Staff Exhibit S-41,consisting of Rept Concerning Analysis of Heat Aging Data on 52 Moulding Matl to Determine pre-aging Conditions for Nuclear Qualification TestingML20094N405 |
Person / Time |
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Site: |
Farley ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
02/19/1992 |
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From: |
Albertalli F, Mcgowan E, Scott R RAYCHEM CORP. |
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To: |
|
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References |
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CIVP-S-041, CIVP-S-41, NUDOCS 9204060337 |
Download: ML20094N405 (13) |
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Category:EXHIBITS (DOCKETING AND SERVICES BRANCH INFORMATION
MONTHYEARML20118A1461992-05-21021 May 1992 Staff Exhibit S-83,consisting of Graph Re Sandia Test Re Exposure ML20118A1241992-05-21021 May 1992 Applicant Exhibit A-135,consisting of Diagram Re NSS3 Terminal Block Assembly as-built Dimensions ML20118A1481992-05-21021 May 1992 Staff Exhibit S-85,consisting of Paper by J Delmonte Re Plastics in Engineering ML20118A1471992-05-21021 May 1992 Staff Exhibit S-84,consisting of Graph Re 120 Divs 5th,10th Accent by 6 Cycle semi-log ML20118A1231992-05-20020 May 1992 Applicant Exhibit A-129,consisting of Memo Forwarding Record of 920514 Telcon ML20118A1191992-05-20020 May 1992 Applicant Exhibit A-125,consisting of Notes from 871118 Meeting ML20118A1201992-05-20020 May 1992 Applicant Exhibit A-126,consisting of Notes Re Rcw Open Areas ML20118A1221992-05-20020 May 1992 Applicant Exhibit A-128,consisting of Notes Re 871120 Plant Exit Meeting ML20118A1211992-05-20020 May 1992 Applicant Exhibit A-127,consisting of Notes Re 871120 Plant Exit Meeting ML20118A1181992-05-19019 May 1992 Applicant Exhibit A-124,consisting of Rept IPS-107, Test Rept on Electrical Terminations Subjected to Design Basis Accident Environ ML20118A1341992-05-18018 May 1992 Staff Exhibit S-70,consisting of Sys Component Evaluation Worksheet ML20118A1171992-05-18018 May 1992 Applicant Exhibit A-123,consisting of Operator Handbook Re Nuclear Containment Axivane Fan ML20118A1121992-05-18018 May 1992 Applicant Exhibit A-118,consisting of Product Control Document NCBK-04-04 ML20118A1131992-05-18018 May 1992 Applicant Exhibit A-119,consisting of Matl Safety Data Sheet ML20118A1111992-05-18018 May 1992 Applicant Exhibit A-117,consisting of 871109 Notes Re Plant ML20118A1091992-05-18018 May 1992 Applicant Exhibit A-115,consisting of Record of 891121 Telcon Re Okonite Tape Splices ML20118A1051992-05-18018 May 1992 Applicant Exhibit A-112,consisting of Re Closure of Completed License Conditions ML20118A1101992-05-18018 May 1992 Applicant Exhibit A-116,consisting of Drawing 1366C51 Re Electric Heater Wire Bill & Diagram ML20118A1161992-05-18018 May 1992 Applicant Exhibit A-122,consisting of Re Qualification Info ML20118A1391992-05-18018 May 1992 Staff Exhibit S-75,consisting of Table 1 Re Reg Guide Variable Cross Ref to Variable Number ML20118A1401992-05-18018 May 1992 Staff Exhibit S-76,consisting of Paper Entitled, Westinghouse Setpoint Methodology for Control & Protection Sys ML20118A1381992-05-18018 May 1992 Staff Exhibit S-74,consisting of NUREG/CR-3691, Assessment of Terminal Blocks in Nuclear Power Industry ML20118A1321992-05-18018 May 1992 Staff Exhibit S-68,consisting of 900619 Memo Re Plant Tape Splice Test & Info Received from Okonite Re Thermal Properties of Okonite T-95 Splicing Tape ML20118A1431992-05-18018 May 1992 Staff Exhibit S-79,consisting of Info Re Continuous Vs Intermittent Use & Lube Performance ML20118A1451992-05-18018 May 1992 Staff Exhibit S-82,consisting of 831202 Memo Re Composite Audit Rept 83/19 for Plant ML20118A1311992-05-18018 May 1992 Staff Exhibit S-67,consisting of Re Mlea Project 90009 Involving Thermal Behavior of T-95 & Scotch 33 ML20118A1351992-05-18018 May 1992 Staff Exhibit S-71,consisting of EQ Insp Tracking Sheet for Farley Nuclear Plant ML20118A1331992-05-18018 May 1992 Staff Exhibit S-69,consisting of Sys Component Evaluation Worksheet ML20118A1421992-05-18018 May 1992 Staff Exhibit S-78,consisting of Installation & Maint Manual Re Series 800/1000/2000/3000 Axivane Fans ML20118A1151992-05-18018 May 1992 Applicant Exhibit A-121,consisting of Performance Test Data of Limitorque Valve Operator ML20118A1371992-05-18018 May 1992 Staff Exhibit S-73,consisting of NUREG/CR-3418, Screening Tests of Terminal Block Performance in Simulated LOCA Environ ML20118A1361992-05-18018 May 1992 Staff Exhibit S-72,consisting of EQ Insp Tracking Sheet for Farley Nuclear Plant ML20100R4001992-02-21021 February 1992 Applicant Exhibit A-81 Consisting of Rept Entitled, Clarification of Info Re Environ Qualification of Limitorque Motorized Valve Operators ML20100R4051992-02-21021 February 1992 Applicant Exhibit A-82,consisting of Resume for Vs Noonan ML20100R3991992-02-21021 February 1992 Applicant Exhibit A-79,consisting of Resume for PA Dibenedetto ML20100R4281992-02-21021 February 1992 Applicant Exhibit A-110,consisting of Graph of Insulation Resistance & Temp Periods ML20100R4301992-02-21021 February 1992 Applicant Exhibit A-111,consisting of Graph of Total Elapsed Time Re Phase Two of Environ Temp Profile ML20094P3991992-02-20020 February 1992 Applicant Exhibit A-46,consisting of Ltr Confirming Info Previously Provided to Util Re Environmentally Qualified Prototype Testing ML20094N7191992-02-20020 February 1992 Staff Exhibit S-60,consisting of Memo Recommending That Licensees Review Facilities to Determine If Specific Terminal Blocks Used in Low Voltage Application ML20100R4271992-02-20020 February 1992 Applicant Exhibit A-109,consisting of Ltr Forwarding Document on Limitorque Actuator Environ Qualification ML20094N7351992-02-20020 February 1992 Applicant Exhibit A-70,consisting of EQ Action Item Describing Problem & Resolution Status.Related Correspondence ML20094P2021992-02-20020 February 1992 Applicant Exhibit A-23,consisting of Util Environ Qualification Program for Plant ML20094P2281992-02-20020 February 1992 Applicant Exhibit A-29,consisting of Work History & Educational Background for Util Project Engineer ML20094P2331992-02-20020 February 1992 Applicant Exhibit A-30,consisting of Work History & Related Experience of Util Employee ML20094P3621992-02-20020 February 1992 Applicant Exhibit A-36,consisting of Rept Indicating IEEE Std for Qualifying Class 1E Equipment for Nuclear Power Generating Stations ML20094P3651992-02-20020 February 1992 Applicant Exhibit A-38,consisting of Working Specs for Installation of Cables ML20100R3931992-02-20020 February 1992 Applicant Exhibit A-76,consisting of Rept Entitled, Radiation Exposure & Accident Simulation Test Program on Texaco Greases & Oils ML20094P4101992-02-20020 February 1992 Applicant Exhibit A-37,consisting of Excerpts from IEEE Trial Use Std Re General Guide for Qualifying Class One Electric Equipment for Nuclear Power Generating Stations ML20100R3791992-02-20020 February 1992 Applicant Exhibit A-57,consisting of Info Re CR151B Terminal Boards for Control Circuits ML20100R3801992-02-20020 February 1992 Applicant Exhibit A-58,consisting of Sensor Products Qualification Test Summary Rept 1992-05-21
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20196J3291999-06-28028 June 1999 Comment Supporting Proposed Rule 10CFR50 Re Industry Codes & Standards ML20206M7291999-04-30030 April 1999 Comment Supporting Draft RG DG-1083, Content of UFSAR IAW 10CFR50.71(e). Licensee of Listed Plants in Total Agreement with Comments Provided to NRC by NEI HL-5717, Comment Supporting Proposed Rule 10CFR50,52 & 72 Re Changes, Tests & Experiments.Util in Total Agreement with NEI Comments to Be Provided to NRC1998-12-18018 December 1998 Comment Supporting Proposed Rule 10CFR50,52 & 72 Re Changes, Tests & Experiments.Util in Total Agreement with NEI Comments to Be Provided to NRC HL-5715, Comments on Proposed Rule 10CFR50 Re Monitoring Effectiveness of Maint at Nuclear Power Plants.Util Is in Total Agreement with NEI Comments1998-12-14014 December 1998 Comments on Proposed Rule 10CFR50 Re Monitoring Effectiveness of Maint at Nuclear Power Plants.Util Is in Total Agreement with NEI Comments HL-5702, Comment Supporting NEI Comments Totally on Proposed Draft RG DG-4005, Preparation of Supplemental Environmental Repts for Applications to Renew Nuclear Power Plant Ols1998-10-23023 October 1998 Comment Supporting NEI Comments Totally on Proposed Draft RG DG-4005, Preparation of Supplemental Environmental Repts for Applications to Renew Nuclear Power Plant Ols HL-5695, Comment Supporting Nuclear Energy Institute (NEI) Comments on 10CFR50.55(a) Pr, Streamlined Hearing Process for NRC Approval of License Transfers1998-10-13013 October 1998 Comment Supporting Nuclear Energy Institute (NEI) Comments on 10CFR50.55(a) Pr, Streamlined Hearing Process for NRC Approval of License Transfers HL-5690, Comment on Integrated Review of Assessment Process for Commercial Nuclear Plants. Util in Total Agreement with NEI Comments Provided to NRC1998-10-0505 October 1998 Comment on Integrated Review of Assessment Process for Commercial Nuclear Plants. Util in Total Agreement with NEI Comments Provided to NRC HL-5983, Comment on Proposed Rule 10CFR50 Re Reporting Requirements for Nuclear Power Reactors. Snoc in Total Agreement with NEI Comments,To Be Provided to Nrc.Requests That NRC Provide Guidance to Application of NUREG-1022,rev 1 as Listed1998-09-21021 September 1998 Comment on Proposed Rule 10CFR50 Re Reporting Requirements for Nuclear Power Reactors. Snoc in Total Agreement with NEI Comments,To Be Provided to Nrc.Requests That NRC Provide Guidance to Application of NUREG-1022,rev 1 as Listed HL-5682, Comment Opposing Draft NUREG-1633, Assessment of Use of Potassium Iodide (Ki) as Protective Action During Severe Reactor Accidents, & Endorsing Comments Submitted by Nuclear Energy Institute1998-09-15015 September 1998 Comment Opposing Draft NUREG-1633, Assessment of Use of Potassium Iodide (Ki) as Protective Action During Severe Reactor Accidents, & Endorsing Comments Submitted by Nuclear Energy Institute ML20153B2391998-09-15015 September 1998 Comment on Draft NUREG-1633, Assessment of Use of Ki as Protective Action During Severe Reactor Accidents. Endorses NEI Comments HL-5602, Comment Opposing Proposed Rule 10CFR50 Re Industry Codes & Stds1998-04-0303 April 1998 Comment Opposing Proposed Rule 10CFR50 Re Industry Codes & Stds HL-5586, Comment on Proposed Generic Ltr, Year 2000 Readiness of Computer Sys at Npps1998-03-0404 March 1998 Comment on Proposed Generic Ltr, Year 2000 Readiness of Computer Sys at Npps HL-5582, Comment on Draft Reg Guide DG-5008, Reporting of Safeguards Events1998-02-27027 February 1998 Comment on Draft Reg Guide DG-5008, Reporting of Safeguards Events ML20203B9761998-02-23023 February 1998 Order Prohibiting Involvement in NRC Licensed Activities (Effective Immediately).Requires That Mcgriff Be Prohibited from Any Involvement in NRC-licensed Activities for Period of 3 Yrs from Date of Dismissal from SNC on 970305 HL-5564, Comment on Draft NUREG 1555, Updated Environ Standard Review Plan1998-01-30030 January 1998 Comment on Draft NUREG 1555, Updated Environ Standard Review Plan HL-5554, Comment Supporting NEI Comments on PRM 50-63A by P Crane Recommending Emergency Planning Standard for Protective Actions Be Changed to Require Explicit Consideration of Prophylactic Use of Potassium Iodide for General Public1998-01-15015 January 1998 Comment Supporting NEI Comments on PRM 50-63A by P Crane Recommending Emergency Planning Standard for Protective Actions Be Changed to Require Explicit Consideration of Prophylactic Use of Potassium Iodide for General Public HL-5546, Comment Supporting Proposed Rule & Direct Final Rule on 10CFR50.68 & 10CFR70.24, Criticality Accident Requirements1997-12-31031 December 1997 Comment Supporting Proposed Rule & Direct Final Rule on 10CFR50.68 & 10CFR70.24, Criticality Accident Requirements HL-5529, Comment Opposing Rule 10CFR50 Re Codes & Standards,Ieee National Consensus Standard1997-12-0101 December 1997 Comment Opposing Rule 10CFR50 Re Codes & Standards,Ieee National Consensus Standard ML20199J0031997-11-24024 November 1997 Comment Supporting Proposed Rule Re Financial Requirements for Decommissioning Nuclear Power Reactors & Draft RG 1060 HL-5424, Comment on NUREG-1606, Proposed Regulatory Guidance Re Implementation of 10CFR50.59 (Changes,Tests or Experiments). Encourages NRC Not to Abandon 30 Yrs of Effective Implementation of 10CFR.50.59 for New Positions1997-07-0707 July 1997 Comment on NUREG-1606, Proposed Regulatory Guidance Re Implementation of 10CFR50.59 (Changes,Tests or Experiments). Encourages NRC Not to Abandon 30 Yrs of Effective Implementation of 10CFR.50.59 for New Positions ML20148N0741997-06-19019 June 1997 Comment on Proposed Suppl to Bulletin 96-001 Re Control Rod Insertion Problems.Util in Complete Agreement That Incomplete Rcca Insertion Not Acceptable HL-5407, Comment Opposing NRC Proposed Strategies to Address Licensees Need to Establish & Maintain safety-conscious Work Environ1997-05-27027 May 1997 Comment Opposing NRC Proposed Strategies to Address Licensees Need to Establish & Maintain safety-conscious Work Environ ML20132A9171996-11-27027 November 1996 Comment Supporting Draft RG DG-1047, Stds Format & Content for Applications to Renew NPP Ols ML20128M3411996-09-30030 September 1996 Comment on Proposed Generic Communication, Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism & Other Vessel Head Penetrations ML20116D6491996-07-31031 July 1996 Exemption from Requirements of 10CFR70.24 Re Criticality Monitoring Requirements ML20116G9271996-07-29029 July 1996 Comment Supporting Proposed Rule 10CFR26 Re Mods to Fitness-For-Duty Program Requirements ML20115D1911996-07-0505 July 1996 Comment on Final Rule 10CFR51 Re Environ Review for Renewal of Nuclear Power Plant Operating License.Supports NEI Comments ML20115H1951996-07-0303 July 1996 Comment Supporting Proposed Rule 10CFR50, Reporting Reliability & Availability Info for Risk-Significant Sys & Equipment ML20113C6691996-06-24024 June 1996 Comments on Proposed Rule 10CFR50 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors ML20100D1871996-01-29029 January 1996 Comment Opposing Petition for Rulemaking PRM-50-63, Recommending That Planning Std for Protective Actions for General Public Include Stockpile or Predistribution of Ki for Prophylactic Use ML20095D9801995-12-0808 December 1995 Comments on Proposed Generic Communication, Boraflex Degradation in SFP Storage Racks ML20094M9691995-11-13013 November 1995 Comment on Proposed Rules 10CFR60,72,73 & 75, Safeguards for Spent Nuclear Fuel or High-Level Radioactive Waste ML20091Q2711995-08-28028 August 1995 Comment Opposing Review of Revised NRC SALP ML20086N6141995-07-10010 July 1995 Comment on Proposed Generic communication;10CFR50.54(p), Process for Changes to Security Plans W/O Prior NRC Approval. Endorses NEI Comments ML20086M8011995-06-28028 June 1995 Comment on Proposed Review of NRC Insp Rept Content,Format & Style. Util Applauds NRC for Undertaking Endeavor to Make Insp Rept More Effective Tool for Communicating W/Licensees & Public ML20083N4921995-05-0404 May 1995 Comment on Proposed Rule 10CFR50, Primary Reactor Containment Leakage Testing for Water-Cooled Power. Util in Total Agreement W/Nei Comments ML20082K0461995-04-10010 April 1995 Comment on Draft Policy Statement, Freedom of Employees to Raise Safety Concerns W/O Fear of Retaliation. Endorses NEI Comments ML20078J8101995-02-0303 February 1995 Comment Supporting NUMARC Comments on Proposed Rule 10CFR50 Re Shutdown & low-power Operations for Nuclear Power Reactors ML20080G8471995-02-0101 February 1995 Comment on Proposed Rule 10CFR21 Re Procurement of Commercial Grade Items by NPP Licensees.Recommends That New Definitions Be Applicable & Consistent to Licensees Who Hold Other Licenses as Well as Part 50 License ML20085E5381995-01-0505 January 1995 Comment on Proposed Rule 10CFR73 Re Changes to NPP Security Requirements Associated W/Containment Access Control. Supports NEI Comments ML20077F6561994-12-0101 December 1994 Comment on Proposed Generic Ltr Re Reconsideration of NPP Security Requirements for Internal Threat.Util in Total Agreement W/Nei Comments ML20077E9171994-12-0101 December 1994 Comments on Proposed Rule 10CFR2,51 & 54 Re NPP License Renewal,Proposed Revs.Informs That Util in Total Agreement W/Nei Comments to Be Provided to NRC ML20072T6651994-09-0202 September 1994 Comment on Supplemental Proposed Rule 10CFR51 Re Environ Review for Renewal of Operating Licenses.Util in Agreement W/Nei Comments to Be Provided to NRC ML20072K3331994-08-17017 August 1994 Comment Supporting Petition for Rulemaking PRM-9-2 Re Ohio Citizens for Responsible Energy,Inc Petition ML20072B3711994-08-0909 August 1994 Comments on Proposed Rule 10CFR26 Re Consideration of Changes to FFD Requirements.Licensee in Total Agreement W/Nei Comments ML20071H1321994-06-27027 June 1994 Comment Supporting Proposed Rulemaking 50-60 Re Virginia Power;Filing of Petition for Rulemaking ML20069J5901994-06-0909 June 1994 Comment Supporting Proposed Rule 10CFR170 & 171 Re Rev of Fee schedules;100% Fee recovery,FY94 ML20065P4631994-04-25025 April 1994 Comment Supporting Proposed Rule 10CFR50 Re Codes & Stds for Npps;Subsections IWE & Iwl ML20065P4541994-04-0505 April 1994 Comments on Draft NUREG-1022,Rev 1, Event Reporting Sys (10CFR50.72 & 50.73) Clarification of NRC Sys & Guidelines for Reporting. Util in Total Agreement W/Nei Comments ML20064L8671994-03-11011 March 1994 Comment Supporting Proposed Amends to 10CFR20 Re Radiological Criteria for Decommissioning of NRC Licensed Facilities 1999-06-28
[Table view] |
Text
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- g ANA.YSI5 0F HEAT AG;NG DATA ON --52 MOLDING MATERIAL TO DETEW;NE PRiaGING C0CITIONS FOR NUCLDR QijALIFICATIGN 7gg 7gg, f.netciure s
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1 EDR-5040 Page i REVISION RECORD
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4 EDR-iO4C 10/15/5'.
CONTINTS Page Section Title 1
- 1. OBJECTIVE 1
- 2.
SUMMARY
1
- 3. CONCLUSIONS 2
4 INTRODUCTION 2
- 5. REQUIREMENTS
- 6. TEST PROCEDURE .
1 3
6.1 Specimen Preparation 3
6.2 Oven Aging 4
- 7. ARRHENIUS PLOTTING 5
- 8. OETERMINATION OF ACCELERATED AGING CONDITIONS '
- 9. TABLES AND GRAPHS ,
TABLE 1, Oven Aging Data .
,6 for -52 Moleing Material TABLE 2, . Time-Temperature 6 Relationship of -52 Molcing Material using 30 Percent Retention of Elongation TAELE 3, Aging Times anc - 6' Temperatures Needec to Satisfy a 40 Year Life at 90*C Requirement _
7 FIGURE 1, Oven Aging Data of -52 Molatng Material FIGURE 2, Arrnenius plot of -52 Molding Material 5
- 10. REFERENCE 5 g 9 APPENDIX A e 10 11.
1 ii l
- - - _ _ _ _ _ _ _ _ _ _ ____1_______
4 ED R - i c.'. .
1C/15/S.
- 1. OBJECTIVE _
The objective of tnis recort is to prtsent and analyze the Ar*henius Osta i obtained in a heat aging study of -52 molding material to determine pre-aging conditignp for Qualifying parts mace from sne materia'. to IEEE St ancard 383-1974(11 and IEEE Standard 323-1974.(2)
- 2. SUMM:EY d
recuires components to be pre-aged to a condition ecu va'en:
IEEE 353-1974 to the design life of the nuclear generating station before exposure to a simulated design basis event (DBE). Tnis report describes these re; # e-meets, outlines the nett aging test procedure, presents and analyzes tne results using Arrnenius plots and discusses end-point criterion to cetem,ine tne time-te.oerature relationsnio for this pre-aging. ,
- 3. CONCLUSIONS A time-tem;erature lationsnip, based on Arrnenius pict:ing, has t&
est a:11sne for -52 molding material wnien satisfies in? recuirements earts of IEEE 383-1974 for establisning the qualified service life of moice: i and for accelerated pre-aging of materials before exposure to ra:1st en and DBE tests.
g.-
1 e - - - - - - - _ _ _ _ _
EDR 5 ::
20./;5 / 5; 4.. INTRODUglCN An kne*4ive study on the aging characteristics of the 52 molding material used for molded parts for nuclear applications has been cor:w:te:,
This report co:vments the times recuirec for the ultimate elongatier cf to te- e-a.
t this m6terial to decrease wnen die cut soe:imens were expose:
tures between 13PC and 175'C. The values are given in per:ent retentien of tne original value and cover the range of 70 per:ent to 30 per:ent.
These data have been analyzed using 4 30 percent retention of elongation as the ene point. The resulting Arrhenius plot, when adjusted to an ene of life of 40 years at 90*C, yieles a series of times at various te .:e a-tures for pre-agieg the material.
- 5. REQUIRE *ENTS
. The recuirements for ele:tric caoles and related materials sucn as so' ice insviating parts for nu: lear power plants a*e given in IEEE 383-19' .
This cocument states tnat ' type tests for cesign basis event concitions snould consist :,f subjecting nonagec and aged cables, fiele splices, an:
i connections to a secuence of environmental extremes wnien simulate the j
most severe costulatec conditions of a design basis event anc s:e:1fie:
concitions of installation."
- int aging re uirement is furthee exclained in anothee section of IEEE r 353-1974 wnsen states, "The basis for estaolishing time anc trce-sta.e concitions for aging of sam:les to simulate their qualif tec life may oe that of Arrnenius plotting or other method of proven valicity and 4;;11ca-bility for the materials in questier."
It is generally specified that the design life of a nuclear gent ating station is 40 years and tnat the majority 4,f the cables usec in the slant .
are rated for a 90'C conductor temperatre. Actual concuctor operating temperatures typically will 1,e 1c <er than 90*C in use due to lowec the
" maximum design" ambient teceratures and CPble derating practices'. H Also molcee parts are typically not in contact witt. the actual concs: tor C*
It is conservative to asses: the aging performance of tne -!2 la itself.
The cables an: M molair.g material at the rated conductor temperature. C splice systes must, therefore, be aged to the equivalent of 40 years C life at 90*C before being subjec*.ed to the radiation anc design basis event reevicec by the standards. Since unaged systems must aise be testec to the same radiation and design basis event conditions, a ca:1e ce system passing the tests in botn tne aged anc unagec con:ition moul:
qualifiec for the design life of tne plant.
E
E*g.53;
).0/15/31 Groups of five specimens were periodically reeved fr The retention of elongation was calculated and the values plo shown in Figure 1. This infortnation is given in retention of. elongation could be found.
Tacle 1.
A list of 43t4 accuisitior eouipment and calibestion information is givea in Aopendix A.
l
- 7. ARb!NIU$ pl0NING f l l
a selected end point at several te?peratures a*e I
When the times to reach plottec on a graph witn tne logarithm of time as the ordinate and tne reciprocal of tne absolute temperature as the abscissa, it is saic to ed an Arrhenius p1.11. The IEEE standards do not state wnien end point j Therefore, it becomes important to enoese one that should be selected. There are many possibl,e parreters is consistent wi.th the applicatinn.to select end point criteria, sucn as retention o
elungation, retention 8 tensile strengtn, retention of.dielectri'c It* is staengin, and voltage witnstand tests af ter a mandre' ben tne original properties but on a specific value of elongation or dielectric st engin after aging.
Fe- the work described in this report, a retention The reason for ttJ!,ofenoice 30 perceu was thatof tne tnis a
original elongation was chosen.ene point left a wide margin of safety anc was material study. Since tne ultimate elongation of sne -52 material Jn tne unaged state is *.ypically over 500 percent, a retention of 30 percent of tne original value would still give an ultimate elongation value of over 150 percent. This is well in excess of the count of elongation Some wire insulation in gene *al use needed for any functional purpose.
nas less than this amount of elongation initially or as manuf acturec.
For clarification, the results presented in Table 1 for 30 percent retention of elongation are given in Tacle 2. Using these results an Arrnenius plot has been drawn and is shown in Figure 2.
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- . __ - - _ _ , , . , , , , , , . - + . . . - - _ . , . . . -
l i
10/15/!:
- 8. DETE8PINATION OF ACCELERATED AGING CONDITIONS
- An extrapolation of the data based on linear regression analysis indicates 7
that the material will retain 30 percent of its initial elongation after
- 40 years at 103*C, a temperature 13*C above its reovired ratto temoe atre.
Therefore, to cetermine appropriate acceleratac aging conditions for tne purpose of p e-aging specimtns for DBE tests, a line may*be ceswn wn*:n passes tnrougn the point corrasponding to 40 years at 90 C and is paratie'.
Such a line is snown (i.e., sme heat of activazion) to the life curve.
' as Curve 8 of Figure 2. Now, any point along Cu ve 5 represents a time tecerature combination that may be used to. pre-age A few suce sper.imens 9;ncitions to are simulate ene of life concitions for D8E tests.It can be seen that en aging time given in Taole 3.150*C is a practical and valid set of conditions for acceleratec based on a design life of 40 years at 90*C. '
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, EDR-5040 10/15/51
- 9. _ TABLES AND GRAPHS ,
TABLE 1 Ovea !;4rg ?ca For 52 Molding Material -
Oven Temper ature Time (h) to Various
('C) Leveis of Retainec Elongation 70% 60% 50% 40% 30%
136 g W W 2025 M
2675 11600 3225 150 510 1200 162 160 525 1000 1225 1350 175 40 160 260 350 450 TABLE 2 Time-Temperature Relationsnip.of 52 Moicing Material Using 30 Percent Retention of Elongation Temeer at ure Time
( g; (h,
'175 450 162 1350 150 3225 136 11600 TABLE 3 Aging Times anc Temperatures Needec To satisfy a A0 Year Life at 90*C Requirement Temeerature Time .
( c) (ni i
175 116 -
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- eda-5040 10/15/81 .
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ECR 500 10/15/51
- 10. REFEtfyCES 383-1974, "IEEE Standard for Type Test of Class (1) 1EEE Standard
' Electric Catics Field Splices, and Connections far Nuclear Powee Generation Stations." .
(2) 1EEE Stancard 323-1974, "!EEE Standar for Qualifyin; IE E wipment for Nu: lear Power Generating Stat sns."
(3) Rayche Laboratory Notebook 3980 307, 313, 314, 322
- Ray:nm Physical Test LaDor atory Notecooks i
i e
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I e
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4%
h 4
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4 1-i EDR $040 10/15/81 8
)- <
APPEND!'1 A
)
1 j LIST OF DAT A AC00151T10N EQUIPMENT
) .
MODEL NO. RAN*,!
d WG 5
_ERIAL-NO.
1N5tRU*ENT Honeyttil DB210735001 16303846/324- 0 300'C j Temperature Recorcer 162 i
i 1
- ----- . 5 LD.
- Instron (Calibration Instron --- -
i Weight)-
t
! Lee Corp. -.--- 7055 0 500*F j Indicating Pyrometer J
The instruments listec aoove we e calibrated against stancards. traceable i to the National Bureau of Stancards or an acceptable natural physical j stancare per MIL-1-45208A and MIL-C-45052A ,equirements.
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_ . . . _ , . _ . _ _ . ~ . _ . _ . . . , . . _ .