ML20072K436
| ML20072K436 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 06/30/1983 |
| From: | Seiken S STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20072K438 | List: |
| References | |
| NUDOCS 8307060280 | |
| Download: ML20072K436 (1) | |
Text
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I s-SNUPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Rockville, Maryland 20850 (301) 869 8010 June 30,1983 SLNRC 83-0034 FILE:~0491.10.2 SUBJ: Significant Deficiency Reports (SDR's) 83-01 and 83-03 Mr. Richard DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washingtun, D.C. 20555 Docket Nos.: STN 50-482 and 50-483
References:
- 1) SLNRC 83-03, Westinghouse EMD Gate Valve Position Indi-cation Issue: 50.55(e) Interim Report 83-01, dated 1/21/83,
- 2) SLNRC 83-008, Significant Deficiency Report (SDR) 83-03 re Design and Installation of U-Bolt Restraints, dated 2/18/83
- 3) SLNRC 83-0032, Westinghouse EMD Gate Valve Position Indica-tion Issue; 50.55(e) Final Report 83-01, dated 5/31/83
Dear Mr. DeYoung:
Copies of the referenced Signification Deficiency Reports were previously transmitted to the Directors of Regions III and IV.
However, SNUPPS inadvertently failed to transmit a copy of each to the Washington Office, as required by internal procedures.
Attached, herewith, are copies of the referenced reports.
If additional clarification is required, please feel free to contact the undersigned.
Very truly yours, 4
S. J. Seiken Manager, Quality Assurance WAB/dck/17bl4 Attachments: References 1) through 3)'
'fl 8307060280 830630 PDR ADOCK 05000482 Q
.-ae SNUPPS Skandardised Nwedeer Unit Pourer Plant System s choke cherry n.ed Nicholes A.Petrick nookvisie. Marytend 20eso Executive Director January 21, 1983 SLNRC 83- 03 FILE: 0491.10.2 SUBJ:
Westinghouse EMD Gate Valve Position Indication Issue; e
50.55 (e) Interim Report 83-01 Mr. James G. Kepple, Director USNRC Office of Inspection & Enforcement, Region III 799 Roosevelt Road Glen Elyn, Illinois 60137 Mr. John T. Collins, Director USNRC Office of Inspection and Enforcement, Region IV 611 Ryan Plaza Drive Arlington, Texas 76102 Docket Nos.:
STN 50-482 and 50-483 Gentlemen:
On December 23, 1982, SNUPPS informed the Nuclear Regulatory Comission, Region III and IV Offices of Inspection and Enforcement of a potential deficiency regarding the Westinghouse EMD nate valve position indication.
This notification was based on information from Westinghouse provided on December 22 and 23, 1982 to SNUPPS. Westinghouse Water Reactor Div-isions Safety Review Committee determined on December 22, 1982 that "a significant deficiency as defined in 10CFR 50.55(e) exists for Callaway and Wolf Creek...." regarding this issue. Further details are provided herein on this matter, with this letter being an interim report. A follow-up report on this matter will be provided by May 31, 1983, when any specific corrective actions for each valve are defined.
The issue involves the valve position indication for certain Westing-house manufactured gate valves. An indication of " closed" could occur l
prior to the valve disc fully isolating flow.
If the valve should stall or bind following the premature closure indication being given, the op-erator would have an inaccurate indication of true valve position.
A geared limit switch rotor is set to provide an electrical bypass of the OPEN torque switch at the beginning of the opening stroke. On a closing stroke, this switch changes state before the flow patn is com-pletely blocked. As a result, it is likely that monitor and/or indicator lights also operated by that rotor will indicate valve closure slightly before the flow path is completely shut off.
If the valve were to stop between this setpoint and the full shut off position, a flow path through the valve could exist even though a CLOSED indication had been achieved.
- % D I G &. (D v
SLNRC 83-03 Page 2.
Depending on the valve application and consequences cf inaccurate closure indication, the wiring of certain valves may need to be altered to avoid the issue defined above.
This conclusion is based on the Westinghouse generic wiring specification. Further checking is still required to ensure that these valves have not been modified to meet additional requirements or rewired as part of modifications to increase shut off pressure rating.
A review of the gate valve applications in the cold and hot leg safety injecfion lines for the SNUPPS plants has indicated that the valves tabulated in the attachment may require modification.
This list includes all valves where incorrect position indication by itself may cause an unacceptable situation that could violate the established licensing basis.
Valves identified in the attached listing are provided for information only. As stated above, any specific corrective actions for each valve will be defined by May 31, 1983.
Very ruly yours, Mt Nicholas A. Petrick J0C/nld2b27 Attachment cc:
G. L. Koester KGE D. T. McPhee KCPL D. F. Schnell UE.
J. H. Neisler NRC/ CAL T. E. Vandel NRC/WC J. Konklin NRC Region III R. Redano NRC Region IV a
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s SLNRC 83-03 Page 3.
I bec:
J. Bailey KGE d
A. Passwater UE G. Rathbun KGE R. Wendling UE J. Smith B
R. Stright Ttaff F. Schwoerer Staff S. Seiken Staff 1
M. Fletcher Staff R. White Staff
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V. Sheffler Staff 4
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e ATTACHMENT Callaway Unit #1 and Wolf Creek e
VALVES IN WHICH INCORRECT POSITION INDICATION BY ITSELF MAY CAUSE AN UNACCEPTABLE SITUATION THAT COULD VIOLATE THE ESTABLISHED LICENSING BASIS
' i'8802A 8802B 8835 8809A 88098 8840 O
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