ML19350E411
Text
.
~
BI$40 Gentlemen:
The enclosed IE Information Notice No. 8!-14 " Potential Overstress of Shafts on Fisher Series 9200 Butterfly Valves with Expandable T Rings," is forwarded to you for information. No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, Boyce H. Grier Director
Enclosure:
IE Information Notice No. 81-14 with 1 attachment CCNTACT:
L. E. Tripp (215-337-5282)
P 8106230016
.a LIST OF HOLDERS OF NUCLEAR PCWER REACTOR OPERATING LICENSES RECEIVING IE INFORMATION NOTICE NO. 81-14 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, Haryland 21203 Boston Edison Company M/C Nuclear Cocket 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 Docket Nos. 50-03 New York, Inc.
50-247 ATTH: Mr. John D. O'Toole Assistant Vice President - Nuclear Affairs and Quality Assurance 4 Irving Place New York, New York 10003 Ouquesne Light Company Occket No. 50-334 ATTN: Mr. C. N. Dunn Vice President Operations 01 vision 435 Sixth Avenue Pittsourgh, Pennsylvania 15219 Jersey Central Power and Light Company Docket No. 50-219 ATTN: Mr. Ivan R. Finfrock, Jr.
Vice President Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 08731
t 2
Maine Yankee Atomic Power Company Oceket No. 50-309 ATTN: Mr. Robert H. Groce Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Metropolitan Edison Company Occket No. 50-289 ATTN: Mr. H. D. Hukill Vice President and Ofrector of TMI-l P. O. Box 480 Middletown, Pennsylvania 17057 Metropolitan Edison Company Occket No. 50-320 ATTN: Mr. G. K. Hovey Vice President and 01 rector of TM!-2 P. O. Box 480 Middletown, Pennsylvania 17057 Niagara Mohawk Power Corporation Docket No. 50-220 ATTN: Mr. T. E. Lempses Vice President Nuclear Generation 300 Erie Boulevard West Syracuse, New York 13202 Northeast Nuclear Energy Company Occket Nos. 50-336 ATTN: Mr. W. G. Counsil 50-245 Senior Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN: Mr. S. L. Daltrof f 50-278 Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Occket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN: Mr. J. C. Brons Resident Manager P. O. Box 215 Buchanan, New York 10511
.L.
s 3
-Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. R. J. Pasternak Resident Manager
.P. O. Box 41 Lycoming, New York 13093 Public Service Electric and Gas Company Occket Nos. 50-272 ATTN: Mr. F. W. Schneider 50-311 Vice President - Production 80 Park Plaza - 15A Newark, New Jersey 07101 Rochester Gas and Electric Corporation Occket No. 50-244 ATTN: Mr. John E. Mater Vice President Electric and Steam Production 89 East Avenue Rochester, 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 Occket No. 50-29 ATTN: Mr. James A. Kay Senior Engineer-Licensing 1671 Worcester Road Framingham, M ssachusetts 01701 O
1
SSINS No.:
6835 4
/
fFP Accession No.:
f g
MY 041985 21
.4, %a%enE ** f/
UNITED STATES a
S NUCLEAR REGULATORY CCMMISSICN s
OFFICE OF INSPECTICN AND ENFCRCEMENT WASHINGTCN, D.C.
20555 April 17,1981 IE Information Notice No. 81-14: POTENTIAL OVERSTRESS OF SHAFTS ON FISHER SERIES 9200 BUTTERFLY VALVES WITH EXPANCABLE T RINGS Cescription of Circumstances:
t l
Northern States Power Company recently informed NRC that the design of certain butterfly valves at Monticello Nuclear Generating Station contained a destga error that shows the calculated maximum shaft stress to be underestimated.
The valves affected are Fisher Controls Company Series 9200 butterfly valves (6 to 48 inches) wie, egandable T rings (inflatable seals) manufactured from 1968 to 1972.
In the calculation of the shaft stress, the length between the shaft bushing and the attachment of the shaft to the valve disc used in the stress calculations was shorter than the actual length.
Frca discussions with the valve manufacturer, the cause of the difference in the design calcu-lation dimension and the actual diinension was that the shaft bushings were recessed into the valve body to acccmmodate the pneumatic passages for the inflatable seals. Evaluation of the design error for the valves at Monticello indicate that the maximum thaft stress in the closed position remains less than the minimum yield strength of the shaft material. The licensee intends P
to keep the affected valves closed while operating and plans to replace the shafts with ones of higher strength material.
The potential consequences of the design error is that, under accident loading conditions, there is a possibility for excessive deformation of the shaft.
Therefore, these valves when closed under the dynamic conditions of a LCCA or, if already closed, may not seal essantially leaktignt.
Since these valves are used primarily in the containment purge and vent lines, a substantial safety ha:ard would exist if these valves could not be closed or if there was excessive leakage past these valves. Containment integrity therefore could not be assured.
The operability of containment purge and vent valves is item II.E.4.2 in the TMI Action Plan.
l The facilities identified that may have the Fisher valves include Cuane Arnold, Monticello, Palisades, Peach Bettem Units 2 and 3, and Point Beach Units 1 and 2.
Discussions with the valve vendor indicate that the reviews of the valve calculations affected should be completed by mid-April.
This information is provided as an early notification of a significant safety satter that is still under review by the NRC staff.
It is expected that licensess will review the information for possible applicability to their p ants.
If NRC evaluations so indicate, further licensee actions may be j
requested.
3..
'., - + '.
IN 81-14 April 17, 1981 Page 2 of 2 l
No written response to this information notice is required.
If you need additional information with regard to this matter contact the Girector of the appropriate NRC Regional Office.
Attachment:
Recently issued Information Notices O
4 4
e n
a.--
.1 IN 81-14 April 17, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Setfect Date Issued to Notice No.
Issued 81-13 Jammed Source Rack in 4/14/81 Specified Irradiator a Gamma Irradiator Licensees 81-12 Guidance en Order 3/31/81 All holders of a Issued January 9,1981 power reactor Regarding Automatic OL or CP Control Rod Insertion on Low Control Air Pressure 81-11 Alternate Rod Insertion 3/30/81 All holders of a for BWR Scram Represents SWR power reactor a Potential Path for OL or CP Loss of Primary Coolant 81 Inadvertant Containment 3/25/81 All holders of a Spray Due to Personnel power reactor Error OL or CP 81-09 Degradation of Residual 3/26/81 All holders of a Heat Removal (RHR) power reactor Systen OL or CP 81-08 Repetitive Failure 3/20/81 All holders of a of Limitorque SMS-4 power reactor Motor-To-Shaft OL or CP 81-07 Potential Problems 3/16/81 All holders of a with Water-Soluble power reactor OL Purge Dam Materials or CP Used During Inert Gas Welding 81-06 Failure of ITE Model 3/11/81 All holders of a 600 Circuit Breaker power reactor 81-05 Degraded DC System 3/13/81 All holdars of at Palisades a power reactor OL or CP 81-04 Cracking in Main 2/27/81 All holders of a Steam Lines power reactor OL or CP