Text

Forwards NUREG/CR-3962, Closeout of IE Bulletin 80-20: Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches
	ML20214H107
Person / Time
Issue date:	07/15/1986
From:	Jordan E; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Norelius C, Starostecki R, Walker R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
	RTR-NUREG-CR-3962 IEB-80-20, NUDOCS 8607180129
	Download: ML20214H107 (42)
	v • d • e

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UNITED STATES

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$3 ij WASHINGTON, D. C. 20555

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JUL 151986-MEMORANDUM FOR:

Richard W. Starostecki, Director, DRP, RI-Roger D. Walker, Director, DRP, RII Charles E. Norelius, Director, DRP, RIII Eric H. Johnson, Director, DRP, RIV Dennis F. Kirsch, Director, DRP, RV FROM:

Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement

SUBJECT:

IE BULLETIN 80-20 CLOSE0VT Enclosed is a copy of NUREG/CR-3962 pertaining to the closeout of IE Bulletin 80-20 " Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches". This report was prepared by. Parameter Inc. under contract to IE.

Parameter's review effort included evaluation of utility responses, deficiency reports, and NRC regional inspection reports for 124 nuclear power plants in operation or under construction.

Parameter's review of utility responses and NRC/IT inspection reports deter-mined that the bulletin has been closed for 122 out of the 124 current facili-ties. _The closed out facilities reported that they either do not use the affected equipment in safety related systems or they corrply with the require-ments of the bulletin.

Proposed followup items for the remaining J current facilities (Sequoyah 1&2) are presented in Appendix C.

IE has reviewed NUREG/CR-3962 and concur in the contractor's conclusions that IEB 80-20 is considered closed. However,. Appendix C proposes followup items for 2 facilities and IE agrees. Since no additional failures were.J10ted in the 2

responses to this bulletin, IE is not suggesting any. additional action.

Q If you have any questions pertaining to the closecut, please contact James C.

Stewart of my staff at 492-9061.

E6ar ( gnt Jordan, Director Divisi of. Emergency Preparedness and ngineering Response Office of Inspection and Enforcement

Enclosure:

NUREG/CR-3962 Y^

I g (, f r1.L 8 f> L %

NUREG/CR-3962 Closeout o" IE Bulletin 80-20:

Failures.of Westinghouse Type W-2 Spring Return to

\\eutral Control Switches Prepared by R. S. Dean, W. J. Foley, A. Hennick PAR AMETER, Inc.

U S Nuclear Regulatory Commission (p n r--)

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F r

NOTICE This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or imphed, or assumes any legal liability of re-sponsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.

NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:

1. The NRC Public Document Room,1717 H Street, N.W.

Washington, DC 20555

2. The Superintendent of Documents, U.S. Government Printing Of fice, Post Of fice Box 37082 Washington, DC 20013-7082

3. The National Technical Information Service, Springfield, VA 22161 Although the listing that follows represents the majority of documents cited in NRC publications, it is not intended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Docu-ment Room include N RC correspondence and internal NRC memoranda: NRC Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investigation notices; Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence.

The following documents in the NUREG series are available for purchase from the GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, and NRC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of Federal Regulations, and Nuclear RegJiatory Commission issuances.

Documents available from the National Technical Information Service include NUREG series reports and technical reports prepared by other federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Comm:ssion.

Documents available from public and special technical libraries include all open literature items, such as books, journal and periodical articles, and transactions. Federal Register notices, federal and state legislation, and congressional reports can usually be obtained from these librar;es.

Documents such as theses, dissertations, foreign reports and translations, and non-NRC conference proceedings are available for purchase from the organization sponsoring the publication cited '

Single copies of NRC draf t reports are available free, to the extent of supply, upon written request to the Division of Technical information and Document Control, U S. Nuclear Regulatory Com-mission, Washington, DC 20555.

Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, 7920 Norfolk Avenue. Bethesda, Maryland, and are available there for reference use by the public. Codes and standards are usually-copyrighted and may be purchased from the originating organization or if they are American National Standards. from the Amencan National Standards institure,1430 Broadway, New York, NY 10018.

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NUREG/CR-3962 PARAMETER IE-150 Closeout of IE Bulletin 80-20:

Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches Manuscript Completed: April 1986 Date Published: June 1986 Prepared by R. S. Dean, W. J. Foley, A. Hennick PARAM ETER, Inc.

13380 Watertown Plank Road Elm Grove, WI 53122 Prepared for Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC FIN B8729

ABSTRACT On June 18, 1980,~ Commonwealth Edison Company submitted Licensee Event Report (LER) 50-295/80-24 to the NRC, describing a malfunction of a Westinghouse Type W-2 control switch important to safety at Zion Unit 1.

On the same date, Westinghouse submitted a preliminary. issue of Technical Bulletin NSD-TB-80-9

~

to the NRC on the subject switches.

On July 31, 1980, IE Bulletin 80-20 was issued to all power plant licensees and permit holders, requiring them to take specific actions and report results.

Evaluation of utility responses and NRC/IE inspection reports shows that the bulletin can be closed out per specific criteria for 122 (98%) of the 124 current facilities to which it was issued.

A followup item for the remaining two facilities is proposed for use by NRC/IE, to ensure satisfactory completion of corrective action.

f I

iii

TABLE OF CONTENTS Page Abstract iii-Introduction 1

1 Summary Conclusions 3

3 Remaining Areas of Concern Criteria for Closeout of Bulletin 4

Appendix A Background Information IE Bulletin 80-20 A-1 CECO LER 50-295/80-24 for Zion 1 A Westinghouse Technical Bulletin NSD-TB-80-9, Rev. 1 A-7 Letter of November 19, 1985, to James Stewart (IE/HQ) from J. W. Hufham (TVA)

A-9 Letter of August 5, 1981 to J. A.

Raulston (TVA) from J. L. Tain~(W)

A-10 Appendix B Documentation of Bulletin Closeout Table B.1 Bulletin Closeout Status B-1 References B-10 Appendix C Proposed Followup Item C-1 Appendix D Table D.1 Identification of Affected Systems, Numbers of Type W-2 Switches and Numbers of Failures D-1 Appendix E Abbreviations E-1 y

i j

4 CLOSE0UT OF IE BULLETIN 80-20:

FAILURES OF WESTINGHOUSE TYPE W-2 SPRING RETURN TO NEUTRAL CONTROL SWITCHES INTRODUCTION i

I In accordance with the Statement of Work in Task Order 003 under Contract NRC 05-85-157-02, this report provides documentation for the closeout status of IE Bulletin 80-20.

Documentation is based on the records obtained from the IE File, the NRC Document Control System, and.the cognizant engineer's file.

IE Bulletin 80-20 was issued July 31, 1980 because of concern about failures of Westinghouse Type W-2 spring return to neutral l

control switches.

Commonwealth Edison Company (CECO) had i

submitted a Licensee Event Report (LER) to the.NRC to describe the failure of a Type W-2 switch to actuate automatic start of a service water pump at Zion Unit 1.

A review of this matter by Westinghouse led to the issuance of a technical bulletin.

In order to ensure operability of safety-related systems containing j

these switches, all holders of operating licenses and i

construction permits were required to take specific actions and

)

report results.

For background information, IE Bulletin 80-20, CECO LER 50-295/80-24, Westinghouse Technical Bulletin NSD-TB-80-9, letter of November 19, 1985 from TVA to IE/HQ and letter of August 5, 1981 from Westinghouse to TVA are included in Appendix A.

Evaluation of licensees' responses and NRC/IE inspection 2

reports is documented in Appendix B as the basis for bulletin i

closeout.

A followup item is proposed in Appendix C for use by

)

NRC/IE in assuring satisfactory completion of corrective i

action.

Tabulation of supplementary information required by the bulletin is included in Appendix D.

Abbreviations used in this report and associated documents are presented in Appendix E.

I

SUMMARY

1. The bulletin has been closed out for 40 non-current facilities, per Criterion 1 (see Page 4).

i i

1 1

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... _ -,.. - - - ~,

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2. The bulletin has been closed out for the following 84 current facilities which have no subject Type W-2 switches in safety-related systems, per Criterion 2.

Arkansas 1,2 Fort Calhoun 1 Perry 1,2 Beaver Valley 1,2 Fort St. Vrain Pilgrim 1 Big Rock Point 1 Grand Gulf 1 Quad Cities 1,2 Browns Ferry 1,2,3 Harris 1 River Bend 1 Brunswick 1,2 Hatch 1,2 Robinson 2 Callaway 1 Hope Creek 1 San Onofre 2,3 Calvert Cliffs 1,2 La Crosse Seabrook 1,2 Catawba 1,2 LaSalle 1,2 Shoreham Clinton 1 Limerick 1,2 South Texas 1,2 Cook 1,2 Maine Yankee Summer 1 Cooper Station McGuire 1,2 Surry 1,2 Crystal River 3 Millstone 1,2,3 TMI 1 Davis-Besse 1 Monticello Trojan Diablo Canyon 1,2 Nine Mile Point 1,2 Vermont Yankee 1 Dresden 2,3 Oconee 1,2,3 Vogtle 1,2 Duane Arnold Oyster Creek 1 WNP 1,2 Fermi 2 Palisades Waterford 3 FitzPatrick Palo Verde 1,2,3 Wolf Creek 1 Yankee-Rowe 1

3. The bulletin has been closed out for the following 14 current facilities which have no subject Type W-2 switches with the neutral position contacts in control circuits for safety-related systems, per Criterion 3.

Facility

Number of Type W-2 Switches Bellefonte 1,2 22 North Anna 1,2 16 Peach Bottom 2,3 26 Rancho Seco 1 4

Salem 1,2 6

St. Lucie 1,2 (Not given)

Susquehanna 1,2 88 WNP 3 (Not given)

Used in safety-related systems, with neutral position contacts not used in circuits for automatic control of safety-related systems.

4. The bulletin has been closed out for the following 24 current facilities for which NRC/IE inspectors indicate satisfactory completion of corrective action, per Criterion 4.

Braidwood 1,2 Haddam Neck San Onofre 1 Byron 1,2 Indian Point 2,3 Turkey Point 3,4 Comanche Peak 1,2 Kewaunee Watts Bar 1,2 Farley 1,2 Point Beach 1,2 Zion 1,2 Ginna Prairie Island 1,2 2

1

5. The bulletin is called open for Sequoyah 1 and 2.

Followup is proposed in Appendix C.

6. Table D.1 lists 1068 subject Type W-2 switches.

No failures during the first series of tests have been reported.

7. For Zion 1,2, closure of the bulletin was by Inspection Report 295/80-20, 304/80-21 (11-28-80).

After that time, problems developed concerning the switch circuits for starting auxiliary feedvater pumps.

The switch modifications made to comply with the bulletin produced these circuitry problems only at Zion.

This situation is addressed in detail in Inspection Report 295/81-22, 304/81-18, where inspection followup items were initiated to track the problem.

The inspection items were closed out by Inspection Report 295/82-20 for Unit 1, and by Inspection Report 302/84-07 for Unit 2.

CONCLUSIONS

1. There were no failures of the neutral contact closure during the first series of tests.

This would verify the Westinghouse conclusion that the problem at Zion 1 was not generic, but rather that the intermittent failure of the contacts to close was a random occurrence.

2. The occurrence of failure of the neutral contacts of the-switch to close has been shown to be random, quite infrequent, and unpredictable.

The safety-related consequences, as described by the bulletin (Appendix A), are serious.

Therefore, action to avoid the occurrence completely is justified.

Suitable action approved by the NRC can be any one of the following:

(1)

The periodic and after use testing for contact closure (2)

Rewiring the switches to put the indicator lamp in series with the neutral contacts (3)

Replacement of switches with ones made using Westinghouse revised manufacturing procedures.*

Refer to Westinghouse letter to TVA of August 3, 1981 (see Appendix A, Page A-10).

3. The problems with modified W-2 switch circuits were unique to Zion and have been corrected.

REMAINING AREAS OF CONCERN Verification by IE inspection that bulletin actions have been completed satisfactorily is needed to close out the bulletin for Sequoyah 1 and 2 (See Appendix C).

3

CRITERIA FOR CLOSE0UT OF BULLETIN The bulletin is closed out for facilities to which one of the following criteria applies:

1. The facility has been cancelled, deferred-indefinitely or shut down indefinitely.

2. A response for the facility complies with actions required by 1

the bulletin and indicates that it does not have Westinghouse Type W-2 spring return to neutral control switches in safety-related systems.

3. A response for the facility complies with actions required by the bulletin and indicates that it has Westinghouse Type W-2 spring return to neutral control switches in safety-related systems, but that the neutral position contacts are not used, or are not used in circuits for automatic control of safety-related systems.

4 A response for the facility complies with required bulletin actions and an NRC/IE inspection report indicates that corrective action has been completed satisfactorily.

4

APPENDIX A Background Information i

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l SSINS No.: 6820 UNITED STATES Accession No.:

NUCLEAR REGULATORY COMMISSION 8006190023 0FFICE OF INSPECTIUN AND ENFORCEMENT WASHINGTON, D.C.

20555 July 31,1980 IE Bulletin No. 60-20 FAILURES OF WESTINGHOUSE TYPE W-2 SPRING RETURN TO NEUTRAL CONTROL SWITCHES By letter dated June 18, 1980, Commonwealth Edison Company submitted Licensee Event Report No. LER 50-295/80-24 to the NRC describing a malfunction of a Uestingr.ouse Type W-2 control switch at the Zion Generating Station, Unit 1.

The malfunctioning switch is a three position spring return to neutral switch.

Althougn the switch was in its proper neutral position when it malfunctioned, its neutral contacts failed to close properly thereby preventing the automatic start of 1A Service Water Pump.

1 Subsequent tests conducted on the malfunctioning switch revealed that contact closure was intermittent with the switch in the neutral (or " Auto Start")

position.

Other tests conducted on identical switches from spares and from Unit 2 equipment disclosed two additional switches with a tendency for inter-mittent contact closure.

A review of this catter by Westinghouse led to the issuance of NSD Technical i

Bulletin No. NSD-TB-80-9 to the utility owners of all Westinghouse operating plants. The recommendations contained in the Westinghouse technical bulletin j

include: (i) testing tne neutral position contacts of the subject W-2 switches i

for continuity, and (ii) rewiring of the indicating light circuit to permit i

the early detection of a neutral contact failure as shown in Figure 1.

Depending on how the indicating light circuit is wired, loss of continuity thru the neutral position contact of a W-2 switch could remain undetected until tne equipment associated with the switch were called upon to operate.

Since such a failure would be equivalent to by-passing the system associated

~

with the switch, consideration should be given to rewiring the switches used in safety-related applications as shown in ' Figure 1.

Such rewiring would provide an acceptable means for detecting contact failure, provided the indicating light is in the control room and readily visible by the operator.

If the indicating light is not so located, consideration should be given to

. annunciating the neutral position contact failures at the control room to alert the operator of the inoperable status of a safety-related system.

In addition, consideration should be given to adding redundant contacts to the W-2 switches or to replacing the W-2 switches with others having a more posi-tive contact wiping action.

ACTIONS TO BE TAKEN BY LICENSEES AND HOLDERS OF CONSTRUCTION PERMITS:

1.

Determine whether Westinghouse Type W-2 control switches with spring return to neutral position are used.in safety-related applications at your facility.

If so, identify the safety-related systems using these A-1 1

IE Bulletin t;o. 80-20 July 31, 1980 Page 2 of 2 switches ant 'M total number of switches so used.

If no such switches are used in your facility, you should indicate that this is the case and ignore the remaining questions.

2.

Licensees of operating plants using Type U-2 spring return to neutral control switches in safety-related applications shall perform continuity tests on all such switches.

These tests shall be performed with the switch operator in the neutral position and completed within ten (10) days of the date of this bulletin.

In addition, this continuity test shall be repeated at least every thirty-one (31) days after the initial test and after each manipulation of the switch from its neutral position.

These continuity tests may be discontinued subsequent to implementing the longer term corrective measures described below.

3.

Licensees of operating plants and holders of construction permits shall describe the longer term corrective measures planned and the date by which such measures will be implemented by actual installation or by design change, as appropriate.

As a minimum, the longer term corrective measures should include rewiring the indicating light as shown in Figure 1 provided the light is readily visible to the control room operator.

If not, failures of the neutral position contacts should be annunicated in the control room.

A report addressing the above matters, including the number of failures detected during the first series of tests and the safety-related systems involved, shall be submitted to the director of the appropriate flRC regional office within forty-five (45) days of the date of this bulletin.

A copy of the report shall be forwarded to the Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, fluclear Regulatory Commission, Washington, D. C. 20555.

Approved by GAO, B180225 (R0072); clearance expires 7/31/80.

Approval was 9iven under a blanket clearance specifically for identified generic problems.

Enclosure:

Figure 1 A-2

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NEUTRAL SWITCH

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FIGURE i REWIRING OF INDICATING LIGHT CIRCUIT OF W-2 SWITCHES AS RECOMMENDED BY WESTINGHOUSE TECHNICAL DULLETIN NSD-TB-80-9 A-3

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.0 EVENT CESCniPTION AND PRO 8 ABLE CONSEQUENCES h l?l lDuring cower coeration while pe r fo rming PT-10, Safeguards Actuation Tests l

.;3; llA service water pump failed to start from train A of Safeguards.

The 1

_a!.,il pump was started from the control board satisfactorily.

Re-test was l

s j limmediately attempted and completed satisf actorily from train A and B of f 3ic;l Safeguards.

Or. 6/14/80 this was reported to the NRC under 10CFR21.

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CAUSE CESCRIPTICN AND COARECTnvE ACTIONS 101lAfter circuit was proved operable a follow up investination revealed l i l i l IWestinghouse Type W-2 switch contacts used in ESP component actuation

,,,i l circuits were making intermittent contact.

The root cause could not be

,;3i ; determined due to the random nature of the failure.

All switch contacts i i,,4 i lhave been verified closed.

Permanent modifications are being evaluated.

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ATTACHMENT TO LER NO. 80-24/99 X-1 COMMONWEALTH EDISON CO.

ZION GENERATING STATION 50-295 The failure of the 1A Service Water Pump during testing preci-pitated an investigation of the actuating circuit for this particular pump.

The testing revealed a random failure mode for the' Westinghouse Type W-2 Control Switch which caused the closed auto start contact to be open intermittently.

These_ switches are used in many of the ESF Components' Circ ~uitry and the failure of the auto start contact could prohibit component auto start on a safeguards actuation signal.

Therefore the NRC was notified of a safety significant defect in the Westinghouse Type W-2 control Switch under the requirements of 10CFR21.21.

Voltage measurements were made to verify the contacts were in fact closed on the operating unit.

All W-2 switch-contacts on the unit in refueling will be verified prior to startup.

Permanent modifications are being evaluated to correct the problem.

The following information is provided as required by 10CFR21.21.b.3:

1.

Name and address of the individual or individuals informing i

the Commission.

Larry Soth, Assistant Superintendent, Zion Generating Station.

101 Shiloh Blvd Zion, Illinois 60099 ii.

Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.

Westinghouse Type W-2 Control Switch with spring return to neutral position.

iii.

Identification of the firm constructing the facility or supplying the basic component which~ fails to comply or contains a defect.

Westinghouse Electric Company (Electrical Division)

A-5

iv.

Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.

The auto start closed contact has been observed to fail open when the switch is in the neutral or auto start position.

This failure could cause the respective piece of ESF equipment controlled by the switch to fail to auto start on a safety injection signal.

v.

The date on which the information of such defect or failure to comply was obtained.

6/13/80 vi.

In the case of a basic component which contains a defect or fails to comply,.the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations in this part.

There are presently 29 switches per unit in ESF circuits at Zion Station and 7 in the station storeroom.

No new switches are presently on order.

vii.

The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.

l All switches on the operating unit in ESF circuits have l

been tested to show the contact to be presently closed.

l 13 of the 29 switches on the unit in refueling have been i

tested and the remaining 16 switches will be tested prior to startup.

Modifications are being evaluated for per-manent solution to the problem by Commonwealth Edison Company' and Westinghouse Electric Corporation.

Modifi-cations will be implemented expeditiously.

viii. Any advice related to the defect or failure to comply about the f acility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.

Commonwealth Edison Company is presently awaiting written results of the Westinghouse management evaluation and recommended solution.

A-6

Westinghouse

.3:

Nuclear hSiil Service Technical Bulletin Division An advisory notice of a recent technical development pertaining to the installation or operation of Westinghouse 4upplied Nuclear Plant equipment. Recipients should evaluate the information and recommendation, and initiate action where appropriate.

P.O. Box 2728, Pittsburgh, PA 15230 Suo;ect Number W-2 Switches (with spring return to neutral)

NSD.TB. 80-9 (Rev. 11 System (s)

Date

. Electrical Control 2/16/81 Attacted Plants S.O.ts)

All Sites 385 References Sheet Of NSD TB-73-26. & initial issue of this bulletin, dated 7/18/80 1

2 BACKGROUND INFORMATION During monthly operational testing of the safeguards system at an operating nuclear plant, intenaittent W-2 switch operation was discovered in the neutral (auto) position Investigations revealed that the intermittent operation resulted when the switch is returned from the eleven or one o' clock position to the neutral (auto) position. The matter was reported to the Nuclear Regulatory Commission on June 18, 1980. At the same time, the initial issue of this Bulletin presented preliminary Westinghouse recomendata W Switchgear Division, the manufacturer, has completed a thorough evaluation of the

_W-2 switch with spring return to neutral (auto), and concluded that no generic failure mechanism exists. This conclusion has been confirTned by independent tests at the W_

Research Laboratories. The intermittent contact closure reported abo've was a random occurrence. The REC 0 MENDED ACTION previously provided by Westinghouse in the initial issue of this Bulletin is modified as indicated below. These actions meet the minimum requirements recommended by NRC Bulletin 80-20 of July 31, 1980.

RECOMMENDED ACTION 1.

All plants should test all safety-related contacts of the W-2 switches (with spring return to neutral position) in the neutral position.

2.

These tests should be repeated following each subsequent use (removal from the neutral position) of the switch, and should be done either at nonnal operating voltage at the contacts, or at least 24 VDC.

AdditionalInformation,if Required rney be obtained from the onginator. Telephone 412 256-5493-or (wim 236 -5493.

V) Y YL

/

W. H. Furfari J. R. Terry, M ager Electric Service Electric Service heither Vuestenghouse Electric Corporation nor its employes make any warranty or representation with respect to the accuracy, completeness or usef>

pena of ane enformation conta.ned in this report or asai.ime any responsability for liability or damage an cn may result itorn the wie of such informatg WESTINGHOUSE FOpa4 SS37e A-7

Westinghouse b

Nuclear MiMD Service Technical Bulletin Division An advisory notice of a recent technical development pertaining to the installation or operation of Westinghouse-supplied Nuclear Pitnt equipment. Recipients should evaluate the information and recommendation, and initiate action where appropriate.

P.O. Box 2728,Pittsburgh,PA 15230 NSD-TB-80-9 (Rev. 1) 2/16/81 As an alternative to these periodic tests, a permanent resolution of any tendencies to intermittent contact continuity is to wire the existing breaker green light indicator in series with the neutral position safety-related switch contacts (See Sketch).

In those instances where no indicating lights exist, a lamp drawing a minimum of 30 milliamperes D.C. should be added.

This current provides for breakdown of contact film contaminents (fritting) so that no safety circuit relaying on contact continuity can fall into a degraded condition. Green light indication will now confinn closure of the safety-related switch contacts, and this indication should be checked after each switch cperation.

EXISTING (TYPICAL)

PROPOSED (TYPICAL)

Neutral [

Neutral Switch j Switch Contact 7 Contact '

I O

Y hf k

Yl Y

hf Safety Safety Signal Signal

+

A-8

TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 SN 157B Lookout Place November 19, 1985 Mr. James Stewart Office of Inspection and Enforcement U..S.

Nuclear Regulatory Commission Wishington, D.C.

20555 Mail Stop 359 EW/W Dear Mr. Stewart WATTS BAR NUCLEAR PLANT UNITS 1 AND 2 - OFFICE OF INSPECTION AND ENFORCEMENT l

- BULLETIN 80 FAILURES OF WESTINGHOUSE TYPE W-2 SPRING RETURN-TO-NEUTRAL i

CONTROL SWITCHES - SUPPLEMENTAL INFORMATION l

As discussed in your recent telephone conversation with Ralph Shell, we are j

providing a copy of the August 5, 1981 Westinghouse letter describing to us the two options available for correction of the problems with the type W-2 awitches.

If there are any question, please get in touch with R. H. Shell at FTS 858-2688.

Very truly yours, TENNESSEE VALLEY AUTHORITY I, tp. //4b,

.W.Hufham,Maddf Licensing and Risk Protection Enclosure A-9 l

L S2082703191 h

Westinghouse Water Reactor w c=recw Electric Corporation Divisions

- *' *5 0*5'"

'8 W easss Ec'c:4 iourrI cou mio out L.

REPLY j COPY COPY DATE 1.c,. n n.re w

<c, g

.s ci n c.s i

i

'.4 s F oop;, x_t i

August 5, 1981 avc :49s tv A i i

T.".---_..'.

.. d.rc._

TVA Contract tios.

919.*

' 9/dl and 71C62-54114-1

., w,~"

i Mr. J. A. Raulston Kw&_J T_,',j jl ~ i g

Chief Nuclear Engineer TVA-8319

^

TENNESSEE VALLEY AUTHORITY *~ " "

Mu,

)(-4/gg WAT-D-4525 r_

400 Cocrnerce Aver.ue, W10 C126 Knoxville, Tennessee 37902 y,Aff),

File: 16.0 E O f/D/gz.

~

C>

Dear Mr. Raulston:

cp e

in TENNESSEE VALLEY AUTHORITY gW SEQUOYAH AND WATTS BAR NUCLEAR PLANTS i'W UNIT NUMBERS 1 AND 2 g

7 g

W-2 Switch - Punch List Iten 12-395-05 The purpose of this lettcr is to review and document the Westinghouse positb on the W-2 Switch used in safety related applications at Sequoyah and Watts Bar and many other Westinghouse designed nuclear facilities.

Follcwing the reported intertaittent behavior at the Zion station, W conducted a thorough investigation of similar W-2 switches in 'ervice at the time of failu*e at Zion, switches mounted at the Byron Units and switches in inventory at both stations.

The results of the testing proved that tScre was no cerrnon mode failure mechanism at work in the W-2 switches. The failures induced in the test samples were rande m in nature and were attributable to dirt, sulfide on ccntact services and plastic.

debris from manufacture.

Westinghouse then recormiended to our customers and the NRC that the lamp, pr viou s%

recormlended, be maintained in service with the subject contact to assure the cpercttor that the contact is capable of carrying current.

In summary, Westinghouse has confined thrcugh the testing that the switch is ode,tuah.

for the service intended, internal contaminants could produce switch malfur.ctions and there are no common raode failure mechanisms. Westinghouse has revised the switch manufacturing process to include additior.31 cleaning steps to reduce internal contamination during assembly.

NEB '8208 03 9 9 2_

a ADVANCE COPY OF Tills A-10 IJ.TTEft SENT '10 SW P.

/VZM 3M-2-)(

TVA has two options:

1) To wire in the monitoring lamp for assurance of contact continuity

-or-

2) To purchase switches manufactured to the new manufacturing process for additional margin.

If Westinghouse can be of any further assistance, please call.

Very truly yours.

WESTINGHOUSE ELECTRI Conc 0R l N' J.* L. Tain, Manager

'd ennessee Valley Author Projects

/rcc J. A. Raulston, 3L cc:

R. E. Lyman. 1L I

S. A. Moser, IL l

B. Wade, IL l

L. M. Mills, IL A-ll

l I

APPENDIX B Documentation of Bulletin Closeout

TABLE B.1 BULLETIN CLOSE0UT STATUS Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Arkansas 1 AP&L 50-313 OL IV 09-09-80 Closed 2 Arkansas 2 AP&L 50-368 OL IV 09-09-80 Closed 2 Bailly 1 NIPSCO 50-367 CD III 08-11-80 Closed 1 Beaver Valley 1 DLC 50-334 OL I

08-18-80 80-25(12-05-80)

Closed 2 Beaver Valley 2 DLC 50-412 CP I

09-19-80 82-11(10-25-82)

Closed 2 Bellefonte 1 TVA 50-438 CP II 09-16-80 82-14(06-15-82)

Closed 3 12-12-80 04-02-81 08-13-81 11-09-81 Bellefonte 2 TVA 50-439 CP II 09-16-80 82-14(06-15-82)

Closed 3 12-12-80 04-02-81 08-13-81 m

11-09-81 1

Big Rock Point 1 CPC 50-155 OL III 08-15-80 80-10(09-25-80)

Closed 2 Braidwood 1 CECO 50-456 CP III 07-23-80 85020(04-30-85)

Closed 4 09-15-80 01-09-81 04-10-81 04-30-81 08-29-84 l

Braidwood 2 CECO 50-457 CP III 07-23-80 85021(04-30-85)

Closed 4 09-15-80 01-09-81 04-10-81 04-30-81 08-29-84 Browns Ferry 1 TVA 50-259 OL II 09-12-80 81-35(12-18-81)

Closed 2 Browns Ferry 2 TVA 50-260 OL II 09-12-80 81-35(12-18-81)

Closed 2 Browns Ferry 3 TVA 50-296 OL II 09-12-80 81-35(12-18-81)

Closed 2 Brunswick 1 CP&L 50-325 OL II 08-19-80 Closed 2 Brunswick 2 CP&L 50-324 OL II 08-19-80 Closed 2 See notes at end of table.

TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Byron 1 CECO 50-454 OL III 07-23-80 84-69(10-10-84)

Closed 4 09-15-80 01-09-81 04-10-81 04-30-81 08-29-84 Byron 2 CECO 50-455 CP III 07-23-80 84-47(10-10-84)

Closed 4-1 09-15-80 01-09-81 04-10-81 04-30-81 08-29-84 Callaway 1 UE 50-483 OL III 09-09-80 81-17(08-13-81)

Closed 2 Callaway 2 UE 50-486 CD III 09-09-80 Closed I Calvert Cliffs 1 BG&E 50-317 OL I

08-21-80 80-26(02-11-81)

Closed 2 w

i Calvert Cliffs 2 BG&E 50-318 OL I

08-21-80 80-22(02-11-81)

Closed 2 Catawba 1 DUPC0 50-413 OL II 08-20-80 Closed 2 Catawba 2 DUPCO 50-414 CP II 08-20-80 Closed 2 Cherokee 1 DUPC0 50-491 CD II 08-14-80 Closed 1 Cherokee 2 DUPCO 50-492 CD II 08-14-80 Closed 1 Cherokee 3 DUPCO 50-493 CD II 08-14-80 Closed 1 Clinton 1 IP 50-461 CP III 09-16-80 81-11(06-19-81)

Closed 2 Clinton 2 IP 50-462 CHI III 09-16-80 Closed 1 Comanche Peak 1 TUGC0 50-445 CP IV 08-29-80 84-22(10-02-84)

Closed 4 11-19-80 05-07-81 08-04-81 10-07-81 12-09-81 See notes at end of table.

TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Comanche Peak 2 TUGC0 50-446 CP IV 08-29-80 84-07(10-02-84)

Closed 4 11-19-80 05-07-81 08-04-81 10-07-81 12-09-81 Cook 1 IMECO 50-315 OL III 09-08-80 80-13(10-22-80)

Closed 2 Cook 2 IMECO 50-316 OL III 09-08-80 80-11(10-22-80)

Closed 2 Cooper Station NPPD 50-298 OL IV 08-06-80 80-12(08-29-80)

Closed 2 Crystal River 3 FP 50-302 OL II 08-05-80 Closed 2 Davis-Besse 1 TECO 50-346 OL III 09-12-80 80-25(10-14-80)

Closed 2 Diablo Canyon 1 PG&E 50-275 OL V

09-22-80 81-06(04-03-81)

Closed 2 Diablo Canyon 2 PG&E 50-323 OL V

09-22-80 81-06(04-03-81)

Closed 2 Dresden 1 CECO 50-010 SDI III 09-15-80 Closed 1 m

Dresden 2 CECO 50-237 OL III 09-15-80 84-03(04-10-84)

Closed 2 Dresden 3 CECO 50-249 OL III 09-15-80 84-02(04-10-84)

Closed 2 Duane Arnold IELPCO 50-331 OL III 08-29-80 Closed 2 Farley 1 APCO 50-348 OL II 09-16-80 83-31(01-10-84)

Closed 4 09-24-80 12-18-81 Farley 2 APCO 50-364 OL II 09-16-80 83-29(01-10-84)

Closed 4 09-24-80 10-28-80 12-18-81 Fermi 2 DECO 50-341 OL III 09-15-80 Closed 2 FitzPatrick PASNY 50-333 OL I

08-12-80 81-06(03-23-81)

Closed 2 Forked River JCP&L 50-363 CD I

Closed 1 Fort Calhoun 1 OPPD 50-285 OL IV 06-08-80 81-14(07-23-81)

Closed 2 Fort St. Vrain PSCC 50-267 OL IV 09-18-80 Closed 2 Ginna RG&E 50-244 OL I

09-10-80 81-11(07-31-81)

Closed 4 11-17-80 Grand Gulf 1 MP&L 50-416 OL II 09-17-80 Closed 2 10-15-80 See notes at end of table.

TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Grand Gulf 2 MP&L 50-417 CHI II 09-17-80 Closed 1 10-15-80 l

Haddam Neck CYAPCO 50-213 OL I

09-15-80 85-13(09-05-85)

Closed 4 Harris 1 CP&L 50-400 CP II 09-12-80 Closed 2 Harris 2 CP&L 50-401 CHI II 09-12-80 Closed 1 Harris 3 CP&L 50-402 CHI II 09-12-80 Closed 1 1

Harris 4 CP&L 50-403 CHI II 09-12-80 Closed 1 Hartsville A-1 TVA 50-518 CD II 09-12-80 Closed 1 Hartsville A-2 TVA 50-519 CD II 02-10-81 Closed 1 Hartsville B-1 TVA 50-520 CD II 06-15-81 Closed 1 Hartsville B-2 TVA 50-521 CD II 08-14-81 Closed 1 10-30-81 02-19-82 Hatch 1 GPC 50-321 OL II 09-12-80 Closed 2

?

Hatch 2 GPC 50-366 OL II 09-12-80 Closed 2 Hope Creek 1 PSE&G 50-354 CP I

09-03-80 Closed 2 11-14-80 12-23-80 11-04-83 Hope Creek 2 PSE&G 50-355 CHI I

09-03-80 Closed 1 11-14-80 12-23-80 11-04-83

~

Humboldt Bay 3 PG&E 50-133 SDI V

09-08-80 Closed 1 Indian Point 1 Coned 50-003 SDI I

09-15-80 Closed 1 Indian Point 2 Coned 50-247 OL I

09-15-80 85-07(04-22-85)

Closed 4 03-03-81 Indian Point 3 PASNY 50-286 OL.

I 09-12-80 82-03(03-19-82)

Closed 4 02-10-81 85-24(12-12-85) 03-03-81 06-24-82 Jamesport 1 LILCO 50-516 CD I

09-16-80 Closed 1 Jamesport 2 LILCO 50-517 CD I

09-16-80 Closed 1 See notes at end of table.

i TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Kewaunee WPS 50-305 OL III 09-19-80 80-28(01-15-81)

Closed 4 La Crosse DPC 50-409 OL III 08-08-80 Closed 2 i

LaSalle 1 CECO 50-373 OL III 09-15-80 Closed 2 LaSalle 2 CECO 50-374 OL III 09-15-80 83-08(04-06-83)

Closed 2 Limerick 1 PECO 50-352 OL I

09-10-80 84-01(02-17-84)

Closed 2 Limerick 2 PECO 50-353 CP I

09-10-80 84-02(02-17-84)

Closed 2 Maine Yankee MYAPC0 50-309 OL I

09-04-80 Closed 2 Marble Hill 1 PSI 50-546 CHI III 09-15-80 Closed 1 Marble Hill 2 PSI 50-547 CHI III 09-15-80 Closed 1 McGuire 1 DUPCO 50-369 OL II 08-20-80 80-33(12-11-80)

Closed 2 McGuire 2 DUPC0 50-370 OL II 08-20-80 80-18(12-11-80)

Closed 2 Midland 1 CPC 50-329 CHI III 09-22-80 Closed 1 Midland 2 CPC 50-330 CHI III 09-22-80 Closed 1 E

Millstone 1 NNECO 50-245 OL I

09-15-80 Closed 2 Millstone 2 NNECO 50-336 OL I

09-15-80 Closed 2 Millstone 3 NNECO 50-423 CP I

09-15-80 82-02(03-11-82)

Closed 2 Monticello NSP 50-263 OL III 09-12-80 80-20(01-16-81)

Closed 2

-Nine Mile Point 1 NMP 50-220 OL I

09-11-80 Closed 2 Nine Mile Point 2 NMP 50-410 CP I

09-11-80 Closed 2 10-30-80 North Anna 1

.VEPC0 50-338 OL II 09-15-80 82-40(02-07-83)

Closed 3 North Anna 2 VEPCO 50-339 OL II 09-15-80 G2-40(02-07-83)

Closed 3 North Anna 3 VEPC0 50-404 CD II 08-27-80 Closed 1 09-01-82 North Anna 4 VEPCO 50-405 CD II 08-27-80 Closed 1 09-01-82 Oconee 1 DUPCO 50-269 OL II 08-14-80 80-32(.11-03'80)

Closed 2 Oconee 2 DUPCO 50-270 OL II 08-14-80 80-28(11-03-80)

Closed 2 Oconee 3 DUPC0 50-287 OL II 08-14-80 80-25(11-03-80)

Closed 2 Oyster Creek 1 JCP&L

,50-219 OL I

08-28-80 Closed 2 Palisades CPC 50-255 OL III 08-12-80 80-21(11-21-80)

Closed 2 See notes at end of table.

TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Palo Verde 1 APSCO 50-528 OL V

09-15-80 83-08(03-30-83)

Closed 2 Palo Verde 2 APSCO 50-529 CP V

09-15-80 83-04(03-30-83)

Closed 2 Palo Verde 3 APSCO 50-530 CP V

09-15-80 83-03(03-30-83)

Closed 2 Peach Bottom 2 PECO 50-277 OL I

09-10-80 84-26(09-21-84)

Closed 3 Peach Bottom 3 PECO 50-278 OL I

09-10-80 84-22(09-21-84)

Closed 3 i

Perkins 1 DUPC0 50-488 CD II 08-14-80 Closed 1 Perkins 2 DUPCO 50-489 CD II 08-14-80 Closed 1 Perkins 3 DUPCO 50-490 CD II 08-14-80 Closed 1 Perry 1 CEI 50-440 CP III 09-04-80 Closed 2 Perry 2 CEI 50-441 CP III 09-04-80 Closed 2 Phipps Bend 1 TVA 50-553 CD II 09-12-80 Closed 1 Phipps Bend 2 TVA 50-554 CD II 02-10-81 Closed 1 06-15-81 08-14-81 i

10-30-81 02-19-82 Pilgrim 1 BECO 50-293 OL I

08-08-80.

Closed 2 Point Beach 1 WEPCO 50-266 OL III 09-16-80 80-20(12-17-80)

Closed'4 Point Beach 2 WEPCO 50-301 OL III 09-16-80 80-20(12-17-80)

Closed 4 Prairie Island 1 NSP 50-282 OL III 09-12-80 82-05(04-19-82)

Closed 4 12-11-80 Prairie Island 2 NSP 50-306 OL III 09-12-80 82-05(04-19-82)

Closed 4 12-11-80 i

Quad Cities 1 CECO 50-254 OL III 09-15-80 Closed 2 Quad Cities 2 CECO 50-265 OL III 09-15-80 Closed 2 Rancho Seco 1 SMUD 50-312 OL V

09-15-80 80-27(10-22-80)

Closed 3 River Bend 1 GSU 50-458 LPTL IV 09-19-80 Closed 2 4

River Bend 2 GSU 50-459 CD IV 09-19-80 Closed 1 Robinson 2 CP&L 50-261 OL II 08-21-80 80-29(11-10-80)

Closed 2 09-30-80 Salem 1 PSE&G 50-272 OL I

09-05-80 80-23(12-03-80)

Closed 3 10-14-80 Salem 2 PSE&G 50-311 OL I

09-05-80 80-18(12-03-80)

Closed 3 10-14-80 See notes at end of table.

TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion San Onofre 1 SCE 50-206 OL V

09-05-80 81-41(12-30-81)

Closed 4 11-18-81 San Onofre 2 SCE 50-361 OL V

09-11-80 81-07(05-22-81)

Closed 2 San Onofre 3 SCE 50-362 OL V

09-11-80 81-02(05-22-81)

Closed 2 Seabrook 1 PSNH 50-443 CP I

08-22-80 82-04(07-07-82)

Closed 2 Seabrook 2 PSNH 50-444 CP I

08-22-80 82-04(07-07-82)

Closed 2 Sequoyah 1 TVA 50-327 OL II 09-16-80 81-09(03-19-81)

Open 12 '_2-80 04-02-81 08-13-81 11-09-81 01-20-83 Sequoyah 2 TVA 50-328 OL II 09-16-80 81-08(03-19-81)

Open 12-12-80 04-02-81 i

08-13-81 11-09-81 01-20-83 Shoreham LILCO 50-322 LPTL I

10-10-80 81-22(01-14-82)

Closed 2 South Texas 1 HL&P 50-498 CP IV 09-09-80 81-32(11-12-81)- Closed 2 South Texas 2 HL&P 50-499 CP IV 09-09-80 81-32(11-12-81)

Closed 2 St. Lucie 1 FPL 50-335 OL II 09-12-80 80-36(01-29-81)

Closed 3 St. Lucie 2 FPL 50-389 OL II 09-15-80 80-16(12-15-80)

Closed 3 11-13-80 Sterling RG&E 50-485 CD I

Closed 1 Summer 1 SCE&G 50-395 OL II 09-11-80 81-04(03-09-81)

Closed 2 Surry 1 VEPCO 50-280 OL II 09-15-80 84-09(03-23-84)

Closed 2 Surry 2 VEPC0 50-281 OL II 09-15-80 84-09(03-23-84)

Closed 2 Susquehanna 1 PP&L 50-387 OL I

09-23-80 82-08(04-08-82)

Closed 3 11-03-80 Susquehanna 2 PP&L 50-388 OL I

09-23-80 82-04(05-19-82)

Closed 3 11-03-80 TMI 1 Met-Ed 50-289 OL I

09-02-80 80-29(05-12-81)

Closed 2 TMI 2 Met-Ed 50-320 SDI I

09-30-80 Closed 1 See notes at end of table.

TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Trojan PGE 50-344 OL V

09-15-80 80-25(11-03-80)

Closed 2 Turkey Point 3 FPL 50-250 OL II 09-16-80 84-14(06-15-84)

Closed 4 03-31-81 Turkey Point 4 FPL 50-251 OL II 09-16-80 84-14(06-15-84)

Closed 4 03-31-81 Vermont Yankee 1 VYNP 50-271 OL I

08-22-80 Closed 2 Vogtle 1 GPC 50-424 CP II 09-16-80 81-15(01-28-82)

Closed 2 Vogtle 2 GPC 50-425 CP II 09-16-80 81-15(01-28-82)

Closed 2 WNP 1 WPPSS 50-460 CP V

09-08-80 80-13(11-21-80)

Closed 2 WNP 2 WPPSS 50-397 OL V

09-15-80 81-02(02-19-81)

Closed 2 WNP 3 WPPSS 50-508 CP V

10-01-60 82-03(02-26-82)

Closed 3-WNP 4 WPPSS 50-513 CHI V

09-08-80 Closed 1 WNP 5 WPPSS 50-509 CHI V

10-01-80 Closed 1 Waterford 3 LP&L 50-382 OL IV 09-09-80 Closed 2 10-15-80 Watts Bar 1 TVA 50-390 CP II 09-16-80 83-46(11-22-83)

Closed 4 12-12-80 04-02-81 08-13 11-09-81 06-02-82 03-30-83 11-19-85

-Watts Bar 2 TVA 50-391 CP II 09-16-80 83-35(11-22-83)

Closed 4 12-12-80 04-02-81 08-13-81 11-09-81 06-02-82 03-30-83 11-19-85 Wolf Creek 1 KG&E 50-482 OL IV 09-09-80 84-01(02-14-84)

Closed 2 See notes at end of table.

~

=

TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion Yankee-Rowe 1 YAECO 50-029 OL I

08-29-80 80-20(01-28-81)

Closed 2 Yellow Creek 1 TVA 50-566 CHI II 09-16-80 Closed 1 Yellow Creek 2 TVA 50-567 CHI II 12-12-80 Closed 1 04-02-81 08-13-81 11-09-81 Zimmer 1 CG&E 50-358 CD III 09-02-80 Closed 1 Zion 1 CECO 50-295 OL III 09-15-80 80-20(11-28-80)

Closed 4 Zion 2 CECO 50-304 OL III 09-15-80 80-21(11-28-80)

Closed 4

]

Notes:

1.

Facility Status is based on References 1, 2, and 3, Page B-10.

2.

The following abbreviations apply to facility status:

CD, Cancelled; CHI, Construction Halted Indefinitely; CP, Construction Permit;

LPTL, Low Power Testing License; OL, Operating License; SDI, Shut Down Indefinitely.

3.

Refer to Page 4 for Bulletin Closeout Criteria.

REFERENCES

1. United States Nuclear Regulatory Commission, Licensed Operating Reactors,_ Status Summary Report, Data as of 09-30-85, NUREG-0020, Volume 9, Number 10, October 1985.

2. United States Nuclear Regulatory Commission, Nuclear Power Plants, Con _struction Status Report, Data as of 06-30-82, NUREG-0030, Volume 6, Number 2, October 1982.

3. United States Nuclear Regulatory Commission, Listing ot Inactive Current Holders of Construction Permits, Letter dated May 29, 1985, to Richard A. Lofy (Parameter, Inc.) from Robert L. Beer (NRC/IE HQ).

4. United States Nuclear Regulatory Commission, Code of Federal Regulations, Energy, Title 10, Chapter 1, January 1,

1985, cited as 10CFR 0.735-1.

B-10

APPENDIX C Proposed Followup Item Region II Sequoyah 1,2 IE inspection report 81-09/81-08 of 03-19-81 holds the bulletin open.

Open status was confirmed by NRC/IE in letter to Parameter, Inc. (R.S. Dean) from R.L. Baer (IE) of February 12, 1986.

Closeout is to be included in a future inspection report.

i C-1

APPENDIX D TABLE D.1 IDENTIFICATION OF AFFECTED SYSTEMS, NUMBER OF TYPE W-2 SWITCHES AND NUMBER OF FAILURES Number of Switches:

Facility Affected Systems Used Failed Braidwood 1,2 Primary Containment HVAC 16 Auxiliary Feedwater 4

Essential Service Water 4

Component Cooling 8

Containment Spray 4

Safety Injection 4

Residual Heat Removal 4

Boron Thermal Regeneration 2

Chemical and Volun.e Control 6

Boric Acid Processing 2

Reactor Coolant 24 Main Steam 4

Diesel Generator Room Ventilation 4

Switchgear Room Ventilation 12 Containment Purge 4

Auxiliary Power 24 Diesel Generator 12 Auxiliary Building Ventilation 16*

Control Room Ventilation 6*

Chilled Water 4*

Essential Service Water 18*

Total 182 Byron 1,2 Primary Containment HVAC 16 Auxiliary Feedwater 4

Essential Service Water 4

Component Cooling 8

Containment Spray 4

Safety Injection 4

Residual Heat Removal 4

Boron Thermal Regeneration 2

Chemical and Volume Control 6

Boric Acid Processing 2

Reactor Coolant 24 See notes nt end of table.

D-1

ll TABLE D.1 (contd)

Number of Switches:

Facility Affected Systems Used Failed

~~

Byron 1,2 Main Steam 4

(contd)

Diesel Generator Room Ventilation 4

Switchgear Room Ventilation 12 Containment Purge 4

Auxiliary Power 24 Diesel Generator 12 Auxiliary Building Ventilation 16*

Control Room Ventilation 6*

Chilled Water 4*

Essential Service Water 18*

Total 182 Comanche Peak 1,2 Electrical System (alternate offsite and onsite 6.9KV breakers) 8 Service Water 4

Safety Injection 8

Containment Spray 12 Containment Vent 2*

Component Cooling Water 4

Safety Chiller Water 4

Residual Heat Removal 4

Chemical and Volume Control 4

Main Steam Reheat 8

Main Feedwater 24 Auxiliary Feedwater 4

Safeguard and Electrical Area Vent 48 Auxiliary Building and Fuel Building Vent 8

Uncontrolled and Miscellaneous Areas Vent 8

Primary Plant Vent 2*

Control Room and Facilities Vent 20*

Total 172 Farley 1,2 Electrical 14 Reactor Trip

_4_

Total 18

~~

See notes at end of table.

D-2

. ~.

TABLE D.1 (contd)

Number of Switches:

Facility Affected Systems Used Failed Ginna Safety Injection 4

l Containment Spray 2

Component Cooling Water 2

Auxiliary Feedwater 2

Residual Heat Removal 2

l Service Water 4

Containment Vent 4

~

i Diesel Generator Supply

_4 Total

'24 4

Haddam Neck Containment Air Recirculation 4

1 Service Water 4

High Pressure Safety Injoction 2

Low Pressure Safety Injection 2

3 Charging Pumps 2

j Emergency Diesel Generators 2

Primary Water Transfer

_j[

Total 18 Indian Point 2 Service Water 8

Component Cooling 3

1 Residual Heat Removal 2

j Emergency Power Systems (includes MCC's) 10 Containment Recirculation 5

Safety Injection 4

j Containment Spray 2

j Auxiliary Feedwater 2

1 Recirculation Pumps

_j[

Total 38 0

I i

Indian Point 3 Safety Injection 5

Auxiliary Coolant 5

j Containment Spray 2

1 Containment Ventilation 5

j Service Water 6

j Feedwater 2

Electrical Distribution 13 j

Total 38 0

~

See notes at end of table.

i i

i D-3

TABLE D.1 (contd)

Number of Switches:

Facility Affected Systems Used Failed Kewaunee-4150V Supply & Distribution Diesel Generators Component Cooling Containment Spray Residual Heat Removal Safety Injection Service Water Reactor Building Vent Feedwater & Auxiliary Feedwater Total 27 0

Point Beach 1,2 Residual Heat Removal 4

Containment Spray 4

Containment Cooling ~ Fans 8

Service Water 6

Auxiliary Feedwater 2

Safety Injection 4

Component Cooling 4

Supply Breaker 4

Tie Breaker

_2 Total 38 0

Prairie Island 1,2 (Not identified) 42 0

San Onofre 1 Safety Injection 3

0 Sequoyah 1,2 Main Steam including Generator Blowdown Main and Auxiliary Feedwater High-pressure Fire Protection Diesel-generator. Turbine, Auxiliary Control and Reactor Buildings Ventilation Control Building, Heating and Air Conditioning Auxiliary Building, Additional Equipment Building, and Fuel Handling, Heat and Air Conditioning Associated Electrical Systems Chemical and Volume Control Safety Injection Emergency Gas Treatment Essential Raw Cooling Water Reactor Coolant Component Cooling Containment Spray System Residual Heat Removal Total 130 0

See notes at end of table, i

D-4 l

=

l 1

t i

TABLE D.1 (contd)

Number of Switches:

}

Facility Affected Systems _

Used Failed l

l-Turkey Point 3,4 Component Cooling Water 6

i Safety Injection 8

Residual Heat Removal 4

Containment Spray 4

Intake Cooling Water 6

Startup Transformer Breaker 4

j Load Center Feeder Breaker 8

i Emergency Startup Transfer i

Breaker 2

)

Total 42 0

t i

Watts Bar 1,2 Volume Control Safety Injection i

Emergency Gas Treatment Residual Heat Removal Containment Spray l

Auxiliary Feedwater j

Essential Raw Cooling Water j

Ventilation l

Air Conditioning Reactor Coolant Total 67 Zion 1,2 Auxiliary Power j

Component Cooling Containment Spray Auxiliary Feedwater 3

Residual Heat Removal i

Reactor Ventilation i

Safety Injection l

Service Water j

Volume Control Total

'47 0

4 A

j Notes:

I 1.

An affected system is a safety-related system containing a j

subject Type W-2 switch.

j 2.

The information given in this table.is required per Action Item 1 and the second.last paragraph of IEB 80-20.

^

?

3.

Blanks indicate information not given.

4.

For twin units, numbers are totals for both units.

i l

D-5 4

II -------....

5.

Switches common to twin units are identified with asterisks

(*).

6.

No failures were reported as a result of the testing required by the bulletin.

I 1

i l

I D-6 t

i v

APPENDIX E Abbreviations AEPSCO American Electric Power Services Corporation AFW Auxiliary Feedwater APC0 Alabama Power Company AP&L Arkansas Power and Light Company APSCO Arizona Public Service Company BECO Boston Edison Company BG&E.

Baltimore Gas and Electric Company CD Cancelled CECO Commonwealth Edison Company CEI Cleveland Electric Illuminating Company CFR Code of Federal Regulations CG&E Cincinnati Gas and Electric Company.

CHI Construction Halted Indefinitely Coned Consolidated Edison Company'of New York, Inc.

CP Construction Permit CPC Consumers Power Company CP&L Carolina Power and Light Company CR Contractor Report CYAPCO Connecticut Yankee Atomic Power Company DECO Detroit Edison Company DLC Duquesne' Light Company DPC Dairyland Power Cooperative i

DUPCO Duke Power Company FP Florida Power Corporation FPL Florida Power & Light Company GAO Government Accounting Office GPC Georgia Power Company GSU Gulf States Utilities Company HL&P Houston Lighting and Power Company}

\\

IE (See NRC/IE)

IEB Inspection and Enforcement Bulletin (NRC)

IELPCO Iowa Electric Light and Power Company IMECO Indiana and Michigan Electric Company IP Illinois Power Company IR Inspection Report (NRC/IE)

JCP&L

= Jersey Central Power.and Light Company KG&E Kansas Gas and Electric Company, LER Licensee Event Report R

E-1 s

LILCO Long Island Lighting Company LP&L Louisiana Power and Light Company LPTL Low Power Testing License Met-Ed Metropolitan Edison Company MP&L Mississippi Power and Light Company MYAPC0 Maine Yankee Atomic Power Company NIPSCO Northern Indiana Public Service Company NMP Niagara Mohawk Power Company NNECO Northeast Nuclear Energy Company NPPD Nebraska Public Power District NRC/IE Nuclear Regulatory Commission /

Office of Inspection & Enforcement NRR Office of Nuclear Reactor Regulation, NRC NSP Northern States Power Company NU Northeast Utilities OL Operating License OPPD Omaha Public Power District PASNY Power Authority of the State of New York PECO Philadelphia Electric Company PGE Portland General Electric Company PG&E Pacific Gas and Electric Company PP&L Pennsylvania Power and Light Company PSCC Public Service Company of Colorado PSE&G Public Service Electric and Gas Company PSI Public Service Indiana PSNH Public Service Company of New Hampshire R

Region (NRC)

RG&E Rochester Gas and Electric Corporation SCE Southern California Edison Company SCE&G South Carolina Electric and Gas Company SDI Shut Down Indefinitely l

SMUD Sacramento Munic ipal Utility District SNUPPS Standardized Nuclear Unit Power Plant Systems TECO Toledo Edison Company TMI Three Mile Island TUGC0 Texas Utilities Generating Company TVA Tennessee Valley Authority UE Union Electric Company VEPC0 Virginia Electric and Power Company VYNP Vermont Yankee Nuclear Power Corporation W

Westinghouse Electric Corporation WEPC0 Wisconsin Electric Power Company WNP Washington Nuclear Project WNSD Westinghouse Nuclear Service Division WPPSS Washington Public Power Supply System WPS Wisconsin Public Service Corporation YAECO Yankee Atomic Electric Company E-2 6

y...

..._..........._.s.

...- T _...

EES'-

BIBLIOGRAPHIC DATA SHEET NUREG/CR-3962 sis sstavCT.o~s os t..sve s.

PARAMETER IE-150 2 76TLE A%Q sueTafit JLlavtgLANs Closcout of IE Bulletin 80-20:

Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches

,o,,,,,,0,,cO.,,,,,,

g 3,-

,.A.

..ui-0.is, April 1986 R.

S.

Dean, W.

J.

Foley, A.

Hennick

. DAf g agromi sS5vED 0, T,,

v.A.

June 1986 7

E=8 02 Wi%G OR s A%i2 AT SON N AWE AND W AILING ADDa ts5 ndic8a,.ple Ceart e PROJECTif A5n WORE uhaf NuwetR Task Order No. 003 PARAMETER, Inc.

... 0aena~i~vv e.

13380 Watertown Plank Road Elm Grove, Wisconsin 53122 B8729 10 5/ON50megg onGA%i2 ATION NewE AND waitsNG ADDRE55 0eicfu. ele Ca.er Ita TvPtOFREPORT Division gf Emgrgency Preparedness and Engineering Response Technical Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission

.,sa,Oo COviaio u,i.

Washington, D.C.

20555 8/1/85 - 4/28/86 12 5.' PPLE MEN T AR Y h0 TE%

13 AB5TeACT (Joo res., eens On June 18, 1980, Commonwealth Edison Company submitted Licensee Event Report (LER) 50-295/80-24 to the NRC, describing a malfunction of a Westinghouse Type W-2 control switch important to safety at Zion Unit 1.

l On the same date, Westinghouse submitted a preliminary issue of Technical Bulletin NSD-TB-80-9 to the NRC on the subject switches.

On July 31, 1980, IE Bulletin 80-20 was issued to all power plant licensees and permit holders, requiring them to take specific actions and report results.

~

Evaluation of utility responses and NRC/IE inspection reports shows that the bulletin can be closed out per specific criteria for 122 (98%). of the 124 current facilities to which it was issued.

A followup item for the remaining two facilities is proposed for use by NRC/IE, to ensure satisfactory completion of corrective action.

14 DOCuwt%T AN ALYS'S - e Ki vwOmOS DESCmiPTORS 16 AvaiLasiksiv

$TAftutNT Closeout of IE Bulletin 80-20 Unlimited 16 SECum TY CL AS$t# C ATION iTne enpeo

. ietsTias oPa= s~cio Teams Unelassifiec

, r,s

.ru Unclassifiec 17 Nuoate Os PAG 5 is PmeCE

___________________-_.____.--_-.-----b

NUREG/CR-3962, Forwards NUREG/CR-3962, Closeout of IE Bulletin 80-20: Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches

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NUREG/CR-3962, Forwards NUREG/CR-3962, Closeout of IE Bulletin 80-20: Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches

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SUBJECT:

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Dear Mr. Raulston:

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