ML20064A943
| 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
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Route 9 South.
- Forked River, New' Jersey 087310308 609 9714000 =
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- 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
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- If there should'be any'further questions,.please contact Mr. John Rogers, at'
- (609)971-4893.
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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
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