ML20005B675
| ML20005B675 | |
| Person / Time | |
|---|---|
| Issue date: | 08/18/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| IEB-81-02-S01, IEB-81-2-S1, NUDOCS 8107230028 | |
| Download: ML20005B675 (5) | |
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SSIN No. 6820 Accession No.:
80100026; 9/073 3dodd[
IEB 81-02. Supp. 1 c,
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 18, 1981 IE BULLETIN NO. 81-02 SUPPLEMENT:
FAILURE OF GATE TYPE VALVES TO CLOSE AGAINST DIFFERENTIAL PRESSURE Description of Circumstances:
.ilure of Gate Type Vcives to Close Against Differential Pressure," identified several gate type valves that had been shown by tests and/or analyses by Westinghouse to have a potential for not closing against differential pressure.
As a part of its ongoing analysis program, Westinghouse Electro-Mechanical Division (W-EMD) has applied the analytical methods developed for valves discussed in IE Bulletin 81-02 to the remaining motor operated gate valves that they manufacture.
These analyses predict that closure problems could also be anticipated with 6, 8, 10, 12, 14, 16, and 18-inch nominal size valves in addition to 3-and 4-inch low pressure valves.
Thus, the entire line of W-EMD manufactured motor-operated gate valves has the potential for not closing against differential pressure.
Westinghouse has indicated to NRC that they have notified all of their domestic nuclear customers of this problem. When the valves were provided as original scope of supply, they also identified the recommended corrective action necessary to assure valve closure under the system service conditions that their records show the valves will experience. Where the valves were provided as spares or replacements, they indicated the threshold differential pressure across the valves above which closure could not be assured under the utility order equip-ment specification conditions.
A list of power reactor facilities that Westinghouse believes to have the potentially affected valves is given in Table 1.
However, this list, as well as Westinghouse's notifications, does not take into consideration the fact that the valves may have been transferred between facilities.
In additior., the Westinghouse determinations of operability and corrective action do not take into consideration the fact that the valves may have been transferred between systems ogjthat the system service conditions may have changed through design evolution.
It is therefore essential that all facilities verify the presence or absence of W-EMD manufactured motor-operated gate valves and also verify their ability to 5
close under the current and/or intended service conditions.
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1 IEB 81-02. Supp. 1 August 18, 1981 Page 2 of 4 Actions To Be Taken by Licensees:
1.
Within 30 days of the issuance date of this bulletin supplement, ascertain whether any W-EMD manufactured motor-operated gate valves have been installed, or are maintained as spares for installation, in safety-related systems where they are required to close against a differential pressure.
2.
If no valves, other than those reported in response to IE Bulletin 81-02, are identified, report this to be the case. No further action is required.
3.
If any valves are identified as being installed, verify that they are capable of closing under their current limiting normal and post accident service conditions.
If such cannot be shown, take corrective action on these affected valves and evaluate the effect that failure to close under any condition requiring closure would have on system (s) operability pursuant to the facility technical specif.ications for continued operation.
4.
If any valves are identified as spares, verify that they are capable of closing under their intended limiting normal and post accident service conditions.
If such cannot be shown, either modify the affected valves so that they are qualified for the intended service or obtain qualified replacements prior to installation.
5.
Within 45 days of the issuance date of this bulletin supplement, submit a report to NRC listing the affected valves identified in safety related systems, their service or planned service, and the maximum differential pressure at which they would be required to close, the safety consequences of the valves failing to close, the corrective action taken or planned, and the schedule for completing the corrective action.
Actions To Be Taken by Construction Permit Holders:
1.
Ascertain whether any W-EMD manufactured motor operated gates valves are or will be installed, or maintained as spares for installation, in safety-related systems where they are required to close against a differential pressure.
2.
If no valves, other than those reported in response to IE Bulletin 81-02, i
are identified, report this to be the case. No further action ~is required.
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3.
If any valves are identified, verify that they are capable of closing under' their intended limiting normal and post accident service conditions.
If such gannot be shown, either modify the affected valves so that they are qualffied for the intended service or obtain qualified replacements prior to startup.
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i IEB 81-02, Supp. 1 i
August 18, 1981 J
Page 3 of 4 4.
Within 90 days of the issuance date of this bulletin supplement, submit a report to NRC listing the affected valves identified for use in safety-related systems, their planned service, the maximum differential pressure at which they would be required to close, the safety consequences of the valves failing to close, the corrective action taken or planned, and the t
schedule for completing the corrective action.
For those cases in which reports have already been submitted in accordance with the Technical Specification,10 CFR Parts 21 and/or 50.55(e), this information need not be resubmitted.
Rather, licensees or construction permit holders should reference this earlier report and submit only the additional information requested above.
Reports, signed under oath or affirmation under the provisions of Section 182a of the Atomic Energy Act of 1954, shall be submitted to the Director of the appropriate NRC Regional Office and a copy shall be forwarded to the Director J
of the NRC Office of Inspection and Enforcement, Washington, D.C.
20555.
If you need additional information regarding this matter. please contact the appropriate NRC Regional Office.
This request for inforn.ation was approved by OMB under blanket clearance number 3150-0012 that expires December 31, 1981.
Comments on burden and duplication should be directed to.he Office of Management and Budget, Reports Management Room 3208, New Executive Cffice Building, Washington, D.C.
20503.
Attachments:
o 1.
Table 1, Partial List of Plants With Valves Manufactured by WEMD 2.
Recently issued IE Bulletins d
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IEB 81-02, Supp. 1
, J August 18, 1981 i
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TABLE 1.
PARTIAL LIST OF PLANTS WITH l
VALVES MANUFACTURED BY W-EMD
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Valves Supplied as Valves Supplied as Spares or Replacements Original Scope of Capply 4
i Arkansas Nuclear One 1 Beaver Valley 2 Beaver Valley 1 Braidwood 1, 2 j
Callaway 1, e Byron 1, 2 Catawba 1, 2 Callaway 1, 2 Diablo Canyon Comanche Peak 1, 2 Farley Shearon Harris 1, 2, 3 Indian Point 2 Marble Hill 1, 2 Midland 1, 2 Seabrook 1, 2 Oyster Creek South Texas 1, 2 Prairie Island 1, 2 Summer 1 St. Lucie 2 Vogtle 1, 2 San Onofre 1, 2, 3 Watts Bar 1, 2 Summer 1 Wolf Creek 1 Surry 2 1
Wolf Creek 1
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IEB 81-02, Supp. 1 August 18, 1981 RECENTLY ISSUED IE BULLETINS Bulletin No.
Subject Date issued Issued To 81-03 Flow Blockage of Cooling 4/10/81 All nuclear power Water to Safety System facilities with Components by Corbicula an OL or CP Sp. (Asiatic Clam) and Mytilus Sp. (Mussel) 81-02 Failure of Gate Type Valves 3/9/81 A?1 power reactor to Close Against Differential facilities with an Pressure OL or CP 81-01 Surveillance of Mechanical 3/5/81 All power reactor Rev. 1 Snubbers facilities with an OL & specified facilities with CP 80-17, Failure of Control Rods 2/13/81 All BWR facilities Supplement 5 to Insert During a Scram w'th OL or CP 81-01 Surveillance of 1/27/81 All Power reactor Mechanical Snubbers facilities with OL
& to specified facilities with CP 80-25 Operating Problems with 12/19/80 All BWR facilities Target Rock Safety-Relief with OL & specified Valves at BWRs near-term OL BWR facilities & all BWRs with a CP Supplement 4 Failure of Control Rods 12/18/80 To specified BWRs to 80-17 to Insert During a Scram with an OL & All at a BWR BWRs kith a CP 80-24 Prevention of Damage 11/21/80 All powet reactor Due to Water Leakage facilities with Inside Containment OL or CP (October 17, 1980 l
4I Indian Point 2 Event) 80-23 Failures of Solenoid 11/14/80 All power reactor
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Valves Manufactured by facilities with Valcor Engineering OL or CP Corpora tion OL = Ooerating License CP = Construction Permit
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