ML20010D062
| ML20010D062 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Dresden, Davis Besse, Palisades, Perry, Fermi, Kewaunee, Point Beach, Byron, Braidwood, Prairie Island, Callaway, Duane Arnold, Clinton, Cook, Quad Cities, La Crosse, Big Rock Point, Zion, Midland, LaSalle, Zimmer, Bailly, Marble Hill  |
| Issue date: | 08/18/1981 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8108210414 | |
| Download: ML20010D062 (2) | |
Text
AUG 18 981
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% I Illinois Department of ff Nuclear Safety
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Mr. Gary N. Wright l-
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NOfgpye,,3' Deputy Director 1035 Outer Park Drive
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Gentlemen:
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The enclosed IE Bulletin 81-02, Supplement 1, titled " Failure of Gate Type Valves to Close Against Differential Pressure" was sent to the licensees listed below on August 18, 1981:
American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas and Electric Company Zimmer (50-358) 0 Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
Cresden 1, 2, 3 (50-10, 50-237, 50-249)
LaSalle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
Palisades (50-255)
Midland 1, 2 (50-329, 50-330) 56/
Dairylari<l Power Cooperative LACBWK (50-409) y/
hl Detroit Edison Company A pp.'
Fermi 2 (50-341) p7 y
8108210414 81081L PDR ADOc:' 05000010 g
Illinois Department of Nuclear Safety Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Iowa Electric Light & Power Compmay Duane Arnold (50-331)
Northern Indiana Public Serv ce Company Bai11y (50-367)
Northern States Power Company tfonticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Public Service of Indiana tia rble 11111 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346)
Union Electric Company Callaway 1, 2 (50-483, 50-48b1 Wisccasin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
Sincerely, o othy E.
.arroll, Chic Word Processing and Document Control Section
Enclosure:
IE lhilletin No. 81-02, Supplement I cc w/ encl:
tir. D. W. ::ane, Sargent & Lundy J. G. Keppler, RIII Division Directors, RIII P. R. Wohld, RIII Rill 8/18/81
SSIN No. 6820 Accession _No. :
( 8011040283 A ~
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IEBT1'-02, Supp.1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 18, 1981 IE BULLETIN N0. 81-02 SUPPLEMENT:
FAILURE OF GATE TYPE VALVES TO CLOSE AGAINST 1
DIFFERENTIAL PRESSURE Description of Circumstances:
i IE Bulletin No. 81-02, " Failure of Gate Type Valves 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 g-EMD) has applied the analytical methods developed for valves discussec in IE Bulletin 81-02 to the remaining motor operated gate valves that they manufacture.
These analy,es 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 pressurr.
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. 'riere 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 fm:ilities that Westinghouse believes to nave 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 addition, the Westinghouse determinations of operability and corrective action do not take into consideration the fact that the valves mey have been transferred between systems or that the system service conditions may have changed through design evolution.
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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 close under the current and/or intended service conditions.
Actione To Be Taken by Licensees:
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1.
Within 30 days of the issuance date of this bulletin supplement, ascertain /
whether any W-EMD manufactured motor-operated gate valves have been
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IEB 81-02. Supp.1 August 18, 1981 Page 2 of 4 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 ;eported 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 specifications for continued operation.
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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 clode, 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, are identified, report this to be the case.
No further action is required.
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 cannot be shown, either modify the affected valves so that they are qualified for the intended service or obtain qualified replacements prior to startup.
4.
Within 90 days of the issuance date of this bulletin supplement, cubmit 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 schedule for completing the corrective action.
For those cast; in which reports have already been submitted in accordance with the Technica1' 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.
IEB 81-02, Supp. 1 August 18,-1981 Fage 3 of 4 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 Re0ional Office and a copy shall be forwarded to the Director of the NRC Of fice of Inspection and Enforcement, Washington, D.C.
20555.
7 If you need additional information regarding this matter, please contact the appropriate NRC Regional Office.
This request for information was approved by
- 0MB under blanket clearance number 3150-0012 that expires December 31, 1981.
Comments on burden and duplication should be directed to the Office of Management 4 -
and Budget, Reports Management Room 3208, New Executive Office Building,
- Washington, D.C.
20503.
Attachments:
1.
Table 1, Partial List of Plants With Valves Manufactured by W-EMD-2.
Recently issued IE Bulletins i
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4 IEB 81-02, Supp.1 August 18, 1981 TABLE 1.
PARTIAL LIST OF PLANTS WITH VALVES MANUFACTURED BY W-EMD
.. Valves Supplied as Valves Supplied as Spares or Replacements Original Scope of Supply Arkansas Nuclear One 1 Beaver Valley 2 i
Beaver Valley 1 Braidwood 1, 2 Callaway 1, 2 Byron 1, 2 Catawba 1, 2 Callaway 1, 2 Diablo Canyon Comanche Peak 1, 2 Farley Shearon Harris 1, 2, 3
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Indian Point 2 Marble Hill 1, 2 Midlar.1 1, 2 Seabrook 1, 2 Oyster Creek _
South Texas 1, 2 Prairie Island 1, 2 Summer 1 St. Lucie 2 Vogtle 1, 2
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San Onotre 1, 2, 3 Watts Bar 1, 2 3
- Summer 1 Wolf Creek 1 Surry 2 Wolf Creek 1 a
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Attachaent 2 IEB 81-02, Supp. 1 August 18, 1981 RECENTLY ISSUED IE BULLETINS Bulletin No.
Subject Date Issued Issued To 81-03 Flow Blockage c7 Cooling 4/10/81 All nuclear powre Water to Safety System facilities with Components by Corbicula nn OL or CP Sp. (Asiatic Clam) and Mytilus Sp. (Hussel) 81-02 Failure of Gate Type Valves 3/9/81 All 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 with OL or CP 81-01 Surveillance of 1/27/81 All power reactor Mechanical Snubbers facilities with OL
& to spacified 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 3WRs with a CP 80-24 Prevention of Damage 11/21/80 All power reactor Due to Water Leakage facilities with Inside Containment OL or CP (October 17, 1980 Indian Point 2 Event) 80-23 Failures of Solanoid 11/14/80 All power reactor Valves Manufactured by facilities with Valcor Engineering OL or CP Corporation OL = Op3 rating License CP = Construction Permit
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