ML19225A391
| ML19225A391 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/06/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 7907190123 | |
| Download: ML19225A391 (1) | |
Text
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UNITED STATES E"
l' 7, NUCLEAR REGUI.ATORY COMMISSION ih
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REGION I 0,
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KING OF PRUSSI A, PENNSYLVANI A 19406 Docket No. 50-29 Yankee Atomic Electric Company ATTN:
Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Gentlemen:
Enclosed is supplement IE Bulletin 79-01 A.
It requires action by you with regard to power reactor facility (ies) with an operating license except for the 11 SEP (Systematic Evaluation Program) plants which are listed in Enclosure 3.
This Bulletin is also being sent for information to the 11 SEP plants and all power reactor facilities with a construction permit.
No action or written response is required for these two categories of facilities.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, A
~ Boyce H. Grier Director
Enclosures:
1.
List of IE Bulletins Issueo in Last Twelve Months 3.
List of SEP Plants (11) cc w/encis:
H. Autio, Plant Superintendent L. E. Minnick, President
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ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.
20555 IE Bulletin No.79-01A Date:
June 6, 1979 Page 1 of 3 SUPPLEMENT NO.79-01A TO IE BULLETIN 79 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT (DEFICIENCIES IN THE ENVIRONMENTAL QUALIFICATION OF ASCO S0LEN0ID VALVES)
Description of Circumstances:
Recently, a noncompliance report under 10 CFR P&rt 21 was received by the NRC from the Henry Pratt Company, manufacturer of butterfly valves which are installed in the primary containment at the Three Mile Island 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 (ASCO) of Florham Park, New Jersey.
This pilot valve is used to pilot control the pneumatic valve actuators which are installed on the containment ventilation butterfly valves at this facility.
The deficiency in these solenoid valves identified in the Part 21 Report concerns the parts made of acetal plastic material.
The acetal disc holder assembly and bottom plug in the pilcc va;ve assembly 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 malfunction.
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 Rad 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, utilize 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 manufacturer, at the end of this period, the coil, manual operator (option.1 feature) and all resilient parts must be replaced.
These preventive maintenance instructions are specified in the. installation and instruction bulletins which are provided to the purchaser with each shipment of solanoid valves.
The final items of concern identified during this investigation deals with the application of Class "A", "B", or "F", solenoid coils which are exposed to an accident environment.
In this regard, ASCO representatives stated that the
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IE Palletin No. 79-01 A Date:
June 6,1979 Page 2 or 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 concerns, ASCO recommends the following:
1.
The parts of the solenoid 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 vitor elastomers, considered by ASCO as suitable for the service intended.
3.
Review and determine that the coils of the solenoid valves installed inside containment are Class "HT" or "HB" as required for high temperature environmental conditions.
4.
Review and determine that the solenoid enclosures installed 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 correcti.'e measures should reference both catalogue and serial numbers of each valve in question.
These nunbers are stamped on the metal nameplate on each solenoid valve.
Action to be Taken by Licensees of all Power Reactor Facilities (except those 11 SEP Plants listed on Enclosure 3) with an Operating License:
1.
Determine whether or not ASCO solenoid valves are use ' or planned for use in safety-related systems at your facility (ies).
2.
If such valves are used or planned for use, identify the safety system in alved and determine that:
(a) valves which could be subjected to a LOCA envircnment are qualified to that environment.
Specifically that no parts made of acetal plastic or Buna "N" materials or Class "A", "B",
or "F" ;alenoid coils are used in such valves; (b) a preventive main-tenance program is being conducted such that the solenoid coil, the manual operator (if applicable), and the resilient parts of the valve are being replaced in accordance with the time period established by the manufacturer and documented as the qualified life of the assembled component.
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June o, 1979 Page 3 of 3 3.
All holders of operating liceases 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 this Supplement IE Bulletin is required other than those responses described above.
NRC inspectors will continue to monitor the licensees' progress in completing the requested action described above. If additional information 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 bWnket clearance specifically for identified generic problems.
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IE Bulletin No. 79-01 A Date:
June 6, 1979 Page 1 of 5 ENCLOSURE 2 LISTING 0F IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority I Material Licensees 78-08 Radiation Leveis from 6/12/78 All Power, Test and Fuel Element Transfer Research Reactor Tubes Facilities with aa OL having Fuel Element Transfer Tubes 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL (for action)
Closures or CP (for information) 78-10 Bergen-Paterson 6/27/78 All BWR Power Reactor Hydraulic Shock Facilities with Suppressor Accumulator an OL or CP Spring Coils 78-11 ix.mination of Mark I 7/24/78 BWR Power Reactor Lontainment Torus Facilities with an OL Welds for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee.
All other BWR Power Reactor Facilities with an OL for information 3 ';I J
IE Bulletin No.79-01A Date: June 6, 1979 Page 2 of 5 LISTING 0F IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued To No.
78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-128 Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-13 Failures In Source Heads 10/27/78 All General and of Kay-Ray, Inc., Gauges Specific Licensees Models 7050, 705U8, 7051, with the subject 7051B, 7060, 70608, 7061 Kay-Ray, Inc.
and 7061B Gauges 78-14 Deterioration of Buna-N 12/19/78 All GE BWR Faci-Components In ASCO lities with an OL Solenoids (for action), and all other Power Reactor Facilities with an OL or CP (for informatit )
79-01 Environmental Qualif-2/8/79 All Power Reactor ication of Class IE Facilities with an OL, Equipment except the 11 Systematic Evaluation Program Plants (for action), and all other Power Reactor Facilities with an OL or CP (For Information) 79-02 Pipe Support Base Plate 3/8/79 All Power Reactor Design Using Concrete Facilities with an OL Expansion Anchor Bolts or CP 2'
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June 6, 1979 Page 3 of 5 LISTING OF IE BULLETINS 7SSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued to No.
79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor in ASME SA-312 Type Facilities with 304 Stainless Steel Pipe an OL or CP Spools Manufactured by Youngstown Welding and Engineering Company 79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 79-05 Muclear Incident at 4/1/79 All Babcock and Three Mile Island Wilcox Power Reactor Facilities with an OL, Except Three Mile Island 1 and 2 (For Action),
and All Other Power Reactor Facilities dith an OL or CP (For Information)79-05A Nuclear Incident at 4/5/79 Same as 79-05 Three Mile Island -
Supplement 79-06 Review of Operational 4/11/79 All Pre urized Water Errors and System Mis-Power Reactor Facil-alignments Identified ities with an OL Except During the Three Mile B&W Facilities (For Incident Action), All Other Power Reactor Facil-ities with an OL or CP (For Information) o e S i
June 6, 1979 Page 4 of 5 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (C0iiTINUED)
Bulletin Subject Date Issued Issued to No.79-06A Same Title as 79-06 4/14/79 All Westinghouse Designed Pressurized Power Reactor Facil-ities with an O' (For Action), and All Other Power Rsactor Facilities with an OL or CP (For Information)79-06A Same Title as 79-06 4/18/79 All Westinghouse (Revision 1)
Designed Pressurized Power Reactor Facil-ities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information)79-06B Same Title as 79-06 4/14/79 All Combustion Engineering Designed Pressurized Power Reactor Facilities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information) 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP g., (
'[' >lr IE Bulletin No.79-01A Date:
June 6, 1979 Page 5 of 5 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin
' Subject Date Issued Issued to No.
79-0L Events Relevant to 4/14/79 All BWR Power Boiling Water Power Reactor Facilities Reactors Identified with an OL (For During Three Mile Action), All Other Island Incident Power Reactor Facil-ities with an OL or CP (For Infonnation) 79-09 Failures of GE Type 4/17/79 All Power Reactor AK-2 Type Circuit Facilities with an Breaker in Safety OL or CP Related Systems 79-10 Requalification Training 5/11/79 All Power Reactor Program Statistics 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 CP Systems 79-12 Short Period Scrams at 5/31/79 All GE BWR Facilities BWR Facilities with an OL
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ENCLOSURE 3 SEP Plants Plant Region Dresden 1 III Yankee Rovce I
Big Rock Point III San Onofre 1 V
Haddam Neck I
Lacrosse III Oyster Creek I
R. E. Ginna I
Dresden 2 III Millstone 1 I
Palisades III
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