Event Tracking & Followup Assignment Sheet of 951106 Event Re Region Draft Info Notice Discussing Series of Difficulties at Plant W/Square D Series 8501 KPD-13 Relays Installed in RS11 SocketsML20134B742 |
Person / Time |
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Site: |
Saint Lucie |
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Issue date: |
03/08/1996 |
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From: |
Hodge V NRC |
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To: |
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Shared Package |
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ML20134B255 |
List: |
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References |
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FOIA-96-485 NUDOCS 9605300137 |
Download: ML20134B742 (4) |
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Category:ARCHIVE RECORDS
MONTHYEARML17229A7861998-06-16016 June 1998 Rev 2 to Cable Derating in Conduits W/Fire Barrier Coatings. ML17309A9491998-06-0202 June 1998 Rev 0 to Electrical Cable Ampacity Correction Factors for Thermo-Lag Fire Barriers. ML17309A8961997-06-11011 June 1997 Non-proprietary Rev 0 to ST-257, Structural Evaluation of St Lucie SG Package. IR 05000335/19960041997-05-23023 May 1997 Partially Withheld Draft Ltr Forwarding Draft Insp Repts 50-335/96-04 & 50-389/96-04 on 960218-0330 & Draft Notice of Violation ML20148E8881997-05-21021 May 1997 Monthly Performance Monitoring Audit QSL-PM-96-08, May/June 1996. Encl Partially Deleted ML20141J0861997-05-19019 May 1997 Undated Partially Deleted Package Re Allegation Mgt Sys for Plant.Functional Areas,Including Operations,Safeguards, Offsite Health & Safety & Onsite Health & Safety Discussed ML20137M4951997-04-0101 April 1997 Undated,QSL-MR-96-14, Maint Rule Compliance ML17229A8641997-02-14014 February 1997 Rev 0 to MECH-0088, Transient Temp of SFP Following Full Core Offload. ML20133E3251997-01-10010 January 1997 Press Release II-97-06, NRC Staff Proposes $100,000 Fines Against FPL at Slp ML20133D9801997-01-0707 January 1997 Calculation of Psl LOSP Initiator Event Frequency & Confidence Limits ML17229A1771996-12-18018 December 1996 Rev 1 to Cable Derating in Conduits W/Fire Barrier Coatings. ML20137K7711996-11-30030 November 1996 Monthly Performance Monitoring Audit for Oct/Nov 1996 ML20134M2121996-11-22022 November 1996 Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants ML20134D7471996-10-30030 October 1996 Press Release II-96-89, NRC Schedules Special Insp Exit Meeting at St Lucie Plant,Nrc Also Schedules St Lucie Corrective Action Meeting in Atlanta ML20137L0031996-09-0909 September 1996 Monthly Performance Monitoring Audit for July to Aug 1996 ML17229A0941996-08-30030 August 1996 Rev a to SAIC 05-5049-05-6734-500, Steam Generator Degradation Specific Mgt Leakage Limit Calculation for St Lucie Unit 1. ML20137M2241996-07-0808 July 1996 QSL-PM-96-08, Monthly Performance Monitoring Audit, May/June 1996 ML20137M5321996-04-19019 April 1996 QSL-SEC-96-03, Functional Area Audit of Security & Safeguards Info Control ML17229A1781996-04-10010 April 1996 Rev 0 to Fire Barrier Ampacity Correction Factors Extrapolation of Test Results for 3 Hour Barrier. ML20137M1771996-04-0202 April 1996 Audit Rept QSL-PM-96-02, Monthly Performance Monitoring Audit, Feb 1996 ML20137K9291996-04-0101 April 1996 Star/Pmai Conversion Process QSL-CA-96-05. W/Related Info ML20134B7421996-03-0808 March 1996 Event Tracking & Followup Assignment Sheet of 951106 Event Re Region Draft Info Notice Discussing Series of Difficulties at Plant W/Square D Series 8501 KPD-13 Relays Installed in RS11 Sockets ML20137M9071996-01-10010 January 1996 Quality Assurance Audit Rept QSL-OPS-95-22, Monthly Performance Monitoring Audit, Nov 1995 ML20141D7991996-01-0101 January 1996 Partially Deleted Package Consisting of Personnel Contaminations for 1995,rev 1 to Health Physics Procedure HPP-70,util inter-office Correspondence & Instrument & Control Info ML20137K9351995-09-15015 September 1995 Nuclear Engineering Audit,QAS-JPN-95-01,for June 1995 ML20134B6291995-09-0606 September 1995 Event Tracking & Assignment Sheets of 950818 Event Re Spray Down of Containment ML20134B6241995-08-0909 August 1995 Event Tracking & Follow Up Assignment Sheet of 950802 Event Re UE Declaration Resulting from Two Stages of Reactor Rc Pump Seal Failures w/2 Gpm Identified Leakage ML20137L0851995-08-0808 August 1995 Pmon Activities QAS-PMON-95-5 for June 1995. Related Info Encl ML20137M8031995-08-0303 August 1995 Quality Assurance Audit Rept QSL-OPS-95-10, Radiation Protection Functional Area Audit ML20137M7111995-07-25025 July 1995 Quality Assurance Audit Rept QAS-ENV-95-1, Radiological Environ Monitoring Program & Site Nonradiological Environ Protection Plans Functional Area Audit, 950525-0714 ML17228B2371995-07-14014 July 1995 Stresses for St Lucie Unit 2,PZR Lefm. ML17228B2351995-07-11011 July 1995 Fm Analysis of St Lucie Pressurizer Instrument Nozzle. ML20137M7631995-03-30030 March 1995 Quality Assurance Audit Rept QSL-OPS-95-04, Odcm,Pcp, Effluents Functional Area Audit ML17228B0481995-02-15015 February 1995 Nonproprietary Version of Stresses for St Lucie Unit 2 Pressurizer Lefm. ML17228B0471995-02-13013 February 1995 Nonproprietary Version of Fracture Mechanics Evaluation of St Lucie Pressurizer Instrument Nozzles. ML20134B5381994-11-10010 November 1994 Event Tracking Sheet Re 941023 Event Concerning Potential Containment Bypass Path Thru Lpsi/Naoh Addition Sys.Caused by Design or Installation Error ML20134B5161994-07-26026 July 1994 Event Tracking & follow-up Assignment Sheet of 940714 Event Re Failure of Trip Circuit Breaker 5 to Open ML20134B5611994-06-17017 June 1994 Event Tracking Sheet Re 930625 Event Involving Refueling Water Tank Corrosion ML20134B5351994-06-17017 June 1994 Event Tracking Sheet Re 930414 Event Involving Relay Failures ML20134B5021994-03-22022 March 1994 Package Consisting of Oeab Event Tracking Sheet Re 930416 Event ML20064K7521993-06-0808 June 1993 Package Consisting of St Lucie & Turkey Point 1992 Preliminary Llnl Hazard Estimates for Peak Acceleration ML20137K9661993-02-26026 February 1993 Rept of QA Audit for 921027-930204. Incomplete QA Audit Rept QSL-PCM-96-11 Encl ML20079N2201991-11-11011 November 1991 Responses to NUMARC Survey in Support of NRC License Renewal Rulemaking ML20132F8891985-09-20020 September 1985 Power Plant Exam Results Summary Sheets.Info Deleted ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20134A5681983-06-13013 June 1983 Press Release Discussing 830610 Amend to Facility License Authorizing Full Power Operation.Viewgraphs of 830627 Briefing Re Nuclear QA & of 830627-0701 Site Visit Encl ML19208A6111979-07-26026 July 1979 Discusses Possibility of Obtaining Extension for Commitments Re Responses to IE Bulletin 79-06A 1998-06-02
[Table view] Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARIR 05000335/19960041997-05-23023 May 1997 Partially Withheld Draft Ltr Forwarding Draft Insp Repts 50-335/96-04 & 50-389/96-04 on 960218-0330 & Draft Notice of Violation ML20141J0861997-05-19019 May 1997 Undated Partially Deleted Package Re Allegation Mgt Sys for Plant.Functional Areas,Including Operations,Safeguards, Offsite Health & Safety & Onsite Health & Safety Discussed ML20134B7421996-03-0808 March 1996 Event Tracking & Followup Assignment Sheet of 951106 Event Re Region Draft Info Notice Discussing Series of Difficulties at Plant W/Square D Series 8501 KPD-13 Relays Installed in RS11 Sockets ML20141D7991996-01-0101 January 1996 Partially Deleted Package Consisting of Personnel Contaminations for 1995,rev 1 to Health Physics Procedure HPP-70,util inter-office Correspondence & Instrument & Control Info ML20134B6291995-09-0606 September 1995 Event Tracking & Assignment Sheets of 950818 Event Re Spray Down of Containment ML20134B6241995-08-0909 August 1995 Event Tracking & Follow Up Assignment Sheet of 950802 Event Re UE Declaration Resulting from Two Stages of Reactor Rc Pump Seal Failures w/2 Gpm Identified Leakage ML20134B5381994-11-10010 November 1994 Event Tracking Sheet Re 941023 Event Concerning Potential Containment Bypass Path Thru Lpsi/Naoh Addition Sys.Caused by Design or Installation Error ML20134B5161994-07-26026 July 1994 Event Tracking & follow-up Assignment Sheet of 940714 Event Re Failure of Trip Circuit Breaker 5 to Open ML20134B5611994-06-17017 June 1994 Event Tracking Sheet Re 930625 Event Involving Refueling Water Tank Corrosion ML20134B5351994-06-17017 June 1994 Event Tracking Sheet Re 930414 Event Involving Relay Failures ML20134B5021994-03-22022 March 1994 Package Consisting of Oeab Event Tracking Sheet Re 930416 Event ML20064K7521993-06-0808 June 1993 Package Consisting of St Lucie & Turkey Point 1992 Preliminary Llnl Hazard Estimates for Peak Acceleration ML20079N2201991-11-11011 November 1991 Responses to NUMARC Survey in Support of NRC License Renewal Rulemaking ML20132F8891985-09-20020 September 1985 Power Plant Exam Results Summary Sheets.Info Deleted ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams 1997-05-23
[Table view] |
Text
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G CEAR EVENT TRACRIN3 SEEET No Sort Specified QUERY > "HODGE" $ Assigned To & Assigned Date >= 01/19/96 & Assigned Date <- 01/19/96 i
Pltat INFO NOTICE AUTH0 Unit Engineer:
H0DGE V.
Ev02t 11/06/95 Morning Reports Eriefing 50.72#3 0 LER#
050000009600000 PN#:
Cth2r Notification:
DRAIT IN FR REGION 2 (1/11/96) a Sycteas Component OP5 EATING MODE SIGNIFICANCE t
1 - Operation A - Reactor Protection System 2 - Startup B - Safety Related Cooling System i
3 Hot Standby C - Ebel Cladding 4 - Hot Shutdown D - Reactor Coolant Pressure Boundary 5 - Cold Shutdown IL-Containment 6 - Refueling 67-Plant Power j
7 - Other n/r ded.ka G - Unexpected Plant Performance H - Other:
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-{ LLC $22 (p EVENTS ASSESSMENT PANEL First Screening:
C osuraj sigaificance Descriptions Ch 47 7
REGION DRAFT INFORMATION NOTICE DISCUSSES SERIES OF DIFFICULTIES AT ST.
LUCIE 2 WITH SQUARE D SERIES 8501 KPD-23 RELAYS INSTALLED IN RS11 SOCKETS.
3 THESE PROBLEMS IMPACTED DIESEL GENERATOR OPERABILITY DURING TESTING.
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ASSIGle4ENT DATE:
1/19/96 ASSIGNED TO:
V. HOOGE i
PLANT & UNIT:
ST. LUCIE UNIT 2
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i EVENT DATE:
11/6/95 i
50.72 REPORT NO:
1 MR NO:
OTHER SOURCE REPORT:
DRAFT IN FROM REGION II (1/11/96)
RELATED REPORTS:
SPECIALTY CODE:
i EVENT /CONLITION Sb;i4ARY REGION DRAFT INFORMATION NOTICE DISCUSSES SERIES OF DIFFICULTIES AT ST. LUCIE l
2 WITH SQUARE D SERIES 8501 KPD-13 RELAYS INSTALLED IN RS11 SOCKETS. THESE PROBLENS INPACTED DIESEL GENERATOR OPERABILITY DURING TESTING.
4 SPECIFIC FOLLOW-UP ASSIGNNENT i
DETERMINE DETAILS, EVALUATE SAFETY SIGNIFICANCE AND GENERIC INPLICATIONS.
IN j
ADDITION, ADDRESS THE FOLLOWING SPECIFIC CONCERNS:
PREPARE PANEL PRESENTATION TO DETERMINE IF IN ISSUANCE IS WARRANTED.
PREPARE TO BRIEF: _ YES
_ NO TARGET CLOSE00T SCHEDULE:
INITIAL SCREENING BY PANEL REGULATORY ASSESSMENT:
EVENT / CONDITION SAFETY SIGNIFICANCE: _ OTH _ E01 _ SIG _ A0 i
REMAINING OR ADDITIONAL FOLLOW-UP ITEMS:
I CLOSEOUT TEXT REGULATORY ASSESSMENT:
(Abstract of Closeout / Findings)
Region II submitted a draft information notice describing diesel generator testing difficulties at St. Lucie 2 with electrical contacts of Square 0 Series 0501 KPD-13 relays installed in RSll sockets. The vendor
- W Power Systems submitted a Part 21 report on a contact rating change and a contact i
failure at Point Beach for the same relay about six months earlier.
The i
contact failure was caused by licensee modification of the circuit to admit a i
curs;nt 3 times the contact rating. The events assessment panel closed the i
Part 21 report at that time because of minimal safety significance and lack of
A survey of event notifications the past two years and generic implications.
of the list of generic issues revealed no other concerns similar to the St.
A similar subject, stamping rather than achining or soldering Lucie event.
socket contacts in digital instrumentation circuit boards, was treated in IN 94-04. Though the problem at St. Lucie needed to be corrected, issuance of the draft information notice is not warranted.
i CLOSE00T/ FINDINGS:
11, 1996, Region II submitted a draft information notice to PCEB On January discussing a series of difficulties at St. Lucie 2 with Square D Series 0501 KPD-13 relays installed in RS11 sockets. These problems affected diesel generator operability during testing. The licensee conducted a contact resistance program,ver several years and concluded that two socket failures were related to support of the socket on the circuit board being based on soldered connections, an inadequate amount of solder on the failed terminals, and mechanical cycling of the solder joints because of relay removals and replacements.
On April 24, 1995, MXW Power Systems submitted a Part 21 report to the NRC (designated as Pt21 95122) about a contact failure of a Square D class 0501, type KPD relay used in a diesel generator control panel at Point Beach.
PECB learned from MKW that the burnt contact was apparently the result of a misapplication by the licensee for Point Beach because the licensee had modified a relay actuation circuit to include an indication resistance, increasing the current to about 3 times the contact rating. MKW decided to issue a Part 21 report to alert the NRC to a concomitant decrease in the The vendor stated that all of their nuclear Square D type KPD contact rating.
customers except Point Beach and Turkey Point have over 10 years of operating
.blem with the experience and Point Beach is the only plant to have a p:
contacts.
The generic implications of the Part 21 report are minimal.
The difference between the original and actual make/ break current ratings of the Square D type KPD relays is small.
It is not likely that this difference would significantly impact the circuits in which they are typically used. Years of problem free operating experience support this view.
On July 26, 1995, the events assessment panel considered Pt21 95122 and closed it as an other event with no generic implications.
A survey of events reported the last 2 years (search words included socket, solder) shows:
Plant Date Event Braidwood 960130 Solder defects in edg Amerace relays w commercial add-on board to suppress coil deenergization Byron transient Pt Beach 2 950304 Blown fuse in 125 vdc ctri power because of shorted indicating light and socket l
St Lucie 2 951120 Broken socket solder connections in 5 edg relays l
Diablo 1 940426 Shorted phase potential light on startup feeder brkr Brunswick 1 940513 Riown fuse for cooling valve ctrl power when unlit
c
bulb blew out ofsocket on removal of bulb cover Turkey Pt 4 940924 Unguarded bulb for shutdown rod off bottom light shorted when touched by operator, overloading i
120v internal power supply and tripping a fast-acting 10 amp brkr at the vital instrument power i
i bus Mill 1 2 940624 Manufacturing defect (possible cold solder joints) in Bussman Type KTK,120 vac, 5 amp fuses installed in vital ac inverters 4
l The event at St. Lucie 2 in November 1995 is the only one related to the draft information notice, which describes circumstances at St. Lucie 2 in October and November 1995.
Concerning electrical contacts in sockets, on January 14, 1994, NRC issued IN l
94-04:
" Digital Integrated Circuit Sockets with Intermittent Conctact," to i
all NRC licensees except licensed operators. This notice dealt with sockets manufactured by Augat, Inc., an international supplier of interconnections 4
systems for the computer, automotive, and telecommunications industries. The NRC learned about this recurrent problem during an analog-to-digital process I
instrumentation inspection at Cook. The contact portion of these sockets were i
produced by a stamping process rather than by a machining process.
1 j
An electronic search of NUREG 0933'did not reveal any generic issues on this j
subject.
Based on this information, the draft IN from Region II describes a moderately safety-significant problem that is not generic. This draft information notice should not be authorized for issuance by the panel.
1 FINAL PANEL ASSESSNENT:
The panel considered the significance of this to be insufficient to merit issuance of an information notice.
It was judged not to be generic.
EVENT / CONDITION SAFETY SIGNIFICANCE: x OTH _ E01 _ SIG _ A0 BASIS: _ RISK _ PROGRAMATIC _ MARGIN _ N/A GENERIC FOLLOW-UP ACTION REC 0 MENDED:. YES _ NO g PRIORITY (1,2,3,4)'
_ IN
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_ NUREG
_ REG GUIDE FILE: G:\\vern\\ socket _it.ets BRIEF f
- 1. Priarity en h te M10 Riff la lamediate aselyment of resources (e.g.
for highly risk significant safety concerns)
MICRITY 28 lieer tors actlen (e.g., alpificant safety 1soues not marrant r.g lamedlete actlan) i M10 Riff 3: Lens tors actlen (e.g., leeues of anderate to teu safety el etticence)
MIGilfY 4: Resource dependent actlen (e.g., items that can be deferred)
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