ML19345C762
| ML19345C762 | |
| Person / Time | |
|---|---|
| Site: | Harris, Brunswick, Robinson  |
| Issue date: | 11/10/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8012080316 | |
| Download: ML19345C762 (1) | |
Text
,-
e arec
/
'o,,
UNITED STATES 7{
NUCLEAR REGULATORY COMMISSION i
n REGION 11 0,
[
101 MARIETTA sT., N.W., sulTE 3100 O
ATLANTA. GEORGIA 30303 7.. ;
%*****o yov o 1980 M
9
.In Reply Refer To:
RII:JPO
.1 50-325,_50-32_4 w
p 0-402, 50-403 )
m 0-400, 50-40 N
.a s5
'. f" U
nci 5F241
!j
- =;
.e
(' 1 Q
tj]
g Carolina Power and Light Company ATTN:
J. A. Jones Senior Executive Vice President and Chief Operating Officer 411 Fayetteville Street Raleigh, NC 27602 Gentlemen:
This Information Notice is provided as an early notification of a possibly significan-matter. It is expected that recipients will review the information for possibit applicability to their facilities. 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 recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 80-41 2.
List of Recently Issued IE Information Notices cc w/ encl:
R. B. Starkey, Jr., Plant Manager R. P.rsons, Site Manager A. C. Tollison, Jr., Plant Manager i
l 3 lh 8012080
SSINS Ns.: 6835 Accessica No.:
8008220260 UNITED STATES NUCLEAR REGULATORY COMMISSION l
OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 O~
November 10, 1980 IE Information Notice No. 80-41: FAILURE OF SWING CHECK VALVE IN THE DECAY HEAT REMOVAL SYSTEM AT DAVIS-BESSE UNIT NO. 1 Description of Circumstances:
On October 9, 1980 the resident inspector at the Davis-Besse faci'ity was informed that the licensee had performed leak rate tests and ident!.fied exces-sive leakage through Decay Heat Removal System check valve CF-30.
Valve CF-30 is the inboard one of two in-series check valves chat 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-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 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 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.
IN 80-41 N2vember 10, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 80-41 Failure to Swing Check Valve 11/10/80 All nuclear power reactor in the Decay Heat Removal facilities with an OL System at Davie-Besse Unit or CP No. 1 80-40 Failure Of Swing Check 11/10/80 All power facilities Valve In The Decay Heat with and OL or CP Removal System At Davis-Besse Unit No. I 80-39 Malfnnetions Of Solenoid 10/31/80 All light water reactor V _ves Manufactured By facilities holding Valcor Engineerine, Corporation power reactor OLs or cps 80-38 Cracking In Charging Pump 10/30/80 All PWR facilities Casing Cladding with an OL or CP 80-37 Containment cooler leaks 10/24/80 All nuclear power and reactor cavity facilities holding flooding at Indian Point power reactor OLs Unit 2 or cps 80-36 Failure of Steam 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding power reactor OLs or cps 80-35 Leaking and dislodged 10/10/80 All categories G and Iodine-124 implant seeds G1 medical licensees 80-34 Boron dilution of reactor 9/26/80 All pressurized water coolant during sf;eam reactor faci _lities generator decontamination holding power reactor OLs 80-33 Determination of teletherapy 9/15/80 All teletherapy timer accuracy (G3) licensees 80-32 Clarification of certain 3/12/80 All NRC and agreement requirements for Exclu-state licensees sive-use shipments of radioactive materials 80-31 Maloperation'of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding OLs volt type K-600S and or cps K-DON 600S circuit breakers 1
- Operating Licenses or Construction Permits
_ _ __