ML19225A423
| ML19225A423 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Perkins, Cherokee  |
| Issue date: | 06/06/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7907190159 | |
| Download: ML19225A423 (2) | |
Text
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'o UN11 LD STATES 8 ', s., (f[,7.
N'JCLEAR REGULATORY COMMISSION 3
% [*E 3
REGION 11
f 101 MARIETTA ST., NW., SUITE 310o o,
ATL ANTA, G E oRGI A 30303 J1[(h.
g..%.r JUN 6 1979 In Reply Refer To:
RII:JP0 50-413, 50-414 50-488, 50-489 5.0-49.,::50-491) 0
/50-492, 50-493 w._ ~- s Duke Power Company Attn:
L. C. Dail, Vice President Design Engineering P. O. Box 33189 Charlotte, North Carolina 28242 Gentlemen:
Enclosed is supplenent IE Bulletin 79-01 A.
It requires action by you with regard to power reactor f acilities with an operating license except for the 11 SEP plants which are listed in Enclosure 3.
This Bulletin is also being sent for information to the 11 SEP plants and all power reactor f acilities with a construction permit. No action or written response is required for construction permit f acilities or the 11 SEP plants.
Should you have questions regarding this Bulletin or the actions required of yoti, please contact this office.
Sincerely, g, Ja=es P. O'Reill]y Director
Enclosures:
1.
List of IE Bulletins Issued in the past 12 months 3.
List of SEP Plants (11)
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7007190359
JUN 6 1979
. Duke Power Company cc w/ encl:
D. G. Beam, Project Manager i
Post Office Box 223 Clover, South Carolina 29710 J. T. Moore, Project Manager Post Office Box 422 Gaffney, South Carolina 29340 G
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UNITED STATES NUCLEAR REGlLATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 6, 1979 IE Bulletin No.79-01A SUPPLEMENT NO.79-01A TO IE BULLETIN 79 ENVIRONMENTAL QUALIFICATION OF CLASS lE EQUIPMENT (DEFICIENCIES IN THE ENVIRONMENTAL QUALIFICATION OF ASCO SOLEN 0ID VALVES)
Description of Circumstances:
Recently, a noncompliance report under 10 CFR Part 21 was received by the NRC frcm the Henry Pratt Company, manufacturer of butterfly valves which are installed in tre primary containment at the Three Mile Isisnd Unit 2 Nuclear Station. These butterfly valves are used for purge and exhaust purposes and are required to operate during accident conditions. The report discusses the use of an unqualified solenoid valve for a safety-related valve function which requires operation under accident conditions. The solenoid valve in question is Catalogue No. HT-8331A45, manufactured by the Automatic Switch Company
.' Acro) of Florham Park, New Jersey. This pilot valve is used to pilot control c'3e pneumatic valve actuators which are tratalled on the containment ventila-tion butterfly valves at this facility.
The deficiency in these solenoid valves identified in the Part 21 Report concerns the parts made of acetal plastic materia).
The acetal 'isc holder 1
asse=L.y and bottom plug in the pilot valve assemoly are stated by ASCO to have a maximum service limit of 400,000 Rad integrated dosage and 200 degrees F temperature. According to ASCO, exposure of these acetal plastic parts to specified maximum environmental conditions may render the solenoid pilot valve inoperable which would cause the associated butterfly valve to malf"nction.
Further investigation at ASCO by the NRC staff has revealed that the valve seals in most ASCO solenoid valves contain Buna "N" elastomer material, which reportedly has a maximum service limit of 7,000,000 Rnd integrated dosage and 180 degrees F temperature. The investigation further revealed that ASCO has available a line of qualified solenoid operated pilot valves (ASCO Catalogue No. NP-1) which have no plastic parts, utiliza ethylene propylene or viton elastomers and have a continuously energized operating life of four years, under normal embient conditions up to 140 degrees F.
According to the manu-facturer, at the end of this period, the coil, manual operator (optional fea-ture) and all resilient parts must te replsced. These preventive maintenance instructions are specified in the installation and instructior. bulletins which are provided to the purchaser wit each shipment of solenoid va.'ves.
The final items of concern identified during this investigation deals with tt.e application of CTzss "A", "B",
or "F", solenoid coils which are exposad to an accicent environment.
In this regard, ASCO reprecentatives stated that the bb
IE Bulletin No. 79-OlA June 6, 1979 Page 2 of 3 high temperature coils identified as Class "HT" or "HB" are the only coils con-sidered suitable for service under accident conditions; whereas, Class "A", "B",
and "F" coils are not.
With respect to the corrective measures to be taken to resolve the above concerne, LSCO recommends the follewing:
1.
The parts of the solencid valve made of acetal plastic material should be replaced with similar parts made of metal which can be provided by ASCO.
2.
The valve seals and gaskets which are made of Buna "N" material should be replaced with either ethylene propylene or viton elastomers, considered by ASCO as suitable for the service intended.
3.
Review and datermine that the coils of the solenoid valves installed inside contain=ent are Class "HT" or "HB" as required for high temperature environmental conditions.
4.
Review and determine that the solenoid enclosures instelled inside contain-ment have at least a NEMA 4 enclosure rating.
5.
Establish a preventive maintenance program to assure replacement of those valve parts identified above in the time period recommended in the appro-priate ASCO valve bulletin.
6.
ASCO also stated that all unqualified solenoid valves inside containment be retrofitted to qualified ASCO No. NP-1 valves in lieu of the above.
7.
Questions from licensees to ASCO concerning corrective measures should reference both catalogue and serial numbers of each valve in question.
These numbers are stamped on the metal nameplate on e-
'noid valve.
Action to be Taken by Licensees of all Power Peactor Facilities (except those 11 SEP Plants ?.isted on Enclosure 3) with an Operating License:
1.
Determine whether or not ASCO solenoid valves are used or planned for use in safety-related systers ct your facility (ies).
2.
If such valves are used or planned for usc, identify the safety system involved and determine that:
(a) valves which could be subjected to a LOCA environment are qualified to t'at environment.
Specificclly that no parts made of acetal plastic or Buna "N" materials or Class "A", "B",
or "F" solenoid coils are used in such valves; (b) a preventive main-tenance program is being conoucted such that the solenoid coil, the manual operator (if applicable), and the resilient parts of the valve are being replaced in accordance with e.he time period established by the manufacturer and documented as the qualified life of the assembled component.
336 J,0
IE Bulletin No.79-01A June 6, 1979 Pcge 3 of 3 3.
All holders of operating licenses of power reactor facilities are obligated to meet the review and reporting requirements established in previously issued IE Bulletin 79-01, regarding environmental qualifica-tion of electrical equipment installed in their plants.
No additional written response to th*.s Supplement IE Bulletin is required other than t hose responses described above. NRC inspectors will continue to monitor the licensees' progress in completing the requested action deceribed above.
If additional iaformation is required, contact the Director of the appropriate NRC Regional Office.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
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IE Bulletin No.79-01A Enclosure June 6, 1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subj ect Date Issued Issued To No.
79-12 Short Period Scrams at 5/31/79 All GE BWR Facilities BWR Facilities with an OL 79-11 Faulty Overcurrent Trip 5/22/79 All Power Reactor Device in Circuit Breakers Facilities with an for Engineered Safety OL or a CP Systems 79-10 Requalification Training 5/11/79 All Power Reactor Program Statistics Facilities with an OL 79-09 Failures of GE Type AK-2 4/17/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systems OL or CP 79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP 79-05B Review of Operational 4/14/79 All Combustion Engineer-Errors and System Mis-irg Designed iressurized alignments Identified Water Power Reactor During the Three Mile Facilities virh an Island Incident Operating Licensee 79-06A Review of Operational 4/18/79 All Pressurized Water (Rev 1)
Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-06A Review of Operational 4/14/79 All Pressurized Wa'er Errors and Systen Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident
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IE Eulletin No. 79-OLA Enclosure June 6, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST 'lVELVE MONTHS Bulletin Subject Date Issued Issued To No.
79-06 Review of Operational 4/11/79 All Treasurized Water Errors and System Mis-Power Reactors with an alignents Identified OL except B&W facilities During the Three Mile Island Incident 79-05A Nuclear Incident at 4/5/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05 Nuclear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP 79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP "agineering Corporation 79-03 Longitudinal Welds Defects 3/12/?9 All Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstown Welding and Er;ineering Co.
79-02 Pipe Support Base Plate 3/2/70 All Power Recctor Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or CP 79-01 Environmental Qualification 2/8/79 All Power Reactor of Class IE Equipment Pacilities with an OL or CP 8-14 Deterioration of Buna-N 12/19/78 All CE FWR facilities Component In ASCO with an OL or CP Solenoids 78-13 Failurcs in Source Heads 10/27/78 All general and of Kay-Ray, Inc., Cauges specific licensees Models 7050, 7050B, 7051, with che subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B gauges bJ N
IE Bulletin No. 79-OlA Enclosure June 6, 1979 Page 3 of 3 LISTING OF IE BULLETINS
~ SLTD IN LAST IWELVE MONI11S Bulletin Subject Date Issued Issued To No.78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 8-12A Atypical Weld Material 11/24/78 All Power Reacter in Reactor Pressure Facilities with an Vessel Welds OL or CP 8-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-11 Examination of Mark I 7/ 21 /78 BWR Power Reactor Containment Torus Welds Facilities for sction:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee 78-10 Bergen-Paterson Hydraulic 6/27/78 All BWR Power Reactor Shock Suppr essor Accumulator Facilities with an Spring Coi?.s OL or CP 78-09 BWR Dryve'l Leakage Paths 6/14/79 All BWR Power Reactor Associated with Inadequate Facilities with an Dryvell Closures OL or CP 78-08 Radiation Levels from Fuel 6/12/78 All Power and Research Element Transfer Tubes Reactor Facilities with a Fuel Element transfer tube and an OL 78-07 Protection afforded by 6/12/78 All Power Reactor Air-Line Respirators and Facilities with an OL, Supplied-Air Hoods all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees 7-(
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Enclosure No. 3 SEP Plants Plant Region Dresden 1 III Yankee Rowe I
Big Rock Point III San Onofre 1 V
Haddam Neck I
Lacrosse IIT Oyster Creek I
R. E. Ginna I
Dresden 2 III hillstone I
Palisades III
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