ML18018A939

Letter Responding to Oral Requests Made by the Commission Staff Regarding the Unit 2 Cooling Tower

ML18018A939
Person / Time
Site:	Nine Mile Point
Issue date:	04/18/1978
From:	Rhode G Niagara Mohawk Power Corp
To:	Case E Office of Nuclear Reactor Regulation
References
Download: ML18018A939 (48)

Text

'e 5 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >

DISTRIBUTION FOR INCOMING MATERIAL 50-410 r

REC: CASE E G ORG: RHODE G K DOCD ATE: 04/18/78 NRC NIAGARA MOHAWK PWR DATE RCVD:" <)4/26/78

,DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 0 RESPONSE TO ORAL REQUESTS MADE BY NRC... FURNISHING INFO CONCERNING SUB JECT FACILITY' UNIT 2) COOLING TOWER.

PLANT NAME: NINE MILE POINT UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++++<<+<<<+<+~<++

~

ENVIRONMENTAL COMMENTS (DISTRIBUTION CODE C002>

FOR ACTION: ASST DIR MOORE++LTR ONLY(i> BR CHIEF REGAN>>LTR ONLY(i>

PROJ MGR NORRIS+4LTR ONLY(i) LIC ASST DUNCAN+<LTR ONLY<i)

FOR INFO: VASSALLO+4LTR ONLY(1) VARGA44LTR ONLY< 1)

FOR INFO: KANE++LTR ONLY( SERVICE4+LTR ONLY(1)

INTERNAL: EG FILE+%LTR ONLY(i NRC PDR++LTR ONLY(i>

.~N OELD+<LTR ONLY<i)

HANAUER++LTR ONLY(1) DENTON/MULLER++LTR ONLY(1)

ERNST+%LTR ONLY<i) BALLARD++LTR ONLY< 1)

YOUNGBLOOD>+LTR ONLY(i> GAMMILL4+LTR ONLY(2)

VOLLMER44LTR ONLY<i) BUNCH++LTR ONLY<1)-

J. COLLINS++LTR ONLY(i> KREGER++LTR ONLY(i>

EXTERNAL: LPDR S OSWEGO'Y++LTR ONLY<i)

NATL LAB ANL4+LTR ONLY(6)

NS I C++LTR ONLY < 1 )

TIC++LTR ONLY(i>

ACRS CAT B4+LTR ONLY<0)

DISTRIBUTION: LTR 34 ENCL 0 CONTROL NBR: 781160153 SI ZE: 3P

t " I l 0 I l(P j( ji Ighfh I ~ t It

," ~~

4 II I, h>>

h

~,

j p

'I ~ .

h It I

)' ll

'* jg fI

~

It W

4 w I I'I P<<r ( Wr ~

(i\(j jj'<P MOHAWK POWER CORPORATION P'IAGARA NIAGARA l 'OHAWK 300 ERIE BOULEVARD, WEST SYRACUSE, N. Y. 13202 April 18, 1978 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation CP A 1 U. S, Nuclear Regulatory Commission Ca I'h a Washington, D. C. 20555 CAW

~C/7

~ C)

P7

Dear Mr. Case:

S 11 1

ITI I CO Nine Mile Point Unit 2~

Docket No. 50-410 The following information responds to oral requests made by your staff regarding the Nine Mile Point Unit 2 cooling tower.

Section 8.4.1.3.11 of the Environmental Report-Construction Permit Stage and Figure 14 of the "Report on Circulating Water Cooling System Employing a Natural Draft Cooling Tower," July 1976, do not agree with respect to the predicted area affected by plant noise. The data contained in the latter report are more recent and accurate. These values should be used for plant noise evaluation. The major reasons for the differences in the predictions are as follows:

1) The Ellis Method used to evaluate noise for the Environmental Report was the best method available at that time. This method was developed fox small cooling towers. The Ellis Method overpredicts noise for large cooling towers. The predictions in the July 1976 report~13 were made using a new method based upon field measurements of a number of large cooling towers.

2) The 1976 noise calculations include the effect of atmospheric adsorption for transformer noise. The Environmental Report predictions did not and are therefore louder.

Qo Sy 78li60],g3 ,(0

p I

Mr. Edson Case April 18, 1978 U. S. Nuclear Regulatory Commission Page Two

= The discharge hT calculated from the heat addition to the lake value (0.-74 x 109 Btu/hr) on Page 6 of the "Report on Circulating Water Cooling System Employing a Natural Draft Cooling Tower,," July, 1976, does not agree with the value in Response 14 of our September 30, 1977 submittal. The 19F hT indicated in this latter report is the correct-value and incorporates specific cooling tower vendor predictions. The discharge,hT of 19F is an annual average based on. a discharge flow of 25,000 gallons per minute. The earlier calculations were not based, upon a specific tower since the vendor had not been selected at that time.

The worst case lake surface temperature increase is about 2.7F. This corresponds to a combined plant discharge hT of 30.6F and a flow of 18,.020 gallons per minute. These calculations are based upon conservative worst case conditions of 32F lake. temperature and a wet bulb air temperature of 57F at 45 percent relative humidity. Air temperature was selected from Rochester weather data for the period 1933 to 1972, and lake temperature was based upon 1972 weather conditions.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION Geral K. Rh de, Vice President System Project Management NLR/szd

)

P

Mr. Edson Case April 18, 1978 U. S..Nuclear Regulatory Commission Page Three REFERENCES 1

R. M. Ellis, Coolin Tower Noise Generation and Radiation Journal of .San an Vibration, Vo ume 1 , Pages 17 -1 2, 1971.

2 Capano, G. A.; Bradley, W.E., "Radiation of Noise From Large Natural Draft and Mechanical Draft Cooling Towers" ASME Paper No. 74-WA-HT-55.

3 Capano, G.A.; Bradley,- W.E., "Noise Predicting Techniques for Siting Large. Mechanical Draft Cooling Towers" presented at the 38th Annual Meeting of American Power Conference, April, 1976.

J

~ ~

- DIS ocket fi Local SVarga LP[1: ~

PDR HService LWR-4 Attorney OEL'D

I

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20666 APR 311978 Docket No. 50-410 Niagara Mohawk Power Corporation ATTN: Mr. Gerald K. Rhode, Vice President Systems Project Management 300 Erie Boulevard West Syracuse, New York 13202 Gentlemen:

SUBJECT:

REVISED INTRUSION DETION SYSTEMS HANDBOOK - Nine Mile Point 2 Transmitted under separate cover is a revision of the Intrusion Detection Handbook, SAND 76-0554, which may have been sent to you in 51ay 1977. This handbook revision was prepared by the Facilities Protection Department, Sandia Laboratories, Albuquerque, New Mexico under contract with the Division of Safeguards and Security, Department of Energy (DOE) and is made available for your information as a reference source for use .in the design, installation, and operation of intrusion detection systems. The attached revision supersedes the previous version.

In addition, we are also including two other reports in the same series:

"Nuclear Safeguards Technology Handbook" dated December 1977, which outlines current safeguards technology development programs, and "Entry Control System Handbook" dated September 1977, which describes systems used to

'ontrol access to and egress from controlled areas.

These documents are marked "Official Use Only." In releasing them to you, we request that distribution of the documents be controlled so that sub-sequent revisions may be sent to all recipients. Feedback from recipients of these handbooks should be addressed to Dr. Samuel C. T. McDowell, Assistant Director for Research and Development, Office of Safeguards and Security, Department of Energy, Washington, D.C. 20545.

Sincerely, D. B. Vassallo, Assistant Director for Light Water Reactors Division of Project Management

Enclosures:

(3)

Under separate cove~

cc w/o enclosures:

See next page

Niagara fdohawk Power Corporation V'

(

ccs:

Arvin E. Upton, Esq.

LeBoeuf, Lamb, Leiby 5 MacRae

,,1757 N Street, N. M.

Mashi'ngton, O. C. 20036 Anthony Z. Roisman, Esq.

Natural Resources Defense Council 917 15th Street, N. M.

Mashington, O. C. 20005 ter. Richard Goldsmith Syracuse Universi ty College of Law E. I. Mhite Hall Campus Syracuse, New York 13210

. T. K. DeBoer, Director Technological Development Programs New York State Energy Office Swan Street Building Core 1 - 2nd Floor Empire State Plaza Albany, New York 12223

Qj ~

( ~ I I lp IIVI; I'i~I<

L~ccl I Pl~~~

TIC IIP.R lleldin;I I >/P BI I i ir E. l a-e I! ~ I'o;".I I<. I)eYn~ii).>

I). >/a s ~..i I I ~

Stol z V,. Voipl

0. I)a I'r S. V(1vq<1 I.. n~I:ri 4 I.cl! i'. l C>

I). s, I. IlilI ic~'-,

I? . t la I.l.'ski>>

II . I)< >) I p~~

I). I'pl I er Pro jpr I Rttnir>>y, l.l I>

HY I t'OI1 IL ("3 )

RC~S (IC)

L ..1)rnllr.;r Iff1C I'ai <i~ i >>~l",:

S. Bulipoc I,p; i

/ 7

~pR Rf 0y 0 UNITED STATES

.-r W~

NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 205SS APR 1 8 1978

++*++

Docket Nos: 50-358 50-387 50-352/353 50-367 50-373/374 50-388 AO-410 II 50-322'PPLICANTS:

Members of Mark Owner's Group

SUBJECT:

MEETING WITH MARK II OWNER'S GROUP AND GENERAL ELECTRIC COMPANY TO DISCUSS THE MARK II CONTAINHENT POOL DYNAMICS LOAD PROGRAM - APRIL 6, 1978 - SAN JOSE

~kd:

The staff's Hark II Containment Task Group (Task Action Plan No. A-8) met in Livermore, California and San Jose, California on April'th and April 6th respectively to discuss the Livermore Fluid Structure Interaction Program and Submerged Structure Drag Loads Program and the Owner's Group Monticello SRV, Fluid Structure Interaction Studies, the staff's Pool Temperature Limits review, the 4T Fluid Structures Interaction Studies and other matter's related to Hark II Containment Pool-'ynamics.

These meetings will be reported later when information becomes available from the Task Group. The DPM Hark II coordinator attended the San Jose meeting only.

~Summar:

4 General Electric made a presentation'n the effort underway to show that 4T impulse loads at the wall result in responses that will be bounded by the preveously defined bounding loads. GE will informally write up what it is doing in this effort and provide the information to the staff. Another meeting will be held in Bethesda in about three weeks to present the results.

GE made a presentation on the FSI - SRV work using the Montecello bench work study to show that flexibility in the pool wall does not introduce lack of conservatism in comparison with the Livermore work.

The staff reported its preliminary conclusio8 that data are not adequate to support the pool temperature limit of 150 F for the ramshead. A position paper on this matter is being reviewed by management within the NRC.

APR 18 1978 The discussion on impact loads was deferred until the end of April at which time GE will address this problem.

All Nark II owners who originally planned to use the ramshead device have not made the decision to switch to quencher devices. The Cincinnati Gas and Electric Company (Zimmer) has decided to switch.

It intends to continue plant analyses and modification on the basis of its own definition of 'ramshead bounding loads in anticipation that the quencher will provide additional margin. The staff cautioned CG8E that the DFFR loads are not necessarily acceptable to the staff and that the burden is on the applicant to'establish that quencher loads are less than whatever bounding loads are'sed by the applic'ant.

At this time the Hark II owners plan to address SRV second actuation problems on an individual plant basis.

I. Peltier, Project Manager Light Water Reactors Branch No. 1

, Division of Project Management cc: See Following Pages

0 APR 18 1978-Niagra Mohawk Power Corporation ATTN: Mr. Jerald K. Rhode Vice President Engineering 300 Erie Boulavard West Syracuse New York 13202 Eugene B. Thomas, Jr.

LeBoeuf, Lamb, Leiby & MacRae 1757 N Street, N. W.

Washington, D. C. 20036 Anthony Z. Roisman, Esq.

Roisman, Kessler & Cashdan 1025 15th Street, N. W.

Washington, D. C. 20036 Mr. Richard Goldsmith Syra'cuse University College of Law E. I. White Hall Campus Syracuse, Nevi York 13210 T. K. DeBoer, Director Technological Development Programs New York State Energy Office Swan Street Building Core 1 2nd Floor Etapire State Plaza, Albany, New York 12223

1 Washington Public Power Supply System PAP.R 78 1978 ATTN: Mr. Kneil 0. Strand Managing Director 3000 George Washington Way Richland Washington 99352 Joseph B. Knotts, Jr., Esq.

Debevoise 5 Liberman 700 Shoreham Building 806 Fifteenth Street, N. W.

Washington, D. C. 20005 Richard g. guigley, Esq.

Washington Public Power Supply System P. 0. Box 968 Richland, Washington 99352

0 Pennsylvania Power and Light Company APR >8 1978 ATTN: Mr. Norman W. Curtis Vice President,- Engineering and Construction 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Earle M, Mead Project Manager Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Gerald Charnoff, Esq.

Shaw, Pi.ttman, Potts, Trowbridge

& Madden 1800 M Street, N, D. C. W.'ashington, 20036 Mr. William E. Barberich Licensing Engineer Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Robert J. Shovlin, Project Manager Susquehanna Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hubert Barnes, Esq.

Pennsylvania Power & Light Company 901 Hamilton Street Allentown, Pennsylvania 18101 Edward M. Nagel, Esquire Genera'I Counsel and Secretary Pennsylvania Pov(er '& Light Company' North Ninth Street Allentown, Pennsylvania 18101

Commonwealth Edison Company APR 18 1978 ATTN: Nr. Byron Lee, Jr.

Vice President P. 0. Box 767 Chicago, Illinois 60690 Richard E. Powell, Esq.

Isham, Lincoln & Beale One First National Plaza 2400 Chicago, Illinois 60670

APR 78 1978 Northern Indiana Pub i c Service Company 1

ATTN: Mr. H. P. Lyle, Vice President Electric Production 8 Engineering 5265 Holman Ave.

Hammond, Indiana 46325 Meredith Hemphill, Jr. Esq.

Assistant General Counsel Bethlehem Steel Corporation Martin Tower Bethlehem, Pennsylvania 18016 William H. Eichhorn, Esq.

Eichhorn, Morrow 8 Eichhorn 5243 Hohman Avenue Hammond, Indiana 46320 Edward W. Osann, Jr., Esq.

Wolfe, Hubbard, Leydid, Voit 8 Osann, Ltd.

Suite 4600 One IBM Plaza Chicago, Illinois 60611 Marvin N. Berm, Esq.

Special Assistant Attorney General 134 North LaSalle Street Suite 2222 Chicago, Illinois 60602 Robert J. Vol)en, Esq.

109 North Dearborn Street Chicago, Illinois 60602

~ e The Cincinnati Gas 5 Electric Company David B. Fankhauser, PhD ATTN: Mr. Earl A. Borgmann 3569 Nine Mile Road Vice President - Engineering Cincinnati, Ohio 45230 P. 0. Box 960 Cincinnati, Ohio 45201 Thomas A. Luebbers, Esq.

Cincinnati City Solicitor Mr. William J. Moran Room 214 - City Hall General Counsel Cincinnati, Ohio 45202 The Cincinnati Gas 8 Electric Co.

P. 0. Box 960 Troy B. Conner, Esq.

Cincinnati, Ohio 45201 Conner, Moore 8 Cober 1747 Pennsylvania Ave. N. W.

Hr. William G. Porter, 'Jr. Washington, D. C. 20006 Porter, Stanley, Arthur, 8 Platt 37 West Broad Street Columbus, Ohio 43215 Mr. Robert Killen, Chairman of the Board 8 Chief Executive Officer The Dayton Power 5 Light Company P. 0. Box 1034 Dayton, Ohio 45401 Mr. J. Robert Newlin, Counsel The Dayton Power 8 Light Company P. 0. Box 1034 Dayton, Ohio 45401 Mr. Stephen Schumacher Hiani Valley Power'roject P. 0, Box 252 Dayton, Ohio 45401 Hs. Augusta Price 601 Stanley Avenue Cincinnati, Ohio 45226 Mr. James D. Flynn Manager, Licensing 8 Environmental. Affaiis The Cincinnati Gas 8 Electri.c Company P. 0. Box 960 Cincinnati, Ohio 45201 Hr. J. P. Fenstermaker Senior Vice President - Operations Columbus & Southern Ohio Electric Co.

215 North Fr .it Street Columbus, Ohio 43215

'I ~

) 'V APR 18 ]97)

Philadelphi Electric Company Eugene J. Bradley ATTN: Mr. Edward G. Bauer, Jr. Philadelphia Electric Company Vice President and General Associate General Counsel Counsel 2301 Market Street 2301 Market Street Philad'elphia, Pennsylvania 19101 Philadelphia, Pensylvania .19101 Troy B. Conner, Jr. Ewq.

Conner, Moore 5 Corber 1747 Pennsylvania Avenue, N. W; Washington, D. C. 20006 W. William Anderson, Esq.

Deputy Attorney General

• Room 512, Main Capitol Building Harrisburg, Pennsylvania 17120 Frank R. Clokey, Esq.

Special Assistant Attorney General Room 218, Towne House Apartments P. 0. Box 2063 Harrisburg, Pensylvania 17105 Honorable Lawrence Coughlin House of Representatives Congress of the United States Washington, D. C. 20515 Roger B. Reynolds, Jr., Esq.

324 Swede Street Norristown, Pennsylvania 19401 Willard C. Hetzel, Esq.

312 main Street East Greenville, Pennsylvania 18041 Lawrence Sager, Esq.

Sager & Sager Associates 45 High Street Pottstown, Pennsylvania 19464 Joseph A. Smyth Assistant County Solicitor County of Montgomery Courthouse Norristown, Pennsylvania 19404

T ~ ~

APR 18 1978 Long Island Lighting Company ATTN: Mr. Andrew W: Wofford Vice President 175 East Old Country Road Hicksville, New York 11801 Edward M. Barrett, Esq.

General Counsel Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Edward J. Walsh. Esq.

General Attorney Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Mr. Thomas Burke Project Manager Shoreham Nuclear Power Station P. 0. Box 618 Wading River, New York 11792 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plazq Albany, New York 12223 Haward L. Blau Blau and Cohn, P. C.

380 North Broadway jericho, New York 11753 Irving Like,,Esq.

Reilly, Like and Schnieder 200 West Main Street Babylon, New York 11702 MUB Technical Associates 366 California Avenue Suite 6 Palo Alto, California 94306

F

+

Cy

~JR RSGIJ(

'fp 0

t UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406

~O April 14, 1978

++*+4'ocket No. 50-410 Niagara Mohawk Power Corporation ATTN: Mr. G. K. Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, NY 13202 Gentlemen:

Enclosed is IE Bulletin No. 78-05 which requires action by you with regard to your power reactor facility(ies) having an operating license or a construction permit.

Should you have questions regarding this Bulletin or the actions required, please contact this office.

Sincerely, Boyce H. Grier Director

Enclosures:

l. IE Bulletin No. 78-05

2. List of IE Bulletins, Issued in 1978 cc w/encls:

Eugene B. Thomas, Jr., Esquire

1 M-h UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 IE Bulletin No. 78-05 Date: April 14, 1978 Page 1 of 2 MALFUNCTIONING OF CIRCUIT BREAKER AUXILIARY CONTACT MECHANISM - GENERAL ELECTRIC MODEL CR105X Description of Circumstances:

The Sacramento Municipal Utility District recently reported a problem encountered with the operation of the GE Model CR105X auxiliary contact mechanism installed in a 480 volt circuit breaker. Investigation into the cause for the inability to shutdown a booster supply fan (SF-A-7) in the control room emergency air conditioning system revealed that an auxiliary contact (GE Model CR105X) had failed in the closed position, preventing the fan's power supply circuit breaker from opening. The specific cause for failure was binding of the plunger arm due to burrs and nicks on its surface.

An investigation was conducted by the licensee to determine the extent of usage of this type auxiliary contact in other circuits throughout the reactor power plant. Approximately fifty (50) positions in the nuclear service motor control centers were identified as having a similar type auxiliary contact mechanism. It was also determined that many of the affected systems which require contact operation similar to that described above, either permit or provide a safety feature function during emer-gency conditions. An example of this type application is auxiliary

, contacts that must open to permit closing of certain safety related valves from 480 volt motor control centers.

The attached GE Service Advice Letter and associated instruction/drawing sheet were sent to all nuclear power reactor facilities by GE Field Service Offices. The letter, together with the instruction/drawing sheet identifies the problem and provides the recommended corrective action.

~ y IE Bulletin No. 78-05 Date: April 14, 1978 Page 2 of 2 Action To Be Taken By Licensees and Permit Holders:

for all power reactor facilities with an operating license or construc-tion permit:

l. If you have received the enclosed General Electric letter and instruction/drawing sheet addressing the auxiliary contact mech-anism problem, and if you have these devices in use at your facility, it is requested that you describe what corrective action you have taken.

2. If you have not received the enclosed GE documents before, it is requested that you describe what action you plan to take if CR105X auxiliary contact mechanism is in use or planned for use in the GE safety systems at your facility(ies).

3. Facilities having an operating license should report in writing, within 45 days, and facilities with construction permits within 60 days, the results of action taken or planned with regard to Items 1 and 2 above. Your written reply should also include the date when such actions were or will be completed. Reports should be sub-mitted to the Director of the appropriate NRC Regional office and a copy should be forwarded to the U. S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, Washington, D. C.

20555.

Approved by GAO, 8180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.

Attachments:

1. GE Letter

2. GE Control and Instruction Sheet

h~

ConttOI IN STRU CTlONS 1QSX AUXfLtARYCONTACT (CHANGt=GUT OF Pt UNGEFt ARM AND lNSULRTlON) for nema size 0 8 5 magnetic starters and contractors CHANGING PLUNGER ARM 4 INSULATION(SKK FtG. 2)

Slide plunger assembty out ot auxiGary contact block. by lifting REMOVING OVERLOAD RELAY BRACKET (SE Fi" 1) up and out.

1, Rcmove all otcctricat power fram device. 2. Select the new plunger arm that is bent the someway as the ene

2. Oisassembte device by pressing an the coil while pulling out ca installed.

the coil retainers. Move retainers back and away from coiL 3. Lcason screw aa plunger ta release metal arm but OO ttOT

3. Grasp movable ~ion of magnet and pull out. remeving RKhlOVK SCREW FROM PHKNOUC PLUtfGER (OR magnet assembly. coil, molded cover and movable arm in ane PLLtNGERS).

motion. (NGTK: On revorsers ar multispoed starters, this 4. Mauat nrw plunger arm on plunger. Fasten arm to plunger with magnet assembly is linked ta the mechanicat interlock arm screw (or plunger pc t if installing double aux. blacks).

between cantactars and should be t I p pod toward iaterlack alm 5. Apply thin coat at aeroshett grease along plunget'uides.

to tacitnate easy removaL)

6. Reinstall plunger assembty in contact black.

4. Remove overload relay bracket by sliding tt out ef the keyed

7. Peassemble overload to mounting bracket. Remove overload sets m the molded base. (NOTE: lf any wires are tao short to ~

insulation and install new. (NOTE; Overload insulation must be aticw easy renwvaL temporarily disconnect these.)

removed and replaced with new insulatiaa supplied with kit)

5. Remove overload relay fram bracket by loosening screw on tL Romaunt complete assembly cn cantactor base.

bottom of overload bracket: I ct. Reconnect any wires previously removed.

10. Reassemble magnet assematy to contact base-(on revorsers or multtspeeds be sure ta interlock this assembly with mechancat

%4 interlock arm. Check for tree movement ef armature assemblies QVEALQAO RBJLY S4CXArrlttO BRACKET -' i and mechanics',interlocks).

rf I~ 11. Observe that auxiliary cancxct ptungcr aamnbties are operating pfcperfyo CCNi. RETAiNCRS 44'>>r r

r I ~

<<Ot>>

Q',.'z] i

' A'

~ '

NOVA8LKSiAGttKT i,.

ASS gtrutLY 7 ttKyED

, SLciT8.,

r 4 r frrr4rI4rr rr 4 4>>rOorr  %>>4t

~ 44 '

rr 'l&

F)GVRE 1 RKMOVtNG OVKRLOAO RELAY MOVrtTt NQ BRACKET TV>lClLDOVILX 4USll.laltJEl4VWLV lgrrr arw7l FIGURE 2 GKNKRAl. ELECTRIC COMPANY GENERAL FrJRPOSK CONTROL GKPARTLlKtfT g KN E R AL We,~<~, E LE tl T R I

It has been brought to our attention that a potential binding problem may exist with the 100 Line CR105X... auxiliary inter locks mounted on HEMA size 00, 0 and 1 contactors, starters, or reversers used in control equipment manufactured by General Electric Co. (including 7700 Line motor control centers) and other control equipment manufacturers. The interlocks involved are used on the following devices.

CR105A, -B., -C, -H, -J, -K, -R, -S with additional suffix letters and numbers (contactors}

CR106A, -B, -C, -H, -0, -K, -R, -S with additional suffix '1et ers

.and numbers (starters)

CP109A, -B, -C. -H, -0, K, -R, -S with additional suffix letters and numbers (t eversing starters)

If any of these devices are currently used in your installations, you should obtain replacement parts to correct this condition by forwarding the following information to my attention:

1. Complete catalog (CR) numbers on device nameplate.

2. guantity of each device catalog number.

3. Are the auxiliary interlocks mounted on the left side, right side, or both sides of the device? How many are there at each location?

Since the General Purpose Control Department of the General Electric Co.

does not know all applications of these interlocks,'t is assumed that some may be in "critical" applications and should be changed out as soon as possible, while those in non-critical applications may be changed out at some routine maintenance period.

Since these interlocks are on devices which have been in service for over one (1) year and are out of our normal warranty period, we feel a fair and equitable solution would require that the necessary parts and instructions for the'uggested changeout be provided by GE at no expense to the user. At your ear liest convenience, please provide me with the information requested in paragraph 2 of this letter so that the necessary parts may be provided.

This information should be forwarded to:

General ElecWic Company P, 0. Box 2913 Bloomington, Illinois 61701 Attention: Hr, John E. Corbitt Product Service (Oial Com: 8~325-4416, or 4294)

Attachment 1 Page 1 of 1

IE Bulletin No. 78-05 April 14, 1978 ENCLOSURE 2 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.

78-01 Flammable Contact I/16/78 All Power Reactor Retainers in G.E. Facilities with an

-'rm CR120A Relays Operating License (OL) or Construc-tion Permit (CP) 78-02 Terminal Block 1/30/78 All Power Reactor qualification Facilities with an Operating License (OL) or Construc-tion Permit (CP) 78-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accumula- Reactor Facilities tions Associated with with an Operating BWR Offgas System License (OL)

Operations 78-04 Environmental guali- 2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit Operating License Switches Inside (OL) or Construc-Reactor Containment tion Permit (CP)

Page 1 of 1

I