ML19225A430
| ML19225A430 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle  |
| Issue date: | 06/06/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 7907190175 | |
| Download: ML19225A430 (2) | |
Text
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on aucuq'o, UNITED STATES l'
?,o NUCLEAR REGULATORY COMMISSION
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101 M ARIETT A $1., N.W., SUlT E 3100 o
Y AT L ANT A, GE oRGI A 30303 eg JUN 6 1979 In Reply Refer To:
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u 50-424, 504 25 Georgia Power Company Attn:
J. H. Miller, Jr.
Executive Vice President 270 Peachtree Street, N. W.
Atlanta, Georgia 30303 Gentlemen:
Enclosed is supplement lE Bulletin 79-01A.
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 No action or written power reactor facilities with a construction permit.
response is required f or construction permit f acilities or the 11 SEP plants.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, k
p Ja=es P. O'Reilly Director
Enclosures:
1.
List of IE Bulletins Issued in the past 12 months 3.
List of SEP Plants (11)
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7907190175
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JUN 6 1979 Gecrgia Power Company cc w/ enc 1:
M. Manry, Plant Manager Post Office Box 442 Baxley, Georgia 31513 C. E. Belflower Site QA Supervisor Post Office Box 442 Baxley, Georgia 31513 K. 7. Gillespie Construction Project Manager Post Office Box 282 Vaynesboro, Georgia 30830 E. D. Grover QA Site Supervisor Post Office Box 232 Wynesboro, Georgia 30830
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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-OLA SUPPLEMEhT 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 CFP 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 Ihree 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 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 asse=bly are stated by ASCO to have a maximum service lLnit of 400,000 Rad integrated dosage and 200 degrees F teuperature. 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 Es.
maximum service limit of 7,000,000 Rad integrated dosage and 180 degre2s 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 ennrgized operating life of four years, '
under normal embient conditions up to 140 degrees F.
According to the manus-facturer, at the end of this period, the coil, manual operator (optional fea-ture) and all resilient parts must be replaced. These preventh e maintenance instructions are specified in the installation and instruction bulletins which are provided to the purchascr 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 accideat environment.
In this regard, ASCO representatives stated that the s,
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IE Bulletin No.79-01A June 6, 1979 Page 2 of 3 high temperature coils identified as Class "ET" or "HB" are the only coils con-sidered suitable 'or service under accident conditions; whereas, Class "A", "B",
and "F" coils are nat.
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 pcovided by ASCO.
2.
The valve seals and gaskets which are made of Buna "N" Mr.cerial 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 r.cing.
5.
Establish a preventive maintenance program to assure replacement of those valve parts identif ted above in the time period recommended in the appro-pria.e A500 valve bulletin.
6.
ASCO also statad 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 er 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),
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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IE Bulletin No.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 comp 12 ting the requested action described above.
If additional information is wequired, contact the Director of the appropriate
' 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 Bullet 1.
No.79-01A Enclosure June 6, 1979 Page 1 of 3 LISTING 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 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 Rea tor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seismic Strest Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilitiec 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 Mir-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident f7V n-i J/
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Enclosure June 6, ;979 Page 2 of 3 LISTING OF IE BULLETINS ISJ'TED IN LAST IVELVE 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 en 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 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 PoTer Reacter 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 ASHI SA-312 Type 304 Facilities with an Stainless Steel Pipe Spcols OL or CP
&nuf actured 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 CE 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 M.-dels 7050, 7050B, 7051, with the subject 7051B, 7060, 70603, 7061 Kay-Ray, Inc.
and 7061B gauges
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IE Bulletin No. 79-OlA Enclosure June 6, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST IWELVE MONIES 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 Reactor 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 Yacilities with an Vessel Welds OL or CP 78-11 Examination of Mark I 7/ 21 /7 8 JWR Power Reactor Containment Torus Welds Facilities for action:
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 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 6/12/78 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
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Enclosure No. 3 SEP Plants Plant Region Dresden 1 III I
Yankee Rowe III Big Rock Point San Onofre 1 V
I Haddam Neck III Lacrosse I
Oyster Creek I
R. E. Ginna III Dresden 2 I
Millstone III Palisades b b f (ilD