ML19345C899
| ML19345C899 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/10/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 8012080575 | |
| Download: ML19345C899 (1) | |
Text
6-m7ly/ &/s o
e, UNITED STATES
, {
NUCLEAR REGULATORY COMMISSION
', j REGloN IV 8
611 RYAN Pt.AZA ORIVE. SUITE 1000 S,,,,8 ARUNGToN. TEXAS 76011 November 10, 1980 In Reply Refer To:
RIV 1
Docket No. 50-382/IE Information Notice No. 80-41 j
$d Louisiana Power and Light Co.
~ ;
ATTN: Mr. O. L. Aswcli
'a' Vice President of Power Production S
~i
~3 142 Delarende Street A
?
2 New Orleans, Louisiana 70174 Gentlemen:
This IE Infomation Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facility. No specific action or res;:anse is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to reconrnend or request specific licensee a"
actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, L
Karl V. Seyfr$t' Director
Enclosures:
1.
IE Infomation Notice No. 80-41 2.
List of Recently Issued IE Infomation Notices
/
wannr
SSINS No.:
6835.
Accession No.:
8008220260 UNITED STATES 4N NUCLEAR REGULATORY COMMISSION N
OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555
' i- >
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 Octobe-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 throt gh Decay Heat Removal 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' frem the valve body and was lodged just under the valve cover plate.
The two 2 5/8 x 5/8-inch loits and locking mechanism for the bolts that holds the arm to the valve body were missing ana have not been located.
The CF-30 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 ?ressure Isolation Valves, February 23, 1980.
Thic 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 rt2ponse 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.
1 l
1
4.
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 Boron Oilution of Reactor 9/26/80 All Pressurized Coolant Ouring Steam Water Reactor Generator Decontamination Facilities holding power reactor Operating Licenses (0Ls) 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 (OLs) or Construction Permits (cps) 80-37 Containment Cooler Leaks 10/24/80 All nuclear power and Reactor Cavity facilities holding r: coding at-Indian Point-power reactor Operating-Unit 2 Licenses (OLs) or Construction Permits (cps) 80-38 Cracking in Charging 10/30/80 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 light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor Operating Licenses (OLs) or Construc-tion Perrits (cps) 80-40 Excessive Nitrogen 11/7/80 All power facilities Supply Pressure with an'0perating License Actuates Safety-Relief (OL) or Construction Valve Operation to Permit (CP)
Cause Reactor Depressuriza-tion Enclosure
.~
_..