ML19345C908
| ML19345C908 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/10/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Draper E GULF STATES UTILITIES CO. |
| References | |
| NUDOCS 8012080591 | |
| Download: ML19345C908 (1) | |
Text
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p' UNITED STATE 2 NUCLEAR REGULATORY COMMISSION 3.+
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611 RYAN Pt.AZA DRIVE. SulTE 1000 h,..,-
ARUNGTON. TEXAS 76011 November 10, 1980 j
In Reply Refer To:
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Docket Nos. 50-458/IE Information Notice No. 80-41 50-459/IE Information Notice No. 80-41 1
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Gulf States Utilities 0
Attn: Dr. E. Linn Draper, Jr.
Vice President - Technology Post Office Box 2951 Beaumont, Texas 77704 Gentlemen:
This IE Infonation Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the infomation for possible applicdility to their facilities. No specific action or response
,s recuested ac 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 Direccor of the appropriate NRC Regional Office.
Sincerely, i
/Karl V. Seyfrite Director L. closures.:
1.
IE Infomation Notice No. 80-41 2.
List of Recently Issued IE Infomation Notices 2
8019080 59 /
K.
2_
SSINS No.:
6835.
Accession No.:
8008220260 UNITED STATES NUCLEAR REGULATORY COMMISSION s
0FFICE OF INSPECTION AND ENFORCEMENT j
b 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-SESSF. 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 tnrnugh Decay Heat Removal System check valve CF-30.
Valve CF-30 is the inboard c1e 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 located. The CF-;d valve is a 14-inch swing check valve manufactured by Velan Valve Corporation.
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 matter that is still under review by the NRC staff.
It is expected that recipients wil'. 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.
I, T_
l IE Info. nation Notice No. 80-41 November 10, 1980 LISTING OF RECENTLY ISSUEG IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 80-34 Baron Oilution of Reactor 9/26/80 All Pressurized Coolant During Steam Water Reactor Generator Decontamination Facilities holding power reactor Operatine Licenses (OLs)
J 80-35 Leaking and Dislodged 10/10/80 All categories G and
)
Iodine-124 Implant Seeds G1 medical licensees 80-36 Tailure of Steam 10/10/80 All nuclear power tienerator Support Bolting reactor facilities holding Operating Licensees (OLs) or Construction Permits (cps) 80-37 Containment Cooler Leaks 10/24/80 All nuclear power and Reactor Cavity facilitie, holding i
Flooding at Indian Point power re ctor Operating i
Unit 2 Licenses (OLs) or l
Construction Permits (cps) l 80-38 Cracking in Charging 16/30/80 All Pressurized Water Pump Casing Cladding Reactor Facilities holding power reac+ar Operating Licenses (OLs)
I and Construction Perm hs (cps) 80-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding e'
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 iafety-Relief (OL) or Construction Valve Operation to Permit (CP)
Cause Reactor Depressuriza-tion Enclosure w.
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