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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217J2381999-10-13013 October 1999 Informs That Attached Questions Transmitted by Fax on 991013 to J Rainsberry of Southern California Corp to Prepare for Upcoming Telephone Call ML20212G3791999-09-24024 September 1999 Notification of 991006-07 Meeting with Industry in San Clemente,California to Discuss Technical Issues Re Industry Development of Submittals for risk-informed Technical Specification Improvements ML20211J5591999-09-0101 September 1999 Informs That Application Date in First Line of Attached Ltr Issued 990823 Corrected to Read 990625, Not 1997. Requests That Corrected Copy Be Submitted to H Ray ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211H0431999-08-0909 August 1999 Submits Comments on San Onofre Response to NRC Request for Addl Info on risk-informed IST Program ML20210G4671999-07-30030 July 1999 Forwards Draft rept,NUREG/CR-xxxx,Vol x,INEEL/EXT-99-00373, High-Pressure Safety Injection Sys Reliability,1987-1997 ML20195H7251999-06-11011 June 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam,Submittal for Retake Exam Administered on 990416 ML20195H6031999-06-11011 June 1999 Forwards Exam Repts 50-361/99-301 & 50-362/99-301 Administered at Facility on 990416,with as Given Written Exam Attached ML20207F1141999-06-0404 June 1999 Notification of Significant Licensee Meeting with Util on 990628 to Discuss Emergency Preparedness Program Status & Planned Changes ML20205Q4491999-04-19019 April 1999 Forwards Viewgraphs of 990419 Telcon Re SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N8821999-04-15015 April 1999 Forwards Questions Transmitted by Fax on 990415 to J Rainsberry of SCE & Request for Conference Call to Be Scheduled with Staff to Discuss SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N5991999-04-14014 April 1999 Forwards Questions That Were Transmitted by Fax on 990414 to J Rainsberry of Southern California Corp,In Preparation for Upcoming Telcon on Recirculation Signal/Emergency Feedwater Actuation Signal While Channel in Tripped Condition ML20205M0111999-04-13013 April 1999 Forwards Questions to Be Discussed in Upcoming Telcon on GL 95-07.Questions Transmitted by Fax on 990413 to J Rrainsberry of SCE ML20205K4621999-04-0606 April 1999 Notification of Licensee Meeting with Util on 990422 to Discuss Results of PPR 99-01 ML20207L7041999-03-0202 March 1999 Notification of 990318 Meeting with SCE in Rockville, Maryland to Discuss SCE Mgt Plans for Future risk-informed License Amend Applications for SONGS ML20207L7091999-03-0202 March 1999 Notification of 990317 Meeting with SCE in Rockville, Maryland to Discuss Topics Resulting from NRC Staff Review & Confirmatory Analysis of Licensee Request to Remove Hydrogen Control Sys from SONGS Licensing Basis.Meeting Agenda Encl ML20199L3401999-01-22022 January 1999 Forwards Facility Submitted Outline,Initial Exam & as Given Operating Exam for Test Administered on 981115-20 at San Onofre Nuclear Generation Station ML20202C3931999-01-22022 January 1999 Forwards Exam Rept Administered on 981115-20 at San Onofre Nuclear Generating Station,With as Given Written Exam Encl ML20198M3241998-12-29029 December 1998 Submits Summary of Telcon Re Proposed Criteria to Support Development of SER Constraints for Reload Analysis Tr,For Plant,Units 2 & 3 ML20196G6481998-11-0303 November 1998 Notification of Significant Meeting with Util on 981125 at One White Flint to Discuss Licensee Views on Efforts to Maintain Safety Conscious Work Environ ML20155C9621998-10-27027 October 1998 Notification of 981124 Meeting with Util to Discuss Results of Employee Concerns Program Survey ML20153B4531998-09-0404 September 1998 Notification of Cancellation of 980924 Meeting with TVA in Rockville,Md to Discuss Review of Best Estimate of LOCA Methodology at Plant,Unit 2 ML20236Y6301998-08-0808 August 1998 Forwards Monthly Rept Reflecting Status of 10CFR2.206 Petitions as of 980731.Petitions on Plant GT97494 & GT97339 for Which DD Became Final Actions During Month Were Closed. Portion of Encl Withheld ML20237A0011998-08-0707 August 1998 Informs That Extension Granted on Envirocare Decision of 980904.Two Week Extension on Philadelphia VA Decision of 980828 Requested.Submits Concurrence of Changes.Rept on 2.206 July Status for Plants Encl ML20236K9071998-07-0707 July 1998 Notification of 980710 Meeting W/Util,Rescheduled from 980707,in Rockville MD to Discuss Proposed Amend for Extension of Allowed Outage Times for EDG ML20236K3021998-06-30030 June 1998 Notification of 980707 Meeting W/Util in Rockville,Md to Discuss Licensee Proposed Amend for Extension of Allowed Outage Times for EDG ML20249C2721998-06-19019 June 1998 Notification of 980707 Meeting W/Util in Arlington,Texas to Discuss SONGS New Security Mgt ML20249A1181998-06-11011 June 1998 Notification of 980630 Meeting W/Util in Region IV Office to Discuss Plant Performance Status & Effectiveness of Initiatives to Improve Performance ML20249A1221998-06-11011 June 1998 Forwards Unsolicited Info from San Onofre Licensee Re Emergency Diesel Generator Delegation Allowed Outage Time Extension TS Request ML20249A5621998-06-10010 June 1998 Notification of 980615 Meeting W/Util in Rockville,Md to Discuss SONGS Mgt drop-in Visit by Licensee New Manager, Regulatory Affairs ML20248L8621998-06-0909 June 1998 Forwards May 1998 Rept on Status of Public Petitioners Under 10CFR2.206.Petition on Seabrook (GT970873) for Which DD 98- 03 Became Final Agency Decision on 980413 Closed.Attachment 3 Withheld ML20248C8461998-05-29029 May 1998 Notification of 980529 Meeting W/Util in Rockville,Md for Licensee to Present Proposal for Performing Own Reload Analyses ML20248B6071998-05-26026 May 1998 Notification of Licensee Meeting W/Util on 980528 Re drop-in Visit by Licensee New Manager of Regulatory Affairs for Purpose of Meeting Senior Region IV Mgt ML20216H3281998-04-15015 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Licensee Proposal for Changing Minimum Tcold for Plant Operation & Performing Own Reload Analyses ML20198J5461998-01-0707 January 1998 Notification of Licensee Meeting W/Util on 980120 to Discuss Apparent Violations Involving Physical Security Program. Meeting Not Open to Public ML20198F8931997-12-22022 December 1997 Informs That on 970304,San Onofre,Unit 2,pressurizer Vessel Experienced Cooldown Transient at Rate Greater than 200 F/Hr Limit Specified in Tss.Fracture Mechanics Evaluation of Pressurizer Transient Met Criteria in App G of ASME Code ML20203D4321997-12-0909 December 1997 Notifies of 971223 Meeting W/Util in Rockville,Md to Discuss Use of Mechanical Nozzle Seal Assemblies as Alternate ASME Code Replacements at Plant ML20199A7951997-11-0707 November 1997 Notification of Meeting W/Util on 971121 at Plant to Discuss Employee Concerns Program ML20198Q8611997-11-0606 November 1997 Forwards Copy of e-mail Response to e-mail Inquiry Received from J Chang of San Onofre Nuclear Station Re Info Notice 97-038, Level Sensing System Initiates Common Mode Failure of High Pressure Injection Pumps ML20217J6961997-10-16016 October 1997 Notification of Meeting W/Util on 971023 in Rockville,Md to Discuss Plans for Inspecting SG at Plant,Units 2 & 3 & Runtime Analysis Submitted on 970925 ML20211C4001997-09-22022 September 1997 Notification of Revised Licensee Meeting W/Util on 970930 in Arlington,Tx Re Predecisional Enforcement Conference ML20210T2841997-09-10010 September 1997 Notification of 970924 Licensee Meeting W/Sce in in Arlington,Tx Re Predecisional Enforcement Conference ML20141J8201997-08-18018 August 1997 Notification of 970821 Licensee Meeting W/Util in Arlington, Tx to Discuss RCS Nozzle Penetration Cracking ML20217G5901997-08-0202 August 1997 Informs That Notification Was Made to NRC Operations Center on 970802 as Listed ML20149F8771997-07-18018 July 1997 Notification of 970827 Licensee Meeting W/Util in San Clemente,Ca Re SALP ML20149D7881997-07-15015 July 1997 Revised Notice of Licensee Meeting W/Util in Arlington,Tx on 970805 to Discuss Employee Concerns Program ML20140B6061997-06-0303 June 1997 Notification of 970611 Meeting in Rockville,Md to Discuss Evaluation Rept Re Eggcrate Support Degradation Identified in San Onofre Unit 3 SG ML20141K8751997-05-27027 May 1997 Notifies of 970529 Meeting W/Util in Rockville,Md to Discuss San Onofre Unit 3 SG Eggcrate Visual Exam Results ML20138G2891997-04-30030 April 1997 Notification of 970509 Meeting W/Util in Rockville,Md to Discuss Operational Issues Re Eggcrate Support Degradation Recently Identified in Plant,Unit 3 SGs ML20149H5221997-04-25025 April 1997 Amended Emergency Petition Re Degradation of Steam Generator Internal Tube Supports (Egg Crates),Based on 970417 Rept. Plant Will Not Be Able to Completely Withstand Major Seismic Event 1999-09-24
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J2381999-10-13013 October 1999 Informs That Attached Questions Transmitted by Fax on 991013 to J Rainsberry of Southern California Corp to Prepare for Upcoming Telephone Call ML20212G3791999-09-24024 September 1999 Notification of 991006-07 Meeting with Industry in San Clemente,California to Discuss Technical Issues Re Industry Development of Submittals for risk-informed Technical Specification Improvements ML20211J5591999-09-0101 September 1999 Informs That Application Date in First Line of Attached Ltr Issued 990823 Corrected to Read 990625, Not 1997. Requests That Corrected Copy Be Submitted to H Ray ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211H0431999-08-0909 August 1999 Submits Comments on San Onofre Response to NRC Request for Addl Info on risk-informed IST Program ML20210G4671999-07-30030 July 1999 Forwards Draft rept,NUREG/CR-xxxx,Vol x,INEEL/EXT-99-00373, High-Pressure Safety Injection Sys Reliability,1987-1997 ML20195H7251999-06-11011 June 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam,Submittal for Retake Exam Administered on 990416 ML20195H6031999-06-11011 June 1999 Forwards Exam Repts 50-361/99-301 & 50-362/99-301 Administered at Facility on 990416,with as Given Written Exam Attached ML20207F1141999-06-0404 June 1999 Notification of Significant Licensee Meeting with Util on 990628 to Discuss Emergency Preparedness Program Status & Planned Changes ML20205Q4491999-04-19019 April 1999 Forwards Viewgraphs of 990419 Telcon Re SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N8821999-04-15015 April 1999 Forwards Questions Transmitted by Fax on 990415 to J Rainsberry of SCE & Request for Conference Call to Be Scheduled with Staff to Discuss SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N5991999-04-14014 April 1999 Forwards Questions That Were Transmitted by Fax on 990414 to J Rainsberry of Southern California Corp,In Preparation for Upcoming Telcon on Recirculation Signal/Emergency Feedwater Actuation Signal While Channel in Tripped Condition ML20205M0111999-04-13013 April 1999 Forwards Questions to Be Discussed in Upcoming Telcon on GL 95-07.Questions Transmitted by Fax on 990413 to J Rrainsberry of SCE ML20205K4621999-04-0606 April 1999 Notification of Licensee Meeting with Util on 990422 to Discuss Results of PPR 99-01 ML20207L7091999-03-0202 March 1999 Notification of 990317 Meeting with SCE in Rockville, Maryland to Discuss Topics Resulting from NRC Staff Review & Confirmatory Analysis of Licensee Request to Remove Hydrogen Control Sys from SONGS Licensing Basis.Meeting Agenda Encl ML20207L7041999-03-0202 March 1999 Notification of 990318 Meeting with SCE in Rockville, Maryland to Discuss SCE Mgt Plans for Future risk-informed License Amend Applications for SONGS ML20199L3401999-01-22022 January 1999 Forwards Facility Submitted Outline,Initial Exam & as Given Operating Exam for Test Administered on 981115-20 at San Onofre Nuclear Generation Station ML20202C3931999-01-22022 January 1999 Forwards Exam Rept Administered on 981115-20 at San Onofre Nuclear Generating Station,With as Given Written Exam Encl ML20198M3241998-12-29029 December 1998 Submits Summary of Telcon Re Proposed Criteria to Support Development of SER Constraints for Reload Analysis Tr,For Plant,Units 2 & 3 ML20196G6481998-11-0303 November 1998 Notification of Significant Meeting with Util on 981125 at One White Flint to Discuss Licensee Views on Efforts to Maintain Safety Conscious Work Environ ML20155C9621998-10-27027 October 1998 Notification of 981124 Meeting with Util to Discuss Results of Employee Concerns Program Survey ML20153B4531998-09-0404 September 1998 Notification of Cancellation of 980924 Meeting with TVA in Rockville,Md to Discuss Review of Best Estimate of LOCA Methodology at Plant,Unit 2 ML20236Y6301998-08-0808 August 1998 Forwards Monthly Rept Reflecting Status of 10CFR2.206 Petitions as of 980731.Petitions on Plant GT97494 & GT97339 for Which DD Became Final Actions During Month Were Closed. Portion of Encl Withheld ML20237A0011998-08-0707 August 1998 Informs That Extension Granted on Envirocare Decision of 980904.Two Week Extension on Philadelphia VA Decision of 980828 Requested.Submits Concurrence of Changes.Rept on 2.206 July Status for Plants Encl ML20236K9071998-07-0707 July 1998 Notification of 980710 Meeting W/Util,Rescheduled from 980707,in Rockville MD to Discuss Proposed Amend for Extension of Allowed Outage Times for EDG ML20236K3021998-06-30030 June 1998 Notification of 980707 Meeting W/Util in Rockville,Md to Discuss Licensee Proposed Amend for Extension of Allowed Outage Times for EDG ML20249C2721998-06-19019 June 1998 Notification of 980707 Meeting W/Util in Arlington,Texas to Discuss SONGS New Security Mgt ML20249A1221998-06-11011 June 1998 Forwards Unsolicited Info from San Onofre Licensee Re Emergency Diesel Generator Delegation Allowed Outage Time Extension TS Request ML20249A1181998-06-11011 June 1998 Notification of 980630 Meeting W/Util in Region IV Office to Discuss Plant Performance Status & Effectiveness of Initiatives to Improve Performance ML20249A5621998-06-10010 June 1998 Notification of 980615 Meeting W/Util in Rockville,Md to Discuss SONGS Mgt drop-in Visit by Licensee New Manager, Regulatory Affairs ML20248L8621998-06-0909 June 1998 Forwards May 1998 Rept on Status of Public Petitioners Under 10CFR2.206.Petition on Seabrook (GT970873) for Which DD 98- 03 Became Final Agency Decision on 980413 Closed.Attachment 3 Withheld ML20248C8461998-05-29029 May 1998 Notification of 980529 Meeting W/Util in Rockville,Md for Licensee to Present Proposal for Performing Own Reload Analyses ML20248B6071998-05-26026 May 1998 Notification of Licensee Meeting W/Util on 980528 Re drop-in Visit by Licensee New Manager of Regulatory Affairs for Purpose of Meeting Senior Region IV Mgt ML20216H3281998-04-15015 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Licensee Proposal for Changing Minimum Tcold for Plant Operation & Performing Own Reload Analyses ML20198J5461998-01-0707 January 1998 Notification of Licensee Meeting W/Util on 980120 to Discuss Apparent Violations Involving Physical Security Program. Meeting Not Open to Public ML20198F8931997-12-22022 December 1997 Informs That on 970304,San Onofre,Unit 2,pressurizer Vessel Experienced Cooldown Transient at Rate Greater than 200 F/Hr Limit Specified in Tss.Fracture Mechanics Evaluation of Pressurizer Transient Met Criteria in App G of ASME Code ML20203D4321997-12-0909 December 1997 Notifies of 971223 Meeting W/Util in Rockville,Md to Discuss Use of Mechanical Nozzle Seal Assemblies as Alternate ASME Code Replacements at Plant ML20199A7951997-11-0707 November 1997 Notification of Meeting W/Util on 971121 at Plant to Discuss Employee Concerns Program ML20198Q8611997-11-0606 November 1997 Forwards Copy of e-mail Response to e-mail Inquiry Received from J Chang of San Onofre Nuclear Station Re Info Notice 97-038, Level Sensing System Initiates Common Mode Failure of High Pressure Injection Pumps ML20217J6961997-10-16016 October 1997 Notification of Meeting W/Util on 971023 in Rockville,Md to Discuss Plans for Inspecting SG at Plant,Units 2 & 3 & Runtime Analysis Submitted on 970925 ML20211C4001997-09-22022 September 1997 Notification of Revised Licensee Meeting W/Util on 970930 in Arlington,Tx Re Predecisional Enforcement Conference ML20210T2841997-09-10010 September 1997 Notification of 970924 Licensee Meeting W/Sce in in Arlington,Tx Re Predecisional Enforcement Conference ML20141J8201997-08-18018 August 1997 Notification of 970821 Licensee Meeting W/Util in Arlington, Tx to Discuss RCS Nozzle Penetration Cracking ML20217G5901997-08-0202 August 1997 Informs That Notification Was Made to NRC Operations Center on 970802 as Listed ML20149F8771997-07-18018 July 1997 Notification of 970827 Licensee Meeting W/Util in San Clemente,Ca Re SALP ML20149D7881997-07-15015 July 1997 Revised Notice of Licensee Meeting W/Util in Arlington,Tx on 970805 to Discuss Employee Concerns Program ML20140B6061997-06-0303 June 1997 Notification of 970611 Meeting in Rockville,Md to Discuss Evaluation Rept Re Eggcrate Support Degradation Identified in San Onofre Unit 3 SG ML20141K8751997-05-27027 May 1997 Notifies of 970529 Meeting W/Util in Rockville,Md to Discuss San Onofre Unit 3 SG Eggcrate Visual Exam Results ML20138G2891997-04-30030 April 1997 Notification of 970509 Meeting W/Util in Rockville,Md to Discuss Operational Issues Re Eggcrate Support Degradation Recently Identified in Plant,Unit 3 SGs ML20149H5221997-04-25025 April 1997 Amended Emergency Petition Re Degradation of Steam Generator Internal Tube Supports (Egg Crates),Based on 970417 Rept. Plant Will Not Be Able to Completely Withstand Major Seismic Event 1999-09-24
[Table view] |
Text
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- jtMac UNITED STATES
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NUCLEAR REGULATORY COMMISSION 0 p L'9
[ E REGION V o 5
D 1450 MARIA LANE.SulTE 210 WALNUT CRE E K, CM,lFORNIA 94596 '
%*****,o June 23, 1987 MEMORANDUM FOR: C. E. Rossi, Director Division of Operational Events Assessment FROM: Dennis F. Kirsch, Director Division of Reactor Safety and Projects
SUBJECT:
POTENTIALLY GENERIC ISSUE RV-87-04, DETERIORATION OF INSULATION ON CONAX CONTAINMENT PENETRATIONS AT SAN ON0FRE UNIT 1 On June 15, 1987, Southern California Edison (SCE) advised Region V of a
, potentially significant problem involving the deterioration of insulation on containment penetration electrical circuits in Unit 1. The licensee is still attempting to determine the magnitude of this problem but the Region has been informed of the current developments and the following is the extent of our understanding of this issue.
During the current outage, SCE performed megger testing of the control rod drive mechanism (CRDM) coil stacks to determine if any damage resulted from
, previous cooling fm malfunctions. During this testing, although the CRDM coils tested satisfactorily, unaccentably low resistance readings were found on 11 CRDM cables. Troubleshooting determined that the low megger readings
- were the result of insulation damage on " pigtails" associated with new containment electrical oenetrations that were recently installed during the last refuelino outaae (about I vear of operation). These new penetrations were installed as part of committed EQ upgrading. The new penetrations are manufactured to include pigtails on either end, which are field spliced onto existing plant cabling. The pigtails are multi-conductor cables that are factory spliced tn the single conductor of the penetration. The pigtiils are insulated by a very thin dielectric called DuPont "Kapton" (about 1 mil thick) with an additional thin teflon coating (about 0.5 mil thick). The insulation is installed as a double wrapping of Kapton tape, which is installed by the vendor, CONAX. The entire insulation is about 8 mils thick. Since the insulation is so thin, the pigtails are also protected by a polyolefin sheathing.
To date, SCE has visually inspected about 800 of approximately 7000 cables and discovered about 30 defects. It is our understanding that these inspections have been somewhat limited in their degree of detail. Many of the involved cable trays contain energized cables and inspections only covered those portions of cables that were immediately visible without any repositioning.
Other than the initial CRDM cable meggering, all inspection has been visual.
All of the damaged cables appear to involve cables for which the polyolefin sheathing was cut back to facilitate field splicing at the cable trays (e.g.
all of cne damage has been observed ac the field splice end, not the factory spliced end). The cables with the most severe insulation damage (e.g. the CRDM cables) are located outside of containment. SCE has performed laboratory evaluation of portions of these cables which appears to confirm salt water attack of the Kapton. The mechanism appears to involve salt water infusion 9611130508 961028 PDR FOIA WHITE 96-354 PDR
through what appear to be knife cuts in the Kapton/ Teflon coating. Once the salt water gets to the copper conductor, copper chloride and sodium hydroxide are produced. The sodium hydroxide has been shown to easily dissolve the Kapton tape. This mechanism seems to be confimed by the fact that none of the cut Kapton obse,ryed inside of_containmertt_appe.ars ts_i_nlolve Kapton ~
deterioratiog. j Although SCE has yet to confim their evaluatinn of the cause and correction i of this problem, it is our understanding that the leading theory involves accidental cutting of the Kapton during removal of the polyolefin sheathing.
SCE has agreed to perform a thorough visual inspection of every bare Kapton wire associated with all* the containment penetrations and provide the results to Region V.
This potential generic issue has been discussed with Messrs. Lanning and Merschoff. Region V is not aware of other' potential uses or users of the ,
subject coating material.and recommends that NRR evaluate whether other l nuclear applications of the coating material may be subject to similar !
degradation or environmental conditions inducing degradation.
{
l YennisKirsch, F. M'h Director Division of Reactor Safety and Projects cc: E. L. Jordan, AE00 C. H. Berlinger, NRR G. W. Knighton, NRR R. F. Dudley, NRR D. Crutchfield, NRR W. Lanning, NRR ,3)p E. Merschoff, NRR g P. H. Johnson, RV P. Qualls, RV F. R. Huey, RV l
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i July 10, 1987 l ,
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U. $. Nuclear Regulatory Comission I Document Control Desk l l Washington, D.C. 20555 - I 1
Subjects cceket No. 50-206 Im ormation LER t
j Licensee Event Report No.87-008 -
q San Onofre Nuclear Senerating tation Unit 1 1 l l
! The attached Licensee Event Report (LER) provides information regarding damage to i the insulatior, of conductors which connect field cabling to containment 1
' electrical per.etrations. Neither the health and safety of plant personnel nor the health anc safety of the public was affected by this event. ,
If you require any additional information, please so advise.
I l
j Sincerely, ,
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. M H. E. MORGAN y
STATION MANAGER RCDouglas j
Enclosure:
LtR No.87-008 cc F. R. Huey (USNRC Senior Resident Inspector Units 1, t and 3)
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i i i-i 4 e... .n cu i. i . oo .= c.. . . . Tn,. . -.i... mi . ..ni. . . .. .... .a . .> a e s on June 2,1987 with Unit 1 in Mode 5, moqge-ing of Control Rod Drive Mechanism (CRDN) '
coil circuits revealec low insulation resustance in 22 circuits. The source of the low resistance was later found in Conax containment electrical penetration " pigtails" which c nnect the field cables to the penetration conductors, i
Laboratory analysis and subsequent evaluation of the damaged CRDN pigtails revealed that tho Kapton insulation appeared to have been cut or punctured through to the conductor.
The analysis further determined the insulation damage did not resu' t from electrical l causes. Subsequent visual inspection of those portions of approximately 8,000 p:netration pigtails which are not protected with a polyolefin ,jecitet, revealed that less thar. 2 per cent were damaged (including the CRDN cables). Osmaged pigtails in circuits which are safety related or which are important to safety have been repaired.
Investigation of the cause of the insulation damage indicates that most of the damage occurred during initial installation of the Coner penetrations in 1988/1386. Corrective action will be developed and implemented to prevent recurrence of insulation damage.
Th) Units 2 and 3 electrical penetrations are of a different design and thus are not sia11erly affected.
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. LICENSEE EVENT REPORT (LER) TEXT CONTivalATl0N !'
i 5AM DNOFRE NUCLEAR GENERATIUR 5TATION potKET NUMBER LER NUMER PAGE i UNIT 1 05000206 87-008 00-- 2 0F 3 i I
i i On June 2,1987 with Unit 1 in Mode 5, meggering of Control Rod Drive Mechanism (CRDM) i roll circuits revealed low insulation resistance b 22 circuits. The source of the low ,
! resistance was later found in Conax containment electrical penetration ' pigtails",
i ranging in length from four to twenty feet, which connect field cables to the solid l copper penetration feed throuqhs. These pigtails ar. insulated with a double wrap of .
- Kapton insulation approximate'y 9 mils thick. A leflon-based adhesive is used to bind I l the Kapton wrap and to provide a moisture barrier. As provided by the manufacturer, the i pigtails originating from each feed through are grouped together and jacketed with a i j loose fitting polyolefin s,eeye which protects the insulation from mechanical damage.
Visual examination of the CADN pigtails outside containment, which are in an outside l j marine air environment., identified points at which the insulation was damaged and the
! copper conductor displayed signs of corrosion. Laboratory analysis and subsequent i evaluation of two samples of damaged cable revealed that the insulation appeared to have i j been cut or punctured through to the conductor. j 1
! Subsequent visual insroction of those portions of approximately 5,000 penetration l j pigtails which are not protected with the polyolefin sleeve, revealed that less than 2 per cent were damaged (incluoing the CRON cables).
! The inspection further revealed a i
! pattern of physical danage (i.e., cuts, punctures, or abrasion) to the exposed portion I of the pigtail insulattor, shere the pigtails are connected to the field cables. None of i j the damaged pigtails 'iocated inside containment revealed evidence of conductor '
3 corrosion. I i
j .ne laboratory analysis, further determined that the failures did not result from i electrical causes. The postulated corrosion mechanism was intrusion of moisture and l Nacl from the marine air anvironment outside of containment, through a cut in the i
- insulation. Reaction with the conductor formed CuC1 2 and Na0H. The NaOH, in a
! saturated water soluta.on, degraded the Kapton insulation around the cut. I 1
investigatton of the cause of the insulation damage indicates that most of the damage h occurred during initial installation of the Conax penetrations in IM5/1986. The balance of the damage appears to be from other causes such as dropping or placing gl; objects on the cables, and stepping on the cables during subsequent construction, O aaintenance and inspection activities.
j A sa ple of exposed polyelefin jacketing was also visually surveyed. The survey revealed three instances of jacketing damege extending through to the conductor insulation. The damage to the jat.keting appears to be random and unrelated to the Kapton insulation damage described above.
04: aged pigtails in circuits which are safety telated or which are important to safety I were repaired by cutting out the damaged section and reconnecting the field cable to the !l re2aining portion of the pigtail, or sy covering 'he damaged section with an approved heat shrink insulating tube. The remaining damaged pigtalls are part of non essential lighting and communication circuits, which will be repaired during the next refueling l1!!
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outage.
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! LICENSEE EVENT REPORT (LER) TEXT CONTINUATION i M NERATION STATION DOCKET NUMBER LER NLmer.R PAGE I
- UNIT 1 -
05000206 87-008-00 3 0F 3 l l i
i C rrective action to prevent recurrence will include providing cable tray covers where
. appropriate, and administrative controls on activities which could potentially damage i l j conductor insulation. Additionally, appropriate procedures will be revised to address I protection and handling of Kapton insulated cabla. Implementation of corrective action i uill be completed by the end of the next refueling outage.
i These instances of installation damage to Kapton insulation are similar to the i installation damage.r/ ;
i i Unit I (Docket 50 450)inported January, ,by1985.
Gulf 5tates Utilities company for the River Bend Station ,
i I l The Units 2 and 3 electrical penetrations are of a different design and thus are not ;
similarly affected. !
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