ML20213E369
| ML20213E369 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Salem |
| Issue date: | 03/11/1983 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Lainas G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20213E339 | List: |
| References | |
| FOIA-87-152 NUDOCS 8303220494 | |
| Download: ML20213E369 (4) | |
Text
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MW90RANDUM FOR:
Gus C. Lainas Assistant Director for Operating Reactors. DL FROM:
Frank J. Miraglia, Assistant Director for Safety Assessment Ot.
SUBJECT:
CDNGRESSIONAL SUBCom!TTEE REQUEST This is in response to Darrell G. Eisenhut's memorandus of March 10,1983 on subject matter. Enclosed you will find documents relative to the Sales event of February 25.1983' requested in the subject request.
Frank J. Miraglia, Assistant Director for Safety Assessment. DL
Enclosures:
as stated See attached list DISTRIBUTION cc w/o encl:
f4aligatirrSt)er D. Eisenhut ORAB r/f F. Mi ragl ia T. Ippolito G. Holahan JT 8eard D. Pickett D. Wessman
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9 List of Documents Related to Salem Februa ry 25,1983 Event AD/SA Response to March 10, 1983 Request 1.
Memo from F. J. Miraglia to 0. G. Eisenhut dated March 9,1983 - Use of D8-50 Breakers in RPS at Ginna and Haddem Neck.
2.
Copies of slides for Commission Briefing on Salem Event of February 25, 1983. Presented by D. G. Eisenhut on March 2,1983.
3.
Memorandum from William Dircks to Harold Denton dated February 28, 1983 -
Evaluation of the Implications of the Salem Unit 1 Event.
4.
Letter from E. P. Rahe (Manager, Nuclear Safety Department, Westinghouse) to Harold Denton dated March 1,1983.
5.
Letter from J. J. Shephar6 (Chairman, Westinghouse Owners Group) to Harold Denton dated March 1,1983 - Salem RT Breaker Incident.
6.
Letter from Richard Uderitz (Vice President Public Service Electric and Gas Company) to Darrell Eisenhut dated March 1,1983 - Reactor Trip Breaker Failure No.1 Unit Salem Generating Station Docket No. 50-272.
7.
Letter from Richard Uderitz (Vice President, Public Service Electric and Gas Company) to Richard Starostecki (NRC Region I) dated March 8,1983 -
Supplements his letter to Eisenhut on March 1,1983.
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8.
U. S. NRC IE Bulletin No. 83-01 dated February 25, 1983 - Failure of Reactor Trip Breakers (Westinghouse 08-50) To Open on Automatic Trip signal.
9.
Westinghouse publication I. B. 33-850-3D, effective May 1970 - Instructions for Types 08-50, 08F-16 and 08L-50 Air Circuit Breakers.
- 10. Preliminary Notification PNO-I-83-ll dated February 25, 1983 - Reactor Trip l
Breakers Failed to Open on Trip Signal (ATWS).
i l
- 11. Preliminary Notification PNO-I-83-ll A dated February 25,190 - Reactor Trip Breakers Failed to Open on Trip Signal (ATWS).
12.
U.S.N.R.C. Region I Daily Report dated February 24i 1983.
13.
U.S.N.R.C. Region I Daily Report dated February 23,,1983.
- 14. Copy of NRC Duty Officer Log dated February 25, 1983 - Indicates initial l
notification of NRC of Salem event.
15.
U.S.N.R.C.
Regional Daily Report dated February 28, 1983 - Region II and III reported plants that are affected by I.E.Bulletin 83-01.
l
i 16.
Plant status summary of Salem Units 1 and 2 from January 3,1983 to February 25, 1983.
17.
Copies of slides presented by licensee (Public Service Electric and Gas Company) during February 28, 1983 meeting with NRC staff.
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- 18. Note from J.T. Beard to Gary Holahan/ Thomas Ippolito dated March 1,1983 -
Breaker Failures.at Robinson.
- 19. Note from J.T. Beard to Gary Holahan/ Thomas Ippolito dated March 1,1983 -
i' LER Search / Review.
i 20.
Letter from Hal B. Tucker (Vice-President Nuclear Production, Duke Power
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Company) to Harold Denton dated February 28, 1983.
21.
Itemized list of Westinghouse domestic plants using DS Breakers.
22.
Unconfimed Ifst of Westinghouse domestic plants using 08 Breakers.
i
- 23. Salem Unit I licensee's description of February 22,1983 event including l
plant computer printout.
24.
Itemized list of Westinghouse domestic plants and Reactor Trip Breakers i
being used.
- 25. Salem Unit 1 plant computer printout during event of February 25, 1983.
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l 26.
Draft copy of Salem Restart Action Plan dated March 8,1983 prepared b NRC Region I (signature by William Dircks to be sent to Commissioners)y I
27..
Inventory of control room instrument recorder strip charts for February 25 j
1983 Salem Unit 1 event. Obtained during plant visit.
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28.
Control room instrument recorder strip charts for February 22, 1983 Salem Unit 1 event. Obtained during plant visit, j
- 29. Salem electrical drawing #240148 8 9654-0.
- 30. Salem plant procedure IPD-18.1.004 Solid State Protection System Reactor Trip Breaker and Pemissive P-4 Test - Train A.
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31. Salem plant procedure IPD-18.1.008 Solid State Protection System l
Functional Test - Train A.
- 32. Salem Emergency Procedure EPI-l Notification of Unu'sual Event /Significant l
Event.
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- 33. Salem Unit 1 Alarm Procedures.
34.
Certificate of Conformance accompanying UV trip attachment 23A9019G61.
- 35. Copy of Work Order No. 925774 for Reactor Trip Breakers.
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- 36. Salem plant procedure IPD-18.1.009 Solid State Protection System Functional Test - Train B.
- 37. Salem plant procedure IPD-18.1.005 Solid State Protection Sys' tem Reactor Trip Breaker and Permissive P-4 Test - Train B.
- 38. Westinghouse publication NCD-ELEC-18 dated December 17, 1971 - Replacement of Undervoltage Attachments on Breakers in Reactor Trip Switchgear.
- 39. Salem Emergency Instruction I-4.3 Reactor Trip.
- 40. Task Interface Agreement No. 83-20, dated March 3,1983 - indicates certain NRC responsibilities regarding evaluation of Salem I restart.
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UNITED STATES NUCLEAR REGULATORY COMMISSION 7.
WA$HINGTON, D. C. 20665
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MAR 141983 Docket No. 50-272 LICENSEE:
Public Service Electric and Gas Company FACILITY:
Salem Nuclear Generating Station, Unit 1
SUBJECT:
MEETING
SUMMARY
- SALEM UNIT 1 - FAILURE OF REACTOR TRIP BREAKERS A meeting was held with the staff and with representatives of Public Service Electric and Gas on February 28, 1983, to discuss the failure of both of the trip breakers to open following receipt of a trip signal from the automatic protection system. Two such events occurred at Unit 1, the first on February 22, 1983 and the second on February 25, 1983. For both events, the reactor was successfully tripped by manual action.
The licensee attributed the failures of the breakers to improper maintenance of undervoltage relays which translate the signal from the protection system to a mechanical action that opens the breakers.- The computer printout of the event sequence for both transients was discussed and the actions taken by the operators were described. Copies of the handouts which the licensee used for his presentation are enclosed as are copies of tha event sequence.
The itcensee described his short and long term corrective actions. The staff was in general agreement with the actions listed, however, the staff added that the list would probably grow following our evaluation of the two events.
Westinghouse, the manufacturer and supplier of the breakers described their reconmended lubrication procedures that should have been followed by the licensee, however,' were not. A representative of the Westinghouse Regulatory Response Group discussed their intended follow up involvement.
The staff stated that they will provide the licensee a list of actions as soon as the review and evaluation are completed. The licensee is expected to provide responses to each of the actions which satisfy our safety requirements prior to restart of Unit 1.
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Donald Fischer, roject Manager l
Operating Reactors Branch No.1 Division of Licensing
Enclosures:
As stated cc w/ enclosures:
1 See next page f
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t Mr. R. A. Uderitz Public Service Electric and Gas Company cc: Mark J. Wetterhahn, Esquire Mr. Edwin A. Liden, Manager -
Conner and Wetterhahn Nuclear Licensing Suite 1050 Public Service Electric and 1747 Pennsylvania Avenue, NW Gas Company Washington, D. C.
20006 Post Office Box 236 Hancocks Bridge, New Jersey 08038 Richard Fryling, Jr., Esquire Assistant General Solicitor Ronald C. Haynes Public Service Electric and Gas Company Regional Administrator - Region I Mail Code T5E - P.O. Box 570 U. S. Nuclear Regulatory Commission Newark, New Jersey 07101 631 Park Avenue King of Prussia, Pennsylvania 19406 Gene Fisher, Bureau of Chief Bureau of Radiation Protection Mr. Charles P. Johnson 380 Scotch Road Assistant to Vice President - Nuclear Trenton, New Jersey 08628 Public Service Electric and Gas Company P.O. Box 570 Mr. R. L. Mitti, General Manager 80 Park Plaza - 15A Nuclear Assurance and Regulation Newark, New Jersey 07101 Public Service Electric and Gas Company Mail Code T160 - P.O. Box 570 Mr. R. A. Uderitz, Vice President -
Newark, New Jersey 07101 Nuclear Pubite Service Electric and Gas Company Post Office Box 236 Mr. Henry J. Midura, Manager Salem Operations Hancocks Bridge, NJ 08038 Public Service Electric and Gas Company P. O. Box E Hancocks Bridge, New Jersey 08038 Leif J. Norrholm, Resident Inspector Salem Nuclear Generating Station U. S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038
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6 SALEM MEETING FEBRUARY 28, 1983 ATTENDANCE LIST ATTENDEES AFFILIATION H. R. Denton NRC/NRR D. C. Fischer NRR/DL J. H. Sniezek Deputy Director, IE Ed Jordan IE Division Director G. C. Lainas NRR/DL D. G. Eisenhut NRR/DL T. A. Ippolito NRR/DL R. W. Starostecki NRR Region I, Director, DPRP J. T. Beard NRC/DL S. Varga NRC/DL F. Miraglia NRC/DL G. M. Holahan NRC/DL T. M. Novak NRC/DL R. C. Tang NRC/ACRS T. C. Houghton KMC Inc.
W. D. Lanning NRC/AE00 1
F. H. Rowsome NRC/NRR/ DST F. T. Murphy W Bethesda A. Thadani RRC/NRR E. Rossi NRC/NRR W. Hodges NRC/NRR W. Minners NRC/NRR J. Milhoan NRC/0CM Dale Thatcher NRC/NRR/SPEB Rick Kendall NRC/DSI/ICSB C. Graves NRR/DSI/RSB B. W. Sheron NRR/DSI/RSB R. Mattson NRR C. Brinkman CE B. Newlin NRC/PA J. S. Guermann NRC/0CA Roger Huston CPCo R. B. Borsum B&W W. G. Kennedy NRC/DHFS Dave Pratt NRC/RES P. W. Baranowsky NRC/RES Bill Mills NRC/IE Nat Villalva NRC/IE W. F. Kane DEDROGR Staff D. A. Smith NRC/RES C. Trammell NRC J. Thomas NRC/IE
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. ATTENDEES AFFILIATION Bill Travers NRC/0EDO R. A. Purple NRC/DL R. H. Vollmer NRC/DE T. G. Dunning NRC/ICSB E. A. Liden PSESG J. J. Wroblewski PSE&G N. M. Pavincich PSE&G J. G. Beattie PSE&G J. Bailey PSE&G Victor W. Lowenstein, Jr.PSE&G R. H. MacWatters PSE&G A. Orticelle PSE&G J. E. Gallagher PSE&G J. D. Rriscoll PSE&G H. J. Midura PSE&G R. A. Uderitz PSE&G R. M. Eckort PSE&G J. M. Zupko, Jr.
PSE&G J. T. Boettger PSE&G Armand Nassman PSE&G L. A. Reiter PSE&G J. A. Ketcham PSE&G D. J. Jogt PSE&G E. Goodwin NRC/NRR V. S. Noonan NRC/NRR John Pendlebury General Electric Clarence Draughs W Nuclear Safety Pres Rahe 7 Nuclear Safety Jim Little 7 Nuclear Safety Joseph R. Bergan 7 Engr. Div.
William H. Furfari F Nuc. Serv. Div.
Phil Marasco 7 Nuclear Safety Dave' Sharp 7 Nuclear Safety Anthony Tomed 7 Swtichgear Div.
Donald Milchak 7 Switchgear Div.
Joe Sheppard Carolina Power & Light / Westinghouse Owners' Gp.
Faust Rosa NRC/DSI/ICSB G. Bagchi NRC/DE/EQB
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PUBLIC SERVICE ELECTRIC AND GAS CO.
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REACTOR TRIP BREAKER PROBLEMS 4
SALEM NO. 1 AND 2 UNITS INTRODUCTION (RAU)
HISTORY OF SALEM NO. 1 AND 2 UNIT OPERATION DECEMBER 1982 THROUGH PEBRUARY 25, 1983 (HJM)
DESCRIPTION OF EVENTS OF PEBRUARY 22 AND FEBRUARY 25,1983 (JDD)
EXPLANATION OF SOLID STATE PROTECTION SYSTEM (AO)
EXPLANATION OF DB-50 CIRCUIT BREAKER OPERATION (W)
HISTORY OF REACTOR TRIP BREAKER PROBLEMS AT SALEM (JG)
CORRECTIVE ACTION (JG, AO)
CONCLUSION (RAU) l J
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CORRECTIVE ACTIONS 1.
PSE8G VERIFIED SALEM SURVEILLANCE TESTING MEETS TECH f.?EC REQUIREMENTS.
i 2.
NAINTENANCE PROCEDURES FOR THE UV TRIP DEVICES WILL BE DEVEl.0 PED BASED ON NSD 74-02 AND 'lCD-ELEC-18, 3.
!!WILLINSTALLNEWUNIT1UVATTACHMENTS.
4 PROPER OPERATION OF,THE BREAKERS WILL BE VERIFIED BY PSEAGAND!!-PROGRAMBEINGDEVELOPED.
5.
)!WILLVERIFYTHATTHEUVATTACHMENTSMEETSAFETY CLASSIFICATION SPECIFICATIONS FOR THE ORIGINAL RX SWITCHGEAR.
6 SURVEILLANCE OF BREAKER OPERATION WILL BE INCREASED TO MONTHLY INTERVAL,
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7.
PROCEDURES WILL BE REVISED TO REQUIRE THE OPERATOR TO ACTUATE THE REACTOR MANUAL TRIP SWITCH FOLLOWING AN AUTOMATIC REACTOR TRIP.
8.'DEVELOPAFORMALIZEDPOSTTRIPsEVIEWPROCEDURE.
9.
)[ WILL SEND COMPILATION OF ALL TECH BULLETINS, MANUALS PERTAINING TO !! EQUIPMENT AT SALEM SALEM WILL REVIEW AND INCORPORATE AS NECESSARY INTO STATION DOCUMENTS, e
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s 10, lf IS CONDUCTING AN INTERNAL REVIEW 0F THEIR PROCEDURES FOR DISSENINATION OF TECHNICAL INFORMATION TO UTILITIES, PSEAG RAS IDENTIFIED THE DESIRED DISTRIBUTION OF THIS INFORMATION AS PART OF RECENT IMPROVEMENT IN THEIR HANDLING OF TECHNICAL DOCUMENTS..
II, A REVIEW IS IN PROGRESS AT SALEN OF PAST EQUIPMENT FAILURES DOCUMENTED IN LER's, GR, A PREVENTIVE MAINTENANCE PROGRAM WILL BE IMPLEMENTED BASED UPON RESULTS OF REVIEW, e
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s SALEM REACTOR TRIP BREAKER FAILURES 1.
AUGUST 20, 1982, UNIT #2 "B" TRIP BREAKER FAILED TO'OPEN ON. SOLID STATE PROTECTION SYSTEM SIGNAL DURING SURVEILLANCE TESTING.
2.
JANUARY 6, 1983, UNIT #2 "A" TRIP BREAKER FAILED TO OPEN ON SOLID STATE PROTECTION SYSTEM SIGNAL DURING A UNIT TRIP.
3.
FEBRUARY 22s.1983, UNIT #1 "B" TRIP BREAKER FAILED TO CLOSE DURING UNIT START-UP.
4.
FEBRUARY 22 AND 25, 1983, UNIT #1 "A" AND "B" TRIP BREAKERS FAILED TO OPEN ON A UNIT TRIP, 4
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i SALEM REACTOR TRIP BREAKER FAILURE AUGUST 20, 1982 - UNIT #2 1." THE B REACTOR TRIP BREAKER WOULD NOT OPEN ON A SIGNAL THE SOLID STATE PROTECTION SYSTEM DURING ltC SURVE!LLANCE TESTING (WORK ORDER #90110).
2.
BREAKER WAS CAPABLE OF BEING TRIPPED MANUAL FROM CONTROL ROOM.
3.
PROBLEM WAS FOUND TO BE BINDING OF THE UNDERVOLTAGE TRIP ATTACHMENT LATCH MECHANISM.
4.
CHANGED C0!L AND CLEANED TRIP C0!L LATCH MECHANISM.
BREAKER l
TESTEDSATISFACTORILY.
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SALEM REACTOR TRIP BREAKER FAILURE JANUARY,6, 1983 - UNIT #2
- 1. " REACTOR TRIP BREAKER A FAILED TO TRIP DN SOLID STATE PR SYSTEM SIGNAL.
2.
REPLACED REACTOR TRIP BREAKER FROM UNIT #2 WITH BREAKER FROM.
UNIT #1 BREAKER TESTED SATISFACTORY.
3.
THE FOLLOWING REMEDIAL ACTION WAS TAKEN:
A.
WORK ORDERS WERE WRITTEN FOR UNIT #1 AND #2 REACTOR TRIP '
BREAKERS TO PERFORM INSPECTION, CLEANING AND TESTING OF THE BREAKERS.
B.
PURCHASE ORDERS WERE WRITTEN TO WESTINGHOUSE TO PROVIDE A SERVICE ENGINEER FROM DB-50 BREAKER INSPECTION AND MAINTENANCE ON #1 AND #2 UNIT.
4.
BETWEEN JANUARY 13 AND 18, 1983, A SERVICE REPRESENTATIVE 0F WESTINGHOUSE WAS ON SITE TO PROVIDE TECHNICAL ASSISTANCE IN THE OVERHAUL AND INSPECTION OF THE REACTOR TRIP BREAKERS.
5.
THE FIRST BREAKER TO BE ADDRESSED WAS THE BREAKER. THAT WAS REMOVED FROM UNIT #2.
THE PROBLEM FOUND WAS A BINDING OF-THE UNDERVOLTAGE TRIP ATTACHMENT.,
6.
WESTINGHOUSE RECOMMENDED THAT CLEANING AND' LUBRICATION OF THE MECHANISM WITH CRC-2-26 SHOULD CORRECT THE PROBLEM.
THIS WAS SATISFACTORILY ACCOMPLISHED.
7.
WESTINGHOUSE ASSISTED lis DIRECTLY ON THE UNIT #1A AND B REAC TRIP BREAKER OVERHAULS AND THE MOTOR GENERATOR A AND B BREAKERS..
THE A AND B BYPASS BREAKERS WERE COMPLETED BY STATION PERSONNEL.-
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8.
WESTINGHOUSE STATED THAT OVERALL THE BREAKERS WERE Ifl GOOD CONDITION COMPARED TO SOME BREAKERS HE HAD WORKED ON AT OTHER LOCATIONS, 9.
WESTINGHOUSE REJECTED A SUGGESTION BY THE MAINTENANCE SUPERVISOR TO USE ANDER0L LUBRICANT ON THE UNDERVOLTAGE ATTACHMENT AND OTHER MOVING PARTS TO ELIMINATE A POSSIBLE FRICTION PROBLEM.
THE SERVICE ENGINEER STATED THAT THE GREASE WOULD ACT IN SUCH A MANNER AS TO COLLECT DUST AND DIRT, WHICH WOULD PROBABLY LEAD TO A FA! LURE.
ANDER0L WAS NOT USED AND THE DEVICES WERE LUBRICATED WITH CRC-2-26.
10.
AT THE CONCLUSION OF THE INSPECTION AND LUBRICATION, ALL BREAKERS WERE TESTED SATISFACTORILY.
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SALEM REACTOR TRIP BREAKER FAILURE FEBRUARY 22, 1983 - UNI.T #1 1.
DURING PLANT START-UP ON FEBRUARY 22, 1983, "B" REA TOR TRIP -
BREAKER FAILED TO CLOSE PROPERLY.DUE TO THE BREAKER MECHANISM DUST' COVER COMING LOOSE AND JAMMING THE BREAKER, 2.
THE BREAKER WAS INSPECTED AND WAS FOUND TO BE UNDAMAGED.
'3.
THE DUST COVER WAS REMOVED, 14.
THE BREAKER WAS TESTED SATISFACTORILY AND RETURNED TO SERVICE, 5.
ALL DUST COVERS HAVE BEEN REMOVED FROM NO,1 UNIT BREAKERS.
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SALEM REACTOR TRIP BREAKER FAILURE FEBRUARY 22 AND 25, 1983 - UNIT #1 4
1.
DURING PLANT START-UP ON FEBRUARY 22 AND 25, 1983, BOTH "A" AND "B" REACTOR TRIP BREAKERS FAILED TO TRIP WHEN A SOLID STATE PROTECTION SYSTEM SIGNAL WAS RECEIVED, 2,
WESTINGHOUSE AND PSE&G MAINTENANCE AND ENGINEERING PERSONNEL HAVE INSPECTED AND TESTED THE UNDERVOLTAGE TRIP ATTACHMENTS.
3.
THE PROBLEM IS BINDING OF THE UNDERVOLTAGE TRIP ATTACHMENT, CAUSED BY A LACK 0F LUBRICATION TO THE TRIP LATCH, 4.
AREVISEDMAINTENdNCEAPPROACHHASBEENDEVELOPED,ASFOLLOWS:
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ORIGINhl SALEM MAINTENANCE APPROACH TO R (WESTINGHOUSE DB-50) 1.
LIGHT DUTY BREAKER WITH NO THERMAL OR MAGNETIC OVER 0 2.
NO LUBRICATION REQUIRED BY WESTINGHOUSE TECHNICAL MANUAL (I.B. 33-850-3D, PG. 5).
3.
BREAKERS WERE TRIP TESTED'USING THE UNDERVOLTAGE COIL E SIXTY (60) DAYS AS PART OF ISC DEPARTMENT SURVEILLANCE
- TESTING, 4.
NO KNOWN PROBLEMS EXISTED WITH THE BREAKERS, O
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SALEM REACTOR TRIP BREAKER FAILURES SHORT-TERM MAINTENANCE APPROACH 1.' MAINTENANCE PROCEDURES FOR 'HE UNDERVOLTAGE TRIP ATTACHM T
WILLBEDEVELOPEDBASEDONNSD74-02ANDNCD-ELEC-18.
2.
WESTINGHOUSE WILL PROVIDE FOUR NEW UNDERVOLTAGE TRIP ATTACH-MENTS FOR NO. 1 UNIT.
3.
PROPER OPERATION OF THE BREAKERS WILL THEN BE VERIFIED BY PSE8G AND WESTINGHOUSE, 4.
THE IaC DEPARTMENT WILL TEST THE REACTOR TRIP BREAKERS AFTER MAINTENANCE IS PERFORMED.
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CORE SPRiwG Lgygn Fig.17. Undervoltage Trip Attachment Construction Details of the armature, to trip the breaker. The above. Check for loose bolts and open cir-armature should move without friction, and cuit in potential coil.
should have approximately 1/32-inch over-travel after tripping.
FIELD DISCHARGE SWITCH Final inspection should be made eleo-The DBF-16 breaker is a two-pole DB-50 trically, after the circuit connections are breaker having special are chutes and modi-complete as shown in Fig. 2. Page 10.
fled arcing contacts plus a field discharge switch mounted on the center pole (Fig.20).
The field discharge switch is shipped Remove all power from the breaker and with the gap setting shown in Fig. 20. for repeat the mechanical inspection given generator field protection. However, the
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MEETING
SUMMARY
DISTRIBUTION OPERATING REACTORS BRANCH NO. 1 Docket / Central File NRC POR L PDR NSIC OR8#1 Rdg J.. Neltemes, AE00 B.. Grimes (Emergency Preparedness)
- 5. Varga Project Manager DELD E. L. Jordan DEQA:IE J. M. Taylor, DRP:IE ACRS-10 NRC Participants cc: Licensee w/short cc list D. Eisenhut R.'Mattson R. Vollmer T..Speis H. Thompson foIR -f ? "'S) o//>
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