ML19323D721
| ML19323D721 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/29/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| References | |
| NUDOCS 8005220219 | |
| Download: ML19323D721 (1) | |
Text
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CENTRAL FILES PDR:HQ h# a'%n%,
UNITED STATES NUCLEAR REGULATORY COMMISSION LPDR 3"
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April 29, 1980 Docket Nc 50-267 u.
Public Service Company of Colorado ATTN:
Mr. C. K. Millen Senior Vice President P. O. Box 840 Denver, Colorado 80201 Gentlemen:
The enclosed IE Information Notice No. 80-16 provides information on two in2tances of main steam swing check or isolation valves binding due to shaft packing.
No written response is required.
If you have any questions regarding this matter, please contact this office.
Sincerely, gpb
~ r1 V. Seyfria Director Encle.ures :
1.
IE Information Notice No. 80-16 2.
Recently Issued IE Information Notices cc:
D. W. Warembourg, Nuclear Production Manager Fort St. Vrain Nuclear Station P. O. Box 368 Platteville, Colorado 80651 L. Brey, Manager, Quality Assurance 80052e0 2/ jP
SSINS No.:
6870 Accession No.:
UNITED STATES 8002280667 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, DC 20555 IE Information Notice No. 80-16 Date:
April 29, 1980 Page 1 of 2 SHAFT SEAL PACKING CAUSES BINDING IN MAIN STEAM SWING DISC CHECK AND ISOLATION VALVES Description of Circumstances:
Recently two instances of binding of swing check valves have occurred.
During disassembly of the main steam isolation valves at Indian Point 2, it was observed that all four reverse flow check valves were stuck at or near fully open. These 28" valves are manufactured by Atwood & Morrill Co.
Investigation revealed that this condition was apparently caused by excessively tight shaft packing which did not allow free movement of the valve disc.
This condition was reported on January 31, 1980. An evaluation determined that with the existence of the reported condition in event of a main steam line break upstream of a main steam isolation valve together with coincident single failure of a main steam isolation valve to close in another loop, the potential existed for blowdown of the contents of two steam generators.
Main steam line break analyses applicable to Indian Point 2 have been performed assuming blowdown of the contents of one steam generator and have not considered multiple steam generator blowdow..
Therefore, it is possible that the reported condition could have contributed to the exceeding of a safety limit as defined in the Unit 2 Technical Specifications if a main steam line break had occurred.
The reported condition was corrected by adjusting the packing of these valves in all four loops and verifying that valve disc movement is not restricted.
During testing in the hot standby mode at the Trojan Nucle r Plant on April 15, 1980, three of the four main steam line isolation valves failed to close when manually actuated.
The cause of the occurrence was binding in the shaft packing.
The valve is air opened and is closed by gravity, steam flow and a small spring force; the valves were manufactured by Atwood & Morrill Co.
The licensee believes that the valves would have closed during actual operations with steam flow in the line.
The valves were repaired and tested satisfactorily.
Modifications to the valves to install air operators to help close the valves are being investigated by the licensee.
IE Information Notice No. 80-16 Date:
April 29, 1980 Page 2 of 2 This Information Notice is provided as notification of a possible significant matter.
It is expected that the recipients will review the information for possible applicability to their facilities and appropriate corrective action taken.
t No written response to this IE Information Notice is required.
IE Information Notice No. 80-16 April 29, 1980 LISTING 0F RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued d0-11 General Probleas with ASCO 3/14/80 All holders of Reactor Valves in Nuclear Applicatic-Operating License (OL),
Including Fire Protection Construction Permit (CP),
Systems fuel fabrication and processing facilities 80-12 Instrument Failure Causes 3/21/80 All holders of Power Opening of PORV and Block Reactor Operating Valve Licenses (OLs) and Construction Permits (cps) 80-13 General Electric Type SBM 4/2/80 All light water reactor Control Switches - Defective facilities holding power Cam Followers reactor Operating Licenses (OLs) and Construction Permits (cps) 80-14 Safety Suggestions From 4/2/80 All power reactor Employees facilities with an Operating License (OL) or Construction Permit (CP) 80-15 Axial (Longitudinal)
All light water reactor i
Oriented Cracking In facilities holding power Piping reactor Operating Licenses (OLs) or Construction Permits (cps)
Enclosure
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