
; | |||
for both Units 1 and 2. | |||
! as stated in Appendix J to 10 CFR 50 is 0.6 times the maximum allowable leakage rate as specified for periodic tests in the operating license. For North Anna Units 1 and 2 the allowable leakage rate is 171 SCFH. The as j found leakag'e rates for both units exceeded 171 SCFH by a factor of at least | |||
; 3, due primarily to isolation valve leakage. Subsequent to repair, the leakage was reduced in all cases to less than 60 SCFH. The licensee is required by Appendix J to provide to the NRC a summary analysis of periodic | The allowable leakage rate for Type B and C tests | ||
' | |||
! | |||
as stated in Appendix J to 10 CFR 50 is 0.6 times the maximum allowable leakage rate as specified for periodic tests in the operating license. For North Anna Units 1 and 2 the allowable leakage rate is 171 SCFH. The as j | |||
found leakag'e rates for both units exceeded 171 SCFH by a factor of at least | |||
; | |||
3, due primarily to isolation valve leakage. | |||
Subsequent to repair, the leakage was reduced in all cases to less than 60 SCFH. | |||
The licensee is required by Appendix J to provide to the NRC a summary analysis of periodic r | |||
Type B and Type C tests that were performed since the last containment integrated leakage rate test (Type A). | |||
In the area of Type B and C local leakage rate testing no violations or deviations were identified. | In the area of Type B and C local leakage rate testing no violations or deviations were identified. | ||
' | ' | ||
. | |||
M i | M i | ||
l | l | ||
; | |||
i | i | ||
_ . _ , _ _ _ _ | _. _, _ _ _ _ | ||
}} | }} | ||
Latest revision as of 22:55, 16 December 2024
| ML20062H743 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 07/22/1982 |
| From: | Brooks E, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20062H731 | List: |
| References | |
| 50-338-82-23, 50-339-82-23, IEB-81-01, IEB-81-1, NUDOCS 8208160151 | |
| Download: ML20062H743 (3) | |
Text
g>n paco.
UNITED STATES
- *
f
[o NUCLEAR REGULATORY COMMISSION g
!'.
REGION n n
,$
101 M ARIETTA STRE ET, N.W.
k
ATLANTA, GEORGI A 30303 s... /
}
I f
(
Report Nos. 50-388/82-23, 50-339/82-23
Licensee:
Virginia Electric and Power Company
,
-
P. O. Box 26666 i
"
Richmond, VA 23262 Facility Name: North Anna Units 1 and 2 Docket Nos. 50-338, 50-339
!
License Nos. NPF-4 and NPF-7 Inspection at North Anna site near Mineral, Virginia i
'
Inspector:
7 - / 9 - 8 2.--
l E. H. Brooks Date Signed l
Approved by u.4dc{ [
- /d 7/
F. Jape, Section hief / F Date Signed Engineering Inspection [ Branch
'
Division of Engineering and Technical Programs i
SUMMARY Inspection on June 28 - July 2,1982 Areas Inspected
,
This routine, unannounced inspection involved 31 inspector-hours on site in the areas of pipe supports and directional restraints, and types B and C leakage rate j
testing.
Results Within the scope of this inspection no violations or deviations were identified.
,
$
i l
8208160151 820723 PDR ADOCK 05000338 G
-_. _.,
__.
_
_
.,
,
REPORT DETAILS 1.
Persons Contacted Licensee Employees W. R. Cartwright, Station Manager
- E. W. Harrell, Assistant Station Manager
- D. L. Benson, Superintendent Operations
- R. T. Johnson, Quality Assurance
- J. A. Hanson, Jr., Superintendent Technical Services
- J. C. Smith, Engineer Supervisor Performance & Test J. Roth, Engineer, Performance & Test J. Masticone, Operations Coordinator F. Timpano, Engineer Performance & Test
- M. E. Fellows, Staff Assistant
'
NRC Resident Inspector
- D. Johnson M. Shymlock
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on July 2,1982, with those persons indicated in paragraph 1 above.
Licensee acknowledged the findings without significant comment.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inspection of Pipe Support and Restraint Systems The inspector and licensee representative performed an inspection of snubbers installed in both Units 1 and 2.
Approximately 75 snubbers in the main steam valve house, service building, safeguards building and auxiliary feedwater pump house were inspected.
All snubbers appeared to be well maintained, properly installed, and free from " lockup." One snubber in the Unit 2 mechanical equipment room was exposed to high temperature feedwater leaking from feedwater value 2-FW-196.
The water was impinging on the snubber piston rod and seal.
Licensee management was advised of the potential for snubber damage. The licensee was in the process of performing
-
.
_.=
_
.
-. - -
.
-.
_
..
.
,
,
'
,
,
f scheduled snubber inspection and functional testing on Unit 1.
The previous inspection. and functional testing of Unit 1 snubbers was performed during the 1981 spring outage.
The most recent inspection and functional testing of Unit 2 snubbers was performed during the 1982 spring outage.
Based on technical specifications requirements for augmented inservice
'
inspection, both Units I and 2 are presently on a 12 months 25% subsequent visual inspection period.
Also, the licensee has properly selected for functional testing a representative sample in accordance with the technical
,
specifications requirements for both Units 1 and 2.
l The licensee has received an exemption from the requirement to functionally i
'
test large snubbers greater than 50 KIP around the steam generators and reactor coolant pumps, during the current outage only. These snubbers will be included in representative samples selected for tes *,ing during future outages. Open Items (79-04-02 and 79-04-06) concerning this subject are
-
considered closed.
.
Bulletin 81-01 concerns surveillance of mechanical snubbers. The licensee l
has responded to the bulletin, stating that no mechanical snubbers are
'
installed in North Anna Unit 1.
Four mechanical snubbers installed in Unit 2 will be sent to Wyle Laboratories for testing and the NRC will be advised of the test results. This item remains open pending receipt of test results.
'
,
In the area of pipe support and restraint systems no violations or devia-tions were identifed.
6.
Type B and C Local Leakage Rate Testing
'
The inspector reviewed the documentation of local leakage rate testing for containment penetrations (Type B) and containment isolation valves (Type C)
L
,
for both Units 1 and 2.
The allowable leakage rate for Type B and C tests
'
!
as stated in Appendix J to 10 CFR 50 is 0.6 times the maximum allowable leakage rate as specified for periodic tests in the operating license. For North Anna Units 1 and 2 the allowable leakage rate is 171 SCFH. The as j
found leakag'e rates for both units exceeded 171 SCFH by a factor of at least
3, due primarily to isolation valve leakage.
Subsequent to repair, the leakage was reduced in all cases to less than 60 SCFH.
The licensee is required by Appendix J to provide to the NRC a summary analysis of periodic r
Type B and Type C tests that were performed since the last containment integrated leakage rate test (Type A).
In the area of Type B and C local leakage rate testing no violations or deviations were identified.
'
.
M i
l
i
_. _, _ _ _ _