ML19246B917
| ML19246B917 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/06/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mary Johnson SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 7907190187 | |
| Download: ML19246B917 (2) | |
Text
.
/
'o UNITED STATES c'
NUCLEAR REGULATORY COMMICSION 3
11f. ')
REGION 11
[I f
101 MARIETT A ST., N.W., SulT E 3100 ATLANTA, GEORGIA 30303 9
JUN 6 1979 In Reply Refer To:
RII:JPO 50-395
(w
/
South Carolina Electric and Gas Company Attn:
M. C. Johnson, Vice President Special Services and Purchasing Post Office Box 764 Columbia, South Carolina 29218 Gentlemen:
Enclosed is supplement IE Bulletin 79-01A.
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.
nis Bulletin is also being sent for informatior to the 11 SEP plants and all No action or written power reactor facilities wit h a cons truction perwit.
response is recuired f or con'struction permit f acilities or the 11 SEP plants.
Should you have questions regarding this nulletin or the actions required of you, please contact this office.
Fiacerely, DO p Ja=es P. O'Reilly Director
Enclosures:
1.
IE Bulletin No. 79-OlA 2.
List of IE Bulletins Issued in the past 12 nonths 3.
List of SEP Plants (11)
?t 7 d
)
7007190yg7
JUN 6 8 79 I
South Carolina Electric and Gas Company cc v/enti:
- 1. B. Conne rs, Jr.
Conners, Moore and Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 A. A. Seith Quality Assurance Post Office Box 8 29065 Jenkinsville, South Carolina O. S. Bradham, Manar t Nuclear Operations Post Office Box 8 29065 Jenkinsville, South Carolina 3I 3 0}h 7007020178
=
l UNITED STATES NUCLEAR REGULATORY COMMISSION O.ZICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 6, 1979 IE Bulletin No. 79-OlA SUPPLEMENT NO. 79-OlA TO IE BULLETIN 79 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT (DEFICIENCIES IN THE ENVIRONMENTAL QUALIFICATION OF ASCO SOLEN 0ID 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 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 solentid 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 w uld 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 e'mbient 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 environmert.
In this regard, ASCO representatives stated that the 343 0it
IE Bulletin No.79-01A June 6, 1979 Page 2 of 3 hf-
'mperature coils identified as Class "HT" or "HB" are the only coils con-siderea suitable for service under accident conditions; whereas, Class "A", "B",
ana "/" 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 viton elasto=ers, 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 patts 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 :alves in lieu of the above.
7.
Questions from licensees to ASCO concerning corrective measures should reference both catalogue and serial numbers cf each valve in question.
These numbers are stamped on the metal namepla;a on each solenoid valve.
Action to be Takta by Li.ensees 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 manufac*.urer and documented as the qualified life of the assembled component.
fl}b
h lE 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 equi,' ment installed in their plants.
No additional written response to this Supplement IE Bulletin is required other than those responres described avove.
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 expirec 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
3zi3 0ill
IE B 211etin No. 79-OlA Enclosura June 6, 1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST T'IELVE MONTHS Bulletin Subj ect Date Issued Is,ued To No.
79-12 Short Period Scrams at 5/31/79 All CE BWR Facilities EUR 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/',9 All BWR 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 Mie-ing Designed Pressurized align =ents Identified Water Power Reactor During the Three Mlle Facilities with an Island Incident Operating Licensee 79-06A Review of Operational 4/18/79 All Pressurized %'ater (Rev 1)
Errors and System His-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 343 0 idl
IE Bulletin No. 79-OLA Enclosure June 6, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST IWELVE NONTES 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 B6W 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 3/20/79 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 Manuf 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 Equipnent Facilities with an OL or CP 8-14 Deterioration of Buna-N 12/19/78 All CE BWR facilities Conponent 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 343 O!E
IE Bulletin No.79-01A Enclosure June 6, 1979 Page 3 of 3 LISTING OF IE BULI.ETINS ISSUED IN LAST IWELVE N0hTdS 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 Ali 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 Facilities with an Vessel Welds OL or CP 78-11 Examination of Mark I 7/ 21 /7 8 BWR Power Reactor Containment Torus Welds Facilities for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Eatch 1, Monticello and Vermont Yankee 78.0 Bergen-Paterson Hydraulic 6/27/78 All BWR Power Reactor Shock Supprescor Accumulator Facilities with an Spring coils OL or CP 78-09 BWR Dryvell Leakage Paths 6/14/79 All BWR Power Reactor Associated with Inadequate Facilities with an Drywell Closures OL or CP 78-08 Radiation Lewis froc 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 343 013
Enclosure No. 3 SEP Plants Pegion Plant III Dresden 1 I
Yank.
.e III Big Rock Point V
San Onofre 1 I
Haddam Neck III Lacrosse I
Oyster Creek I
R. E. Ginna III Dresden 2 I
Millstone III Palisades 343 O r2