ML20009D227
| ML20009D227 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Millstone, Calvert Cliffs, Peach Bottom, Salem, Nine Mile Point, Indian Point, Oyster Creek, Hope Creek, Pilgrim, Susquehanna, Seabrook, Limerick, Vermont Yankee, Haddam Neck, Ginna, Sterling, Yankee Rowe, Maine Yankee, Reed College, FitzPatrick, 05000363, 05000516, 05000517, Shoreham, Crane  |
| Issue date: | 04/09/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8107230297 | |
| Download: ML20009D227 (4) | |
Text
LIST OF HOLDERS OF A NUCLEAR PCWER REACTOR OPERATING LICENSE OR CONSTRUCTION PERMIT RECEIVING IE BULLETIN N0. 81-02 (FOR ACTION)
Baltimore Gas and Electric Company Docket Nos. 50-317 ATTH: 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 and Operations P. O. Box 270 Hartford, Connecticut 06101 Consolidated Edison Company of Occket Nos. 50-03 New York, Inc.
50-247 ATTN: Mr. John O'Toole Assistant Vice President - Nuclear Affairs and Quality Assurance 4 Irving Place New York, New York 10003 Duquesne Light Company Occket No. 50-334 ATTN: Mr. C. N. Dunn Vice Aresident Oper-. ions Division 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power and Light Company Occket No. 50-219 ATTN: Mr. Ivan R. Finfrock, Jr.
Vice President Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 03731 8107230297 810409 DR ADOCK 05000 n
w 2
Maine Yankee Atomic Power Company Docket No. 50-309 ATTN: Mr. Robert H. Grace Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 i
Metropolitan Edison Company Docket No. 50-289 ATTN: Mr. H. O. Hukill Vice President and Director of TMI-l 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 Northeast Nuclear Energy Comoany Docket Nos. 50-336 i
ATTN: Mr. W. G. Counsil 50-245 Senior Vice President - Nuclear 50-423 Engineering and Operations P. O. Box 270 i
Hartford, Connecticut 06101 Philadelphia Electric Company Occket Nos. 50-277 ATTN: Mr. S. L. Daltroff 50-278 I
Vice President Electric Production 2301 Market Street l
Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN:
Mr. S. S. Zulla Resident Manager P. O. Box 215 Buchanan, New York 10511 l
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3 Power Authority of the State of New York Occket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. R. J. Pasternak Resident Marager 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 Occket 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 Occket 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: Mr. James A. Kay Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Duquesne Licht Company Docket No. 50-412 ATTN: Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power & Light Company Decket No. 50-363 ATTN: Mr. I. R. Finfrock, Jr.
Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Long Island Lighting Company Docket No. 50-322 ATTN: Mr. M. S. Pollock Vice President - Nuclear 175 East Old Country Road i
Hicksville, New York 11801
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Long Island Lighting Company Docket Nos. 50-516 ATTN: Mr. Charles P. Davis 50-517 Senior Vice President 250 Old Country Road Mineola, New York 11501 Niagara Mohawk Power Corporation Occket 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. Jonn S. Kemper 50-353 Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Nos. 50 15 ATTN: Mr. T. J. Martin 50-1.
Vice President Engineering and Construction 80 Park Plaza - 17C Newark, New Jersey 07101 Public Service Company of New Hampshire Occket Nos. 50-443 ATTN: Mr. W. C. Tallman 50-444 Chairman and Chief Executive Officer 1000 Elm Street Manchester, New Hampshire 03105 Rochester Gas & Electric Corporation Occket No. 50-485 ATTN:
Mr. J. E. Arthur Chief Engineer 89 East Avenue Rochester, New York 14649
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Accession No.:
N{V@lWfjff h 8011040283 p
d IES 81-02
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I98I UNITED STATES D $ ma 3/ '
NUCLEAR REGULATORY CCMMISSION j
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OFFICE OF INSPECTION ANC ENFORCEMENT l
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WASHINGTON, D.C.
20555 April 9, 1981 IE Bulletin No. 81-02,-
FAILURE OF GATE TYPE VALVES TO CLOSE AGAINST DIFFERENTIAL PRESSURE Description of Circumstances:
As a part of its pressurized water reactor (PWR) Safety and Relief Valve Testing Program, the Electric Power Research Institute (EPRI) conducted limited testing of a number of valves used on PWRs as power-operated relief valve (PORV) isolation or block valves.
These tests indicate a number of cases in which certairr of these valves failed to fully close under conditions that approximated those of their intended service (f.e., saturated steam at approximately 2,400 psi).
The valves that failed to fully close are gate type motor-operated valves that may be used in various safety-related applications in addition to PORV block valves.
Backcround on EPRI Testino:
The proposed full-scale qualification testing of PCRV block valves, with a completion date of July 1,1982, was first provided to the utilities in a September 5, 1980, draft of NUREG-0737. The item was formally issued, with Commission approval, in NUREG-0737 on October 31, 1980.
The block valve qualification testing was proposed in NUREG-0737 primari'y as an
. additional means of reducing the number of challenges to the emergency core cooling system and the safety valves during plant coeration.
In anticipating a request for PWR block valve testing, EPRI decided to make provisions for the -installation of block valves between the test steam source and the test PORV in July 1980 at the Marshall test facility.
The Marshall test facility is a full-ficw steam test facility owned by Cuke Power Comcany.
Test PORVs had been carefully selected, with close coordination between EPRI,.
its consultants and PWR utilities, to assure that PORVs representative of those in service or intended for service would be tasted.
However, for the block valves that have been tested concurrently, this selection process was not followed because an NRC block valve test program had not been formulated.
Therefore, seven readily available valves were obtained and tested by EPRI, i
primarily to obtain some general baseline information on block valve closure capability.
t l
For the block valves that were tested, EPRI had not established, at least at the time'_ of testing, the copulation of plants, either coerating or under construction, that might have a valve of the type needed for testing.
In addition, it should be noted that the test conditions used at Marshall to date were only those :nat were determined to be aoplicable for steam testing of PORVs.
ISB 81-02
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April 9,1981 l
Page 2 of 4 These test conditions were selected after review by EPRI, utilities, and PWR NSSS vendors.
NRC staff also reviewed and concurred with the test. conditions.
To date, there has been..o sf ailar specific determination by EPRI or the NRC staff as to the relevance of the Marshall block valve tsst conditions to the conditions in any specific PWR plant under which a block valve should be able to close to isolate a stuck-open PORV.
To date, EPRI has tested a total of seven PORV block valves, all at the Marshall facility.
During these tests, the following valves failed to fully close during the EPRI PORV block valve testing:
1.
Westinghouse E!ectro-Mechanical Division (W-EMD) 3-inch Valves - These valves, wnich are manufactured my y-EMO, can :e icentifiec Oy the yoke-mounted nameplates that are stampec '"#ESTINGHOUSE" and include " VALVE IDENT." and " VALVE I.D." numoers given in Table 1.
Supplemental analyses and water testing, performed by W-EMD, determined that a 4-inch valve also would not close fully and therefore is included in this bulletin. The nameplate data on this valve are given in Table 1.
These analyses and tests also dete mined the threshold differential pressure across the valves above which closure cannot be assured. These values are given in Table 1.
A list of power reactor facilities believed to have the affected valves is given in Table 2.
It is our understanding that W-EMD has notified these facilities of the failure of these valves to fulTy close.
2.
Borg-Warner Nuclear Valve Division (BW-NVD) 3-inch 1500-oound Motor-Operated Gate Valves - These valves can ce icentifled by SW-NVQ part numoers 75460, 77910, and 79190.
Supplemental testing to determine threshold differeatial pressures for less severe service has yet to be completed. A list of power reactor facilities believed to have the affected valves i', given in Table 3.
SW-NVD has submitted a 10 CCR Part 21 report in which they indicated that they have notified these facilities of l
the failure of these valves to fully close.
(Note:
Similar valves with l
BW-NVD part numbers 74380 and 74380-1 have been modified, recested, and l
demonstrated to close under test conditiens. As a resu't, they are not included in this bulletin.)
3.
Anchor Darling 3-inch 1540-ocund Ocuble-Oisc Valve - This valve, the first l
of a series of specially designec valves, nas twaa modified, retested, and l
demonstrated to close under test conditions.
The remaining va' /es will be similarily modified curing manufacture. As a result, they are not included I
in this bulletin.
It must be cautioned that Tables 2 and 3 may not be umplete.
For example, the j
staff is aware of one power reactor facility that obtained affected valves from another inventory.. For this reason, this bul:etin is applicable to all power l
reactor facilities with an operating license or construction permit.
The tests.and analyses performed to date raise coucts as to the ability of the affected valves to close under less severe service conditions. These valves have also been supplied for utilization i.' a number of safety-related
IEB 81-02 April 9, 1981 Page 3 of 4 applications.
In the case of the W-EMD valves, they are also provided as spares or replacements through direct sales from the manufacturer.
For this reason, this bulletin is applicable to the affected valves that are required to close with a differential pressure across them in safety-related systems or as PORV block valves.
The responsibility for notification and corrective actions based on adverse test results continues to lie with the utilities and vendors in the industry.
NRC will continue to monitor the progress of the qualification program. All adverse test data will continue to be evaluated on a case-by-case basis.
NRC staff will take appropriate action, if necessary, to assure that the necessary corrective acticas are made in a timely manner.
Actions to be Taken by Licensees:
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1.
Within 30 days of the issuance date of tais bulletin, ascertain whether any of the affected valves have been installed, or are maintainad as spares for installation, where they are required to close with a differential pressure across them in safety-related systems or as PORV block valves.
The differ-ential pressures of concern include the follow'ng:
a.
For the W-EMD manuf actured valves, va, lues in excess of the. threshold values in Table 1.
b.
For the BW-NVD valves, any value.
2.
If no affected valves are identified, report this to be the case and +
ignore the items below.
3.
If any affected valves are identified as being installed, take corrective action and evaluate the effect that fcilure to close under any condition l
requiring closure would have on system (s) operability pursuant to the facility technical specifications for continued operation.
4.
If any affected valves are identified as spares, either modify the valves so that they are qualifie; per the intended service or obtain qualified replacements prior to installation.
5.
'Within 45 days of the issuance date of this bulletin, submit a recort to NRC listing the affected valves identified, their service or planned service, the maximum differential pressure at which they would be required to close, the safety consequences of che valve's failure to close, the l
l corrective action taken or planned, and the schedule for completing the corrective action.
Actions to be Taken by Construction permit Holders:
l 1.
Ascertain whether any of the affected valves are or will be installed or l
maintained as spares for installation where they are required to close i
IEB 81-02 April 9, 1981 Page 4 of 4 with a differential pressure across them in safety-related systems or as PORV block valves.
The differential pressures of concern include the following:
a.
For the W-EMD manufactured valves, values in excess of the threshold values in Table 1.
b.
For the BW-NVD valves, any value.
2.
If no affected valves are identified, report this to be the case and ignore the items below.
3.
If any affected valves are identified, either modify the 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, submit a report to NRC listing the affected valves identified, their plannec service, the maximum cifferential pressure at which they would be required to close, the safety coasaquences of the valve's failure to close, the corrective action taken or planned, and the schedule for completing the corrective action.
Far 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 r.eed-not be resubmitted.
Rather, licensees or construction parmit holders should reference this earlier report and submit only the additional information requested above.
Reports, signed under oath or affirmation uncer the provisions of Section 182a of the Atomic Energy Act of 1954, shall be submitted to the Director of the appropriate NRC Recional Office and a copy shall be forwarded to the Dir ector of the NRC Office af Inspection and Enforcement, Washington, D.C.
20s55.
If you need addit'onal information regarding this matter, please contact the appropriate NRC Regional Office.
This request for information was approved by GAO under blanket clearance numcer R0072 that expires November 30, 1983.
Comment on burden and dupiteation should be directed to Office of Management and Budget, Room 3201, New Executive Office Building, Was51ngton, D.C.
20503.
Attachments:
l 1.
Table 1 - Identification of W-EMD Manufactured Valves and Differantial Pressure Limits for Operation 2.
Table 2 - Partial List of Plants With Affected Valves Manufactured by W-EMD 3.
Table 3 - Partial List of Plants With Affected Valves Manufactured by SW-NVD a.
Recently issued IE Bulletins
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Aoril 9,1981 IES 81-02 TABLE 1.
IDENTIFICATION OF W-EMD MANUFACTURED VALVES AND DIFFERENTIAL PRESSURE LIMITS FOR VALVE OPERATICN Nom 1ral W-EMD Valve Nodel
" VALVE A***
Size (in.)
Reference IDENT.""
" VALVE I.O. "**
(esid) 3 3GM88 03000GM88 3GM58 or 3GM73 or 3GM88 1300 3GM88 0.?D02GM88 3GM58 or 3GM78 or 3GM38 1500 3GM99 03001GM99 3GM58 or 3GM73 or 3GM88 750 4
- 4GM88, 0400GGM88 4GM73 or 1GM88 750 4GM88 04002GM88 4GM78 or 4GM88 750 4
4GM87 04000GM87 4GM77 750 4GM87 04C02GM87 4GM77 750 This number is found on the yoke-mounted nameplate and occupies tha first nine positions of a 24 posit'on number.
It is used in evaluating the functional AP requirements.
This number is found on the yoke-morated nameplate and occupies the first three positions of a six position number. Valves sold as spares or replacements may not contain this numcer.
Pressure below which valve will close (as shippec).
Notes: A " position" may contain mere than one character.
The threa position
" VALVE I.D." numcer consists of five digits in the three positions; for example, 3 GM 78.
All nameplates have " VALVE IDENT." numbers, but those sold as spares or replacements may nct have "VE.VE I.D." numbers.
The " VALVE ICENT.'
aumber includes the manufacturer's model reference, and the " VALVE I.O." number is a reference to the valve system application.
The
" VALVE I.O." number also appears on Westinghouse valve indexes and system flow diagrams.
There is no reference to the " VALVE IDENT."
number on these indexes or flow diagrams.
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Attachm2nt 2 April 9, 1981 IEB 81-02 TABLE 2.
PARTIAL LIST OF PLANTS WITH AFFECTED VALVES MANUFACTURED BY W--30 i
" VALVE IDENT." Number 0400 CGM 88 04002GM88 03000GM88 04000GM87 03002GM88 03001GM99 04002GM87 Plant Operating plants (supplied as f.:c ;s or replacements except as noted):
Seaver Valley 1 X
Connecticut Yankee X
FarTey 1, 2 X"
Indian Point 2 X
Kewaunee X
North Anna 1, 2 X
Oconee 1, 2, 3 X
X San Onofre 1 X
Surry 1, 2 X
X X
Zion 1, 2 X
Nonoperating plants (supplied as original scope of supply except as noted):
Seaver Valley 2 X
X Braidwood 1, 2 X
X l
Syron 1, 2 X
X Callaway 1, 2 X
X Comanche Peak 1, 2 X
X Harris 1, 2, 3, 4 X
X Jamesport 1, 2 X
X Marble Hill 1, 2 X
X San Onofre 2, 3 X**
l Seabrook 1, 2 X
X South Texas 1, 2 X
l Summer X
X l
Vogtle 1, 2 X
X Watts Bar 1, 2 X
X Wolf Creek X
X l
l
" Transferred from inventory at another plant.
- Spares or replacements.
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t
~4 Attachmint 3 April 9, 1981 1
IES 81-02 i
TABLE 3.
PARTIAL LIST OF PLANTS WITH AFFECTED VALVES MANUFACTURED BY BW-NVD Plant NVD-P/N Arkansas Nuclear One, Unit 2 75460 Bellefonte 79190 Pa!c Verde 77910 i
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April 9, 1981 RECENTLY ISSUED IE RULLETINS Bulletin Subject Data Issued Issued To No.
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 holders of a Snuubers power reactor OL or CP 80-25 Operating Problems 12/19/80 All holders of a with Target Rock Safety-8WR 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 Scram at a BWR OL or CP 80-24 Prevention of Damage Due 11/21/80 All holders of a to Water Leakage Inside power reactor OL Containment (October 17, or CP 1980 Indian Point 2 Event) 80-23 Failures of Solencid 11/14/80 All holders of a l
Valves Manufactured by power reactor OL Valcor Engineering or CP l
Corporation 1
1 80-22 Automation Industries, 9/12/80 All holders of a Model 200-520-008 Sealed-radiography license Source Connectors 80-21 Valve Yokes Supplied by 11/6/80 All holders of a l
Malcolm Foundry Company, Inc.
power reactor OL or CP Revision 1 Baron Loss from 8/29/80 All holders to 79-26 BWR Control Blades of a SWR power reactor OL l
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