ML20010D023
| ML20010D023 | |
| 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: | 08/20/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8108210385 | |
| Download: ML20010D023 (1) | |
Text
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n-yeu TEfS '&l-O A h pgicauntl American Electric Power Service Corporation N
D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas and Electr u Company w
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Zimmer (50 358)
,g The Cleveland Electric Illun.inating Company
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Perry 1, 2 (50-440, 50-441)
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Commonwealth Edison Company liraidwood 1, 2 (50-456, 50-457) c Djgu.cq ^ '[
c Byron 1, 2 (50-454, 50-455)
>Dresden 1, 2, 3 (50-10, 50-237, 50-249) i
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La Salle 1, 2 (50-373, 50-374)
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Quad-Cities I, 2 (50-254, 50-265)
M Zion 1, 2 (50-295, 50,304)
Consumers Power Company Big Rock Point (50-155)
Palisades (50-255)
Midland I, 2 (50-329, 50-330)
Dairyl_and Power Corporation LACBWR (50-409)
The Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 3 0-461, 50- 62)
Iowa Electric Light and Power Companj Duane Arnold (50-331T Northern Indiana Public Service Company liailly 150-367)
Northern States Power Company Monti'ello (50-263)
Pra i rie Island 1, 2 (50-282, 50-306)
Public Service of Indiana Marble 11111 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346)
$65/
s Union Electric Company
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Callaway 1, 2 (40-483, 50-486)
I ADD Wisconsin Electric Power Company
- N P-aint Beach 1, 2 (50-266, 50-301)
'C 5e Wisconsin Public Service Corporation Kewaunee (50-305)
Illinois Department of Nuclear Safety Gary N. Wright, Deputy Director 8108210385 810820 PDR ORO ESGILPH (ET@
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i SSIN No. 6820 Accession No.:
8011040283 IEB 81-02, Supp.1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 18, 1981 1
IE BULLETIN NO. 81-02 SUPPLEMENT:
FAILURE OF GATE TYPE VALVES TO CLOSE AGAINST DIFFERENTIAL PRESSURE Description of Circumstances:
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 Electrc-Mechanical Division Q-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-EMO 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 j
nuclear customers o' 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 canditions that their records i
show the valves will experience.
Where the valve, were provided as spares or replacements, they indicated the threshold diffarential pressure across the valves above which closure could not be assured 1nder the utility order equip-ment sp.:ification conditions.
A list of power reactor facilities that WestinghoJse believes to have the potentially affected valves is given in Table 1.
However, this list, as well I
as Westinghouse's notifications, does not take into censideration 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 -tha fact that the valves niay have been transferred between systems or thai, the system service conditions inay have changed through design evolution.
It is therefore essential that all facilities verify the presrice or absence of W-EMD manufactered motor-operated gate valves and also verify their ability to close under the current andhr intended :>ervice conditions Actions To Be Taken by Licensees:
4 1.
Within 30 days of the issuance date of this bulletin supplement, ascertain whether my W-EMD manufactured motor operated gate valves have been 9
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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 raported 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.
4.
If any valves are identified as sparer, 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 prier 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 cicse, 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, 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 toe valves failing to close, the corrective at. tion taken or planned, and the 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.
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IEB 81-02, Supp.1 August 18, 1981 Page 3 of 4 Reports, signed under aath 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 tre Director 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 information was approved by OMB under blanket clearance number 3150-0012 that expires December 31, 1981.
Comments on burden and duplication should be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D.C.
20503.
Attachments:
1.
Table 1, Partial List of Plants With Vaives Manufactured by W-EMD 2.
Recently issued IE Bulletins
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Attachment I l
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 Beaver Valley 1 Braidwood 1, 2 Callaway 1, 2 Byron 1, 2 Catawbal',J Callaway 1, 2 Diablo Canyon Comanche Peak 1, 2 Farley Marble Hill 1, 2 Shearon Harris 1, 2, 3 Indian Point 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
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Summer 1 Wolf Creek 1 1-Surry 2 Wolf Creek 1 1
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4 IEB 81-02, Supp.1 August 18, 3981 RECENTLY ISSUE 0 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 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 v.ith CP 80-17, Failure of Control Rods 2/13/81 All BWR facilities i
Supplement 5 to Insert During a Scram with OL'cr CP l
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 1
facilities & all BWRs with a CP Supplement 4 Failure of Control Rods 12/18/80 To specified BWRs i
to 80-17 to Insert During a Scram with an OL & All j
at a BWR BWRs 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 (Octcber 17, 1980 Indian Point 2 Event) 80-23 Failures of Solenoid 11/14/80 All power reactor Valves Manufactured by facilities with' Valcor Engir,aering OL or CP Corporation OL = Operating License CP = Construction Permit
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