ML20064A943: Difference between revisions

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=Text=
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{{#Wiki_filter:E f ;i           ,                    ,    x
{{#Wiki_filter:E f ;i x
          ;; n.g .
;; n.g.
m     .-      p r
m p
ENuclear                                                                                  = =e w --
r ENuclear
Route 9 South .
= =e w --
                                                                                                      ; Forked River, New' Jersey 087310308
Route 9 South.
                                    ~                                                 ~
; Forked River, New' Jersey 087310308 609 9714000 =
609 9714000 =
~
                                                                                                      - Writer's Direct Dial Number:
~
- 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
' Attn Document Control Desk
                  ' Washington,;DC =20555
' Washington,;DC =20555 Dear Sir
      .              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                                           i reverse direction tested and that adequate documentation for the acceptability ofLthe reverse! direction testing was not available, as required.
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;
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.                                         j
: 1) 13 valves were being reverse ~ direction tested;
                  . 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.
: 2) written justification for the reverse direction testing was com91eted for nine of the, valves; 3) an engineering evaluation was performed to demonstrate.
                  -Subsequent to that submittal, extensive research and evaluation into valve                                               j E                   design. yielded new information. Seven of the nine valves which were found                                               '
j
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                                     1   i classified as a-10'CFR 50 Appendix-J, Type B penetration.
. 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.
                                                                                                                                            -t In J order to test these new Type B penetrations, additional modifications will-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                                           ;
-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                                               i
Seven of the nine valves which were found l
                  . 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
acceptable =for reverse direction testing of the valve seat-(10CFR50 Appendix J,-Type C testing) were wafer seal butterfly valves.
                  -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
This valve configuration has'an innermost seal which is only tested during a 10 CFR 50 Appendix J Type iL A test.
                        . Ov'10g GPU Nuclear Corporation is a subsidiary of General Public UtMties Corporation
This innermost seal has been determined to be more appropriately i
* 7 s                             1                                       --    --        -        - .
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


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: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.
;(609)971-4893.
                                                                                                        -)
-)
Very truly yours, f     )
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
E.'
                            -Region 1I                                                                   ,,
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
                              ~475 Allendale Road-                                                         i King of Prussia, PA 19406 Mr. Alexe.nder W. Dromerick                                                 '
-Region 1I U.
U.S. Nuclear Regulatory Commission
S. Nuclear Regulatory Commission
                            ' Mail Station Pl-137
~475 Allendale Road-i King of Prussia, PA 19406 Mr. Alexe.nder W. Dromerick U.S. Nuclear Regulatory Commission
                            -Washington, DC 20555 NRC Resident Inspectors                                                     1
' Mail Station Pl-137
',                            OCNGS-                                                                   :r i
-Washington, DC 20555 NRC Resident Inspectors 1
    ?
OCNGS-
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                                                                                          *_ +}}
+}}

Latest revision as of 21:12, 16 December 2024

Revised Response to NRC Re Violations Noted in Insp Rept 50-219/89-12.Spectacle Flanges Containing Testable O-ring to Allow Type B Testing Will Be Installed Adjacent to Butterfly Valves
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

+