ML18116A166
| ML18116A166 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 06/06/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7907190209 | |
| Download: ML18116A166 (9) | |
Text
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In Reply Refer To:
RII:JPO 50-338, 50-339
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 JUN 6 1979 50-280, 50-281)
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_L Virginia Electric and Power Company Attn:
W. L. Proffitt Senior Vice President, Power P.O. Box 26666 Richmond, Virginia 23261 Gentlemen_:
Enclosed is supplement IE Bulletin 79-0lA. 'it requires action by you with regard to power reactor facilities 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 facilities with a construction permit.
No action or written response is required for construction permit facilities or the 11 SEP plants.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Enclosures:
- 1.
IE Bulletin No. 79-0lA
- 2.
List of IE Bulletins Issued in the past 12 IDOUtha
- 3.
List of SEP Plants (11)
Sincerely,
~~
-r'~ James P. O'Reilly Director
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Virginia Electric and Power Company cc v/encl:
e W.R. Cartwright, Station Manager Poat Office Boz 402 Mineral, Virginia 23117 P. G. Perry Senior Resident Engineer Post Office Boz 38 Mineral, Virginia 23117 W. t. Stewart, Manager Po~t Office Boz 315 Surry, Virginia 23883 JUN 6 79"79*
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 6, 1979 IE Bulletin No. 79-0lA SUPPLEMENT NO. 79-0lA TO IE BULLETIN 79 ENVIRONMENTAL QUALIFICATION OF CLASS lE EQUIPMENT (DEFICIENCIES IN THE ENVIRONMENTAL QUALIFICATION OF ASCO SOLENOID VALVES)
Description of Circumstances:
Recently, a noncompliance report under 10 CFR Part 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 Stati~n.
These butterfly valves are used for purge and exhaust purposes and
~re 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 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 material.
The acetal disc holder assembly and bottom plug in the pilot valve 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 manu-facturer, at the end of this period, the coil, manual operator (optional fea-ture) 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 solenoid 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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e IE Bulletin No. 79-0lA e
.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 condit*ions; wh~reas, Class "A", "B",
and "F" coils are not.
With respect to the corrective measures to be taken to resolve the above concerns, ASCO reco1lllll.ends the following:
- l.
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 viton 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 corrective measures should reference both catalogue and serial numbers of each valve in question.
These numbers 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 used 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 involved and determine that:
(a) valves which could be subjected to a LOCA environment are qualified to that environment. Specifically 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 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.
e IE Bulletin No. 79-0lA e
June 6, 1979 Page 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 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, Bl80225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
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e IE Bulletin No. 79-0lA June 6, 1979 Bulletin No.
79-12 79-11 79-10 79-09 79-08 79-07 79-06B 79-06A (Rev 1)79-06A LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Subject Date Issued Short Period Scrams at 5/31/79 BWR. Facilities Faulty Overcurrent Trip 5/22/79 Device in Circuit Breakers for Engineered Safety Systems Requalification Training 5/11/79 Program Statistics Failures of GE Type AK-2 4/17/79 Circuit Breaker in Safety Related Systems Events Relevant to BWR.
4/14/79 Reactors Identified During Three Mile Island Incident Seismic Stress Analysis 4/14/79 of Safety-Related Piping Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident 4/14/79 4/18/79 4/14/79
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e Enclosure Page 1 of 3 Issued To All GE BWR Facilities with an OL All Power Reactor Facilities with an OL or a CP All Power Reactor Facilities with an OL All Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with an OL All Power Reactor Facilities with an OL or CP All Combustion Engineer-ing Designed Pressurized Water Power Reactor Facilities with an Operating Licensee All Pressurized Water Power Reactor Facilities of Westinghouse Design with an OL All Pressurized Water Power Reactor Facilities of Westinghouse Design with an OL
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IE Bulletin No. 79-0lA Enclosure June 6, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
79-06 Review of Operational 4/11/79.
All Pressurized Water Errors and System Mis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident 79-0SA Nuclear Incident at 4/5/79 All B&W Power Reactor Three Mile Is land 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 Engineering Corporation 79-03 Longitudinal Welds Defects 3/12/79 All Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstown Welding and Engineering Co.
79-02 Pipe Support Base Plate 3/2/70 All Power Reactor 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 Facilities with an OL or CP 8-14 Deterioration of Buna-N 12/19/78 All GE BWR facilities Component In ASCO with an OL or CP Solenoids 78-13 Failures in Source Heads 10/27/78 All general and of Kay-Ray, Inc., Cauges specific licensees Models 7050, 7050B, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B gauges
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IE Bulletin No. 79-0lA June 6, 1979
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e LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin No.78-12B 8-12A 8-12 78-11 78-10 78-09 78-08 78-07 Subject Atypical Weld Material in Reactor Pressure Vessel Welds Atypical Weld Material in Reactor Pressure Vessel Welds Atypical Weld Material in Reactor Pressure Vessel Welds Examination of Mark I Containment Torus Welds Bergen-Paterson Hydraulic Shock Suppressor Accumulator Spring Coils
- BWR Drywell Leakage Paths Associated with Inadequate Drywell Closures Radiation Levels from Fuel Element Transfer Tubes Protection afforded by Air-Line Respirators and Supplied-Air Hoods Date Issued 3/19/79 11/24/78 9/29/78 7/21/78 6/27 /78 6/14/79 6/12/78 6/12/78 e
Enclosure Page 3 of 3 Issued To All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP BWR Power Reactor Facilities for action~
Peach Bottom 2 and 3, Quad Cities 1 and 2, Batch 1, Monticello and Vermont Yankee All BWR Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with an OL or CP All Power and Research Reactor Facilities with a Fuel Element transfer tube and an OL All Power Reactor Facilities with an OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees
Plant Dresden 1 Yankee Rowe Big Rock Point San Onofre 1 Haddam Neck Lacrosse Oyster Creek R. E. Ginna Dresden 2 Millstone Palisades Enclosure No. 3 SEP Plants Region III I
III V
I III I
I III I
III