ML18043A830

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Forwards Suppl IE Bulletin 79-01A, Environ Qualification of Class IE Equipment (Deficiencies in Environ Qualification of Asco Solenoid Valves). Action Required
ML18043A830
Person / Time
Site: Big Rock Point, Palisades  File:Consumers Energy icon.png
Issue date: 06/06/1979
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Dewitt R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 7907190245
Download: ML18043A830 (8)
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Docket No. ;<>-155 Docket No.,;S0-255 Consumers Power Company ATrN:

Mr. R. B. DeWitt Manager of Nuclear Plant Operations 212 West Michigan Avenue Jackson, MI 49201 Gentlemen:

JUN 6 1979 e

CENTRAL F1(ES

'..'tLLOW FILE cop*~

Enclosed is.. supplement IE Bulletin No. 79-0lA. 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 con~truction 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 *.

Enclosure:

IEBulletin No.* 79-0lA cc w/encl:

  • Mr. C. J. Hartman, Plant Superintendent Mr.* J.
  • G. Lewis, Plant Superintendent Central Files
  • Director, NRR/DPM Director, NRR/DOR PDR RIII He&.man/blk 6/5/79 RIII tflt)l Keppler

~

Sincerely, James G. Keppler Direc:tor Local PDR NSIC TIC Ronald. Callen, Michigan Public Service Commission Anthony Reisman, Esq.,

Attorney Myron M. Cherry, Chicago

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III June 6, 1979 IE Bulletin No, 79-0lA SUPPLEMENT NO. 79-0lA TO IE BULLETIN 79 ENVIRONMENTAL.QUALIFICATION OF CLASS lE EQUIPMENT (DEFICIENCIES IN THE ENVIRONMENTAL QUALIFICATION OF ASCO SOLENOID 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 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 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.

Furthe~ 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

  • availab_le 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-notma! *.ambient 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 environment.

In this regard*, ASCO representatives stated that the r:*

i-I

't IE Bulletin No. 79-0lA 2 -

June 6, 1979 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:

l.

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 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 "BB" 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 parts identified above in the time period recommended in the appro-priate ASCO valve bulletin *.

6. -

AS.CO also stated 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 'Doth catalogue. and serial nwnbers* 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.

Deterniine 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 1Dade of acetal plastic or B1.nla 0 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 manufacturer
  • and documented as the qualified life of the assembled component.

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IE Bulletin No. 79-0lA 3 -

June 6, 1979

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

. NR.C Regional Office.

Approved by GAO, Bl80225 (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)
  • -------~-

\\

IE Bulletin No. 79-0lA Bulletin No *.

79-ri 79-11 79-10 79-09 79-08*

79-07 79-06B 79-06A (Rev. l)79-06A LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Subject Date Issued Short Period Scrams at 5/31/79 BWR Facilities Faulty Overcurrent Trip 5/22/79 Device in Circuit Breakers.

for Engineered Safety Systems Requalification Training 5/11/79*

Program Statistics Failures of GE Type AK-2*

4/17 /79 Circuit. Breaker in Safety-Related Systems Events Relevant to. BWR 4/14/79 Reactors Identified During Three Mile Island Incident Seismic Stress Analysis*

4/14/79 of Safety-Related Piping Review_ of Operational 4/14/79-Errors and System Mis-alignments Identified During the.Three Mile Island Incident Review of Operational.*

4/18/79 Errors and System Mis-alignments Identified'

  • During the Three Mile Island Incident Review of Operational 4/1~/79 Errors and System Mis-aligmnents.. Identified Doring: the Three Mile Island Incident
  • June 6, 1979 Issued To All GE BWR Facilities with an OL All Power Reactor Facilities with an OL or a CP All Power Reactor Facilities with an OL All Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with an OL All Power Reactor Facilities with an OL or CP All Combustion Engineer-ing Designed Pressurized Water Power Reactor Facilities with an Operating Licensee All pressurized Water Power Reactor Facilities of Westinghouse Design with anOL All Pressurized Water Power Reactor Facilities of Westinghouse Design with an OL Enclosure Page l of 3

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IE Bulletin No. 79-0lA Bulletin No.

79-06 79-05A 79-05 79-04 79-03 79-02.

79-01 78-14 78-13 I

LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Subject Date Issued Review of Operational 4/11/79 Errors and System Mis-alignments Identified During the Three Mile Island Incident Nuclear Incident at 4/5/79 Three Mile Island Nuclear Incident at.

4/2/79° Three*Hile Island Incor.rect Weights for 3/30/79 Swing Check Valves Manufactured by Velan

  • Engineering Corporation.

Longitudinal Welds Defects.

3/12/79 In ASME SA-312 Type 304 Stainless Steel Pipe* Spools Manufactured by Youngstown Welding. and: *Engineering Co.

Pipe Support Base, Plate*

3/2/70 Designs Using Concrete Expansion Anchor Bolts Environmental Qtialification 2/8/79 of Class IE Equipment Deterioration of Buna-N Component In ASCO Solenoids Failures in_ Source Heads of Kay-Ray, Inc., Gauges.

l!odels 7050,. 7050B, 7051, 7051B~ 7060,. 7060B, 7061 and 706lB 12/19/78 10/27 /78

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June 6, 1979 Issued To All Pressurized Water Power Reactors with an CL except B&W facilities All B&W Power Reactor Facilities with an OL

  • All Power Reactor Facilities with an OL and CP All Power Reactor Facilities with an OL or CP All -Power Reactor

.Facilities with an OL or CP All Power Reactor Facilities with. an OL or CP All Power.Reactor Facilities with an OL.or CF All GE Bw"ll facilities with anOL or CP All general and specific licensees with the subject Kay-Ray,. Inc *.

gauges Enclosure Page 2 of 3 i

I

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IE Bulletin No. 79-0lA.

Bulletin No.

.78-L2B 78-12A 78-12 78-11 78-10 78-09" 78-08:

.78-07

)

LISTING OF IE BULLETINS

.ISSUED IN LAST TWELVE MONTHS Subject Atypical Weld Material in Reactor Pressure Vessel Welds Atypical Weld.Material in Reactor* Pressure Vessel Welds Atypical Weld Material in Reactor Pressure JTessel Welds Date Issued 3/19/79 11/24/78 9/29/78' Examination of Mark I 7/21/78 Containment Torus Weld's Bergen~Paterson Hydraulic 6/27 /78*

Shock Suppressor Accumu*lator Spring. Coils.

BWR Dcywell Leakage Paths*

6/14/79 Associated with. *Inadequate***

Drywell Closures:

Radiation Levels from Fuel. 6/12/78 Element. Transfer Tubes Protection: afforded by

  • 6/12/78

.Air-Line Respirators and

    • Supplied-Air Hoods..

June 6, 1979 Issued To All Power Reactor*

Facilities with an OL or CP All Power Reactor Facilities with an OL. or CP All Power Reactor Facilities with an OL or CP BWR Power* Reactor Facilities for action:

Peach.Bottom 2 and 3, Quad Cities l and 2,.

Hatch 1, Monticello and Vermont Yankee.

All BWR Power Reactor Facilities with* an OL or CP All.BWR Power Reactor Facilities with an OL*or CP All Power and Research Reactor Facilities with a Fuel Element transfer tube and an OL All~ *Power Reactor

    • . Facilities with an OL,
  • all. class E and F Research Reactors with an OL, all. Fuel Cycle
  • Facilities with an OL, and all Priority 1 Material Licensees Enclosure Page 3 of 3
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Plant Dresden 1 Yankee Rowe Big Rock Point San Onofre 1 Haddam Neck Lacrosse Oyster Creek R. E. Ginna Dresden 2 Millstone Palisades

    • .SEP Plants Region III I

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I III I

I III I

III Enclosure Page 1 of 1

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