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Gentlemen:
The enclosed IE Bulletin No. 81-02, Supplement 1, " Failure of Gate Type Valves to Close Against Differential Pressure", is forwarded to you for action. A written response is required.
In order to assist the NRC in evaluating the value/ingact of each Bulletin on licensees, it would be helpful if you would provide an estimate of th manpower expended in conduct of the review and preparation of the report (s) reeired by the Bulletin.
Please estimate separately the manpower associated with corrective actions following identification of problems through the Bulletin.
If you desire a.1ditional information regarding this matter, please contact this office.
Sincerely, WL W
s yce H. Grier irector
Enclosure:
IE Bulletin No. 81-02, Supplement I w;th 2 attachments CONTACT:
D. L. Caphton (215-337-5287) i l
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Attar.hment )
TEB 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 Valicy 2 Beaver Valley 1 Braidwood 1, 2 Callaway 1, 2 Byron 1, 2 Catawba 1, 2 Callaway 1, 2 Diablo Canyon Comanch. Peak 1, 2 Farley Shearon Harris 1, 2, 3 Indian Point 2 Marble Hiii 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 Wolf Creek 1
IEB 81-02, Supplement 1 August 18, 1981 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
81-03 Flow Blockage of Cooling 4/10/81 Ali holders of a Water to Safety System power reactor Components by Carbicula 01 or CP Sp. (Asiatic Clam) ar.d My_tilus Sp. (Mussel) 81-02 Failure of a Gate Type 3/9/81 All holders of a Valves to Close Against power reactor Differentici Pressure OL or CP Revision 1 Surveillance of Mechanical 3/5/81 All holders of a 81-01 Snubbers power reactor OL or CP Supplement 5 Failure of Control Rods 2/13/81 All holders 80-17 to Insert During a Scram of a BWR power at BWR reactor OL or CP 81-01 Surveillance of Mechanical 1/27/81 All hoiders of a Snubb9rs power reactor OL or CP 80-25 Operating Problems 12/19/80 All holders of a with Target Rock Safecy-BWR power reactor Relief Valves at BWRs OL or CP Supplement 4 Failure of Control Rods 12/18/80 All holders of a to 80-17 to Insert During a BWR power reactor l
Scram at a BWR OL or CP 80-24 Prevention of Damage Due 11/21/80 All holders of a l
to Water Leakage Inside power reactor OL Containment (October 17, or CP 1980 Indian Point 2 Event) 80-23 Failures t( Solenoid 11/14/80 All holders of a Valves Manufactured by power reactor OL Valcor Engineering or CP Corporation 80-22 Automation Industries, 9/12/80 All holders of a Model 200-520-008 Sealed-radiography license Source Connectors
LIST OF HOLDERS OF A NUCLEAR POWER REACTOR OPERATING LICENSES AND CONSTRUCTION PERMITS RECEIVING IE BULLETIN NO. 81-02 SUPPLEMENT 1 (FOR ACTION)
Baltimore Gas and Electric Company Docket Nos. 50-317 ATTN:
Mr. A. E. Lundvall, Jr.
50-318 Vice President, Supply P. O. Box 1475 Baltimore, Maryland 21203 Boston Edison Company M/C Nuclear Docket No. 50-293 ATTN: Mr. A. V. Morisi Nuclear Operations Support Manager 800 Boylston Street Boston, Massachusetts 02199 Connecticut Yankee Atomic Power Company Docket No. 50-213 ATTN:
Mr. W. G. Counsil Vice President - Nuclear Engineering ano Operations P. O. Box 270 Hartford, Connecticut 06101 Consolidated Edison Company of Docket Nos. 50-03 New Yorr., Inc.
50-247 ATTN:
Mr. John O'Toole Vice President - Nuclear Engineering and Quality Assurance 4 Irving Place New York, New York 10003 Duquesne Light Company Docket No. 50-334 ATTN:
Mr. J. J. Carey Vice President Nuclear Division P. O. Box 4 Shippingport, Pennsylvania 15077 Jersey Central Power and Light Company Docket No. 50-219 ATTN:
Mr. Philip R. Clark Vice President - Nuclear GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 i
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2 Maine Yankee Atomic Power Company Docket No. 50-309 ATTN:
Mr. Robert H. Groce Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Metropolitan Edison Company Docket No. 50-289 ATTN: Mr H. D. Hukill Vice President ar.d Director of TMI-1 P. O. Box 480 Middletown, Pennsylvania 17057 Metropolitan Edison Company Docket No. 50-320 ATTN:
Mr. G. K. Hovey Vice President and Director of TMI-2 P. O. Box 480 Middletown, Pennsylvania 17057 Niagara Mohawk Power Corporation Docket No. 50-220 ATTN:
Mr. T. E. Lempges Vice President Nuclear Generation 300 Erie Boulevard West Syracuse, New York 13202 i
Northeast Nuclear Energy Company Docket Nos. 50-336 ATTN:
Mr. W. G. Counsil 50-245 Senior Vice President - Nuclear 50-423 Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN: Mr. S. L. Daltroff 50-278 Vice President Electri: Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN:
Mr. J. C. Brons Resident Manager P. O. Box 215 Buchanan, New York 10511
3 Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant AT!N: Mr. R. J. Pasternak Resident Manager P. O. Box 41 Lycoming, New York 13093 Public Service Electric and Gas Company Docket Nos. 50-272 ATTN: Mr. F. W. Schneider 50-311 Vice President - Production 80 Park Plaza Newark, New Jersey 07101 Rochester Gas and Electric Corporation Docket No. 50-244 ATTN:
Mr. John E. Maier Vice President Electric and Steam Production 89 East Avenue Rechester, New York 14649 Vermont Yankee Nuclear Power Corporation Docket No. 50-271 ATTN: Mr. Robert L. Smith Licensing Engineer 1671 Worcester Road Framingham, Massachusetts 01701 Yankee Atomic Electric Company Docket No. 50-29 ATTN: Pr. James A. Kay Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Duquesne Light Company Docket No. 50-412 ATTN:
Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power & Light Company Docket No. 50-363 ATTN:
Mr. J. T. Carroll Acting Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 08731 Long Island Lighting Company Docket No. 50-322 ATTN:
Mr. M. S. Dollock Vice President - Nuclear 175 East Old Country Road Hicksville, New York 11801
4 Niagara Mohawk Dower Corporation Docket No. 50-410 ATTN: Mr. G. K. Rhode Vice President System Project Management c/o Miss Catherine R. Seibert 300 Erie Boulevard, West Syracuse, NY 13202 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN: Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction - Nuclear 2 North Ninth Street Allentown, Pennsylvania 18101 Philadelphia Electric Company Docket Nos. 50-352 ATTN:
Mr. John S. Kemper 50-353 Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Nos. 50-354 ATTN: Mr. T. J. Martin 50-355 Vice President Engineering and Construction 80 Park Plaza - 17C Newark, New Jersey 07101 Public Service Company of New Hampshire Docket Nos. 50-443 ATTN:
Mr. W. C. Tallman 50-444 Chairman and Chief Executive Officer 1000 Elm Street Manchester, New Hampshire 03105
o SSIN No. 68 80110t J
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IE BULLETIN N0. 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, Westiaghouse 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 valv,es 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 closura 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 uader the utility order equip-ment specification conditions.
A list of power reactor facilities that Westinghouse believes to have the i
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 may have been transferred between systems or that 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 close under the current and/or intended service conditions.
M3 Actions To Be Taken by Licensees:
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1.
Within 30 days of th'_ issuance date of this bulletin supplement, ascertain wu. -
whether any W-EMD manufactured motor-operated gate valves have been g / //
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IEB 81-02. Supp. 1 August 18, 1981 Page 2 of 4 f
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 identiftad, report this to be the ease.
No further action is required.
t 3.
If any valves are identiftad as being installed, verify that they are capable of closing under their ::urrent 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 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.
E.
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 co.rrective 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 wFere they are required to close against a differential i
pressure.
2.
If no valves, other than those reported in response to IE Bulletin 81-02, are identified,' report this to be the case.
Na '"-ther action is required.
3.
If any valves are identified, verify that they are capable of closing under their intended limitirg 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 fur 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 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 informatien requested above.
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4 IEB 81-02, Supp. 1 August 18, 1981 Page 3 of 4 Reports, signed under oath or af firmation 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 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 Decen.ber 31, 1981.
Comments on burden and daglication should be directed to the Office of Management and Budget, Reports Management Room 3208, New Execu+.ive 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 l
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