ML19246B996
| ML19246B996 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/06/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 7907190425 | |
| Download: ML19246B996 (1) | |
Text
{{#Wiki_filter:p" %q, j UN. IED STATES E y' y'4j NUCLEAR HEGULATORY COMMISSION [f" REGION V (L G,-{A pb 1990 N. CALIFORNI A DOULEVARD I S,, SUITE 202, WALNUT CREE K PLAZA
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,W ,G WALNUT CREE K, CALIFOHNIA 949G June 6, 1979 Docket tio. 50-344 Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention: Mr. Charles Goodwin Assistant Vice President Gentlemen: Enclosed is supplement lE Bulletin 79-01 A. It requires action by you with regard to power eactor facilities with an operating license except for the 11 SEP plants which are listed in Enclostre 2. This Bulletin is also cang 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. Sincerely, ,1 i [irector
Enclosure:
IE Bulletin flo. 79-01 A cc w/ enclosure: B. Withers, PGE F. C. Gaidos, PGE e ,oa i (; )Li JJe 1()g q
UtilfED STATES NUCLEAR REGULATORY COMMISS10?i 0FFICE OF ItiSPECTION AND ENFORCEMEtiT WASHIf1GTON D.C. 20535 Jun9 6, 1979 IE Bulletin No. 79-01A SUPPLEMEtiT t10. 79-01A TO IE BULLETIrl 79 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMEtiT (DEFICIENCIES Iti THE ENVIRONMEtiTAL QUALIFICATION OF ASCO SOLEnulD 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 Station. These butterfly valves are uFed 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 fio. HT-8331A45, manufactured by the Automatic Switch Company (ASCO) of Florham Park, flew Jersey. This pilot valve is used to pilot control the pneumatic valve actuators which are installed or: 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 maximm service limit of 400,000 Rad integrated dosage and 200 degrees F temperiture. According to ASCO, exposure of these acetal plastic parts to specified marimum environmental conditions may render the solenoid pilot valve inoperable which would cause the associated butterfly valve to malfunction. Further :'vestigation at ASCO by the fiRC staff has revealed that the valve seals in mon ASCO solenoid valves contain Buna "fi" elastomer material, which reoortedly 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 tio. 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 deal 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 324 E6 ~
IE Bulletin tio. 79-01A 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 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 " naterial should be replaced with either ethylene propylene or viton elsstomars, 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 temperaturi environmental conditions. 4. Review and determine that the solenoid enclosures installed inside contain-ment have at least a f4Ef4A 4 enclosure rating. 5. Establish a preventive maintenance program to assure replacement of those valve parts identified above in the time period reconanended in the appro-priate ASCO valve bulletin. 6. ASCO also stated that a.1 unqualified solenoid valves inside containment be retrofitted to qualified ASCO tio. f1P-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 laken by Licensees of all Power Reactor 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 cc Buna "il" naterials 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. na 7F7 { 't -) N o
IE Bu.fletin 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 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 flRC 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) '[ I ,e;QA }g ,) )v
IE Bulletin No. 79-01A June 6, 1979 Page 1 of 3 LISTIllG OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No. 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 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 Faci'.itics 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 Inci.ent 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 /9-06A 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 [j 2 4 3.)9
IE Bulletin No. 79-01A 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- ?ower 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 Reactor Three Mile Island Facilities with an OL 79-05 Nuciear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP 79-04 Incorrect Waights for 3/30/79 All Pcwer 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. 75-02 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 78-14 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., Gauges specific licensees Models 7050, 7050B, 7051, with the subject 7051B, 7050, 70608, 7061 Kay-Ray, Inc. and 7061B gauges 320r J Uv
IE Bulletin No. 79-01A June 6, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS 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 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 78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Velds Facilicies for action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-nllo and Vermont Yankee 78-10 Bergen-Paterson Hydraulic 6/27/78 All BWP Power Reactor Shock Suppressor Accumulator Facilities with an Spring Coils OL or CP 78-09 BWR Drywell Leakage Paths 6/14/79 All bWR Power 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 Fuel Element transfer tube and an OL 78-07 Protection afforded by 6/JE/78 Power Reactor Air-Line Respirators and F lities with an OL, Supplied-Air Hoods class E and F 2earch Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees ??5
Enclosure fio. 2 SEP Plants Plant Region Dresden 1 III Yankee Rowe I Big Rock Paint ?II San Onofre 1 V Haddam Neck I Lacrosse III Oyster Creek I R. E. Ginna I Dresden 2 III Mills tone I Palisades III u ,' / .S c; j 0._' 7 e}}