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{{#Wiki_filter:E f ;i | {{#Wiki_filter:E f ;i x | ||
;; n.g. | |||
m | m p | ||
r ENuclear | |||
Route 9 South . | = =e w -- | ||
Route 9 South. | |||
; Forked River, New' Jersey 087310308 609 9714000 = | |||
~ | |||
~ | |||
- Writer's Direct Dial Number: | |||
September 24, 1990 U.S. Nucle.ar Regulatory Commission | September 24, 1990 U.S. Nucle.ar Regulatory Commission | ||
' Attn Document Control Desk | |||
' Washington,;DC =20555 Dear Sir | |||
==Subject:== | ==Subject:== | ||
Oyster-Creek Nuclear Generating Station Docket No. 50-219 Revised Response to Notice of Violation | Oyster-Creek Nuclear Generating Station Docket No. 50-219 Revised Response to Notice of Violation Inspection Report 89-12 By {{letter dated|date=September 8, 1989|text=letter dated September 8, 1989}}, GPU Nuclear submitted the response to the Notice of Violation documented in Appendix A to NRC Inspection 50-219/89-12. | ||
Inspection Report 89-12 By {{letter dated|date=September 8, 1989|text=letter dated September 8, 1989}}, GPU Nuclear submitted the response to the Notice of Violation documented in Appendix A to NRC Inspection 50-219/89-12. | Example B in the' violation noted that four containment isolation valves were i | ||
Example B in the' violation noted that four containment isolation valves were | reverse direction tested and that adequate documentation for the acceptability ofLthe reverse! direction testing was not available, as required. | ||
o GPU Nuclear: responded that: | o GPU Nuclear: responded that: | ||
: 2) written justification for the reverse direction testing was com91eted for nine of the, valves; 3) an engineering evaluation was performed to demonstrate. | : 1) 13 valves were being reverse ~ direction tested; | ||
: 2) written justification for the reverse direction testing was com91eted for nine of the, valves; 3) an engineering evaluation was performed to demonstrate. | |||
j | |||
. valve acceptability for the. remaining four globe valves; and 4) any, requisite i | |||
modifications to these four valves would be completed prior to restart from-y refueling outage 13R. | |||
-Subsequent to that submittal, extensive research and evaluation into valve j | |||
E design. yielded new information. | |||
_ provide a passive barrier to containment pressure in that no movement of | Seven of the nine valves which were found l | ||
acceptable =for reverse direction testing of the valve seat-(10CFR50 Appendix J,-Type C testing) were wafer seal butterfly valves. | |||
This valve configuration has'an innermost seal which is only tested during a 10 CFR 50 Appendix J Type iL A test. | |||
This innermost seal has been determined to be more appropriately i | |||
1 classified as a-10'CFR 50 Appendix-J, Type B penetration. | |||
-[ | |||
-t In order to test these new Type B penetrations, additional modifications will-J be required. | |||
The most effective resolution would be the installation of spectacle flanges adjacert to the butterfly valves.- The soectacle flange twould contain.a testable O-ring to allow Type B testing. The existing flanges | |||
_ provide a passive barrier to containment pressure in that no movement of i | |||
+ | |||
. mechanical parts is required to perform the boundary function. | |||
Previous test 1 | |||
data of similar flangen has generally yielded acceptable leakage results. | |||
In addition,~should a: butterfly valve flange connection be disassembled for any l | |||
reason during 13R, the spectacle flange modification will be insta'. led and the 1 | |||
L. | |||
Type B test performed prior to startup. | |||
The four previously identified globe Ji | |||
-valves will all be modified prior to restart from 14R rather than 13R as previously stated. | |||
9010030060 900924 f | |||
PDR ADOCK 05000219 0 | |||
PNU h | |||
. Ov'10g GPU Nuclear Corporation is a subsidiary of General Public UtMties Corporation 7 | |||
s 1 | |||
c.; | c.; | ||
"7 t' | |||
e. | |||
<.~'', ' ' ' | |||
' 1 'i 4 | |||
~ | |||
:If there should'be any'further questions,.please contact Mr. John Rogers, at' | :If there should'be any'further questions,.please contact Mr. John Rogers, at' | ||
;(609)971-4893. | |||
-) | |||
Very truly yours, f | Very truly yours, f | ||
E.' E.-Fitzpatrick | ) | ||
Vice President and Director Oyster Creek | E.' | ||
E.-Fitzpatrick Vice President and Director Oyster Creek f | |||
U. S. Nuclear Regulatory Commission | EEF/JJR/dmd (JR-LTRS2:23) ocs Mr. Thomas T. Martin, Administrator | ||
-Region 1I U. | |||
U.S. Nuclear Regulatory Commission | S. Nuclear Regulatory Commission | ||
~475 Allendale Road-i King of Prussia, PA 19406 Mr. Alexe.nder W. Dromerick U.S. Nuclear Regulatory Commission | |||
' Mail Station Pl-137 | |||
-Washington, DC 20555 NRC Resident Inspectors 1 | |||
OCNGS- | |||
k) | :r i | ||
? | |||
1 l | k) 1 l | ||
1 | 1 | ||
+}} | |||
Latest revision as of 21:12, 16 December 2024
| ML20064A943 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/24/1990 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9010030068 | |
| Download: ML20064A943 (2) | |
Text
E f ;i x
- n.g.
m p
r ENuclear
= =e w --
Route 9 South.
- Forked River, New' Jersey 087310308 609 9714000 =
~
~
- Writer's Direct Dial Number:
September 24, 1990 U.S. Nucle.ar Regulatory Commission
' Attn Document Control Desk
' Washington,;DC =20555 Dear Sir
Subject:
Oyster-Creek Nuclear Generating Station Docket No. 50-219 Revised Response to Notice of Violation Inspection Report 89-12 By letter dated September 8, 1989, GPU Nuclear submitted the response to the Notice of Violation documented in Appendix A to NRC Inspection 50-219/89-12.
Example B in the' violation noted that four containment isolation valves were i
reverse direction tested and that adequate documentation for the acceptability ofLthe reverse! direction testing was not available, as required.
o GPU Nuclear: responded that:
- 1) 13 valves were being reverse ~ direction tested;
- 2) written justification for the reverse direction testing was com91eted for nine of the, valves; 3) an engineering evaluation was performed to demonstrate.
j
. valve acceptability for the. remaining four globe valves; and 4) any, requisite i
modifications to these four valves would be completed prior to restart from-y refueling outage 13R.
-Subsequent to that submittal, extensive research and evaluation into valve j
E design. yielded new information.
Seven of the nine valves which were found l
acceptable =for reverse direction testing of the valve seat-(10CFR50 Appendix J,-Type C testing) were wafer seal butterfly valves.
This valve configuration has'an innermost seal which is only tested during a 10 CFR 50 Appendix J Type iL A test.
This innermost seal has been determined to be more appropriately i
1 classified as a-10'CFR 50 Appendix-J, Type B penetration.
-[
-t In order to test these new Type B penetrations, additional modifications will-J be required.
The most effective resolution would be the installation of spectacle flanges adjacert to the butterfly valves.- The soectacle flange twould contain.a testable O-ring to allow Type B testing. The existing flanges
_ provide a passive barrier to containment pressure in that no movement of i
+
. mechanical parts is required to perform the boundary function.
Previous test 1
data of similar flangen has generally yielded acceptable leakage results.
In addition,~should a: butterfly valve flange connection be disassembled for any l
reason during 13R, the spectacle flange modification will be insta'. led and the 1
L.
Type B test performed prior to startup.
The four previously identified globe Ji
-valves will all be modified prior to restart from 14R rather than 13R as previously stated.
9010030060 900924 f
PDR ADOCK 05000219 0
PNU h
. Ov'10g GPU Nuclear Corporation is a subsidiary of General Public UtMties Corporation 7
s 1
c.;
"7 t'
e.
<.~, ' ' '
' 1 'i 4
~
- If there should'be any'further questions,.please contact Mr. John Rogers, at'
- (609)971-4893.
-)
Very truly yours, f
)
E.'
E.-Fitzpatrick Vice President and Director Oyster Creek f
EEF/JJR/dmd (JR-LTRS2:23) ocs Mr. Thomas T. Martin, Administrator
-Region 1I U.
S. Nuclear Regulatory Commission
~475 Allendale Road-i King of Prussia, PA 19406 Mr. Alexe.nder W. Dromerick U.S. Nuclear Regulatory Commission
' Mail Station Pl-137
-Washington, DC 20555 NRC Resident Inspectors 1
OCNGS-
- r i
?
k) 1 l
1
+