ML19345C964
| ML19345C964 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/10/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8012080675 | |
| Download: ML19345C964 (1) | |
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UNITED STATE 3
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NUCLEAR REGULATORY COMMISSION
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.j REGION IV
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Sit RYAN Pt.AZA DRIVE. SUITE 1000 ARUNGTON. TEXAS 79011 November IC, 1980
.In Reply Refer To:
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RIV Docket No. 3TN 50-482/IE Information Notice No. 80-41
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Kansas Gas & Electric Co.
Attn: Mr. Glenn L. Koester -
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- i Vice President-Nuclear y
y Post Office Box 208 v
Wichita, Kansas 67201 Gentlemen:
This IE Infomation Notice is provided as an early notificar.fon of a possibly significant matter.
It is expected that recipients will review the infc mation for possible applicability to their facility. No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be: issued to.recomend or request specific licensee.
actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, M
Karl V. Seyfri, f
Director
Enclosures:
1.
IE Information Notice No. 80-41 2.
List of Recently Issued IE Infomation Notices cc: w/ enclosures Messrs. Nicholas A. Petrick, SNUPPS
- 0. T. McPhee, Kansas City Power and Light Company Gerald Charnoff, Shaw, Pittman, Potts & Trowbridge E. W. Creel, Kansas Gas and Electric Company 8012080(7f
T SSINS No.:
6835.
Accession No.:
8008220260 UNITED STATES NUCLEAR REGULATORY COMMISSION-0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 80-41 Date:
November 10, 1980 Page 1 of 1 FAILURE OF SWING CHECK VALVE IN THE DECAY HEAT REMOVAL SYSTEM AT DAVIS-BESSE UNIT NO. 1 Descriotion of Circumstances:
On October 9,1980 the Resident Reactor Inspector at the Davis-Besse facility was informed that the licensee had performed leak rate tests and identified exces-sive leakage through Decay Heat Remeval System check valve CF-30.
Valve CF-30 is the inboard one of two in-series check valves that is used to isolate the reactor coolant system from the low pressure decay heat removal system.
On further investigation the licensee found that the valve disc and arm had separated from the valve body and was lodged just under the valve cover plate.
The two 2 5/8 x 5/8-inch bolts and locking mechanism for the bolts that holds the arm to the valve body were missing and have not been locsted.
The CF-30 valve is a 14-inch swing check valve manufactured by: Velan' Valve Corporation.-
4 The cause of the failure has not-been identified.-
The test that was in progress when the failure was identified was being con-ducted in response to a letter from Darrell-G. Eisenhut, Office of Nuclear Reactor Regulations to all Light Water Reactor Licensees, LWR Primary Coolant System Pressure Isolation Valves, February 23, 1980.
This IE Information Notice is provided as an early notification of a possibly significant satter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facilities. No specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
No written response to this IE Information Notice is required.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
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IE Information Notice No. 80-41 November 10, 1980 LISTING OF RECENTLY ISSUED IE INFORMATICN NOTICES Information Subject Date Issued To Notice No.
Issued 80-34 Baron Dilution of Reactor 9/26/80 All Pressurized Coolant During Steam Water Reactor Generator Oecontamination Facilities holding power reactor Operating Licenses (OLs) 80-35 Leaking and Dislodged 10/10/80 All categories G and Iodine-124 Implant Seeds G1 medical licensees 80-36 Failure of Steam 10/10/80 All nuclear power Cererator Support Bolting reactor facilities holding Operating Licensees (CLs) or Construction Permits (cps) 80-37 Containment Cooler Leaks 10/24/80 All nuclear power and Reactor Cavity facilities holding Flooding at Indian Point' power reactor Operating Unit 2 Licenses (OLs) or Construction Permits (cps) 80-38 Cracking in Charging id/30/80 All Pressurized Water Pump Casing Cladding Reactor Facilities holding power reactor Operating Licenses (OLs) and Construction Permits (cps) 80-39 Malfunctions Of Solenoid 10/31/80 All lig't water reactor Valves Manufactured By facilit is holding Valcar Engineering Corporation power ratctor Operating Licenses (OLs) or Construc-tion Permica (cps) 80-40 Excessive Nitrogen 11/7/80 All power facilities Supply Pressure with an Operating License Actuates Safety-Relief (OL) or Construction Valve Operation to Permit (CP)
Cause Reactor Depressuriza-tion Enclosure
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