ML19246C000
| ML19246C000 | |
| Person / Time | |
|---|---|
| Site: | Columbia, Washington Public Power Supply System, Satsop  |
| Issue date: | 06/06/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Strand N WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 7907190436 | |
| Download: ML19246C000 (1) | |
Text
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'~.'ALNUT CRE E K, CALIFORNIA 94506 June 6, 1979 Docket flos. 50-460, 50-397, 50-508, 50-509, 50-513 Washington Public Power Supply System P. O. Box 968 3000 George Washington Way Richland, Washington 99352 Attention:
Mr. fl. O. Strand Managing Director Gentlemen:
Enclosed is supplement IE Bulletin 79-01 A.
It requires action by you with regard to power rcactor facilities with an operating license except for the 11 SEP plants which are listed in Enclosure 2.
This Bulletin is also being sent for information to the 11 SEP plants and all power reactor facilities with a construction permit.
fio 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.
Sincerely, s
L / gt:lken f c
wu Enge
/, Dire'ctor,
Enclosure:
IE Bulletin flo. 79-01 A cc w/ enclosure:
M. E. Witherspoon, WPPSS A. D. Kohler, WNP-2, WPPSS J. P. Thomas, WPPSS W. J. Talbot, WPPSS G. C. Sorensen, WPPSS C
79071904 36
UttITED STATES NUCLEAR REGULATORY C0F.MISSI0tl 0FFICE OF INSPECTION AND EtlFORCEMEilT WASHINGTON, D.C.
20555 June 6, 1979 IE Bulletin tio.79-01A SUPPLEMErlT NO.79-01A TO IE BULLETIll 79 EtlVIRONMENTAL QUALIFICATI0ti 0F CLASS 1E EQUIPMENT (DEFICIEtiCIES Ill THE EriVIRONMENTAL QUALIFICATION OF ASCO SOLEtiOID VALVES)
Description of Circumstances:
Recently, a noncompliance report under 10 CFR Part ?1 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, tiew Jersey.
This pilot valve is used to pilot control the pneumatic valve actuators which are installed on the containment ventila-tion butte-fly 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, utili;;e 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 maintentnce 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 deal with the application of Llass "A", "B", or "F" solenoid coils which are exposed to an accident environment.
In this regard, ASCO representatives stated that the 99070go1 W
IE B0lletin fio.79-01A June 6, 1979 Page 2 of 3 ht,h tenperature coils identified as Class "HT" or "HB" are the only coils con-s d; ed suitable for service under accident conditions; whereas, Class "A", "B",
dnd "f" Coils are rot.
Wi th 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 netal which can be provided by ASCO.
2.
The valve seals and gaskets which are made of Buna "t;" 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 f;Ef1A t 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 flo. IIP-1 valves in lieu of the above.
7.
Questions from licernees 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 P,eactor Facilities (except those 11 SEP Plants listed on Enclosure 2) 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 "f1" 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 solenoit coil, the manual operator (if applicable), and the resilient parts of the valve are being replaced in uccordance with the time period established by the manufacturer and documented as the qualified life of the assembled component.
341 275
IE Bulletin fio.79-01A 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 requirenents established in previously issued IE Bulletin 79-01, regarding environmental qualifica-tion of electrical equipment installed in their piants.
l10 additional written response to this Supplement IE Bulletin is required other than those responses described above.
fiRC 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 f!RC Regional Office.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
Enclosures:
1.
List of IE Bulletins Issued in the past 12 months 2.
List of SEP Plants (11) 341 2 ~/ ~
IE Bulletin ilo.79-61A Uune 6, 1979 Page 1 of 3 LISTIllG OF IE CULLETIriS ISSUED Ill LAST TWELVE M0flTHS Bulletin Subject Date Issued Issued To tio.
79-12 Short Period Scrams at 5/31/79 All GE BUR 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 Statistks 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 BhR 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 79-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and System Mis-ing Designed Pressurized alignments Identified Water Power Reactor During the Three Mile Facilities with 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 Water Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 341 277
IE Bulletin No. 79-Ol A 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 79-05A Nuclear Incident at 4/5/79 All B&W Power Recc. tor 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 Reacter Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 79-03 Longituainal 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 Ca.
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 Environnental Qualification 2/8/79 All Power Reactor of Class IE Equipment Facilitics with an OL or CP 78-14 Deterioration of Buna-N 12/19/78 All GE BWR facilities Component In ASCO with an OL or CP Solenoids 73-13 Failures in Source Heads 10/27/78 All general and of Kay-Fay, Inc., Gauges specific licensees Models il50, 70508, 7051, with the subject 7051B, 7350 70603, 7061 Kay-Ray, Inc.
and 7051B gauges 341 278
IE B0lletin fio.79-01A June 6, 1979 Page 3 of 3 LISTIf1G OF IE BULLETIriS ISSUED Ill LAST TWELV? M0:lTHS Bulletin Subject Date Issued Issued To flo.78-12B Atypical Weld Material 3/19/79 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 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP
8-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Welds Facilities for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vennont Yankee 78-10 Bergen-Paterson Hydraulic 6/27/78 All BWR Power Reactor Shock Suppressor Accumulator Facilities with an Sprin9 Coils OL or CP 78-09 BWR Drywell Leakage Paths 6/14/79 All BWR Pcwer Reactor Associated with Inadequate Facilities with an Drywell Closures OL or CP 78-08 Radiation Levels from Fuel 6/12/78 All Power and Research Element Transfer Tubes Reactor Facilities with a Fuei Element transfer tube and an OL 78-07 Protecti]n 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 Sf9
9 Enclosure flo. 2 SEP Plants Plant Region Dresden 1 III Yankee Rowe I
Big Rock Point III San Onofre 1 V
Haddam iteck I
Lacrosse III Oyster Creek I
R. E. Ginna I
Dresden 2 III Pillstone I
Palisades III 341 280