ML19345C905
| ML19345C905 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/10/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Gary R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 8012080584 | |
| Download: ML19345C905 (1) | |
Text
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g UNITED STATES
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NUCLEAR REGULATORY COMMISSION z
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REGION IV 7.
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,,8 ARUNGToN. 'ibAS 76011 November 10, 1980 In Reply Refer To:
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Occket Not. 50-445/IE Information Notice No. 80-41 50-446/IE Infonnation Notice No. 80-41 q
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Texas Utilities Generating Company
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'l 95 ATTN: Mr. R. J. Gary, Executive Vice
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Dallas, Texas 75201 Gentlemen:
This IE Information Notice is provided as an early noti #ication of a pessibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities. No specific action or response is requ1sted at this time.
If further NRC evaluations so indicate, an IE Circula or Bulletin will be issued to recorrinend or request specific licensee actions.
If you ~1 ave questions regarding this matter, please contact the Director of the at propriate NRC Regional Office.
Sincerel-y,
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. Seyfrit/,
Director
Enclosures:
1.
IE Information Notice No. 80-41 2.
List of Recently Issued IE Information Notices 8012080 gg y
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3 SSINS No.:
6835.
Accession No.:
8008220260 UNITED STATES w
NUCLEAR REGULATORY COMMISSION l
OFFICE OF INSPECTION AND ENFORCEMENT c
. 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. Removal System check valve CF-30.
Valve CF-30 is the inboard one of f.wo 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. tne 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 nive body were missing and have not been located.
The CF-30 valve i:, a 14-inch swing check valve manufactured by Velan Valve ^ Corporation.
The cause e,f the failure has not been identified.
The test that was in progress when tt.c 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, J.WR Primary Coolant i
System Pressure Isolation Valves, February 23, 1980.
This IE Information Notice is provided as an early notification of a possibly significant matter that is still under review E 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 INFORMATION NOTICES Information-Subject Date Issued To Notice No.
Issued 80-34 Baron Dilution of Reactor 9/26/80 All Pressurized Csolant During Steam Water Reactor Generator Decontamination Facilities holding power reactor Operating Licenses (OLs)
I 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 Generator Support Bolting reactor facilities holding Operating Licensees (0Ls) or Construction Permits (cps) 80-37 Containment Cooler Leaks 10/24/80.
All nuclear power and Reactor Cavity facilities holding i
Flooding at: Indian: Point" power reactor Operating
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Unit.2 Licenses (OLs) or Construction Permits (cps) 80-38 Cracking in Charging 16/30/80 All Pressurized Water Pump Casing Cladding Reactor Facilities holding power reactor Operating Licenses (OLs) and Construction Permits (cps) 00-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor Operating -
Licenses (OLs) or Construc-tion Permits (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-
'fon Enclosure i
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