ML19246B912
| ML19246B912 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/06/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 7907190180 | |
| Download: ML19246B912 (2) | |
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'o UNITED STATES E",w NUCLEAR REGULATORY COMMISSION
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I 101 MARIETT A ST., N.W., SUIT E 3100 g *g' E
AT LANT A, GEORGI A 30303
%.....o JUN 6 1979 In Reply Refer To:
RIIrJPO me-( 50-416, 50-417 Mississippi Power and Light Company Attn:
N. L. Stanpley Vice Prerident of Production P. O. Box 1640 Jackson, Mississippi 39205 Gentlemen:
Enclosed is supplement IE Bulletin 79-OlA. 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 f or construction pernit f acilities or the 11 SEP plants.
Should you have questions regarding this Bulletin or the actions required of you, please contact this of fice.
Sinceraly, bOh p Ja:nes P. O'Reilly Director
Enclosures:
1.
List of IE Bulletins M
Issued in the past 3
Q M
12 months 3.
List of SEP Plants (11) kg i \\
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JUN 6 1979 I
Mississippi Power and Light Company cc w/ encl:
C. K. McCoy Plant Manager Post Office Box 756 Port Gibson, Mississippi 39150 O
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i UNITED STATES NUCLEAR REGULATORY COMM1SSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 6, 1979 IE Bulletin No. 79-OLA SUPPLEMENT No. 79 01A TO IE BULLETIN 79 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT (DEFICIENCIES IN THE ENVIRONMENTAL QUALIFICATION OF ASCO SOLEh0ID 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 Uni: 2 Nucles Station. These butterfly valves are used for purge s't exhaust purposes and are required to operate during accident conditions. ihe report discusses te use of an unqualified solenoid valve for a safety-related valve function whicn requires operation under accident conditions. The solenoid valve in question is Catalogue No. HT-8331A45, manufactured by the Automatic Swiret. Company (ASCO) of Florham Park, New Jersey. This pilot valve is used te ptlet control the pneumatic valve actuators which are installed on the centaimnent ventila-tion butterfly valves at this facility.
The deficiency in these solenoid valves identified in the Part 21 Report xoncerns the parts made of acetal plastic material. The acetal disc holder asserbly and bottom plug in the pilot valve assembly are stated by ASCO to have a mnximum 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 solencid 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 contin" asly 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 bulletics which are provided to the purchaser with each shipment of solenoid valves.
The final items of concern identified during thin 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 344 344
IE Bulletin No.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 conditious; 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 p..rts of the solenoid valve made of acetal plastic material should be replaced with similar parts made of matal which can be provided by ASCO.
2.
The valve seals and gaskets which are rede of Buna "N" material should be replaced with either ethylene precyleno 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 containr-at 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 <ssure 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.
Qucstions from licensees to ASCO concerning corrective measures should reference both catalogue and serial numbers of each valve in question.
Thene 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 uuch valves are used or planned for use, identify the safety system ir<olved and determine that:
(a) valves which could be subjected to a LO'.A environment are qualified to that environment. Specifically that
'o 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), an' 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.
344 345
IE Bulletin No.79-01A Jene 6, 1979 Pr.ge 3 of 3 3.
All holders of operating licenses of power reactor facilfcies are obligated to meet the review and reporting requicements established in previously issued IE Bulletin 79-01, regarding environmental qualifica-tion of electrical equipment ins.slied in their plants.
No additional written response to this Supplement IE Bulletin is required other than those responses described above. NRC inspectors vill continue to monitor the licensees' progress in completing the reso sted action described above.
If additiona) information is required, contact the Director of the appropriate NRC Regicnal Office.
Approved by G40, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems, hk
IE Bulletin No.79-01A Enclosure June 6, 1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subj ect 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 Safa.ty 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 Sa'aty Facilities with an Related Systems OL ar CP 79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seismic Stress Analysis 4/14f 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 ar.
Island Incident Operating Licensee 79-06A Review of Operational 4/18/79 All Pressurized Water (Rev 1)
Errors and System Mis-Fower 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 34]7
IE Bulletin No.79-01A Enclosure June 6, 1979 Page 2 of 3 LISTING OF IE BULLETINS IShu D IN LAST TWELVE M0! TIES Bulletin Subject Date Issued Iasued 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 Incid-nt at 4/5/79 All B&W Power Reactor Three Mile Islacd Facilities with an OL 79-05 Nuclear Incident at 4/2/79 All Power Reautor 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 Longitedinal Welds Defects 3/12/79 All Power Reactor In ASME SA-312 Type 304 Facil' ties 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 witn en Expansion Anchor Bolts OL or CP 79-01 Environmental Qualification 2/8/79 All Power Reactor of Class IE Equipment Facili*.ies with an OL or CP 8-14 Deterioration of Buna-N 12/19/78 All CE BWR f acilities Component In ASCO with an OL or CP Solecoids 78-13 Failures in Source Leads 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 1061B gacaea gk
IE Bulletin No. 79-OlA Enclosure June 6, 1979 Page 3 of 3 LISTING OP IE BULLETINS ISSUED IN LAST IVELVE MONTFS Bulletin Subject Date Issued Issued To No.78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities uith an Vessel Welds OL or CP 8-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Walds 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 7/21/78 EWR Power Reactor Containment Torus Welds Facilities for action:
Peach Bottom 2 and 3 Quad Cities 1 and 2, Batch 1 Monticelin and Vermont Yankee 78-10 Bergen-Paterson Eydraulic 6/27/78 All HWR Power Reactor Shock Suppressor Ar.cumulator Facilities with an Spring Coils OL or CP 78-09 BWP Drywell Leakage Paths 6/14/79 All BWR Power Reactor Associated with Inadequate Facilities with an Dryvell Closures OL or CP 78-08 Radiation Levels from Fuel 6/12/70 All Power and Research Element Transfer Tubes Reactor Facilities with a Fuel Element transfe; tube and an OL 78-07 Protection afforded by 6/12/78 All Power Reactor Air-Line Respirators and Facilities with 2n 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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h iosure No. 3 SEP Plants Plant Region III Dresden 1 I
Yankee Rowe III Big Rock Point V
San Onofre 1 I
Haddam Neck III I.aCrosse I
Oyst.,r Crcek I
R. E. Ginna III Dresden 2 I
Millstone III Palisades 344 350