ML19345C918
| ML19345C918 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/10/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| References | |
| NUDOCS 8012080611 | |
| Download: ML19345C918 (1) | |
Text
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NUC!.IAR REGULATORY COMMISSION TIC C "<
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m m.. c_f.u caive. suits eco AauNcTen. rsxAs son SgTE Novemcer 10, 1980 Docket No. 50-267 S
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?uolic Service Ccmcany of Coloraco ATTN: Mr. C. K. Millen
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5 Senior Vice President 3
"j P. G. Box 340 Cenver, Coloraco 50201 Gentlemen:
l~nis IE Information Notice is Orovided as an early notification of a possibly significant matter.
I: is ex:ected that recioients will review :ne infomation for possible acplicability to -heir facility.
No scecific action or resconse is recuested at :nis time.
I-fur ner NRC evaluations so indicate, ae IE Circular or Sulletin will be issued :c recenrend or recuest scecific licensee acticns.
If ycu nave cuestions regarding tnis matter, clease c ntac: :ne 4_
Direc:cr of :ne a ::ropriate NRC Regional Office.
Sincerely,
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' Karl V. Seyfrit -
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Director
Enclosures:
1.
IE Info mation Notice No. 30 41 2.
List of Recently Issued IE Infonation Notices cc:
D.
'4. 'Jaremcourg, Nuclear Production Manager cr: St. Vrain Nuclear Station
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P. O. Box 368 Platteville, Colorado 30651 L. Brey, Manager, Cuality Assurance 8012080 h
SSINS No.:
6835 Accession No.:
8008220260 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 80-42 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 tne Davis-Besse facility was informed that the licensee had performed leak rate tests and identified exces-sive leakage througn Decay Heat Removal System check valve CF-30.
Valve CF-30 is the inboard one of two in-series check valvas that is us4d to isolate the reactor coolant system from the Tow 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-inca 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 Oarrell 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-Informa: ion 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 aopropriate NRC Regional Office.
4 IE Information Notice No. 80-41 Novemoer. 10, 1980 LISTING OF RECENTLY ISSUED
.IE INFCRMATION NOTICES Information -
Suoject Date Issued To Notice No.
Issued 80-34 Boron Oilution of Reactor 9/26/80 All Pressurized
-Coolant'Ouring 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-Generator Support Bolting reactor facilities holding Operating Licansees (OLs) or-Construction Permits (cps) 80-37 Containment. Cooler Leaks 10/24/80 All nuclear powe:
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 -
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 (0Ls) 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-
-tion 4
Enclosure l
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