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| number = ML18019A494
| number = ML18019A494
| issue date = 11/21/1985
| issue date = 11/21/1985
| title = Test Rept on Electrical Separation Verification Testing for Cp&L for Use in Shearon Harris Nuclear Power Plant.
| title = Test Rept on Electrical Separation Verification Testing for CP&L for Use in Shearon Harris Nuclear Power Plant.
| author name =  
| author name =  
| author affiliation = WYLE LABORATORIES
| author affiliation = WYLE LABORATORIES
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:TEST REPORT ON ELECTRICAL SEPARATION VERIFICATION TESTING POR THE CAROLINA POWER AND LIGHT COMPANY POR USE ZN THE SHEARON HARRIS NUCX EAR POWER PLANT Por Carolina Power and Light Company Shearon Harris Nuclear Power Plant New Hill, North Carolina 27562 85i f 260458 851123.PDR ADOCH, 05000400, FDa
{{#Wiki_filter:TEST REPORT ON ELECTRICAL SEPARATION VERIFICATIONTESTING POR THE CAROLINA POWER AND LIGHT COMPANY POR USE ZN THE SHEARON HARRIS NUCX EAR POWER PLANT Por Carolina Power and Light Company Shearon Harris Nuclear Power Plant New Hill, North Carolina 27562 85i f 260458   851123.
: 0)
PDR   ADOCH, 05000400, FDa
Page No.ii Test Report No.47879-02 TABLE OF CONTENTS Section 1.0 CUSTOMER 2.0 TEST SPECIMEN" 3.0 ABSTRACT 4.0
 
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Page No.         ii Test Report No.           47879-02 TABLE OF CONTENTS Section                                                       Paae TEST REPORT


==SUMMARY==
==SUMMARY==


==5.0 REFERENCES==
1.0   CUSTOMER 2.0  TEST SPECIMEN    "
3.0  ABSTRACT 4.0 


TEST REPORT
==SUMMARY==
 
==5.0  REFERENCES==
 
6.0  TEST SPECIMEN DESCRIPTION TEST PROGRAM DESCRIPTION 7.1  Control Cable Screening Tests 7.2  Power Cable Screening Tests                          8 7.3  Configuration Number 1 Test                          10 7.4  Configuration Number 2 Test                          12 7.5  Configuration Number  3 Tests                      15 8.0  QUALITYASSURANCE                                          20 9.0  TEST EQUIPMENT AND INSTRUMENTATION                        20 TABLE I. TEST RESULTS


==SUMMARY==
==SUMMARY==
Paae 6.0 TEST SPECIMEN DESCRIPTION TEST PROGRAM DESCRIPTION 7.1 7.2 7.3 7.4 7.5 Control Cable Screening Tests Power Cable Screening Tests Configuration Number 1 Test Configuration Number 2 Test Configuration Number 3 Tests 8 10 12 15 8.0 QUALITY ASSURANCE 9.0 TEST EQUIPMENT AND INSTRUMENTATION TABLE I.TEST RESULTS
21 WYLE LABORATORIES Huntsville Facility


==SUMMARY==
Page No.         iii Test Report No.           47879-02 TABLE OF CONTENTS (Continued)
20 20 21 WYLE LABORATORIES Huntsville Facility Page No.iii Test Report No.47879-02 TABLE OF CONTENTS (Continued)
Section                                                                           Paae SECTION   I CONTROL CABLE SCREENING OF IGNITION CAPABILI'FYOF TEST'DETERMINAT1ON CONTROL CABLES IN A CABLE TRAY) 1.0   REQUIREMENTS 1.1   Acceptance Criteria 2.0   PROCEDURES 2.1 'est   Specimen Identification                                           I-2 2.2 Test Specimen Preparation                                               I-2 2.3 Instrumentation Setup                                                   I-3 2.4 Baseline Functional Tests                                               I-4 2.5 Overcurrent Test                                                       I-5 2.6 Post-Overcurrent Test Functional Test                                 I-6 3.0   RESULTS                                                                     I-7 APPENDIX I       Test Specimen Inspection Sheets                                 I-9 APPENDIX II     Instrumentation Equipment Sheets                                 I-13 APPENDIX III     Test Setup Photographs                                           I-17 APPENDIX IV     Control Cable Screening Test Setup Figure                       I-21 APPENDIX V       Individual Test Data                                             I-23 Control Cable Screening     Test   Nl                         I-25 Control Cable Screening     Test   N2                         I-35 Control Cable Screening     Test   03                         I-45 Control Cable Screening     Test   N4                         I-55 Control Cable Screening     Test   g5                         I-65 WYLE LABOAATORIES Huntsville Facility
Section Paae SECTION I-CONTROL CABLE SCREENING TEST'DETERMINAT1ON OF IGNITION CAPABILI'FY OF CONTROL CABLES IN A CABLE TRAY)1.0 REQUIREMENTS 1.1 Acceptance Criteria 2.0 PROCEDURES 2.1'est Specimen Identification 2.2 Test Specimen Preparation 2.3 Instrumentation Setup 2.4 Baseline Functional Tests 2.5 Overcurrent Test 2.6 Post-Overcurrent Test Functional Test 3.0 RESULTS APPENDIX I Test Specimen Inspection Sheets APPENDIX II Instrumentation Equipment Sheets APPENDIX III Test Setup Photographs APPENDIX IV Control Cable Screening Test Setup Figure APPENDIX V Individual Test Data Control Cable Screening Test Nl Control Cable Screening Test N2 Control Cable Screening Test 03 Control Cable Screening Test N4 Control Cable Screening Test g5 I-2 I-2 I-3 I-4 I-5 I-6 I-7 I-9 I-13 I-17 I-21 I-23 I-25 I-35 I-45 I-55 I-65 WYLE LABOAATORIES Huntsville Facility  
 
Page No.          iv Test Report No.          47879-02 TABLE OE CONTENTS (Continued)
Section                                                        ~Pa      e SECTION II POWER CABLE SCREENING TESTS (DETERMINATIONOP WORST CASE CABLE AND HORIZONTAL CABLE TRAY TO CONDUIT SEPARATION TEST) 1.0  REQUIREMENTS 1.1  Acceptance Criteria 2.0  PROCEDURES II-2'I-2 2.1  Test Specimen Preparation 2.2  Instrumentation Setup 2.3   Baseline Functional Tests                          II-4 2.4  Overcurrent Test                                    II-5 2.5  Post-Overcurrent Test Functional Test              lI-6
.,3.0  RESULTS APPENDIX I       Notice of Anomaly APPENDIX II      Test Setup Figure                            II-15 APPENDS III      Individual Test Data Power  Cable  Screening    Test      ¹1      H-19 Power  Cable  Screening    Test      ¹2      II-27 Power  Cable  Screening    Test      ¹3      11-35 Power  Cable  Screening    Test      ¹4      II-43 Power  Cable  Screening    Test      ¹5      II-53 WYLE LABORATORlES Huntsville Facility
 
Page No.          v Test Report No.          47879-02 TABLE OP CONTENTS (Continued)
Section                                                          Paae SECTION III CONFIGURATION NO. 1 TEST (FREE AIR SEPARATION WITHOUT BARRIERS) 1.0  REQUIREMEN'IS 1.1  Acceptance Criteria 2.0  PROCEDURES 2.1  Test Specimen Preparation 2.2  Instrumentation Setup 2.3  Baseline Functional Tests                            III-3 2.4  Overeurrent Test 2.5  Post-Overcurrent Test Functional Test                III-5 3.0  RESULTS                                                    III-6 APPENDIX I       Configuration Number-1 Test Data SECTION IV    CONFIGURATION NO. 2 TESTS (CONDUIT-TCH ONDUIT AND CABLE IN FREE AIR SEPARATION TES'IS) 1.0  REQUIREMENTS                                              IV-1 1.1 Acceptance Criteria 2.0  PROCEDURES                                                IV-2 2.1 Test Specimen Preparation                            IV-2 2.2 Instrumentation Setup 2.3 Baseline Functional Tests 2.4 Overeurrent Test                                      IV-6 2.5 Post-Overeurrent Test Functional Test 3.0  RESULTS                                                  IV-8 APPENDIX I       Configuration Number      2  Test No. 1 Data IV-11 APPENDIX II      Configuration Number      2 Test No. 2 Data IV-27 WYLE LABOAATOAIES Huntsville Facility


Page No.iv Test Report No.47879-02 TABLE OE CONTENTS (Continued)
Page No.         vi Test Report No.         47879-02 TABLE OF CONTENTS (Continued)
Section~Pa e SECTION II-POWER CABLE SCREENING TESTS (DETERMINATION OP WORST CASE CABLE AND HORIZONTAL CABLE TRAY TO CONDUIT SEPARATION TEST)1.0 REQUIREMENTS 1.1 Acceptance Criteria 2.0 PROCEDURES 2.1 Test Specimen Preparation 2.2 Instrumentation Setup 2.3 Baseline Functional Tests 2.4 Overcurrent Test 2.5 Post-Overcurrent Test Functional Test.,3.0 RESULTS APPENDIX I Notice of Anomaly APPENDIX II Test Setup Figure APPENDS III Individual Test Data Power Cable Screening Test¹1 Power Cable Screening Test¹2 Power Cable Screening Test¹3 Power Cable Screening Test¹4 Power Cable Screening Test¹5 II-2'I-2 II-4 II-5 lI-6 II-15 H-19 II-27 11-35 II-43 II-53WYLE LABORATORlES Huntsville Facility Page No.v Test Report No.47879-02 Section TABLE OP CONTENTS (Continued)
Section                                                         Paae SECTION V    CONFIGURATION NO. 3 TESTS (2-TRAY HORIZONTAL STACK WITH VERTICALTRAY AND CONDUITS OR FREE AIR SEPARATION TESTS) 1.0   REQUIREMENTS                                             V-1 1.1 Acceptance Criteria                                   V-1 2.0   PROCEDURES                                               V-2 2.1 Test Specimen Preparation                             V-2 2.2 Instrumentation Setup                                 V-3 2.3 Baseline Functional Tests 2.4 Overcurrent Test                                     V-10 2.5
SECTION III-CONFIGURATION NO.1 TEST (FREE AIR SEPARATION WITHOUT BARRIERS)Paae 1.0 REQUIREMEN'IS 1.1 Acceptance Criteria 2.0 PROCEDURES 2.1 Test Specimen Preparation 2.2 Instrumentation Setup 2.3 Baseline Functional Tests 2.4 Overeurrent Test 2.5 Post-Overcurrent Test Functional Test 3.0 RESULTS APPENDIX I Configuration Number-1 Test Data III-3 III-5 III-6 SECTION IV-CONFIGURATION NO.2 TESTS (CONDUIT-TCH ONDUIT AND CABLE IN FREE AIR SEPARATION TES'IS)1.0 REQUIREMENTS 1.1 Acceptance Criteria 2.0 PROCEDURES IV-1 IV-2 2.1 2.2 2.3 Test Specimen Preparation Instrumentation Setup Baseline Functional Tests IV-2 2.4 Overeurrent Test 2.5 Post-Overeurrent Test Functional Test 3.0 RESULTS APPENDIX I Configuration Number 2 Test No.1 Data APPENDIX II Configuration Number 2 Test No.2 Data IV-6 IV-8 IV-11 IV-27 WYLE LABOAATOAIES Huntsville Facility  
      ~  Post-Overcurrent Test Functional Test                 V-12 3.0
~    RESULTS                                                   V-12 APPENDIX I     Configuration Number 3, Test No.         1 Data V-15 APPENDIX II    Configuration Number 3, Test No.         2 Data V-33 APPENDIX III    Configuration Number 3, Test No.         3 Data V-53 SECTION VI  WYLE LABORATORIES TEST PROCEDURE NO. 47879-01, REVISION A WYLE LABORATORlES Huntsville Facility


Page No.vi Test Report No.47879-02 TABLE OF CONTENTS (Continued)
Test Report i.'s-REPORT NO.
Section SECTION V-CONFIGURATION NO.3 TESTS (2-TRAY HORIZONTAL STACK WITH VERTICAL TRAY AND CONDUITS OR FREE AIR SEPARATION TESTS)Paae 1.0 REQUIREMENTS 1.1 Acceptance Criteria 2.0 PROCEDURES V-1 V-1 V-2 2.1 Test Specimen Preparation 2.2 Instrumentation Setup 2.3 Baseline Functional Tests 2.4 Overcurrent Test 2.5 Post-Overcurrent Test Functional Test~~3.0 RESULTS APPENDIX I Configuration Number 3, Test No.1 Data APPENDIX II Configuration Number 3, Test No.2 Data APPENDIX III Configuration Number 3, Test No.3 Data V-2 V-3 V-10 V-12 V-12 V-15 V-33 V-53 SECTION VI-WYLE LABORATORIES TEST PROCEDURE NO.47879-01, REVISION A WYLE LABORATORlES Huntsville Facility
4?879-02
                                                                            '..tr,',.",c 47879 WYLE JOB NO.
CUSTOMER P. O. NO.
H-61740 E
                                                      ~~            r PAGE      10F                                          PAGE REPORT t        j DATE                        October 11, 1985 SPECIFICATION (S)
See References in Section 5.0.
1.0    CUSTOMER                            Carolina Power and Li ht Com an ADDRESS                              Shearon Harris Nuclear Power Plant New                              Hill NC            27562
    .0    TEST SPECIMEN                        Power, Control, and Instrumentation Cables as described in Paragraph 6.0
('3.0    ABSTRACT The test program described herein was conducted for Carolina Power and Light Company's Shearon Harris 5'uclear Power Plant to support compliance with Regulatory Guide 1.75, Revision 1, "Physical Independence of Electrical Systems", and with Section 5.1.1.2 of IEEE Standard 384-1974, "IEEE Trial-Use Criteria for Separation of Class 1E Equipment and Circuits", which allows the use of testing and analyses to justify separation of less than the spatial requirements of Sections 5.1.3 and 5.1.4 of IEEE Standard 384-1974.
(jmk) sTATE oF ALABAMA coUNTY oF MAolsoN
                                  )
i  *'eg. Alabama Professional Eng.
Gerald R. Carbonneau No. 13475 wyte shas have no riabiaty for damages or any trtnd to coneertrrenaat damages, PREPARED BY hom                  0>>
or property.inctrrrang special or o--S covered by this report
                                                                                                                                        .H              ne deposes and says: The Information contained In this report ls the result of complete and carefully conducted tests and Is to th        t of s knowledge true and correct In    APPROVED rtlptIs ecfs.                                                                                                                                      . ~ld-J 0-JP~              'O- -8 WYLE Q. A.
SUBS RIBED ~and sworn to
                        ~
fo    e thl            day of                      , tg                                                  ay          1g Notary    blic in and for the State of Alabama t large.
My Commission expires                      t3 LABORATORIES SCIENTIFIC SERVICES & SYSTEMS GROUP HUNTSVILLE, ALABAMA                    .-


i.'s-'..tr,',.",c
Page No.           2 Test Report No.           47879-02 4.0        
*~~r E t j WYLE JOB NO.CUSTOMER P.O.NO.47879 H-61740 PAGE 10F PAGE REPORT Test Report 4?879-02 REPORT NO.DATE October 11, 1985 SPECIFICATION (S)See References in Section 5.0.1.0 CUSTOMER ADDRESS.0 TEST SPECIMEN Carolina Power and Li ht Com an Shearon Harris Nuclear Power Plant New Hill NC 27562 Power, Control, and Instrumentation Cables as described in Paragraph 6.0 ('3.0 ABSTRACT The test program described herein was conducted for Carolina Power and Light Company's Shearon Harris 5'uclear Power Plant to support compliance with Regulatory Guide 1.75, Revision 1,"Physical Independence of Electrical Systems", and with Section 5.1.1.2 of IEEE Standard 384-1974,"IEEE Trial-Use Criteria for Separation of Class 1E Equipment and Circuits", which allows the use of testing and analyses to justify separation of less than the spatial requirements of Sections 5.1.3 and 5.1.4 of IEEE Standard 384-1974.sTATE oF ALABAMA)Alabama Professional Eng.coUNTY oF MAolsoN i*'eg.No.13475 Gerald R.Carbonneau deposes and says: The Information contained In this report ls the result of complete and carefully conducted tests and Is to th t of s knowledge true and correct In rtlptIs ecfs.SUBS RIBED and sworn to fo e thl , tg day of~~PREPARED BY APPROVED.H WYLE Q.A.ay wyte shas have no riabiaty for damages or any trtnd to coneertrrenaat damages, hom (jmk)or property.inctrrrang special or 0>>covered by this report o--S ne.~ld-J 0-JP~'O--8 1g Notary blic in and for the State of Alabama t large.My Commission expires t3 LABORATORIES SCIENTIFIC SERVICES&SYSTEMS GROUP HUNTSVILLE, ALABAMA.-
Page No.2 Test Report No.47879-02 4.0  


==SUMMARY==
==SUMMARY==
Prior to initiation of the testing phase of the program, Harris Plant Engineering Section (HPES)and Wyle Laboratories personnel developed Test Procedure 47879-01, Revision A (see Section VI).Selection of overcurrent conditions, test.configuratiops, tray fill, test initial conditions, and functional test are based on the following:
 
a)Overcurrent Condition-All test currents were based on failure of a circuits primary overcurrent protection, and are that current level just below the pickup setting (+1096 for power panel and motor control center circuits)of the circuits secondary overcurrent protection.
Prior to initiation of the testing phase of the program, Harris Plant Engineering Section (HPES) and Wyle Laboratories personnel developed Test Procedure 47879-01, Revision A (see Section VI). Selection of overcurrent conditions, test.configuratiops, tray fill, test initial conditions, and functional test are based on the following:
Test currents were conservatively maintained at a constant value as the circuits impedance increased due to conductor temperature-rise.b)ConQgurations
a)   Overcurrent Condition All test currents were based on failure of a circuits primary overcurrent protection, and are that current level just below the pickup setting (+1096 for power panel and motor control center circuits) of the circuits secondary overcurrent protection. Test currents were conservatively maintained at a constant value as the circuits impedance increased due to conductor temperature- rise.
-Test configurations were conservatively developed based on actual field installations.
b)   ConQgurations Test configurations were conservatively developed based on actual field installations. HPES/Wyle personnel developed test configurations after inspecting actual Shearon Harris Nuclear Power Plant (SHNPP) as-built conditions.
HPES/Wyle personnel developed test configurations after inspecting actual Shearon Harris Nuclear Power Plant (SHNPP)as-built conditions.
e)   Tray FiI1 Trays   were conservatively filled to the top of the side rails.
-e)Tray FiI1-Trays were conservatively filled to the top of the side rails.d)~Test Initia1 Conditions
d) ~
-Actual cable operating conditions were established prior to the fault current test by energizing the fault cable and several adjacent cables.e)Functional Tests-All functional tests were based on industry-accepted standards.
Test Initia1 Conditions Actual cable operating conditions were established prior to the fault current test by energizing the fault cable and several adjacent cables.
Visual inspections and temperature monitoring were also recorded and performed on all test specimens.
e)   Functional Tests   All functional tests were based on industry-accepted standards. Visual inspections and temperature monitoring were also recorded and performed on all test specimens.
f)Cables-All cables were from SHNPP stock.The results of the test program and the test procedure are detailed in the appropriate sections as listed below: e Section I o Section II~Section III Control Cable Screening Tests (Determination of ignition capability of control cables in a cable tray)Power Cable Screening Tests (Worst case cable determination and horizontal tray to parallel conduit)Configuration Number 1 Test (Free Air Separation Test without barriers)~Section IV Configuration Number 2 Tests (Conduit to Conduit and Cable in Free Air Tests)e Section V Configuration Number 3 Tests (2-Tray horizontal st ack with vertical tray, conduits and a free air cable)~Section VI Wyle Laboratories'est Procedure 47879-01, Revision A IN YI.E LABORATORIES Huntsville Facility Page No.3 Test Report No.47879-02  
f)   Cables All cables     were from SHNPP stock.
The results of the test program and the test procedure are detailed in the appropriate sections as listed below:
e     Section I     Control Cable Screening Tests (Determination                   of ignition capability of control cables in a cable tray) o    Section II    Power Cable Screening Tests (Worst case cable determination and horizontal tray to parallel conduit)
      ~    Section III  Configuration Number         1   Test (Free Air Separation Test without barriers)
      ~     Section IV   Configuration Number         2   Tests (Conduit to Conduit and Cable in Free Air Tests) e     Section V     Configuration     Number       3     Tests   (2-Tray horizontal st ack with vertical tray, conduits and         a free air cable)
      ~     Section VI   Wyle Laboratories'est Procedure 47879-01, Revision A INYI.E LABORATORIES Huntsville Facility
 
Page No.         3 Test Report No.             47879-02


==SUMMARY==
==SUMMARY==
(Continued)
(Continued)
Each of the configuration tests was conducted in the following sequence: 'a Baseline Functional Tests Overcurrent Test Post-Overcurrent Test Functional Tests One anomaly occurred during this test program.This anomaly is discussed briefly below and in more detail in Section II of this report.Notice of Anomaly No.Date Desc tion08/30/85 Documents the failure of the Twisted Pair 16 AWG target cable during the Post-Overcurrent Test Functional Tests for Power Cable Screening Test Number 4.This cable was installed inside a 1-inch rigid steel conduit mounted 1 inch above the faulted Triplex 4/0 AWG cable.The fault cable ignited and the target cable was exposed to temperatures of 644.8oF inside the conduit.It was judged that 1-inch vertical separation was inadequate physical independence, and the remaining Power Cable Screening Tests were conducted successfully using 12-inch vertical separation.
Each of the configuration tests   was'a conducted in the         following sequence:
5.1 5.2 Wyle Laboratories Technical Proposal for Cable Separation Test Program for Carolina Power and Light Company, No.543/3737/GH.
Baseline Functional Tests Overcurrent Test Post-Overcurrent Test Functional Tests One anomaly occurred during this test program. This anomaly is discussed briefly below and in more detail in Section II of this report.
Wyle Laboratories'est Procedure 47879-01, Revision A,"Electrical Raceway Separation Verification Testing for the Carolina Power and Light for use in the Shearon Harris Nuclear Power Plant".5.3 5.4 IEEE Std.383-1974,"IEEE Standard for Type Test of Class lE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations." IEEE Std.384-1974,"IEEE Trial Use Standard Criteria for Separation of Class 1E Equipment and Circuits." 5.5 5.6 United States Nuclear Regulatory Commission Guide 1.?5, Revision 1,"Physical Independence of Electric Systems." IEEE Std.323-1974,"IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations." 5.7 Code of Federal Regulations, Section 10, Part 21.Code of Federal Regulations, Section 10, Part 50, Appendix B.WYLE LABORATORIES Huntsville Facility Page No.4 Test Report No.47879-02 6.0 TEST SPECIMEN DESCRIPTION All cables used in this test program were qualified to meet the requirements of IEEE Standard 383-1974,"IEEE Standard for Type Test of Class 1E Electrical Cables, Field Splices, and Connections for Nuclear Power Generating Stations".
Notice of Anomaly No.         Date                                             Desc   tion 08/30/85       Documents the failure of the Twisted Pair 16 AWG target cable during the Post-Overcurrent Test Functional Tests for Power Cable Screening Test Number 4. This cable was installed inside a 1-inch rigid steel conduit mounted 1 inch above the faulted Triplex 4/0 AWG cable. The fault cable ignited and the target cable was exposed to temperatures of 644.8oF inside the conduit. It was judged that 1-inch vertical separation was inadequate physical independence, and the remaining Power Cable Screening Tests were conducted successfully using 12-inch vertical separation.
The test specimens consisted of the following cables instaQed into the various configurations as described in Sections I through V of this report and were provided to Wyle Laboratories from Shearon Harris Nuclear Power Plant stock.Item No.10 11 12 Desc tion 1/C 500 MCM Triplex 350 MCM Triplex 4/0 AWG 1/C 2 AWG 1/C 6 AWG 1/C 10 AWG 1/C 6 AWG 1/C 10 AWG 2/C 10 AWG 2/C 12 AWG 2/C 16 AWG 1 Pair 16 AWG Cable*P P P P P P C C C C C L COL B/M*+'25-11 D25-10 D25-08 D25-05 D25-03 D25-01 D59-03 D59-02 D50-01 D50-06 D50-11 D60-01 P-Power Type Cable C-Control Type Cable L--Low Energy Type Cable B/M-Bill of iMaterials Number WYLE LABORATORIES Huntsville Facility Page No.5 Test Report No.47879-02 Ve1 TEST PROGRAM DESCRIPTION-Control Cable Screening Tests V J.J.'urpose The purposes of these tests were to: 1.Demonstrate that the worst case electrical fault, in a control cable tray, does not have the potential to support combustion or have the capability to generate enough heat to adversely affect the operation of any cabling located 1 inch or more from a faulted cable in a control tray prior to open-circuiting and thus separation distances less than those specified in IEEE Standard 384-1974 and Nuclear Regulatory Guide 1.75 are acceptable.
5.1         Wyle Laboratories Technical Proposal for Cable Separation Test Program for Carolina Power and Light Company, No. 543/3737/GH.
2.Demonstrate the adequacy of'esign where a cable/raceway of one safety division is located within 1 inch of a.faulted NNS control cable, or a control cable of a redundant safety division, in a tray.The Control Cable Screening Tests consisted of five tests to determine the ignition and heat eration capability of control-type cables in a filled ladder rung.cable tray.The fault was mounted as the top centerline cable in the tray.A 1-inch rigid steel conduit, with misted Pair 16 AWG target cable, and three thermocouple arrays were mounted 1 inch vertically above the faulted cable.The cables tested and the currents-applied in the Control Cable Screening Tests were as.follows: Test No.Cable Size 2/C 16 AWG 2/C 12 AWG 2/C 10 AWG 3-1/C 10 AWG 3-1/C 6 AWG Warm Currents*18A, 25A 30A, 41A 40A, 50A 40A, SOA VSA, VSA Pault Current 139A Initially**'80A 180A 180A 180A Initial warmup current and current at 90oC+SoC conductor temperature.
5.2          Wyle Laboratories'est Procedure 47879-01, Revision A, "Electrical Raceway Separation Verification Testing for the Carolina Power and Light for use in the Shearon Harris Nuclear Power Plant".
See Paragraph 3.0, Table I, Note 1 on Page I-7.WYLE LABORATORIES Huntsville Facility Page No.6 Test Report No.47879-02 7.0 TEST PROGRAM DESCRIPTION (Continued) 7.1'ontrol Cable Screening Tests (Continued) 7.1.3'esulte The results of the five Control Cable Screening Tests are briefly summarized in the following table: Test No.Fault Cable Size Maximum Fault Maximum Temp.Cable Jacket Tem.1 Inch Above TIIne To en Circuit*5 2/C 16 AWG 2/C 12 AWG 2/C 10 AWG 3-1/C 10 AWG 3-1/C 6 AWG 409.4oF 519.1oF 672.9oF 963.4oF 934.4oF 128.5oF 128.0oF 172.6oF 231.8 F 219.1'F 55.12 sec 118.15 sec (1)324.4 sec (2)After application of fault current to the fault cable.Notes: (1)Fault cable did not open-circuit.
5.3         IEEE Std. 383-1974, "IEEE Standard for Type Test of Class lE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations."
After approximately 358 seconds, the conductors shorted together and the temperature then dropped from 1464.3oF to 317.3oF.This test was terminated at the customer's request after 767.75 seconds (12.8 minutes).Based on the results of the previous tests, which did open-circuit, the conductor temperatures recorded indicated that the fault cable was on the verge of open-circuiting.
5.4        IEEE Std. 384-1974, "IEEE Trial Use Standard Criteria for Separation of Class 1E Equipment and Circuits."
(2)Fault cable did not open-circuit.
5.5         United States Nuclear Regulatory Commission Guide 1.?5, Revision 1, "Physical Independence of Electric Systems."
This test was terminated after the heat-up rate fell to less than 10 F in 15 minutes (from an initial heatup rate of 18 F per minute)which indicates that steady-state conditions had effectively been reached.Total duration, with 180 amperes applied, was'10,802.32 seconds (3 hours).There were no ignitions inside the cable tray area during any of the Control Cable Screening Tests.WYLE LABORATORIES Huntsville Facility Page No.7 Test Report No.47879-02 TEST PROGRAM DESCRIPTION (Continued)
5.6        IEEE Std. 323-1974, "IEEE Standard                 for Qualifying Class lE Equipment for Nuclear Power Generating Stations."
Control Cable Screening Tests (Continued) 7.1.4 Conclusions The above results generated the following conclusions:
5.7         Code   of Federal Regulations, Section         10, Part 21.
The acceptability of design was demonstrated where a rigid steel conduit passes 1 inch vertically above and parallel to a faulted control cable in a cable tray when the worst case electrical fault occurred in the cable tray.The maximum observed temperature to the jacket of the Twisted Pair 16 AWG cable inside the 1-inch rigid steel conduit was 185.8oF (Test No.4)which is below the rated temperature of the cables insulation system (90oC).2.The amount of heat released to the environment by a faulted control-type cable, at the Shearon Harris Nuclear Power Plant, is not capable of adversely affecting the operation of cabling located 1 inch or greater away during electrical fault conditions.
Code   of Federal Regulations, Section         10, Part 50, Appendix B.
Therefore, the spatial separation distances of IEEE 384-1974 can be reduced between control-type raceways/cable.
WYLE LABORATORIES Huntsville Facility
The tested configuration demonstrated that separation distances of one inch or greater are adequate.It was demonstrated that the worst case electrical fault, in a control-type tray, does not generate sufficient heat to cause ignition of a faulted cable's insulation system., Therefore, configuration testing was not required.WYLE LABORATORIES Huntsville Faclllty Page No.8 Test Report No.47879-02 7.0 TEST PROGRAM DESCRIPTION (Continued) 7.2 Power Cable Screening Tests 7.2.1 Purpose The purposes of these tests were to: 1.Determine the worst case electrical fault and cable size.This worst case cable was based on a combination of time to ignition, insulation burn time, and observed temperatures.
 
Once the worst-case cable was determined, this cable was used as the faulted cable in all subsequent configuration tests.2.Demonstrate the adequacy of design where a 1-inch conduit runs parallel to and 1 inch above a faulted cable in a power-type cable tray.(Subsequent to failure during Test No.4, which was run out of sequence at the customer's request, the separation distance was revised to 12 inches vertically.)
Page No.           4 Test Report No.           47879-02 6.0         TEST SPECIMEN DESCRIPTION All cables used in this test program were qualified to meet the requirements of IEEE Standard 383-1974, "IEEE Standard for Type Test of Class 1E Electrical Cables, Field Splices, and Connections for Nuclear Power Generating Stations". The test specimens consisted of the following cables instaQed into the various configurations as described in Sections I through V of this report and were provided to Wyle Laboratories from Shearon Harris Nuclear Power Plant stock.
The Power Cable Screening Tests consisted of six tests between a faulted power-type cabl and a 1-inch rigid steel conduit mounted above the faulted cable.The conduit was mount 12 inches above the fault cable for Tests No.1, 2, 3, 5 and 6, and 1 inch above the fau'cable for Test No.4.,The cables tested and the currents applied in the Power Cable Screening Tests were as" follows: Test No.Cable Size 3-1/C 10 AWG 3-1/C 6 AWG 3-1/C 2 A WG Triplex 4/0 AWG Triplex 350 iMCM 3-1/C 500 MCM Warm Currents*40A, 50A 75A, 75A 130A, 130A 260A, 285A 350A, 370A 430A, 476A Pault Current 620 A Initially**
Cable*      COL Item No.                   Desc       tion B/M*+'25-11 1/C 500 MCM                   P Triplex 350 MCM                   P    D25-10 Triplex 4/0 AWG                   P    D25-08 1/C 2 AWG                   P    D25-05 1/C 6 AWG                   P    D25-03 1/C 10 AWG                   P    D25-01 1/C 6 AWG                   C    D59-03 1/C 10 AWG                   C    D59-02 2/C 10 AWG                   C    D50-01 10                  2/C 12 AWG                     C     D50-06 11                  2/C 16 AWG                     C    D50-11 12                  1 Pair 16 AWG                   L    D60-01 P    Power Type Cable C   Control Type Cable L   -- Low Energy  Type Cable B/M Bill of iMaterials  Number WYLE LABORATORIES Huntsville Facility
704A 704A 4200A 4200A 4200A Initial warmup current and current at 90oC+SoC conductor temperature.
 
See Paragraph 3.0, Table I, Note 1 on Page II-7.WYLE LABORATORIES Huntsville Facility Page No.9 Test Report No.47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.2 7.2.3 Power Cable Screening Tests (Continued)
Page No.          5 Test Report No.          47879-02 TEST PROGRAM DESCRIPTION-Ve1          Control Cable Screening Tests VJ.J.'urpose The purposes of these tests were to:
Results The results of the six Power Cable Screening Tests are briefly summarized in the following table: Maximum Temperature Test Fault Cable-Fault Target Time to Insulation No.Size Cable Cable ltutition Burn Time 1 3-1/C 10 AWG 1136.2cF'08.1cF 160 sec 1 min 2 3-1/C 6 A WG 1060.7oF 99.0oF None N/A 3 3-1/C 2 AWG 2141.5oF 166.5oF 410 sec 9 min 4 Triplex 4/0 AWG 1673.4oF 644.8oF 83 sec 8 min 5 Triplex 350 MCM 1600.3oF 251.6oF 154 sec 7 min, 6'-1/C 500 MCM 1534.0oF 210.1oF-441 sec 6 min After application of fault current to the fault cable.Notes: (1)Fault cable conductor shorted together after 10 seconds.(2)Fault cable conductors shorted together after 338 seconds.(3)-1-inch conduit mounted 1 inch above fault cable for'this test (4)Fault cable conductors shorted together after 320 seconds.Time-to Open*Circuit 160.64 sec (1)105.7 sec 598.0 sec (2)93.0 sec (3)183.25 sec 459.07 sec (4)only.7'.2.'4 Conclusions The above results generated the following conclusions:
: 1. Demonstrate that the worst case electrical fault, in a control cable tray, does not have the potential to support combustion or have the capability to generate enough heat to adversely affect the operation of any cabling located 1 inch or more from a faulted cable in a control tray prior to open-circuiting and thus separation distances less than those specified in IEEE Standard 384-1974 and Nuclear Regulatory Guide 1.75 are acceptable.
The Triplex 350 MCM cable was selected as the worst case cable.This selection was based on the fact that the Triplex 4/0 AWG and the Triplex 350 MCiM generated similar jacket temperatures and insulation burn times.However, the Triplex 350 MCM sustained the fault current for a longer period of time and visually was a more violent fire than either the Triplex 4/0 AWG cable or the 3-1/C 500 MCM cable.2.3.The acceptability of design where a 1-inch rigid steel conduit is mounted 1 inch above a faulted power cable was not demonstrated by these tests.The size of the fire and the intensity of the heat generated during the electrical fault for Test No.4 severely damaged the target cable in the 1-inch rigid steel conduit.(See Notice of Anomaly No.1 in Section lI of this report.)Consequently, this cable did not possess sufficient integrity to pass the Post-Overcurrent Test Functional Tests.The acceptability of design where a 1-inch rigid steel conduit is mounted 12 inches above a faulted power cable tray was demonstrated by Tests 1, 2, 3, 5, and 6.During these tests, the maximum observed jacket temperature was 251.6oF (Test No.5).There was no visible damage to the Twisted Pair 16 AWG target cable, and the target cable passed the Post-Overcurrent Test Functional Tests.WYLE LABORATORIES Huntsville Facility Page No.10 Test Report No.4VSV9-02 V.O TEST PROGRAM'DESCRIPTION (Continued)
: 2. Demonstrate the adequacy of'esign where a cable/raceway of one safety division is located within 1 inch of a. faulted NNS control cable, or a control cable of a redundant safety division, in a tray.
V;3 ConQguration Number 1 Test Configuration Number 1 Test consisted of a test between a free air faulted Triplex 350 MCM cable and a free air Twisted Pair 16 AWG'arget cable separated by 6 inches horizontally.
The Control Cable Screening Tests consisted of five tests to determine the ignition and heat eration capability of control-type cables in a filled ladder rung. cable tray. The fault was mounted as the top centerline cable in the tray. A 1-inch rigid steel conduit, with misted Pair 16 AWG target cable, and three thermocouple arrays were mounted 1 inch vertically above the faulted cable.
V.3.1 Purpose The purpose of the Configuration Number 1 Test was to demonstrate the acceptability of design where two cables in free air pass 6 inches horizontally from each other when the worst case electrical fault occurs-to one of these cables.This configuration represents field installation of free air cables going from: a..Tray to tray b..Tray to conduit c.Conduit to conduit.d.Tray/conduit to equipment..The cables tested and electrical powering were as follows: Cable Size Function Location Powe Triplex 350 MCM Fault Cable Twisted Pair 16 AWG Target Cable Free Air-Free Air 350A, 510A, 4200A*50 VAC, 1A Initial Warmup Current, Final Warmup Current, and Fault Current.V.3.3 Results The results of the Configuration Number 1 Test are briefly summarized in the following table: Cable Size Triplex 350 MCM Function Location Fault Cable Free Air Twisted Pair 16AWG Target Cable Free Air Maximum Jacket Tem.1489.6oF 580 3oF Time to Ignition: Time to Open Circuit: 105 seconds at 4200A 148.29 seconds at 4200A WYLE LABOAATOAIKS Huntsville Facility Page No.11 Test Report No.47879-02 7.3 TEST PROGRAM DESCRIPTlON (Continued)
The cables tested and the currents- applied in the Control Cable Screening Tests were as
Configuration Number 1 Test (Continued) 7.3.4 Conclusions These results generated the conclusion that the Twisted Pair 16 AWG target cable possessed sufficient integrity to continue to conduct 1 ampere at 50 VAC throughout this test and to successfully complete the Post-Overcurrent Test Functional Tests.Therefore, the cable met the established test acceptance criteria.However, the jacket was scorched in several locations from exposure to the flames from the fault cable.Thus, it was.decided that the 6-inch horizontal separation was not adequate and a free air separation of 12 inches was evaluated during Configuration No.3, Test 3 (see Paragraph 7.5.4).WYLE LASORATORIES Huntsville Fcclllty Page No.12 Test Report No.47879-02 V.O TEST PROGRAM DESCRIPTION (Continued) 7.4'onQguration Number-2.Test Configuration Number 2 consisted of two tests between a free air cable, a cable in rigid steel conduit, and a cable in flexible conduit.The faulted Triplex 350 MCM cable was in free air for Test No.1 and the separation was 6 inches verticaQy to the conduits.The faulted Triplex 350 MCM was inside the flexible conduit for Test No.2 and the separation was 1 inch to the free air and rigid steel conduit.V.4J.Pur~se The purposes of the Configuration Number 2 Tests were to: 1., Demonstrate the acceptabiTity of design where a free air cable, a rigid steel conduit, and a flexible steel conduit are separated by 6 inches vertically when the worst case electrical fault occurs to the free air cable.2.Demonstrate the acceptability of design where a free air cable, a rigid steel conduit, and a flexible steel conduit are separated by 1 inch when the worst case electrical fault occurs to the cable inside the flexible steel conduit.-':-V.4.2 Descr tion The cables tested and the electrical powering were as follows: ,'7.4;2J.Test No.1 Cable Size Triplex 350 MCM 2/C 16 AWG Function'ault Cable Target Cable Location Free Air 1" Flexible Steel Conduit Power 350A, 505A, 4200A*50 VAC, 1A 3-1/C'10 A WG Target Cable 1" Flexible Steel Conduit 480 VAC, 40A Initial Warmup Current, Final Warmup Current, and Fault Current.WYLE LABORATORIES Huntsville Facility Page No.13 Test Report No.47879-02 7.4 7.4.2.2 TEST PROGRAM DESCRIPTION (Continued)
.follows:
ConQguration-Number 2 Test (Continued)
Test No.           Cable Size         Warm          Currents*        Pault Current 2/C 16 AWG                   18A, 25A                    139A    Initially**'80A 2/C 12 AWG                   30A, 41A 2/C 10 AWG                 40A, 50A                      180A 3-1/C 10 AWG                 40A, SOA                      180A 3-1/C 6 AWG                   VSA, VSA                     180A Initial warmup current   and current   at 90oC       +SoC conductor temperature.
Test No.2.Cable Size Triplex 350 MCM Function Fault Cable Location 4" Flexible Conduit Power 350A, 425A, 4200A*2/C 16 AWG Target Cable 1" Rigid Steel Conduit 50 VAC, 1A 3-1/C 10 AWG Target Cable Free Air 480 VAC, 40A Initial Warmup Current, Final Warmup Current, and Fault Current.V.4.3 Results The results of these tests are briefly summarized in the following tables.Test No.1 Cable Size Triplex 350 MCM 2/C 16 AWG Function Fault Cable Lccaticu Free Air Target Cable 1" Flexible Steel Conduit Maximum Temperatures Jacket Conduit 1312.3oF N/A 751.7 F 777.6 F 3-1/C 10 AWG Target Cable 1" Rigid Steel Conduit 490 6oF 719 4oF Time to Ignition: Time to Open Circuit: 126 seconds at 4200A 167.57 seconds at 4200A WYLE LABORATORlES Huntsville Facility Page No.14 Test Report No.47879-02 V.O 7.4 7.4.3 TEST PROGRAM DESCRIPTION (Continued)
See Paragraph 3.0, Table   I, Note 1 on Page I-7.
ConQguration Number 2 Test (Continued)
WYLE LABORATORIES Huntsville Facility
Results (Continued) 7.'4.3.2 Test No.2 Cable Size Function Location Maximum Temperatures Jacket Conduit Triplex 350 MCM Fault Cable 4" Flexible Steel Conduit 1593 9oF 509.5oF 2/C 16 AWG Target Cable 1" Rigid Steel Conduit 131.6 F 141.0 F 3-1/C 10 AWG Target Cable Free Air 169.8oF N/A Time to Ignition: Time to Open Circuit: None 231.63 seconds at 4200A 7.4.4 Conclusions The above results generated the following conclusions:
 
1.The acceptability of design was demonstrated where a free air cable, a 1-inch flexible steel conduit, and a 1-inch rigid steel conduit are mounted 6 inches apart when the worst case electrical fault occurs to the free air cable.During this test, relatively high temperatures were observed inside the flexible steel and rigid steel conduits (751.V F and 490.6 F, respectively).
Page No.           6 Test Report No.           47879-02 7.0         TEST PROGRAM DESCRIPTION (Continued) 7.1'ontrol Cable Screening Tests             (Continued) 7.1.3'esulte The results   of the five Control Cable Screening Tests are briefly summarized in the following table:
However, damage to the target cables was limited to the jackets only.In addition, both cables possessed sufficient integrity to successfully maintain continuity of power and to complete the Post-Overcurrent Test Functional Tests.Due to the high temperatures observed on the target cable jackets, this separation distance will not be permitted, without interposing barriers, in design at the Shearon Harris Nuclear Power Plant.2.The acceptability of design was demonstrated where a free air cable, a 1-inch rigid steel conduit, and a 4-inch flexible steel conduit are mounted 1 inch apart, when the worst case electrical fault occurs inside the flexible steel conduit.The flexible steel conduit acted as an effective thermal barrier and suppressed the ignition of the Triplex 350 MCM fault cable.WYLE LABORATORIES Huntsville Facility Page No.15 Test Report No.47879-02 7.'5 TEST PROGRAM DESCRIPTION (Continued)
Maximum Fault              Maximum Temp. TIIne To Test No.         Fault Cable Size     Cable Jacket Tem .           1 Inch Above en Circuit*
Configuration Number 3 Tests Configuration Number 3 consisted of three tests between two horizontal trays, a vertical tray, a parallel conduit or free air cable, and a perpendicular conduit.The horizontal trays were separated by 36 inches vertically and the vertical tray was separated by 12 inches horizontally.
2/C 16 AWG                 409.4oF                  128.5oF    55.12 sec 2/C 12 AWG                 519.1oF                  128.0oF  118.15 sec 2/C 10 AWG                 672.9oF                  172.6oF        (1) 3-1/C 10 AWG                 963.4oF                  231.8 F  324.4 sec 5            3-1/C 6 AWG                 934.4oF                   219.1'F       (2)
The faulted Triplex 350 MCM cable was in the upper horizontal tray for Test No.1, the lower horizontal tray for Test No.2, and the vertical tray for Test No.3.7.5.1 Purpose The purposes of the Configuration Number 3 tests were to: 1.Demonstrate the acceptability of design where three horizontal cable trays are separated by 36 inches{from the top of one tray to the bottom of the next tray)when the worst case electrical fault occurs in either cable tray.*2.Demonstrate the acceptability of design where a horizontal cable tray passes 12 inches from a vertical cable tray when the worst case electrical fault occurs in either tray.3.Demonstrate the acceptability of design where a 1-inch rigid steel conduit passes: 1)1 inch below and perpendicular to a faulted cable in a ladder rung cable tray, or 2)1 inch horizontaQy away from and parallel to the siderail wall of a ladder rung cable tray, or 3)1 inch horizontally away from and perpendicular to the siderail wall of a ladder rung cable tray.4.Demonstrate the acceptability of design where a free air cable passes 12 inches horizontally away from and parallel to a faulted cable in a ladder rung cable tray when the worst case electrical fault occurs in the cable tray.WYLE LABORATORlKS Muntsvllle Facility Page No.16 Test Report No.4V8V9-02 V.D TEST PROGRAM DESCRIPTION (Continued)
After application of fault current to the fault cable.
V.5 Configuration Number 3 Tests.(Continued)
Notes:
The cables tested and the electrical powering were as follows: V.5.2.1 Test No.I Cable Size Triplex 350 MCM Punction Fault Cable Location Povrerin Upper Horizontal 350A, 415A, 4200A*Tray 3-1/C 10 AWG 2/C'16 AWG 2/C 16 AWG Target Cable Vertical Tray Target Cable Perpendicular Conduit-Below Upper Tray Target Cable Parallel Conduit 480 VAC, 40A 120 VAC, 10A 120 VAC, 10A Initial Warmup Current, Final Warmup Current, and Fault Current.V.5.2.2.Test No.2 Cable Size Triplex 350 MCM 3-1/C 10 AWG Punction Fault Cable Target Cable Location Powerin Lower Horizontal 350A, 440A, 4200A*-Tray Upper Horizontal 480 VAC, 40A Tray 3-1/C 10 AWG 2/C 16 AWG 2/C 16 AWG Target Cable Vertical Tray Target Cable Perpendicular Conduit Target Cable Parallel Conduit 480 VAC, 40A 120 VAC, 10A 120 VAC, 10A Initial Warmup Current, Final Warmup Current, and Fault Current.WYLF.LASOAATOAIES Huntsville Facility Page No.17 Test Report No.47879-02 7.5 TEST PROGRAM DESCRIPTION (Continued)
(1) Fault cable did not open-circuit.             After approximately 358 seconds, the conductors shorted together and the temperature then dropped from 1464.3oF to 317.3oF. This test was terminated at the customer's request after 767.75 seconds (12.8 minutes). Based on the results of the previous tests, which did open-circuit, the conductor temperatures recorded indicated that the fault cable was on the verge of open-circuiting.
ConQguration Number 3 Tests (Continued) 7.5;2.3 Test No..3 Cable Size Function Location-Powerin Triplex 350 MCM 3-1/C 10 AWG 3-1/C 10 AWG Fault Cable Vertical Tray 350A, 465A, 4200A~Target'Cable Upper Horizontal 480 VAC, 40A Tray Target Cable Lower Horizontal 480 VAC, 40A Tray 2/C 16 AWG Target Cable Parallel Free-Air 120 VAC, 10A Initial Warmup Current, Final Warmup Current, and Fault Current.V.'5.3 Results'results from the three Configuration Number 3 Tests are briefly summarized in the wing tables.7.5.3Z Test No.1 Cable Size Triplex 350 MCM Function Location Maximum Temperatures
(2) Fault cable did not open-circuit. This test was terminated after the heat-up rate fell to less than 10 F in 15 minutes (from an initial heatup rate of 18 F per minute) which indicates that steady-state conditions had effectively been reached. Total duration, with 180 amperes applied, was'10,802.32 seconds (3 hours).
~Ci l7 Fault Cable Upper Horizontal 1554.4oF N/A Tray 3-1/C 10 AWG 2/C 16 AWG 2/C 16 AWG Time to Ignition: Time to Open Circuit: Target Cable Parallel Conduit Target Cable Perpendicular Conduit-Below Upper Tray 183 seconds at 4200A 266.13 seconds at 4200A Target Cable Vertical Tray 202.1 F 154.3oF 365.4 F 454.2oF 262.3oF 415.7oF WYLE LASORATORIES Huntsville Facility Page No.18 Test Report No.*47879-02 7.0 TEST PROGRAM DESCRIPTION (Continued) 7.5, ConQguration Number 3 Tests (Continued) 7.54.2, Test No.2 Cable Size Function Location Maximum Temperatures
There were no ignitions inside the cable tray area during any of the Control Cable Screening Tests.
~PI Triplex 350 MCM 3-1/C 10 AWG 3-1/C 10 AWG 2/C 16 AWG 2/C 16 AWG Time to Ignition: Time to Open Circuit: Target Cable Target Cable Target Cable Perpendicular Conduit 160 seconds at 4200A 223.98 seconds at 4200A Fault Cable Lower Horizontal Tray Target Cable Upper Horizontal Tray Vertical Tray Parallel Conduit 1372.4oF 942.4oF 236.2oP 378.7oP 203.7oP N/A 223.9oF 382.9op 248.5 F 539.9 F , 7.5.3.3 Test No.3 Cable Size Triplex 350 MCM 3-1/C 10 AWG 3-1/C 10 AWG 2/C 16 AWG Time to Ignition: Time to Open Circuit: Fault Cable Target Cable Target Cable Target Cable Vertical Tray Upper Horizontal Tray Lower Horizontal Tray Free Air 193 seconds at 4200A 201.16 seconds at 4200A Function Loeatim Maximum Temperatures k~M~/~1514.7oF N/A 132.4oF 135.8op 133.0oF 130.7 P 166.4oP N/A WYLE LABORATORIES Huntsville Facility Page No.19 Test Report No.47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.5'onfiguration Number 3 Tests (Continued) 7.5.4.Conclusions The above results generated the following conclusions:
WYLE LABORATORIES Huntsville Facility
The acceptability of design was demonstrated for the following physical separation distances:
 
2.36-inch-vertical separation between two ladder rung cable trays with the worst case electrical fault.in either tray.12-inch horizontal separation between a vertical and a horizontal cable-tray with the worst electrical fault in either tray;3'.4,.1-inch horizontal separation between the siderail walls of a horizontal tray and a 1-inch rigid steel conduit when the worst case electrical fault occurs in the tray.1-inch vertical separation between a ladder rung cable tray and a perpendicular 1-inch conduit below the tray when the worst case electrical fault occurs in the tray..1-inch horizontal separation between a horizontal ladder rung cable tray and a perpendicular vertical 1-inch rigid steel conduit when the worst case electrical fault'occurs in the tray.6.-12-inch horizontal separation between a vertical free air cable parallel to a vertical ladder rung cable tray when the worst case electrical fault occurs in the tray.WYLE LABORATORIES Huntsville Facility Page No.20 Test Report No.47879-02 8.0 QUALITY ASSURANCE All work performed on this test.program was done in accordance with Wyle Laboratories'uality Assurance Program, which complies with the applicable requirements of 10 CFR 50, Appendix B;ANSI N45.2', and the"daughter" standards.
Page No.           7 Test Report No.           47879-02 TEST PROGRAM DESCRIPTION (Continued)
Defects are reported in accordance with the requirements of 10 CFR Part 21.9.0 TEST EQUIPMENT AND INSTRUMENTATION All.instrumentation, measuring, and test equipment used in the performance of this test program were calibrated in accordance with Wyle Laboratories Quality Assurance Program, which complies with the requirements of Military Specification MIL-STD-45662.
Control Cable Screening Tests (Continued) 7.1.4     Conclusions The above results generated the following conclusions:
Standards used in performing all calibrations are traceable to the National Bureau of Standards by report number and date.When no national standards exist, the standards are traceable to international standards or the basis for calibration is otherwise documented.
The acceptability of design was demonstrated where a rigid steel conduit passes 1 inch vertically above and parallel to a faulted control cable in a cable tray when the worst case electrical fault occurred in the cable tray. The maximum observed temperature to the jacket of the Twisted Pair 16 AWG cable inside the 1-inch rigid steel conduit was 185.8oF (Test No. 4) which is below the rated temperature of the cables insulation system (90oC).
WY1E LABORATORlFS Huntsville Facility Page No.21 Test Report No.47879-02 TABLE L TEST RESULTS  
: 2. The amount of heat released to the environment by a faulted control-type cable, at the Shearon Harris Nuclear Power Plant, is not capable of adversely affecting the operation of cabling located 1 inch or greater away during electrical fault conditions. Therefore, the spatial separation distances of IEEE 384-1974 can be reduced between control-type raceways/cable.             The tested configuration demonstrated that separation distances of one inch or greater are adequate.
It was demonstrated that the worst case electrical fault, in a control-type tray, does not generate sufficient heat to cause ignition of a faulted cable's insulation system., Therefore, configuration testing was not required.
WYLE LABORATORIES Huntsville Faclllty
 
Page No.           8 Test Report No.           47879-02 7.0         TEST PROGRAM DESCRIPTION (Continued) 7.2         Power Cable Screening Tests 7.2.1       Purpose The purposes of these tests were to:
: 1. Determine the worst case electrical fault and cable size. This worst case cable was based on a combination of time to ignition, insulation burn time, and observed temperatures.
Once the worst-case cable was determined, this cable was used as the faulted cable in all subsequent configuration tests.
: 2. Demonstrate the adequacy of design where a 1-inch conduit runs parallel to and 1 inch above a faulted cable in a power-type cable tray. (Subsequent to failure during Test No. 4, which was run out of sequence at the customer's request, the separation distance was revised to 12 inches vertically.)
The Power Cable Screening Tests consisted of six tests between a faulted power-type cabl and a 1-inch rigid steel conduit mounted above the faulted cable. The conduit was mount 12 inches above the fault cable for Tests No. 1, 2, 3, 5 and 6, and 1 inch above the fau
'cable for Test No. 4.
  ,The cables   tested and the currents applied in the Power Cable Screening Tests were as follows:
Test No.           Cable Size         Warm          Currents*          Pault Current 3-1/C 10 AWG                 40A, 50A                      620 A Initially**
3-1/C 6 AWG                 75A, 75A                      704A 3-1/C 2 AWG              130A, 130A                      704A Triplex 4/0 AWG             260A, 285A                      4200A Triplex 350 iMCM             350A, 370A                      4200A 3-1/C 500 MCM               430A, 476A                     4200A Initial warmup current   and current at 90oC         +SoC conductor temperature.
See Paragraph 3.0, Table I, Note 1 on Page           II-7.
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Page No.           9 Test Report No.           47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.2           Power Cable Screening Tests (Continued) 7.2.3          Results The results of the six Power Cable Screening Tests are briefly summarized in the following table:
Maximum Temperature Test       Fault Cable-       Fault       Target           Time to   Insulation Time-to Open*
No.             Size           Cable         Cable           ltutition Burn Time     Circuit 1       3-1/C 10 AWG       1136.2cF   '08.1cF               160 sec   1 min   160.64 sec (1) 2       3-1/C 6 AWG        1060.7oF       99.0oF             None     N/A     105.7 sec 3       3-1/C 2 AWG       2141.5oF     166.5oF             410 sec   9 min     598.0 sec (2) 4     Triplex 4/0 AWG     1673.4oF     644.8oF             83 sec   8 min     93.0 sec (3) 5     Triplex 350 MCM     1600.3oF     251.6oF             154 sec   7 min,   183.25 sec 6'-1/C         500 MCM     1534.0oF     210.1oF       -
441 sec   6 min   459.07 sec (4)
After application of fault current to the fault cable.
Notes:     (1)   Fault cable conductor shorted together after 10 seconds.
(2)   Fault cable conductors shorted together after 338 seconds.
(3)-   1-inch conduit mounted 1 inch above fault cable for'this test only.
(4)   Fault cable conductors shorted together after 320 seconds.
7'.2.'4    Conclusions The above results generated the following conclusions:
The Triplex 350 MCM cable was selected as the worst case cable. This selection was based on the fact that the Triplex 4/0 AWG and the Triplex 350 MCiM generated similar jacket temperatures and insulation burn times. However, the Triplex 350 MCM sustained the fault current for a longer period of time and visually was a more violent fire than either the Triplex 4/0 AWG cable or the 3-1/C 500 MCM cable.
: 2. The acceptability of design where a 1-inch rigid steel conduit is mounted 1 inch above a faulted power cable was not demonstrated by these tests. The size of the fire and the intensity of the heat generated during the electrical fault for Test No. 4 severely damaged the target cable in the 1-inch rigid steel conduit.
(See Notice of Anomaly No. 1 in Section lI of this report.) Consequently, this cable did not possess sufficient integrity to pass the Post-Overcurrent Test Functional Tests.
: 3. The acceptability of design where a 1-inch rigid steel conduit is mounted 12 inches above a faulted power cable tray was demonstrated by Tests 1, 2, 3, 5, and 6. During these tests, the maximum observed jacket temperature was 251.6oF (Test No. 5). There was no visible damage to the Twisted Pair 16 AWG target cable, and the target cable passed the Post-Overcurrent Test Functional Tests.
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Page No.         10 Test Report No.           4VSV9-02 V.O         TEST PROGRAM'DESCRIPTION (Continued)
V;3         ConQguration Number 1 Test Configuration Number   1 Test consisted   of a test between a free air faulted Triplex 350 MCM cable and a     free air Twisted Pair       16 AWG'arget cable separated by 6 inches horizontally.
V.3.1       Purpose The purpose of the Configuration Number 1 Test was to demonstrate the acceptability of design where two cables in free air pass 6 inches horizontally from each other when the worst case electrical fault occurs- to one of these cables. This configuration represents field installation of free air cables going from:
a.. Tray to tray b.. Tray to conduit
: c. Conduit to conduit.
: d. Tray/conduit to equipment.
.The cables tested and   electrical powering were       as follows:
Cable Size             Function                   Location             Powe Triplex 350 MCM           Fault Cable                 Free Air-      350A, 510A, 4200A*
Twisted Pair 16 AWG       Target Cable                 Free Air           50 VAC, 1A Initial Warmup Current, Final Warmup Current,           and Fault Current.
V.3.3       Results The results   of the Configuration Number     1   Test are briefly summarized in the following table:
Cable Size             Function              Location      Maximum Jacket Tem .
Triplex 350 MCM           Fault Cable             Free Air             1489.6oF Twisted Pair 16AWG         Target Cable             Free Air               580 3oF Time to Ignition:             105 seconds    at 4200A Time to Open Circuit:         148.29 seconds at 4200A WYLE LABOAATOAIKS Huntsville Facility
 
Page No.         11 Test Report No.         47879-02 TEST PROGRAM DESCRIPTlON (Continued) 7.3        Configuration Number 1 Test (Continued) 7.3.4       Conclusions These results generated the conclusion that the Twisted Pair 16 AWG target cable possessed sufficient integrity to continue to conduct 1 ampere at 50 VAC throughout this test and to successfully complete the Post-Overcurrent Test Functional Tests. Therefore, the cable met the established test acceptance criteria. However, the jacket was scorched in several locations from exposure to the flames from the fault cable. Thus, it was.decided that the 6-inch horizontal separation was not adequate and a free air separation of 12 inches was evaluated during Configuration No. 3, Test 3 (see Paragraph 7.5.4).
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Page No.           12 Test Report No.           47879-02 V.O           TEST PROGRAM DESCRIPTION (Continued) 7.4'onQguration             Number-2. Test Configuration Number 2 consisted of two tests between a free air cable, a cable in rigid steel conduit, and a cable in flexible conduit. The faulted Triplex 350 MCM cable was in free air for Test No. 1 and the separation was 6 inches verticaQy to the conduits. The faulted Triplex 350 MCM was inside the flexible conduit for Test No. 2 and the separation was 1 inch to the free air and rigid steel conduit.
V.4J.         Pur~se The purposes     of the Configuration Number   2 Tests were to:
1.,     Demonstrate the acceptabiTity of design where a free air cable, a rigid steel conduit, and a flexible steel conduit are separated by 6 inches vertically when the worst case electrical fault occurs to the free air cable.
: 2. Demonstrate the acceptability of design where a free air cable, a rigid steel conduit, and a flexible steel conduit are separated by 1 inch when the worst case electrical fault occurs to the cable inside the flexible steel conduit.
-':-V.4.2       Descr   tion The cables tested and the electrical powering were as follows:
,'7.4;2J.       Test No. 1 Cable Size             Function                  Location              Power Triplex 350 MCM         'ault Cable                   Free Air       350A, 505A, 4200A*
2/C 16 AWG            Target Cable                1" Flexible          50 VAC, 1A Steel Conduit 3-1/C'10 AWG            Target Cable               1" Flexible         480 VAC, 40A Steel Conduit Initial Warmup Current, Final Warmup Current,             and Fault Current.
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Page No.           13 Test Report No.           47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.4          ConQguration-Number 2 Test (Continued) 7.4.2.2      Test No. 2.
Cable Size             Function                  Location            Power Triplex 350 MCM           Fault Cable               4" Flexible     350A, 425A, 4200A*
Conduit 2/C 16 AWG             Target Cable             1" Rigid Steel         50 VAC, 1A Conduit 3-1/C   10 AWG         Target Cable                 Free Air           480 VAC, 40A Initial Warmup Current, Final Warmup Current,           and Fault Current.
V.4.3       Results The results of these tests are briefly summarized in the following tables.
Test No. 1 Maximum Temperatures Cable Size           Function                Lccaticu          Jacket    Conduit Triplex 350 MCM         Fault Cable              Free Air          1312.3oF      N/A 2/C 16 AWG           Target Cable           1" Flexible         751.7 F   777.6 F Steel Conduit 3-1/C 10 AWG         Target Cable               1" Rigid         490 6oF   719 4oF Steel Conduit Time to Ignition:             126 seconds      at 4200A Time to Open Circuit:         167.57 seconds       at 4200A WYLE LABORATORlES Huntsville Facility
 
Page No.           14 Test Report No.           47879-02 V.O           TEST PROGRAM DESCRIPTION (Continued) 7.4          ConQguration Number     2 Test (Continued) 7.4.3        Results (Continued) 7.'4.3.2     Test No. 2 Maximum Temperatures Cable Size             Function               Location     Jacket   Conduit Triplex 350 MCM         Fault Cable           4" Flexible   1593 9oF   509.5oF Steel Conduit 2/C 16 AWG           Target Cable               1" Rigid     131.6 F   141.0 F Steel Conduit 3-1/C 10 AWG         Target Cable             Free Air     169.8oF     N/A Time to Ignition:             None Time to Open Circuit:         231.63 seconds       at 4200A 7.4.4         Conclusions The above results generated the following conclusions:
: 1. The acceptability of design was demonstrated where a free air cable, a 1-inch flexible steel conduit, and a 1-inch rigid steel conduit are mounted 6 inches apart when the worst case electrical fault occurs to the free air cable. During this test, relatively high temperatures were observed inside the flexible steel and rigid steel conduits (751.V F and 490.6 F, respectively). However, damage to the target cables was limited to the jackets only. In addition, both cables possessed sufficient integrity to successfully maintain continuity of power and to complete the Post-Overcurrent Test Functional Tests.               Due to the high temperatures observed on the target cable jackets, this separation distance will not be permitted, without interposing barriers, in design at the Shearon Harris Nuclear Power Plant.
: 2. The acceptability of design was demonstrated where a free air cable, a 1-inch rigid steel conduit, and a 4-inch flexible steel conduit are mounted 1 inch apart, when the worst case electrical fault occurs inside the flexible steel conduit. The flexible steel conduit acted as an effective thermal barrier and suppressed the ignition of the Triplex 350 MCM fault cable.
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Page No.         15 Test Report No.         47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.'5        Configuration Number     3 Tests Configuration Number 3 consisted of three tests between two horizontal trays, a vertical tray, a parallel conduit or free air cable, and a perpendicular conduit. The horizontal trays were separated by 36 inches vertically and the vertical tray was separated by 12 inches horizontally. The faulted Triplex 350 MCM cable was in the upper horizontal tray for Test No. 1, the lower horizontal tray for Test No. 2, and the vertical tray for Test No. 3.
7.5.1       Purpose The purposes of the Configuration Number 3 tests were to:
: 1. Demonstrate the acceptability of design where three horizontal cable trays are separated by 36 inches {from the top of one tray to the bottom *of the next tray) when the worst case electrical fault occurs in either cable tray.
: 2. Demonstrate the acceptability of design where a horizontal cable tray passes 12 inches from a vertical cable tray when the worst case electrical fault occurs in either tray.
: 3. Demonstrate     the acceptability of design where a 1-inch rigid steel conduit passes:
: 1)     1 inch below and perpendicular to a faulted cable in a ladder rung cable tray, or
: 2)     1 inch horizontaQy away from and parallel to the siderail wall of a ladder rung cable tray, or
: 3)     1 inch horizontally away from and perpendicular to the siderail wall of a ladder rung cable tray.
: 4. Demonstrate the acceptability of design where a free air cable passes 12 inches horizontally away from and parallel to a faulted cable in a ladder rung cable tray when the worst case electrical fault occurs in the cable tray.
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Page No.           16 Test Report No.           4V8V9-02 V.D           TEST PROGRAM DESCRIPTION (Continued)
V.5           Configuration Number 3 Tests. (Continued)
The cables tested and the electrical powering were as follows:
V.5.2.1     Test No. I Cable Size           Punction                    Location              Povrerin Triplex 350 MCM         Fault Cable         Upper Horizontal       350A, 415A, 4200A*
Tray 3-1/C 10 AWG         Target Cable              Vertical Tray          480 VAC, 40A 2/C'16 AWG           Target Cable          Parallel Conduit          120 VAC, 10A 2/C 16 AWG           Target Cable             Perpendicular           120 VAC, 10A Conduit-Below Upper Tray Initial Warmup Current, Final Warmup Current,           and Fault Current.
V.5.2.2. Test No. 2 Cable Size           Punction                    Location            Powerin Triplex 350 MCM         Fault Cable           Lower Horizontal      350A, 440A, 4200A*-
Tray 3-1/C  10 AWG        Target Cable          Upper Horizontal         480 VAC, 40A Tray 3-1/C 10 AWG       Target Cable              Vertical Tray          480 VAC, 40A 2/C 16 AWG         Target Cable          Parallel Conduit          120 VAC, 10A 2/C 16 AWG         Target Cable             Perpendicular           120 VAC, 10A Conduit Initial Warmup Current, Final Warmup Current,           and Fault Current.
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Page No.           17 Test Report No.           47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.5            ConQguration Number 3 Tests (Continued) 7.5;2.3       Test No..3 Cable Size           Function                   Location-             Powerin Triplex 350 MCM         Fault Cable             Vertical Tray     350A, 465A, 4200A~
3-1/C  10 AWG        Target'Cable         Upper Horizontal         480 VAC, 40A Tray 3-1/C 10 AWG        Target Cable         Lower Horizontal         480 VAC, 40A Tray 2/C 16 AWG         Target Cable         Parallel Free-Air         120 VAC, 10A Initial Warmup Current, Final Warmup Current,         and Fault Current.
V.'5.3         Results
      'results from the three Configuration Number             3 Tests are briefly summarized in the wing tables.
7.5.3Z         Test No. 1 Maximum Temperatures Cable Size         Function               Location                   ~Ci l7 Triplex 350 MCM        Fault Cable       Upper Horizontal       1554.4oF     N/A Tray 3-1/C 10 AWG       Target Cable          Vertical Tray          202.1 F    154.3oF 2/C 16 AWG       Target Cable              Parallel          365.4 F    454.2oF Conduit 2/C 16 AWG         Target Cable          Perpendicular          262.3oF    415.7oF Conduit-Below Upper Tray Time to Ignition:           183 seconds      at 4200A Time to Open Circuit:       266.13 seconds at 4200A WYLE LASORATORIES Huntsville Facility
 
Page No.           18 Test Report No. *47879-02 7.0         TEST PROGRAM DESCRIPTION (Continued) 7.5,         ConQguration Number 3 Tests (Continued) 7.54.2,     Test No. 2 Cable Size       Function               Location           ~PI Maximum Temperatures Triplex 350 MCM     Fault Cable      Lower Horizontal 1372.4oF  942.4oF Tray 3-1/C 10 AWG       Target Cable      Upper Horizontal  236.2oP  378.7oP Tray 3-1/C 10 AWG       Target Cable          Vertical Tray  203.7oP    N/A 2/C 16 AWG       Target Cable              Parallel  223.9oF  382.9op Conduit 2/C 16 AWG       Target Cable          Perpendicular  248.5 F  539.9 F Conduit Time to Ignition:         160 seconds    at 4200A Time to Open Circuit:     223.98 seconds at 4200A
, 7.5.3.3      Test No. 3 Maximum Temperatures Cable Size        Function              Loeatim        k    ~/~
                                                                            ~M Triplex 350 MCM      Fault Cable          Vertical Tray 1514.7oF    N/A 3-1/C 10 AWG      Target Cable     Upper Horizontal   132.4oF 135.8op Tray 3-1/C 10 AWG      Target Cable      Lower Horizontal  133.0oF  130.7 P Tray 2/C 16 AWG        Target Cable            Free Air    166.4oP    N/A Time to Ignition:        193 seconds      at 4200A Time to Open Circuit:    201.16 seconds at 4200A WYLE LABORATORIES Huntsville Facility
 
Page No.          19 Test Report No.           47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.5'onfiguration            Number 3 Tests (Continued) 7.5.4.     Conclusions The above results generated the following conclusions:
The acceptability of design        was    demonstrated          for the following physical separation distances:
36-inch-vertical separation between two ladder rung cable trays with the worst case  electrical fault. in either tray.
: 2. 12-inch horizontal separation between a vertical and a horizontal cable-tray with the worst electrical fault in either tray; 3'. 1-inch horizontal separation between the siderail walls of a horizontal tray and a 1-inch rigid steel conduit when the worst case electrical fault occurs in the tray.
4,  1-inch vertical separation between a ladder rung cable tray and a perpendicular 1-inch conduit below the tray when the worst case electrical fault occurs in the tray..
1-inch horizontal separation between a horizontal ladder rung cable tray and a perpendicular vertical 1-inch rigid steel conduit when the worst case electrical fault'occurs in the tray.
6.- 12-inch horizontal separation between a vertical free air cable parallel to a vertical ladder rung cable tray when the worst case electrical fault occurs in the tray.
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Page No.          20 Test Report No.           47879-02 8.0          QUALITYASSURANCE All work performed    on this test. program was done in accordance with Wyle Assurance Program, which complies with the applicable requirements of 10 CFR 50, Laboratories'uality Appendix B; ANSI N45.2', and the "daughter" standards. Defects are reported in accordance with the requirements of 10 CFR Part 21.
9.0          TEST EQUIPMENT AND INSTRUMENTATION All. instrumentation, measuring, and test equipment used in the performance of this test program were calibrated in accordance with Wyle Laboratories Quality Assurance Program, which complies with the requirements of Military Specification MIL-STD-45662. Standards used in performing all calibrations are traceable to the National Bureau of Standards by report number and date. When no national standards exist, the standards are traceable to international standards or the basis for calibration is otherwise documented.
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Page No.       21 Test Report No.         47879-02 TABLE L TEST RESULTS  


==SUMMARY==
==SUMMARY==
nflgurat ion Description Design Minimum Physical Separation Tested Spacing est Number'anmum a t Temperature axrmum arget Temperature Control Instrument Tray to Conduit 1" H 3n ln V Control Cable Screening Tests No.1-5 (4)>>963.4oP 185.8oF Power Tray to, Conduit Free Air to Pree Air Cables 4n H 2n V 12" H (Power Cables)6n H (Control/instrument Cables)12n V 6n H Power Cable Screening Tests 1,2,3,5 6r 6 Configuration No.1 (3)2141.5oP 1489.6oP (5)251.6oP 551.3oF Power Free Air to Plex.4r R/S Conduit Plexible Conduit to Pree Air dc R/S Conduit r Tray to ower Tray Horizontal Power Tray to Conduit Under Tray Horizontal
 
" Power Tray to Conduit Parallel to Tray Horizontal Power Tray to Conduit Riser Riser Tray to Parallel Pree Air Cable 12" H 12n H 12" H 36" V 1" H 1n V 12 H 36" V 12n V 4n H 4n H 12n V 12n H 36n V 6" V ln V 12n H 36n V ln V (Perpendicular Crossing X-Z Plane)1" H (Conduit Parallel To Tray SideraQ)ln H (Perpendicular Crossing Z-Y Plane)12n H Configuration 2 Test No.1 Configuration 2 Test No.3 Configuration 3 Tests 1,
nflgurat ion Description Design Minimum Physical Separation Tested Spacing est Number
                                                                                  'anmum    Temperature a t    axrmum arget Temperature Control Instrument                1" H                                    Control Cable          (4) >>
Tray                                        ln V                Screening                963.4oP                185.8oF to                  3n                                      Tests No. 1-5 Conduit Power Tray                4n H                                    Power Cable          (3)                  (5) to,                                        12n V              Screening                2141.5oP                251.6oP Conduit                2n V                                  Tests 1,2,3,5    6r 6 12" H Free Air          (Power Cables)                                Configuration to                  6n H                  6n H                                        1489.6oP                551.3oF Pree Air        (Control/instrument                                  No. 1 Cables              Cables)
Power            12" H Free Air            12n H                                      Configuration      2                            (F) 751.7oF to              12" H                      6" V                                        1312.3oF Plex. 4r R/S          36" V                                        Test No. 1                              (R/S) 490.6oF Conduit Plexible Conduit                1" H                                  Configuration      2                          (FA) 131,6oP to                                          ln V                                        1593.9oF Pree Air dc                1n V                                      Test No. 3                              (R/S) 169.8oF R/S Conduit r Tray            12  H                  12n H            Configuration      3  (2)                      (V) 236.2op to                                                                                      1554,4op ower Tray              36" V                  36n V            Tests 1,  2 Cc  3                              H) 203 7o Horizontal Power Tray                                        ln V            Configuration      3 to                  12n V            (Perpendicular                                    1554.4op                262 3op Conduit                              Crossing X-Z Plane)        Test No. 1 Under Tray Horizontal Power Tray                                        1" H            Configuration      3 (1) to Conduit                4n H          (Conduit Parallel                                    1554 4OP                365.4oF Parallel to                              To Tray SideraQ)          Tests  1  2  2 Tray Horizontal Power Tray                4n H                  ln H            Configuration      3 to                                    (Perpendicular                                    1372.4oP                248.5oF Conduit                12n V          Crossing Z-Y Plane)        Test Vo. 2 Riser Riser Tray to                  12n H                                  Configuration      3 Parallel                                      12n H                                        1514 7oP                166.4oF Pree Air                36n V                                      Test No. 3 Cable KEY:                                                        Refers to test number of data when multiple tests conducted.
H  = Horizontal Distance V  = Vertical Distance R/S  = Rigid Steel Conduit P  = Flexible Steel Conduit PA P    = Free  Air Cable
 
Page No.          I-1 Test Report No.            47879-02 SECTION          I CONTROL CABLE SCREENING TESTS (DETERMINATIONOP IGNITION CAPABILITYOP CONTROL CABLES IN A CABLE TRAY) 1.0        REQUIREMENTS Acceptance Criteria 1.1 J.      Insulation Resistance Test Insulation resistance on all "target cables"* shall be greater than 1.6 x 106 ohms with a potential of  500 VDC'applied for 60 seconds.                Before testing insulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an
. ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the
'vercurrent Test.
T ere shall be no evidence of insulation breakdown or flashover with a potential of VAC applied for one minute.
1..3=        Cable Continui      Test Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 50 VAC before, during, and after the overcurrent test.
Cable                No.              CPRL          Cable                Rated Size          Conductors          LD. Nu.                Volt~e      Current 16 AWG              1 Tw. Pr.          D60-01            L    50 VAC        1A 1.1.4      Tolerance s All target cable voltages specified in this procedure shall be maintained within                  a +3%
tolerance. All target cable currents shall be maintained within a+10% tolerance.
All fault cable currents shall be maintained within a+3% tolerance.
The term "target cable" refers to energized and monitored nonfault cables used in this program.
WYLE LABORATORIES Huntsville Facility
 
Page No.          I-2 Test Report No.            47879-02 2.0          PROCEDURES 2.1          Test Specimen Identification An inspection was performed upon receipt of the test specimen components at 'Wyle Laboratories.      This inspection ensured that the test specimens were as described in Paragraph 6.0 of the Summary section. Applicable manufacturer, model, part, and serial numbers were verified and recorded.            The test specimens were labeled to facilitate identification throughout the test program.
Test Specimen Receipt Inspection forms are presented in Appendix I of this section.
2.2          Test Specimen Preparation The test setup for the five Control Cable Screening Tests was identical except as noted in the following paragraphs.
The test specimens. were mounted to the unistrut frame of Figure 1 of Section VI; This apparatus was assembled to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following guidelines were observed with regard to the materials and construction of this assembly:
P
: 1. The faulted cable was one  of the following cables from CP*L stock:
Test No.            Fault Cable Size              COL LD. No.
2/C 16 AWG                    D50-11 2/C 12 AWG                    D50-06 2/C 10 AWG                    D50-01 3-1/C 10 AWG                    D59-02    (D25-01) 3-1/C 6 AWG                    D59-03    (D25-03)
The fault cable was the top centermost cable inside an 8' 24" x 4" ladder rung cable tray filled to the top of the siderails with de-energized control-type cables.
: 2. Nine 1/C 10 AWG cables were mounted underneath and around the faulted cable per Figure I-1. These cables were energized and their conductor temperatures increased prior to applying the fault current to the fault cable. This was done to simulate the heat which the fault cable would experience in a cable tray of
          'nergized    cables.
: 3. The ends of the faulted cable from their termination to the edge of the cable tray were wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape. This was done as a safety measure to ensure that any ignition that might occur was contained to the cable tray area.
WYLE LABORATORIES Huntsville Facility
 
Page No.          I-3 Test Report No.          47879-02 PROCEDURES (Continued) 2.2          Test Specimen Preparation (Continued)
: 4. A 9-foot long, 1-inch rigid steel conduit was mounted parallel to and 1 inch above the fault cable. This conduit contained a single pair 16 AWG target cable (CPRL I.D. No. D60-01). The 1-foot section of this conduit which extended past the cable tray was wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape.
: 5. A wind barrier was installed around the unistrut frame to eliminate the effects of wind on the heat transfer of the fault cable.
: 6. Photographs were taken of the test setup.
: 7. A 1/2-inch VHS recording was taken of the Overcurrent Test encompassing the entire application of the test current.
2.3'nstrumentation            Setup 2.3;1        Thermoco      le Locations A total of 35 Type "K" thermocouples were utilized for these tests.          These thermocouples
      -mounted as described below:
Channel No.                                            Location 1-8          Mounted to the jacket of the fault cable. These thermocouples were spaced approximately 12 inches apart.
9@10            Mounted to the conductors of the fault cable.            These thermocouples were applied by cutting the cable insulation, approximately 12 inches from the series connection points, forcing the thermocouple into the conductor strands and then taping the area with 3M No. 69 glass tape.
11-16          Mounted to the conductors of the nine cables adjacent to the faulted cable. The six thermocouples were mounted with three thermocouples at each end of these cables in three of the four series connections.
17-24          Mounted to the jacket of the single pair 16 AWG target cable inside the 1-inch conduit. These thermocouples were spaced approximately 12 inches apart and were even with the eight fault cable thermocouples.
25 2  26        Mounted underneath the 1-inch conduit.
27-35          Mounted 1 inch above and 1 inch horizontally from the fault cable in three groups of three thermocouples.
thermocouples were monitored using a Fluke Datalogger feeding a high-speed printer.
atalogger was operated at its maximum rate throughout the Overcurrent Test. The t      erature data is plotted versus time in Appendix V of this section.
WYLE LABORATORIES Huntsville Facility
 
Page No.          I-4 Test Report No.          47879-02 2.0          PROCEDURES (Continued) 2.3          Instrumentation Setup (Continued) 2.3.2        Electrical Monitor The voltage and current of the target cable and the fault cable current were continuously monitored with an osciQograph recorder. The oscillograph was operated at the O.l-inch per minute rate throughout the Overcurrent Test. The oscillograph channels were as specified in the following table:
Channel No.                    S                            Location Current                    Tw. Pr. 16 AWG Voltage                    Tw. Pr. 16 AWG Current                      Fault Cable A digital multimeter was utilized to measure voltage and current of the target cable prior to, during, and after the Overcurrent Test. This data was recorded to provide accurate
~
evidence of the specimen's capability to conduct rated current at 50 VAC throughout the Overcurrent Test and is presented in Appendix V of this section.
2 .4        Baseline Functional Tests
  >The  baseline    functional tests consisted of Insulation Resistance and High Potential measurements    on each  of the target cables. These tests were performed as described below:
2.4.1        Insulation Resistance Test
: 1. All power and instrumentation leads were disconnected from the target cable.
: 2. Shield continuity to the conduit was measured with a digital multimeter.
: 3. Using a megohmmeter, a potential of 500 VDC was applied and the minimum insulation resistance indicated after a period of 60 seconds was recorded between the following test points:
Phase-to-Phase                      Phase-toW round*
1to2                              1 to conduit 2 to conduit
* Shield tied to conduit.
For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 1.1.1, i.e., greater than 1.6 x 10 WYLE LABORATORIES Huntsville Facility
 
Page No.          I-5 Test Report No.          47879-02 PROCEDURES (Continued) 2.4          Baseline Functional Tests (Continued) 2.4.2        H h Potential Test
: 1. Using a Hi-Pot Test Set, a potential of 1600 VAC was applied and the leakage current observed after a period of 60 seconds was recorded between the following test points:
Phase-to-Phase                      Phase-to-Ground*
1 to 2                            1 to conduit 2 to conduit
* Shield tied to conduit.
flasho
: 2. Power and instrumentation leads were reconnected to the target cable.
For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 1.1.2, i.e., there shall be no evidence of insulation breakdown or ve.
2.5          Overcurrent Test, vercurrent. Test was conducted in two sequential phases with no intentional time delay een phases. The first phase consisted of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90 C +5 C. The second phase consisted of energizing the fault cable with the test current until the cable open-circuited, temperatures stabilized or decreased, or the test was terminated at the customer's request.
The"target cable was energized at rated current and 50 VAC throughout the Overcurrent Test. The Overcurrent Test was conducted using the following procedure:
: 1. Nine 1/C 10 AWG cables            were      installed adjacent      to the fault cable per Figure I-1.
: 2. The fault cable (see the table on following page) was connected to the copper bus bars.
: 3. A single pair 16 AWG target cable was installed in the 1-inch rigid steel conduit per Figure I-1.
4,    The single pair 16 AWG target cable were connected to the instrumentation and power supplies of Figure 11 of Section VI.
      =5. The nine 1/C 10 AWG cables were connected to the power supply per Figure              8 of Section VI.
'he    6.          single pair 16 AWG cable were energized with            1 ampere at 50 YAC.
The nine 1/C 10 AWG cables, adjacent to the fault cable, were energized with 40 amperes at reduced voltage.
WYLE LABORATORIES Huntsville Facility
 
Page No.          I-6 Test Report No.          47879-02 2.0        PROCEDURES (Continued) 2.5        Overcurrent Test (Continued)
: 8. The fault cable was energized with the        initial currents listed in the table below.
: 9. Target cable voltage and current, fault cable current and initial eonduetor temperature, and adjacent cable current were recorded.
: 10. Pault cable and adjacent cable currents were slowly increased to achieve a fault cable conductor temperature of 90 C +5oC for a period of 15 minutes.
: 11. Target cable voltage and current, fault cable current                      and  conductor temperature, and adjacent cable current were recorded.
: 12. The fault cable current was increased              to the test current value in the table below.
: 13. Target cable voltage and current, fault cable current                      and  conductor temperature, and adjacent cable current were recorded.
: 14. The  fault cable  was allowed to conduct the test current until either the cable open-eircuited (Tests 1, 2 and 4), temperatures stabilized or decreased (Test 5},
or the test was terminated at the customer's request (Test 3).
: 15. Time to open-circuit or stabilized temperature was recorded, as applicable.
: 16. Target cable voltage and current and adjacent cable current were recorded.
: 17. The target cables,    adjacent  cables,        and the Multi-Amp Test Set were de-energized.
: 18. Post-test conditions were photographed..
Por all performances of this test, the observed target cable operation was compared to the acceptance criteria, Paragraph 1.1.3, i.e., they maintained continuity of power.
Pault Cable Sizes and Currents Test                                    CPRL                Initial            Test No. Pault Cable Size              LD. No.                  C            Current 1        2/C 16 AWG                  D50-11                18A              136A 2        2/C 12 AWG                  D50-06                30A              180A 3        2/C 10 AWG                  D50-01                40A              180A 4      3-1/C 10 AWG          D59-02 (D25-01}              4QA              180A 5        3-1/C 6 AWG          D59
r For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.2, i.e., there was no evidence of insulation breakdown or flashover.
r For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.2, i.e., there was no evidence of insulation breakdown or flashover.
WYLE LABORATORIES Huntsville Facility Page No.IV-6 Test Report No.47879-02 2.'4 PROCEDURES (Coatiaued)
WYLE LABORATORIES Huntsville Facility
Overcurreat Test The Overcurrent Test was conducted in two sequential phases with no intentional time delay between phases.The first phase consisted of powering the fault'cable with rated current and increasing this current until temperatures of 90oC+5oC were indicated for 15 minutes on the fault cable conductor.
 
The second phase consisted of energizing the fault cable with the test current until the cable open-circuited.
Page No.          IV-6 Test Report No.          47879-02 PROCEDURES (Coatiaued) 2.'4        Overcurreat Test The Overcurrent Test was conducted in two sequential phases with no intentional time delay between phases. The first phase consisted of powering the fault 'cable with rated current and increasing this current until temperatures of 90oC +5oC were indicated for 15 minutes on the fault cable conductor. The second phase consisted of energizing the fault cable with the test current until the cable open-circuited.
The target cable conducted rated current at 480 VAC (power cables)or 120 VAC (control cables)throughout the Overcurrent Test.The Overcurrent Test was conducted using the following procedure:
The target cable conducted rated current at 480 VAC (power cables) or 120 VAC (control cables) throughout the Overcurrent Test. The Overcurrent Test was conducted using the following procedure:
1.The Triplex 350 MCM fault cable was connected to the copper bus bars per Figure IV-1 or IV-3.2.A 2/C 16 AWG target cable was installed per Figure IV-1 or IV-3.3.A 3-1/C 10 AWG target cable was installed per Figure IV-1 or IV-3.4.The 3-1/C 10 AWG target cable was connected to the instrumentation and power supplies of Figure 9 of Section YI.5.The 2/C 16 AWG target cable was connected to
: 1. The Triplex 350 MCM fault cable was connected              to the copper bus bars per Figure IV-1 or IV-3.
: 2. A 2/C 16 AWG target cable was installed per Figure IV-1 or IV-3.
: 3. A 3-1/C 10 AWG target cable was installed per Figure IV-1 or IV-3.
: 4. The 3-1/C 10 AWG target cable was connected to the instrumentation and power supplies of Figure 9 of Section YI.
: 5. The 2/C 16 AWG target cable was connected to the instrumentation and po supplies of Figure 10 of Section VI.
: 6. The 3-1/C 10 AWG target cable was        energized'ith  40 ampere at 480 YAC.
: 7. The 2/C 16 AWG target cable was energized with 10 ampere at.120 VAC.
: 8. The  fault cable was energized with 350 amperes per phase (rated current) from the Multi-Amp Test Set.
: 9. Target cable voltages and currents and the fault cables current were recorded.
: 10. Fault cable current was slowly increased until thermocouple Channels          9 and/or 10 indicated a 90oC +5oC conductor temperature.
: 11. The conductor temperature was maintained at 90 C +5 C for 15 minutes.
: 12. Fault cable current and conductor temperature were recorded.
: 13. The Multi-Amp Test Set output was increased to 4200 amperes (test current).
: 14. Target cable voltages, currents and the fault cable current were recorded.
WYLE LASORATORIES Huntsville Facility
 
Page No.          IV-7 Test Report No.          47879-02 PROCEDURES (Continued) 2.4        Overcurrent Test (Continued)
: 15. The  fault cable  was allowed to conduct 4200 amperes      until the cable open-circuited.
: 16. Time to ignition and open-circuit, and maximum fault cable temperature were recorded.
: 17. Target cable voltages and currents were recorded.
: 18. The target cables and the Multi-Amp Test Set were de-energized.
: 19. Photographs were taken of the post-test conditions.
Por all performances of this test, the observed target cable operation was compared to the acceptance criteria, Paragraph 2.1.3, i.e., it maintained continuity of power.
2."5        Post Overcurrent Test Punctional Test'he functional tests of Paragraph 3.5.4 were repeated as soon as the smoke cleared in the cchamber. In addition, the target cable jacket. temperature was recorded.
WYLE LABORATORIES Huntsville Facility
 
Page No.          IV-8 Test Report No.          47879-02.
3.0        RESULTS 3.1        Results of Test No. 1 Configuration Number 2, Test No. 1, with a Triplex 350 MCM fault cable in free air, a 2/C 16 AWG target cable inside a 1-inch flexible steel conduit, and a 3-'1/C 10 AWG cable inside a 1-inch rigid steel conduit, was conducted in accordance with Paragraph 2.0 and successfully met the Acceptance Criteria of Paragraph 1.0. The 4200 ampere fault current was applied, until the fault cable open-circuited in 167.57 seconds. The fault cable ignited after 126 seconds and burned all of the available insulation in approximately 7 minutes with flames approximately 18 inches high. The peak temperature of 1312.3 F was recorded on the fault cable during this test.
The 2/C 16 AWG and 3-1/C 10 AWG target cables maintained their electrical integrity and conducted 10 amperes at 120 VAC and 40 amperes at 480 VAC, respectively, throughout the Overcurrent Test.      In addition,, the target cables successfuQy completed the Post-Overcurrent Test Functional Tests.
The peak temperatures observed on the target cables were:
Jacket            Conduit Cable                    Conduit                                        Tem erature 2/C 16 AWG 3-1/C 10 AWG Flexible Conduit Rigid Steel Conduit 751.7oF 490.6oF 777 6oF 719.4oF
---"The exposure to these temperatures did result in physical damage to the cable jackets. The
                                                                                                    ~
3-1/C 10 AWG target cable jacket deformed and was slightly charred in several areas (see Photograph IV-7 in Appendix I). There was no area where the jacket integrity was ruptured on this cable. The 2/C 16 AWG cable suffered an unusual phenomenon, due to its exposure to high temperatures. The outer jacket swelled and became very spongy, which protected the individual conductors by separating them from the conduit walls (see Photographs IV-8 and IV-9 in Appendix I). The flames from the fault cable engulfed both conduits and the outer coating of the Anaconda Sealtite Type E.F.P. flexible conduit melted and ignited.
These flames were approximately 1 inch high and self-extinguished once the fault cable flames deer eased.
Although both target cables successfully met the Acceptance Criteria, this separation distance will not be permitted, without interposing barriers, in design at the Shearon Harris Nuclear Power Plant.
The  results of this    test  were  judged      to be acceptable          by the CPA L Technical Representative.
Appendix I contains the following data from this test: 1) Figure IV-1 which Qlustrates the test setup; 2) Photographs IV-1 through IV-8 which show the pre-test and post-test conditions; 3) A narrative of this test; 4) A plot of temperatures versus time; and,
:


CAROLINA POWER L LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-002 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM PRESSURE RETAINING PIPING WELDS (PRESERVICE/INSERVICE APPLICABLE)
Page No. V-56 Test Report No. 47879-02 PHOTOGRAPH NO. V-19 OVERALL VIEW OF DAMAGE FROM CONFIGURATION NUMBER 3, TEST NO. 3 PHOTOGRAPH NO. V-20 VIEW OF VERTICALTRAY AFTER THE OVERCURRENT TEST (Note the Limited Damage to Cables in the Tray)
CLASS 1 F-C F3.50 CODE RE UIREME TS: Table IWF-2500-1 defines the testing and inspection criteria for snubbers.RELIEF RE VESTED: Relief is requested from the functional test requirements for snubbers per article IWF-5000.ALTER ATE EXAMINATIO All Shearon Harris component support snubbers will be selected, inspected, and functionally tested per Section 3/4.7.8 of the Shearon Harris Technica I Specifications.  
PHOTOGRAPH NO. V-21 VIEW OF VERTICALTRAY AND FREE AIR CABLE AFTER THE OVERCURRENT TEST


CAROLINA POWER 8c LIGHT SNEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-003 PRESERV ICE EXAHI NAT ION PROGRAM ASHE SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE I TEH.PRESSURE RETAINING PIPING WELDS (PRESERVICE/INSERVICE APPLICABLE)
Test
CLASS 1 8-J B9.11, B9.31 CODE RE UIREME TS: ASHE Section XI, Table IWB-2500-1 requires volumetric and surface examinations on~4" nominal pipe size circumferential and longitudinal pressure retaining welds, including branch connections.
          !Il
RELIEF RE UESTED: ASHE Section XI requires essentially 100/of the weld length be volumetrically examined.Due to piping weld configurations (reducer to tee, pipe to tee, pipe to flange etc.)volumetric examinations of 100$of the weld length was sometimes not feasible.Relief is requested based on weld configurations not being conducive to 100$volumetric examination (see additiona I deta I Is on Attachment"A" to this relief request).ALTER ATE EXAHI ATIO Pressure reta ining welds were surface examined for essentially 100$, of the weld length where possible.-Volumetric examinations were performed to the maximum extent possible on physical limitations.
          !  1 PRAWN BY ~
Where the component configuration or access precluded or limited this examination, that fact and to the extent was documented on the Preservice Baseline Data Sheet.
Cj!ECKED BY 1)J C5 5
Attachment A Page 1 of 2 RELIEF REQUEST NO: Rl-003 EXAMINATIONS Ultrasonic examinations were conducted to inspect as much of the examination zone as was practical, within geometric, metallurgical, and physical limitations.
4 ii 1     I'onfiguration                      LEGENDt 3        3 Fault Cable Jacket Temperature (T/CS'1-8)
When the required ultrasonic examination volume or area could not be examined 100 percent, the examination was considered to be partial and was so noted on the applicable component Data Sheet.Generally, partial examinations were done at fitting to fitting assemblies (explained under limitations) and in areas where integrally welded supports, lugs, etc., preclude access to some part of the examination area.Ultrasonic examinations that produced indications 50 percent of DAC or greater from geometric or metallurgical origin were recorded.Examples of areas that generally produced such indications are as follows: 1.Inside diameter weld preparation or root configuration and the outside diameter down overlay or toe.2.The inside diameter radius of the tube sheet weld of the steam generators where examined from the tube sheet side.3.The metallurgical structure of austenitic materials.
Fault Cable Conductor Temperature (T/CS 9 4 10)
4.Signal responses from the thread areas of bolting.LIMITATIONS Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examinations requirements of Section XI of the 1980 Code could be applied;consequently, some examinations are limited or not practical due to geometric configuration or accessibility.
Target Cable (Tl-3-1/C 10 AWG) Jacket Temperature I                                                                                                                                                                            (T/CS 17-24)
Generally these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length.The limitations exist to a lesser degree at pipe to fitting assemblies, particularly where the weld is not ground flush with the pipe O.D.surface.At these joints examinations can be conduced from the pipe side;however, the fitting again limits precludes examination from the opposite side.In most cases, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code required area or volume (generally,'the weld and base metal of 1"T" on each side)as possible.However, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100 percent.These areas where complete examination of 100 percent of the required volume of area could not be achieved were indicated and noted to the extent on the examiner's Data Sheet, and the limiting cause noted.
Target Cable (T2-3>>1/C 10 AWG) Jacket Temperature (T/CS 25-32)
Attachment A Page 2 of 2 RELIEF REQUEST'NO:
Free Alr Target Cable (2/C 16 AWG) Jacket Temperature (T/CS 33-40)
R1-003 The principal basis for partial examinations is to identify the inability to.examine 100 percent of the, required base metal volume for the 1"T" distance beyond the edge of the weld on a fitting or component.
In'.I!II j:I 41 Ii Nax. Temp. Recordedt  1514.7 P (T/C $ 7) at 143.3 min
Examples are (1)ultrasonic examination of a pipe to elbow assembly, where scanning on the intrados of the elbow causes de-coupling of the sound beam and (2)a pipe to flange or valve assembly where scanning the entire volume on the fitting or component side is limited by configuration.
          !I     rl:!                                                                                                                            Amb(ent Temp.i 80 F Dater September 11, 1985 FIGURE  V-b 1100                                                                              N 1000 4t nit I i i!i!
The resulting coverage is such that examination of the weld, heat affected zone and base metal for 1"T" on indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc.However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by code.In either case, 100 percent of this 1"T" volume cannot be assured, thus a partial examination is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical.
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Specific limitations and restrictions for all examinations are as indicated on the specific report Data Sheet.
                                                                                                                                                                                                        'g 4 0 0 550                                                                                                                                                                                                i I
'CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-004 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS COMPONENTS OR ITEM ASME XI CODE CLASS REQUEST FOR RELIEF FROM CODE REQUIREMENTS CODE CATEGORY CODE ITEM PRESSURE RETAINING WELDS IN REACTOR VESSEL PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSEL (PRESERVICE/INSERVICE APPLICABLE}
500 ij4
CLASS 1 CLASS 1 8-A B-B 81.11'1.21'1.40'1.
~1                                                                                                          Iiij                                                                                          1
12, 81.22 82.11, 82.12, 82.40 CODE RE UIREMENT: Table IWB-2500-1 defines the volume of materia I which should be covered during the volumetric examinations.
        .4I                                                                                                                                                                                              Cl 450
RELIEF RE UESTED:.In instances where component configuration or limited access resulted in the examination of less than 100%%u of the code required volume, a Iternate examination techniques were considered and if, feasible, used.ALTERNATE EXAMINATIO The ultrasonic examinations were performed to the maximum extent possible.Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of materia I not fully examined were defined.
        'm:. ij i                                                  0!                                  12                                                                                          C4 V! ijli e      .rgti    nil 400 z  350                                                                            I   .j".
CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-005 PRESERVICE EXAMINATION PROGRAM ASHE SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASHE XI CODE CLASS CODE CATEGORY CODE ITEM PUMP CASINGS VALVE BODIES'XCEEDING 4 IN.NOMINAL PIPE SIZE (PRESERVICE APPLICABLE)
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CLASS 1 CLASS 1 8" L-2 8"M-2 B12.20 B12.50 CODE RE UIREME T;ASME Section XI, Table IWB-2500-1 requires visual examinations (VT-3)be performed, as part of the Preservice Program, on the Internal surfaces of pump casings and valve bodies, exceeding 4 in.nominal pipe size.RELIEF RE VESTED: Relief is requested from the ASHE Section XI requirements for visual examinations (VT-3)of internal surfaces of pumps and valves.Disassembly of these components would not be practical as unnecessary damage may occur from the disassembly process.ALTERNATE EXAMINATIO S: Manufactures records will be utilized as the recorded condition of internal surfaces for Preservice.
        .!5 i'L                                                                      lb'l o                                                                                  i
No relief Is requested for the Inservice Program.
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i CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-006 PRESERVICE EXAMINATIOII PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROH CODE REQUIREMENTS COHPONENTS OR ITEM ASHE XI CODE CLASS CODE CATEGORY CODE ITEM FULL PENETRATION WELDS OF NOZZLES IN VESSELS PRESSURE RETAINING DISSIMILAR METAL WELDS (PRESERVICE/INSERVICE APPLICABLE)
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CLASS 1 CLASS 1 B-D B-F B3.110, 83.120 83.9, B3.130 85.40 CODE RE UIREMENT: Table IWB-2500-1 defines the volume of material which should be covered during the volumetric examinations.,RELIEF RE'ESTED: In instances where component configuration or limited access resulted in the examination of less than 100$of the code required volume, alternate examination techniques were considered and, if feasible, used.ALTERNATE EXAMINATIO The ultrasonic examinations were performed to the maximum extent possible.Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of mater ial not ful ly examined were defined.
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CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-007 PRESERVICE EXAMINATION PROGRAM ASHE SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASHE XI CODE CLASS CODE CATEGORY CODE ITEM PRESSURE RETAINING PIPING WELDS (PRESERVICE/INSERVICE APPLICABLE)
                                                                    ,in 4      I                                              f I4 I  'I:gj I'lr
CODE RE UIREHENT: CLASS 1 8-J 89.31 ASME Section XI, Table IWB-2500-1 requires volumetric and surface examinations of 4" nominal pipe size circumferential and longitudinal pressure retaining weld, including branch connections.
                                                                ! 4r t it'I                        4  ld 14 nt:                    i 4
RELIEF RE VESTED: Re lief is requested for performing u I trason ic examination on branch connections with nozzle weld configurations not conducive to volumetric examinations.
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These nozzle welds are on line RC27$-6SN (ISO: 1-ISI-FW-HS-RC-2) and line: RC275-3SN (ISO: 1-ISI-FW-HS-RC-l), and are identified on attached computer listings.ALTERNATE EXAMINATIO These pressure retaining welds were surface examined for essentially 100$, of the weld length where possible.These welds will be subjected to hydrostatic as well as leakage pressure tests on periodic intervals.
                                                    '0                                                ft
CAROLINA POWER Ec LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-008 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM INTEGRAL ATTACHMENTS FOR VESSELS (PRESERVICE/INSERVICE APPLICABLE)
                                                                                                  'il, ftt 44I ii      I ti''f jr il I TIME(MIN)
CLASS 1 B-H B8.20 CODE RE UIREME T: ASME Section XI, Table IWB-2500-1 requires volumetric or surface examinations, as applicable on integrally welded attachments for vessels.Examinations are limited to attachment weld joining the attachment to the pressure retaining membrane of the components and where the attachment base material design thickness is 5/8 in.or greater.RELIEF RE VESTED: ASME Section XI requi red essentially 100%of the length of the weld be examined.Due to the design of some Integral attachments, examination of 100%of the weld length was sometimes not feasible.Relief is requested based on weld configuration not being conducive to 100%surface or volumetric examination, as applicable.
ALTER ATE EXAMINATIO Integral attachment welds for vessels were surface examined for essentially 100%of the weld length where possible.Where the component configuration or access precluded or limited this examination, that fact and to the extent was documented on the Preservice Baseline Data Sheet.
CAROLINA POWER Ec LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-009 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM PRESSURE RETAINING BOLTING, 2IN.AND LESS IN DIAMETER (PRESERVICE/INSERVICE APPLICABLE)
CODE RE UIREME T: CLASS 1 B-G-2 B7.60 ASME Section XI, Table IWB-2500-1 requires a visual examination (VT-1)on al I pressure retaining bolting 2 in.and less in diameter, located on Class 1 components.
Bolting may be examined;in place under tension, when the connection is disassembled or when the bolting is removed.RELIEF RE VESTED: Relief is requested from visual examination (VT-1)on two (2)capscrews that are covered by the reactor coolant pump shaft proximity probe mount, and are not accessible for examination.
This condition exist on a II three (3)reactor coolant pumps.Tota I of six (6)capscrews that are not accessible.
ALTER AT EXAMINATIO Should the reactor coolant pumps be disassembled for other activities, the inaccessible capscrews will be examined (VT-1).In addition, the reactor coolant pumps are subject to hydrostatic tests and system leakage tests.
CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-001 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM PRESSURE RETAINING PIPING WELDS (PRESERVICE/INSERVICE APPLICABLE)
CLASS 2 C-C C" F C3.20 C5.12'5.32 C5~21p C5.11 CODE RE UIREMENTS:
ASME Section XI, Table IWC-2500-1 requires surface and/or volumetric examinations to be performed as applicable on pressure retaining welds, and surface examinations on welded pipe attachments (WPA's)meeting the design criteria for examination of IWC-2500-1.
RELIEF RE VESTED: Relief is requested from examinations on Class 2 pressure reta ining welds and/or welded pipe attachments (WPA')due to structura I interferences such as: permanent hangers, saddle plates, support structures, or intervening members for other systems.ALTERNATE EXAMINATION:
To the maximum extent possible volumetric examinations were performed.
Where the weld was identified as being inaccessible to the volumetric examination, surface examinations were used in lieu of the volumetric examinations.
Visual examinations (VT-1)were performed on components which required surface examinations, when accessible.
Where access precluded or limited the examination, that fact was documented on the Preservice Baseline Data Sheet.
CAROLINA POWER L LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-002 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASHE XI CODE CLASS CODE CATEGORY CODE ITEM COMPONENT SNUBBERS (PRESERVICE/INSERVICE APPLICABLE)
CODE RE UIREME T: Table IWF-2500-1 defines the testing and inspection criteria for snubbers.RELIEF RE VESTED: CLASS 2 F" C F3.50 Relief is requested from the functional test requirements for snubbers per article IWF-5000.ALTERNATE EXAMI ATIO Al I Shearon Harris component support snubbers wil I be selected, inspected, and functiona I ly tested per Section 3/4.7.8 of the Shearon Harris Technical Specifications.
0 CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-003 PRESERVICE EXAMINATION PROGRAM ASHE SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COHPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM PRESSURE RETAINING PIPING WELDS (PRESERVICE/INSERVICE APPLICABLE)
CLASS 2 C-F C5.21'5.11 CODE RE UIREME T: ASHE Section XI, Table IWC-2500-1 requires volumetric and surface examinations on circumferential and longitudinal pressure retaining welds, including branch connections.
RELIEF RE VESTED: ASHE Section XI requires essentially 100$of the weld length be volumetrically examined.Due to piping weld configurations (reducer to tee, pipe to tee, pipe to flange, etc.)volumetric examinations of 100%%u of the weld length was sometimes not feasible.Relief is requested based on weld configurations not being conducive to 100$, volumetric examination (see additional details on Attachment"A" to this relief request).ALTER ATE EXAMI ATION: Pressure retaining welds were surface examined for essential ly 100$of the weld length where possible.Volumetric examinations were performed to the maximum extent possible based on physical I imitations.
Where the component configuration or access precluded or I imited this examination, that fact and to the extent was documented on the Preservice Basel lne Data Sheet.
Attachment A Page 1 of 2 RELIEF REQUEST NO: R2-003 EXAHINATIONS Ultrasonic examinations were conducted to inspect as much of the examination zone as was practical, within geometric, metallurgical, and physical limitations.
When the required ultrasonic examination volume or area could not be examined 100 percent, the examination was considered to be partial and was so noted on the applicable component Data Sheet.Generally, partial examinations were done at fitting to fitting assemblies (explained under limitations) and in areas where integrally welded supports, lugs, etc., preclude access to some part of the examination area.Ultrasonic examinations that produced indications 50 percent of DAC or greater from geometric or metallurgical origin were recorded.Examples of areas that, generally produced such indications are as follows: 1.Inside diameter weld preparation or root configuration and the outside diameter down overlay or toe.2.The inside diameter radius of the tube sheet weld of the steam generators where examined from the tube sheet side.3.The metallurgical structure of austenitic materials.
4.Signal responses from the thread areas of bolting.LIHITATIONS Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examinations requirements of Section XI of the 1980 Code could be applied;consequently, some examinations are limited or not practical due to geometric configuration or accessibility.
Generally these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length.The limitations exist to a lesser degree at pipe to fitting assemblies, particularly where the weld is not ground flush with the pipe O.D.surface.At these joints examinations can be conduced from the pipe side;however, the fitting again limits precludes examination from the opposite side.In most cases, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code required area or volume (generally, the weld and base metal of 1"T" on each side)as possible.However, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100 percent.These areas where complete examination of 100 percent of the required volume of area could not be achieved were indicated and noted to the extent on the examiner's Data Sheet and the limiting cause noted.
Attachment A Page 2 of 2 RELIEF REQUEST NO: R2-003 The principal basis for partial examinations is to identify the inability to examine 100 percent of the required base metal volume for the 1 T distance beyond the edge of the weld on a fitting or component.
Examples are (1)ultrasonic examination of a pipe to elbow assembly, where scanning on the intrados of the elbow causes de-coupling of the sound beam and (2)a pipe to flange or valve assembly where scanning the entire volume on the fitting or component side is limited by configuration.
The resulting coverage is such that examination of the weld, heat affected zone and base metal for 1"T" on indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc.However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by code.In either case, 100 percent of this 1"T" volume cannot be assured, thus a partial examination is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical.
Specific limitations and restrictions for all examinations are as indicated on the specific report Data Sheet.
CAROLINA POWER K LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-004 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM, PRESSURE RETAINING WELDS LOCATED INSIDE OF CONTAINMENT PENETRATIONS (PRESERVICE/INSERVICE APPLICABLE)
CLASS 2 C-C C-F C3.20 C5.11 CODE RE UIREME T: ASME Section XI, Table IWC-2500-1 requires surface and/or volumetric examination on circumferential and longitudinal piping welds.RELIEF RE UESTED: Relief is requested from ASME Section XI requirements as these welds are located inside of conta inment penetrations and are not physically accessible for examination.
ALTER ATE EXAMI ATIO None.Hydrostatic tests and system leakage pressure tests will be performed as required by ASME Section XI requirements.


CAROLINA POWER&LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-005 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM PRESSURE RETAINING WELDS IN PRESSURE VESSELS PRESSURE RETAINING NOZZLE WELDS IN VESSELS CLASS 2 CLASS 2 C-A C-B C-C C1.20, C1.10 C1.30 C2.21, C2.22 C3.10 CODE RE UIREMENT: ASME Section XI, Table IWC-2500-1 requires surface and/or volumetric examinations be performed on pressure retaining we lds and pressure retaining nozzle welds in pressure vessels.BASIS: In instances where component configuration or limited access resulted in the examination of less than 100$, of the code required volume, alternate examination techniques were considered and if, feasible, used.ALTERNATE EXAMINATIO The ultrasonic examinations were performed to the maximum extent possible.Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of material not fully examined were defined.
t ili I
CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R3-001 PRESERVICE EXAMINATION PROGRAM ASME SECTION XI SYSTEMS REQUEST FOR RELIEF FROM CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CLASS CODE CATEGORY CODE ITEM COMPONENT SNUBBERS (PRESERVICE/INSERVICE APPLICABLE)
                ~
CLASS 3 F-C F3.50 CODE RE UIREM T: Table IWF-2500-1 defines the testing and inspection criteria for snubbers.RELIEF RE UESTED: Relief is requested from the functional test requirements for snubbers per article IWF-5000.ALTERNATE EXAMINATION:
LEGEND>    ~
All Shearon Harris component snubbers wIII be selected, inspected, and functionally tested per Section 3/4.7.8 of the Shearon Harris Technlca I Specifications.
Configuration          3  - Test  3 Fault cable Jacket Tcaperaturo (T/cs 1-8)
44f 444 44444444444444444444444444444444444444414444444444444 44444444444444 12/02xs5 NUTECH/PRI iM 4 QUERY RESPONSE REPORT CP8L HARRIS RELIEF REQUEST R1-001: COMPONENTS REQUESTED FOR RELIEF 444444444444 44444444444444444444444444444t444444444444444444444444444444444444O444444t40O44444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SI-02251-SW-DS SI PE, LR-PC, PIPE B-J 89.11 UT-53S P01-01 44 444444444444044444444444444444444t4444444444444444444 44444444444 4 12/05/NUTECH/PRIS QUERY RESPONSE REPORT CPSL-HARRIS RELIEF REQUEST Rl-003: COMPONENTS REQUESTED FO 4et+t4444444t44444044444%844i88440444444444444044444444444444444444444ftt4444444 444444444444444444444444440444444444444444 PAGE: R RELIEF COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-CS-007SI-FW-25 II-FMR-01RC-10-17-FW-2 I I-FMR-01RC-10-17-FW-3 I I-FMR-01RC-10-17-FW-8 I I-FMR-01RC-10-17-SW-L2 I I-FMR-01RC-10-17-SW-L3 I I-FMR-01RC-10-17-SW-PS I I-FMR-01RC-10-17-SW-PB I I-FMR-02RC-10-18-FW-2 I I-FMR-02RC-10-18-FW-3 I I-FMR-02RC-10-18-FW-8 I I-FMR-02RC-10-18-SW-K2 I I-FMR-02RC-10-18-SW-KB I I-FMR-02RC-10-18-SW-LS I I-FMR-02RC-10-18-SW-L7 I I-FMR-03RC-10-19-FW-2 I I-FMR-03RC-10-19-FW-3 I I-FMR-03RC-10-19-FW-5 I I-FMR-03RC-10-19-FW-8 I I-FMR-03RC-10-19-SW-N2 I I-FMR-03RC-10-19-SW-N3 I I-FMR-03RC-10-19-SW-04 I I-FMR-03RC-10-19-SW-05 SI RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC PBCC,T-PC,PIPE PE,RED-VNOZ1AI VNOZ1AO-PE,LR PE,LR-VNOZ1AI PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PE,RED-VNOZ1BI VNOZ180-PE,LR PE,LR-VNOZ1BI PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PE,RED-VNOZ1CI VNOZ1CO-PE,LR VNOZ1CO-PC,PIPE PE,LR-VNOZlCI PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PC,PIPE-PC,NOZ PCrPIPE PCiNOZ SER 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 250.1V 89.11 89.11 89.11 89.31 89.31 89.31 89.31 89.11 89.11 89.11 89.31 89.31 89.31 89.31 89.11 89.11 89.11 89.11 89.31 89.31 89.11 89.11 UT-45S P03-01 UT-45L UT-45L Po1-01 Po1-01 UT-45L UT-45L P01-01 Po 1-01 UT-45L Pol-01 UT-45S P01-01 UT-45S Po 1-01 UT-45L Pol-01 UT-45L P01-01 UT-45L Po 1-01 UT-45L Pol-01 UT-45L Po 1-0'I UT-45L Pol-01 UT-45S P01-01 UT-45L Po 1-01 UT-45L Pol-01 UT-45L P01-01 UT-45L P01-01 UT-45L Pol-01 UT-45L Po 1-01 UT-45L P01-01 UT-45L P01-01 44W444 44tf4ff4440 f4'4f444f44444444444f444444 12/05 cs5 NUTECH/PRI QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R1-003: COMPONENTS REQUESTED FOR RELIEF 444444444444444444444r4444444444444444444444444444444444444444444444444444444444444444444444444 44$444ft4444t44444444tS t44t44 PAGE: 2 44444444f 444444444444f 4444444444444444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-RC-009RC-FW-1 II-RC-022RC-SW-A6 II-RC-023RC-FW-322 Ii-RC-023RC-FW-323 II-RC-023RC-FW-325 II-RC-023RC-FW-326 II-RC-023RC-FW-327 II-RC-023RC-SW-84 II-RC-023RC-SW-85 II-RC-023RC-SW-86 II-RC-023RC-SW-C13 II-RC-023RC-SW-C9 Ii-RC-023RC-SW-D12 II-RC-023RC-SW-DB II-RC-023RC-SW-09 II-RC-023RC-SW-E11 II-RC-023RC-SW-E7 II-RC-023RC-SW-EB II-RC-023RC-92-2-SW-1 II-RC-024RC-FW-318 II-RC-025RC-FW-331 II-RC-025RC-SW-A3 II-RC-025RC-SW-A4 RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC PC,NOZ-PC,PB PE,LR-PC,PIPE PC,PIPE-PC,VLV PC,VLV-PC,PIPE PC,VLV-PC,PIPE PC,PIPE-PC,VLV PBCC,T-PC,PB PC,PIPE-PBCC,T PBCC,T-PC,PIPE PC,PIPE-PC,RED PBCC,TR-PC,PIPE PC,PIPE-PBCC,TR PBCC,T-PC,PIPE PC,PIPE-PBCC,T PBCC,T-PC,PIPE PC,PIPE-PBCC,T PBCC,T-PC,PIPE PBCC,T-PC,PIPE PC,PIPE-PBCC,TR PBCC,T-PC,PIPE PC,NOZ-PC,PIPE PC~PIPE PE LR PE,LR-PC,PIPE 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.31 89.11 89.11 89.11 89.11 UT-45S P01-01 UT-45S P01-01 UT-45S P01-01 UT-455 P01-01 UT-45S P01-01 UT-455 P01-01 UT-45S P01-01 UT-45S P01-01 UT-45S P01-01 UT-455 P01-01 UT-45S P01-01 UT-455 P01-01 UT-455 P01-01 UT-45S P01-01 UT-45S P01-01 UT-45S P01-01 UT-455 P01-01 C UT-455 P01-01 UT-45S P01-01 UT-45S P01-01 UT-45S P01-01 UT-45S P01-01 UT-455 P01-01 tf44444444444444f44444444r4444444444444444444444f44 44f4444t44f444444444t4444444 12/05/a5 NUTECH/PRIS QUERY RESPONSE REPORT CP8 L-HARRIS 4 RELIEF REQUEST R1-003: COMPONENTS REQUESTED FOR RELIEF 4 4 4 4 4 4 4 4 4 44 0 4 4 0 44 4 4 0 4 4 4 4 4 0 444 44 4 444O4444444444444 0 0 444 f f 444 4 0 t 0 4444 4444444 i t'0 t 4 4 O4 4444'4444 44O f 4 4444444444444444444444444 444f44 PAGE: COMPNOEX SYSTEM COMPOES CATEGORY ITEMNO EXSCHD EXREQ II-RC-027RC-SW-A11 II-RC-027RC-SW-812 II-RC-027RC-SW-C3 II-RH-009RC-FW-291 II-RH-009RC-FW-292 II-RH-009RC-SW-A4 II-RH-009RC-SW-AS II-RH-009RC-SW-A6 II-RH-009RH-FW-200 II-RH-009RH-FW-204 I I-RH-010RH-FW-194 I I-RH-010RH-FW-198 I I-SI-017RC-FW-297 II-SI-017SI-FW-604 I I-S I-017SI-FW-605 II-SI-021RC-FW-300 I I-SI-021SI-FW-547 I I-SI-021SI-FW-549 I I-SI-021SI-FW-550 II-SI-022RC-FW-301 I I-SI-022SI-FW-551 II-SI-022SI-FW-553 II-SI-022SI-FW-554 RC RC RC RC RC RC RC RH RH RH RH RC SI SI RC SI SI RC RC SI SI RC PC,PIPE-PF,WN PC,PIPE-PF,WN PC,PIPE-PF,WN PC,PIPE-PC,VLV PCeNOZ-PCePIPE PE,LR-PC,PIPE PC,PIPE-PE,LR PE,LR-PC,PIPE PC,PIPE-PC,VLV PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,VLV-PC,PB PC,PIPE-PBC,S PSW,VLV-PC,PIPE PC,PIPE-PSW,VLV PC,PIPE-PC,NOZ PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,VLV-PCoPIPE PC,PIPE-PC,NOZ PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,VLV-PC,PIPE 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 8-J 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 89.11 UT-45S P01-01 UT-45S PO 1-01 UT-45S P01-01 UT-50S P01-01 UT-505 P01-01 UT-50S P01-01 UT-50S P01-01 UT-50S PO 1-01 UT-SOS P01-01 UT-50S P01-01 UT-535 P01-01 UT-53S P01-01 UT-45S P01-01 UT-45S P01-01 UT-455 P01-01 UT-535 P01-01 UT-505 P01-01 UT-53S P01-01 UT-SOS P01-01 UT-53S P01-01 UT-535 P01-01 UT-535 P01-01 UT-53S P01-01
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444444 444444444444i884444444f444444444444f44444444f4t444404 44444444444444 12/03/NUTECH/PR I 5 QUERY RESPONSE REPORT CP8 L-HARRI S RELIEF REQUEST Rl-004: COMPONENTS REQUESTED FOR 444444444'44444444444488444444444444044444444444440444044j44444ir44444400044444444 444440t444444444444444444'444444444444444 PAGE: 1 RELIEF 40444444444444444444440004 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-PZR-01LSW-06 II-PZR-01LSW-06 II-PZR-01LSW-06 II-PZR-01STHW-01 II-PZR-01STHW-01 II-PZR-01STHW-01 II-PZR-01STHW-04 II-PZR-01STHW-04 II-PZR-01STHW-04 II-RV-001CHW-RV-17 II-RV-001CSW-RV-02 II-RV-001FTHW-RV-18 I I-RV-001FTHW-RV-18 I I-RV-001FTHW-RV-18 I I-RV-001LSW-RV-05 II-RV-001LSW-RV-06 II-RV-001MHW-RV-'ll I I-RV-001MHW-RV-12 I I-RV-001MHW-RV-13 II-RV-001MHW-RV-14 II-RV-001MHW-RV-15 I I-RV-001MHW-RV-16 I I-RV-001STHW-RV" 04 RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC VLSW VLSW VLSW VSTHW VSTHW VSTHW VSTHW VSTHW VSTHW VCHW VCSW VFTHW VFTHW VFTHW VLSW VLSW VMHW VMHW VMHW VMHW VMHW VMHW VSTHW 8-8 B-B 8-8 B-B 8-8 8-8 8-8 8-8 8-8 8-A 8-A 8-A 8-A 8-A 8-A 8-A 8-A 8-A 8-A 8-A 8-A 8-A 8-A 82.12 82.12 82.12 82.11 82.11 82.11 82.11 82.11 82.11 81.21 81.11 81.40 81.40 81.40 Bl.12 81.12 Bl.228 81.228 81.228 81.228 81.228 81.228 Bl.11 UT-00 F01-01 UT-45S Pol-01 UT-605 Pol-01 UT-00 P01-01 UT-45S F0 1-01 UT-60S P01-01 UT-00 Po 1-01 UT-455 P01-01 UT-60S Pol-01 UT-RVS P01-01 UT-RVS P01-01 UT-00 Po 1-01 UT-455 P01-01 UT-60S P01-01 UT-RVS Pol-01 UT-RVS Po 1-01 UT-RVS Pol-01 UT-RVS Pol-01 UT-RVS Pol-01 UT-RVS P01-01 UT-RVS Pol-01 UT-RVS P01-01 UT-RVS P01-01
Page No. VI-I Test Repot't No.        47879-02 TEST PROCEDURE S01ENT1EC SEAYCES                                                              TEST PROOEOURE RO. ~4TETR"O
              . 8 SYSTEMS ATQAIES QAQVP
    . Box 1008, Honlsvl0e, Al SMOT TWX 1910> 9914888. Phene 1205) 8974411                                                          DATE:          AU    t1    198 Revision A k 1  >>.a ELECTRICAL RACEWAY SEPARATION VERIFICATIONTESTING POR THE CAROLINA POWER AND LIGHT COMPANY POR USE IN THE SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 APPROVED BY PROJECT MANAGER:                                          -/-     S
                                                                                                          . Johnson APPROVED BY QUALITYENGINEER:
ayne'Hight PREPARED BY PROJECT ENGINEER:
                                                                                                        . Hazeltin
                                                                                                                        /N REVISIONS                          (jmk)          FORM 1054-1 Rev. 4/74 REV. NO.           DATE                PAGES AFFECTED            BY    APP'L                DESCRIPTION OF CHANGES 9/30/B5          4  10" 11P 14 16P19 22          T                Revised to Enter Interim Procedure and 27-51                                /o-/-  Revisions 1, 2 and 3.
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44444444444444ff44444444t4ff84444t44t44444444440t44f4 4444400044444t 12/03 5 NUTECH/PRIS 4 QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R1-006: COMPONENTS REQUESTED FOR 444444444440404444t44044444'444444t4444444f44444f4440044404f44444444t40fktfOt440444 444444444444tt44444444444444444444444444 PAGE: 2 RELIEF 4 4444440444444444444444444444+444444444444444440044 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-PZR-0 INTHW-12 I I-PZR-01NTHW-'1 2 I I-PZR-01NTHW-13 I I-PZR-01NTHW-13 I I-PZR-01NTHW-13 I I-RV-001RVNOZAI-N-01 II-RV-001RVNOZAO-N-06 II-RV-001RVNOZBO-N-02 II-RV-001RVNOZCO-N-04 II-SG-001SGA-CLMWTHW-15 II-SG-001SGA-CLMWTHW-15 II-SG-001SGA-CLMWTHW-15 II-SG-001SGA-CLNTVW-12 II-SG-001SGA-CLNTVW-12 II-SG-001SGA-CLNTVW-12 II-SG-001SGA-HLMWTHW-14 II-SG-001SGA-HLMWTHW-14 II-SG-001SGA-HLMWTHW-14 II-SG-001SGA-HLNTVW-07 II-SG-001SGA-HLNTVW-07 II-SG-001SGA-HLNTVW-07 II-SG-001SGB-CLMWTHW-15 I I-SG-001SGB-CLMWTHW-15 RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC VNTVWO VNTVWO VNTVWO VNTVWO VNTVWO VNOZ VNOZ VNOZ VNOZ VMTHW VMTHW VMTHW VNTVWO VNTVWO VNTVWO VMTHW VMTHW VMTHW VNTVWI VNTVWI VNTVWI VMTHW VMTHW 8-DB 8-DB 8-DB 8-DB 8-08 8-DB 8-DB 8-DB 8-DB 8-DB 8-08 8-DB 8-DB B-DB 83.110 83.110 83.110 83.110 83.110 83.9S 83.9S 83.95 83.95 83.130 83.130 83.130 83.130 83.130 8-08 8-DB 8-DB B-DB 8-08 8-DB B-DB 8-DB 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 8-DB~83.130 UT-45S P01-01 UT-605 P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-RVS P01-01 UT-RVS P01-01 UT-RVS P01-01 UT-RVS P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 F01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-605 P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 0
Page No. VI-2 Test Report No. 47879-02 Page No.           1 Test Procedure No.           47879-01 SCOPE This document has been prepared by Wyle Laboratories for the Carolina Power and Light Company (CPRL) and encompasses the testing of physical separation, with respect to electrical faults, between Class 1E and non-Class lE electrical systems in representative configurations at Shearon Harris Nuclear Power Plant (SHNPP)    Unit 1.
ttttttttttttttttttttttttttttttttttttttttttttttttttttt tttttttttttttt 12/03 5 NUTECH/PRI QUERY RESPONSE REPORT CP8 L-HARRIS RELIEF REQUEST R1-006: COMPONENTS REQUESTED FOR tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttttttttttttttttttttttttttt tttttt PAGE: 3 RELIEF tttttttttttttttttttttttttttttttttttttttttttttttttt COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I-SG-001SGB-CLMWTHW-15 I I-SG-001SGB-CLNTVW-12 I I-SG-001SGB-CLNTVW-12 II-SG-001SGB-CLNTVW-12 II-SG-001SGB-HLMWTHW-14 II-SG-001SGB-HLMWTHW-14 II-SG-001SGB-HLMWTHW-14 II-SG-001SGB-HLNTVW-07 II-SG-001SGB-HLNTVW-07 II-SG-001SGB-HLNTVW-07 II-SG-001SGC-CLMWTHW-15 II-SG-001SGC-CLMWTHW-15 II-SG-001SGC-CLMWTHW-15 II-SG-001SGC-CLNTVW-12 II-SG-001SGC-CLNTVW-12 II-SG-001SGC-CLNTVW-12 II-SG-001SGC-HLMWTHW-14 II-SG-001SGC-HLMWTHW-14 II-SG-001SGC-HLMWTHW-14 II-SG-001SGC-HLNTVW-07 II-SG-001SGC-HLNTVW-07 II-SG-001SGC-HLNTVW-07 RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC RC VMTHW VNTVWO VNTVWO VNTVWO VMTHW VMTHW VMTHW VNTVWI VNTVWI VNTVWI VMTHW VMTHW VMTHW VNTVWO VNTVWO VNTVWO VMTHW VMTHW VMTHW VNTVWI VNTVWI VNTVWI 8-DB 8-DB 8-08 8-08 B-DB 8-DB B-DB 8-DB B-DB 8-08 8-DB 8-DB B-OB 8-DB 8-DB B-DB 8-DB B-OB 8-DB 8-08 B-OB 8-DB 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 83.130 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 UT-00 P01-01 UT-45S P01-01 UT-60S P01-01 4444444444444444444444t4444444444444444444444444444444 444t4444tt444444444444 12/03 5 NUTECH/PRI QUERY RESPONSE REPORT CPS L-HARRI S RELIEF REQUEST R'1-007: COMPONENTS REQUESTED FOR RELIEF 44444444444444f4f444444404444f4f444f440t44440044fftfffft44ft44440444044444 PAGE: 1 44404444tt4444t444444444f44444444440440444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I-FMR-01RC-10-17-SW-P4 I I-FMR-02RC-10-18-SW-L4 RC PC,PIPE-PC,NOZ RC PCoPIPE-PCoNOZ 8-J B9.31 B9.31 UT-455 P01-01 UT-455 P01-01 44444t++++444444444444444 12/02 5 S08444444+4404444444444444444 4444444444444444444444444440444440 44444444440440400440 NUTECH/PRI QUERY RESPONSE REPORT CPS L-HARR I S RELIEF REQUEST R1-008: COMPONENTS REQUESTED FOR RELIEF 44444404444t44444444444440444444044444404444440044t44440444 44044444444444444444044t444444444 444444 PAGE: 1 44444444444444444444044444444444444444444444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I-P ZR-01 SBW-A 1A I I-PZR-01SBW-A18 I I-PZR-01SBW-AZA II-PZR-01SBW-A28 II-PZR-01SBW-A3A I I-PZR-01 SBW-A38 II-PZR-0 ISBW-A4A II-PZR-01SBW-A48 RC RC RC RC RC RC RC RC VI, PSB VI, PSB VI, PSB VI, PSB VI, PSB VI, PSB VI, PSB VI,PSB 8-H 8-H 8-H 8-H 8-H 8"H 8-H 8-H 88.20 88.20 88.20 88.20 88.20 88.20 88.20 88.20 MT MT MT MT MT MT MT MT P01-01 P01-01 P01-01 P01-01 P01-01 P01-01 P01-01 P01-01 44+++++<44444444444444444444444444444404t44t444t444444 44444444444444 12/02i4$5 NUTECH/PR I S QUERY RESPONSE REPORT CPS L-HARRI S RELIEF REQUEST R1-009: COMPONENTS REQUESTED FOR ef444t+44f44444488f88448t48t84444t80444444ff004444444444f444444444f444fft444tf4 444444444444444444444444444'444444444444 444444 PAGE: 1 RELIEF 4 4444444440444444444444444444444444444444444444444t COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-RCP-01RCPA-SBOLT(8)
Objectives The purpose of this procedure is to present the requirements, procedures, and sequence to test the design adequacy of worst case configurations in the following electrical separation situations:
II-RCP-01RCPB-SBOLT(8)
      ~    Horizontal cable tray to parallel conduit (see Figures      2 and 3)
II-RCP-01RCPC-SBOLT(8)
      ~:    Free Air Separation without barriers (see Figure 4)
RC BPSB RC BPSB RC BPSB B-G-2 87.60 B-G-2 87.60 VT-1 VT-1 P01 01 P01-01 B-G-2 87.60 VT-1 P01-01 4444444444444444444444 12/04 5 44444444444444444444444444t44444 44444$444444444444444f 4444t4f O4 44444440444044448444444444 NUTECH/PRI QUERY RESPONSE REPORT CP8 L-HARRI 5 RE)IEF REQUEST R2-001: COMPONENTS REQUESTED FOR RELIEF 4444$444444444444444444444404444444440444444444444044444444444444 444444444444444444444444 4 4 4'4 4 4 PAGE: 1 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4I il 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-AF-006AF-FW-245 II-CS-001CT-SW-J3 II-CS-001CT-SW-J3A II-CS-006CS-SW-I4 II-CS-006CS-SW-J6 II-CS-007CS-SW-A4 II-CS-021CS-FW-111A II-CS-021CS-FW-211A II-CS-021CS-H-0011I(4)
      ~    Conduit to conduit and free air (see Figure 5)
II-CS-021RH-SW-86A II-CT-007CT-FW-35A II-CT-014CT-FW-174 II-CT-016CT-SW-A3 II-FMR-01FW-H-0212I(8)
      ~    Vertical cable tray to horizontal cable tray (see Figure 6)
II-FMR-01MS-FW-229 II-FW"002AF-FW-257 II-FW-002AF-FW-258 II-FW-003AF-FW-269 II-FW-004AF-FW-277 II-FW-004AF-FW-277 I I-RH-001SI-FW-6A I I-S I-OOBRH-SW-K3A I I-SI-009CT-FW-96 AF CT CT CS CS CS CS PC,PIPE-PBCC,T PE,LR-PC.PIPE PLSW,P PCeRED-PCiPIPE PC, PIPE-PC, PIPE PC,RED-PC,PIPE PLSW,P CS.PLSW,P CS RH CT CT CT FW MS AF AF AF AF SI RH CT PC,PIPE-PI,LUGN PLSW,P PLSW,P PI,FHI-PE,LR PE,LR-PC,PIPE PC,PIPE-PI,LUGN PC,PIPE-PI,FHI PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,PIPE-PC,VLV PC,PIPE-PC,VLV PC,PIPE-PC,VLV PLSW,P PLSW,P PE,LR-PC,PIPE FSAR SER SER SER SER SER C-F C-F C-C C-F C-F SER SER C-C C-F FSAR FSAR FSAR C-F FSAR C-F C-F SER 6.6.88 250.1S 250.1S 250.IV 250.1V UT-45S P04-01 PT P03-01 PT P03-01 UT-455 P03-01 UT-455 P03-01 C5.12 C5.12 C3.20 CS.12 C5.32 250.1V 250.1V C3.20 C5.21 6.6.88 6.6.88 6.6.88 C5.11 6.6.88 C5.12 CS.11 250.1S PT PT P01-01 F01-01 PT P01-01 PT P01-01 PT P01-01 UT-455 P03-01 UT-45S P03-01 MT P01-01 UT-45S P01-01 UT-45S P04-01 UT-455 P04-01 UT-45S P04-01 MT P01-01 UT-45S P04-01 PT PT PT P01-01 P01-01 P03-01 250.1V UT-45S P03-01 12/04 5 4\44 4 4 4 4 4 4 4 44 4 4 4 4 4 4 4 4 4 4 4 4 44 444444444f4444444t444444444444444444 444444444444444444 NUTECH/PRI
Applicable Documents Wyle Laboratories Technical Proposal for Cable Separation Test Program for Carolina Power and Light Company, No. 543/3737/GH, dated May 15, 1985.
..c PAGE: QUERY RESPONSE REPORT CP&L-HARRIS RELIEF REQUEST R2-001: COMPONENTS REQUESTED FOR RELIEF f444444444444404404444t44444444444444f44444f44ff4444404t4444444ff4444ff4f4f4444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I-SI-027SI-H-0181 I (8)I I-SI-032SI-FW"979 II-SI-032SI"SW-C3 SI PC, PIPE-PI, LUGN SI PC,PIPE-PSW,VLV SI PF>WNO-PCsPIPE C-C SER SER C3.20 250.1S 250.1S PT PT PT P01-01 P03-01 P03-01 44444444 12/04>a5 444444444444444444 444444444444444444444444444444444444444444444 44444444444 NUTECH/PRI QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED'444f4ff4404tft444tf4'44f444ffftttt44ffff44f 444444444444444444444044444444444444444444 444444 PAGE: 1 FOR RELIEF 44444444444844444444444444444444444440 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-AF-005AF-FW-249 II-AF-005AF-FW-251 II-AF-006AF-FW-246 II-AF-007AF-FW-239 II-AF-007AF-FW-241 II-CS-006CS-FW-102 II-CS-006CS-FW-103 II-CS-006CS-FW-104 II-CS-006CS-FW-105 II-CS-006CS-FW-106 II-CS-006CS-FW-122 II-CS-.006CS-FW-123 II-CS-006CS-FW-124 II-CS-006CS-FW-125 II-CS-006CS-FW-126 II-CS-006CS-FW-130 II'-CS-006CS-FW-132 II-CS-006CS-FW-201 II-CS-006CS-FW-202 II-CS-006CS-SW-A3 II-CS-006CS-SW-D4 II-CS-006CS-SW-D5 II-CS"006CS-SW-F3 AF PC,VLV-PC,PIPE AF PC,VLV-PC,PIPE AF PC>VLV-PCePIPE AF PC,VLV-PC,PIPE AF PC,VLV-PC,PIPE CS PC,PIPE-PC,VLV CS PC,VLV-PC,PIPE CS PCoPIPE-PCoVLV CS PC,VLV-PC,PIPE CS PC,PIPE-PBCC,T CS PC,PIPE-PC,VLV CS PC,VLV-PC,PIPE CS PC,PIPE-PC,VLV CS PC,VLV-PC,PIPE CS PC,PIPE-PBCC,TR CS PC,VLV-PC,PIPE CS PC,VLV-PC,PIPE CS PC,PIPE-PC,VLV CS PC,VLV-PC,PIPE CS PF,RFWN-PC,RED CS PBCCoTR PC.PIPE CS PC,PIPE-PBCC,TR CS PBCC,TR-PC,PIPE FSAR FSAR FSAR FSAR FSAR SER SER SER SER SER SER SER SER SER SER SER SER SER SER SER SER SER SER 6.6.88 6.6.88 6.6.88 6.6.88 6.6.88 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.IV 250.1V UT-45S P04-01 UT-45S P04-01 UT-455 P04-01 UT-45S P04-01 UT-45S P04-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 250.1V UT-45S P03-01 eeee4e 4f4444ee444444444044440444444444444444444444044444444 44444444444 12/04/5 NUTECH/PRI QUERY RESPONSE REPORT CPSL-HARRIS 4 RELIEF REQUEST R2-003: COMPONENTS REQUESTED 444444444440444444444444444444444444444t44444444444444044444444444444444t444440 44444444444444t444444444444444444444444444 444444 PAGE: 2 FOR RELIEF 4 44444444444444444444444444444444444444444444444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-CS-006CS-SW-F4 II-CS-007CS-FW-203 II-CS-007CS-FW-204 II-CS-007CS-FW-205 II-CS-007CS-FW-92 II-CS-007CS-FW-93 II-CS-007CS-FW-94 II-CS-007CS-FW-95 II-CS-007CS-FW-96 II-CS-007CS-SW-A3 II-CS-007CS-SW-D3 II-CS-007CS-SW-D4 II-CS-007CS-SW-D5 II-CS-007CS-SW-06 II-CS-007CS-SW-D7 II-CS-022CS-FW-561 II-CS-022CS-FW-562 II-CS-022CS-SW-85 II-CS-022CS-SW-86 II-CS-092CS-FW-3029 II-CT-001CT-FW-1 II-CT-001CT-FW-8 II-CT-001CT-FW-9 CS CS CS CS CS CS CS CS CS CS CS CS CS CS CS CS CS CS CS CS CT CT CT PC,PIPE-PBCC,TR PCoPIPE-PCiVLV PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,PIPE-PC,VLV PC,VLV-PC,PIPE PC,PIPE-PC,VLV PCJVLV-PC,PIPE PC,PIPE-PC,RED PF,RFWN-PC,RED PBCC AT-PC,PIPE PC,PIPE-PBCC,T PBCC,T-PC,PIPE PC,RED-PBCC,T PBCC,T-PC,RED PC,VLV-PC,PIPE PC,PIPE-PI,FHB PBCC,T-PC,RED PC,PIPE-PBCC,T PC,PIPE-PC,VLV VNOZ180-PC,PIPE PC,PIPE-PC,VLV PC,VLV-PC,PIPE SER SER SER SER SER SER SER SER SER SER SER SER SER SER SER FSAR FSAR SER SER FSAR SER SER SER 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.IV 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 6.6.88 6.6.88 250.1V 250.1V 6.6.88 250.1V 250.1V 250.1V UT-455 P03-01 UT-455 P03-01 UT-45S P03-01 UT-45S P03-01 UT-455 P03-01 UT-455 P03-01 UT-455 P03-01 UT-45S P03-01 UT-455 P03-01 UT-45S P03-01 UT-45S P03-01 UT-455 P03-01 UT-45S P03-01 UT-455 P03-01 UT-45S P03-01 UT-455 P04-01 UT-45S P04-01 UT-455 P03-01 UT-455 P03-01 UT-455 P04-O'I UT-45S P03-01 UT-45S P03-01 UT-45S P03-01
IEEE Std. 383-1974, "IEEE Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations."
IEEE Std. 384-1974, "IEEE Trial Use Standard Criteria for Separation of Class 1E Equipment and Circuits."
United States Nuclear Regulatory Commission Guide 1.75, Revision 1, "Physical Independence of Electric Systems."
IEEE Std. 323-1974, "IEEE Standard                for Qualifying Class 1E Equipment for Nuclear Power Generating Stations."
Code of Federal Regulations, Section 10, Part 21.
Code of Federal Regulations, Section 10, Part 50, Appendix B.
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444444+44444t4444444444444444 12/04 u5 4444444444444444444444444444444 44444444444 NUTECH/PRI QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED 444'44444t4444444444444440444444444044'444444444 44$f044444444444444444444444444 PAGE:-4 FOR RELIEF 4044044444044444444444444448%444444444444444444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-FW-004FW-FW-572 II-FW-004FW-SW-C3 II-MS-001MS-FW-258A II-MS-001MS-FW-259A I I-MS-001MS-SW-A 1 I I I-MS-001MS-SW-81 1 I I-MS-001MS-SW-C 1 1 II-MS-001MS-SW-K2A II-MS-001MS-SW-M28 II-MS-002MS-FW-566 II-MS"002MS-FW-567 II-MS-002MS-FW-568 II-MS-002MS-FW-690 II-MS-002MS-FW-691 II-MS-002MS-FW-692 II-MS-007MS-FW-678 II-MS-009MS-FW-583 II-MS-009MS-FW-586 II-MS-009MS-FW-589 II"RH-001RH-FW-8 II-RH-001RH-FW-9 II-RH-001RH-SW-EB II-RH"002RH-FW-21 FW FW MS MS MS MS MS MS MS MS MS MS MS MS MS MS MS RH RH RH RH PC,VLV-PC~PIPE PC,PIPE-PE,LR PLSW,P PLSW,P PC,PIPE-PC,NOZW PC,PIPE-PC,NOZW PC,PIPE-PC,NOZW PLSW,P PLSW,P PC,PIPE-PC,VLV PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,PIPE-PC,VLV PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,PIPE-PC,VLV PC,PIPE-PC,VLV PC,PIPE-PC,VLV PC,PIPE-PC,VLV PE, LR-VNOZ 1 A I PBCC,T-PC,PIPE PBCC,T-PF,WNO FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR FSAR SER SER SER PE, LR-VNOZ1BI SER 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 6.6.8C 250.1V 250.1V 250.1V 250.1V UT-45S 805-01 UT-455 P05-01 UT-455 P05-01 UT-455 P05-01 UT-455 POS-01 UT-45S P05-01 UT-455 P05-01 UT-455 P05-01 UT-455 P05-01 UT-455 P05-01 UT-45S P05-01 UT-45S POS-01 UT-455 P05-01 UT-45S POS-01 UT-455 P05-01 UT-455 P05-01 UT-45S P05-01 UT-455 P05-01 UT-45S P05-01 UT-45S P03-01 UT-45S P03-01 UT-455 P03-01 UT-455 P03-01
Page No. VI-3 Test Report No. 47879-02 Page No.          2 Test Procedure No.            47879-01 SCOPE (Continued)
Equipment Description This test procedure encompasses testing of the following IEEE Std. 383-1974 qualified power, control, and instrumentation cables as descr ibed below.
Cable*            CPRL Item No.                      Desc        tion                              Mark No.
1                    1/C 500 MCM                        p          D25-11 2                  Triplex 350 MCM                        p          D25-10 3                  Triplex 4/0 AWG                      p          D25-08 4                        1/C 2 AWG                        p          D25-05 5                        1/C 6 AWG                        p          D25-03 6                       1/C'10 AWG                        p          D25-01 7                      1/C 6 AWG                        C          D59-03 8                      1/C 10 AWG                        C          D59-02 9                      2/C 10 AWG                        C          D50-01 10                      2/C 12 AWG                        C          D50-06 11                      2/C 16 AWG                        C          D50-11 12                    1  Pair 16 AWG                      L          D60-01 P  Power. Type Cable C Control Type Cable L Low Energy Type Cable Test Sequence The test program shall be performed in the following sequence:
o      Test specimen identification
~'    Control Cable Screening Tests (determination of ignition capability of control cables in a cable tray)
Power  Cable  Screening    Tests        (worst  case  cable  determination  and horizontal tray to parallel conduit)
Configuration Number    1  Test (Free Air Separation Test without barriers) r    Configuration Number    2  Tests (Conduit to Conduit and Cable in Free Air Tests)
~r    Configuration Number    3  Tests (2-Tray Stack with vertical tray)
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444444444444f4444444t444444444444444444f4444f444t4444 44444444444 12/04 5 NUTECH/PRI QUERY RESPONSE REPORT CP8 L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED 4'44f44f4444444444444444444444444444044444444%4444404444f44040444404444444404 444444444444444444t44444444444444444 PAGE: 7 FOR RELIEF 4444044r444444444444444444444444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SI-010SI-SW-Cj I I-S I-010S I-SW-CB I I-SI-010SI-100-FW-275 I I-SI-010SI-100-FW-276 I I-SI-010SI-99-FW-269 I I-SI-0105 I-99-FW-270 I I-S I-0 105 I-99-FW-271 I I-SI-011SI-FW-475 I I-SI-01 1SI-FW-476 I I-SI-016SI-FW-36 I I-SI-016SI-SW-D4 II-SI-016SI-SW-05 I I-SI-019SI-SW-04 II-SI-019SI-SW-05 I I-SI-019SI-14-FW-276 I I-SI-019SI-14-FW-277 II-SI-021SI-FW-557 I I-SI-0215 I-FW-558 II-SI-022SI-FW-559 I I-SI-022SI-FW-564 I I-SI-023SI-FW-562 I I-SI-023SI-FW-563 I I-SI-024SI-213-FW-573 SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI PC e PIPE-PC i PIPE PC,PIPE-PBCC,T PC,RED-PC,PIPE PBCC,T-PC,PIPE PBCC,T-PC,PIPE PC,PIPE-PC
Page No. VI-4 Test Repor t No. 47879-02 Page No.          3 Test Procedure No.            47879-01 2.0    TEST REQUIREMENTS 2.1    Acceptance Criteria 2;1.1  Insulation Resistance Test resistance on all "target cables"* shall be greater than 1.6 x 10 ohms with a potential of 500 VDC applied for 60 seconds. Before testing insulation 2.1.2'nsulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the Overcurrent Test.
~VLV PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,VLV-PC,PIPE PC,PIPE-PBCC,T PBCCrT PC~PIPE PBCC,T-PC,PIPE PBCC,T-PC,PIPE PBCC,T-PC,PIPE PI,FHI-PC,PIPE PC,PIPE-PBCC,T PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,PB-PC,VLV PC,VLV-PC,PIPE PC,VLV-PC,PIPE PC,PIPE-PC,VLV PC,PB-PC,VLV SER SER SER SER SER SER SER SER SER SER SER SER SER SER SER SER C-F C-F C-F C-F C-F C-F C-F 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V 250.1V CS.21 CS.21 C5.21 C5.21 C5.21 C5.21 C5.21 UT-45S P03-01 UT-455 P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-455 UT-45S P03-01 P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 UT-53S P01-01 UT-50S P01-01 UT-53S P01-01 UT-53S F01-01 UT-53S P01-01 UT-50S P01-01 UT-45S P01-01 444444 44444444t44444844444444 12/04 5 0444444440444444444444444r4444 4444444444444444 NUTECH/PRI QUERY RESPONSE REPORT CPS L" HARRI S RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RE 444444444t4444444f444f4444f4444444444444444f44444444444444444444444444444444444440444 444444444444444444444444448444044444 444444 PAGE: 8 4 LIEF 44444044444444444444444444t44444444444444t44444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHO EXREQ I I-SI-025SI-FW-574 II-SI-025SI-FW-575 II-SI-025SI-FW"576 II-SI-025SI-FW-577 II-SI-025SI-FW-578 II-SI-025SI-FW-579 I I-SI-025SI-FW-580 II-SI-025SI-FW-583 II-SI-025SI-FW-584 I I-SI-025SI-SW-A6 II-SI"025SI-SW-83 II-SI-025SI-SW-84 II-SI-025SI-SW-B5 II-SI-025SI-SW-05 II-SI-025SI-SW-06 II-SI-025SI-SW-E3 II-SI-025SI-SW-E4 I I-SI-025SI-SW-F5 II-SI-025SI-SW-G3 II-SI-026SI-FW"581 II-SI-026SI-FW-582 II-SI-02651-FW-590 I I-SI-026SI-FW-591 SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI SI PC,VLV-PC,PIPE PC,PIPE-PC,VLV PI, FHI-PC, PIPE PBCC,TR-PC,PIPE PC,PB-PC,VLV PC,VLV-PC,PB PC,VLV-PC,PIPE PBCC,T-PC,PIPE PCoPB-PCeVLV PFeRWNR-PCePIPE PC,PIPE-PF,RFWN PBCC,TR-PC,PIPE PC,PIPE-PBCC,TR PC~PIPE PE~LR PE,LR-PC,PIPE PC,PB-PBCC,T PC,PIPE-PBCC,T PC,PB-PF,RFWN PF,RFWN-PC,PB PC,PIPE-PC,VLV PBCC,T-PC,PIPE PC,VLV-PC,PIPE PC,PIPE-PC,VLV C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F C-F CS.21 CS.21 C5.21 CS.21 C5.21 C5.21 C5.21 C5.21 C5.21 C5.21 C5.11 C5.21 C5.21 C5.21 C5.21 CS.21 CS.21 C5.21 C5.21 C5.21 C5.21 C5.21 C5.21 UT-60S P01-01 UT-605 P01-01 UT-605 UT-455 Po 1-01 P01-01 UT-455 P01-01 UT-45S P01-01 UT-455 P01-01 UT-45S P01-01 UT-455 Po 1-01 UT-455 Po 1-01 UT-605 Pol-O'I UT-60S P01-01 UT-605 Pol-01 UT-455 Pol-01 UT-455 Pol-01 UT-45S P01-Ol UT-45S Pol-01 UT-455 Po 1-01 UT-455 P01-01 UT-45S Pol-01 UT-455 Po 1-01 UT-60S P01-01 UT-605 P01-01 4
H h Potential Test There shall be no evidence of insulation breakdown or flashover with a potential of 2200 VAC (1600 VAC for Twisted Fair 16 AWG cables) applied for one minute.
444444 4444444444444444444444444t444444444444444404t44444444 44404444444 12/04/a5 NUTECH/PRIS QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED 44444444444444444444444444r44444444444444444440044444444440444444ft4444444444444 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4r 4 4 4 4 4 4 4 4 4 4 4 4 4 4 404404 PAGE: 9 FOR RELIEF 444444444t4444t444444444t4cf4444%4r44444rtttkt4tktkt4444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SI-026SI-FW-592 II-SI-026SI-FW-594 II-SI-026SI-SW-G3 II-SI-026SI-SW-G5 II-SI-027SI-FW-606 II-SI-027SI-SW-K3 II-SI-027SI-SW-K5 II-SI-027SI-SW-K6 II-SI-028SI-FW-608 II-SI-028SI-FW-609 I I"SI-028SI-FW-610 II-SI-028SI-SW-A5 II-SI-028SI-SW-A6 II-SI-028SI-SW-A7 II-SI-028SI-SW-AB II-SI-028SI-SW-A9 II-SI-029SI-SW-C10 I I-SI-029SI-SW-C1 1 I I-SI-0295 I-SW-C12 I I-SI-029SI-SW-C14 II-SI-029SI-SW-C4 II-SI-029SI-SW-C5 II-SI-029SI-SW"C7 SI SI SI SI SI SI SI SI SI SI SI Sj SI SI SI SI SI SI SI SI SI SI SI PI,FHI-PC,PIPE PC,PB-PC,VLV PC,PIPE-PF,RED PC,PIPE=PBCC,TR PC,PB-PC,VLV PC,PB-PBCC,T PBCC,T-PC,PIPE PBCCeT-PCoPIPE PC,RED-PC,PIPE PI~FHI-PC, PIPE PC,PB-PC,VLV PC,PIPE-PBCC,T PBCC,T-PC,PIPE PC,PIPE-PC,RED PBCC,T-PC,PIPE PC,PIPE-PC,RED PC,PIPE-PBCC,T PBCC,T-PC,RED PBCCsT-PC>PIPE PC,PIPE-PBCC,T PBCC,T-PC,PIPE PBCC,T-PC,PIPE PCsPIPE-PBCCeT C-F C-F C-F C-F C-F SER SER SER C-F C-F C-F C-F C-F C-F C-F C-F SER SER SER SER SER SER SER C5.21 C5.21 C5.21 C5.21 C5.21 250.1V 250.1V 250.1V C5.21 C5.21 C5.21 C5.21 C5.21 C5.21 C5.21 C5.21 250.1V 250.1V 250.1V 250.1V 250.1V 250.IV 250.1V UT-60S P01-01 UT-45S P01-01 UT-60S P01-01 UT-605 P01-01 UT-45S P01-01 UT-60S P03-01 UT-45S P03-01 UT-45S P03-01 UT-605 P01-01 UT-60S P01-01 UT-455 P01-01 UT-60S P01-01 UT-60S P01-01 UT-60S P01-01 UT-605 P01-01 UT-60S P01-01 UT-45S P03-01 UT-45S P03-01 UT-455 P03-01 UT-455 P03-01 UT-45S P03-01 UT-45S P03-01 UT-45S P03-01 0
2.1.3    Cable Continui      Test Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 480 VAC (120 VAC for control cables and 50 VAC for instrument cables) before, during, and after the overcurrent test.
Cable                No.             CPRL            Cable              Rated Size            Conductors          LD. No.         Ttpe  Volt~e    Current 16 AWG              1 Tw. Pr.         D60-01                 50 VAC 16 AWG                  2/C             D50-11            C   120 VAC      10A 10 AWG                3-1/C           D25-01            p  480 VAC      40A 500 MCM                  3-1/C           D25-11             p  480 VAC      430A 2.1.4  Tolerances All target cable voltages specified in this procedure shall be maintained within a
        +3% tolerance.       All target cable currents shall be maintained within a +10%
toler ance.
AQ  fault cable currents shall be maintained within a+3% tolerance.
The term "target cable" refers to energized and monitored nonfault cables used in this program.
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Page No. VI-5 Test Report No. 47879-02 Page No.          4 Test Procedure No.            47879-01, Revision A 3.0   TEST PROGRAM 3.1  Test Specimen Identification An inspection shall be performed upon receipt of the test specimen components at Wyle Laboratories. This inspection will ensure that the test specimens are as described in Paragraph 1.3. Applicable manufacturer, model, part and serial numbers shall be verified and recorded on a Test Specimen Inspection Sheet. The test specimens shall be labeled to facilitate identification throughout the test program.
3.2  Control Cable Screening Tests Five tests shall be conducted in cable tray with various cable overloads to determine whether or not the control-type cables have the potential to support combustion or have the capability to generate enough heat to adversely affect the operation of any cabling located 1 inch or more from a faulted cable in a control tray. A 1-inch conduit, with a single pair 16 AWG target cable inside, shall be mounted 1 inch above the faulted cable.
3.2.1 Pt~ose The purposes  of these tests  are- to:
: 1. Demonstrate that the worst case electrical fault, in a control cable tray, does not have the potential to support combustion or have the capability to generate enough heat to adversely affect the operation of any cabling located 1 inch or more from a faulted cable in a control tray prior to open-circuiting and thus separation distances less than those specified in IEEE Standard 384-19?4-and Nuclear Regulatory Guide 1.75 are acceptable.
: 2. Demonstrate the adequacy, of design where a cable/raceway of one safety division is located within 1 inch of a faulted NNS cable, or a cable of a redundant safety division, in a control tray.
3.2.2 Test    ecimen Pre aration The test specimens shall be mounted to the unistrut frame of Figure 1. This apparatus shall be assembled to the indicated dimensions by Wyle technicians using materials supplied by CPtst:L. The following guidelines shall be observed with regard to the materials and construction of this assembly:
: 1. The faulted cable shall be one of the following cables from CPRL stock:
Test No.            Fault Cable Size                      CPRL LD. No.
2/C 16 AWG                            D50-11 2/C 12 AWG                            D50-06 2/C 10 AWG                            D50-01                  A 3-1/C 10 AWG                            D59-02    (D25-01)      A 3-1/C 6 AWG                            D59-03    (D25-03)      A WYLE LABORATORIES Huntsville Facility


444 444444444444t44f4444444f4444f444444444444444444t44444 44444444444444444444444444444444 12/04 5 NUTECH/PRI QUERY RESPONSE REPORT CPB L-HARR I S RELIEF REQUEST R2-005: COMPONENTS REQUESTED FOR RELIEF 4444f4444444444444f4ff4t4f4444f44444444444444444444444t44044044ff0f4444444444444444444444f4444444404 4444444 444444 PAGE:-2 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-RHX-01CHTSW-04 II-RHX-01CHTSW-05 II-RHX-01CHTSW-05 II-RHX-01CHTSW-06 II-RHX-01CHTSW-06 II-RHX-01HSTSW-A'I II-RHX-01TSTSW-07 II-RHX-O'ITSTSW-07 II-RHX-01TSTSW-07 II-RHX-01TSTSW-08 II-RHX-01TSTSW-08 II-RHX-01TSTSW-08 II-RHX-01TSTSW-08 II-RHX-01TSTSW-09 II-RHX-01TSTSW-09 I I-RHX-01TSTSW-09 II-RHX-01TSTSW-10 II-RHX-01TSTSW-10 I I-RHX-01TSTSW-10 II-RHX-01TSTSW-11 II-RHX-01TSTSW-11 II-RHX-01TSTSW-11 I I-RHX-01TSTSW-1 1 CS VCHW CS VCHW CS VCHW CS VCHW CS VCHW CS VI,LUG CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW CS VTSTVW C-A C-A C-A C-A C-A C-C C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C-A C1.20 C1.20 C1.20 C1.20 C1.20 C3.10 C1.30 C1.30 C1.30 C1.30 C I.30 C1.30 C1.30 C1.30 C1.30 C1.30 C1.30 C1.30 C1.30 C1.30 C1.30 C1.30 C1.30 UT-45L P01-01 UT-00 P01-01 UT-45L P01-01 UT-00 P01-01 UT-45L P01-01 PT P01-01 UT-00 P01-01 UT-45L P01-01 UC 45L P01-01 UT-OO P01-01 UT-45L P01-01 PT P01-01 PT P01-01 UC-45L P01-01 UC-45L P01-01 UT-00 P01-01 UT-45L P01-01 UC-45L P01-01 UT-00 P01-01 UT-45L P01-01 UC-45L P01-01 UT-00 P01-01 UT-45L P01-01
Page iNo. VI-6 Test Report No. 47879-02 Page No..        5 Test Procedure No.          47879-01 3.0      TEST PROGRAM (Continued)
Control Cable Screening Tests (Continued) 3;2'.2.2 Test  S  ecimen Pre aration (Continued)
The fault cable shall be the top centermost cable inside an 8'           24" x 4" ladder rung cable tray filled to the top of the siderails with de-energized contr ol-type cables.
: 2. Nine 1/C 10 AWG cables shall be mounted underneath and around the faulted cable per Figure 2. These cables shaQ be energized. and their conductor temperatures increased to 90oC +5oC prior to applying the fault current to the fault cable. This shall be done to simulate the heat which the fault cable would experience in a cable tray of energized cables.
: 3. The ends of the faulted cable from their termination to the edge of the cable tray shall be wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape per'Figure 7. This shall be done as a safety measure to ensure that any ignition that might occur is contained to the cable tray area.
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: 4. A 10-foot long, 1-inch rigid steel conduit shall be mounted parallel to and 1 inch above the fault cable.       This conduit shall contain a single pair 16 AWG target cable (CPRL I.D. No. D60-01). The 1-foot section of this conduit which extends past the cable tray shall be wrapped with a single layer, 50% overlap, of SILTEMP,WT-65 covered with a single layer, 50%
overlap, of 3M No. 69 glass tape.
5;    Photographs shall be taken of the test setup.
: 6. A 1/2-inch VHS recording shall be taken of the                Overcurrent Test encompassing the entire application of the test current.
3.2.3    Instrumentation Setu 3.2.3.1  Thermoco      le Locations A total of 35 Type "K" thermocouples shall be utilized for these tests.           These thermocouples shall be mounted as descr ibed below:
Channel No.                                         Location 1-8          Mounted to the jacket of the fault cable. These thermocouples shall be spaced approximately 12 inches apart.
9 2  10        Mounted to the conductors of the fault cable at the two series connections.
WYLE LABORATORIES Huntsville Facility


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Page No. VI-7 Test Repor  t No. 47879-02 Page No.          6 Test Procedure No.            47879-01 3.0      TEST PROGRAM (Continued) 3;2'. Control. Cable Screening Tests (Continued) 3.2.3    Instrumentation  Se      (Continued)
Channel No.                                            Location 11-16          Mounted to the conductors of the three cables adjacent to the faulted cable. Two thermocouples shall be mounted to each cable with one thermocouple at each series connection.
17-24          Mounted to the jacket of the single pair 16 AWG target cable inside the 1-inch conduit. These thermocouples shall be spaced approximately 12 inches apart and shall be even with the eight fault cable thermocouples.
25  ttt: 26      Mounted underneath the 1-inch conduit per Figure 2.
27-35          Mounted 1 inch above and 1 inch horizontally from the fault cable in three groups of three thermocouples per Figure 2.
These ther mocouples shall be monitored using a Fluke Datalogger feeding a high-speed printer. The datalogger shall be operated at its maximum rate throughout the-Overcurrent Test.
, 3-2.3.2 Electrical Monitorin The voltage and current of the target cable and the fault cable current shall be continuously monitored with an oscillograph recorder. The oscillograph shall be operated at the O.l-inch per minute rate throughout the Overcurrent Test. The oscillograph channels shall be as specified in the following table:
Channel No.                  S    al                        Location Current                        Tw. Pr. 16 AWG Voltage                        Tw. Pr. 16 AWG Current                          Fault Cable A digital multimeter shall be utilized            to measure voltage and current of the target cable prior to, during, and after          the Overcurrent Test. This data shall be recorded to provide accurate evidence              of the specimen's capability to conduct rated current at 50 VAC throughout the            Overcurrent Test.
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Page No. VI-8 Test Repor t No. 47879-02 Page No.         7 Test PIocedure No.         47879-01 3.'0    TEST PROGRAM (Continued) 3.2    Control Cable Screening Tests (Continued) 3.2.4  Baseline Functional Tests The baseline functional tests shall consist of Insulation Resistance and High Potential measurements on each of the target cables. These tests shall be performed as described below:
COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SG-001SGC-FWNTSW-05 II-SG-001SGC-FWNTSW-05 II-SG-001SGC-FWNTSW-05 II-SG-001SGC-MSNIR-15 II-SG-001SGC-MSNTHW-01 II-SG-001SGC-MSNTHW-01 II-SG-001SGC-MSNTHW-01 II-SG-001SGC-STHW-02 II-SG-001SGC-STHW-02 II-SG-001SGC-STHW-02 II-SG-001SGC-TSTSW-09 II-SG-001SGC-TSTSW-09 II-SG-001SGC-TSTSW-09 RC VNTVWI RC VNTVWI RC VNTVWI RC VNIR RC VNTVWO RC VNTVWO RC VNTVWO RC VSTHW RC VSTHW RC VSTHW RC VTSTVW RC VTSTVW RC VTSTVW C-B C-B C-B C-B C-B C-B C-B C-A C-A C-A C-A C-A C-A C2.21 C2.21 C2.21 C2.22 C2.21 C2.21 C2.21 C 1.20 Cl.20 C 1.20 Cl.30 Cl.30 C1.30 UT-00 Po 1-01 UT-45S P01-01 UT-60S P01-Ol VOL P01-01 UT-00 Pol-01 UT-455 P01-01 UT-60S P01-01 UT-00 Pol-01 UT-455 Pol-01 UT-605 PO'1-01 UT-00 P01-01 UT-455 Pol-01 UT-605 Pol-01 ISOMETRIC DRAMING II-AF-00100 Revision Number<Does not appear as part of component number)ISO Number (Appears as first nine characters of component number) as+4444444444444444444444444444444444444444444f4444444444 NUTECH CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 44444444444f4444444444fOt44f444444444444444444f4444 4t 44444f444444444 PRISIM 4 4444444 PAGE 39 REVISION RRS 1 DATE 85/12/04 REFERENCE KEY DESCRIPTION II-ACC-0100 SAFETY INJECTION ACCUMULATOR TANKS A,8,8C II-AF-00100 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.001 REVISION NO.00 II-AF-00200 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.002 REVISION NO.00 I I-AF-00300 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.003 REVISION NO.00 I I-AF-00400 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.004 REVISION NO.00 I I-AF-00500 AUXILIARY FEEDWATER I SI ISOMETRIC SHEET NO.005 REVISION NO.00 I I-AF-00600 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.006 REVISION NO.00 I I-AF-00700 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.007 REVISION NO.00 I I-AF-00800 AUXILIARY FEEDWATER I SI ISOMETRIC SHEET NO.008 REVISION NO.00 I I-AF-00900 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.009 REVISION NO.00 4444444444444444t4ftf444'444t44444444444444f44f44444444f404444
3.2.4.1 Insulation Resistance Test
+4444444444f4444444444444f4444t444$
: 1. Disconnect all power and instrumentation leads from the target cable.
444444404444f4 NUTECH 4444444ts 44$444444444t44 PRI SIM 4 444444444444444444 PAGE 40 REVISION RRS1 DATE 85/12/04 CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 4444444444tkktkkt4444tkf44444f4444444444fff44ft4444444444fflt444f4444tf4tt4'EFERENCE KEY DESCRIPTION I I-AF-01000 I I-AF-01100 I I-80-00100 II-80-00200 II-BD"00300 II-BD-00700 II"80-00800 II-BO-00900 II-BD-01000 II-BD-01100 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.010 REVISION NO.00 AUXILIARY FEEDWATER ISI ISOMETRIC SHEET NO.011 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO.001 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO.002 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO.003 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO.007 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO: 008 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO.009 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO.010 REVISION NO.00 BLOW DOWN ISI ISOMETRIC SHEET NO.011 REVISION NO.00 444444444444444t44f44444444444444444444t44444f44f44444f440f44444f44t4444
2.. Using a megohmmeter, apply a potential of 500 VDC and record the minimum insulation resistance indicated after a period of 60 seconds between the following test points:
++44444444444444444444444444444444444t444444444f4444fff4fv
Phase-to-Phase                    Phase-to-Ground*
+f444444444444tf NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO PAGE 41'4 REVISION, RRS1 DATE 85/12/04 44444444444444444444'44t444444ff4444ffff4t4f444444f444 REFERENCE KEY DESCRIPTION I I-BD-01200 I I-BIT-0100 II-CC-00100 II-CC-00200 II-CC-00300 II-CC-00400 II-CC-00600 II"CC-00700 II-CC-00800 II-CC-00900 II-CC-01000 BLOW DOWN ISI ISOMETRIC SHEET NO.012 REVISION NO.00 BORON INJECTION TANK COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.001 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.002 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.003 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.004 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.006 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.007 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.008 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.009 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.010 REVISION NO.00 444444444444t4444444f4444444444f444444044444444444444444444444444444t44444
1to2                            1 to conduit 2 to conduit
~~4444t444000444484444f400444444f44444444444444444t44444fa
* Shield tied to conduit.
+f444444tf44444f NUTECH PRISIM 4 CAROLINA POWER L'LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO PAGE,.42 REVISION RRS1 DATE, 85/12/04 44444444444444444444tt44f44444444444444444f444f444444444tf444f444444444444t REFERENCE KEY DESCRIPTION II-CC-01100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.011 REVISION NO.00 I I-CC-01200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.012 REVISION NO.00 II-CC-01300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.013 REVISION NO.00 I I-CC-01400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.014 REVISION NO.00 I I-CC-01500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.015 REVISION NO.00 II-CC-02100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.021 REVISION NO.00 II-CC-02200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.022 REVISION NO.00 II-CC-02300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.023 REVISION NO.00 II-CC-02400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.024 REVISION NO.00 II-CC-02500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.025 REVISION NO.00 OS4444444444444444404444444444444444444444f4f4f4444444444444444444444444444 w+4444444444444444f444ff44ff444444444444444444fffkt4'444444 444'4ff444444444 NUTECH PRISIM CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 4440444444440444 DATA ELEMENT: ISONO PAGE.43 4 REVISION RRS1 4 DATE 85/12/04 444444444t4444444444444f444444444444t444f444444f4444444444444f444ff4f44f444 REFERENCE KEY DESCRIPTION I I-CC-02700 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.027 REVISION NO.00 I I-CC-02900 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.029 REVISION NO.00 I I-CC-03000 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.030 REVISION NO.00 I I-CC-03100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.031 REVISION NO.00 I I-CC-03200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.032 REVISION NO.00 II-CC-03300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.033 REVISION NO.00 II-CC-03400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.034 REVISION NO.00 I I CC-03700 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.037 REVISION NO.00 I I-CC-03900 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.039 REVISION NO.00 II-CC-04300 COMPONENT COOLING WATER ISI SHEET NO.043 REVISION NO.44404444444444f44444f4f44f44444f44444t44444 ISOMETRIC 00 44444444444444 4444444444 t44 0 f 0 44
For all performances of this test, the measured values shaH btcompared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 ohms.
3.2.4.2 Hi h Potential Test
: 1. Using a Hi-Pot Test Set, apply a potential of 1600 YAC and record the leakage current observed after a period of 60 seconds between the foQowing test points:
Phase-to-Phase                    Phase-to-Ground*
1 to 2                          1 to conduit 2 to conduit
* Shield tied to conduit.
: 2. Reconnect power and instrumentation leads to the target cable.
For aQ performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shaQ be no evidence of insulation breakdown or flashover.
WYLE LABdRATdRIES Huntsville Facility


+w t t t t t t t t t t t t t t t t t t t t t t t t t t t NUTECH tt t t tt tt t t t t t t t t t t t t tt t tt tt t t t tt t t t t t tt t t t t t t PRISIM PAGE 44 REVISION.RRS 1 DATE 85/12/04 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION II-CC-04400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.044 REVISION NO.00 I I-CC-04500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.045 REVISION NO.00 II-CC-04600 II-CC-04700 II-CC-04800 II-CC-04900 II-CC-05000 II-CC-05100 II-CC-05200 II-CC-05300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.046 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.047 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.048 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.049 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.050 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.051 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.052 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.053 REVISION NO.00
Page No. VI-9 Test Report No. 47879-02 Page No.           8 Test Procedur e No.           47879-01 3.0  TEST PROGRAM (Continued) 3".2  Control Cable Screening Tests (Continued) 3D.5  Overcurrent Test The Overcurrent Test shall be conducted in two sequential phases with no intentional time delay. The first phase consists of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90oC
+~4444444444444444444444444444444t4444t4t44444tbStd'444444t~~4444444444444t4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444044444444444 DATA ELEMENT: ISONO PAGE...45 REVISION RRS 1 DATE 85/12/04 44444444f444444444444444444444fkkf44$
      +SOC. The second phase consists of energizing the fault cable with the test current until the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request. The conductor temperatures on the three adjacent cables (to the fault cable) shall be maintained in a 90oC +5oC band and the target cable shall be energized at rated current and 50 VAC throughout the Overcurrent Test. The Overcurrent Test shall be conducted using, the following procedure:
44440444f4444044444f444444f44444444444 REFERENCE KEY DESCRIPTION I I-CC-05400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.054 REVISION NO.00 I I-CC-05500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.055 REVISION NO.00 II-CC-05600 II-CC-05800 II-CC-05900 II-CC-06000 I I-CC-06100 II-CC-06200 II-CC-06300 II"CC-06400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.056 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.058 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.059 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.060 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.061 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.062 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.063 REVISION NO.00 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO.064 REVISION NO.00 444444fftt44t444fft444t444tt444444t44444444448444f44f444tkf444444tt44444ttt 4404444ft4444404+
: 1. Connect the fault cable (see the table on following page) to the copper bus bars per Figures 2 and 7.
+Of44t4444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444444444f4444444 DATA ELEMENT: ISONO PAGE..46 4 REVISION RRS1 DATE 85/12/04 44444444444444444$
: 2. Install a single paiI 16 AWG target cable in the 1-inch rigid steel conduit per Figure 2.
444444444444444tff4444444444444444t44f44444444f4444444 REFERENCE KEY DESCRIPTION II-CE-00100-II-,CE-00200 I I-CH-00100 II-CH-00200 II-CH-00300 II-CH-00400 II-CH-00500 II-CH-00600 II-CH-00700 II-CH-00800 CONDENSATE ISI ISOMETRIC SHEET NO.001 REVISION NO.00 CONDENSATE ISI ISOMETRIC SHEET NO.002 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.001 REVISION NO.00 CHILLED WATER SUPPLY IS I ISOMETRIC SHEET NO.002 REVISION NO.00 CHILLED WATER, SUPPLY ISI ISOMETRIC SHEET NO.003 REVISION NO.00 CHILLED WATER SUPPLY IS I ISOMETRIC SHEET NO.004 REVISION NO.00 CHILLED WATER SUPPLY IS I ISOMETRIC SHEET NO.005 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.006 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.007 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.008 REVISION NO.00 444fftkff4444ff4044444444t44444444444444444f4444444444444444444444t444f4444 4444f4444ff4444444444444444444444444444444444444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 444444'444444444 PRI SIM 4 1 PAGE 47 REVISION RRS1 DATE 85/12/04 4444440448%444tt4444444444444444444$
: 3. Install nine 1/C  10 AWG cables      adjacent to the fault cable per Figure 2.
44444444t4444444444t44444tbt4444444'444t REFERENCE KEY DESCRIPTION II-CH-00900 II-CH-01000 II-CH-01100 II-CH-01200 II-CH-01300 II-CH-01400 II-CH-01500 II-CH-01600 II-CH-01900 II-CH-02000 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.009 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.010 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.011 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.012 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.013 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.014 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.015 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.016 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.019 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.020 REVISION NO.00 444444444444t44444444444044444444444444 044 f 404 f 44444444444 t~tttttttttttttttttttttttttttttttttttttttttttttttttttttttt tttt NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO PAGE REVI S DATE PRISIM 48 ION RRS1 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION II-CH-02100 II-CH-02300 II-CH-02400 II-CH-02500 II-CH-02600 II-CH-03300 II-CH-03400 II-CH-03500 II-CH-03600 II-CH-03700 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.021 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.023 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.024 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.025 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.026 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.033 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.034 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.035 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.036 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.037 REVISION NO.00
: 4. Connect the single pair 16 AWG target cable to the instrumentation and power supplies of Figure 11.
+++4444tf44444444f444444t4444844444444444444444t444f44444 NUTECH CAROLINA POWER L LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 4 4 0 4 4 4 t4 4'4 4 44 4 4 4 444 4 4 4 t 4 t 0 4 t 4 4 4 4 4 4 4 f 4 4 44 4 44 4 4 4444404444444 PRISIM 4444 4 44 4 4 4 4 44 4 44 4 4 PAGE 49 REVISION RRS1 DATE 85/12/04 O444444444444O4444 REFERENCE KEY DESCRIPTION II-CH-03800 I I-CH-04100 II-CH-04400 II-CH-04500 II-CH-04600 II-CH-04700 II-CH-04800 II-CH-04900 I I-CH-05100 I I-CH-05700 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.038 REVISION NO.00 CHILLED WATER SUPPLY I SI ISOMETRIC SHEET NO.041 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.044 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.045 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.046 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.047 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.048 REVISION NO.00 CHILLEO WATER SUPPLY I SI ISOMETRIC SHEET NO.049 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.051 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.057 REVISION NO.00 444444444f444444t44f4444444044f4444444444444444444444444444f444444444444444
: 5. Connect the nine 1/C 10 AWG cables to the oower supply per Figure 8.
++4444444444444444444444444444444444444444440444440444fff NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 4444444444444444f 4t4444444t4f 44f 4444444f 44444444444444f 44 4+4444444444444'44 PRI RIM 4444444444444444t4 PAGE 50 REVISION RRS1 DATE 85/12/04 REFERENCE KEY DESCRIPTION II-CH-05800 II-CH-06100 II-CH-06400 II-CH-06500 II-CH-07000 I I-CH-07100 II-CH-07300 II-CH-07500 II-CH-07700 II-CH-07800 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.058 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.061 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.064 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.065 REVISION NO.00 CHILLED WATER SUPPLY I SI ISOMETRIC SHEET NO.070 REVISION NO.00 CHILLED WATER SUPPLY I SI ISOMETRIC SHEET NO.071 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.073 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.075 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.077 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.078 REVISION NO.00 444444444444444444444484444t4444444444444f44444444444444f4'44t444444ft444444
: 6. Energize the single pair 16 AWG cable with          1 ampere at 50 VAC.
+444f 4444f 4444 44f f 4444 t4444f 44f f 44444f 44444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO+044C44444444444 PRISIM 4444t44t44t4444444 PAGE.S 1 REVISION, RRS 1 DATE 85/12/04 4 4 4'4444 4 4 4 4 44 44 4 4 4 44 4 44 0 f 4 4 4 0 4 44 444 t 444444 4 4 4 44 t 444I 444444 444 4I 4 44 444 4 4 4 0 44 4 4 REFERENCE KEY DESCRIPTION II-CH-07900 II-CH-08000 I I-CH-08100 II-CH-08200 II-CH-08300 II-CH-08600 II-CS-00100 II-CS-00200 II-CS-00300 II-CS-00400 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.079 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.080 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.081 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.082 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.083 REVISION NO.00 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO.086 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.001 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.002 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.003 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.004 REVISION NO.00 444444444444444444 NUTECH+444444444444444 PRI SIM 444444444444444444 PAGE ,52 REVISION RRS1 DATE 85/12/04 4444444444444444444f44444444f44 44444444444444444444444444444 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO REFERENCE KEY DESCRIPTION II-CS-00500 II-CS-00600 II-CS-00700 II-CS-00800 II-CS-00900 II-CS-0 1000 I I-CS-01100 II-CS-01300 II-CS-01500 I I-CS-01900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.005 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.006 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.007 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.008 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.009 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.010 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.011 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.013 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.015 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.019 REVISION NO.00 44444t444t44444'44444444444444444444444444444444f4444444t444444444444444t444 aa04444444444440844444044444484t4444444444444t444444444404++44444444444444t NUTECH PRISIM 4 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING t4444f44444444 DATA ELEMENT: ISONO PAGE,.53 REVISION RRS1 DATE 85/12/04 44444444f'4444tf4tt44444f4444t44444444f4444444444444444444444444f44444f44444 REFERENCE KEY DESCRIPTION II-CS-02000 I I-CS-02100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI SHEET NO.020 REVISION NO.00 h CHEMICAL AND VOLUME CONTROL SYSTEM ISI SHEET NO.021 REVISION NO.00 ISOMETRIC ISOMETRIC II-CS-02200 I I-CS-02400 II-CS-02500 II-CS-02600 II-CS-02700 II-CS-02800 II-CS-02900 II-CS-03000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.022 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.024 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.025 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.026 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.027 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.028 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.029 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.030 REVISION NO.00 444 44444 44444444444444444444444444444 f 44444444444t444444444 444444 04444444 t+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt+
: 7. Energize the nine 1/C 10 AWG cables, adjacent to the fault cable, with 40 amperes    at reduced voltage.
ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 t PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO PAGE',, 54 REVISION,, RRS 1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttt,tttttttttttttttttttttttt REFERENCE KEY DESCRIPTION II-CS-03100 II-CS-03300 II-CS-03400 II-CS-03600 II-CS-03700 II-CS-03800 II-CS-03900 II-CS-04100 11-CS"04700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.031 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.033 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.034 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.036 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.037 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.038 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.039 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.041 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.047 REVISION NO.00 II-CS-04800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.048 REVISION NO.00
: 8. Energize the fault cable with the initial currents listed in the table on the following page.
: 9. Record target cable voltage and current, fault cable current and initial conductor temperature, and adjacent cable current and initial conductor temperature.
: 10. Slowly increase fault cable and adjacent cable currents to achieve conductor temperature of 90oC +SOC for a period of 15 minutes.
ll. Record target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures.
WYLE LABORATORIES Huntsville Facility


NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 4444444f444tf4444ttt444444444f4444~+4444t44484fktent PRISIM 444444444444444444 PAGE 55 REVISION RRS 1 REFERENCE KEY DESCRIPTION I I-CS-04900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.048 REVISION NO.00 I I-CS-05700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.057 REVISION NO.00 I I-CS-05800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.058 REVISION NO.00 I I-CS-06000 CHEMICAL AND VOLUNME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.060 REVISION NO.00 II-CS-06100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.061 REVISION NO.00 II-CS-06200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.062 REVISION NO.00 I'I-CS-06300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.063 REVISION NO.00 II-CS-06500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.065 REVISION NO.00 II-CS-06700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.067 REVISION NO.00 I I-CS-07500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.075 REVISION NO.00 4 44 4 0 0 44 44 0 0 t 44 0'0 4 0 0 44 t4 4 44 44 444 0 4 444 44 44 4 0 4 44 0 4 444 0 0 4 44 4 0 t 4 0 44 f 444 44 0 44444 44r44444f444444844ff44t444444f44044444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO PRISIM 444444440444444444 PAGE 56 REVISION RRS1 DATE 85/12/04 4400444444t44444444444444440444444444444044444044444444444044f444440044t440 REFERENCE KEY DESCRIPTION I I-CS-07600 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.076 REVISION NO.00 II-CS-07700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.077 REVISION NO.00 II-CS-07800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.078 REVISION NO.00 I I-CS-07900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.079 REVISION NO.00 I I"CS-08000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.080 REVISION NO.00 II-CS-08100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.081 REVISION NO.00 II-CS-08200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.082 REVISION NO.00 I I-CS-08300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.083 REVISION NO.00 II-CS-08400 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.084 REVISION NO.00 I I-CS-08500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.085 REVISION NO.00 4444444444444444444f4f44tf4444f4444444444ft4444444444444444444444444444444f
Page No. VI-10 Test Report No. 47879-02 Page No.         9 Test Procedure No.         47879-01 3.0    TEST PROGRAM (Continued) 3.2    Control Cable Screening Tests (Continued) 3.2.5  Overcurrent Test (Continued)
.-~4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4'4 4 4 4 4 4 4 4 4 NUTECH 4444444444444444444444 444444444444444 PRISIM PAGE 57 REVISION RRS 1 DATE 85/12/04 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT l PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO REFERENCE KEY DESCRIPTION II-CS-08700 II-CS-08800 II-CS-08900 II-CS-09200 II-CS-09300 II-CS-09400 II-CS"09500 II-CS-09600 II-CS-09700 II-CS-09800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.087 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.088 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.089 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.092 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.093 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.094 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.095 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.096 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.097 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.098 REVISION NO.00 444tftt44444f444444444444tf44f444444ttt4444444444f44tt44444444444f44444444'0
: 12. Increase the fault cable current to the test current value in the table below.
++0 0 4444 0 0 4 0 0 IF 0 4 0 0 f 44'444 0 0 0 0 4 4 0 0 0 0 4444 0 0 4f 4 0 0 0 t 44 0 0 0 0 0 4444+s 0 0 4 0 44 444 f 44 0 0 0 NUTECH PRISIM 4 CAROLINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ISONO PAGE 58 REVISION RRS1 DATE 85/12/04 44444f444444444444444tf44444444444f44444tf44444444fff4444444f44444f44444444 REFERENCE KEY DESCRIPTION II-CS-09900 II-CS-10000 II-CS-10200 II-CS-10300 II-CS-10400 II-CS-10500 II-CS-10600 II-CS-10700 I I-CS-10800 II-CS-10900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.099 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.100 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.102 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.103 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.104 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.105 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.106 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.107 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.108 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.109 REVISION NO.00 Ct44f.44444844444444444444444044444444444444444
: 13. Record target cable voltage and current, fault cable current and conductbr temperature, and adjacent cable current and conductor temperatures.
: 14. Allow the fault cable to conduct the test current until either the cable openmircuits, temperatures stabilize or decrease, or the test is terminated at the customer's request.
: 15. Record time to ignition, open-circuit,            or stabilized  temperature  as applicable.
: 16. Record target cable voltage and current and adjacent cable current and conductor temperatures.
: 17. De-energize the target cables, adjacent cables, and the Multi-Amp Test Set.
: 18. Photograph the post-test conditions.
For all performances of this test, the observed target cable operation shall be compared to the acceptance criteria, Paragraph 2.1.3, i.e., they shall maintain continuity of power.
Fault Cable Sizes and Currents Test                                  CPRL              Initial          Test No.     Fault Cable Size            iD. No.                             Current 2/C 16 AWG                D50-11              18A              180A 2/C 12 AWG                D50-06              30A              180A 2/C 10 AWG                D50-04               40A              180A 2-1/C 10 AWG      D59-02 (D25-01)              40A              180A 2-1/C 6 AWG        D59-03 (D25-03)              75A              180A 3.2.6  Post-Overcurrent Test Functional Test The functional tests of Paragraph 3.2.4 shall      be repeated on the  target cable.
WYLE LABORATORIES Huntsville Facility


PRI SIM PAGE 59 REVISION RRS1 DATE 85/12/04 tttttttttttttttfttttttttttttttttttttttttttttt NUTECH CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO ttttttttttttttttttttttttttttt
Page No. VI-11 Test Report No. 47879-02 Page No.           10 Test Procedure No.           47879-01, Revision A 3.0    TEST PROGRAM (Continued) 3.3    Power Cable Screening Test Six tests shall be conducted in cable tray with various cable overloads to determine the cable, when subjected to the worst case electrical fault at the Shearon Harris Nuclear Power Plant, that delivers the maximum amount of heat to the environment. In addition, a 1-inch conduit, with a single oair 16 AWG target cable inside, shall be mounted 1 inch above (Test 4) and 12 inches above                  A (Tests 1-3, 4 and 5) the faulted cable to evaluate conduit-to-tray spatial separation.
++tttttttttttttttftttttttttftttttffttttttttttttttttttttftt+
3.3.1  Pur~e
ttttttttttttttt REFERENCE KEY DESCRIPTION II-CS-11000 II-CS-11100 II-CS-11200 II-CT-00100 II-CT-00200 II-CT-00300 II-CT-00400 II-CT-00500 II-CT-00700 II-CT-00800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.110 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.111 REVISION NO.00 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO.112 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.001 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.002 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.003 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.004 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.005 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.007 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.008 REVISION NO.00 4i44$440444444408444444444444444844444444444444444444444444+444444444t44444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 4 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ISONO PAGE 60 REVISION RRS1 DATE 85/12/04 44444444444444444444444444t44444044444f444444ttff444444ft44444ir444f444444f4 REFERENCE KEY DESCRIPTION II-CT-00900 I I-CT-01000 II-CT-01400 I I-CT-01500 II-CT-01600 II-CT-01700 I I-CT-01800 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.009 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.010 REVISION NO.00 CONTAINMENT SPRAY I SI ISOMETRIC SHEET NO.014 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.015 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.016 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.017 REVISION NO.00 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO.018 REVISION NO.00 II-CX-00'100 II-CX-00200 II-CX-00300 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.001 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.002 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.003 REVISION NO.00 444844844444444444444444444444444f 4t'44f 4f t444'4444444f 044444f tt4f 04444444444
: 1. Determine the worst case electrical fault and cable size. This worst case cable shall be based on the following selection criteria:
~004444044444444444444444444444444444444044444444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO+444tt44t44t444e PRISIM PAGE;", 61 REVISION RRS1 DATE 85/12/04 4444t44444f444444f4444tkkt44t44t44444444444444448444f4t444440444444t444t REFERENCE KEY DESCRIPTION II-CX-00400 II-CX-00500 II-CX-00600 II-CX-00800 II-CX-01000 II-CX-01100 I I-CX-01300 I I-,CX-01400 Ii-CX-01500 ii-CX-01600 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.004 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.005 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.006 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.008 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.010 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.011 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.013 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.014 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.015 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.016 REVISION NO.00 0
A.     If the  cables ignite, a combination of time to ignition, insulation burn time, and observed temperatures shall be utilized to determine the worse-case cable.
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B.     If no  cables ignite, the cable which is the last to open-circuit (or does not open) shall be considered the worse-case cable.
444f44444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUClEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 4 44 4 4 0 4 S 44 4 4 4 0 4 0 4 4 4 0 0 PRISIM 444444444444444444 PAGE 62 REVISION RRS1 DATE 85/12/04 444444444444 REFERENCE KEY DESCRIPTION II-CX-01700 II-CX-01800 II-CX-01900 II-CX"02000 11-CX-02100 II-CX-02300 II-CX-02500 11-CX-02700 11-CX-03100 II-CX-03300 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.017 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.018 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.019 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.020 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.021 REVISION NO.00 CHILLED WATER RETURN I SI ISOMETRIC SHEET NO.023 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.025 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.027 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.031 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.033 REVISION NO.00 444444444444t444444f4444444444'444444444444444444444t44444444440
C.     If no  cables ignite and two or more do not openmircuit, the-cable with the highest, continuous temperatures achieved during the test shall be considered the worse-case cable.
~444444f44484884f44f4444444f4444444444f8444444ftt NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO PRISIM UNIT 1 44444444444444 PAGE" 63 REVISION RRS1 DATE 85/12/04 4444 0 0 4 44 4 f 444444t f 0 444 0 4 f 44 0 4r 0 0 44444444 f 4444444 444 444444$44 0 t44 444 44 t 444 4 0 REFERENCE KEY DESCRIPTION II-CX-03400 II-CX-03800 II-CX-03900 II-CX-04000 II-CX-04100 II-CX-04200 II-CX-04300 II-CX-04400 II-CX-04500 II-CX-04600 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.034 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.038 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.039 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.040 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.041 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.042 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.043 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.044 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.045 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.046 REVISION NO.00 44t444444444444444444444444f444444444444444444444444444444444f4444444444ff4 0
Once the worse-case- cable has been determined,                 this cable shall be the faulted cable in all subsequent configuration tests.
+~44444444444444444444444444f44 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 44444444f4444444444444+f44t4444 4f444t4444t44~
2.,  Demonstrate the adequacy of design where a 1-inch conduit runs parallel to and  1 inch above a faulted cable in a power-type cable tray.
444444444444444 PRI SIM 444444444444444444 PAGE 64 REVISION RRS 1 DATE 85/12/04 44444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION II-CX-04700 II-CX-04800 Ii-CX-04900 II-CX-05200 II-CX-05900 II-CX-06000 II-CX-06100 II-CX-06500 II-CX-06900 II-CX-07100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.047 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.048 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.049 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.052 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.059 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.060 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.061 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.065 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.069 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.071 REVISION NO.00
3.3.2" Test    ecimen Pre aration The test specimens shall be mounted to the unistrut frame of Figure 1. This apparatus shall be assembled to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following guidelines shall be observed with regard to the materials and construction of this assembly:
++4444444t NUTECH 4444f44444f444f4444444444444t444444ftff4444t4444 44t444444444444 PRI SIM CAROlINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ISONO PAGE 65 REVISION RRS1 DATE 85/12/04 44444444444444fkf444f44444 REFERENCE KEY DESCRIPTION I I-CX-07700 CHILLEO WATER RETURN ISI ISOMETRIC SHEET NO.077 REVISION NO.00 II-CX-07800 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.078 REVISION NO.00 II-CX-07900 II-CX-08100 II-CX-08300 II-CX-08400 II-CX-08700 II-CX-08800 II-CX-08900 II-DW-00100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.079 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.081 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.083 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.084 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.087 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.088 REVISION NO.00 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO.089 REVISION NO.00 DEMINERALIZED WATER ISI ISOMETRIC SHEET NO.001 REVISION NO.00 4444tkkt$44444444f44444444444444444444444fkf4444f444440f4444t4f444f44444444
: 1. The faulted cable shall be one        of the following cables from CPRL stock:
+444040444t4444'44'44444O444444444444444444444444444440444
Test No.               Fault Cable Size                      COL LD. No.
%44444444444444f NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ISONO PAGE 66 REVISION.RRS1 DATE 85/12/04 444444444444044444444444444444444444444444444444444444044t404444444 REFERENCE KEY DESCRIPTION II-DW-01000 I I-EA-00100 II-EA-00200 II-EA-00300 II-EA-01200 I I-EA-01300 I I-EA-01400 I I-EL-00100 II-FMR-0100 II-FMR-0200 II-FMR-0300 DEMINERALIZED WATER ISI ISOMETRIC SHEET NO.010 REVISION NO.00 DIESEL STARTING AIR ISI ISOMETRIC SHEET NO.001 REVISION NO.00 DIESEL STARTING AIR ISI ISOMETRIC SHEET NO.002 REVISION NO.00 DIESEL STARTING AIR ISI ISOMETRIC SHEET NO.003 REVISION NO.00 DIESEL STARTING AIR ISI ISOMETRIC SHEET NO.012 REVISION NO.00 DIESEL STARTING AIR ISI ISOMETRIC SHEET NO.013 REVISION NO.00 DIESEL STARTING AIR ISI ISOMETRIC SHEET NO.014 REVISION NO.00 EXCESS LETDOWN HEAT EXCHANGER FEEDWATER, MAIN STEAM, AND REACTOR COOLANT ISI ISOMETRIC SHEET NO.01 REVISION NO.00 FEEDWATER, MAIN STEAM, AND REACTOR COOLANT ISI ISOMETRIC SHEET NO.02 REVISION NO.00 FEEDWATER, MAIN STEAM, AND REACTOR COOLANT ISI ISOMETRIC SHEET NO.03 REVISION NO.00 4444444444444444844440444444444rttf4444444t44444444f044404444 444444444404444444444444w PRI SIM 44444444t444444444 PAGE 67 REVISION RRS1 DATE 85/12/04+44444444444t4444 NUTECH CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT I PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 44 0 4444 f 0 0 0 f 44 0 44 4444 444 444444 44444 0 0 0 444 0 44 44 0 44 444 tlat 444 4IIS 0 f 444 f 0 REFERENCE KEY DESCRIPTION II-FO-00100 II-FO-00200 II-FO-00300 II-FO-00500 II-FO-11400 II-FO-11600 II-FO-12200 II-FO-12300 II-F0-.12400 II-FO-12500 FUEL OIL ISI ISOMETRIC SHEET NO.001 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.002 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.003 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.005 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.114 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.116 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.122 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.123 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.124 REVISION NO.00 FUEL OIL ISI ISOMETRIC SHEET NO.125 REVISION NO.00 44444444f44444'444444444444444444444f4444444444444444t4484444444444444444f44
1                  3-1/C 10 AWG                            D25-01 2                  3-1/C 6 AWG                            D25-03 3                  3-1/C 2 AWG                            D25-05 4                Triplex 4/0 AWG                          D25-08 5                Tr iplex 350 itIICM                      D25-01 6                Triplex 500 MCM                          D25-11 WYIE LASORATORIES Huntsville Facility


444444444'4t 44444444444f444 PRISIM PAGE 68 REVISION RRS1 DATE 85/12/04 44444t44444444f444tt44444444440 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 44444444444444444444444444444444444444444ttk
Page No. VI-12 Test Report No. 47879-02 Page No.           11 Test Procedure No.           47879-01, Revision A 3.0                  PROGRAM (Continued) 3.3'-       Power Cable Screening    Test (Continued) 3.3.2'EST Test  S    imen Pre    ation (Continued)
+~444444444444444444'44t44444444444444444t444 NUTECH REFERENCE KEY DESCRIPTION I I-FP-00500 FIRE PROTECTION ISI ISOMETRIC SHEET NO.005 REVISION NO.00 II-FP-00700 FIRE PROTECTION ISI ISOMETRIC SHEET NO.007 REVISION NO.00 II-FP-04900 FIRE PROTECTION ISI ISOMETRIC SHEET NO.049 REVISION NO.00 II-FP-05100 FIRE PROTECTION ISI ISOMETRIC SHEET NO.051 REVISION NO.00 I I-FW-00100 FEEDWATER ISI ISOMETRIC SHEET NO.001 REVISION NO.00 II-FW-00200 FEEDWATER ISI ISOMETRIC SHEET NO.002 REVISION NO.00 II-FW-00300 FEEDWATER ISI ISOMETRIC SHEET NO.003 REVISION NO.00 II-FW-00400 FEEDWATER ISI ISOMETRIC SHEET NO.004 REVISION NO.00 II-FW-00700 FEEDWATER ISI ISOMETRIC SHEET NO.007 REVISION NO.00 II-FW-00800 FEEDWATER ISI ISOMETRIC SHEET NO.008 REVISION NO.00 44444444444444444444444444444444444444444444444444+t444444444444444444t4444 v+44t4444444444444f44444444 4 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 444444444444444 PRI SIM 44 444444 4 444444 4 44 PAGE.', 69 REVISION RRS1 DATE 85/12/04 444444444444444f44444f44444444444f'4444444444 REFERENCE KEY DESCRIPTION I I-FW-00900 FEEDWATER ISI ISOMETRIC SHEET NO.009 REVISION NO.00 I I-FW-01000 FEEDWATER ISI ISOMETRIC SHEET NO.010 REVISION NO.00 I I-FW-01200 FEEDWATER ISI ISOMETRIC SHEET NO.012 REVISION NO.00 I I-FW-01300 FEEDWATER Isi ISOMETRIC SHEET NO.013 REVISION NO.00 I I-IA-00100 INSTRUMENT AIR ISI ISOMETRIC SHEET NO.001 REVISION NO.00 I I-IA-00300 INSTRUMENT AIR ISI ISOMETRIC SHEET NO.003 REVISION NO.00 I I-MD-00300 MISCELLANEOUS DRAINS ISI ISOMETRIC SHEET NO.003 REVISION NO.00 II-MD-00700 MISCELLANEOUS DRAINS ISI ISOMETRIC SHEET NO.007 REVISION NO.00 I I"MS-00100 MAIN STEAM ISI ISOMETRIC SHEET NO.001 REVISION NO.00 I I-MS-00200 MAIN STEAM ISI ISOMETRIC SHEET NO.002 REVISION NO.00 4444444444444444444444444444444t444444444f444t444t444444444444ft444444444'44 ttttttttttttttt PRISIM t t t tt t t t t t t t t t t t t t PAGE 70 REVISION RRS1 DATE 85/12/04 tttttttttttttttttttttttttt CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO ttttttttttttttttttttttttttttttttttttttttttttttttt
The  fault cable shall be the top centermost cable inside an 8' 24" x 4" ladder rung cable tray filled to the top of the siderails with de-energized power-type cables.
++ttttttttttttttttttttttttttttttttttttttttttttttt NUTECH REFERENCE KEY DESCRIPTION II-MS"00300 II-MS-00700 II-MS-00800 II-MS-00900 II-MS-01500 II-MS-02400 II-PZR-0100 II-RC-00100 II-RC-00200 II-RC-00300 II-RC-00800 MAIN STEAM ISI ISOMETRIC SHEET NO.003 REVISION NO.00 MAIN STEAM ISI ISOMETRIC SHEET NO.007 REVISION NO.00 MAIN STEAM ISI ISOMETRIC SHEET NO.008 REVISION NO.00 MAIN STEAM ISI ISOMETRIC SHEET NO.009 REVISION NO.00 MAIN STEAM ISI ISOMETRIC SHEET NO.015 REVISION NO.00 MAIN STEAM ISI ISOMETRIC SHEET NO.024 REVISION NO.00 PRESSURIZER REACTOR COOLANT ISI ISOMETRIC SHEET NO.001 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.002 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.003 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.008 REVISION NO.00 044404444444+i4444t44404400444 PRISIM 444444444444444444 PAGE 71 REVISION RRS1 DATE 85/12/04 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO~eeeeeeeee44444444444444444444444444444444444 NUTECH 444444444440444444t4444444444444444444444t444 REFERENCE KEY DESCRIPTION II-RC-00900 I I-RC-01000 II-RC-01100 II"RC-01200 II"RC-01300 I I-RC-01400 II-RC-01500 II-RC-0'1700 I I-RC-01800 II-RC-01900 REACTOR COOLANT ISI ISOMETRIC SHEET NO.009 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.010 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.011 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.012 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.013 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.014 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.015 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.017 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.018 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.019 REVISION NO.00'444444444f444444444444444444444444444444f4'44444444444444444444
: 2. Nine 1/C 10 AWG cables (Tests 1-4) and nine 1/C 6 AWG cables (Tests 5 and 6) shall be mounted underneath and around the faulted cable per Figure 3. These cables shall be energized and their conductor temperatures increased to 90oC'+5oC prior to applying the fault current to the fault cable; This shall be done to simulate the heat which the fault cable would experience in a cable tray of energized cables.
~ee444444t44444444444444444444444444444444444444t NUTECH CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO PRI SIM<<e4444444444444444 PAGE 72 REVISION RRS1 DATE 85/12/04 4440444t4444444444444f44444f4444444444f444444f444444f44f44444f444 REFERENCE KEY DESCRIPTION II-RC-02000 REACTOR COOLANT ISI ISOMETRIC SHEET NO.020 REVISION NO.00 II-RC-02200 II-RC-02300 II-RC-02400 II-RC-02500 II-RC-02700 II-RC-02800 II-RC-02900 II-RC-03000 II-RC-10000 REACTOR COOLANT ISI ISOMETRIC SHEET NO.022 REVISION NO.00 REACTOR COOLANT I SI ISOMETRIC SHEET NO.023 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.024 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.025 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.027 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.028 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.029 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.030 REVISION NO.00 REACTOR COOLANT ISI ISOMETRIC SHEET NO.100 REVISION NO.00 0e
: 3. The ends of the faulted. cable from their termination to the edge of the cable tray shall be wrapped with a single layer; 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape per Figure 7. This shaQ be done as a safety measure to ensure that any ignition that might occur is contained to the cable tray area.
~+44444444444tkf44444444f4444f4444444444444444r44444444444W 444444444t4440f NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444 444 444444 444 44 DATA ELEMENT: ISONO PAGE,.73 REVISION RRS1 DATE 85/12/04 444444t44f4444ff444444f4f4404 REFERENCE KEY DESCRIPTION II-RCP-0100 REACTOR COOLANT PUMPS II-RH-00100 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.001 REVISION NO.00 I I-RH-00200 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.002 REVISION NO.00 I I-RH-00400 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.004 REVISION NO.00 I I-RH-00500 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.005 REVISION NO.00 I I-RH-00600 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.006 REVISION NO.00 I I-RH-00700 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.007 REVISION NO.00 I I-RH-00800 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.008 REVISION NO.00 I I-RH-00900 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.009 REVISION NO.00 I I-RH-01000 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO.010 REVISION NO.00 I I-RHR-0100 RESIDUAL HEAT REMOVAL HEAT EXCHANGERA88 444444444444444444444444444444444444444444444440444444444444444404440444444 w m$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$PRISIM$PAGE 74 REVISION RRS 1 DATE 85/12/04$NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO$4$$$$$'$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$4$$$$$$0 0$$$$$$$$$$$$$$$$$f$$$$$$$f 0$$REFERENCE KEY DESCRIPTION I I-RHX-0100 REGENERATIVE HEAT EXCHANGER II-RV-00100 DESCRIPTION TM BE ADDED BY SHNPP I I-SA-00100 SERVICE AIR ISI ISOMETRIC SHEET NO.001 REVISION NO.00 I I-SA-00300 SERVICE AIR ISI ISOMETRIC SHEET NO.003 REVISION NO.00 II-SC-00100 II-SC-00200 II-SC-00700 II-SF-00100 II-SF-00200 II-SF-00400 II-SF-00500 SCREEN WASH ISI ISOMETRIC SHEET NO.001 REVISION NO.00 SCREEN WASH ISI ISOMETRIC SHEET NO.002 REVISION NO.00 SCREEN WASH ISI ISOMETRIC SHEET NO.007 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.001 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.002 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.004 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.005 REVISION NO.00$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$
4,    A 10-foot long, 1-inch rigid steel conduit shall be mounted parallel to and 1 inch above (Test 4) and 12 inches above (Tests 1-3, 5 and 6) the fault cable. This conduit shall contain a single pair 16 AWG target cable (CP@L I.D. No. D60-01). The 1-foot section of this conduit which extends past the cable tray shall be wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape.
w~44444444444444 44444444t44444444444444t44444444444444444 444444444444444 PRISIM PAGE-,-75 REVISION RRS1.*DATE 85/12/04 NUTECH CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO 4f 4444t44444 f 4444444f 44444f 444444f 444f 444444f AIOt4444444444444f4444444444444 REFERENCE KEY DESCRIPTION II-SF-00600 II-SF-00700 II-SF-00800 II-SF-00900 II-SF-01000 II-SG-00100 II-SI-00100 II-SI-00200 II-SI-00300 II-SI-00400 II-SI-00500 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.006 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.007 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.008 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.009 REVISION NO.00 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO.010 REVISION NO.00 STEAM GENERATORS A,B,&C SAFETY INJECTION ISI ISOMETRIC SHEET NO.001 REVISION NO.00 SAFETY INJECTION ISI ISOMETRIC SHEET NO.002 REVISION NO.00 SAFETY INJECTION ISI ISOMETRIC SHEET NO.003 REVISION NO.00 SAFETY INJECTION ISI ISOMETRIC SHEET NO.004 REVISION NO.00 SAFETY INJECTION ISI ISOMETRIC SHEET NO.005 REVISION NO.00 4444444444444444444444444ff44444444f4444444444444f444444f44444444f444444 w+t t t t t t t t NUTECH tttttttttttttttttta
: 5. Photographs shall be taken of the test setup.
+ttttttttttttttt PRISIM CAROLINA POWER 8 LIGHT COMPANY t SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: ISONO PAGE 76 REVISION, RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION I I-SI-00600 SAFETY INJECTION ISI ISOMETRIC SHEET.NO.006 REVISION NO.00 II-SI-00800 SAFETY INJECTION ISI ISOMETRIC SHEET NO.008 REVISION NO.00 II-SI-00900 SAFETY INJECTION I SI ISOMETRIC SHEET NO.009 REVISION NO.00 II-SI-01000 SAFETY INJECTION ISI ISOMETRIC SHEET NO.010 REVISION NO.00 II-SI-01100 SAFETY INJECTION ISI ISOMETRIC SHEET NO.011 REVISION NO.00 I I-SI-01200 SAFETY INJECTION ISI ISOMETRIC SHEET NO.012 REVISION NO.00 I I-SI-01300 SAFETY INJECTION I SI ISOMETRIC SHEET NO.013 REVISION NO.00 I I-SI-01400 SAFETY INJECTION ISI ISOMETRIC SHEET NO.014 REVISION NO.00 I I-SI-01600 SAFETY INJECTION ISI ISOMETRIC SHEET NO.016 REVISION NO.00 I I-SI-01700 SAFETY INJECTION ISI ISOMETRIC SHEET NO.017 REVISION NO.00 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt
: 6. A 1/2-inch VHS recording shall be taken of the Overcurrent                      Test encompassing the entire application of the test current.,
Instrumentation Set 3.3.3'.3.3.1 Thermocou le Locations A total of 26 Type "K" thermocouples shall be utilized for these tests.               These thermocouples shall be mounted as described below:
Channel No.                                           Location 1-8          Mounted to the jacket of the fault cable. These thermocouples shall be spaced approximately 12 inches apart.
9@10            Mounted to the conductors of the fault cable at the two series connections.
WYLE LABORATORIES Huntsville Facility


+~444444444'44444f4444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ISONO
Page No. VI-13 Test Report No. 47879-02 Page No.          12 Test Procedure No.            47879-01 3.0    TEST PROGRAM (Continued) 3.3    Power Cable Screening Test (Continued) 3.3.3  Instrumentation Set      (Continued)
Channel No.                                            Location 11-16        Mounted to the conductors of the three cables adjacent to the faulted cable. Two thermocouples shall be mounted to each cable with one thermocouple at each series connection.
17-24        Mounted to the jacket of the single pair 16 AWG target cable inside. the 1-inch conduit. These thermocouples shall be spaced approximately 12 inches apart and shall be even with the eight fault cable thermocouples.
25@ 26        iMounted underneath the 1-inch conduit and spaced              2 feet from the center of the conduit.
These thermocouples shall be monitored using a Fluke Datalogger feeding a high-speed printer. The datalog er shall be operated at its maximum rate throughout the Overcurrent Test.
.3.3.2 Electrical Monitorin The voltage and current    of the target cable and the fault cable current shall be continuously monitored with an oscillograph recorder. The oscillograph shall be operated at the O.l-inch per minute rate throughout the Overcurrent Test. The oscillograph channels shall be as specified in the following table:
Channel No.                      Si                              Location Current                        Tw. Pr. 16 AWG Voltage                      Tw. Pr. 16 A WG Current                          Fault Cable A digital multimeter shall be utilized            to measure voltage and current of the target cable prior to, during, and after          the Overcurrent Test. This data shall be recorded to provide accurate evidence              of the specimen's capability to conduct rated current at 50 VAC throughout the            Overcurrent Test.
WYLE LABORATORIES Huntsville Facility
 
Page No. VI-14 Test Report No. 47879-02 Page No.        13 Test Procedure No.          47879-01 3.'0    TEST PROGRAM (Continued) 3;3      Power Cable Screening Test (Continued) 3.3.4-  Baseline Functional Tests baseline functional tests shall consist of Insulation Resistance and High Potential measurements on each of the target cables. These tests shall be performed as described below:
3.3.4.1'he Insulation Resistance Test
: 1. Disconnect all power and instrumentation leads from the target cable.
2;    Using a megohmmeter, apply a potential of 500 VDC and record the minimum insulation resistance indicated after a period of 50 seconds between the following test points:
Phase-to-Phase                    Phase-to-Ground*
1to2                            1 to conduit 2 to conduit
* Shield tied to conduit.
For all performances of this test, the measured values shall bq compared to the acceptance criteria, Paragraph 2.1.1, i.e,, greater than 1.6 x 10 ohms.
3.3.4.2 Hi h Potential Test
: 1. Using a Hi-Pot Test Set, apply a potential of 1600 VAC and record the leakage current observed after a period of 60 seconds between the following test points:
Phase-to-Phase                    Phase-to-Ground*
1 to 2                          1 to conduit 2 to conduit
                    'e Shield tied to conduit.
: 2. Reconnect power and instrumentation leads to the target cable.
For all performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shall be no evidence of insulation breakdown or flashover.
WYLE LA8ORATORIES Huntsville Facility
 
Page No.                VI-15 Test Repor t No.              47879-02 Page No.          14 Test Procedure No.            47879-01, Revision A 3.0    TEST PROGRAM (Continued) 3.3    Power Cable Screening Test (Continued) 3.3.5  Overcurrent Test The Overcurrent Test shall be conducted in two sequential phases with no intentional time delay. The first phase consists of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90OC
      +5oC. The second phase consists of energizing the fault cable with the test current until the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request. The conductor temperatures on the three adjacent cables'(to the fault cable) shall be
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
ADJ STR ADJUSTABLE RIGID STRUT (WELDED ATTACHMENT TO COMPONENT)
HARSW          ADJ STR ADJUSTABLE RIGID STRUT (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
3WY BOX THREE WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
HBTWM          3WY BOX THREE WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN 3 DIRECTIONS (TENSION AND COMPRESSION) 40444444444t444444044444444444444444tf0444444444444444444444444444444t44444 4444f444484444404444404444444044444444t44f444444f4444444 440444044f44f44 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 44t44444 DATA ELEMENT: COMPDES PAGE , 11 REVISION RRS1 DATE 85/12/04 444444444444444444444444444444444444444444444440444444t4444044t4444444t REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS)COMPONENT DESCRIPTION HBTWW HCONM HCONW HGUDM HGUDW HHSBM HHSBW HMSBM 3WY BOX THREE WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN 3 DIRECTIONS (TENSION AND COMPRESSION) 40444444444t444444044444444444444444tf0444444444444444444444444444444t44444
 
4444f444484444404444404444444044444444t44f444444f4444444       440444044f44f44 NUTECH                                                             PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                         44t44444 DATA ELEMENT : COMPDES                 PAGE       , 11 REVISION   RRS1 DATE 85/12/04 444444444444444444444444444444444444444444444440444444t4444044t4444444t REFERENCE KEY   HANGERS (ALL TYPES INCLUDING SNUBBERS) COMPONENT DESCRIPTION HBTWW           3WY BOX THREE WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN 3 DIRECTIONS (TENSION AND COMPRESSION)
RESTRICTS FORCES IN 3 DIRECTIONS (TENSION AND COMPRESSION)
CONSTNT CONSTANT (MECHANICAL ATTACHMENT TO COMPONENT)
HCONM            CONSTNT CONSTANT (MECHANICAL ATTACHMENT TO COMPONENT)
ACTS IN TENSION ONLY, SPRING/LEVER ASSEMBLY PROVIDES CONSTANT RESTRAINING FORCE CONSTNT CONSTANT (WELDED ATTACHMENT TO COMPONENT)
ACTS IN TENSION ONLY, SPRING/LEVER ASSEMBLY PROVIDES CONSTANT RESTRAINING FORCE HCONW            CONSTNT CONSTANT (WELDED ATTACHMENT TO COMPONENT)
ACTS IN TENSION ONLY, SPRING/LEVER ASSEMBLY PROVIDES CONSTANT RESTRAINING FORCE GUIDE GUIDE (MECHANICAL ATTACHMENT TO COMPONENT)
ACTS IN TENSION ONLY, SPRING/LEVER ASSEMBLY PROVIDES CONSTANT RESTRAINING FORCE HGUDM            GUIDE GUIDE (MECHANICAL ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION)
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION)
GUIDE GUIDE (WELDED ATTACHMENT TO COMPONENT)
HGUDW            GUIDE GUIDE (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION)
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION)
HSNUBBR HYDRAULIC SNUBBER (MECHANICAL ATTACHMENT TO COMPONENT)
HHSBM            HSNUBBR HYDRAULIC SNUBBER (MECHANICAL ATTACHMENT TO COMPONENT)
HSNUBBR HYDRAULIC SNUBBER (WELDED ATTACHMENT TO COMPONENT)
HHSBW            HSNUBBR HYDRAULIC SNUBBER (WELDED ATTACHMENT TO COMPONENT)
MSNUBBR MECHANICAL SNUBBER (MECHANICAL ATTACHMENT TO COMPONENT) 444444444'4444t444444444444444444444444440444444f444444444444444444404044444
HMSBM            MSNUBBR MECHANICAL SNUBBER (MECHANICAL ATTACHMENT TO COMPONENT) 444444444'4444t444444444444444444444444440444444f444444444444444444404044444
:~e  
 
+444444404t4404444444t4t444444444444444444444f4444444f444 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4 DATA ELEMENT: COMPDES PAGE, 12 REVISION RRS1 DATE 85/12/04 444444444f444444ftt404440444444444ff444f4444f44444444444444444f444f44f44444 REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS)COMPONENT DESCRIPTION HMSBW HOWBM HOWBW HRESM HRESW HRRSM HRRSW MSNUBBR MECHANICAL SNUBBER (WELDED ATTACHMENT TO COMPONENT) 1WY BOX ONE WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
  ~
e
 
+ 444444404t4404444444t4t444444444444444444444f4444444f444 NUTECH                                                             PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4                       DATA ELEMENT : COMPDES                 PAGE,RRS112 REVISION DATE 85/12/04 444444444f444444ftt404440444444444ff444f4444f44444444444444444f444f44f44444 REFERENCE KEY   HANGERS (ALL TYPES INCLUDING SNUBBERS)   COMPONENT DESCRIPTION HMSBW           MSNUBBR MECHANICAL SNUBBER (WELDED ATTACHMENT TO COMPONENT)
HOWBM          1WY BOX ONE WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
1WY BOX ONE WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
HOWBW          1WY BOX ONE WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRNT RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
HRESM          RESTRNT RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. E.G.) A STRUT HRESW          RESTRNT RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
E.G.)A STRUT RESTRNT RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS   AXIS), RIGID IN TENSION AND COMPRESSION. E.G.) A STRUT HRRSM          R STRUT RIGID ROD STRUT (MECHANICAL ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS) . RIGID IN TENSION AND COMPRESSION.
E.G.)A STRUT R STRUT RIGID ROD STRUT (MECHANICAL ATTACHMENT TO COMPONENT)
HRRSW          R STRUT RIGID ROD STRUT (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS).RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS   AXIS), RIGID IN TENSION AND COMPRESSION.
R STRUT RIGID ROD STRUT (WELDED ATTACHMENT TO COMPONENT)
4444444444444444444444444444444444444444444t40444444444444444044t444
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
 
4444444444444444444444444444444444444444444t40444444444444444044t444  
  +444444444444444444 4444444444444440444444404440444t4f444+                                                             4444444444tff44 NUTECH                                                                                                                        PRISIM         4 CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                                                 4444444 44 444444444 DATA ELEMENT : COMPDES                                                     PAGE                   13 REVISION           RRS1 DATE       85/12/04 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 '4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 REFERENCE KEY                 HANGERS         (ALL TYPES INCLUDING SNUBBERS)                                 COMPONENT DESCRIPTION HRTSM                         T STRUT RIGID TELESCOPING STRUT (MECHANICAL ATTACHMENT TO COMPONENT)
+444444444444444444 NUTECH 4444444444444440444444404440444t4f444+
4444444444tff44 PRISIM 4 REFERENCE CLUSTER LISTING 4444444 44 444444444 DATA ELEMENT: COMPDES PAGE 13 REVISION RRS1 DATE 85/12/04 CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4'4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS)COMPONENT DESCRIPTION HRTSM HRTSW T STRUT RIGID TELESCOPING STRUT (MECHANICAL ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
T STRUT RIGID TELESCOPING STRUT (WELDED ATTACHMENT TO COMPONENT)
HRTSW                        T STRUT RIGID TELESCOPING STRUT (WELDED ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION.
HSSAM HSSAW HSUPM ARRESTR SHOCK AND SWAY ARRESTOR (MECH.ATTACHMENT TO COMPONENT)
HSSAM                         ARRESTR SHOCK AND SWAY ARRESTOR (MECH. ATTACHMENT TO COMPONENT)
A PRECOMPRESSED SPRING THAT PROVIDES A RESTRICTING FORCE PROPORTIONAL TO DEFLECTION IN BOTH TENSION AND COMPRESSION.
A PRECOMPRESSED SPRING THAT PROVIDES A RESTRICTING FORCE PROPORTIONAL TO DEFLECTION IN BOTH TENSION AND COMPRESSION.
NOTE: SOME SNUBBERS ARE CALLED SHOCK AND SWAY ARRESTORS.
NOTE: SOME SNUBBERS ARE CALLED SHOCK AND SWAY ARRESTORS.
00 NOT USE HSSAM FOR SNUBBERS ARRESTR SHOCK AND SWAY ARRESTOR (WELDED ATTACHMENT TO COMPONENT)
00 NOT USE HSSAM FOR SNUBBERS HSSAW                        ARRESTR SHOCK AND SWAY ARRESTOR (WELDED ATTACHMENT TO COMPONENT)
A PRECOMPRESSED SPRING THAT PROVIDES A RESTRICTING FORCE PROPORTIONAL TO DEFLECTION IN BOTH TENSION AND COMPRESSION.
A PRECOMPRESSED SPRING THAT PROVIDES A RESTRICTING FORCE PROPORTIONAL TO DEFLECTION IN BOTH TENSION AND COMPRESSION.
NOTE: SOME SNUBBERS ARE CALLED SHOCK AND SWAY ARRESTORS.
NOTE: SOME SNUBBERS ARE CALLED SHOCK AND SWAY ARRESTORS.
DO NOT USE HSSAW FOR SNUBBERS SUPPORT SUPPORT (MECHANICAL ATTACHMENT TO COMPONENT)
DO NOT USE HSSAW FOR SNUBBERS HSUPM                        SUPPORT SUPPORT (MECHANICAL ATTACHMENT TO COMPONENT)
A HANGER THAT ACTS IN TENSION ONLY, OR COMPRESSION ONLY E.G.1)A DEAD WEIGHT HANGER RIGID IN TENSION ONLY E.G.2)A STANCHION ON A SLIDING PAD RIGID IN COMPRESSION 44444t44444444444444444444f4444444444f44444444t444444444444444444444444 PRI SIM MPANY tttttttttttttttttt PAGE'14 REVISION RRS1 DATE 85/12/04 tttttttttttttttttttttttttttttt NUTECH CAROLINA POWER 8 LIGHT CO t SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES ttttttttttttttttttttttttttttttttttttttttttttt tttttttttttttttttttttttttttttt ttttttttttttttt REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS)COMPONENT DESCRIPTION HSUPW HTWBM HTWBW HUBTM HUBTW HVARM HVARW SUPPORT SUPPORT (WELDED ATTACHMENT TO COMPONENT)
A HANGER THAT ACTS IN TENSION ONLY, OR COMPRESSION ONLY E.G. 1) A DEAD WEIGHT HANGER RIGID IN TENSION ONLY E.G. 2) A STANCHION ON A SLIDING PAD RIGID IN COMPRESSION 44444t44444444444444444444f4444444444f44444444t444444444444444444444444
A HANGER THAT ACTS IN TENSION ONLY, OR COMPRESSION ONLY E.G.1)A DEAD WEIGHT HANGER RIGID IN TENSION ONLY E.G.2)A STANCHION ON A SLIDING PAD RIGID IN COMPRESSION 2WY BOX TWO WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
 
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION) 2WY BOX TWO WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
tttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                          PRI SIM CAROLINA POWER 8 LIGHT CO MPANY t                             SYSTEM REFERENCE CLUSTER LISTING             tttttttttttttttttt
                                                                      '14 DATA ELEMENT : COMPDES               PAGE REVISION  RRS1 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt DATE REFERENCE KEY HANGERS   (ALL TYPES INCLUDING SNUBBERS) COMPONENT DESCRIPTION HSUPW         SUPPORT SUPPORT (WELDED ATTACHMENT TO COMPONENT)
A HANGER THAT ACTS IN TENSION ONLY, OR COMPRESSION ONLY E.G. 1) A DEAD WEIGHT HANGER RIGID IN TENSION ONLY E.G. 2) A STANCHION ON A SLIDING PAD RIGID IN COMPRESSION HTWBM        2WY BOX TWO WAY BOX   RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT)
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION)
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION)
U-BOLT U-BOLT (MECHANICAL ATACHMENT TO COMPONENT)
HTWBW        2WY BOX TWO WAY BOX  RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
U-BOLT U-BOLT (WELDED ATACHMENT TO COMPONENT)
RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION)
VARABLE VARIABLE (MECHANICAL ATTACHMENT TO COMPONENT)
HUBTM        U-BOLT U-BOLT (MECHANICAL ATACHMENT TO COMPONENT)
ACTS IN TENSION ONLY, A SPRING ASSEMBLY WHERE THE RESTRICTING FORCE IS PROPORTIONAL TO DEFLECTION VARABLE VARIABLE (WELDED ATTACHMENT TO COMPONENT)
HUBTW        U-BOLT U-BOLT (WELDED ATACHMENT TO COMPONENT)
ACTS IN TENSION ONLY, A SPRING ASSEMBLY WHERE THE RESTRICTING FORCE IS PROPORTIONAL TO DEFLECTION  
HVARM        VARABLE VARIABLE (MECHANICAL ATTACHMENT TO COMPONENT)
, 0 444444444444444444444444444444444t44444444444 444t44f44t444f4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING%4f44444t44444 4 DATA ELEMENT: COMPDES PAGE 15 REVISION RRS1 DATE 85/12/04 4444444444t444f444444444444444444t444440444444t44444f44 REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS)COMPONENT DESCRIPTION HWHPM HWHPW HXXXX WHI PRES WHIP RESTRAINT (MECHANICAL ATTACHMENT)
ACTS IN TENSION ONLY, A SPRING ASSEMBLY WHERE THE RESTRICTING FORCE IS PROPORTIONAL TO DEFLECTION HVARW        VARABLE VARIABLE (WELDED ATTACHMENT TO COMPONENT)
A HANGER DESIGNED FOR PIPE BREAK EVENTS THAT IS CHARACTERIZED BY LARGE GAPS (>1/8 INCH)AND ENERGY ABSORBING (CRUSHABLE)
ACTS IN TENSION ONLY, A SPRING ASSEMBLY WHERE THE RESTRICTING FORCE IS PROPORTIONAL TO DEFLECTION
MATERIALS EXEMPT FROM EXAMINATION BY INTERPRETATION XI-80-02 SEE ITEMNO 81W-01F1.EX, 81W-01F2.EX, AND 81W-01F3.EX WHIPRES WHIP RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
 
A HANGER DESIGNED FOR PIPE BREAK EVENTS THAT IS CHARACTERIZED BY LARGE GAPS (>1/8 INCH)AND ENERGY ABSORBING (CRUSHABLE)
0
MATERIALS EXEMPT FROM EXAMINATION BY INTERPRETATION XI-80-02 SEE ITEMNO 81W-01F1.EX, 81W-01F2.EX, AND 81W"01F3.EX TEMPORARY COMPONENT DESCRIPTION VALIDATION CHECK FOR HANGER LOAD 4444444444444t444444444f444440444444f4f4ff44444f444tff4404444444440  
 
444444444444444444444444444444444t44444444444     444t44f44t444f4 NUTECH                                                             PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4                     REFERENCE CLUSTER LISTING                 %4f44444t44444 4                       DATA ELEMENT : COMPDES               PAGE         15 REVISION   RRS1 DATE   85/12/04 4444444444t444f444444444444444444t444440444444t44444f44 REFERENCE KEY   HANGERS   (ALL TYPES INCLUDING SNUBBERS) COMPONENT DESCRIPTION HWHPM           WHI PRES WHIP RESTRAINT (MECHANICAL ATTACHMENT)
A HANGER DESIGNED FOR PIPE BREAK EVENTS THAT IS CHARACTERIZED BY LARGE GAPS ( > 1/8 INCH )
AND ENERGY ABSORBING (CRUSHABLE) MATERIALS EXEMPT FROM EXAMINATION BY INTERPRETATION XI-80-02 SEE ITEMNO 81W-01F1.EX, 81W-01F2.EX, AND 81W-01F3.EX HWHPW          WHIPRES WHIP RESTRAINT (WELDED ATTACHMENT TO COMPONENT)
A HANGER DESIGNED FOR PIPE BREAK EVENTS THAT IS CHARACTERIZED BY LARGE GAPS ( > 1/8 INCH )
AND ENERGY ABSORBING (CRUSHABLE) MATERIALS EXEMPT FROM EXAMINATION BY INTERPRETATION XI-80-02 SEE ITEMNO 81W-01F1.EX, 81W-01F2.EX, AND 81W"01F3.EX HXXXX          TEMPORARY COMPONENT DESCRIPTION VALIDATION CHECK FOR HANGER LOAD 4444444444444t444444444f444440444444f4f4ff44444f444tff4404444444440
 
a~44444444444444444444444444444444444444444444444444444444      444444444404444 NUTECH                                                            PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                PAGE          16 REVISION ,RRS1 4                                                              DATE  85/12/04 4444444444444444444444444444t44t444t444044444444444444444 REFERENCE KEY                    PIPING  COMPONENT DESCRIPTION
                +++++++++++++t++++++++++    PIPING  +++t++++++++++++++++++++++
                +  EXAMINATION CATEGORIES  B-F, B-J, B-K-1, C-C, C-F,        +
                +                    D-A, D-B,  AND 0-C (81W)                  +
PBC,            +++ A BRANCH CONNECTION WITHOUT CIRCUMFERENTIAL WELDS +++
PBC,A          BC UNK BRANCH CONNECTION, TYPE UNKNOWN PBC,E          ELBOWLT ELBOWLET PBC,HC          HALFCPL HALF COUPLING PBC,LOL        LATROLT LATEROLET PBC,LSP        LSWEEPT LATERAL SWEEPOLET PBC,S          SOCKOLT SOCKOLET PBC,SWP        SWPOLET SWEEPOLET PBC,T          THREDLT THREADOLET 4444444444444448t444ft444444444ft444444444044fffkf4f4444444444444444444444
 
44444444444444t44444444t4444444444444  4444444444444444444    C44444444444444 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              444444444444444444 DATA ELEMENT : COMPDES                  PAGE          17 REVISION  RRS1 DATE  85/12/04 440444440444444444444444444440444444f44  44444444r4444444444444044044444444444 REFERENCE KEY                    PIPING COMPONENT DESCRIPTION PBC,TE          THERMOWELL TEMPERATURE ELEMENT PBC,W          WELDOLT WELDOLET PBCC,          +++ A BRANCH CONNECTION WITH CIRCUMFERENTIAL WELDS ONLY +++
PBCC,CR        CROSS PBCC,EX        EXTRUD PIPE EXTRUSION PBCC,L          LATERAL PBCC,T          TEE PBCC,TR        RED TEE TEE, REDUCING PC,            +++  CIRCUMFERENTIAL PIPING WELD    +++
PC,ACC          ACCUM ACCUMULATOR PC,CAP          CAP PC,EXPJ        EXP JNT EXPANSION JOINT 444444444444f4444444444444444t44t444444ff444t44f4444444
 
44444444444444444444444444f444444444444444444444444+      f44f444444444f4 4'UTECH                                                                PRISIM CAROLINA POWER  8 LIGHT COM PANY SYSTEM 4
REFERENCE CLUSTER LISTING              444444444444444444 DATA ELEMENT : COMPDES                PAGE          18 REVISION  RRS1 DATE  85/12/04 444444444W444444444444444444444444444444444444            4444444444444444t444f REFERENCE KEY                    PIPING  COMPONENT DESCRIPTION PC,FE            FLOW EL FLOW ELEMENT PC,MAN          MANIFLD MANIFOLD PC,NOZ          NOZZLE PC,NOZW          NOZ WLD WELD IN NOZZLE FLANGE PC,PB            P BEND PIPING BEND PC, PIPE        PIPE PC,PUMP          PUMP PC,RED          REDUCER PC,REDI          RED INS REDUCING INSERT PC,SDFP          SUMP PL SUMP DRAIN  FILTER PLATE PC,SE            SAFEEND SAFE END PC,SEE          SAFEEND SAFE END EXTENSION 44444444444444f444tf44444tt44444444444444444444444444f4f44f444444444t44444f
 
++44444444f444444444t4444f44444444444444f444f444444444444+        444444444t44044 NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4                      DATA ELEMENT : COMPDES                  PAGE        19 REVISION RRS1 DATE 85/12/04 44444444444f444444444444444f44I44444444444444444444fff4444444f4044f44fff444 REFERENCE KEY                    PIPING  COMPONENT DESCRIPTION PC,TRS          TRANS TRANSITION PIECE PC,TS          T STRNR TEMPORARY STRAINER PC,VENC        VENTURI CAVITATING VENTURI PC,VLV          VALVE PE ~
                +++ ELBOWS +++
PE,ELR          ELB ELR ELBOW, EXTRA LONG RADIUS PE,LR          ELB LR ELBOW, LONG RADIUS PE,RED          RED ELB REDUCING ELBOW PE,SR          ELB SR ELBOW, SHORT RADIUS PELBOW          ELBOW ELBOW, RADIUS UNKNOWN PF,            +++  FLANGES  +++
044444444444444'444440t4444444444444'4004004440t444444t4044444444444440444444
 
  ~1 dl
 
440444444440044 NUTECH                                                              PRISIM CAROLINA POWER  8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              444444444444044444 DATA ELEMENT : COMPDES                  PAGE      ~. 20 REVISION  RRS 1 DATE  85/12/04 444488444444444t4444444444t44444t44444444444444444444444f44444f44444444 REFERENCE KEY                    PIPING  COMPONENT DESCRIPTION PF,A            FLG UNK FLANGE, TYPE UNKNOWN PF,B            FLG BLN FLANGE, BLIND PF,O            FLG ORF FLANGE, ORIFICE PF,RED          FLG RED FLANGE, REDUCING PF,RFWN        FLG RFW FLANGE, RAISED FACE WELD NECK PF,RWNR        FLG RWR FLANGE, RAISED FACE WELD NECK REDUCING PF,SO          FLG SLP FLANGE,  SLIP ON PF,SW          +++  FLANGE, SOCKET WELDED (SHOULD BE ENTERED AS PSW,F)      +++
PF,WN          FLG WN FLANGE, WELD NECK PF,WNGF        FLG WNG FLANGE, WELD NECK GROOVED FACE PF,WNO          FLG WNO FLANGE, RAISED FACE WELD NECK ORIFICE 888444408040444t44444444444444444444444444444444444440444t44t44444t44444444
 
0 444444444444f44444444444444444444~    444444f44444444 NUTECH                                                              PRISIM CAROLINA POWER  8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                <<.PAGE          21 4                                                                REVISION  RRS1 DATE  85/12/04 4444448044444444444444444444444404444444f444444444t44444444444404t444tt4444 REFERENCE KEY                    PIPING  COMPONENT DESCRIPTION PF,WNTF        FLG WNT FLANGE, WELD NECK TONGUE FACE PI            +++  INTEGRALLY WELDED ATTACHMENTS      +++
PI,            +++  EXAMINATION CATEGORIES 8-K- 1, C-C, D-A,      +++
              +++              D-B, AND D-C (81W)                +++
PI, CL        CENTER PIPE SUPPORT,  CENTERING LUG PI, CLVN      CLEVIS WELDED LUGS,  FORMING A CLEVIS, NOT FULL PENETRATION PI, FHA        TYPEI IA FLUED HEAD, TYPE  IIA PI, FHB        TYPEIIB FLUED HEAD, TYPE  IIB PI, FHI        TYPE I FLUED HEAD, TYPE  I PI, HL        HANGER PIPE SUPPORT,  HANGER LUG PI,LUGF        LUG, FP LUG, FULL PENETRATION WELD PI, LUGN        LUG, PP LUG, NOT FULL PENETRATION    (FILLET OR  PARTIAL PENETRATION) e8884t8%4%444444444444tt4444404404444444444444444404044444444444444444444%4
 
~404444444444444444t444444444t44tt444444444404444440444'4 NUTECH                                                              PRISIM CAROLINA POWER    8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              44444444 4 44444  444 4 DATA ELEMENT : COMPDES                PAGE,        ~ 22 REVISION '.RRSl DATE  85/12/04 4444444t4444tt444444444t44t444444t04444440444t44444444404444t444t4440444440 REFERENCE  KEY                    PIPING COMPONENT DESCRIPTION PI,PSU          SUPPORT PIPE SUPPORT,  TYPE UNKNOWN PI,R            RING RING SUPPORT PI, SADL        SADDLE PI, STAN        STANCHN STANCHION PI,TRUN        TRUNNON TRUNNION PLSW,          +++ LONGITUDINAL SEAM WELDS +++
PLSW,C          CRSSEAM LONGITUDINAL SEAM WELD, CROSS PLSW,EI        ELBSEAM LONGITUDINAL SEAM WELD'LBOW INSIDE ARC PLSW,EO        ELBSEAM LONGITUDINAL SEAM WELD'LBOW OUTSIDE ARC PLSW,P          LNGSEAM LONGITUDINAL SEAM WELD, PIPE PLSW,R          REDSEAM LONGITUDINAL SEAM WELD, REDUCER 044t4444444t444444tttt4444444444444f4444444444444ft4444444404tt444f4444f4
 
i444t4444 eeyeekgeg4444444444444444444444f444f44444444444        s444444444444444 NUTECH                                                              PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                444444444444404444 DATA ELEMENT : COMPDES                  PAGE          23 REVISION  RRS 1 "2                          DATE  85/12/04 4444440444444444444404404444444440444r4448448444444 REFERENCE KEY                      PIPING COMPONENT DESCRIPTION PLSW,T          TEESEAM LONGITUDINAL SEAM WELD, TEE PP,              +++ PENETRATION COMPONENTS +++
                + USE  PI,FHA  OR  PI,FHB FOR INTEGRAL ATTACHMENT FLUED HEADS +
PP,ENDP          PPLATE PENETRATION END PLATE PP,FHS          FL HEAD FLUED HEAD, SINGLE (WITH A WELD IN THE PENETRATION)
PP,FHSI          FL HEAD FLUED HEAD, SINGLE INTEGRAL (ALL ONE PIECE)
PP,FHT          FL HEAD FLUED HEAD, TRIPLE (WITH A WELD IN THE PENETRATION)
PP,FHTI          FL HEAD FLUED HEAD, TRIPLE INTEGRAL (ALL ONE PIECE)
PP,PIPE          PENPIPE PENETRATION PIPE (THE PIPE SUPPLIED BY THE CONTAINMENT SUPPLIER RATHER THAN THE PIPING SUPPLIER)
PP PLT
    ~            PPLATE PENETRATION PLATE PP,TRP          PENPLT TORUS SHELL PENETRATION REINFORCEMENT PLATE 444444444444444t44f44444444444t4444t44444f444444f44444444444t44444tft44t4f4
 
ittttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                          PRISIM CAROLINA POWER  8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING            tttttttttttttttttt DATA ELEMENT : COMPDES                PAGE        24 REVISION  RRS 1 DATE 85/12/04 tttttttttttttttttttt          ttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                  PIPING COMPONENT DESCRIPTION PSW,          +++ SOCKET WELDS +++
PSW,C          CAP PSW,CPL        COUPLNG COUPLING PSW,CPR        RCUPLNG REDUCING COUPLING PS'            ELBOW PSW,F          FLANGE PSW,FO        ORIFICE FLANGE, ORIFICE PSW,HC        HLF CUP HALF COUPLING PSW,MAN        MANIFLD MANIFOLD PSW,P          PIPE PSW,PB        P BEND PIPING BEND PSW,RED        REDUCER tttttttttttttttttttttttttttttttttttttttttttttttttttttttttt
 
444t4444444444444f44444044444    44t4444440444444444444444+        444444t4t4f44f4 NUTECH                                                                    PRISIM CAROLINA POWER  8 LIGHT  CO MPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                      PAGE          25 REVISION  RRS1 DATE  85/12/04 44444444$ 444444444444444444444444444444fay    f 444 4444444444444444444444440444t@4I REFERENCE KEY                      PIPING  COMPONENT DESCRIPTION PSW, RIN        RED INS REDUCING INSERT PSW,T            TEE PSW,TR          RED TEE REDUCING TEE PSW,UN          UNION PSW,VLV          VALVE 44444444444444444444444444444444444444444f44444444444444444f44444444444f44f
 
w+4444444%484844444444444404444404tf444440444444444f444444      44f444444t444ff NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4                    REFERENCE CLUSTER LISTING              444444444444444444 DATA ELEMENT : COMPDES                PAGE        = '26 REVISION  RRS  1 DATE  85/12/04 4044444444f44444444404t444444f444444444t404444440404444t440440 REFERENCE KEY            PWR  VESSEL INTERNAL COMPONENT DESCRIPTION
                +                                                                +
                +++++++++++++    PWR REACTOR VESSEL INTERNALS +++++++++++++++
                +        EXAMINATION CATEGORIES 8-N-1 AN B-N-2 (81W)            +
RAKUSP          AKUSP ALIGNMENT KEYWAYS UPPER SUPPORT PLATE RAP            ACC PLT ACCESS PLATE RBBBC          BBBC BAFFLE BOLTING AND BAFFLE CORNERS RCBFFN          CBFFN CORE BARREL FLANGE FLOW NOZZLES RCBMPGW        CBMPGW CORE BARREL  MID-PLANE GIRTH WELD RCBNVIS        CBNVIS CORE BARREL OUTLET NOZZLE/VESSEL INTERFACE SURFACE RCRDGT          CRDGT CONTROL ROD DRIVE GUIDE TUBE  (INTERNAL INSPECTION OF GUIDE TUBE)
RCRODS          CRODS CONTROL RODS RCSC            CSC CORE SUPPORT  COLUMN 48444t444fkt444444444444444440444t404t444444444444444444f444444444444444404
 
0 44444444484444444444444t44444444444404444444444444044444      444444f40444f44 NUTECH                                                              PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                0444444444444444 DATA ELEMENT : COMPDES                PAGE          27 REVISION    RRS1 DATE  B5/12/04 444444444444444444444444444444444444444044444444444444444444444444444444444 REFERENCE KEY              PWR VESSEL INTERNAL COMPONENT DESCRIPTION RCSPACB        CSPACB CORE SUPPORT PLATE ATTACHMENTS TO CORE BARREL RCSS            CSS CORE SUPPORT  STRUCTURES RFTCBW          FTCBW FLANGE TO CORE BARREL WELD RGTAUCP        GTAUCP GUIDE TUBE ATTACHMENTS TO UPPER CORE PLATE RHAVAP          HAVAP HEAD 8 VESSEL ALIGNMENT PINS (MATING SURFACES    8  ATTACHMENTS)
RIGC            IGC INSTRUMENT GUIDE COLUMNS RINT            INT  SUR INTERIOR SURFACE RISB            ISB IRRADIATION SPECIMEN BASKETS RLCP            LCP LOWER CORE PLATE RLCPFAP        LCPFAP LOWER CORE PLATE FUEL ALIGNMENT  PINS 44444444f444444f4444t444444444ff44fff4444444f44444444444t4444444444f4444444
 
444444444444444444444444  444444444444444'4444444444444444      444444444444444 NUTECH                                                              PRIS(M CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : COMPDES                    PAGE        28 REVISION  RRS 1 DATE  85/12/04 REFERENCE KEY            PWR  VESSEL INTERNAL COMPONENT DESCRIPTION RLCSC          LCSC LOWER CORE SUPPORT    COLUMNS RLCSCB          LCSCB LOWER CORE SUPPORT    COLUMN BOLTING RLSC            LSC LOWER SUPPORT  COLUMNS RNPLS          NPLS NEUTRON PANEL LOCKING SCREWS RRCCADS        RCCADS ROD CLUSTER CONTROL ASSEMBLY (RCCA)      DRIVE SHAFTS RRCCAHS        RCCAHS ROD CLUSTER CONTROL ASSEMBLY (RCCA)      HUBS/SPIDERS RRS/LCS        RS/LCS RADIAL SUPPORTS/LOWER CORE SUPPORTS RSCSA          SCSA SECONDARY CORE SUPPORT    ASSEMBLY RTC            TC THERMOCOUPLE CONDUITS RTFM            TFM THERMOCOUPLES AND FLOW MIXERS 444444444444444444444444444444440444f444f44tf4tffff4444t44444444f400t44ftf4
 
44444448%4444444444444444444444444404t444444 NUTECH                                                              PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                PAGE        29 REVISION  RRS1 DATE  85/12/04 St44444t4444444444444444ff44444444444444444444  44440444444444444440444444444 REFERENCE KEY            PWR  VESSEL INTERNAL COMPONENT DESCRIPTION RTSF            TSF THERMAL SHIELD FLEXURES RUCPAK          UCPAK UPPER CORE PLATE ALIGNMENT KEYWAYS RUCPFAP        UCPFAP UPPER CORE PLATE FUEL ALIGNMENT PINS RUIAKCB        UIAKC8 UPPER INTERNALS ALIGNMENT KEYS IN CORE 8ARREL RUSC            USC UPPER  SUPPORT  COLUMNS RUSF            USF UPPER SUPPORT FLANGE (LOCKING DEVICE WELDS) 4444444444f4444444444444444tbt44f4444444f44444444444444444444444t4444444044
 
tf44t4444t44t44444f4444444tff44444f4440444444+    444444444444444 NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM                                        4 REFERENCE CLUSTER LISTING              444444444444444044 DATA ELEMENT : COMPDES                PAGE, REVISION 30 RRS1 DATE  85/12/04 4444444444444444444444444440444044444444444t4444444044444444444 REFERENCE KEY            BWR VESSEL INTERNAL COMPONENT DESCRIPTION
                +                                                              +
                +++++++++++++  BWR REACTOR VESSEL INTERNALS +++++++++++++++
                +        EXAMINATION CATEGORIES 8-N-1 AND 8-N-3 (81W)
SCORES          CORESUP REACTOR VESSEL CORE SUPPORT  STRUCTURE SINT            INT SUR REACTOR VESSEL INTERIOR SURFACES SINTBL          INTATCH REACTOR VESSEL INTERIOR ATTACHMENTS  - BELTLINE SINTNBL        INTATCH REACTOR VESSEL INTERIOR ATTACHMENTS  - NON BELTLINE 4444444444444444444444444444444t404t4444t44444444f4444440444444t444404f4f44
 
  +ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH                                                          PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM t
REFERENCE CLUSTER LISTING            tttttttttttttttttt DATA ELEMENT : COMPDES                PAGE        31 REVISION  RRS1 t                                                            DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                  PWR PUMP COMPONENT  DESCRIPTION
              +++++++++++++++++++++  PWR PUMPS  +++++++++++++++++++++++++++
              +      EXAMINATION CATEGORIES B-M-1, B-M-2, AND C-G (81W)    +
TCHP1A        CH PMPA CHARGING WATER PUMP A TCHP1 8        CH PMPB CHARGING WATER PUMP 8 TCHPlc        CH PMPC CHARGING WATER PUMP C TFLYWHL        FLYWHL FLYWHEEL TIFEET        FEET PUMP SUPPORT  FEET TPUINT        PUMP INT PUMP INTERNALS TPUMPCW        PUMPCW PUMP CASING WELD TRCP          RC PMP REACTOR COOLANT PUMP TRCP1A        RC PMPA REACTOR COOLANT PUMP A
 
+ 44f4f4444444444444 44444444444444444444444444444404444444    444844444484044 NUTECH                                                              PRISIM CAROLINA POWER  8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              444440444044444444 DATA ELEMENT : COMPDES                PAGE        " 32 REVISION  RRS1 DATE  85/12/04 444444444444444444444444444444444444444444440444444444444444040444444444444 REFERENCE KEY                  PWR  PUMP COMPONENT DESCRIPTION TRCP1B          RC PMPB REACTOR COOLANT PUMP B TRCPlc          RC PMPC REACTOR COOLANT PUMP C TRHP1A          RH PMPA RESIDUAL HEAT REMOVAL PUMP A TRHPlB          RH PMPB RESIDUAL HEAT REMOVAL PUMP B TRSP1A          RS PMPA RECIRCULATION SPRAY PUMP A TRSP1B          RS PMPB RECIRCULATION SPRAY PUMP  B TRSP1C          RS PMPC RECIRCULATION SPRAY PUMP  C TRSP10          RS PMPD RECIRCULATION SPRAY PUMP  D TSRCP          S RCP SUPPORT, REACTOR COOLANT PUMP 444t4444444444f44f4tkf4f4404444444444444444444444t40444044
 
4444444444444t444t44t44ftf4f4    +44f44f444444444 NUTECH                                                                PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : COMPDES                  PAGE          33 REVISION    RRS1 DATE BS/12/04 4444444444444444444  444'4f4444t4444444444444tkf444444444444f4444444444444444 REFERENCE KEY                    BWR PUMP COMPONENT  DESCRIPTION
                +                                                                +
                +++++++++++++++++++++    BWR PUMPS  +++++++++++++++++++++++++++
                +    EXAMINATION CATEGORIES B-M-1, B-M-2, AND C-G (81W)          +
UCSP1A          CS PMPA CORE SPRAY PUMP A UCSP1B          CS PMPB CORE SPRAY PUMP B UCSP1C          CS PMPC CORE SPRAY PUMP C UCSP1D          CS PMPD CORE SPRAY PUMP D UHPB            HP 800S HIGH PRESSURE  COOLANT INJECTION BOOSTER PUMP UHPCS          HPCS HIGH PRESSURE CORE SPRAY UHPM            HP MAIN HIGH PRESSURE  COOLANT INJECTION MAIN PUMP UPUHL          PUMPHL PUMP HANGER LUGS UPUINT          PUMP INT PUMP INTERNALS 444444444444444444444444444444444444444440444444444444444444444444444444444
 
C4 44  4444 44444444444444444444444044444444444444444444404+      444444444444444 NUTECH                                                                PRI SIM CAROLINA POWER a LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              444444444444404444 DATA ELEMENT : COMPDES                  PAGE      , 34 REVISION    RRS  1 DATE  85/12/04 4444444444444444444444444t44444444404440444444444t44444 REFERENCE KEY                      BWR PUMP COMPONENT  DESCRIPTION UPUMPCW            PUMPCW PUMP CASING WELD URCIC              RCIC REACTOR CORE ISOLATION COOLING PUMP URHP1A            RH PMPA RESIDUAL HEAT REMOVAL PUMP A URHP1B            RH PMPB RESIDUAL HEAT REMOVAL PUMP B URHP 1 c          RH PMPC RESIDUAL HEAT REMOVAL PUMP  C URHP1D            RH PMPD RESIDUAL HEAT REMOVAL PUMP  D URRP1A            RR PMPA REACTOR RECIRCULATION PUMP A URRP1B            RR PMPB REACTOR RECIRCULATION PUMP 8 USLP1A            SL PMPA STANDBY LIQUID CONTROL PUMP A USLP1B            SL PMPB STANDBY LIQUID CONTROL PUMP B t
eeeeee44444444t44444444ft44t4444ekee444444444ekff4444444444444444t444444444
 
t ttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt f
NUTECH                                                          PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM t
REFERENCE CLUSTER LISTING            ttttttttttttttttttt DATA ELEMENT : COMPDES                PAGE        ... 35 REVISION  RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION
              +                                                                +
              ++++++++++++++++++  PWR  PRESSURE VESSELS ++++++++++++++++++++
              + EXAMINATION CATEGORIES B-A, B-B, B-C, B-E, B-H, B-O, C-A +
              +                      C-8 AND C-C (81W)                        +
VAT1A        A TANKA ACCUMULATOR TANK A VAT18        A TANKB ACCUMULATOR TANK 8 VAT1C        A TANKC ACCUMULATOR TANK C VCHVP        CHVP CLOSURE HEAD VENT PENETRATION VCHW          C  HEAD CIRCUMFERENTIAL HEAD WELD VCLADH        CLAD HD CLADDING, HEAD VCLADV        CLAD VS CLADDING, VESSEL VCRDHW        CRDHW CONTROL ROD DRIVE HOUSING WELD VCRDTVW        CRDTVW CONTROL ROD DRIVE TO VESSEL WELD
 
ttttttttttttttttttttttttt tttttttttttttttttttttttttttttt tttttttttttttttt NUTECH                                                        PRISIM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                PAGE        36 REVISION  RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VCSW          C SHELL CIRCUMFERENTIAL SHELL WELD VELHE          ELHE EXCESS LETDOWN HEAT EXCHANGER VFTHW          FTHW FLANGE TO HEAD WELD VFTSW          FTSW FLANGE TO SHELL WELD VHTRPEN        HTR PEN HEATER PENETRATIONS (PRESSURIZER)
VI,            +++ INTEGRALLY WELDED ATTACHMENT +++
VI, LUG        LUG VI,PSB        PZR SUP BR PRESSURIZER  SUPPORT BRACKET VI . PSC      PZR COL PRESSURIZER SUPPORT COLLAR VI, SGSW      SGSW STEAM GENERATOR SUPPORT WELD VI,SR          SADDLE SADDLE REINFORCEMENT (NOZZLE, TRUNION,  ETC.)
 
+~444444444444444444444444444444444444444444444t4444444444+    444444444404444 NUTECH                                                          PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              44444444444t 0 0 44 44 DATA ELEMENT : COMPDES                PAGE,      - 37 REVISION  RRS1 DATE  85/12/04 44444444440444444404444f4404404444444f4444444f444ff44404444t44t4 REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VI ~ STAN      STANCHN STANCHION VI, STVW        SKIRT SKIRT TO VESSEL WELD VI, SWP        WELDPAD SUPPORT WELD PAO VI o TRUN      TRUNNON TRUNNION VI,WSUP        PLATE WELDED SUPPORT  PLATE VICINOZ        ICI NOZ IN-CORE INSTRUMENTATION NOZZLES VINT            INT SUR VESSEL INTERIOR SURFACE VLSW            L SHELL LONGITUDINAL SHELL WELD VMHW            M HEAD MERIDIONAL HEAD WELD VMTHW          MANWAY MANWAY TO HEAD WELD  (CIRCUMFERENTIAL WELD) t44t444f44444444f44444444444444444444444tff4444f444ft4444444444444444444f44
 
4444444f444444444444444t4444f44444444444444t444f$    444444    4444444444444t4 NUTECH                                                              PRISIM CAROLINA POWER  8, LIGHT COMPANY SYSTEM 4
REFERENCE CLUSTER LISTING              444444444444444444 4                      DATA ELEMENT : COMPDES                  PAGE        =,38 REVISION,  RRS1 DATE 85/12/04 efee44444444004444444f444f444t444044444444f44f444444f4444f4444440444ftf44ff REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNIR            NIR NOZZLE INNER RADIUS VNIR---        NIR NIR---;  WHERE NIR INDICATES NOZZLE INNER RADIUS AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF      INLET OR OUTLET    EG. NIR1AO IS NOZZLE 1A, OUTLET NIR3BI IS NOZZLE 38, INLET VNIR1AI        NIR1AI NOZZLE 1A  (INLET) INNER RADIUS VNIR1BI        NIR1BI NOZZLE 1B  (INLET) INNER RADIUS VNIR1CI        NIR1CI NOZZI.E 1C ( INLET) INNER RADIUS VNIR3AO        NIR3AO NOZZLE 3A (OUTLET) INNER RADIUS VNIR3BO        NIR3BO NOZZLE 3B (OUTLET) INNER RADIUS VNI R3CO        NIR3CO NOZZLE 3C (OUTLET) INNER RADIUS VNOZ            NOZZLE VNOZ---        NOZZLE NOZ--- ; WHERE NOZ INDICATES A VESSEL NOZZLE AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF      INLET OR OUTLET EG. NOZIAO IS NOZZLE 1A, OUTLET NOZ3BI IS NOZZLE 3B, INLET 444444444444444444t4t.0444444f444ff4ff444f444f4f444444f44444444
 
44444444444444t44  s44444444444tt44 NUTECH                                                              PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4                    REFERENCE CLUSTER LISTING              444444404444444444 DATA ELEMENT : COMPDES                  PAGE, s REVISION RRS1 39 e
4                                                              DATE 85/12/04 4444444444444444444444C4444440444444444444444444444444444444444444444444444 REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNOZ1A I        NOZ1AI NOZZLE 1A (INLET)
VNOZ1AO        NOZ1AO NOZZLE 1A (OUTLET)
VNOZ1BI        NOZ1BI NOZZLE 18  (INLET)
VN02180        NOZ180 NOZZLE 18 (OUTLET)
VNOZ1CI        NOZ1CI NOZZLE 1C ( INLET)
VNOZ1CO        NOZ1CO NOZZLE 1C (OUTLET)
VNOZ1XI        VNOZ1XI NOZZLE 1X  (INLET)
VNOZ1XO        NOZ1XO NOZZLE 1X (OUTLET)
VNOZ3AI        NOZ3AI NOZZLE 3A  (INLET)
VNOZ3AO        NOZ3AO NOZZLE 3A (OUTLET) 444444444444444444444444444t444444444044404404f4404444f4444444444440444
 
  +444ff44f444f4444f4f4444f44f44f44f44444444f44444tf44f444+    4t4444ft4444444 NUTECH                                                          PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES              PAGE      ;, 40 REVISION  RRS1 4                                                            DATE  85/12/04 444444444444444444444444444444444f444f4444444444t4444444444444444444444f4t4 REFERENCE KEY      PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNOZ3BI          NOZ38I NOZZLE 38  (INLET)
VNOZ380          NOZ380 NOZZLE 38 (OUTLET)
VNOZ3CI          NOZ3CI NOZZLE 3C  (INLET)
VNOZ3CO          NOZ3CO NOZZLE 3C (OUTLET)
VNRHE            NRHE NON-REGENERATIVE HEAT EXCHANGER VNTHW            NOZZLE NOZZLE TO HEAD WELD VNTHWI          NOZZLE NOZZLE TO HEAD WELD    (INLET)
VNTHWO          NOZZLE NOZZLE TO HEAD WELD (OUTLET)
VNTVW            NOZZLE NOZZLE TO VESSEL WELD VNTVWI          NOZZLE NOZZLE TO VESSEL WELD    (INLET) 44444'4t44f44444ff444444444ft4444440444f4444444444444444440444f444fftf
 
~~444444444444444444044444444444444444444444444444444          444444044444444 NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM
                                                                              '4 REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                PAGE      -<<41 REVISION  RRS1 0 DATE  BB/12/04 REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNTVWO          NOZZLE NOZZLE TO VESSEL WELD (OUTLET)
VPRZ            PRZ PRESSURIZER VRCF            RCFILTR REACTOR COOLANT  FILTER VREPAIR        REPAIR REPAIR AREA IN BELTLINE REGION ONLY VRHE            RHE REGENERATIVE HEAT EXCHANGER VRH1A          RH HX A RESIDUAL HEAT REMOVAL HEAT EXCHANGER A VRH18          RH HX 8 RESIDUAL HEAT REMOVAL HEAT EXCHANGER 8 VRS1A          RS CLRA RECIRCULATION SPRAY COOLER A VRS18          RS CLRB RECIRCULATION SPRAY COOLER 8 VRS1C          RS CLRC RECIRCULATION SPRAY COOLER  C 44f4440f444f404444444444f444444f0444444444444444444444044444f44444444444
 
444444440444ff4444444f44444t4f44f4444444f4f44444444f4f44      4f44t4044444444 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              44t444444444444444 DATA ELEMENT : COMPDES                PAGE        ,42 REVISION    RRS1 DATE 85/12/04 4$ 44444444f444f4444444444448404404444044444f0440f4444f4444f4f4tf444444tfftt REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VRS10          RS CLRC RECIRCULATION SPRAY COOLER D VRV            REACTOR REACTOR VESSEL VSE            SAFEEND SAFE END VSGA            SGA STEAM GENERATOR A VSGB            SGB STEAM GENERATOR B VSGC            SGC STEAM GENERATOR C VSG1A          CHANGED TO VSGA VSG1B          CHANGED TO VSGB VSG1C          CHANGED TO VSGC VSTHW          STHW SHELL TO HEAD WELD VSWHE          SWHE SEAL WATER HEAT EXCHANGER 4444444444444444444444444t444tt44044444444444444t444444tkt4444404480t444444
 
+844t44444444444444444t444444f4448444444f44444444f444444      444444444444f44 NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                PAGE        43 REVISION RRSl DATE  85/12/04 4444444444444044444t44444444t4t4444t44444  444444444444444440444444f44444 REFERENCE KEY    PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VSWIFA          SWIFA SEAL WATER INJECTION FILTER A VSWIFB          SWIFB SEAL WATER INJECTION FILTER B VSWRF          SWRF SEAL WATER RETURN FILTER VTSTHW          TSTHW TUBE SHEET TO HEAD WELD VTSTVW          TSTVW TUBE SHEET TO VESSEL WELD VVCT            VC TANK VOLUME CONTROL TANK 4444t44444444444444444f4444444444444f444444f4444444444444444444404444404444
 
++444444t44ft444444444f4444444444444444444tf44444t44444444      +4444f44f4444444 4  NUTECH                                                                    PRISIM CAROLINA POWER  8  LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              4 4 4 4 4 4 4 4 4 4 '4 4 4 4 4 4 4 4 4                      DATA ELEMENT : COMPDES                  PAGE          -.        44 REVISION            RRS1 DATE        85/12/04 444444444444444444404044444444f4444t444444444444f444444f444tkft4f0444440 REFERENCE KEY    BWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION
                ++++++++++++++++++  BWR PRESSURE VESSELS ++++++++++++++++++++
                + EXAMINATION CATEGORIES B-A, B-B, B-C, B-E, B-H, 8-0, C-A C-8 AND C-C (81W)                                      +
WCHW            C HEAD CIRCUMFERENTIAL HEAD WELD WCLADH          CLAD HD CLADDING, HEAD WCLADV          CLAD VS CLADDING, VESSEL WCRDHW          CRDHW CONTROL ROD DRIVE HOUSING WELD WCRDTVW        CRDTVW CONTROL ROD DRIVE TO VESSEL WELD WCSW            C SHELL CIRCUMFERENTIAL SHELL WELD WFTHW          FTHW FLANGE TO HEAD WELD WFTSW          FTSW FLANGE TO SHELL WELD WI,            +++ INTEGRALLY WELDED ATTACHMENT +++
444444t44444444$ 4444f44444t4444444444444444444444t444444444444444444444$                  44f
 
t tttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                              PRISIM REFERENCE CLUSTER LISTING            t t t t tt t t t t t t t t t t t t DATA ELEMENT : COMPDES                PAGE                  45 REVISION          RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY  BWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WI,LUG        LUG WI,SR        SADDLE SADDLE REINFORCEMENT (NOZZLE, TRUNION, ETC.)
WI, STAN      STANCHN STANCHION WI, STVW      SKIRT SKIRT TO VESSEL WELD WI, SWP      WELDPAD SUPPORT WELD PAD WI, TRUN      TRUNNON TRUNNION WI CI NOZ    ICI NOZ IN-CORE INSTRUMENTATION NOZZLES WINT          INT SUR VESSEL INTERIOR SURFACE WLSW          L SHELL LONGITUDINAL SHELL WELD WMHW          M HEAD MERIDIONAL HEAD WELD WN I R        NIR NOZZLE INNER RADIUS
 
+~44444444444444444444444444$    44444f44444444f44444444444444    44444444t444444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                444444444404444444 DATA ELEMENT : COMPDES                  PAGE          46 REVISION  RRSl DATE  85/12/04 44444444444t4044444444444t444444t4t444444t440444444444444444404444 REFERENCE KEY      BWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WNIR---          NIR---
NIR---;    WHERE NIR INDICATES NOZZLE INNER RADIUS AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF        INLET OR OUTLET    EG. NIR1AO IS NOZZLE 1A, OUTLET NIR3BI IS NOZZLE 3B, INLET WNIR3AI          NOZZLE INNER RADIUS    - NOZZLE 3A, INLET WNIR3BI          NOZZLE INNER RADIUS  NOZZLE 3B, INLET WNIR4AO          NOZZLE INNER RADIUS  NOZZLE 4A, OUTLET WNI R4BO        NOZZLE INNER RADIUS  N022LE 4B, OUTLET WNOZ            NOZZLE WNOZ---          NOZZLE N02--- ; WHERE NOZ INDICATES A VESSEL NOZZLE AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF        INLET OR  OUTLET  EG. N021AO IS N022LE 1A, OUTLET N023BI IS NOZZLE 38, INLET WN023AI          VESSEL NOZZLE  N022LE 3A, INLET WN023BI          VESSEL NOZZLE  NOZZLE 3B, INLET WN024AO          VESSEL NOZZLE    -  NOZZLE 4A, OUTLET WN02480          VESSEL NOZZLE    -  NOZZLE 4Be OUTLET 04444f444f44t444f44444ff4444444444%44444444444444
 
+w4444444044444t4444044444444444444444440444444444'0444444 NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING            444444444444444444 DATA ELEMENT : COMPDES              PAGE          47 REVISION  . RRS1 DATE  85/12/04 4444444444444444444444444t4444444444444444444444444444444  444444444444444444 REFERENCE KEY    BWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WNTHW          NOZZLE NOZZLE TO HEAD WELD WNTS            TSLEEVE NOZZLE THERMAL SLEEVE WNTVW          NOZZLE NOZZLE TO VESSEL WELD WNTVWI          NOZZLE NOZZLE TO VESSEL WELD  (INLET)
WNTVWO          NOZZLE NOZZLE TO VESSEL WELD (OUTLET)
WREPAIR        REPAIR REPAIR AREA IN BELTLINE REGION ONLY WRH I A        RH HX A RESIDUAL HEAT REMOVAL HEAT EXCHANGER A WRH18          RH HX  8 RESIDUAL HEAT REMOVAL HEAT EXCHANGER 8 WRV            REACTOR REACTOR VESSEL WSE            SAFEEND SAFE END 44ttf4444444f4444444444444tt4fff444444f4444444444444444ft4444444f444f444444
 
444444444444444444444444444404444444444444444      444444444444444 NUTECH                                                              PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                  PAGE          48 REVISION  RRS1 DATE  85/12/04 444444444444444444044444444444444444444444444444444444444444444 REFERENCE KEY    BWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WSTHW          STHW SHELL TO HEAD WELD WTSTVW        TSTVW TUBE SHEET TO VESSEL WELD 4444t44444444444444f444t444444444t44ft444444444f444'4444t44f44444044f4440444
 
CATEGORY REFERENCE KEY: Example - P01-01B-B MHERE: P01-01 is the EXAM REQUIREMENT for PSI PSI is considered An Interval for computer purposes.
P01 =  PSI program 01
                      -01 =  Xnterval  01 B-B  -"  Section XX category NOTE:  If a category  has the same designation for program A and B the following method is employed:
B-DA  = CATEGORY  B-D Program  A B-DB  = CATEGORY B-D Program  B AUGMENTED    programs are assigned category and item numbers to reflect, as close as possible the source of the exam requirement.
EXAMPLE:  P04"01FSAR P04 = PSI program number 04
                                        -01  = Xnte val 01 FSAR  = Source of examination requirement
 
                                                                              'I
+~444444444444444444444444444444444444404444t4440444444444        44444444444444t NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT    1 PLANNING REFERENCE CLUSTER LISTING              444444444444444444
'4 DATA ELEMENT : CATEGORY                PAGE            18 REVISION  RRS1 DATE  85/12/05 444444444444444444444444044444444444444444444444444444444444444444444444444 REFERENCE KEY                              DESCRIPTION 802"01RG1. 14  REACTOR COOLANT PUMP FLYWHEEL INTEGRITY EXAMINATION 804-01FSAR      FINAL SAFETY ANALYSIS REPORT  SECTION    6.6.8, PARAGRAPHS 8 AND E.
805-0'IFSAR      FINAL SAFETY ANALYSIS REPORT  SECTION    6.6.8, PARAGRAPHS C AND E.
806-01FSAR      FINAL SAFETY ANALYSIS REPORT  SECTION    6.6.8, PARAGRAPHS D AND E.
P01-018-A      PRESSURE  RETAINING WELDS IN REACTOR VESSEL Po 1-018-8      PRESSURE  RETAINING WELDS IN VESSELS OTHER THAN THE RV I
PRESSURE RETAINING WELDS  IN VESSELS  OTHER THAN REACTOR VESSELS P01-018-DA      FULL PENETRATION WELDS OF NOZZLES IN VESSELS  PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM A P01-018-DB      FULL PENETRATION WELDS OF NOZZLES IN VESSELS  PROGRAM 8 FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM 8 P01-018-E        EXAMINATION CATEGORY 8-E IS NOT SUBJECT TO PSI 444444444444444f44f4444444444444f444t4f444t4444444444444f444$    ffffff44444f
 
4444444444444f44444ff44444444t44f4t044f44444444 NUTECH                                                                PRISIM CAROLINA POWER 1l LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING                                        4 REFERENCE CLUSTER LISTING DATA ELEMENT : CATEGORY                  PAGE        .19 REVISION  RRSl DATE  85/12/05 4444444444444444444444444444444044444444444444444444444    44444444444044044444 REFERENCE KEY                              DESCRIPTION P01-018-F        PRESSURE  RETAINING DISSIMILAR METAL WELDS P01-018-G-1      PRESSURE  RETAINING BOLTS GREATER THAN  TWO  INCHES IN DIAMETER P01-018-G-2      PRESSURE  RETAINING BOLTS,  TWO  INCHES AND LESS IN DIAMETER P01-018-H        INTEGRAL ATTACHMENTS FOR VESSELS P01-018- J      PRESSURE  RETAINING WELDS IN PIPING P01-018-K-1      INTEGRAL ATTACHMENTS    FOR PIPING, PUMPS,  AND VALVES P01-018-L-1      PRESSURE  RETAINING WELDS IN PUMP CASINGS P01-018-L-2      PUMP CASINGS P01-018-M-1      PRESSURE  RETAINING WELDS IN VALVE BODIES P01-018-M-2      VALVE BODIES P01-018-N-1      INTERIOR OF REACTOR VESSEL P01-018-N-2      RV INTEGRALLY WELDED CORE SUPPORTS AND ATTACHMENTS (BWR)
I INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS (BWR)
P01-018-N-3      REMOVABLE CORE SUPPORT  STRUCTURES  (PWR)
P01-018-0        PRESSURE  RETAINING WELDS IN CONTROL ROD HOUSING PRESSURE  RETAINING WELDS IN PERIHERAL CONTROL    ROD  DRIVE HOUSING 444'4444444444044t44444f444444f44440444444f444f444444444400444
 
4~444444444444444444f444444444444444404444444  4444444444444      44444444444444'4 NUTECH                                                                PRISIM i CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : CATEGORY                  PAGE        ,20 REVISION  RRS1 DATE  85/12/05 444444f444444ttff4444tt44f44ftkf4444444fftt444444444t4'444t4 REFERENCE KEY                            DESCRIPTION P01-01B-P      +++EXAMINATION CATEGORY 8-P IS NOT SUBJECT TO PSI+++
P01-01B-Q      +++FOR STEAM GENERATOR TUBING, SEE PRISIM-SST+++
P01-01C-A      PRESSURE  RETAINING WELDS IN PRESSURE VESSELS P01-01C-B      PRESSURE  RETAINING NOZZLE WELDS IN VESSELS P01-01C-C      INTEGRAL ATTACHMENTS FOR VESSELS,    PIPING, PUMPS,    AND VALVES P01-01C-D      PRESSURE  RETAINING BOLTS GREATER THAN  TWO  INCHES IN DIAMETER P01-01C-F      PRESSURE  RETAINING WELDS IN PIPING P01-01C-G      PRESSURE  RETAINING WELDS IN PUMPS AND VALVES P01-01C-H      +++EXAMINATION CATEGORY C-H IS NOT SUBJECT TO PSI+++
P01-01D-A      SYSTEMS  IN SUPPORT OF REACTOR SHUTDOWN FUNCTION P01-01D-B      ECCS,  CHR, ACU, AND RHR SUPPORT  SYSTEMS SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEAN-UP, AND REACTOR RESIDUAL HEAT REMOVAL P01-01D-C      SYSTEMS  IN SUPPORT OF RHR FROM SPENT FUEL STORAGE POOL SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL 44444444444r4444448t444t4844444444444t44ttkf44444444444444444444
 
e
  +444444444444004444444f444444444444044ft44444444ff44444 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : CATEGORY                PAGE          21 REVISION  RRS1 DATE  85/12/05 44444444444444t444444t4444444t444444444444444444444444444    404444444444444444 REFERENCE KEY                            DESCRIPTION P01-01E-A      PRESSURE  RETAINING WELDS IN VESSELS P01-01E-A-1    NONPRESSURE-RETAINING WELDS P01-01E-B      PRESSURE  RETAINING WELDS IN CONTAINMENT PENETRATIONS P01-01E-C      PRESSURE  RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES P01-01E-D      SEALS AND GASKETS P01-01E-E      INTEGRAL ATTACHMENTS P01-01E-F      PRESSURE  RETAINING DISSIMILAR METAL WELDS P01-01E-G      PRESSURE  RETAINING BOLTING P01-01E-P      ALL PRESSURE RETAINING COMPONENTS P01-01F-A      PLATE AND SHELL TYPE SUPPORTS P01-01F-B      LINEAR TYPE SUPPORTS P01-01F-C      COMPONENT STANDARD SUPPORTS P02-01RG1.14    REACTOR COOLANT PUMP FLYWHEEL INTEGRITY EXAMINATION P03-01SER      SAFETY EVALUATION REPORT,  SAFETY REVIEW QUESTION P04-01FSAR      FINAL SAFETY ANALYSIS REPORT  SECTION  6.6.8, PARAGRAPHS B AND E.
4444tkt44f4444444ff44444404444444444444f44444444t4444044f44444
 
+ 4+4+4+4444444ff4444444444t444f444f4444444t444044'44t44444 NUTECH                                                                  PR I SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT        1 PLANNING REFERENCE CLUSTER LISTING                  444444444444444444 DATA ELEMENT : CATEGORY                    PAGE          22 REVISION    RRS1 DATE  85/12/05 444444444444844444444444'44444444r44444444 REFERENCE KEY                              DESCRIPTION P05-01FSAR    FINAL SAFETY ANALYSIS REPORT  SECTION        6.6.8, PARAGRAPHS C AND E.
P06-01FSAR    FINAL SAFETY ANALYSIS REPORT  SECTION        6.6.8, PARAGRAPHS D AND E.
V01-01C-C      INTEGRAL ATTACHMENTS FOR VESSELS,      PIPING,  PUMPS>  AND VALVES 81W-018-A      PRESSURE  RETAINING WELDS IN REACTOR VESSEL 81W-018-8      PRESSURE  RETAINING WELDS IN VESSELS OTHER THAN THE RV PRESSURE RETAINING WELDS      IN VESSELS OTHER THAN REACTOR VESSELS 81W-018-DA    FULL PENETRATION WELDS OF NOZZLES IN VESSELS  PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM A 81W-018-DB    FULL PENETRATION WELDS OF NOZZLES IN VESSELS  PROGRAM 8 I
FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM 8 81W-018-E      PRESSURE    RETAINING PARTIAL PENETRATION WELDS IN VESSELS 81W-018-F      PRESSURE    RETAINING DISSIMILAR METAL WELDS 81W-018-G-1    PRESSURE  RETAINING BOLTS GREATER THAN    TWO  INCHES IN DIAMETER 444444'4444tf44440444t44440444'44444440t444444444444444044
 
ee444444444f44444444444f4444f4444f444404444444444444444        444f4444f444444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 4                                PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : CATEGORY                  PAGE          23 REVISION  RRS1 DATE  85/12/05 44444444444f4444444444444444444044f44444444tff444444444f44444 REFERENCE KEY                            DESCRIPTION 81W-018-G-2    PRESSURE RETAINING BOLTS,  TWO  INCHES AND LESS IN DIAMETER 81W-018-H      INTEGRAL ATTACHMENTS FOR VESSELS 81W-01 8- J    PRESSURE RETAINING WELDS IN PIPING 81W-018-K-1    INTEGRAL ATTACHMENTS    FOR PIPING,  PUMPS>  AND VALVES 81W-018-L-1    PRESSURE RETAINING WELDS IN PUMP CASINGS 81W-018-L-2    PUMP CASINGS 81W-018-M-1    PRESSURE RETAINING WELDS IN VALVE BODIES 81W-018-M-2    VALVE BODIES 81W-018-N-1    INTERIOR OF REACTOR VESSEL 81W-018-N-2    RV INTEGRALLY WELDED CORE SUPPORTS    AND ATTACHMENTS (BWR)
INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS (BWR) 81W-018-N-3    REMOVABLE CORE SUPPORT  STRUCTURES  (PWR) 81W 018 0      PRESSURE  RETAINING WELDS IN CONTROL  ROD  HOUSING, PRESSURE  RETAINING WELDS IN PERIHERAL CONTROL ROD DRIVE HOUSING
 
444444444444444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT      UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : CATEGORY                  PAGE      " -
                                                                                -24 REVISION  RRS  1 DATE  85/12/05 4444444444444444444404444440444444444444444444444444444444444 REFERENCE KEY                              DESCRIPTION 81W-018-P      ALL PRESSURE RETAINING COMPONENTS 81W-01B-Q      +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T+++
81W-01C-A      PRESSURE  RETAINING WELDS IN PRESSURE VESSELS 81W-01C-B      PRESSURE  RETAINING NOZZLE WELDS IN VESSELS 81W-01C-C      INTEGRAL ATTACHMENTS FOR VESSELS,    PIPING, PUMPS,    AND VALVES 81W-01C-D      PRESSURE  RETAINING BOLTS GREATER THAN  TWO  INCHES IN DIAMETER 81W-01C-F      PRESSURE  RETAINING WELDS IN PIPING 81W-01C-G      PRESSURE  RETAINING WELDS IN PUMPS AND VALVES 81W-01C-H      ALL PRESSURE RETAINING COMPONENTS 81W-010-A      SYSTEMS  IN SUPPORT  OF REACTOR SHUTDOWN FUNCTION 81W-010-B      ECCS,  CHR, ACU  ~ AND RHR SUPPORT  SYSTEMS SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEAN-UP, AND REACTOR RESIDUAL HEAT REMOVAL 81W-01D" C      SYSTEMS  IN SUPPORT  OF RHR FROM SPENT FUEL STORAGE POOL SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL 444t444444444444444tkt444f444444444444444444444f444444t4444444444444f
 
+  44444444t444444'440440f44444tt4f4444444f4444f4444                                                                  4444404f44f'4444 NUTECH                                                                                                                      PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT                                      UNIT      1 PLANNING                                                                            4I REFERENCE CLUSTER LISTING                                                44044404444444t444 DATA ELEMENT : CATEGORY                                                  PAGE                    25 REVI SION          RRS  1 DATE        85/12/05 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 4 4 4 O4 4 4 4 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 REFERENCE KEY                                                                DESCRIPTION 81W-01E-A                    PRESSURE          RETAINING WELDS IN VESSELS 81W-01E-A-1                  NONPRESSURE-RETAINING WELDS 81W-01E-8                    PRESSURE          RETAINING WELDS IN CONTAINMENT PENETRATIONS 81W-01E-C                    PRESSURE          RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES 81W-01E-0                    SEALS AND GASKETS 81W-01E-E                    INTEGRAL ATTACHMENTS 81W-01E-F                    PRESSURE          RETAINING DISSIMILAR METAL WELDS 81W-01E-G                    PRESSURE          RETAINING BOLTING 81W-0 IE-P                    ALL PRESSURE RETAINING COMPONENTS 81W-01F-A                    PLATE AND SHELL TYPE SUPPORTS 81W-0 F-8  '1 LINEAR TYPE SUPPORTS 81W-01F-C                    COMPONENT STANDARD SUPPORTS 4444444444ff4444f444444f44444444444444f44444444tf444444444444
 
ITEM NO.
REFERENCE KEY: Example    P01"01B1.11 P01"01 is the    EXAM REQUIREMENT  for PSI MHERE:  P01    PSI program 01
                -01    Interval 01 B1.11    is the Section XI    Xtem Number AUGMENTED  programs are assigned    item numbers to reflect the location,    as  close as possible, of the exam  requirement within the category.
Example:  For category P04-01FSAR one Item No. is P04-016.6.8B Mhere:      POC    PSI program 04
                                      -01    Interval  01 6.6.8B    Paragraph number in category "FSAR".
 
+~ 44444444%44f448884fggg44444444444444444444444        44t444444    444f44444444444 NUTECH                                                                  PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT      1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE          87 REVISION  RRS 1 DATE  85/12/05 444444444444444444444488444444+t4444444444444444444444444444444444444 REFERENCE KEY                                DESCRIPTION 802-0  'I          +++    EXAMINATION CATEGORY RG1. 14  +++
802-0180RE        REACTOR COOLANT PUMP FLYWHEEL BORE  UT 802-01FLYWHL      REACTOR COOLANT PUMP FLYWHEEL -SURFACE AND UT 802-01KEYWAY      REACTOR COOLANT PUMP FLYWHEEL KEYWAY  UT 803-01            +++    EXAMINATION CATEGORY OPEN TO FUTUREUSE      +++
804-01            +++    EXAMINATION CATEGORY FSAR      +++
804-016.6.88        AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.88. (INSERVICE) 804-016.6.8E        AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. (INSERVICE) 805-01              +++  EXAMINATION CATEGORY FSAR    +++
805-016.6.8C        AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.8C. (INSERVICE) 805-016.6.8E        AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. (INSERVICE) 806" 0'1            +++  EXAMINATION CATEGORY FSAR    +++
806-016. 6. BD      AUGMENTED  PIPING WELD SURFACE EXAMINATION PER FSAR PARAGRAPH  6.6.8D. (INSERVICE) 4444844444444444404440tkt4444444444tttkt444444448444444404444444444r444
 
44444f444444444444044444444444444f4t44444444444fStd      44444ftt4444444 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING                440444448444444444 DATA ELEMENT : ITEMNO                    PAGE        . 88 REVISION  RRS 1 DATE  85/12/05 44444t444444044f4tt444444444440t44444t4444t44444444444 REFERENCE KEY                              DESCRIPTION 806-016.6.8E    AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. (INSERVICE)
Po 1-0181        +++EXAMINATION CATEGORY 8-A+++
P01-0'I 81 .      +++REACTOR VESSEL+++
P01-0181. 10    +++SHELL WELDS+++
P01-0181. 11  RV CIRCUMFERENTIAL SHELL WELDS P01-0181. 12  RV LONGITUDINAL SHELL WELDS P01-0181. 20      +++HEAD WELDS+++
P01-0181. 21  RV CIRCUMFERENTIAL HEAD WELDS Po 1-0181. 22    RV MERIDIONAL HEAD WELDS Po 1-0181. 228    RV MERIDIONAL BOTTOM HEAD WELDS RV MERIDIONAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL.
Po 1 -0181. 30    RV SHELL-TO-FLANGE WELD P01-0181.40      RV HEAD-TO-FLANGE WELD P01-0181.50      +++REPAIR WELDS+++
44444444444f44444444444444444444444f44444444444444444t44444444$        4444444f4444
 
44444t44444444444444f444444t4444444t44444444444t44444444                        f4444444444444 NUTECH                                                                                  PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT              1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                                PAGE                ,;. 89 REVISION            RRS1 4                                                                              DATE        85/12/05 4444444444444444444 444444t44ftt44444444444444444444444t444444444444t444444t REFERENCE KEY                              DESCRIPTION Po 1 -0181. 51    RV  BELTLINE REGION REPAIR WELDS P01-0181.99      +++ITEM NUMBERS 82.XX THROUGH 89.XX APPEAR AFTER 816.20+++
Po 1-01810        +++EXAMINATION CATEGORY 8-K-1+++
P01-01810. 1  +++PIPING+++
P01-01810.10      PIPING INTEGRALLY WELDED ATTACHMENTS Po 1-01810. 2  +++PUMPS+++
P01-01810.20      PUMP INTEGRALLY WELDED ATTACHMENTS P01-01810. 3  +++VALVES+++
P01-01810. 30    VALVE INTEGRALLY WELDED ATTACHMENTS P01-01812.        +++PUMPS+++
P01-01812. 1  +++EXAMINATION CATEGORY  8-L-1+++
P01-01812. 10  PUMP CASING WELDS P01-01812. 2  +++EXAMINATION CATEGORY  8-L-2+++
P01-01812. 20      PUMP CASING Po  1-01812. 3    +++EXAMINATION CATEGORY 8-M-1+++
4444444444 t4 4 4 f 4 4 4 4 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 f 4 4 0 4 4 4 4
 
s+ s s s s s s s s s s s          ssssssssssssssssssssssssssssssssssssss            sssssssssssssss s    NUTECH                                                                                PRIS IM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT          1                          s PLANNING REFERENCE CLUSTER LISTING                      ssssssssssssssssss DATA ELEMENT : ITEMNO                          PAGE        - 90 REVISION    RRS    1 DATE  85/12/05 ssssssssssssssssssssssssssssssssssssssssssssfsssssssssssssssss REFERENCE KEY                                            DESCRIPTION P01-01812.3A              +++VALVES+++
P01-01812.30              VALVES, NOMINAL PIPE SIZE        < 4  IN. VALVE BODY WELDS Pol  "01812.40            VALVES, NOMINAL PIPE SIZE >= 4        IN. VALVE BODY WELDS P01-01812. 5              +++EXAMINATION CATEGORY 8-M-2+++
P01-01812.50              VALVE BODY, EXCEEDING 4        IN. NOMINAL PIPE SIZE P01-01813.                +++EXAMINATION CATEGORY 8-N-1+++
Po  1-01813.        1      +++REACTOR VESSEL+++
Po  1-01813.        10      RV VESSEL INTERIOR P01-01813. 2                +++EXAMINATION CATEGORY 8-N-2+++
P01-01813. 2.              +++REACTOR VESSEL (BWR)+++
PO  1-01813.20              RV INTERIOR ATTACHMENTS WITHIN        BELTLINE REGION (BWR)
P01-01813.21                RV INTERIOR ATTACHMENTS BEYOND        BELTLINE REGION (BWR)
P01-01813.22                RV CORE SUPPORT    STRUCTURE (BWR)
P01-01813. 3              +++EXAMINATION CATEGORY      8" N-3+++
P01-01813. 3.              +++REACTOR VESSEL (PWR)+++
ssssssssssssssssssssssssssssssss sssssssssssssssssssssssssssssssssssssss                          st  sss
 
e 4~+4440444444444884888f044t0444444444f44444444444444444444        444444tkt444f4 NUTECH                                                              PRISIM CAROLINA POWER 6 LIGHT COMPANY 4              SHEARON HARRIS NUCLEAR POWER PLANT - UNIT  1 4                                PLANNING REFERENCE CLUSTER LISTING              ee4444444444444404 DATA ELEMENT : ITEMNO                  PAGE          91 REVISION  RRS1 DATE  85/12/05 44t444444404t4444444444t444444444444444444444444444404444444t444404 REFERENCE KEY                            DESCRIPTION P01-01813.30    INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (PWR)
P01-01813.31    INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (PWR)
P01-01813.32    RV CORE SUPPORT  STRUCTURE (PWR)
F01-01814.      +++EXAMINATION CATEGORY 8-0+++
P01-01814. 1  +++REACTOR VESSEL+++
P01-01814.10    RV WELDS  IN PERIPHERAL CRD HOUSING P01-01815.      +++EXAMINATION CATEGORY 8-P IS NOT SUBJECT TO PSI+++
P01-01816.      +++EXAMINATION CATEGORY B-Q+++
P01-01816. 1  +++STEAM GENERATORS+++
P01-01816. 10  +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN STRAIGHT TUBE DESIGN+++
P01-01816. 20    +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN U-TUBE DESIGN+++
P01-0182.        +++EXAMINATION CATEGORY 8-8+++
P01-0182. 1    +++PRESSURIZER+++
P01-0182. 10    +++SHELL-TO-HEAD WELDS+++
4t4444444444444444f444444444444444444444444444444444f4444tt44444444444f4444
 
ttttt        tttttttttttttt ttttttttttttttt NUTECH                                                              PRISIM CAROLINA POWER 1h LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT  1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                  PAGE REVISION
                                                                          '2 RRS1 t DATE 85/12/05 t tttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE    KEY                            DESCRIPTION P01-0182. 11    PZR CIRCUMFERENTIAL SHELL-TO-HEAD WELDS P01-0182. 12    PZR LONGITUDINAL SHELL-TO-HEAD WELOS P01-0182.20      +++HEAD WELOS+++
P01-0182. 21    PZR CIRCUMFERENTIAL HEAD WELDS P01-0182. 22      PZR MERIDIONAL HEAD WELDS PO 1-0182. 3      +++STEAM GENERATORS (PRIMARY SIDE)+++
P01-0182. 30      +++HEAD WELOS+++
P01-0182. 31    SG PRIMARY  SIDE CIRCUMFERENTIAL HEAD WELDS P01"0182.32      SG PRIMARY  SIDE MERIDIONAL HEAD WELDS P01-0182.40      SG  PRIMARY SIDE TUBESHEET-TO-HEAD WELDS P01-0182. 5      +++HEAT EXCHANGERS (PRIMARY SIDE)+++
P01-0182. 50      +++SHELL(OR HEAD) WELDS+++
P01-0182.51      HX PRIMARY SIDE CIRCUMFERENTIAL SHELL (OR HEAD) WELDS P01-0182. 52      HX PRIMARY    MERIDIONAL SHELL (OR HEAD) WELD P01-0182.53      HX PRIMARY LONGITUDINAL SHELL (OR HEAD) WELD
 
~+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                              PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING                tttttttttttttttttt t
DATA ELEMENT : ITEMNO                    PAGE        93 REVISION  RRS 1 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt DATE REFERENCE KEY                              DESCRIPTION P01-0182. 6    +++ SHELL (PRIMARY SIDE) +++
P01-0182. 60      TUBESHEET-TO-SHELL (OR HEAD) WELDS P01-0182. 61    TUBESHEET-TO-SHELL WELDS Po 1-0183        +++EXAMINATION CATEGORY 8-DA+++
P01-0183.        +++PROGRAM A REQUIREMENTS+++
1ST INTERVAL    3 YEARS 2ND INTERVAL      7 YEARS 3RD INTERVAL    13 YEARS 4TH INTERVAL    17 YEARS P01-0183. 1  +++REACTOR VESSEL+++
P01-0183. 10  RV NOZZLE-TO-VESSEL WELOS  PROGRAM A Pol-O'183. 20    RV NOZZLE  INSIDE RADIUS SECTION  - PROGRAM A Po 1 -0183. 3  +++PRESSURIZER+++
Pol-0183. 30      PRZ NOZZLE-TO-VESSEL WELDS  PROGRAM A P01-0183. 40  PRZ NOZZLE  INSIDE RADIUS SECTION    PROGRAM A Po 1-0183. 5      +++STEAM GENERATORS (PRIMARY SIDE)+++
P01-0183. 50  SG PRIMARY NOZZLE-TO-VESSEL WELDS  -  PROGRAM A tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt
 
444f444444f44444tf44444f44444404444444t4444f444      44444444444t444 NUTECH                                                              PRI SIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING              444444444448444444 DATA ELEMENT : ITEMNO                ~ PAGE          94 REVISION    RRS1 DATE 85/12/05 444444t4440440'04t44444ttttftf404t4tt4tt444444t40f44 REFERENCE KEY                                DESCRIPTION P01-0183. 60    SG PRIMARY NOZZLE    INSIDE RADIUS SECTION  PROGRAM A P01-0183. 7    +++HEAT EXCHANGERS (PRIMARY SIDE)+++
Pol  "0183. 70    HX PRIMARY NOZZLE-TO-VESSEL WELDS  PROGRAM A P01-0183. 80    HX PRIMARY NOZZLE    INSIDE RADIUS SECTION  PROGRAM  A P01-0183. 9        +++EXAMINATION CATEGORY 8-DB+++
Po  1 -0183. 9.    +++PROGRAM 8 REQUIREMENTS+++
1ST INTERVAL    '10 YEARS 2ND INTERVAL    10 YEARS 3RD INTERVAL    10 YEARS 4TH INTERVAL    10 YEARS POl-0183. 9A      +++REACTOR VESSEL+++
1-0183. 98    RV NOZZLE-TO-VESSEL WELDS, EXAM FROM NOZZLE BORE PROGRAM 8 Po IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
P01-0183. 9S        RV NOZZLE-TO-VESSEL WELDS,  EXAM FROM RV SHELL  PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
44t444f4444444444444444f44444444444444444t4f444ft444444444t4444444444444444
 
e
  +444444f44444440f4444444444444444444f444444444f444444f44        444f44f444f4f44 NUTECH                                                                PRISIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REFERENCE CLUSTER LISTING                44t4444444t444f44f DATA ELEMENT : ITEMNO                    PAGE        95 REVISION  RRS1 DATE  85/12/05
                                                                                  ~'444444t4444444444444444t44r44ft44444ttkt44444444444444444t44 REFERENCE KEY                            DESCRIPTION P01-0183. 90  RV NOZZLE-TO-VESSEL WELDS  PROGRAM 8 P01-0183.100    RV NOZZLE  INSIDE RADIUS SECTION  PROGRAM 8 P01-0183. 11  +++PRESSURIZER+++
P01-0183.110    PZR NOZZLE-TO-VESSEL WELDS  -  PROGRAM 8 P01-0183.120    PZR NOZZLE  INSIDE RADIUS SECTION  PROGRAM 8 P01-0183. 13    +++STEAM GENERATORS (PRIMARY SIDE)+++
P01-0183.130    SG PRIMARY  NOZZLE-TO-VESSEL WELDS  - PROGRAM 8 Po 1-0183. 140  SG PRIMARY NOZZLE  INSIDE RADIUS SECTION      PROGRAM 8 Po 1-0183. 15    +++HEAT EXCHANGERS (PRIMARY SIDE)+++
P01-0183.150    HX PRIMARY NOZZLE-TO-VESSEL WELDS    PROGRAM 8 P01-0183.160    HX PRIMARY NOZZLE  INSIDE RADIUS SECTION  -  PROGRAM 8 Po 1-0184        +++EXAMINATION CATEGORY 8-E IS NOT SUBJECT TO PSI+++
P01-0184. 11    VESSEL NOZZLE PARTIAL PENETRATION WELDS P01-0184. 12    CONTROL ROD DPIVE NOZZLE PARTIAL PENETRATION WELDS P01-0184. 13    INSTRUMENTATIMN NOZZLE PARTIAL PENETRATION WELDS 44444444444444t444444444444f4444t4f4444f44444444444444t
 
4++44t444444444444444444444444444444444444f44444444440444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY t              SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 4                        DATA ELEMENT : ITEMNO                    PAGE 96 REVISION  RRS 1 DATE  85/12/05 44444444444444444f44t44444444f444444444r4444444t44444t44444444444444t4444444 REFERENCE KEY                              DESCRIPTION P01-0184.20      PRZ HEATER PELETRATION WELDS P01-0185.        +++EXAMINATION CATEGORY 8-F+++
P01-0185. 1    +++REACTOR VESSEL+++
Pol-0185. 10  RV NOZZLE-TO-SAFE END BUTT WELDS, NPS >= 4 INCHES Pol-0185. 20    RV NOZZLE-TO-SAFE END BUTT WELDS, NPS < 4 INCHES P01-0185. 30    RV NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 4    +++PRESSURIZER+++
P01-0185. 40    PZR NOMINAL PIPE  SIZE >= 4 IN. NOZZLE-TO-SAFE    END BUTT WELDS POI-0185. 50    PZR NOMINAL PIPE  SIZE < 4 IN. NOZZLE-TO-SAFE    END BUTT WELDS Pol-0185. 60    PZR NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 7    +++STEAM GENERATOR+++
P01-0185. 70  SG NOMINAL  PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELDS P01-0185. 80  SG NOMINAL  PIPE SIZE < 4  IN. NOZZLE-TO-SAFE  END BUTT WELDS Pol-0185. 90    SG  NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 10    +++HEAT EXCHANGERS+++
eoeeeeeeeeeebeeeee44+eekebe4440444444t444444444444440444444t444444444444444
 
~+ttttttttttttttttttttttttttttttttttttttttttttttttttttttti ttttttttttttttt NUTECH                                                              PRISIM CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING                tttttttttttttttttt DATA ELEMENT : ITEMNO                    PAGE      ,  97 REVISION  RRS1 t DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                            DESCRIPTION r
P01-0185. 100  HX NOMINAL  PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELOS P01-0185.110    HX NOMINAL  PIPE SIZE  < 4 IN. NOZZLE-TO-SAFE    END BUTT WELOS P01-0185.120    HX NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 13    +++PIPING+++
P01-0185.130    NOMINAL PIPE SIZE >= 4  IN. DISSIMILAR METAL PIPING    BUTT WELD P01-0185. 140  NOMINAL PIPE SIZE < 4  IN. DISSIMILAR  METAL PIPING BUTT WELD P01-0185. 150  DISSIMILAR METAL PIPING SOCKET WELOS P01-0186.      +++EXAMINATION CATEGORY 8-G-1+++
P01-0186. 1  +++REACTOR VESSEL+++
P01-0186. 10  RV CLOSURE HEAD NUTS  (> 2")
POI-0186. 20    RV CLOSURE STUDS,  IN PLACE (> 2")
P01-0186. 30  RV CLOSURE STUDS,  WHEN REMOVED  (> 2")
P01"0186. 40    RV THREADS  IN FLANGE (> 2")
P01-0186. 50  RV CLOSURE WASHERS,  BUSHINGS (>  2")
P01-0186. 6    +++PRESSURIZER+++
 
44t,f44tf44f44444fft444444444444444444444444444444          444444444ff444t NUTECH                                                                    PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT          1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                      PAGE          98 ~
REVISION    RRS1 DATE    85/12/05 8444444444444444844444444f4444444444044444444444444444444444444444444444044 REFERENCE KEY                                  DESCRIPTION P01-0186. 60    PZR BOLTS AND STUDS    (> 2")
P01-0 186. 70    PZR FLANGE SURFACE WHEN CONNECTION DISASSEMBLED        (>  2")
P01-0186. 80    PZR NUTS,  BUSHINGS'ND      WASHERS  (> 2")
P01-0186. 9      +++STEAM GENERATORS+++
P01-0186. 90    SG BOLTS AND STUDS    (> 2")
P01-0186.100      SG FLANGE SURFACE WHEN CONNECTION DISASSEMBLED        (> 2")
P01-0186. 110    SG NUTS, BUSHINGS, AND WASHERS (>      2")
P01-0186. 12    +++HEAT EXCHANGERS++~
P01-0186. 120    HX BOLTS AND STUDS    (> 2")
P01-0186.130      HX FLANGE SURFACE WHEN CONNECTION DISASSEMBLED        (> 2")
P01-0186.140      HX NUTS, BUSHINGS, AND WASHERS      (> 2")
P01-0186. 15    +++PIPING+++
P01-0186.150      PIPING BOLTS AND STUDS (>      2")
P01-0186. 160    PIPING FLANGE SURFACE      WHEN CONNECTION DISASSEMBLED    (> 2")
P01-0186. 170    PIPING NUTS, BUSHINGS    ~  AND WASHERS  (>  2")
444444'4f044ff4444f444444444f44444444444444444444
 
444444444444444444          444444444444444444444f44444      +44440444444f44 NUTECH                                                                  PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REFERENCE CLUSTER LISTING                444444440444444444 DATA ELEMENT : ITEMNO                    PAGE          . 99 REVISION    RRS1 DATE  85/12/05 44444444484444444444444444444444444444444444444t&4444444444444444444'4444444 REFERENCE KEY                              DESCRIPTION P01-0186. 18    +++PUMPS+++
P01-0186. 180    PUMP BOLTS AND STUDS  (> 2")
P01-0186. 190    PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED        (>  2")
P01-0186.200    PUMP NUTS,  BUSHINGS, AND WASHERS (>  2")
P01-0186. 21    +++VALVES+++
P01-0186.210    VALVE BOLTS AND STUDS (>    2")
P01-0186.220    VALVE FLANGE SURFACE WHEN CONNECTION DISIASSEMBLED (>        2")
P01-0186.230    VALVE NUTS, BUSHINGS, AND WASHERS (>    2")
P01-0187.        +++EXAMINATION CATEGORY 8-G-2+++
P01-0187. 1    +++REACTOR VESSEL+++
P01-0187. 10    REACTOR VESSEL BOLTS, STUDS,    AND NUTS  (<= 2")
P01-0187. 2      +++PRESSURIZER+++
P01-0187. 20      PRESSURIZER BOLTS, STUDS, AND NUTS (<=    2")
PO\-0187.3        +++STEAM GENERATORS+++
P01-0187.30      STEAM GENERATOR BOLTS, STUDS, AND NUTS (<= 2")
444444f4444444f4444444t44f44444444tkf444444ft44444444444444444444f4444
 
tttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                                                                                    PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT                                        1 PLANNING REFERENCE CLUSTER LISTING                                                ttttttttttttttttttt DATA ELEMENT : ITEMNO                                                    PAGE                  ,100 REVISION            RRSl DATE        85/12/05 t t t t t t tt t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t REFERENCE KEY                                                              DESCRIPTION Pol-O'187.4                  +++HEAT EXCHANGERS+++
P01-0187. 40                HEAT EXCHANGER BOLTS, STUDS, AND NUTS (<=                                        2")
Po  1-0187. 5              +++PIPING+++
P01-0187. 50                PIPING BOLTS, STUDS, AND NUTS (<=                                2")
Po  1-0187. 6              +++PUMPS+++
Po  1-0187. 60              PUMP BOLTS,            STUDS, AND NUTS (<=                    2")
P01-0187.        7          +++VAIVFS+++
P01-0187. 70                VALVE BOLTS> STUDS, AND NUTS (<=                                2")
Po  1-0187. 8              +++CRD HOUSING+++
P01-0187. 80                CRD HOUSING BOLTS,                  STUDS, AND NUTS (<=                    2")
P01-0188.                    +++EXAMINATION CATEGORY 8-H+++
P01-0188.        1          +++REACTOR VESSEL+++
P01-0188.        10        RV INTEGRALLY WELDED ATTACHMENTS P01-0188. 2                  +++PRESSURIZER+++
P01-0188. 20                PZR INTEGRALLY WELDED ATTACHMENTS t t t tt t t t tt tt t t t t 4 t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t
 
0++44f4444444f444f44444444444444444444444444t44444f44t44t4        +44044444444f44 NUTECH                                                                PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT    1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                    PAGE,,lRRS101 REVISION DATE  85/12/05 44444444444444444444444444444444444444444    444444444004444444'4444444444440444 REFERENCE KEY                            DESCRIPTION P01-0188.3      +++STEAM GENERATORS+++
P01-0188.30      SG  INTEGRALLY WELDED ATTACHMENTS PO 1-0188.4      +++HEAT EXCHANGERS+++
P01-0188.40      HX INTEGRALLY WELDED ATTACHMENTS P01-0189.        +++EXAMINATION CATEGORY  8- J+++
P01-0189. 1    +++PIPING+++
F0 1-0189. 10    +++NOMINAL PIPE SIZE >= 4 IN.+++
P01-0189.11      CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4        IN.
P01-0189.12      LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4        IN.
P01-0189.20      +++PIPING NOMINAL PIPE SIZE < 4 IN.+++
P01-0189.21      CIRCUMFERENTIAL WELOS IN PIPING, NOMINAL PIPE SIZE < 4        IN.
P01-0189.22      LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4      IN.
P01-0189.30      +++BRANCH PIPE CONNECTION WELDS+++
P01-0189.31      BRANCH  PIPE CONNECTION WELDS, NOMINAL PIPE SIZE >= 4 IN.
P01-0189.32      BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE < 4 IN.
4444444444f4444440444fft4444444444f444444ff44444444444444444440ff44
 
a~tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT  1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                PAGE        102 REVISION  RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                              DESCRIPTION P01-0189. 40      PIPE SOCKET WELDS P01-0189. 99      +++ITEM NUMBERS 810.XX THROUGH 816.XX APPEAR AFTER 81.51+++
P01-01C1  .      +++EXAMINATION CATEGORY C-A+++
P01-01C1. 1    +++PRESSURE VESSELS+++
P01-01C1. 10      PRESSURE  VESSEL SHELL CIRCUMFERENTIAL WELDS P01-01C'I . 20    PRESSURE  VESSEL HEAD CIRCUMFERENTIAL WELDS P01-01C1. 30      PRESSURE  VESSEL TUBESHEET-TO-SHELL WELD P01-01C2.        +++EXAMINATION CATEGORY C-8+++
P01-01C2. 1    +++PRESSURE  VESSELS+++
P01-01C2. 10      +++NOZZLES IN VESSELS  <=1/2 IN. NOMINAL THICKNESS+++
P01-01C2.  'I 1  NOZZLES-TO-SHELL(OR HEAD) WELD P01-01C2.20      +++NOZZLES WITHOUT REINFORCING PlATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++
P01-01C2. 21      NOZZLE-TO-SHELL(OR HEAD) WELD P01-01C2. 22      NOZZLE INSIDE RADIUS SECTION IN VESSELS P01-01C2. 30      +++NOZZLES WITH REINFORCING PLATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++
 
44444444404440444444444440      444444444444444 NUTECH                                                                PR I SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING                                            4 REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE          'I 03 REVISION    RRS1 DATE  85/12/05 444444444444444444444448444444444444444444444444444444444444444444444440444 REFERENCE KEY                              DESCRIPTION P01-01C2. 3'I  REINFORCING PLATE WELDS TO NOZZLE AND VESSEL P01-01C2. 31X  +++NOZZLE-TO-SHELL (OR HEAD) WELDS+++
P01-01C2. 32    INSIDE  OF  VESSEL, NOZZLE-TO-SHELL (OR HEAD) WELD INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM. CAT. C-F P01-01C3.      +++EXAMINATION CATEGORY C-C+++
P01-01C3. 1    +++PRESSURE VESSELS+++
P01-01C3. 10    PRESSURE  VESSEL INTEGRALLY WELDED ATTACHMENTS P01-01C3. 2    +++PIPING+++
P01-01C3. 20    PIPING INTEGRALLY WELDED ATTACHMENTS P01-01C3. 3    +++PUMPS+++
P01-01C3. 30    PUMP  INTEGRALLY WELDED ATTACHMENTS P01-0 IC3.4    +++VALVES+++
P01-01C3. 40    VALVE INTEGRALLY WELDED ATTACHMENTS P01-0 IC4.      +++EXAMINATION CATEGORY C-D+++
P01-01C4. 1    +++PRESSURE VESSELS+++
444444f4444444f44444444ft44444444444444444t444444444444444
 
44444444444444f4444444444 4    NUTECH                                                                PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                    PAGE      '.,1 04 REVISION  RRS  1 DATE  85/12/05 44444444444444444444444444444444444444444444444444444444444444444444444444'0 REFERENCE KEY                                DESCRIPTION P01-01C4. 10      PRESSURE  VESSEL BOLTS AND STUDS (>      2")
P01-01C4. 2      +++PIPING+++
Po 1-01C4. 20      PIPING BOLTS  AND STUDS  (>  2")
P01-01C4. 3      +++PUMPS+++
Po 1 -01C4. 30    PUMP BOLTS AND STUDS  (> 2")
P01-01C4. 4        +++VALVES+++
Po 1-01C4. 40      VALVE BOLTS AND STUDS (>    2")
P01-01C5.          +++EXAMINATION CATEGORY C-F+++
Po 1-01C5. 1      +++PIPING+++
P01-01CS. 10      +++PIPING WELDS <= 1/2 IN. NOMINAL WALL THICKNESS+++
P01-01CS. 11    PIPING CIRCUMFERENTIAL  WELD <=    1/2"  NOMINAL WALL THICKNESS Po 1-01C5. 12      PIPING LONGI TUDINAI WELD <= 1/2" NOMINAL WALL THICKNESS Po 1-01C5. 20      +++PIPING  WELOS >  1/2 IN. NOMINAL WALL THICKNESS+++
P01-01C5. 21      PIPING CIRCUMFERENTIAL WELD > 1/2" NOMINAL WALL THICKNESS PO  1-0 C5. 22 1          PIPING LONGITUDINAL WELD    >  1/2"  NOMINAL WALL THICKNESS
 
4++4444444444444f444444 4444444t44404444444t44f44ftt44f4444                  eft44444f44ff44 NUTECH                                                                            PRISIM CAROLINA POWER It LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT                  1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT ': ITEMNO                              PAGE          105 REVISION    RRS1 DATE  85/12/05 440444444444444444044444  f4 t 4 t 4 4 4 4 4 4 4 '0 4440 t44 0444 04444444t4444444 t44 0 t04 44 44 REFERENCE KEY                                        DESCRIPTION P01-01C5. 30    +++PIPING BRANCH CONNECTIONS+++
P01-01C5. 31    PIPE BRANCH CONNECTION CIRCUMFERENTIAL WELD P01-01C5. 32    PIPE BRANCH CONNECTION LONGITUDINAL WELD P01-01C6.      +++EXAMINATION CATEGORY C-G+++
P01-01C6. 1    +++PUMPS+++
P01-01C6. 10    PUMP CASING WELDS P01-01C6. 2    +++VALVES+++
P01-01C6. 20    VALVE BODY WELDS P01-01C7.      +++EXAMINATION CATEGORY C-H IS NOT SUBJECT TO PSI+++
PO'1-01D1.      +++EXAMINATION CATEGORY D-A+++
P01-0101. 1    +++SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION+++
P01-01D1. 10    +++ITEM NUMBER D1.10 IS EXEMPT                FROM PRESERVICE  INSPECTION++~
P01-01D1. 20    RV SHUTDOWN INTEGRAL ATTACHMENTS                  - SUPPORTS AND RESTRAINTS P01-0101.30    RV SHUTDOWN INTEGRAL ATTACHMENTS  SNUBBERS RV SHUTDOWN INTEGRAL ATTACHMENTS  MECHANICAL AND HYDRAULIC SNUBBERS 4484444444484444444444444444444444444444ff44444444444444444444f444444444444
 
44444444k44444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    - UNIT 1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE, 106 REVISION  RRS1 DATE  85/12/05 4444444444444444f444444444'44t4444f4ff44444f4444f444444f4444t444444'4444 REFERENCE KEY                              DESCRIPTION P01-0101. 40    RV SHUTDOWN INTEGRAL ATTACHMENTS  SPRING TYPE SUPPORTS P01-0101. 50    RV SHUTDOWN INTEGRAL ATTACHMENTS-CONSTANT LOAD TYPE SUPPORTS P01-0101  . 60  RV SHUTDOWN INTEGRAL ATTACHMENTS  SHOCK ABSORBERS P01-0102.      +++EXAMINATION CATEGORY D-8+++
P01-0102. 1  ++~SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL+++
P01-01D2. 10    +++ITEM  NUMBER  D2. 10 IS EXEMPT FROM PRESERVICE    INSPECTION+++
P01-0102. 20    ECCS,  ETC. INTEGRAL ATTACHMENTS  SUPPORTS AND RESTRAINTS P01-0102. 30    ECCSo  ETC. INTEGRAL ATTACHMENTS    - SNUBBERS ECCS, ETC. INTEGRAL ATTACHMENTS  MECHANICAL AND HYDRAULIC SNUBBERS P01-01D2. 40    ECCS,  ETC. INTEGRAL ATTACHMENTS  SPRING TYPE SUPPORTS P01-0102. 50    ECCS,  ETC. INTEGRAL ATTACHMENTS    - CONSTANT LOAD TYPE SUPPORT
'01-01D2. 60  ECCS,  ETC. INTEGRAL ATTACHMENTS  SHOCK ABSORBERS P01-01D3.      +++EXAMINATION CATEGORY D-C+++
P01-01D3. 1  +++SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM THE SPENT FUEL STORAGE POOL+++
4444444444444444444444444444444444444f4444444f4444
 
44444444044440444444400t444444444f4fff44444f444444      4444444f4444t44 NUTECH                                                              PRISIM CAROLINA POWER lt LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING 4                    REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE          107 REVISION  . RRS 1 DATE  85/12/05 444044444444444444444444444444444444444444044r444444444444004444044444444444 REFERENCE KEY                            DESCRIPTION P01-0103.'10    +++ITEM NUMBER D3.10 IS EXEMPT    FROM PRESERVICE    INSPECTION+++
P01-0103.20    RHR FROM SFS  INTEGRAL ATTACHMENTS  SUPPORTS AND RESTRAINTS P01-01D3. 30    RHR FROM SFS  INTEGRAL ATTACHMENTS  SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS  MECHANICAL AND HYDRAULIC SNUBBERS Po 1-01D3. 40  RHR FROM SFS  INTEGRAL ATTACHMENTS  SPRING TYPE SUPPORTS P01-01D3. 50    RHR FROM SFS  INTEGRAL ATTACHMENT-CONSTANT LOAD TYPE SUPPORTS Po 1-01D3. 60  RHR FROM SFS  INTEGRAL ATTACHMENTS  - SHOCK ABSORBERS P01-01E1.      +++EXAMINATION CATEGORY E-A+++
P01-01E1. 1    +++PRESSURE  RETAINING WELDS IN CONTAINMENT VESSELS+++
P01-01E1. 10  +++SHELL WELDS IN CONTAINMENT VESSELS+++
P01-01E1. 11  LONGITUDINAL SHELL WELDS IN VESSELS (CATEGORY A)
P01-01E1. 12  CIRCUMFERENTIAL SHELL WELDS IN VESSELS (CATEGORY B)
P01-01E1. 20    FLANGE WELDS IN VESSELS  ( CATEGORY C)
P01-01E1. 30    NOZZLE-TO-SHELL WELDS IN VESSELS (CATEGORY 0)
P01-01E1.40    +++INSERT PLATE WELDS+++
44t4444444444t44f444f44f444444444444444444444f444444444t444f444444444444444
 
+~4444444f4444444f4t44444444444444444444  444444444444444444  444444444444444 NUTECH                                                              PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                  PAGE        108 REVISION    RRS1 DATE  85/12/05 444444444444444440444444484444444444444444444444444440404444444444444444404 REFERENCE KEY                            DESCRIPTION P01-01E1. 41    INSERT PLATE-TO-SHELL WELDS P01-01E1. 42    LONGITUDINAL INSERT PLATE WELDS P01-01E1. 43    CIRCUMFERENTIAL INSERT PLATE WELDS P01-01E1. 50    +++VENT SYSTEM WELDS+++
P01-01E1. 51    LONGITUDINAL VENT SYSTEM WELDS P01-01E1. 52    CIRCUMFERENTIAL VENT SYSTEM WELDS P01-01E1. 53    OTHER VENT SYSTEM WELDS P01-01E2.        +++EXAMINATION CATEGORY E-A-1+++
P01-01E2. 1      +++NONPRESSURE-RETAINING WELDS+++
P01-01E2. 10    +++REINFORCING STRUCTURE WELDS+++
P01-01E2.11      CONTAINMENT VESSEL ATTACHMENT REINFORCING STRUCTURE WELDS P01-01E2. 12    OTHER REINFORCING STRUCTURE WELDS P01-01E2. 20    REINFORCING STRUCTURE ATTACHMENT WELDS P01-01E3.        +++EXAMINATION CATEGORY E-8+++
P01-01E3. 1      +++PRESSURE  RETAINING WELDS IN CONTAINMENT PENETRATIONS+++
44f$ 44444444444f44444f44444444444t4444444ftfff444444444444f4404f4444
 
E 4~44444444444444444444f4444444444f44f44404f44t44444444444 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                  PAGE        .109 REVISION  RRS1 DATE  85/12/05 444444444444444444444440444444444444444444444444440444444      44444444440444P444 REFERENCE KEY                              DESCRIPTION P01-01E3. 10    +++CONTAINMENT PENETRATION WELDS+++
PO I-01E3. 11    LONGITUDINAL CONTAINMENT PENETRATION WELDS P01-01E3. 12    CIRCUMFERENTIAL CONTAINMENT PENETRATION WELDS P01-01E3. 13    FLUED HEAD AND BELLOWS SEAL CIRC WELDS JOINED TO THE PENET FLUED HEAD AND BELLOWS SEAL CIRCUMFERENTIAL WELDS JOINED TO THE PENETRATION.
P01-01E4.        +++EXAMINATION CATEGORY E-C+++
P01-01E4. 1    +++PRESSURE  RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES+++
P01-01E4. 10    +++AIRLOCK WELDS+++
P01-01E4. 11    LONGITUDINAL AIRLOCK WELDS P01-01E4.12      CIRCUMFERENTIAL AIRLOCK WELDS P01-01E4. 20    +++EQUIPMENT HATCH WELDS+++
P01-0IE4.21      LONGITUDINAL EQUIPMENT HATCH WELDS P01-01E4. 22    CIRCUMFERENTIAL EQUIPMENT HATCH WELDS P01-01E5.        +++EXAMINATION CATEGORY E-0+++
4444t444444444444444444444444ff444444444444444444444444444444444444444444+
 
0 444444444444444444t44444444t4444$  t44 44444444444444    4444444444444$
NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT      UNIT 1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE      . 110 REVISION  RRS1 DATE 85/ 12/05 44444444444444444444444444f4tffttf4444t44444444ff4444444ff444444444404f04t4 REFERENCE KEY                              DESCRIPTION P01-01E5.1      +++SEALS AND GASKETS+++
P01-01E5.10      SEALS P01-01E5.20      GASKETS P01-01E6.        +++EXAMINATION CATEGORY E-E+++
P01-01E6. 1    +++ INTEGRAL ATTACHMENTS+++
P01-01E6.10      INTEGRAL ATTACHMENT WELDS P01-01E7.        +++EXAMINATION CATEGORY E-F+++
P01-01E7. 1    +++PRESSURE  RETAINING DISSIMILAR METAL WELDS+++
P01-01E7.10      DISSIMILAR METAL WELDS Po 1-01EB        +++EXAMINATION CATEGORY E-G+++
P01-01EB.        +++PRESSURE  RETAINING BOLTING+++
P01-01EB. 1    +++BOLTED CONNECTION VISUAL EXAMINATION+++
P01-01E8.10      BOLTED CONNECTION VISUAL EXAMINATION P01-01E8.2      +++BOLTED CONNECTION BOLT TORQUE OR TENSION TEST++~
P01-01E8.20      BOLTED CONNECTION BOLT TORQUE OR TENSION TEST 4444444444444$ 4444444444444444ff444444444444444444444444f4444444444444444f4
 
0++4444444444444f444448444444444444444444444444ft44444 NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNI T    1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                  PAGE        .111 REVISION  RRS 1 DATE  85/12/05 REFERENCE KEY                            DESCRIPTION P01-01E9.      +++EXAMINATION CATEGORY E-P+++
Po 1-01E9. EX  EXEMPT CLASS MC PRESSURE  RETAINING COMPONENTS Po 1-01E9. 1    +++ALL PRESSURE RETAINING COMPONENTS+++
Po 1-01E9. 10  +++PRESSURE  RETAINING BOUNDARY+++
Pol-01E9. 11  10-CFR-50 APPENDIX J TEST OF CONTAINMENT BOUNDARY P01-01E9. 12  SYS LEAKAGE PRESSURE  TEST IWE-5220 OF CONTAINMENT BOUNDARY SYSTEM LEAKAGE PRESSURE  TEST IWE-5220 OF CONTAINMENT BOUNDARY.
P01-01E9. 20    CONTAINMENT PENET BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST)
CONTAINMENT PENETETRATION BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST).
P01-01E9.30    AIRLOCKS (10CFR50 APPENDIX J TYPE 8 TESTS)
P01-01E9. 40    SEALS AND GASKETS (10CFR50 APPENDIX J TYPE 8 TESTS)
P01-01F1.      +++EXAMINATION CATEGORY F-A+++
P01-01F1. EX  EXEMPT CLASS  1, 2,  OR 3 CATEGORY  F-A COMPONENT SUPPORTS Po 1-01F1. 1    +++PLATE AND SHELL TYPE SUPPORTS+++
444444444444444444444444444t4444t444444444444444444444444444444444444440444
 
+  44444t44444444444444444fff44tt44f44f444f4444444444444444 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                    PAGE        112 REVISION  RRS 1 DATE  85/12/05 t444444444444444ff444444t48444444f4444444444444f4444444444444t4444f44444444 REFERENCE KEY                              DESCRIPTION Po 1-01F 1. 10  MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE    RETAINING COMPONENTS AND BUILDING STRUCTURE P01-01F1. 20    WELDED CONNECTIONS TO BUILDING STRUCTURE P01-01F 1. 30  WELD 8 MECH CONNECTIONS    IN SUPPORT  INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE      JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS Po 1-01F1. 40  DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS,      MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS P01-01F2.      +++EXAMINATION CATEGORY F-8++~
Po 1-01F2. EX  EXEMPT CLASS 1,  2, OR 3 CATEGORY  F-8 COMPONENT SUPPORTS P01-01F2. 1  +++LINEAR TYPE SUPPORTS+++
Po 1-01F2. 10  MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE    RETAINING COMPONENTS AND BUILDING STRUCTURE P01-01F2.20    WELDED CONNECTIONS TO    BUILDING STRUCTURE 4444444444444ff48444444f44f444444fft4f444444f4444444444444f44I44f4fff444444
 
V
  +44444444444444444444444444444444404444440444                  4444444444444t4 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT    1 PLANNING REFERENCE CLUSTER LISTING                044444444444444044
                      'ATA ELEMENT : ITEMNO                      PAGE      '113 REVISION  RRS I DATE  85/12/05 44444444444484444444444444444444444444404444444    4444444444444444444444444444 REFERENCE KEY                              DESCRIPTION PO 1,-01F2. 30  WELD 8 MECH CONNECTIONS  IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE      JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS PO)-01F2.40      DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS,      MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS P01-01F2.50      INVALID I TEMNO  +++  THIS ITEMNO IS INVALID P01-01F3.        +++EXAMINATION CATEGORY F-C+++
P01-0 I F3. EX  EXEMPT CLASS  1, 2,  OR 3 CATEGORY  F-C COMPONENT SUPPORTS P01-01F3. 1    +++COMPONENT STANDARD SUPPORTS+++
P01-01F3. 10    MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE    RETAINING COMPONENTS AND BUILDING STRUCTURE P01-01F3. 20    WELDED CONNECTIONS TO BUILDING STRUCTURE P01-01F3. 30    WELD 8 MECH CONNECTIONS  IN  SUPPORT  INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE      JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS 444'44444444tt44444444t44444444444444t4444444444t4444444444r444444444tf444444
 
C
+~4444444444444444444444t44444444444444f444444444t44044444          444444444444444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE          114 REVISION      RRS 1 DATE    85/12/05 444444444444444444444444444444444404444444444444444444444444444444404444040 REFERENCE KEY                              DESCRIPTION P01-01F3.40      DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS,        MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS Po 1 -01F3. 50    SPRING, CONSTANT, SHOCK ABSORBER, AND SNUBBER SUPPORTS SPRING TYPE SUPPORTS, CONSTANT LOAD TYPE SUPPORTS,        SHOCK    AB-SORBERS, HYDRAULIC AND MECHANICAL TYPE SNUBBERS P02-01            +++  EXAMINATION CATEGORY FSAR+++
P02-0180RE        REACTOR COOLANT PUMP FLYWHEEL BORE  UT P02-0 IFLYWHL    REACTOR COOLANT PUMP FLYWHEEL  SURFACE AND UT P02-01KEYWAY      REACTOR COOLANT PUMP FLYWHEEL KEYWAY    - UT P03-01250. 1S  SAFETY EVALUATION REPORT,  SAFETY- REVIEW QUESTION&#xb9;250. 1 SURFACE EXAM P03-01250. 1V  SAFETY EVALUATION REPORT,  SAFETY REVIEW QUESTION    &#xb9;  250. 1 VOLUMETRICEXAM P04-01            +++  EXAhlINATION CATEGORY FSAR  +++
P04-016.6.88      AUGMENTED  PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH  6.6.88.
P04-016.6.8E      AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.
4444444444444444444444444444f44f44t44t44444t4444Std'444444t4f4444fff44f44444
 
4+s44tkt4tftf4444f4444444444444440444t44                                                                                  4fkf44444f4400 NUTECH                                                                                                                        PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT                                    -  UNIT      1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                                                    PAGE                115 REVISION          RRS1 DATE      85/12/05 4 4 4 '4 4 4 4 4 4 4 4 4 t t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t 0 4 4 4 4 4 4 4 4 4 4 t 4 t t 0 4 4 4 4 4 4 4 4 4 t 4 4 tO 4 4 t t t t t 4 4 4 4 0 4 REFERENCE KEY                                                                  DESCRIPTION P05-01                        +++      EXAMINATION CATEGORY FSAR+++
P05-016.6.8C                  AUGMENTED          PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH          6.6.8C.
P05-016.6.8E                  AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.
P06-01                        +++      EXAMINATION CATEGORY FSAR                            +++
P06-016.6.8D                                      AUGMENTED          PIPING        WELD SURFACE EXAMINATION PER FSAR PARAGRAPH          6.6.8D P06-016.6.8E                  AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.
V01-01C3.          10        PRESSURE          VESSEL INTEGRALLY WELDED ATTACHMENTS V01-01C3.20<                  VOLUNTARY EXAM  INTEGRALWELDED PIPE ATTACHMENT LESS THAN 3/4    INCH THICK 250.      1S                  SAFETY EVALUATION REPORT                          250. 1 SURFACE 250.      1V                  SAFETY EVALUATION REPORT                          250.1        VOUMETRIC EXAM 81W-0181                      +++EXAhlINATION CATEGORY 8-A+++
81W-0181          .            +++REACTOR VESSEL+++
81W-0181.          '10        +++SHELL WELDS+++
44444t44444444f44ff4444444444444444ff444444444f444444fftf444444444
 
44444444444444440440444t444444404404444        44444444444440 NUTECH                                                                    PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    - UNIT  1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                      PAGE          116 REVISION    RRS1 DATE 85/12/05 44444444444444444f 4444t44t44f 4f f tft444444444444444f  t4 f 44f f 44tf 044444444 REFERENCE KEY                              DESCRIPTION 81W-0181.11      RV CIRCUMFERENTIAL SHELL WELOS 81W-0181.12      RV LONGITUDINAL SHELL WELDS 81W-0181. 20    +++HEAD WELDS+++
81W-0181.218    RV CIRCUMFERENTIAL BOTTOM HEAD WELDS CIRCUMFERENTIAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL.
81W-0181.21T    RV CIRCUMFERENTIAL TOP HEAD WELDS I
CIRCUMFERENTIAL TOP HEAD WELD INSPECTION MUST BE PERFORMED DURING EACH PERIOD AND MAY NOT BE DEFERRED TO THE END OF THE INTERVAL.
81W-0181.228    RV MERIDIONAL BOTTOM HEAD WELDS RV MERIDIONAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL.
81W-0181.22T    RV MERIDIONAL TOP HEAD WELDS I
RV MERIDIONAL TOP HEAD WELD INSPECTION MUST BE PERFORMED DURING EACH PERIOD AND MAY NOT BE DEFERRED TO THE END OF THE INTERVAL.
81W-0181.30      RV SHELL-TO-FLANGE WELD 44444444404444444444444444f440444444444444444444444444444t444444444444444
 
%%4eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee              eeeeeeeeeeeeeee NUTECH                                                                      PRIS IM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT        1 PLANNING REFERENCE CLUSTER LISTING                    eeeeeeeeeeeeeeeeee DATA ELEMENT : ITEMNO                      PAGE        . 117 REVISION, RRS    1 DATE    85/12/05 eteeeeeeeeeeeeeeeeeteeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeefeeeeeeeeeeeeeee REFERENCE KEY                                  DESCRIPTION 81W-0181.300      RV SHELL-TO-FLANGE WELD TESTING IN CONJUNCTION WITH CAT 8-D I
EXAM OF SHELL-TO-FLANGE WELDS MAY BE PERFORMED DURING THE 1ST AND 3RD INSPECTION PERIOD IN CONJUNCTION WITH THE NOZZLE EXAM OF CAT. B-D (PROGRAM 8). AT LEAST 50k OF SHELL-TO-FLNGE WELDS SHALL BE EXAM BY THE END OF THE 1ST INSPECTION PERIOD, AND THE REMAINDER BY THE END OF THE 3RD INSPECTION PERIOD.
81W-0181. 30F    RV SHELL-TO-FLANGE WELD PARTIAL EXAM FROM FLANGE FACE IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
81W-0181. 30V    RV SHELL-TO-FLANGE WELD EXAM CONDUCTED FROM VESSEL WALL IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
81W-0181.40      RV HEAD-TO-FLANGE WELD 81W-0181.40F      RV HEAD-TO-FLANGE WELD PARTIAL EXAM FROM FLANGE FACE IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE            ~
THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
eeeeeeeeeefeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
 
e~44444444444444444444444444444444444444444444444444444444        C44444444444f44 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    - UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444444444444044 DATA ELEMENT : ITEMNO                    PAGE      '18 REVISION  RRS1 DATE  85/12/05 40t44ftf44t44tf4444f44tf4444ft444444t44 REFERENCE KEY                            DESCRIPTION 81W-0181. 40V  RV HEAD-TO-FLANGE WELD EXAM CONDUCTED FROM VESSEL WALL IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
81W-0181. 50    +++REPAIR WELDS+++
81W-0181. 5'I  RV BELTLINE REGION REPAIR WELOS 81W-0181 . 99  +++ITEM NUMBERS 82.XX THROUGH 89.XX APPEAR AFTER 816.20+++
81W-01810      +++EXAMINATION CATEGORY 8-K-1+++
8 IW-01810. 1  +++PIPING+++
81W-01810. 10    PIPING INTEGRALLY WELDED ATTACHMENTS 81W-01810. 2    +++PUMPS+++
81W-01810. 20    PUMP INTEGRALLY WELDED ATTACHMENTS 81W-01810. 3  +++VALVES+++
81W-01810.30    VALVE INTEGRALLY WELDED ATTACHMENTS 81W-01812.      +++PUMPS+++
81W-01812. 1    +++EXAMINATION CATEGORY 8-L-1+++
444444444444444444C4444444444444444%444444ftf44f4444f44'4444'44440444444ffO
 
t+ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttktttt NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT  1 t
PLANNING REFERENCE CLUSTER LISTING              tttttttttttttttttt DATA ELEMENT : ITEMNO                  PAGE      .119 REVISION 'RRS1 DATE 85/12/05
<<tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                            DESCRIPTION 81W-01812. 10  PUMP CASING WELDS 81W-01812. 2  +++EXAMINATION CATEGORY  8-L-2+++
8 1W-01812. 20  PUMP CASING 81W-01812. 3  +++EXAMINATION CATEGORY 8-M-1+++
81W-01812. 3A    +++VALVES+++
81W-01812.30    VALVES, NOMINAL PIPE SIZE  < 4 IN. VALVE BODY WELDS 81W-01812.40    VALVES, NOMINAL PIPE SIZE >= 4  IN. VALVE BODY WELDS 81W-01812. 5    +++EXAMINATION CATEGORY 8-M-2+++
81W"01812.50    VALVE BODY, EXCEEDING 4  IN. NOMINAL PIPE SIZE 8 I W-01813.    +++EXAMINATION CATEGORY 8-N-1+++
81W-01813. 1  +++REACTOR VESSEL+++
81W-01813. 10    RV VESSEL  INTERIOR 81W-01813. 2  +++EXAMINATION CATEGORY 8-N-2+++
81W-01813. 2.    +++REACTOR VESSEL (BWR)+++
81W-01813.20    RV INTERIOR ATTACHMENTS  WITHIN BELTLINE REGION (BWR) ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt
 
t NUTECH                                                                PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    -  UNIT  1 PLANNING REFERENCE CLUSTER LISTING                44f 444444444444444 DATA ELEMENT : ITEMNO                    PAGE        . 120 REVISION    RRS1 DATE  85/12/05 444444444444t44c0444444444844444444444444tf444404444444444 REFERENCE KEY                              DESCRIPTION 81W-01813.21    RV INTERIOR ATTACHMENTS BEYOND    BELTLINE REGION (BWR) 81W-01813. 22  RV CORE SUPPORT  STRUCTURE (BWR) 81W-01813. 3    +++EXAMINATION CATEGORY 8-N-3+++
81W-01813. 3.  +++REACTOR VESSEL (PWR)+++
81W-01813.30    INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (PWR) 81W-01813.31    INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (PWR) 81W-01813.32    RV CORE SUPPORT  STRUCTURE (PWR) 81W-01814.      +++EXAMINATION CATEGORY 8-0+++
81W-01814. 1  +++REACTOR VESSEL+++
81W-01814.10    RV WELDS  IN PERIPHERAL  CRD HOUSING 8 1W-01815.    +++EXAMINATION CATEGORY 8-P+++
81W" 01815. EX  EXEMPT CLASS 1 PRESSURE RETAINING COMPONENTS
: 1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
: 2) EXEMPT CLASS 1 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.    (E.G ~ WELDS <= 1" NPS) 81W-01815. 1  +++REACTOR VESSEL+++
444444444tt484ftkf44444ttf4ffkt4444444444t444440444t4444444444f4444444fkt44
 
0~+444444444444444444444404444444f44444444tft444444                    +44444444444444 NUTECH                                                                    PRIS IM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REFERENCE CLUSTER LISTING                4444444444t4444444 DATA ELEMENT : ITEMNO                    PAGE        121 REVISION  RRS 1 DATE  85/12/05 44444444444444444 REFERENCE KEY                                  DESCRIPTION 8IW-01815.10        RV PRESSURE  RETAINING BOUNDARY  OPERATIONAL 81W-01815.11        RV PRESSURE  RETAINING BOUNDARY  -  STATIC 81W-01815.      2  +++PRESSURIZER+++
81W-01815.20        PRZ PRESSURE    RETAINING BOUNDARY  -  OPERATIONAL 81W-01815.      21  PRZ PRESSURE    RETAINING BOUNDARY  -  STATIC 81W-01815. 3        ++~STEAM GENERATORS+++
81W-01815.30        SG  PRESSURE RETAINING BOUNDARY  -  OPERATIONAL 81W-01815.31        SG  PRESSURE RETAINING BOUNDARY  -  STATIC 81W-01815. 4        +++HEAT EXCHANGERS+++
81W-01815.40        HX PRESSURE    RETAINING BOUNDARY  -  OPERATIONAL 81W-01815.41        HX PRESSURE    RETAINING BOUNDARY -    STATIC 8 1W-01815. 5      +++PIPING+++
81W-01815.50        PIPING PRESSURE RETAINING BOUNDARY      - OPERATIONAL 81W-01815.51        PIPING PRESSURE RETAINING    BOUNDARY  - STATIC 8 1W-0 18 'I 5. 6  +++PUMPS+++
444444444444444f444444444444444t44f444444444444444444444f40f4444t44'444444t4
 
+~4444444444444444444444444444444444444044444f4444444fff44          44f4k4f4k44440f NUTECH                                                              PRISIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REFERENCE CLUSTER LISTING                  44444444444444444t DATA ELEMENT : ITEMNO                      PAGE        122 REVISION  RRS1 DATE- 85/12/05 444444444444444444444844444444444444444444444444444444444444444444404444444 REFERENCE KEY                            DESCRIPTION 8 IW-01815.60    PUMP PRESSURE  RETAINING BOUNDARY  -  OPERATIONAL 81W-01815.61    PUMP PRESSURE  RETAINING BOUNDARY  -  STATIC 81W-01815. 7  +++VALVES+++
8 1W-01815.70    VALVE PRESSURE  RETAINING BOUNDARY  -  OPERATIONAL 81W-O'1815.71    VALVE PRESSURE  RETAINING BOUNDARY  -  STATIC 81W-01816.      +++EXAMINATION CATEGORY B-Q+++
81W-01816. 1  +++STEAhl GENERATORS+++
81W-01816. 10    +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN STRAIGHT TUBE DESIGN+++
8 W-0 1816. 20
  '1            +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN U-TUBE DESIGN+++
81W-0182.        +++EXAMINATION CATEGORY B-B+++
81W-0182. 1    +++PRESSURIZER+++
81W-0182. 10    +++SHELL-TO-HEAD WELDS+++
81W-0182. 11  PZR CIRCUMFERENTIAL SHELL-TO-HEAD WELDS 81W-0182. 12  PZR LONGITUDINAL SHELL-TO-HEAD WELDS 44444444444f444444444444f444444444444f444ft44444444444444444f4444f444444
 
~~tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT  1 t
PLANNING REFERENCE CLUSTER LISTING              tttttttttttttttttt DATA ELEMENT : ITEMNO                  PAGE        123 REVISION  RRS 1 85/12/05 DATE ttttttt REFERENCE KEY                            DESCRIPTION 81W-0182. 20  +++HEAD WELOS+++
81W-0182.21    PRZ CIRCUMFERENTIAL HEAD WELDS 81W-0182. 22  PRZ MERIDIONAL HEAD WELOS 81W-0182. 3    +++STEAM GENERATORS (PRIMARY SIDE)+++
81W-0182. 30  +++HEAD WELDS+++
81W-0182. 31  SG PRIMARY  SIDE CIRCUMFERENTIAL HEAD WELDS 81W-0182. 32  SG PRIMARY  SIDE MERIDIONAL HEAD WELDS 81W-0182. 40  SG  PRIMARY SIDE TUBESHEET-TO-HEAD WELDS 81W-0182. 5    +++HEAT EXCHANGERS (PRIMARY SIDE)+++
81W" 0182. 50  +++SHELL(OR HEAD) WELDS+++
81W-0182. 51  HX PRIMARY SIDE CIRCUMFERENTIAL SHELL (OR HEAD) WELDS 81W-0182. 52  HX PRIMARY    MERIDIONAL SHELL (OR HEAD) WELD 81W-0182. 53  HX PRIMARY LONGITUDINAL SHELL (OR HEAD) WELD 81W" 0182. 6  +++ SHELL (PRIMARY SIDE) +++
81W-0182. 60  TUBESHEET-TO-SHELL (OR HEAD) WELDS
 
seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeekeeeeeeeee I,
eeeeeeeeeeeeeee NUTECH                                                                        PRISIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT        -  UNIT  1 PLANNING e                        REFERENCE CLUSTER LISTING                    eeeeeeeeeeeeeeeeee DATA ELEMENT : ITEMNO                        PAGE          124 REVISION    RRS1 DATE    85/12/05 eeeeeeeeeeeeeeeeeeeeeee            eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee REFERENCE KEY                                  DESCRIPTION 81W-0182. 61      TUBESHEET-TO-SHELL WELDS 81W-0183          +++EXAMINATION CATEGORY 8-DA+++
81W-0183.          +++PROGRAM A REQUIREMENTS+++
1ST INTERVAL = 3      YEARS 2ND INTERVAL = 7      YEARS 3RD INTERVAL = 13    YEARS 4TH INTERVAL = 17    YEARS 81W-0183. 1    +++REACTOR VESSEL+++
81W-0183. 10    RV NOZZLE-TO-VESSEL WELDS      - PROGRAM A 81W-0183. 20      RV NOZZLE  INSIDE RADIUS SECTION      - PROGRAM A 81W-0183. 3        +++PRESSURIZER+++
81W-0183. 30      PRZ NOZZLE-TO-VESSEL WELDS  PROGRAM A 81W-0183. 40      PRZ NOZZLE  INSIDE RADIUS SECTION        PROGRAM A 81W-0183. 5        +++STEAM GENERATORS (PRIMARY SIDE)+++
81W-0183. 50      SG  PRIMARY NOZZLE-TO-VESSEL WELDS  PROGRAM A 81W-0183. 60      SG PRIMARY NOZZLE    INSIDE RADIUS SECTION        PROGRAM A 81W-0183. 7    +++HEAT EXCHANGERS (PRIMARY SIDE)++~
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
 
NUTECH                                                              PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT      1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                  PAGE      ,  125 REVISION    RRS1 DATE  85/12/05 444444484'444444444444t4444444444444444444444t444444444444444444444444 REFERENCE KEY                              DESCRIPTION 81W-0183. 70    HX PRIMARY NOZZLE-TO-VESSEL WELDS  PROGRAM A 81W-0183. 80    HX PRIMARY NOZZLE  INSIDE RADIUS SECTION  PROGRAM  A 81W-0183. 9    +++EXAMINATION CATEGORY 8-08+++
81W-0183. 9.    +++PROGRAM 8 REQUIREMENTS+++
1ST INTERVAL    10 YEARS 2ND INTERVAL    10 YEARS 3RD INTERVAL    10 YEARS 4TH INTERVAL    10 YEARS 81W-0183. 9A    +++REACTOR VESSEL+++
81W-0183. 98    RV NOZZLE-TO-VESSEL WELDS, EXAM FROM NOZZLE BORE  PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZlE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
81W-0183. 9S    RV NOZZLE-TO-VESSEL WELDS, EXAM FROM RV SHELL  PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
 
444444444444444444444444t4444444444444444444            44444444444444 NUTECH                                                                      PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT        UNIT  1 PLANNING REFERENCE CLUSTER LISTING                    444444444444444444 DATA ELEMENT : ITEMNO                        PAGE        126 REVISION  RRS1 DATE 85/12/05 44444444444444tf4444f4444f444444t44444444444444t4444t444ttt4t44f44444444444 REFERENCE KEY                              DESCRIPTION 81W-0183. 90    RV NOZZLE-TO-VESSEL WELDS  -  PROGRAM 8 81W-0183.100    RV NOZZLE  INSIDE RADIUS SECTION  -  PROGRAM 8 81W-0183. 11    +++PRESSURIZER+++
81W-0183.110    PZR NOZZLE-TO-VESSEL WELDS    -  PROGRAM 8 81W-0183.120    PZR NOZZLE  INSIDE RADIUS SECTION    -  PROGRAM 8 81W-0183. 13    ~++STEAM GENERATORS (PRIMARY SIDE)+++
81W-0183.130    SG PRIMARY  NOZZLE-TO-VESSEL WELDS    -  PROGRAM 8 81W-0183.140    SG PRIMARY NOZZLE  INSIDE RADIUS SECTION          PROGRAM 8 81W-0183. 15    +++HEAT EXCHANGERS (PRIMARY SIDE)+++
81W-0183.150    HX PRIMARY NOZZLE-TO-VESSEL WELDS      -  PROGRAM 8 81W-0183.160    HX PRIMARY NOZZLE  INSIDE RADIUS SECTION      -  PROGRAM 8 81W-0184        +++EXAMINATION CATEGORY 8-E+++
81W-0184. 10    +++ PARTIAL PENETRATION WELDS+++
81W-0184. 11    VESSEL NOZZLE PARTIAL PENETRATION WELDS 81W-0184. 12      CONTROL ROD DRIVE NOZZLE PARTIAL PENETRATION WELDS 444444444444444flf444444f44444f44404404f444444444444444444444444444
 
+~44444444444444f444f4444444444444444444444444      044444444444    444444444444444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE        127 REVISION  RRS1 DATE  85/12/05 4444444444444t44444444444444444444f044t4444444                44444404044044r444444 REFERENCE KEY                              DESCRIPTION 81W" 0184. 13      INSTRUMENTATION NOZZLE PARTIAL PENETRATION WELDS 81W-0184. 2      +++PRESSURIZER+++
81W-0184. 20      PRZ HEATER PENETRATION WELDS 81W-0185.          +++EXAMINATION CATEGORY 8-F+++
8 IW-0185. 1    +++REACTOR VESSEL+++
81W-0185. 10    RV NOZZLE-TO-SAFE END BUTT WELDS. NPS >= 4 INCHES WHEN DONE CONCURRENTLY  WITH CATEGORY 8-D EXAMINATIONS 81W-0185. 10    RV NOZZLE-TO-SAFE END BUTT WELDS, NPS >= 4 INCHES 81W-0185. 2D      RV NOZZLE-TO-SAFE END BUTT WELDS, NPS < 4 INCHES WHEN DONE CONCURRENTLY  WITH CATEGORY 8-D EXAMINATIONS 81W-0185. 20      RV NOZZLE-TO-SAFE END BUTT WELDS, NPS < 4 INCHES 81W-0185. 3D      RV NOZZLE-TO-SAFE END SOCKET WELDS WHEN DONE CONCURRENTLY  WITH CATEGORY 8-D EXAMINATIONS 81W-0185. 30      RV NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185. 4        +++PRESSURIZER+++
444444444444t4%444444444444tt4444444444444444444444440444444444
 
4w4444444t44444444444444444444t4t444444444440444444t4444        444444444444444 NUTECH                                                              PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    UNIT  1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                  PAGE          128 REVISION    RRS1 DATE  85/12/05 4444444444444444444 REFERENCE KEY                              DESCRIPTION 81W-0185. 40    PZR NOMINAL  PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE  END BUTT WELDS 81W-0185. 50    PRZ NOMINAL  PIPE SIZE < 4 IN. NOZZLE-TO-SAFE  ENO BUTT WELDS 81W-0185. 60    PRZ NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185. 7    +++STEAM GENERATOR+++
81W-0185. 70    SG NOMINAL  PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELDS 81W-0185. 80    SG NOMINAL  PIPE SIZE < 4  IN. NOZZLE-TO-SAFE  END BUTT WELDS 81W-0185. 90    SG NOZZLE-TO-SAFF END SOCKET WELDS 81W-0185. 10    +++HEAT EXCHANGERS+++
81W-0185.100    HX NOMINAL  PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE  ENO BUTT WELDS 81W-0185. 110  HX NOMINAL  PIPE SIZE  < 4  IN. NOZZLE-TO-SAFE  END BUTT WELDS 81W-0185.120    HX NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185. 13    +++PIPING+++
81W-0185.130    NOMINAL PIPE SIZE >= 4  IN. DISSIMILAR METAL PIPING    BUTT WELD 81W-0185.140    NOhlINAL PIPE SIZE < 4  IN. DISSIMILAR METAL PIPING    BUTT WELD 81W-0185. 150  DISSIMILAR METAL PIPING SOCKET    WELDS 4t44f4444444444444'4444040ff444444ff404444444rtt44f44444
 
44444444444t4444444444444444444f  4444444f 44444444 NUTECH                                                                  PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT        UNIT 1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ITEMNO                    PAGE        129 REVISION    RRS1 DATE    85/12/05 444844444444444444444404444404tt4444444444444444444444444444444444444404404 REFERENCE KEY                              DESCRIPTION 81W-0186.      +++EXAMINATION CATEGORY 8-G-1+++
81W-0186. 1    +++REACTOR VESSEL+++
81W-0186. 10  RV CLOSURE HEAD NUTS    (> 2")
81W-0186. 20    RV CLOSURE STUDS,  IN PLACE (> 2" )
81W-0186. 30    RV CLOSURE STUDS,  WHEN REMOVED  (> 2")
81W-0186. 40    RV THREADS  IN FLANGE (>  2")
81W-0186. 50    RV CLOSURE WASHERS,  BUSHINGS  (> 2")
81W-0186. 6    +++PRESSURIZER+++
81W-0186. 60    PRZ BOLTS AND STUDS  (>  2")
81W-0186. 70    PRZ FLANGE SURFACE WHEN CONNECTION DISASSEMBLED        (>  2")
81W"0186. 80    PRZ NUTS, BUSHINGS, AND WASHERS    (> 2")
81W-0186. 9    +++STEAM GENERATORS+++
81W-0186. 90    SG BOLTS AND STUDS  (>  2")
81W-0186.100    SG FLANGE SURFACE WHEN CONNECTION DISASSEMBLED      (> 2")
81W-0186. 110    SG NUTS, BUSHINGS, AND WASHERS (>    2" )
4444444444444444444444444444444444444444444444444ff44f444444444444444044f44
 
0 4m+444444$ 444f4444r44444444t4444t4444444444444444ftt4444444          44444444fk44444 NUTECH                                                                    PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT          1 PLANNING REFERENCE CLUSTER LISTING                    444440444440444444 DATA ELEMENT : ITEMNO                      PAGE        130 4 REVISION  RRS1 DATE  85/12/05 44444444444444444444t4444r444444440444444f4fft444444444444440irt4444f REFERENCE KEY                                  DESCRIPTION 81W-0186. 12,,  +++HEAT EXCHANGERS+++
81W-0186.120    HX BOLTS AND STUDS      (>  2")
81W-0186. 130  HX FLANGE SURFACE WHEN CONNECTION DISASSEMBLED            (> 2")
81W-0186. 140  HX NUTS, BUSHINGS, AND WASHERS        (> 2" )
81W-0186. 15    +++ P I P I N 6+++
81W-0186. 150    PIPING BOLTS      AND STUDS  (>  2")
81W-0186.160    PIPING FLANGE SURFACE      WHEN CONNECTION DISASSEMBLED    (> 2")
81W-0186. 170    PIPING NUTS, BUSHINGS, AND WASHERS (>        2")
81W-0186. 18    +++PUMPS+++
81W-0186. 180    PUMP BOLTS AND STUDS      (> 2")
81W-0186. 190    PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED          (> 2")
81W-0186.200    PUMP NUTS,      BUSHINGS, AND WASHERS (>  2")
81W-0186. 21    +++VALVES+++
81W-0186. 210    VALVE BOLTS AND STUDS (>        2")
8 IW-0186.220    VALVE FLANGE SURFACE WHEN CONNECTION DISIASSEMBLED (> 2")
4444444444444444444444444444444444444444444t444444444444f444t444f4444444444
 
0++4444444444444444444444444f444f4444444C4f'444444444f4$    44 NUTECH                                                                PRISIM CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                    PAGE        131 REVISION  RRS1 DATE  85/12/05 4444444444444t4444f4444444444444444444t444444444444t REFERENCE KEY                            DESCRIPTION 81W-0186.230    VALVE NUTS, BUSHINGS, AND WASHERS (>    2")
81W-0187.      +++EXAMINATION CATEGORY 8-G-2+++
81W-0187. 1    +++REACTOR VESSEL+++
81W-0187. 10  REACTOR VESSEL BOLTS, STUDS,    AND NUTS  (<=  2")
81W-0187. 2    +++PRESSURIZER+++
81W-0187. 20    PRESSURIZER BOLTS, STUDS, AND NUTS (<=    2")
81W-0187. 3    +++STEAM GENERATORS+++
81W-0187. 30    STEAM GENERATOR BOLTS, STUDSI AND NUTS    (<=  2")
81W" 0187. 4    +++HEAT EXCHANGERS+++
81W-0187.40    HEAT EXCHANGER BOLTS, STUDS,    AND NUTS  (<=  2")
81W-0187. 5    +++PIPING+++
81W-0187.50      PIPING BOLTS, STUDS, AND NUTS (<=  2")
81W-0187. 6      +++PUMPS+++
81W-0187. 60    PUMP BOLTS, STUDS,  AND NUTS  (<= 2")
81W-0187. 7      t++VALVES+++
444444$ 444444444444044044444444444040440444444444444444444444t4444444444444
 
t
  +4444'44444444444444444444444444444444444444444444f      444444    444444444444444 NUTECH                                                                    PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT      -  UNIT  1 PLANNING REFERENCE CLUSTER LISTING                  44t444444444444444 DATA ELEMENT : ITEMNO                      PAGE          132 REVISION    RRS1 DATE  85/12/05 444444444444f4440444444f4tf44444444tf444tf444444444444444444404444444 REFERENCE KEY                                DESCRIPTION 81W-0187.70      VALVE BOLTS, STUDS, AND NUTS (<=      2")
81W-0187.8      +++CRD HOUSING+++
81W-0187.80      CRD HOUSING BOLTS, STUDS,    AND NUTS  (<= 2")
8 1W-0188 .      +++EXAMINATION CATEGORY 8-H+++
81W-0188. 1    +++REACTOR VESSEL+++
81W-0188. 10      RV INTEGRALLY WELDED ATTACHMENTS 81W-0188. 2      +++ PRESSUR I ZER+++
81W-0188. 20      PZR INTEGRALLY WELDED ATTACHMENTS 81W-0188. 3    +++STEAM GENERATORS+++
81W-0188.30      SG  INTEGRALLY WELDED ATTACHMENTS 81W-0188. 4      +++HEAT EXCHANGERS+++
81W-0188.40      HX INTEGRALLY WELDED ATTACHMENTS 81W-0189.        +++EXAMINATION CATEGORY 8-J+++
81W-0189. 1    +++PIPING+++
81W-0189. 10      +++NOMINAL PIPE SI2E >= 4    IN.+++
4444444444444444444444t444f444444444404tt440tfff444f4444
 
+++44444444444444444444444444444444f    4f 44f 44 444444444444444    444444444444444 NUTECH                                                                    PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT      -  UNIT 1 PLANNING REFERENCE CLUSTER LISTING                  444444444444044444 DATA ELEMENT : ITEMNO                      PAGE    ,    133 REVISION, RRS1 DATE 85/12/05 44444 ~ 4444444444444444444404444t044444tf444tf444444444444444444 REFERENCE KEY                                DESCRIPTION 81W-0189. 11    CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4            IN.
81W-0189. 12    LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4            IN.
81W-0189. 20    +++PIPING NOMINAL PIPE SIZE < 4 IN.+++
81W-0189. 21    CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4            IN.
81W-0189. 22    LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4            IN.
81W-0189.30      +++BRANCH PIPE CONNECTION WELDS+++
8 1W-0189. 31    BRANCH  PIPE CONNECTION WELDS, NOMINAL PIPE SIZE >= 4 IN.
81W-0189. 32      BRANCH  PIPE CONNECTION WELDS, NOMINAL PIPE SIZE < 4 IN.
81W" 0189. 40    PIPE SOCKET WELDS 81W-0189. 99      +++ITEM NUMBERS 810.XX THROUGH 816.XX APPEAR AFTER 81.51+++
81W-01C1.        +++EXAMINATION CATEGORY C-A+++
81W-01C1. 1      +++PRESSURE  VESSELS+++
81W-01C1. 10      PRESSURE  VESSEL SHELL CIRCUMFERENTIAL WELDS 81W-01C1. 20      PRESSURE  VESSEL HEAD CIRCUMFERENTIAL WELDS 81W-01C1. 30      PRESSURE  VESSEL TUBESHEET-TO-SHELL WELD 4444444444444444444444444f44444f444f440444444tf4444444444444444444444444444
 
44444444          444tt4444444t44f44444f444444f    444444444444444 NUTECH                                                                PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING                4444444444t4444f44 DATA ELEMENT : ITEMNO                  PAGE        134 REVISION  RRS 1 DATE  85/12/05 444444444444444444444444444444444444444444444444444444444444444444444444444 REFERENCE KEY                              DESCRIPTION 81W-01C2.        +++EXAMINATION CATEGORY C-B+++
81W-01C2. 1      +++PRESSURE  VESSELS+++
81W-01C2. 10    +++NOZZLES IN VESSELS    <=1/2 IN. NOMINAL THICKNESS+++
81W-01C2. 11    NOZZLES-TO-SHELL(OR HEAD) WELD 81W-01C2. 20    +++NOZZLES WITHOUT REINFORCING PLATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++
81W-01C2. 21    NOZZLE-TO-SHELL(OR HEAD) WELD 81W-01C2. 22    NOZZLE INSIDE RADIUS SECTION IN VESSELS 81W-01C2. 30    +++NOZZLES WITH REINFORCING PLATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++
81W-01C2. 31    REINFORCING PLATE WELDS TO NOZZLE AND VESSEL 81W-01C2. 32    +++NOZZLE-TO-SHELL (OR HEAD) WELDS+++
81W-01C2.32A      INSIDE  OF VESSEL ACCESSIBLE,  NOZZLE-TO-SHELL (OR HEAD) WELD INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM. CAT. C-F WHEN THE INSIDE OF THE VESSEL IS ACCESSIBLE.
81W-01C2. 32 I    INSIDE  OF VESSEL  INACCESSIBLE, NOZZLE-TO-SHELL(OR HEAD) WELD I
INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM. CAT. C-F WHEN THE INSIDE OF THE VESSEL IS INACCESSIBLE.
444tlff44444444t44444444f444444t44f44t444444444444
 
e e
 
  +44444444444444f444444444444440444444444444444f44444444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  -  UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444044444444444 DATA ELEMENT : ITEMNO                    PAGE        135 REVISION 'RRS1 DATE  85/12/05 4444440t44          44444f844t4 REFERENCE KEY                            DESCRIPTION 81W-01C3.      +++EXAMINATION CATEGORY C-C+++
81W-01C3. 1    +++PRESSURE VESSELS+++
81W-01C3. 10    PRESSURE  VESSEL INTEGRALLY WELDED ATTACHMENTS 81W-01C3. 2    +++PIPING+++
81W-01C3. 20    PIPING INTEGRALLY WELDED ATTACHMENTS 81W-01C3. 3    +++PUMPS+++
81W-01C3. 30    PUMP INTEGRALLY WELDED ATTACHMENTS 81W-01C3. 4    +++VA1VFS+++
81W-01C3.40    VALVE INTEGRALLY WELDED ATTACHMENTS 81W-01C4.      +++EXAMINATION CATEGORY C-D+++
81W-01C4. 1    +++PRESSURE VESSELS+++
81W-01C4. 10    PRESSURE  VESSEL BOLTS AND STUDS (>  2")
81W-01C4. 2    +++PIPING+++
81W-01C4. 20    PIPING BOLTS  AND STUDS (> 2")
81W" 01C4. 3    +++PUMPS+++
44444444444444444444404444444444444444444t44444444444t404444444444444444444


a~44444444444444444444444444444444444444444444444444444444 444444444404444 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES PAGE 16 REVISION ,RRS1 4 DATE 85/12/04 4444444444444444444444444444t44t444t444044444444444444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PBC, PBC,A PBC,E PBC,HC PBC,LOL PBC,LSP PBC,S PBC,SWP PBC,T+++++++++++++t++++++++++
J eeeeeeeteteeeeeeteeeeeeeeeeeeeeeeeeteeeeeeeeeeeeeee          e  seeeeeeeeeeeeee NUTECH                                                                       PRISIM t                        CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT        UNIT  1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                      PAGE         136 REVISION     RRS1 DATE   85/12/05 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee            eeeeeeeeeeeeeeeeee REFERENCE KEY                                   DESCRIPTION 81W-01C4. 30      PUMP BOLTS AND STUDS      (>  2")
PIPING+++t++++++++++++++++++++++
81W-01C4. 4        +++VALVES+++
+EXAMINATION CATEGORIES B-F, B-J, B-K-1, C-C, C-F,++D-A, D-B, AND 0-C (81W)++++A BRANCH CONNECTION WITHOUT CIRCUMFERENTIAL WELDS+++BC UNK BRANCH CONNECTION, TYPE UNKNOWN ELBOWLT ELBOWLET HALFCPL HALF COUPLING LATROLT LATEROLET LSWEEPT LATERAL SWEEPOLET SOCKOLT SOCKOLET SWPOLET SWEEPOLET THREDLT THREADOLET 4444444444444448t444ft444444444ft444444444044fffkf4f4444444444444444444444 44444444444444t44444444t4444444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SYSTEM 440444440444444444444444444440444444f44 4444444444444444444 C44444444444444 PRISIM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: COMPDES PAGE 17 REVISION RRS1 DATE 85/12/04 44444444r4444444444444044044444444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PBC,TE PBC,W PBCC, PBCC,CR PBCC,EX PBCC,L PBCC,T PBCC,TR PC, PC,ACC PC,CAP PC,EXPJ THERMOWELL TEMPERATURE ELEMENT WELDOLT WELDOLET+++A BRANCH CONNECTION WITH CIRCUMFERENTIAL WELDS ONLY+++CROSS EXTRUD PIPE EXTRUSION LATERAL TEE RED TEE TEE, REDUCING+++CIRCUMFERENTIAL PIPING WELD+++ACCUM ACCUMULATOR CAP EXP JNT EXPANSION JOINT 444444444444f4444444444444444t44t444444ff444t44f4444444 44444444444444444444444444f444444444444444444444444+
81W-01C4.40        VALVE BOLTS AND STUDS (>      2")
f44f444444444f4 4'UTECH CAROLINA POWER 8 LIGHT COM SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES 444444444W444444444444444444444444444444444444 PRISIM PANY 4 444444444444444444 PAGE 18 REVISION RRS1 DATE 85/12/04 4444444444444444t444f REFERENCE KEY PIPING COMPONENT DESCRIPTION PC,FE PC,MAN PC,NOZ PC,NOZW PC,PB PC, PIPE PC,PUMP PC,RED PC,REDI PC,SDFP PC,SE PC,SEE FLOW EL FLOW ELEMENT MANI FLD MANIFOLD NOZZLE NOZ WLD WELD IN NOZZLE FLANGE P BEND PIPING BEND PIPE PUMP REDUCER RED INS REDUCING INSERT SUMP PL SUMP DRAIN FILTER PLATE SAFEEND SAFE END SAFEEND SAFE END EXTENSION 44444444444444f444tf44444tt44444444444444444444444444f4f44f444444444t44444f
81W-01CS.          +++EXAMINATION CATEGORY C-F+++
++44444444f444444444t4444f44444444444444f444f444444444444+
81W-01C5. I      +++PIPING+++
444444444t44044 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4 DATA ELEMENT: COMPDES PAGE 19 REVISIONRRS1 DATE 85/12/04 44444444444f444444444444444f44I44444444444444444444fff4444444f4044f44fff444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PC,TRS PC,TS PC,VENC PC,VLV PE~PE,ELR PE,LR PE,RED PE,SR PELBOW PF, TRANS TRANSITION PIECE T STRNR TEMPORARY STRAINER VENTURI CAVITATING VENTURI VALVE+++ELBOWS+++ELB ELR ELBOW, EXTRA LONG RADIUS ELB LR ELBOW, LONG RADIUS RED ELB REDUCING ELBOW ELB SR ELBOW, SHORT RADIUS ELBOW ELBOW, RADIUS UNKNOWN+++FLANGES+++044444444444444'444440t4444444444444'4004004440t444444t4044444444444440444444
81W-01CS. 10      +++PIPING WELDS <= 1/2 IN. NOMINAL WALL THICKNESS+++
~1dl 440444444440044 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444044444 DATA ELEMENT: COMPDES PAGE~.20 REVISION RRS 1 DATE 85/12/04 444488444444444t4444444444t44444t44444444444444444444444f44444f44444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PF,A PF,B PF,O PF,RED PF,RFWN PF,RWNR PF,SO PF,SW PF,WN PF,WNGF PF,WNO FLG UNK FLANGE, TYPE UNKNOWN FLG BLN FLANGE, BLIND FLG ORF FLANGE, ORIFICE FLG RED FLANGE, REDUCING FLG RFW FLANGE, RAISED FACE WELD NECK FLG RWR FLANGE, RAISED FACE WELD NECK REDUCING FLG SLP FLANGE, SLIP ON+++FLANGE, SOCKET WELDED (SHOULD BE ENTERED AS PSW,F)+++FLG WN FLANGE, WELD NECK FLG WNG FLANGE, WELD NECK GROOVED FACE FLG WNO FLANGE, RAISED FACE WELD NECK ORIFICE 888444408040444t44444444444444444444444444444444444440444t44t44444t44444444 0
81W-01C5. 11    PIPING CIRCUMFERENTIAL      WELD <=  1/2" NOMINAL WALL THICKNESS 81W-01C5. 12       PIPING LONGITUDINAL WELD <= 1/2" NOMINAL WALL THICKNESS 81W-01CS. 20      +++PIPING WELDS > 1/2 IN. NOMINAL WALL THICKNESS+++
444444444444f44444444444444444444~
81W-01C5. 21      PIPING CIRCUMFERENTIAL WEI.D > 1/2" NOMINAL WALL THICKNESS 81W-01CS. 22       PIPING LONGITUDINAL WELD > 1/2" NOMINAL WALL THICKNESS 81W-01CS. 30      +++PIPING BRANCH CONNECTIONS+++
444444f44444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES<<.PAGE 21 4 REVISION RRS1 DATE 85/12/04 4444448044444444444444444444444404444444f444444444t44444444444404t444tt4444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PF,WNTF PI PI, PI, CL PI, CLVN PI, FHA PI, FHB PI, FHI PI, HL PI,LUGF PI, LUGN FLG WNT FLANGE, WELD NECK TONGUE FACE+++INTEGRALLY WELDED ATTACHMENTS
81W-01CS. 31      PIPE BRANCH CONNECTION CIRCUMFERENTIAL WELD 81W-0 I C5. 32      PIPE BRANCH CONNECTION LONGITUDINAL WELD 8 1W-01C6.        +++EXAMINATION CATEGORY C-G+++
++++++EXAMINATION CATEGORIES 8-K-1, C-C, D-A,++++++D-B, AND D-C (81W)+++CENTER PIPE SUPPORT, CENTERING LUG CLEVIS WELDED LUGS, FORMING A CLEVIS, NOT FULL PENETRATION TYPEI IA FLUED HEAD, TYPE IIA TYPEIIB FLUED HEAD, TYPE IIB TYPE I FLUED HEAD, TYPE I HANGER PIPE SUPPORT, HANGER LUG LUG, FP LUG, FULL PENETRATION WELD LUG, PP LUG, NOT FULL PENETRATION (FILLET OR PARTIAL PENETRATION) e8884t8%4%444444444444tt4444404404444444444444444404044444444444444444444%4
eeeeeteeeeeetteeteeeeeeeeeeeeeeeeeteeeeeeeeteeeeeeteeeeeeeeeeeeeeeeeeeeeeee
~404444444444444444t444444444t44tt444444444404444440444'4 NUTECH CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES PRISIM 44444444 4 44444 444 4 PAGE,~22 REVISION'.RRSl DATE 85/12/04 4444444t4444tt444444444t44t444444t04444440444t44444444404444t444t4440444440 REFERENCE KEY PIPING COMPONENT DESCRIPTION PI,PSU PI,R PI, SADL PI, STAN PI,TRUN PLSW, PLSW,C PLSW,EI PLSW,EO PLSW,P PLSW,R SUPPORT PIPE SUPPORT, TYPE UNKNOWN RING RING SUPPORT SADDLE STANCHN STANCHION TRUNNON TRUNNION+++LONGITUDINAL SEAM WELDS+++CRSSEAM LONGITUDINAL SEAM WELD, CROSS ELBSEAM LONGITUDINAL SEAM WELD'LBOW INSIDE ARC ELBSEAM LONGITUDINAL SEAM WELD'LBOW OUTSIDE ARC LNGSEAM LONGITUDINAL SEAM WELD, PIPE REDSEAM LONGITUDINAL SEAM WELD, REDUCER 044t4444444t444444tttt4444444444444f4444444444444ft4444444404tt444f4444f4 i444t4444 NUTECH eeyeekgeg4444444444444444444444f444f44444444444 s444444444444444 PRISIM CAROLINA POWER&LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444404444 DATA ELEMENT: COMPDES PAGE 23 REVISION RRS 1"2 DATE 85/12/04 4444440444444444444404404444444440444r4448448444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PLSW,T PP, PP,ENDP PP,FHS PP,FHSI PP,FHT PP,FHTI PP,PIPE PP~PLT PP,TRP TEESEAM LONGITUDINAL SEAM WELD, TEE+++PENETRATION COMPONENTS
++++USE PI,FHA OR PI,FHB FOR INTEGRAL ATTACHMENT FLUED HEADS+PPLATE PENETRATION END PLATE FL HEAD FLUED HEAD, SINGLE (WITH A WELD IN THE PENETRATION)
FL HEAD FLUED HEAD, SINGLE INTEGRAL (ALL ONE PIECE)FL HEAD FLUED HEAD, TRIPLE (WITH A WELD IN THE PENETRATION)
FL HEAD FLUED HEAD, TRIPLE INTEGRAL (ALL ONE PIECE)PENPIPE PENETRATION PIPE (THE PIPE SUPPLIED BY THE CONTAINMENT SUPPLIER RATHER THAN THE PIPING SUPPLIER)PPLATE PENETRATION PLATE PENPLT TORUS SHELL PENETRATION REINFORCEMENT PLATE 444444444444444t44f44444444444t4444t44444f444444f44444444444t44444tft44t4f4 ittttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH tttttttttttttttttttt CAROLINA POWER 8 LIGHT COMPANY SYSTEM PRISIM REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: COMPDES PAGE 24 REVISION RRS 1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PIPING COMPONENT DESCRIPTION PSW, PSW,C PSW,CPL PSW,CPR PS'PSW,F PSW,FO PSW,HC PSW,MAN PSW,P PSW,PB+++SOCKET WELDS+++CAP COUPLNG COUPLING RCUPLNG REDUCING COUPLING ELBOW FLANGE ORIFICE FLANGE, ORIFICE HLF CUP HALF COUPLING MANI FLD MANIFOLD PIPE P BEND PIPING BEND PSW,RED REDUCER tttttttttttttttttttttttttttttttttttttttttttttttttttttttttt 44t4444440444444444444444+
444444t4t4f44f4 PRISIM MPANY PAGE 25 REVISION RRS1 DATE 85/12/04 4444444444444444444444440444t@4I 444t4444444444444f44444044444 NUTECH CAROLINA POWER 8 LIGHT CO SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES 44444444$444444444444444444444444444444fay f 444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PSW, RIN RED INS REDUCING INSERT PSW,T PSW,TR PSW,UN PSW,VLV TEE RED TEE REDUCING TEE UNION VALVE 44444444444444444444444444444444444444444f44444444444444444f44444444444f44f


w+4444444%484844444444444404444404tf444440444444444f444444 44f444444t444ff NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: COMPDES PAGE='26 REVISION RRS 1 DATE 85/12/04 4044444444f44444444404t444444f444444444t404444440404444t440440 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION RAKUSP+++++++++++++++
m~4'4444444444444444444444444444444444444444444'044444444444      44t44444t444444 NUTECH                                                               PRI SIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REF ERENCE CLUSTER LISTING               444444444444444444 DATA ELEMENT : ITEMNO                    PAGE       , 137 REVISION   RRS1 DATE   85/12/05 4444444f4044444444444444 REFERENCE KEY                               DESCRIPTION 81W-01C6. 1    +++PUMPS+++
PWR REACTOR VESSEL INTERNALS+++++++++++++++
81W-01C6. 10    PUMP CASING WELDS 81W-01C6. 2    +++VALVES+++
+EXAMINATION CATEGORIES 8-N-1 AN B-N-2 (81W)+AKUSP ALIGNMENT KEYWAYS UPPER SUPPORT PLATE RAP RBBBC RCBFFN RCBMPGW RCBNVIS RCRDGT RCRODS RCSC ACC PLT ACCESS PLATE BBBC BAFFLE BOLTING AND BAFFLE CORNERS CBFFN CORE BARREL FLANGE FLOW NOZZLES CBMPGW CORE BARREL MID-PLANE GIRTH WELD CBNVIS CORE BARREL OUTLET NOZZLE/VESSEL INTERFACE SURFACE CRDGT CONTROL ROD DRIVE GUIDE TUBE (INTERNAL INSPECTION OF GUIDE TUBE)CRODS CONTROL RODS CSC CORE SUPPORT COLUMN 48444t444fkt444444444444444440444t404t444444444444444444f444444444444444404 0
81W-01C6.20    VALVE BODY WELDS 8 IW-01C7.      +++EXAMINATION CATEGORY C-H+++
44444444484444444444444t44444444444404444444444444044444 444444f40444f44 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 0444444444444444 DATA ELEMENT: COMPDES PAGE 27 REVISION RRS1 DATE B5/12/04 444444444444444444444444444444444444444044444444444444444444444444444444444 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION RCSPACB RCSS RFTCBW RGTAUCP RHAVAP RIGC RINT RISB RLCP RLCPFAP CSPACB CORE SUPPORT PLATE ATTACHMENTS TO CORE BARREL CSS CORE SUPPORT STRUCTURES FTCBW FLANGE TO CORE BARREL WELD GTAUCP GUIDE TUBE ATTACHMENTS TO UPPER CORE PLATE HAVAP HEAD 8 VESSEL ALIGNMENT PINS (MATING SURFACES 8 ATTACHMENTS)
81W-01C7. EX    EXEMPT CLASS 2 PRESSURE RETAINING COMPONENTS
IGC INSTRUMENT GUIDE COLUMNS INT SUR INTERIOR SURFACE ISB IRRADIATION SPECIMEN BASKETS LCP LOWER CORE PLATE LCPFAP LOWER CORE PLATE FUEL ALIGNMENT PINS 44444444f444444f4444t444444444ff44fff4444444f44444444444t4444444444f4444444
: 1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
.
: 2) EXEMPT CLASS 2 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.     (E.G. WELDS <= 4" NPS) 81W-01C7. 1    +++PRESSURE  VESSELS+++
444444444444444444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SYSTEM 444444444444444'4444444444444444 444444444444444 PRIS(M REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: COMPDES PAGE" 28 REVISION RRS 1 DATE 85/12/04 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION RLCSC RLCSCB RLSC RNPLS RRCCADS RRCCAHS RRS/LCS RSCSA RTC RTFM LCSC LOWER CORE SUPPORT COLUMNS LCSCB LOWER CORE SUPPORT COLUMN BOLTING LSC LOWER SUPPORT COLUMNS NPLS NEUTRON PANEL LOCKING SCREWS RCCADS ROD CLUSTER CONTROL ASSEMBLY (RCCA)DRIVE SHAFTS RCCAHS ROD CLUSTER CONTROL ASSEMBLY (RCCA)HUBS/SPIDERS RS/LCS RADIAL SUPPORTS/LOWER CORE SUPPORTS SCSA SECONDARY CORE SUPPORT ASSEMBLY TC THERMOCOUPLE CONDUITS TFM THERMOCOUPLES AND FLOW MIXERS 444444444444444444444444444444440444f444f44tf4tffff4444t44444444f400t44ftf4 44444448%4444444444444444444444444404t444444 NUTECH REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES St44444t4444444444444444ff44444444444444444444 PRISIM CAROLINA POWER&LIGHT COMPANY SYSTEM PAGE 29 REVISION RRS1 DATE 85/12/04 44440444444444444440444444444 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION RTSF RUCPAK RUCPFAP RUIAKCB RUSC RUSF TSF THERMAL SHIELD FLEXURES UCPAK UPPER CORE PLATE ALIGNMENT KEYWAYS UCPFAP UPPER CORE PLATE FUEL ALIGNMENT PINS UIAKC8 UPPER INTERNALS ALIGNMENT KEYS IN CORE 8ARREL USC UPPER SUPPORT COLUMNS USF UPPER SUPPORT FLANGE (LOCKING DEVICE WELDS)4444444444f4444444444444444tbt44f4444444f44444444444444444444444t4444444044 NUTECH tf44t4444t44t44444f4444444tff44444f4440444444+
81W-01C7. 10    PRESSURE  VESSEL PRESSURE  RETAINING COMPONENTS  OPERATIONAL 81W"01C7.20      PRESSURE  VESSEL PRESSURE RETAINING COMPONENTS  STATIC 81W-01C7. 3      +++PIPING+++
444444444444444 PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444444444444044 DATA ELEMENT: COMPDES PAGE, 30 REVISION RRS1 DATE 85/12/04 4444444444444444444444444440444044444444444t4444444044444444444 REFERENCE KEY BWR VESSEL INTERNAL COMPONENT DESCRIPTION SCORES SINT SINTBL SINTNBL+++++++++++++++
81W-01C7. 30    PIPING PRESSURE RETAINING    COMPONENTS  OPERATIONAL 81W-01C7. 40    PIPING PRESSURE RETAINING COMPONENTS  STATIC 81W-01C7. 5      +++PUMPS+++
BWR REACTOR VESSEL INTERNALS+++++++++++++++
44444444044444444444444444444444444444f4t44444444440444440444444f44444tf444
+EXAMINATION CATEGORIES 8-N-1 AND 8-N-3 (81W)CORESUP REACTOR VESSEL CORE SUPPORT STRUCTURE INT SUR REACTOR VESSEL INTERIOR SURFACES INTATCH REACTOR VESSEL INTERIOR ATTACHMENTS
-BELTLINE INTATCH REACTOR VESSEL INTERIOR ATTACHMENTS
-NON BELTLINE 4444444444444444444444444444444t404t4444t44444444f4444440444444t444404f4f44
+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM t REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: COMPDES PAGE 31 REVISION RRS1 t DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PWR PUMP COMPONENT DESCRIPTION TCHP1A TCHP1 8 TCHPlc TFLYWHL TIFEET TPUINT TPUMPCW TRCP TRCP1A+++++++++++++++++++++
PWR PUMPS+++++++++++++++++++++++++++
+EXAMINATION CATEGORIES B-M-1, B-M-2, AND C-G (81W)+CH PMPA CHARGING WATER PUMP A CH PMPB CHARGING WATER PUMP 8 CH PMPC CHARGING WATER PUMP C FLYWHL FLYWHEEL FEET PUMP SUPPORT FEET PUMP INT PUMP INTERNALS PUMPCW PUMP CASING WELD RC PMP REACTOR COOLANT PUMP RC PMPA REACTOR COOLANT PUMP A
+44f4f4444444444444 NUTECH 44444444444444444444444444444404444444 444844444484044 PRISIM REFERENCE CLUSTER LISTING 444440444044444444 DATA ELEMENT: COMPDES PAGE" 32 REVISION RRS1 DATE 85/12/04 CAROLINA POWER 8 LIGHT COMPANY SYSTEM 444444444444444444444444444444444444444444440444444444444444040444444444444 REFERENCE KEY PWR PUMP COMPONENT DESCRIPTION TRCP1B TRCPlc TRHP1A TRHPlB TRSP1A TRSP1B TRSP1C TRSP10 TSRCP RC PMPB REACTOR COOLANT PUMP B RC PMPC REACTOR COOLANT PUMP C RH PMPA RESIDUAL HEAT REMOVAL PUMP A RH PMPB RESIDUAL HEAT REMOVAL PUMP B RS PMPA RECIRCULATION SPRAY PUMP A RS PMPB RECIRCULATION SPRAY PUMP B RS PMPC RECIRCULATION SPRAY PUMP C RS PMPD RECIRCULATION SPRAY PUMP D S RCP SUPPORT, REACTOR COOLANT PUMP 444t4444444444f44f4tkf4f4404444444444444444444444t40444044 NUTECH 4444444444444444444 4444444444444t444t44t44ftf4f4
+44f44f444444444 PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: COMPDES PAGE 33 REVISION RRS1 DATE BS/12/04 444'4f4444t4444444444444tkf444444444444f4444444444444444 REFERENCE KEY BWR PUMP COMPONENT DESCRIPTION UCSP1A UCSP1B UCSP1C UCSP1D UHPB UHPCS UHPM UPUHL UPUINT+++++++++++++++++++++++
BWR PUMPS+++++++++++++++++++++++++++
+EXAMINATION CATEGORIES B-M-1, B-M-2, AND C-G (81W)+CS PMPA CORE SPRAY PUMP A CS PMPB CORE SPRAY PUMP B CS PMPC CORE SPRAY PUMP C CS PMPD CORE SPRAY PUMP D HP 800S HIGH PRESSURE COOLANT INJECTION BOOSTER PUMP HPCS HIGH PRESSURE CORE SPRAY HP MAIN HIGH PRESSURE COOLANT INJECTION MAIN PUMP PUMPHL PUMP HANGER LUGS PUMP INT PUMP INTERNALS 444444444444444444444444444444444444444440444444444444444444444444444444444 C4 44 4444 NUTECH 44444444444444444444444044444444444444444444404+
444444444444444 PRI SIM CAROLINA POWER a LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444404444 DATA ELEMENT: COMPDES PAGE , 34 REVISION RRS 1 DATE 85/12/04 4444444444444444444444444t44444444404440444444444t44444 REFERENCE KEY BWR PUMP COMPONENT DESCRIPTION UPUMPCW URCIC URHP1A URHP1B URHP 1 c URHP1D URRP1A URRP1B USLP1A USLP1B PUMPCW PUMP CASING WELD RCIC REACTOR CORE ISOLATION COOLING PUMP RH PMPA RESIDUAL HEAT REMOVAL PUMP A RH PMPB RESIDUAL HEAT REMOVAL PUMP B RH PMPC RESIDUAL HEAT REMOVAL PUMP C RH PMPD RESIDUAL HEAT REMOVAL PUMP D RR PMPA REACTOR RECIRCULATION PUMP A RR PMPB REACTOR RECIRCULATION PUMP 8 SL PMPA STANDBY LIQUID CONTROL PUMP A SL PMPB STANDBY LIQUID CONTROL PUMP B t eeeeee44444444t44444444ft44t4444ekee444444444ekff4444444444444444t444444444 f ttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt t NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM t t REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: COMPDES PAGE...35 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
COMPONENT DESCRIPTION VAT1A VAT18 VAT1C VCHVP VCHW VCLADH VCLADV VCRDHW VCRDTVW++++++++++++++++++++
PWR PRESSURE VESSELS++++++++++++++++++++
+EXAMINATION CATEGORIES B-A, B-B, B-C, B-E, B-H, B-O, C-A++C-8 AND C-C (81W)+A TANKA ACCUMULATOR TANK A A TANKB ACCUMULATOR TANK 8 A TANKC ACCUMULATOR TANK C CHVP CLOSURE HEAD VENT PENETRATION C HEAD CIRCUMFERENTIAL HEAD WELD CLAD HD CLADDING, HEAD CLAD VS CLADDING, VESSEL CRDHW CONTROL ROD DRIVE HOUSING WELD CRDTVW CONTROL ROD DRIVE TO VESSEL WELD ttttttttttttttttttttttttt NUTECH tttttttttttttttttttttttttttttt tttttttttttttttt PRISIM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES PAGE 36 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
COMPONENT DESCRIPTION VCSW VELHE VFTHW VFTSW VHTRPEN VI, VI, LUG VI,PSB VI.PSC VI, SGSW VI,SR C SHELL CIRCUMFERENTIAL SHELL WELD ELHE EXCESS LETDOWN HEAT EXCHANGER FTHW FLANGE TO HEAD WELD FTSW FLANGE TO SHELL WELD HTR PEN HEATER PENETRATIONS (PRESSURIZER)
+++INTEGRALLY WELDED ATTACHMENT
+++LUG PZR SUP BR PRESSURIZER SUPPORT BRACKET PZR COL PRESSURIZER SUPPORT COLLAR SGSW STEAM GENERATOR SUPPORT WELD SADDLE SADDLE REINFORCEMENT (NOZZLE, TRUNION, ETC.)
+~444444444444444444444444444444444444444444444t4444444444+
444444444404444 NUTECH PRISIM CAROLINA POWER&LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 44444444444t 0 0 44 44 DATA ELEMENT: COMPDES PAGE,-37 REVISION RRS1 DATE 85/12/04 44444444440444444404444f4404404444444f4444444f444ff44404444t44t4 REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
COMPONENT DESCRIPTION VI~STAN VI, STVW VI, SWP VI o TRUN VI,WSUP VICINOZ VINT VLSW VMHW VMTHW STANCHN STANCHION SKIRT SKIRT TO VESSEL WELD WELDPAD SUPPORT WELD PAO TRUNNON TRUNNION PLATE WELDED SUPPORT PLATE ICI NOZ IN-CORE INSTRUMENTATION NOZZLES INT SUR VESSEL INTERIOR SURFACE L SHELL LONGITUDINAL SHELL WELD M HEAD MERIDIONAL HEAD WELD MANWAY MANWAY TO HEAD WELD (CIRCUMFERENTIAL WELD)t44t444f44444444f44444444444444444444444tff4444f444ft4444444444444444444f44


4444444f444444444444444t4444f44444444444444t444f$
444404444444444444444444444444444444444+
444444 4444444444444t4 NUTECH PRISIM CAROLINA POWER 8, LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444444444444444 4 DATA ELEMENT: COMPDES PAGE=,38 REVISION, RRS1 DATE 85/12/04 efee44444444004444444f444f444t444044444444f44f444444f4444f4444440444ftf44ff REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
NUTECH                                                                 PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT      1 PLANNING REFERENCE CLUSTER LISTING                 444444444444404444 DATA ELEMENT : ITEMNO                      PAGE         138 REVISION   'RS1 4 DATE   85/12/05 4444444t444t44t444444t4444444444444444f444f444444444f4444 REFERENCE KEY                             DESCRIPTION 81W-01C7.50    PUMPS PRESSURE  RETAINING COMPONENTS  -   OPERATIONAL 81W-01C7.60    PUMPS PRESSURE  RETAINING COMPONENTS  -   STATIC 81W-01C7. 7    +++VALVES+++
COMPONENT DESCRIPTION VNIR VNIR---VNIR1AI VNIR1BI VNIR1CI VNIR3AO VNIR3BO VNI R3CO VNOZ VNOZ---NIR NOZZLE INNER RADIUS NIR NIR---;WHERE NIR INDICATES NOZZLE INNER RADIUS AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG.NIR1AO IS NOZZLE 1A, OUTLET NIR3BI IS NOZZLE 38, INLET NIR1AI NOZZLE 1A (INLET)INNER RADIUS NIR1BI NOZZLE 1B (INLET)INNER RADIUS NIR1CI NOZZI.E 1C (INLET)INNER RADIUS NIR3AO NOZZLE 3A (OUTLET)INNER RADIUS NIR3BO NOZZLE 3B (OUTLET)INNER RADIUS NIR3CO NOZZLE 3C (OUTLET)INNER RADIUS NOZZLE NOZZLE NOZ---;WHERE NOZ INDICATES A VESSEL NOZZLE AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG.NOZIAO IS NOZZLE 1A, OUTLET NOZ3BI IS NOZZLE 3B, INLET 444444444444444444t4t.0444444f444ff4ff444f444f4f444444f44444444 44444444444444t44 s44444444444tt44 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444404444444444 DATA ELEMENT: COMPDES PAGE,-39 s REVISION RRS1 e 4 DATE 85/12/04 4444444444444444444444C4444440444444444444444444444444444444444444444444444 REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
81W-01C7.70    VALVES PRESSURE  RETAINING COMPONENTS  OPERATIONAL 81W-01C7.80    VALVES PRESSURE  RETAINING COMPONENTS    - STATIC 81W-01D1        +++EXAMINATION CATEGORY 0-A+++
COMPONENT DESCRIPTION VNOZ1A I VNOZ1AO VNOZ1BI VN02180 VNOZ1CI VNOZ1CO VNOZ1XI VNOZ1XO VNOZ3AI VNOZ3AO NOZ1AI NOZZLE 1A (INLET)NOZ1AO NOZZLE 1A (OUTLET)NOZ1BI NOZZLE 18 (INLET)NOZ180 NOZZLE 18 (OUTLET)NOZ1CI NOZZLE 1C (INLET)NOZ1CO NOZZLE 1C (OUTLET)VNOZ1XI NOZZLE 1X (INLET)NOZ1XO NOZZLE 1X (OUTLET)NOZ3AI NOZZLE 3A (INLET)NOZ3AO NOZZLE 3A (OUTLET)444444444444444444444444444t444444444044404404f4404444f4444444444440444
81W-0101. 1    +++SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION+++
+444ff44f444f4444f4f4444f44f44f44f44444444f44444tf44f444+
81W-01D1. 1EX  EXEMPT CLASS 3 CATEGORY D-A PRESSURE RETAINING COMPONENTS
4t4444ft4444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES PAGE;, 40 REVISION RRS1 4 DATE 85/12/04 444444444444444444444444444444444f444f4444444444t4444444444444444444444f4t4 REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
: 1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
COMPONENT DESCRIPTION VNOZ3BI VNOZ380 VNOZ3CI VNOZ3CO VNRHE VNTHW VNTHWI VNTHWO VNTVW VNTVWI NOZ38I NOZZLE 38 (INLET)NOZ380 NOZZLE 38 (OUTLET)NOZ3CI NOZZLE 3C (INLET)NOZ3CO NOZZLE 3C (OUTLET)NRHE NON-REGENERATIVE HEAT EXCHANGER NOZZLE NOZZLE TO HEAD WELD NOZZLE NOZZLE TO HEAD WELD (INLET)NOZZLE NOZZLE TO HEAD WELD (OUTLET)NOZZLE NOZZLE TO VESSEL WELD NOZZLE NOZZLE TO VESSEL WELD (INLET)44444'4t44f44444ff444444444ft4444440444f4444444444444444440444f444fftf
: 2) EXEMPT CLASS 3 COMPONENTS ENTEREO IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.     (E.G. <= 4" PIPE ATACHES) 81W-01D1. 100  RV SHUTDOWN PRESSURE    RETAINING COMPONENTS    - OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL. A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.
~~444444444444444444044444444444444444444444444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES 444444044444444 PRISIM'4 PAGE-<<41 REVISION RRS1 0 DATE BB/12/04 REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
OPERATIONAL: SYS FUNCTIONAL, SYS INSERVICE, OR SYS LEAKAGE 81W-01D1 . 10S  RV SHUTDOWN PRESSURE    RETAINING COMPONENTS  STATIC A SYSTEM   STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL.
COMPONENT DESCRIPTION VNTVWO VPRZ VRCF VREPAIR VRHE VRH1A VRH18 VRS1A VRS18 VRS1C NOZZLE NOZZLE TO VESSEL WELD (OUTLET)PRZ PRESSURIZER RCFILTR REACTOR COOLANT FILTER REPAIR REPAIR AREA IN BELTLINE REGION ONLY RHE REGENERATIVE HEAT EXCHANGER RH HX A RESIDUAL HEAT REMOVAL HEAT EXCHANGER A RH HX 8 RESIDUAL HEAT REMOVAL HEAT EXCHANGER 8 RS CLRA RECIRCULATION SPRAY COOLER A RS CLRB RECIRCULATION SPRAY COOLER 8 RS CLRC RECIRCULATION SPRAY COOLER C 44f4440f444f404444444444f444444f0444444444444444444444044444f44444444444
STATIC: HYDROSTATIC OR PNEUMATIC 444444444444444444444444444t4444444444444444444444444444444444444444t444444


444444440444ff4444444f44444t4f44f4444444f4f44444444f4f44 4f44t4044444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 44t444444444444444 DATA ELEMENT: COMPDES PAGE ,42 REVISION RRS1 DATE 85/12/04 4$44444444f444f4444444444448404404444044444f0440f4444f4444f4f4tf444444tfftt REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
+  sttttttttttttttttttttttttttttttttttttttttttttt,tttttttttt tttttttttttttt NUTECH                                                             PRISIM CAROLINA POWER 8 LIGHT COMPANY t            SHEARON HARRIS NUCLEAR POWER PLANT  UNIT ttttttttttttttttttt 1
COMPONENT DESCRIPTION VRS10 VRV VSE VSGA VSGB VSGC VSG1A VSG1B VSG1C VSTHW VSWHE RS CLRC RECIRCULATION SPRAY COOLER D REACTOR REACTOR VESSEL SAFEEND SAFE END SGA STEAM GENERATOR A SGB STEAM GENERATOR B SGC STEAM GENERATOR C CHANGED TO VSGA CHANGED TO VSGB CHANGED TO VSGC STHW SHELL TO HEAD WELD SWHE SEAL WATER HEAT EXCHANGER 4444444444444444444444444t444tt44044444444444444t444444tkt4444404480t444444
PLANNING t                    REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                    PAGE       139 t                                                                REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                           DESCRIPTION 81W-0101 . 20  RV SHUTDOWN INTEGRAL ATTACHMENTS  SUPPORTS      AND RESTRAINTS 81W-0101 . 30  RV SHUTDOWN INTEGRAL ATTACHMENTS    -  SNUBBERS RV SHUTDOWN INTEGRAL ATTACHMENTS    -  MECHANICAL AND HYDRAULIC SNUBBERS 81W-01D1.40    RV SHUTDOWN INTEGRAL ATTACHMENTS  SPRING TYPE SUPPORTS 81W-0101. 50  RV SHUTDOWN INTEGRAL ATTACHMENTS-CONSTANT LOAD TYPE SUPPORTS 81W-0101. 60  RV SHUTDOWN INTEGRAL ATTACHMENTS    -  SHOCK ABSORBERS 8 1W-0102.    +++EXAMINATION CATEGORY D-8+++
81W-0102. 1    +++SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL+++
I 81W-0102. 1EX  EXEMPT CLASS 3 CATEGORY 0-B PRESSURE RETAINING COMPONENTS
: 1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
: 2) EXEMPT CLASS 3 COMPONENTS ENTERED IN THE4"DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.    (E.G. <=      PIPE ATACHES) 81W-01D2. 100  ECCS,  ETC. PRESSURE RETAINING COMPONENTS  OPERATIONAL AN OPERATIONAL PRESSURE  TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL. A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.
OPERATIONAL: SYS FUNCTIONAL, SYS INSERVICE OR SYS LEAKAGE
                                                              ~


NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM PAGE 43 REVISIONRRSl DATE 85/12/04 444444444444444440444444f44444 REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES 4444444444444044444t44444444t4t4444t44444
4444444444t44f4444444f44444444444444444      +44444444444444 NUTECH                                                               PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    -  UNIT 1 PLANNING                                        4 REFERENCE CLUSTER LISTING                  4440t44t44044444 DATA ELEMENT : ITEMNO                    PAGE         140 REVISION  RRS1 DATE 85/12/05 408004444444444444444444444444444444444444444444444444444444444444444444444 REFERENCE KEY                              DESCRIPTION 81W-01D2. 10S  ECCS,  ETC. PRESSURE RETAINING COMPONENTS  STATIC A SYSTEM  STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL.
+844t44444444444444444t444444f4448444444f44444444f444444 444444444444f44 REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS)
STATIC: HYDROSTATIC OR PNEUMATIC 81W-01D2. 20    ECCS,  ETC. INTEGRAL ATTACHMENTS  -  SUPPORTS  AND RESTRAINTS 81W-01D2.30    ECCS,  ETC. INTEGRAL ATTACHMENTS  SNUBBERS ECCS, ETC. INTEGRAL ATTACHMENTS  -  MECHANICAL AND HYDRAULIC SNUBBERS 81W-0102.40    ECCS,  ETC. INTEGRAL ATTACHMENTS  SPRING TYPE SUPPORTS 81W-01D2.50    ECCS,  ETC. INTEGRAL ATTACHMENTS    - CONSTANT LOAD TYPE SUPPORT 81W-01D2.60    ECCS,  ETC. INTEGRAL ATTACHMENTS  SHOCK ABSORBERS 81W-0103.      +++EXAMINATION CATEGORY D-C+++
COMPONENT DESCRIPTION VSWIFA VSWIFB VSWRF VTSTHW VTSTVW VVCT SWIFA SEAL WATER INJECTION FILTER A SWIFB SEAL WATER INJECTION FILTER B SWRF SEAL WATER RETURN FILTER TSTHW TUBE SHEET TO HEAD WELD TSTVW TUBE SHEET TO VESSEL WELD VC TANK VOLUME CONTROL TANK 4444t44444444444444444f4444444444444f444444f4444444444444444444404444404444
81W-0103. 1    +++SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM THE SPENT FUEL STORAGE POOL+++
81W-01D3. 1EX  EXEMPT CLASS 3 CATEGORY D-C PRESSURE RETAINING COMPONENTS
: 1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY'SSIGN THIS ITEM NUMBER.
: 2) EXEMPT CLASS 3 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.      (E.G. <= 4" PIPE ATACHES) 4'4444444444444tf44444444444f4444ftffff44440


++444444t44ft444444444f4444444444444444444tf44444t44444444
444444444444444444444t444444444444      44444444444444 NUTECH                                                                 PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  - UNIT  1 PLANNING REFERENCE CLUSTER LISTING               444444444444440444 DATA ELEMENT : ITEMNO                    PAGE     . 141 REVISION   RRS1 DATE 85/12/05 4444444444444444f4f4f444f444ff444444f44f4ffOtf4f444444f444444444444ft44t4f4 REFERENCE KEY                               DESCRIPTION 81W-0103. 100      RHR FROM SFS  PRESSURE RETAINING COMPONENTS  OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL. A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.
+4444f44f4444444 4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4 4 4 4 4 4 4 4 4 4'4 4 4 4 4 4 4 4 4 DATA ELEMENT: COMPDES PAGE-.44 REVISION RRS1 DATE 85/12/04 444444444444444444404044444444f4444t444444444444f444444f444tkft4f0444440 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS)
OPERATIONAL: SYS FUNCTIONAL, SYS INSERVICE, OR SYS LEAKAGE 81W-0103. 10S      RHR FROM SFS  PRESSURE RETAINING COMPONENTS  STATIC A SYSTEM STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL.
COMPONENT DESCRIPTION WCHW WCLADH WCLADV WCRDHW WCRDTVW WCSW WFTHW WFTSW WI,++++++++++++++++++
STATIC: HYDROSTATIC OR PNEUMATIC 81W-01D3. 20      RHR FROM SFS  INTEGRAL ATTACHMENTS  SUPPORTS AND RESTRAINTS 8 1W-0 'I 03 . 30  RHR FROM SFS  INTEGRAL ATTACHMENTS  SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS  MECHANICAL AND HYDRAULIC SNUBBERS 81W-01D3. 40      RHR FROM SFS  INTEGRAL ATTACHMENTS  SPRING TYPE SUPPORTS 81W-01D3. 50      RHR FROM SFS  INTEGRAL ATTACHMENT-CONSTANT LOAD TYPE SUPPORTS 8 1W-01D3. 60      RHR FROM SFS  INTEGRAL ATTACHMENTS  - SHOCK ABSORBERS 81W-01E1.          +++EXAMINATION CATEGORY E-A+++
BWR PRESSURE VESSELS++++++++++++++++++++
81W-01E1.      1  +++PRESSURE  RETAINING WELDS IN CONTAINMENT VESSELS+++
+EXAMINATION CATEGORIES B-A, B-B, B-C, B-E, B-H, 8-0, C-A C-8 AND C-C (81W)+C HEAD CIRCUMFERENTIAL HEAD WELD CLAD HD CLADDING, HEAD CLAD VS CLADDING, VESSEL CRDHW CONTROL ROD DRIVE HOUSING WELD CRDTVW CONTROL ROD DRIVE TO VESSEL WELD C SHELL CIRCUMFERENTIAL SHELL WELD FTHW FLANGE TO HEAD WELD FTSW FLANGE TO SHELL WELD+++INTEGRALLY WELDED ATTACHMENT
4444444t4444444t444444444444f444f44ff444444tf44
+++444444t44444444$
4444f44444t4444444444444444444444t444444444444444444444$
44f


t NUTECH tttttttttttttttttttttttttttttttttttttt ttttttttttttttt PRISIM REFERENCE CLUSTER LISTING t t t t tt t t t t t t t t t t t t DATA ELEMENT: COMPDES PAGE 45 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS)
++'54444444444444444f 44444444444444444444444444444444444444        444444444444440 4  NUT ECH                                                                PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  - UNIT  1 PLANNING REFERENCE CLUSTER LISTING               4444444444444t444f DATA ELEMENT : ITEMNO                  PAGE       : 142 REVISION   RRS 1 DATE   85/12/05 44444444444444444444444404444404ir444444444444 REFERENCE     KEY                           DESCRIPTION 81W-01E1. 10        +++SHELL WELDS IN CONTAINMENT VESSELS+++
COMPONENT DESCRIPTION WI,LUG WI,SR WI, STAN LUG SADDLE SADDLE REINFORCEMENT (NOZZLE, TRUNION, ETC.)STANCHN STANCHION WI, STVW WI, SWP WI, TRUN WI CI NOZ WINT WLSW WMHW WN I R SKIRT SKIRT TO VESSEL WELD WELDPAD SUPPORT WELD PAD TRUNNON TRUNNION ICI NOZ IN-CORE INSTRUMENTATION NOZZLES INT SUR VESSEL INTERIOR SURFACE L SHELL LONGITUDINAL SHELL WELD M HEAD MERIDIONAL HEAD WELD NIR NOZZLE INNER RADIUS
81W-01E1. 11    LONGITUDINAL SHELL WELDS IN VESSELS (CATEGORY A) 81W-01E1. 12       CIRCUMFERENTIAL SHELL WELDS IN VESSELS (CATEGORY    8) 81W-01E1  . 20    FLANGE WELDS IN VESSELS  ( CATEGORY C) 81W-01E1. 30        NOZZLE-TO-SHELL WELDS IN VESSELS (CATEGORY D) 81W-01E1. 40        +++INSERT PLATE WELDS+++
+~44444444444444444444444444$
81W-01E1. 41        INSERT PLATE-TO-SHELL WELDS 81W-01E1. 42        LONGITUDINAL INSERT PLATE WELDS 81W-01E1. 43        CIRCUMFERENTIAL INSERT PLATE WELDS 81W-01E1. 50        +++VENT SYSTEM WELDS+++
44444f44444444f44444444444444 44444444t444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444404444444 DATA ELEMENT: COMPDES PAGE 46 REVISION RRSl DATE 85/12/04 44444444444t4044444444444t444444t4t444444t440444444444444444404444 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS)
81W"0 IE1. 51      LONGITUDINAL VENT SYSTEM WELDS 81W-01E1. 52        CIRCUMFERENTIAL VENT SYSTEM WELDS 81W-01E1. 53        OTHER VENT SYSTEM WELDS 81W-01E2.          +++EXAMINATION CATEGORY E-A-1+++
COMPONENT DESCRIPTION WNIR---WNIR3AI WNIR3BI WNIR4AO WNI R4BO WNOZ WNOZ---WN023AI WN023BI WN024AO WN02480 NIR---NIR---;WHERE NIR INDICATES NOZZLE INNER RADIUS AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG.NIR1AO IS NOZZLE 1A, OUTLET NIR3BI IS NOZZLE 3B, INLET NOZZLE INNER RADIUS-NOZZLE 3A, INLET NOZZLE INNER RADIUS-NOZZLE 3B, INLET NOZZLE INNER RADIUS-NOZZLE 4A, OUTLET NOZZLE INNER RADIUS-N022LE 4B, OUTLET NOZZLE NOZZLE N02---;WHERE NOZ INDICATES A VESSEL NOZZLE AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG.N021AO IS N022LE 1A, OUTLET N023BI IS NOZZLE 38, INLET VESSEL NOZZLE-N022LE 3A, INLET VESSEL NOZZLE-NOZZLE 3B, INLET VESSEL NOZZLE-NOZZLE 4A, OUTLET VESSEL NOZZLE-NOZZLE 4Be OUTLET 04444f444f44t444f44444ff4444444444%44444444444444
81W-01E2. 1      +++NONPRESSURE-RETAINING WELDS+++
+w4444444044444t4444044444444444444444440444444444'0444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES 4444444444444444444444444t4444444444444444444444444444444 PRISIM 444444444444444444 PAGE 47 REVISION.RRS1 DATE 85/12/04 444444444444444444 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS)
44444444t4444444f44t44f444444444t444444444t4444f44444tt4444444444444t444
COMPONENT DESCRIPTION WNTHW WNTS WNTVW WNTVWI WNTVWO WREPAIR WRH I A WRH18 WRV WSE NOZZLE NOZZLE TO HEAD WELD TSLEEVE NOZZLE THERMAL SLEEVE NOZZLE NOZZLE TO VESSEL WELD NOZZLE NOZZLE TO VESSEL WELD (INLET)NOZZLE NOZZLE TO VESSEL WELD (OUTLET)REPAIR REPAIR AREA IN BELTLINE REGION ONLY RH HX A RESIDUAL HEAT REMOVAL HEAT EXCHANGER A RH HX 8 RESIDUAL HEAT REMOVAL HEAT EXCHANGER 8 REACTOR REACTOR VESSEL SAFEEND SAFE END 44ttf4444444f4444444444444tt4fff444444f4444444444444444ft4444444f444f444444


NUTECH 444444444444444444444444444404444444444444444 444444444444444 PRISIM CAROLINA POWER&LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: COMPDES PAGE 48 REVISION RRS1 DATE 85/12/04 444444444444444444044444444444444444444444444444444444444444444 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS)
44404f44t4t44f44444444444444    444440044444444 NUTECH                                                             PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT     - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO                  PAGE       143 REVISION   RRS 1 4044444444448444444444444444444444t44444444444t444t44t444 REFERENCE KEY                             DESCRIPTION 81W-01E2. 10    +++REINFORCING STRUCTURE WELDS+++
COMPONENT DESCRIPTION WSTHW WTSTVW STHW SHELL TO HEAD WELD TSTVW TUBE SHEET TO VESSEL WELD 4444t44444444444444f444t444444444t44ft444444444f444'4444t44f44444044f4440444 CATEGORY REFERENCE KEY: MHERE: Example-P01-01B-B P01-01 is the EXAM REQUIREMENT for PSI PSI is considered An Interval for computer purposes.P01=PSI program 01-01=Xnterval 01 B-B-" Section XX category NOTE: If a category has the same designation for program A and B the following method is employed: B-DA=CATEGORY B-D Program A B-DB=CATEGORY B-D Program B AUGMENTED programs are assigned category and item numbers to reflect, as close as possible the source of the exam requirement.
81W-01E2. 1 1   CONTAINMENT VESSEL ATTACHMENT REINFORCING STRUCTURE WELDS 81W-01E2. 12    OTHER REINFORCING STRUCTURE WELDS 81W-01E2. 20    REINFORCING STRUCTURE ATTACHMENT WELDS 81W-01E3.       +++EXAMINATION CATEGORY E-8+++
EXAMPLE: P04"01FSAR P04=PSI program number 04-01=Xnte val 01 FSAR=Source of examination requirement
81W-0163. 1    +++PRESSURE   RETAINING WELOS IN CONTAINMENT PENETRATIONS+++
'I+~444444444444444444444444444444444444404444t4440444444444 44444444444444t NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444
81W-01E3. 10    +++CONTAINMENT PENETRATION WELDS+++
'4 DATA ELEMENT: CATEGORY PAGE 18 REVISION RRS1 DATE 85/12/05 444444444444444444444444044444444444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 802"01RG1.
81W-01E3. 1  I LONGITUDINAL CONTAINMENT PENETRATION WELDS 81W-01E3. 12    CIRCUMFERENTIAL CONTAINMENT PENETRATION WELDS 81W-01E3. 13    FLUED HEAD AND BELLOWS SEAL CIRC WELDS JOINED TO THE PENET FLUED HEAD AND BELLOWS SEAL CIRCUMFERENTIAL WELDS JOINED TO THE PENETRATION.
14 REACTOR COOLANT PUMP FLYWHEEL INTEGRITY EXAMINATION 804-01FSAR 805-0'IFSAR 806-01FSAR P01-018-A Po 1-018-8 FINAL SAFETY ANALYSIS REPORT-SECTION 6.6.8, PARAGRAPHS 8 AND E.FINAL SAFETY ANALYSIS REPORT-SECTION 6.6.8, PARAGRAPHS C AND E.FINAL SAFETY ANALYSIS REPORT-SECTION 6.6.8, PARAGRAPHS D AND E.PRESSURE RETAINING WELDS IN REACTOR VESSEL PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV I PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS P01-018-DA P01-018-DB P01-018-E FULL PENETRATION WELDS OF NOZZLES IN VESSELS-PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS-PROGRAM 8 FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM 8 EXAMINATION CATEGORY 8-E IS NOT SUBJECT TO PSI 444444444444444f44f4444444444444f444t4f444t4444444444444f444$
81W-01E4.      +++EXAMINATION CATEGORY E-C+++
ffffff44444f
81W-01E4. 1    +++PRESSURE  RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES+++
81W-01E4. 10    +++AIRLOCK WELDS+++
444444444444444444444444444444444448444444444444444444444444444444444444444


4444444444444f44444ff44444444t44f4t044f44444444 NUTECH PRISIM 4 PAGE.19 REVISION RRSl DATE 85/12/05 44444444444044044444 CAROLINA POWER 1lLIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: CATEGORY 4444444444444444444444444444444044444444444444444444444 REFERENCE KEY DESCRIPTION P01-018-F P01-018-G-1 P01-018-G-2 P01-018-H P01-018-J P01-018-K-1 P01-018-L-1 P01-018-L-2 P01-018-M-1 P01-018-M-2 P01-018-N-1 P01-018-N-2 P01-018-N-3 P01-018-0 PRESSURE RETAINING DISSIMILAR METAL WELDS PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER INTEGRAL ATTACHMENTS FOR VESSELS PRESSURE RETAINING WELDS IN PIPING INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES PRESSURE RETAINING WELDS IN PUMP CASINGS PUMP CASINGS PRESSURE RETAINING WELDS IN VALVE BODIES VALVE BODIES INTERIOR OF REACTOR VESSEL RV INTEGRALLY WELDED CORE SUPPORTS AND ATTACHMENTS (BWR)I INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS (BWR)REMOVABLE CORE SUPPORT STRUCTURES (PWR)PRESSURE RETAINING WELDS IN CONTROL ROD HOUSING PRESSURE RETAINING WELDS IN PERIHERAL CONTROL ROD DRIVE HOUSING 444'4444444444044t44444f444444f44440444444f444f444444444400444 4~444444444444444444f444444444444444404444444 NUTECH 4444444444444 44444444444444'4 PRISIM i 444444444444444444 PAGE ,20 REVISION RRS1 DATE 85/12/05 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: CATEGORY 444444f444444ttff4444tt44f44ftkf4444444fftt444444444t4'444t4 REFERENCE KEY DESCRIPTION P01-01B-P P01-01B-Q P01-01C-A P01-01C-B P01-01C-C P01-01C-D P01-01C-F P01-01C-G P01-01C-H P01-01D-A P01-01D-B P01-01D-C+++EXAMINATION CATEGORY 8-P IS NOT SUBJECT TO PSI++++++FOR STEAM GENERATOR TUBING, SEE PRISIM-SST+++
NUTECH                                                               PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT   1 PLANNING REFERENCE CLUSTER LISTING             tttttttttttttttttt DATA ELEMENT : ITEMNO                  PAGE       144 REVISION RRS 1 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttt        DATE REFERENCE KEY                               DESCRIPTION 81W-01E4. 11  LONGITUDINAL AIRLOCK WELDS 81W-01E4. 12       CIRCUMFERENTIAL AIRLOCK WELDS 81W-01E4. 20      +++EQUIPMENT HATCH WELDS+++
PRESSURE RETAINING WELDS IN PRESSURE VESSELS PRESSURE RETAINING NOZZLE WELDS IN VESSELS INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER PRESSURE RETAINING WELDS IN PIPING PRESSURE RETAINING WELDS IN PUMPS AND VALVES+++EXAMINATION CATEGORY C-H IS NOT SUBJECT TO PSI+++SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEAN-UP, AND REACTOR RESIDUAL HEAT REMOVAL SYSTEMS IN SUPPORT OF RHR FROM SPENT FUEL STORAGE POOL SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL 44444444444r4444448t444t4844444444444t44ttkf44444444444444444444 e
81W-01E4.21        LONGITUDINAL EQUIPMENT HATCH WELDS 81W-01E4. 22      CIRCUMFERENTIAL EQUIPMENT HATCH WELDS 81W"01ES.         +++EXAMINATION CATEGORY E-D+++
+444444444444004444444f444444444444044ft44444444ff44444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: CATEGORY 44444444444444t444444t4444444t444444444444444444444444444 PRISIM PAGE 21 REVISION RRS1 DATE 85/12/05 404444444444444444 REFERENCE KEY DESCRIPTION P01-01E-A P01-01E-A-1 P01-01E-B P01-01E-C P01-01E-D P01-01E-E P01-01E-F P01-01E-G P01-01E-P P01-01F-A P01-01F-B P01-01F-C PRESSURE RETAINING WELDS IN VESSELS NONPRESSURE-RETAINING WELDS PRESSURE RETAINING WELDS IN CONTAINMENT PENETRATIONS PRESSURE RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES SEALS AND GASKETS INTEGRAL ATTACHMENTS PRESSURE RETAINING DISSIMILAR METAL WELDS PRESSURE RETAINING BOLTING ALL PRESSURE RETAINING COMPONENTS PLATE AND SHELL TYPE SUPPORTS LINEAR TYPE SUPPORTS COMPONENT STANDARD SUPPORTS P02-01RG1.14 REACTOR COOLANT PUMP FLYWHEEL INTEGRITY EXAMINATION P03-01SER P04-01FSAR SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION FINAL SAFETY ANALYSIS REPORT-SECTION 6.6.8, PARAGRAPHS B AND E.4444tkt44f4444444ff44444404444444444444f44444444t4444044f44444
81W-01E5. 1   +++SEALS AND GASKETS+++
+4+4+4+4444444ff4444444444t444f444f4444444t444044'44t44444 NUTECH PR I SIM 444444444444444444 PAGE 22 REVISION RRS1 DATE 85/12/05 444444444444844444444444'44444444r44444444 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: CATEGORY REFERENCE KEY DESCRIPTION P05-01FSAR P06-01FSAR V01-01C-C 81W-018-A 81W-018-8 81W-018-DA 81W-018-DB 81W-018-E 81W-018-F 81W-018-G-1 FINAL SAFETY ANALYSIS REPORT-SECTION 6.6.8, PARAGRAPHS C AND E.FINAL SAFETY ANALYSIS REPORT-SECTION 6.6.8, PARAGRAPHS D AND E.INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS>AND VALVES PRESSURE RETAINING WELDS IN REACTOR VESSEL PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS FULL PENETRATION WELDS OF NOZZLES IN VESSELS-PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS-PROGRAM 8 I FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM 8 PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS PRESSURE RETAINING DISSIMILAR METAL WELDS PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 444444'4444tf44440444t44440444'44444440t444444444444444044 ee444444444f44444444444f4444f4444f444404444444444444444 444f4444f444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 4 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: CATEGORY PAGE 23 REVISION RRS1 DATE 85/12/05 44444444444f4444444444444444444044f44444444tff444444444f44444 REFERENCE KEY DESCRIPTION 81W-018-G-2 81W-018-H 81W-01 8-J 81W-018-K-1 81W-018-L-1 81W-018-L-2 81W-018-M-1 81W-018-M-2 81W-018-N-1 81W-018-N-2 81W-018-N-3 81W 018 0 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER INTEGRAL ATTACHMENTS FOR VESSELS PRESSURE RETAINING WELDS IN PIPING INTEGRAL ATTACHMENTS FOR PIPING, PUMPS>AND VALVES PRESSURE RETAINING WELDS IN PUMP CASINGS PUMP CASINGS PRESSURE RETAINING WELDS IN VALVE BODIES VALVE BODIES INTERIOR OF REACTOR VESSEL RV INTEGRALLY WELDED CORE SUPPORTS AND ATTACHMENTS (BWR)INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS (BWR)REMOVABLE CORE SUPPORT STRUCTURES (PWR)PRESSURE RETAINING WELDS IN CONTROL ROD HOUSING, PRESSURE RETAINING WELDS IN PERIHERAL CONTROL ROD DRIVE HOUSING 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: CATEGORY PAGE"--24 REVISION RRS 1 DATE 85/12/05 4444444444444444444404444440444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 81W-018-P 81W-01B-Q 81W-01C-A 81W-01C-B 81W-01C-C 81W-01C-D 81W-01C-F 81W-01C-G 81W-01C-H 81W-010-A 81W-010-B 81W-01D" C ALL PRESSURE RETAINING COMPONENTS
81W-01ES. 10       SEALS 81W-01E5. 20       GASKETS 81W-01E6.         +++EXAMINATION CATEGORY E-E+++
+++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T+++
81W-01E6. 1   +++INTEGRAL ATTACHMENTS+++
PRESSURE RETAINING WELDS IN PRESSURE VESSELS PRESSURE RETAINING NOZZLE WELDS IN VESSELS INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER PRESSURE RETAINING WELDS IN PIPING PRESSURE RETAINING WELDS IN PUMPS AND VALVES ALL PRESSURE RETAINING COMPONENTS SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ECCS, CHR, ACU~AND RHR SUPPORT SYSTEMS SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEAN-UP, AND REACTOR RESIDUAL HEAT REMOVAL SYSTEMS IN SUPPORT OF RHR FROM SPENT FUEL STORAGE POOL SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL 444t444444444444444tkt444f444444444444444444444f444444t4444444444444f
81W-01E6. 10       INTEGRAL ATTACHMENT WELDS 8 1W-0 I Ej .     +++EXAMINATION CATEGORY E-F+++
+44444444t444444'440440f44444tt4f4444444f4444f4444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: CATEGORY 4444404f44f'4444 PRI SIM UNIT 1 4I 44044404444444t444 PAGE 25 REVI SION RRS 1 DATE 85/12/05 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 4 4 4 O4 4 4 4 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 REFERENCE KEY DESCRIPTION 81W-01E-A PRESSURE RETAINING WELDS IN VESSELS 81W-01E-A-1 NONPRESSURE-RETAINING WELDS 81W-01E-8 81W-01E-C 81W-01E-0 81W-01E-E 81W-01E-F 81W-01E-G 81W-0 IE-P 81W-01F-A 81W-0'1 F-8 81W-01F-C PRESSURE RETAINING WELDS IN CONTAINMENT PENETRATIONS PRESSURE RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES SEALS AND GASKETS INTEGRAL ATTACHMENTS PRESSURE RETAINING DISSIMILAR METAL WELDS PRESSURE RETAINING BOLTING ALL PRESSURE RETAINING COMPONENTS PLATE AND SHELL TYPE SUPPORTS LINEAR TYPE SUPPORTS COMPONENT STANDARD SUPPORTS 4444444444ff4444f444444f44444444444444f44444444tf444444444444 ITEM NO.REFERENCE KEY: MHERE: Example P01-01 B1.11 P01"01B1.11 P01"01 is the EXAM REQUIREMENT for PSI PSI program 01 Interval 01 is the Section XI Xtem Number AUGMENTED programs are assigned item numbers to reflect the location, as close as possible, of the exam requirement within the category.Example: For category P04-01FSAR one Item No.is P04-016.6.8B Mhere: POC-01 6.6.8B category PSI program 04 Interval 01 Paragraph number in"FSAR".
81W-01E7. 1   +++PRESSURE  RETAINING DISSIMILAR METAL WELDS+++
44t444444 444f44444444444
81W-01E7.     10 DISSIMILAR METAL WELDS
+~44444444%44f448884fggg44444444444444444444444 NUTECH PRISIM 444444444444444444 PAGE 87 REVISION RRS 1 DATE 85/12/05 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 444444444444444444444488444444+t4444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 802-0'I+++EXAMINATION CATEGORY RG1.14+++802-0180RE REACTOR COOLANT PUMP FLYWHEEL BORE-UT 802-01FLYWHL REACTOR COOLANT PUMP FLYWHEEL-SURFACE AND UT 802-01KEYWAY REACTOR COOLANT PUMP FLYWHEEL KEYWAY-UT 803-01 804-01+++EXAMINATION CATEGORY OPEN TO FUTUREUSE++++++EXAMINATION CATEGORY FSAR+++804-016.6.88 AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.88.(INSERVICE) 804-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.(INSERVICE) 805-01+++EXAMINATION CATEGORY FSAR+++805-016.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.8C.(INSERVICE) 805-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.(INSERVICE) 806" 0'1+++EXAMINATION CATEGORY FSAR+++806-016.6.BD AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8D.(INSERVICE) 4444844444444444404440tkt4444444444tttkt444444448444444404444444444r444 44444f444444444444044444444444444f4t44444444444fStd 44444ftt4444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRISIM 440444448444444444 PAGE.88 REVISION RRS 1 DATE 85/12/05 44444t444444044f4tt444444444440t44444t4444t44444444444 REFERENCE KEY DESCRIPTION 806-016.6.8E Po 1-0181 P01-0'I 81.P01-0181.10 P01-0181.11 P01-0181.12 P01-0181.20 P01-0181.21 Po 1-0181.22 Po 1-0181.228 Po 1-0181.30 P01-0181.40 P01-0181.50 AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.(INSERVICE)
+++EXAMINATION CATEGORY 8-A++++++REACTOR VESSEL++++++SHELL WELDS+++RV CIRCUMFERENTIAL SHELL WELDS RV LONGITUDINAL SHELL WELDS+++HEAD WELDS+++RV CIRCUMFERENTIAL HEAD WELDS RV MERIDIONAL HEAD WELDS RV MERIDIONAL BOTTOM HEAD WELDS RV MERIDIONAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL.RV SHELL-TO-FLANGE WELD RV HEAD-TO-FLANGE WELD+++REPAIR WELDS+++44444444444f44444444444444444444444f44444444444444444t44444444$
4444444f4444 PRISIM PAGE ,;.89 REVISION RRS1 DATE 85/12/05 444444t44ftt44444444444444444444444t444444444444t444444t NUTECH CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 4 4444444444444444444 44444t44444444444444f444444t4444444t44444444444t44444444 f4444444444444 REFERENCE KEY DESCRIPTION Po 1-0181.51 P01-0181.99 Po 1-01810 P01-01810.
1 RV BELTLINE REGION REPAIR WELDS+++ITEM NUMBERS 82.XX THROUGH 89.XX APPEAR AFTER 816.20++++++EXAMINATION CATEGORY 8-K-1++++++PIPING+++
P01-01810.10 PIPING INTEGRALLY WELDED ATTACHMENTS Po 1-01810.2+++PUMPS+++
P01-01810.20 PUMP INTEGRALLY WELDED ATTACHMENTS P01-01810.
3+++VALVES+++
P01-01810.
30 VALVE INTEGRALLY WELDED ATTACHMENTS P01-01812.
P01-01812.
1+++PUMPS+++
+++EXAMINATION CATEGORY 8-L-1+++P01-01812.
10 PUMP CASING WELDS P01-01812.
2+++EXAMINATION CATEGORY 8-L-2+++P01-01812.
20 PUMP CASING Po 1-01812.3+++EXAMINATION CATEGORY 8-M-1+++4 4 4 4 4 4 4 4 4 4 t4 4 4 f 4 4 4 4 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 f 4 4 0 4 4 4 4


s+s s s s s s s s s s s s NUTECH ssssssssssssssssssssssssssssssssssssss sssssssssssssss PRIS IM CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 s PLANNING REFERENCE CLUSTER LISTING ssssssssssssssssss DATA ELEMENT: ITEMNO PAGE-90 REVISION RRS 1 DATE 85/12/05 ssssssssssssssssssssssssssssssssssssssssssssfsssssssssssssssss REFERENCE KEY DESCRIPTION P01-01812.3A
  ~44444444444444444t4444444444t44444444444444444444444$    4   +4444444444444t NUTECH                                                               PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT   - UNIT 1 PLANNING REFERENCE CLUSTER LISTING               444444444444844444 DATA ELEMENT : ITEMNO                   PAGE         145 REVISION   RRS1 DATE   85/12/05 444444444t4ftt44t44444440tt4444444444444444r444044444tt044444t4444t REFERENCE KEY                               DESCRIPTION 81W-01EB.       +++EXAMINATION CATEGORY E-G+++
+++VALVES+++
81W-01EB. 1     +++PRESSURE  RETAINING BOLTING+++
P01-01812.30 VALVES, NOMINAL PIPE SIZE<4 IN.VALVE BODY WELDS Pol"01812.40 VALVES, NOMINAL PIPE SIZE>=4 IN.VALVE BODY WELDS P01-01812.
81W-01EB. 10     +++BOLTED CONNECTION VISUAL EXAMINATION+++
5+++EXAMINATION CATEGORY 8-M-2+++P01-01812.50 VALVE BODY, EXCEEDING 4 IN.NOMINAL PIPE SIZE P01-01813.
81W-01EB. 10A    BOLTED CONNECTION VISUAL EXAMINATION ALL VISIBLE SURFACES SHALL BE EXAMINED. BOLTING MAY REMAIN IN PLACE UNDER TENSION WHEN DISASSEMBLY IS NOT OTHERWISE REQUIRED.
Po 1-01813.1+++EXAMINATION CATEGORY 8-N-1++++++REACTOR VESSEL+++Po 1-01813.10 RV VESSEL INTERIOR P01-01813.
81W-01EB. 10D    BOLTED CONNECTION VISUAL EXAMINATION EXAMINATION OF BUSHINGS, THREADS, AND LIGAMENTS IN BASE MATERIAL OF FLANGES IS REQUIRED ONLY WHEN THE CONNECTION IS DISASSEMBLED.
2+++EXAMINATION CATEGORY 8-N-2+++P01-01813.
81W-01E8.20     +++BOLTED CONNECTION BOLT TORQUE OR TENSION TEST+++
2.+++REACTOR VESSEL (BWR)+++PO 1-01813.20 RV INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (BWR)P01-01813.21 RV INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (BWR)P01-01813.22 RV CORE SUPPORT STRUCTURE (BWR)P01-01813.
81W-01E8. 20A    BOLTED CONNECTION BOLT TORQUE OR TENSION TEST ALL VISIBLE SURFACES SHALL BE EXAMINED. BOLTING MAY REMAIN IN PLACE UNDER TENSION WHEN DISASSEMBLY IS NOT OTHERWISE REQUIRED.
3+++EXAMINATION CATEGORY 8" N-3+++P01-01813.
8 IW-01EB. 20D  BOLTED CONNECTION BOLT TORQUE OR TENSION TEST I
3.+++REACTOR VESSEL (PWR)+++s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s s st s s s e
EXAMINATION OF BUSHINGS, THREADS, AND LIGAMENTS IN BASE MATERIAL OF FLANGES IS REQUIRED ONLY WHEN THE CONNECTION IS DISASSEMBLED.
4~+4440444444444884888f044t0444444444f44444444444444444444 444444tkt444f4 NUTECH PRISIM CAROLINA POWER 6 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 4 PLANNING REFERENCE CLUSTER LISTING ee4444444444444404 DATA ELEMENT: ITEMNO PAGE 91 REVISION RRS1 DATE 85/12/05 44t444444404t4444444444t444444444444444444444444444404444444t444404 REFERENCE KEY DESCRIPTION P01-01813.30 INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (PWR)P01-01813.31 INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (PWR)P01-01813.32 RV CORE SUPPORT STRUCTURE (PWR)F01-01814.
4f4444f4444444444444444444444f4444444f44444444t4444ft4444444444444444444444
P01-01814.
1+++EXAMINATION CATEGORY 8-0++++++REACTOR VESSEL+++P01-01814.10 RV WELDS IN PERIPHERAL CRD HOUSING P01-01815.
P01-01816.
P01-01816.
1 P01-01816.
10 P01-01816.
20 P01-0182.P01-0182.1 P01-0182.10+++EXAMINATION CATEGORY 8-P IS NOT SUBJECT TO PSI++++++EXAMINATION CATEGORY B-Q++++++STEAM GENERATORS+++
+++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN STRAIGHT TUBE DESIGN++++++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN U-TUBE DESIGN++++++EXAMINATION CATEGORY 8-8++++++PRESSURIZER+++
+++SHELL-TO-HEAD WELDS+++4t4444444444444444f444444444444444444444444444444444f4444tt44444444444f4444 ttttt NUTECH tttttttttttttt ttttttttttttttt PRISIM PAGE'2 REVISION RRS1 t DATE 85/12/05 t CAROLINA POWER 1h LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO tttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION P01-0182.11 P01-0182.12 P01-0182.20 P01-0182.21 P01-0182.22 PO 1-0182.3 P01-0182.30 P01-0182.31 P01"0182.32 P01-0182.40 P01-0182.5 P01-0182.50 P01-0182.51 P01-0182.52 P01-0182.53 PZR CIRCUMFERENTIAL SHELL-TO-HEAD WELDS PZR LONGITUDINAL SHELL-TO-HEAD WELOS+++HEAD WELOS+++PZR CIRCUMFERENTIAL HEAD WELDS PZR MERIDIONAL HEAD WELDS+++STEAM GENERATORS (PRIMARY SIDE)++++++HEAD WELOS+++SG PRIMARY SIDE CIRCUMFERENTIAL HEAD WELDS SG PRIMARY SIDE MERIDIONAL HEAD WELDS SG PRIMARY SIDE TUBESHEET-TO-HEAD WELDS+++HEAT EXCHANGERS (PRIMARY SIDE)++++++SHELL(OR HEAD)WELDS+++HX PRIMARY SIDE CIRCUMFERENTIAL SHELL (OR HEAD)WELDS HX PRIMARY MERIDIONAL SHELL (OR HEAD)WELD HX PRIMARY LONGITUDINAL SHELL (OR HEAD)WELD PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: ITEMNO t PAGE 93 REVISION RRS 1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH~+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt REFERENCE KEY DESCRIPTION P01-0182.6 P01-0182.60 P01-0182.61 Po 1-0183 P01-0183.+++PROGRAM A 1ST INTERVAL 2ND INTERVAL 3RD INTERVAL 4TH INTERVAL REQUIREMENTS+++
3 YEARS 7 YEARS 13 YEARS 17 YEARS+++SHELL (PRIMARY SIDE)+++TUBESHEET-TO-SHELL (OR HEAD)WELDS TUBESHEET-TO-SHELL WELDS+++EXAMINATION CATEGORY 8-DA+++P01-0183.1+++REACTOR VESSEL+++P01-0183.10 RV NOZZLE-TO-VESSEL WELOS-PROGRAM A Pol-O'183.
20 RV NOZZLE INSIDE RADIUS SECTION-PROGRAM A Po 1-0183.3+++PRESSURIZER+++
Pol-0183.30 PRZ NOZZLE-TO-VESSEL WELDS-PROGRAM A P01-0183.40 PRZ NOZZLE INSIDE RADIUS SECTION-PROGRAM A Po 1-0183.5+++STEAM GENERATORS (PRIMARY SIDE)+++P01-0183.50 SG PRIMARY NOZZLE-TO-VESSEL WELDS-PROGRAM A tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH 444f444444f44444tf44444f44444404444444t4444f444 44444444444t444 PRI SIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444448444444 DATA ELEMENT: ITEMNO~PAGE 94 REVISION RRS1 DATE 85/12/05 444444t4440440'04t44444ttttftf404t4tt4tt444444t40f44 REFERENCE KEY DESCRIPTION P01-0183.60 SG PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM A P01-0183.7+++HEAT EXCHANGERS (PRIMARY SIDE)+++Pol"0183.70 HX PRIMARY NOZZLE-TO-VESSEL WELDS-PROGRAM A P01-0183.80 HX PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM A P01-0183.9+++EXAMINATION CATEGORY 8-DB+++Po 1-0183.9.+++PROGRAM 8 1ST INTERVAL 2ND INTERVAL 3RD INTERVAL 4TH INTERVAL REQUIREMENTS+++
'10 YEARS 10 YEARS 10 YEARS 10 YEARS POl-0183.9A+++REACTOR VESSEL+++Po 1-0183.98 P01-0183.9S RV NOZZLE-TO-VESSEL WELDS, EXAM FROM NOZZLE BORE-PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.RV NOZZLE-TO-VESSEL WELDS, EXAM FROM RV SHELL-PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.44t444f4444444444444444f44444444444444444t4f444ft444444444t4444444444444444 e
+444444f44444440f4444444444444444444f444444444f444444f44 444f44f444f4f44 NUTECH CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRISIM 44t4444444t444f44f PAGE 95 REVISION RRS1 DATE 85/12/05~'444444t4444444444444444t44r44ft44444ttkt44444444444444444t44 REFERENCE KEY DESCRIPTION P01-0183.90 RV NOZZLE-TO-VESSEL WELDS-PROGRAM 8 P01-0183.100 RV NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 P01-0183.11+++PRESSURIZER+++
P01-0183.110 PZR NOZZLE-TO-VESSEL WELDS-PROGRAM 8 P01-0183.120 PZR NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 P01-0183.13+++STEAM GENERATORS (PRIMARY SIDE)+++P01-0183.130 SG PRIMARY NOZZLE-TO-VESSEL WELDS-PROGRAM 8 Po 1-0183.140 SG PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 Po 1-0183.15+++HEAT EXCHANGERS (PRIMARY SIDE)+++P01-0183.150 HX PRIMARY NOZZLE-TO-VESSEL WELDS PROGRAM 8 P01-0183.160 HX PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 Po 1-0184 P01-0184.11 P01-0184.12 P01-0184.13+++EXAMINATION CATEGORY 8-E IS NOT SUBJECT TO PSI+++VESSEL NOZZLE PARTIAL PENETRATION WELDS CONTROL ROD DPIVE NOZZLE PARTIAL PENETRATION WELDS INSTRUMENTATIMN NOZZLE PARTIAL PENETRATION WELDS 44444444444444t444444444444f4444t4f4444f44444444444444t 4++44t444444444444444444444444444444444444f44444444440444 NUTECH CAROLINA POWER 8 LIGHT COMPANY t SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4 DATA ELEMENT: ITEMNO PRISIM 444444444444444444 PAGE96 REVISION RRS 1 DATE 85/12/05 44444444444444444f44t44444444f444444444r4444444t44444t44444444444444t4444444 REFERENCE KEY DESCRIPTION P01-0184.20 PRZ HEATER PELETRATION WELDS P01-0185.+++EXAMINATION CATEGORY 8-F+++P01-0185.1+++REACTOR VESSEL+++Pol-0185.10 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS>=4 INCHES Pol-0185.20 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS<4 INCHES P01-0185.30 RV NOZZLE-TO-SAFE END SOCKET WELDS P01-0185.4+++PRESSURIZER+++
P01-0185.40 PZR NOMINAL PIPE SIZE>=4 IN.NOZZLE-TO-SAFE END BUTT WELDS POI-0185.50 PZR NOMINAL PIPE SIZE<4 IN.NOZZLE-TO-SAFE END BUTT WELDS Pol-0185.60 PZR NOZZLE-TO-SAFE END SOCKET WELDS P01-0185.7+++STEAM GENERATOR+++
P01-0185.70 SG NOMINAL PIPE SIZE>=4 IN.NOZZLE-TO-SAFE END BUTT WELDS P01-0185.80 SG NOMINAL PIPE SIZE<4 IN.NOZZLE-TO-SAFE END BUTT WELDS Pol-0185.90 SG NOZZLE-TO-SAFE END SOCKET WELDS P01-0185.10+++HEAT EXCHANGERS+++
eoeeeeeeeeeebeeeee44+eekebe4440444444t444444444444440444444t444444444444444
~+ttttttttttttttttttttttttttttttttttttttttttttttttttttttti ttttttttttttttt NUTECH PRISIM CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: ITEMNO PAGE , 97 REVISION RRS1 t DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION r P01-0185.100 HX NOMINAL PIPE SIZE>=4 IN.NOZZLE-TO-SAFE END BUTT WELOS P01-0185.110 HX NOMINAL PIPE SIZE<4 IN.NOZZLE-TO-SAFE END BUTT WELOS P01-0185.120 HX NOZZLE-TO-SAFE END SOCKET WELDS P01-0185.13+++PIPING+++
P01-0185.130 NOMINAL PIPE SIZE>=4 IN.DISSIMILAR METAL PIPING BUTT WELD P01-0185.140 NOMINAL PIPE SIZE<4 IN.DISSIMILAR METAL PIPING BUTT WELD P01-0185.150 DISSIMILAR METAL PIPING SOCKET WELOS P01-0186.P01-0186.1+++EXAMINATION CATEGORY 8-G-1++++++REACTOR VESSEL+++P01-0186.10 RV CLOSURE HEAD NUTS (>2")POI-0186.20 RV CLOSURE STUDS, IN PLACE (>2")P01-0186.30 RV CLOSURE STUDS, WHEN REMOVED (>2")P01"0186.40 RV THREADS IN FLANGE (>2")P01-0186.50 RV CLOSURE WASHERS, BUSHINGS (>2")P01-0186.6+++PRESSURIZER+++
44t,f44tf44f44444fft444444444444444444444444444444 444444444ff444t NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PAGE98~REVISION RRS1 DATE 85/12/05 8444444444444444844444444f4444444444044444444444444444444444444444444444044 REFERENCE KEY DESCRIPTION P01-0186.60 PZR BOLTS AND STUDS (>2")P01-0 186.70 PZR FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")P01-0186.80 PZR NUTS, BUSHINGS'ND WASHERS (>2")P01-0186.9+++STEAM GENERATORS+++
P01-0186.90 SG BOLTS AND STUDS (>2")P01-0186.100 SG FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")P01-0186.110 SG NUTS, BUSHINGS, AND WASHERS (>2")P01-0186.12+++HEAT EXCHANGERS++~
P01-0186.120 HX BOLTS AND STUDS (>2")P01-0186.130 HX FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")P01-0186.140 HX NUTS, BUSHINGS, AND WASHERS (>2")P01-0186.15+++PIPING+++
P01-0186.150 PIPING BOLTS AND STUDS (>2")P01-0186.160 PIPING FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")P01-0186.170 PIPING NUTS, BUSHINGS~AND WASHERS (>2")444444'4f044ff4444f444444444f44444444444444444444 444444444444444444 444444444444444444444f44444
+44440444444f44 PRISIM 444444440444444444 PAGE.99 REVISION RRS1 DATE 85/12/05 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 44444444484444444444444444444444444444444444444t&4444444444444444444'4444444 REFERENCE KEY DESCRIPTION P01-0186.18+++PUMPS+++
P01-0186.180 PUMP BOLTS AND STUDS (>2")P01-0186.190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")P01-0186.200 PUMP NUTS, BUSHINGS, AND WASHERS (>2")P01-0186.21+++VALVES+++
P01-0186.210 VALVE BOLTS AND STUDS (>2")P01-0186.220 VALVE FLANGE SURFACE WHEN CONNECTION DISIASSEMBLED
(>2")P01-0186.230 VALVE NUTS, BUSHINGS, AND WASHERS (>2")P01-0187.P01-0187.1 P01-0187.10 P01-0187.2 P01-0187.20 PO\-0187.3 P01-0187.30
+++EXAMINATION CATEGORY 8-G-2++++++REACTOR VESSEL+++REACTOR VESSEL BOLTS, STUDS, AND NUTS (<=2")+++PRESSURIZER+++
PRESSURIZER BOLTS, STUDS, AND NUTS (<=2")+++STEAM GENERATORS+++
STEAM GENERATOR BOLTS, STUDS, AND NUTS (<=2")444444f4444444f4444444t44f44444444tkf444444ft44444444444444444444f4444 tttttttttttttttttttttttttttttttttttt NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO ttttttttttttttt PRISIM tttttttttttttttttt PAGE ,100 t REVISION RRSl DATE 85/12/05 t t t t t t tt t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t REFERENCE KEY DESCRIPTION Pol-O'187.4 P01-0187.40 Po 1-0187.5 P01-0187.50 Po 1-0187.6 Po 1-0187.60 P01-0187.7 P01-0187.70 Po 1-0187.8 P01-0187.80 P01-0188.P01-0188.1 P01-0188.10 P01-0188.2 P01-0188.20+++HEAT EXCHANGERS+++
HEAT EXCHANGER BOLTS, STUDS, AND NUTS (<=2")+++PIPING+++
PIPING BOLTS, STUDS, AND NUTS (<=2")+++PUMPS+++
PUMP BOLTS, STUDS, AND NUTS (<=2")+++VAIVFS+++
VALVE BOLTS>STUDS, AND NUTS (<=2")+++CRD HOUSING+++
CRD HOUSING BOLTS, STUDS, AND NUTS (<=2")+++EXAMINATION CATEGORY 8-H++++++REACTOR VESSEL+++RV INTEGRALLY WELDED ATTACHMENTS
+++PRESSURIZER+++
PZR INTEGRALLY WELDED ATTACHMENTS t t t t t t t t t t t t t t t t 4 t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t PRI SIM PAGE,,l 01 REVISION RRS1 DATE 85/12/05 444444444004444444'4444444444440444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 44444444444444444444444444444444444444444 0++44f4444444f444f44444444444444444444444444t44444f44t44t4
+44044444444f44 REFERENCE KEY DESCRIPTION P01-0188.3
+++STEAM GENERATORS+++
P01-0188.30 SG INTEGRALLY WELDED ATTACHMENTS PO 1-0188.4+++HEAT EXCHANGERS+++
P01-0188.40 HX INTEGRALLY WELDED ATTACHMENTS P01-0189.+++EXAMINATION CATEGORY 8-J+++P01-0189.1 F0 1-0189.10+++PIPING+++
+++NOMINAL PIPE SIZE>=4 IN.+++P01-0189.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE>=4 IN.P01-0189.12 LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE>=4 IN.P01-0189.20
+++PIPING NOMINAL PIPE SIZE<4 IN.+++P01-0189.21 CIRCUMFERENTIAL WELOS IN PIPING, NOMINAL PIPE SIZE<4 IN.P01-0189.22 LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE<4 IN.P01-0189.30
+++BRANCH PIPE CONNECTION WELDS+++P01-0189.31 BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE>=4 IN.P01-0189.32 BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE<4 IN.4444444444f4444440444fft4444444444f444444ff44444444444444444440ff44 a~tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PAGE 102 REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION P01-0189.40 P01-0189.99 P01-01C1.P01-01C1.1 P01-01C1.10 P01-01C'I.20 P01-01C1.30 P01-01C2.P01-01C2.1 P01-01C2.10 P01-01C2.'I 1 P01-01C2.20 P01-01C2.21 P01-01C2.22 P01-01C2.30 PIPE SOCKET WELDS+++ITEM NUMBERS 810.XX THROUGH 816.XX APPEAR AFTER 81.51++++++EXAMINATION CATEGORY C-A++++++PRESSURE VESSELS+++
PRESSURE VESSEL SHELL CIRCUMFERENTIAL WELDS PRESSURE VESSEL HEAD CIRCUMFERENTIAL WELDS PRESSURE VESSEL TUBESHEET-TO-SHELL WELD+++EXAMINATION CATEGORY C-8++++++PRESSURE VESSELS+++
+++NOZZLES IN VESSELS<=1/2 IN.NOMINAL THICKNESS+++
NOZZLES-TO-SHELL(OR HEAD)WELD+++NOZZLES WITHOUT REINFORCING PlATE IN VESSELS 1/2 IN.NOMINAL THICKNESS+++
NOZZLE-TO-SHELL(OR HEAD)WELD NOZZLE INSIDE RADIUS SECTION IN VESSELS+++NOZZLES WITH REINFORCING PLATE IN VESSELS 1/2 IN.NOMINAL THICKNESS+++
44444444404440444444444440 444444444444444 NUTECH PR I SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ITEMNO PAGE'I 03 REVISION RRS1 DATE 85/12/05 444444444444444444444448444444444444444444444444444444444444444444444440444 REFERENCE KEY DESCRIPTION P01-01C2.3'I REINFORCING PLATE WELDS TO NOZZLE AND VESSEL P01-01C2.31X+++NOZZLE-TO-SHELL (OR HEAD)WELDS+++P01-01C2.32 P01-01C3.P01-01C3.1 P01-01C3.10 P01-01C3.2 P01-01C3.20 P01-01C3.3 P01-01C3.30 P01-0 IC3.4 P01-01C3.40 P01-0 IC4.P01-01C4.1 INSIDE OF VESSEL, NOZZLE-TO-SHELL (OR HEAD)WELD INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM.CAT.C-F+++EXAMINATION CATEGORY C-C++++++PRESSURE VESSELS+++
PRESSURE VESSEL INTEGRALLY WELDED ATTACHMENTS
+++PIPING+++
PIPING INTEGRALLY WELDED ATTACHMENTS
+++PUMPS+++
PUMP INTEGRALLY WELDED ATTACHMENTS
+++VALVES+++
VALVE INTEGRALLY WELDED ATTACHMENTS
+++EXAMINATION CATEGORY C-D++++++PRESSURE VESSELS+++
444444f4444444f44444444ft44444444444444444t444444444444444 44444444444444f4444444444 4 NUTECH CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRISIM PAGE'.,1 04 REVISION RRS 1 DATE 85/12/05 44444444444444444444444444444444444444444444444444444444444444444444444444'0 REFERENCE KEY DESCRIPTION P01-01C4.10 P01-01C4.2 Po 1-01C4.20 P01-01C4.3 Po 1-01C4.30 P01-01C4.4 Po 1-01C4.40 P01-01C5.Po 1-01C5.1 P01-01CS.10 P01-01CS.11 Po 1-01C5.12 Po 1-01C5.20 P01-01C5.21 PO 1-0 1 C5.22 PRESSURE VESSEL BOLTS AND STUDS (>2")+++PIPING+++
PIPING BOLTS AND STUDS (>2")+++PUMPS+++
PUMP BOLTS AND STUDS (>2")+++VALVES+++
VALVE BOLTS AND STUDS (>2")+++EXAMINATION CATEGORY C-F++++++PIPING+++
+++PIPING WELDS<=1/2 IN.NOMINAL WALL THICKNESS+++
PIPING CIRCUMFERENTIAL WELD<=1/2" NOMINAL WALL THICKNESS PIPING LONGI TUDINAI WELD<=1/2".NOMINAL WALL THICKNESS+++PIPING WELOS>1/2 IN.NOMINAL WALL THICKNESS+++
PIPING CIRCUMFERENTIAL WELD>1/2" NOMINAL WALL THICKNESS PIPING LONGITUDINAL WELD>1/2" NOMINAL WALL THICKNESS
:
4++4444444444444f444444 NUTECH 4444444t44404444444t44f44ftt44f4444 eft44444f44ff44 PRISIM PAGE 105 REVISION RRS1 DATE 85/12/05 CAROLINA POWER It LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT': ITEMNO 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 4 4 4 4 4 f 4 t 4 t 4 4 4 4 4 4 4'0 4 4 4 0 t 4 4 0 4 4 4 0 4 4 4 4 4 4 4 t 4 4 4 4 4 4 4 t 4 4 0 t 0 4 4 4 4 4 REFERENCE KEY DESCRIPTION P01-01C5.30 P01-01C5.31 P01-01C5.32 P01-01C6.P01-01C6.1 P01-01C6.10 P01-01C6.2 P01-01C6.20 P01-01C7.PO'1-01D1.
P01-0101.1 P01-01D1.10 P01-01D1.20 P01-0101.30
+++PIPING BRANCH CONNECTIONS+++
PIPE BRANCH CONNECTION CIRCUMFERENTIAL WELD PIPE BRANCH CONNECTION LONGITUDINAL WELD+++EXAMINATION CATEGORY C-G++++++PUMPS+++
PUMP CASING WELDS+++VALVES+++
VALVE BODY WELDS+++EXAMINATION CATEGORY C-H IS NOT SUBJECT TO PSI++++++EXAMINATION CATEGORY D-A++++++SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION+++
+++ITEM NUMBER D1.10 IS EXEMPT FROM PRESERVICE INSPECTION++~
RV SHUTDOWN INTEGRAL ATTACHMENTS
-SUPPORTS AND RESTRAINTS RV SHUTDOWN INTEGRAL ATTACHMENTS
-SNUBBERS RV SHUTDOWN INTEGRAL ATTACHMENTS
-MECHANICAL AND HYDRAULIC SNUBBERS 4484444444484444444444444444444444444444ff44444444444444444444f444444444444 44444444k44444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ITEMNO PAGE, 106 REVISION RRS1 DATE 85/12/05 4444444444444444f444444444'44t4444f4ff44444f4444f444444f4444t444444'4444 REFERENCE KEY DESCRIPTION P01-0101.40 P01-0101.50 P01-0101.60 P01-0102.P01-0102.1 P01-01D2.10 P01-0102.20 P01-0102.30 P01-01D2.40 P01-0102.50'01-01D2.60 P01-01D3.P01-01D3.1 RV SHUTDOWN INTEGRAL ATTACHMENTS
-SPRING TYPE SUPPORTS RV SHUTDOWN INTEGRAL ATTACHMENTS-CONSTANT LOAD TYPE SUPPORTS RV SHUTDOWN INTEGRAL ATTACHMENTS
-SHOCK ABSORBERS+++EXAMINATION CATEGORY D-8+++++~SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL+++
+++ITEM NUMBER D2.10 IS EXEMPT FROM PRESERVICE INSPECTION+++
ECCS, ETC.INTEGRAL ATTACHMENTS
-SUPPORTS AND RESTRAINTS ECCSo ETC.INTEGRAL ATTACHMENTS
-SNUBBERS ECCS, ETC.INTEGRAL ATTACHMENTS
-MECHANICAL AND HYDRAULIC SNUBBERS ECCS, ETC.INTEGRAL ATTACHMENTS
-SPRING TYPE SUPPORTS ECCS, ETC.INTEGRAL ATTACHMENTS
-CONSTANT LOAD TYPE SUPPORT ECCS, ETC.INTEGRAL ATTACHMENTS
-SHOCK ABSORBERS+++EXAMINATION CATEGORY D-C++++++SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM THE SPENT FUEL STORAGE POOL+++4444444444444444444444444444444444444f4444444f4444


44444444044440444444400t444444444f4fff44444f444444 4444444f4444t44 NUTECH PRISIM CAROLINA POWER lt LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ITEMNO PAGE 107 REVISION.RRS 1 DATE 85/12/05 444044444444444444444444444444444444444444044r444444444444004444044444444444 REFERENCE KEY DESCRIPTION P01-0103.'10
  +4ft4444444444444444444444444t4tt4444f44444444444444t444        44444444444'444 NUTECH                                                               PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT   - UNIT 1 PLANNING                                       4 REFERENCE CLUSTER LISTING               444444444444444444 DATA ELEMENT : ITEMNO                   PAGE,1RRS1 REVISION 46 DATE 85/12/05 44444$ 4444444444f444444444ft44t44t44444444444$ 44f44044444f44444404fft444444 REFERENCE KEY                             DESCRIPTION 81W-01E9.       +++EXAMINATION CATEGORY E-P+++
+++ITEM NUMBER D3.10 IS EXEMPT FROM PRESERVICE INSPECTION+++
81W-01E9. EX   EXEMPT CLASS MC PRESSURE   RETAINING COMPONENTS 81W-01E9. 1    +++ALL PRESSURE RETAINING COMPONENTS+++
P01-0103.20 P01-01D3.30 Po 1-01D3.40 P01-01D3.50 Po 1-01D3.60 P01-01E1.P01-01E1.1 P01-01E1.10 P01-01E1.11 P01-01E1.12 P01-01E1.20 P01-01E1.30 P01-01E1.40 RHR FROM SFS INTEGRAL ATTACHMENTS
81W-01E9. 10    +++PRESSURE RETAINING BOUNDARY+++
-SUPPORTS AND RESTRAINTS RHR FROM SFS INTEGRAL ATTACHMENTS
81W-01E9. 11    10-CFR-50 APPENDIX J TEST OF CONTAINMENT BOUNDARY 81W-01E9. 12    SYS LEAKAGE PRESSURE   TEST IWE-5220 OF CONTAINMENT BOUNDARY SYSTEM LEAKAGE PRESSURE   TEST IWE-5220 OF CONTAINMENT BOUNDARY.
-SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS
81W-01E9. 20    CONTAINMENT PENET BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST)
-MECHANICAL AND HYDRAULIC SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS
CONTAINMENT PENETETRATION BELLOWS ( 10CFR50 APPENDIX J TYPE 8 TEST).
-SPRING TYPE SUPPORTS RHR FROM SFS INTEGRAL ATTACHMENT-CONSTANT LOAD TYPE SUPPORTS RHR FROM SFS INTEGRAL ATTACHMENTS
81W-01E9. 30   AIRLOCKS (10CFR50 APPENDIX J TYPE 8 TESTS) 81W-01E9.40     SEALS AND GASKETS (10CFR50 APPENDIX J TYPE 8 TESTS) 81W-01F1.      +++EXAMINATION CATEGORY F-A+++
-SHOCK ABSORBERS+++EXAMINATION CATEGORY E-A++++++PRESSURE RETAINING WELDS IN CONTAINMENT VESSELS+++
81W-01F1. EX   EXEMPT CLASS   1, 2, OR 3 CATEGORY F-A COMPONENT SUPPORTS 81W-01F1. 1   +++PLATE AND SHELL TYPE SUPPORTS+++
+++SHELL WELDS IN CONTAINMENT VESSELS+++
4444444t4444444444444fft440f4444f444444f4444f+444444404t44444444444444f44t4
LONGITUDINAL SHELL WELDS IN VESSELS (CATEGORY A)CIRCUMFERENTIAL SHELL WELDS IN VESSELS (CATEGORY B)FLANGE WELDS IN VESSELS (CATEGORY C)NOZZLE-TO-SHELL WELDS IN VESSELS (CATEGORY 0)+++INSERT PLATE WELDS+++44t4444444444t44f444f44f444444444444444444444f444444444t444f444444444444444
+~4444444f4444444f4t44444444444444444444 NUTECH 444444444444444444 444444444444444 PRI SIM PAGE 108 REVISION RRS1 DATE 85/12/05 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 444444444444444440444444484444444444444444444444444440404444444444444444404 REFERENCE KEY DESCRIPTION P01-01E1.41 P01-01E1.42 P01-01E1.43 P01-01E1.50 P01-01E1.51 P01-01E1.52 P01-01E1.53 P01-01E2.P01-01E2.1 P01-01E2.10 INSERT PLATE-TO-SHELL WELDS LONGITUDINAL INSERT PLATE WELDS CIRCUMFERENTIAL INSERT PLATE WELDS+++VENT SYSTEM WELDS+++LONGITUDINAL VENT SYSTEM WELDS CIRCUMFERENTIAL VENT SYSTEM WELDS OTHER VENT SYSTEM WELDS+++EXAMINATION CATEGORY E-A-1++++++NONPRESSURE-RETAINING WELDS++++++REINFORCING STRUCTURE WELDS+++P01-01E2.11 CONTAINMENT VESSEL ATTACHMENT REINFORCING STRUCTURE WELDS P01-01E2.12 P01-01E2.20 P01-01E3.P01-01E3.1 OTHER REINFORCING STRUCTURE WELDS REINFORCING STRUCTURE ATTACHMENT WELDS+++EXAMINATION CATEGORY E-8++++++PRESSURE RETAINING WELDS IN CONTAINMENT PENETRATIONS+++
44f$44444444444f44444f44444444444t4444444ftfff444444444444f4404f4444 E
4~44444444444444444444f4444444444f44f44404f44t44444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 444444444444444444444440444444444444444444444444440444444 PRISIM PAGE.109 REVISION RRS1 DATE 85/12/05 44444444440444P444 REFERENCE KEY DESCRIPTION P01-01E3.10 PO I-01E3.11 P01-01E3.12 P01-01E3.13 P01-01E4.P01-01E4.1+++CONTAINMENT PENETRATION WELDS+++LONGITUDINAL CONTAINMENT PENETRATION WELDS CIRCUMFERENTIAL CONTAINMENT PENETRATION WELDS FLUED HEAD AND BELLOWS SEAL CIRC WELDS JOINED TO THE PENET FLUED HEAD AND BELLOWS SEAL CIRCUMFERENTIAL WELDS JOINED TO THE PENETRATION.
+++EXAMINATION CATEGORY E-C++++++PRESSURE RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES+++
P01-01E4.10+++AIRLOCK WELDS+++P01-01E4.11 LONGITUDINAL AIRLOCK WELDS P01-01E4.12 CIRCUMFERENTIAL AIRLOCK WELDS P01-01E4.20+++EQUIPMENT HATCH WELDS+++P01-0IE4.21 LONGITUDINAL EQUIPMENT HATCH WELDS P01-01E4.22 CIRCUMFERENTIAL EQUIPMENT HATCH WELDS P01-01E5.+++EXAMINATION CATEGORY E-0+++4444t444444444444444444444444ff444444444444444444444444444444444444444444+
0 44444444444444 4444444444444$
PRISIM 444444444444444444 PAGE.110 REVISION RRS1 DATE 85/12/05 444444444444444444t44444444t4444$
t44 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 44444444444444444444444444f4tffttf4444t44444444ff4444444ff444444444404f04t4 REFERENCE KEY DESCRIPTION P01-01E5.1
+++SEALS AND GASKETS+++
P01-01E5.10 SEALS P01-01E5.20 GASKETS P01-01E6.+++EXAMINATION CATEGORY E-E+++P01-01E6.1+++INTEGRAL ATTACHMENTS+++
P01-01E6.10 INTEGRAL ATTACHMENT WELDS P01-01E7.+++EXAMINATION CATEGORY E-F+++P01-01E7.1+++PRESSURE RETAINING DISSIMILAR METAL WELDS+++P01-01E7.10 DISSIMILAR METAL WELDS Po 1-01EB+++EXAMINATION CATEGORY E-G+++P01-01EB.+++PRESSURE RETAINING BOLTING+++
P01-01EB.1+++BOLTED CONNECTION VISUAL EXAMINATION+++
P01-01E8.10 BOLTED CONNECTION VISUAL EXAMINATION P01-01E8.2
+++BOLTED CONNECTION BOLT TORQUE OR TENSION TEST++~P01-01E8.20 BOLTED CONNECTION BOLT TORQUE OR TENSION TEST 4444444444444$
4444444444444444ff444444444444444444444444f4444444444444444f4 0++4444444444444f444448444444444444444444444444ft44444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNI PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRISIM T 1 PAGE.111 REVISION RRS 1 DATE 85/12/05 REFERENCE KEY DESCRIPTION P01-01E9.Po 1-01E9.EX Po 1-01E9.1 Po 1-01E9.10 Pol-01E9.11 P01-01E9.12 P01-01E9.20+++EXAMINATION CATEGORY E-P+++EXEMPT CLASS MC PRESSURE RETAINING COMPONENTS
+++ALL PRESSURE RETAINING COMPONENTS+++
+++PRESSURE RETAINING BOUNDARY+++
10-CFR-50 APPENDIX J TEST OF CONTAINMENT BOUNDARY SYS LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY SYSTEM LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY.CONTAINMENT PENET BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST)CONTAINMENT PENETETRATION BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST).P01-01E9.30 AIRLOCKS (10CFR50 APPENDIX J TYPE 8 TESTS)P01-01E9.40 P01-01F1.P01-01F1.EX Po 1-01F1.1 SEALS AND GASKETS (10CFR50 APPENDIX J TYPE 8 TESTS)+++EXAMINATION CATEGORY F-A+++EXEMPT CLASS 1, 2, OR 3 CATEGORY F-A COMPONENT SUPPORTS+++PLATE AND SHELL TYPE SUPPORTS+++
444444444444444444444444444t4444t444444444444444444444444444444444444440444
+44444t44444444444444444fff44tt44f44f444f4444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PAGE 112 REVISION RRS 1 DATE 85/12/05 t444444444444444ff444444t48444444f4444444444444f4444444444444t4444f44444444 REFERENCE KEY DESCRIPTION Po 1-01F 1.10 P01-01F1.20 P01-01F 1.30 Po 1-01F1.40 P01-01F2.Po 1-01F2.EX P01-01F2.1 Po 1-01F2.10 P01-01F2.20 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE WELDED CONNECTIONS TO BUILDING STRUCTURE WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS+++EXAMINATION CATEGORY F-8++~EXEMPT CLASS 1, 2, OR 3 CATEGORY F-8 COMPONENT SUPPORTS+++LINEAR TYPE SUPPORTS+++
MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE WELDED CONNECTIONS TO BUILDING STRUCTURE 4444444444444ff48444444f44f444444fft4f444444f4444444444444f44I44f4fff444444 V
4444444444444t4
+44444444444444444444444444444444404444440444 NUTECH PRISIM 044444444444444044 PAGE'113 REVISION RRS I DATE 85/12/05 4444444444444444444444444444 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING'ATA ELEMENT: ITEMNO 44444444444484444444444444444444444444404444444 REFERENCE KEY DESCRIPTION PO 1,-01F2.30 PO)-01F2.40 P01-01F2.50 P01-01F3.P01-0 I F3.EX P01-01F3.1 P01-01F3.10 P01-01F3.20 P01-01F3.30 WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS INVALID I TEMNO+++THIS ITEMNO IS INVALID+++EXAMINATION CATEGORY F-C+++EXEMPT CLASS 1, 2, OR 3 CATEGORY F-C COMPONENT SUPPORTS+++COMPONENT STANDARD SUPPORTS+++
MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE WELDED CONNECTIONS TO BUILDING STRUCTURE WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS 444'44444444tt44444444t44444444444444t4444444444t4444444444r444444444tf444444


C+~4444444444444444444444t44444444444444f444444444t44044444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ITEMNO PAGE 114 REVISION RRS 1 DATE 85/12/05 444444444444444444444444444444444404444444444444444444444444444444404444040 REFERENCE KEY DESCRIPTION P01-01F3.40 Po 1-01F3.50 P02-01 P02-0180RE DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS SPRING, CONSTANT, SHOCK ABSORBER, AND SNUBBER SUPPORTS SPRING TYPE SUPPORTS, CONSTANT LOAD TYPE SUPPORTS, SHOCK AB-SORBERS, HYDRAULIC AND MECHANICAL TYPE SNUBBERS+++EXAMINATION CATEGORY FSAR+++REACTOR COOLANT PUMP FLYWHEEL BORE-UT P02-0 IFLYWHL REACTOR COOLANT PUMP FLYWHEEL-SURFACE AND UT P02-01KEYWAY REACTOR COOLANT PUMP FLYWHEEL KEYWAY-UT P03-01250.
+
1S P03-01250.
t ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH                                                             PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT   1 t                                PLANNING REFERENCE CLUSTER LISTING               tttttttttttttttttt DATA ELEMENT : ITEMNO                   PAGE,      147 REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                             DESCRIPTION 81W-01F1. 10    MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE    RETAINING COMPONENTS AND BUILDING STRUCTURE 81W-01F1.-20    WELDED CONNECTIONS TO BUILDING STRUCTURE 81W-01F1.30      WELD 8 MECH CONNECTIONS  IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE    JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS 8 1W-01F 1 . 40  DISPLACEMENT SETTINGS'ISALIGNMENT'ND ASSEMBLY       OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS,     MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS 8 1W-01F2.      +++EXAMINATION CATEGORY F-8+++
1V P04-01 P04-016.6.88 P04-016.6.8E SAFETY EVALUATION REPORT, SAFETY-REVIEW QUESTION&#xb9;250.
81W-0 I F2. EX  EXEMPT CLASS 1,  2, OR 3 CATEGORY  F-8 COMPONENT SUPPORTS 81W-01F2. 1   +++LINEAR TYPE SUPPORTS+++
1 SURFACE EXAM SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION&#xb9;250.1 VOLUMETRICEXAM
81W-01F2.10      MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING I
+++EXAhlINATION CATEGORY FSAR+++AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.88.AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.4444444444444444444444444444f44f44t44t44444t4444Std'444444t4f4444fff44f44444
MECHANICAL CONNECTIONS TO PRESSURE    RETAINING COMPONENTS AND BUILDING STRUCTURE 81W"01F2.20      WELDED CONNECTIONS TO BUILDING STRUCTURE ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt


4+s44tkt4tftf4444f4444444444444440444t44 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 4fkf44444f4400 PRISIM PAGE 115 REVISION RRS1 DATE 85/12/05 4 4 4'4 4 4 4 4 4 4 4 4 t t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t 0 4 4 4 4 4 4 4 4 4 4 t 4 t t 0 4 4 4 4 4 4 4 4 4 t 4 4 tO 4 4 t t t t t 4 4 4 4 0 4 REFERENCE KEY DESCRIPTION P05-01 P05-016.6.8C P05-016.6.8E P06-01 P06-016.6.8D P06-016.6.8E V01-01C3.10 V01-01C3.20<
tttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH                                                                 PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT   -'NIT  1 t
250.1S 250.1V 81W-0181 81W-0181.81W-0181.'10+++EXAMINATION CATEGORY FSAR+++AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.8C.AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.+++EXAMINATION CATEGORY FSAR+++AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8D AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E.PRESSURE VESSEL INTEGRALLY WELDED ATTACHMENTS VOLUNTARY EXAM-INTEGRALWELDED PIPE ATTACHMENT LESS THAN 3/4 INCH THICK SAFETY EVALUATION REPORT 250.1-SURFACE SAFETY EVALUATION REPORT 250.1-VOUMETRIC EXAM+++EXAhlINATION CATEGORY 8-A++++++REACTOR VESSEL++++++SHELL WELDS+++44444t44444444f44ff4444444444444444ff444444444f444444fftf444444444
PLANNING REFERENCE CLUSTER LISTING               tttttttttttttttttt DATA ELEMENT : ITEMNO                   PAGE         148 REVISION   RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                               DESCRIPTION 81W-01F2.30        WELD 8 MECH CONNECTIONS  IN SUPPORT  INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE    JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS 81W-01F2. 40      DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS,    MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS 81W-01F2. 50      INVALID ITEMNO    ttt  THIS ITEMNO IS INVALID 81W-01F3.         +++EXAMINATION CATEGORY F-C+++
81W-0 I F3. EX    EXEMPT CLASS 1, 2,  OR 3 CATEGORY  F-C COMPONENT SUPPORTS 81W-01F3. 1      +++COMPONENT STANDARD SUPPORTS+++
81W-01F3. 10      MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT ANO BUILDING MECHANICAL CONNECTIONS TO PRESSURE   RETAINING COMPONENTS AND BUILDING STRUCTURE 81W-01F3. 20      WELDED CONNECTIONS TO  BUILDING STRUCTURE 81W-01F3. 30      WELD 8 MECH CONNECTIONS  IN SUPPORT INTERMEDIATE JOINTS WELD ANO MECHANICAL CONNECTIONS AT INTERMEDIATE    JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS


NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 44444444444444440440444t444444404404444 44444444444440 PRISIM PAGE 116 REVISION RRS1 DATE 85/12/05 44444444444444444f 4444t44t44f 4f f tf t444444444444444f t4 f 44f f 44tf 044444444 REFERENCE KEY DESCRIPTION 81W-0181.11 RV CIRCUMFERENTIAL SHELL WELOS 81W-0181.12 RV LONGITUDINAL SHELL WELDS 81W-0181.20+++HEAD WELDS+++81W-0181.218 RV CIRCUMFERENTIAL BOTTOM HEAD WELDS CIRCUMFERENTIAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL.81W-0181.21T RV CIRCUMFERENTIAL TOP HEAD WELDS I CIRCUMFERENTIAL TOP HEAD WELD INSPECTION MUST BE PERFORMED DURING EACH PERIOD AND MAY NOT BE DEFERRED TO THE END OF THE INTERVAL.81W-0181.228 RV MERIDIONAL BOTTOM HEAD WELDS RV MERIDIONAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL.81W-0181.22T RV MERIDIONAL TOP HEAD WELDS I RV MERIDIONAL TOP HEAD WELD INSPECTION MUST BE PERFORMED DURING EACH PERIOD AND MAY NOT BE DEFERRED TO THE END OF THE INTERVAL.81W-0181.30 RV SHELL-TO-FLANGE WELD 44444444404444444444444444f440444444444444444444444444444t444444444444444
ee,e4444444444444444444444444444448444444444444444444404444 NUTECH                                                             PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT   1 PLANNING 4                      REFERENCE CLUSTER LISTING             444444444444444404 DATA ELEMENT : ITEMNO                 PAGE         149 REVISION   RRS1 DATE   85/12/05 444444444444444444444444444440440040004004404444044044444444444444444404440 REFERENCE KEY                             DESCRIPTION 81W-01F3. 40    DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT I
%%4eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeee NUTECH PRIS IM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING eeeeeeeeeeeeeeeeee DATA ELEMENT: ITEMNO PAGE.117 REVISION, RRS 1 DATE 85/12/05 eteeeeeeeeeeeeeeeeeteeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeefeeeeeeeeeeeeeee REFERENCE KEY DESCRIPTION 81W-0181.300 81W-0181.30F 81W-0181.30V RV SHELL-TO-FLANGE WELD TESTING IN CONJUNCTION WITH CAT 8-D I EXAM OF SHELL-TO-FLANGE WELDS MAY BE PERFORMED DURING THE 1ST AND 3RD INSPECTION PERIOD IN CONJUNCTION WITH THE NOZZLE EXAM OF CAT.B-D (PROGRAM 8).AT LEAST 50k OF SHELL-TO-FLNGE WELDS SHALL BE EXAM BY THE END OF THE 1ST INSPECTION PERIOD, AND THE REMAINDER BY THE END OF THE 3RD INSPECTION PERIOD.RV SHELL-TO-FLANGE WELD PARTIAL EXAM FROM FLANGE FACE IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.RV SHELL-TO-FLANGE WELD EXAM CONDUCTED FROM VESSEL WALL IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.81W-0181.40 RV HEAD-TO-FLANGE WELD 81W-0181.40F RV HEAD-TO-FLANGE WELD PARTIAL EXAM FROM FLANGE FACE IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE~THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.eeeeeeeeeefeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS,    MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS 81W-01F3. 50    SPRING, CONSTANT, SHOCK ABSORBER, AND SNUBBER SUPPORTS SPRING TYPE SUPPORTS, CONSTANT LOAD TYPE SUPPORTS,     SHOCK  AB-SORBERS, HYDRAULIC AND MECHANICAL TYPE SNUBBERS 444ff4444444444444404444444444f4444tt44f4444444444444444t44ff4


e~44444444444444444444444444444444444444444444444444444444 C44444444444f44 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444044 DATA ELEMENT: ITEMNO PAGE'18 REVISION RRS1 DATE 85/12/05 40t44ftf44t44tf4444f44tf4444ft444444t44 REFERENCE KEY DESCRIPTION 81W-0181.40V 81W-0181.50 81W-0181.5'I 81W-0181.99 81W-01810 8 IW-01810.1 RV HEAD-TO-FLANGE WELD EXAM CONDUCTED FROM VESSEL WALL IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.+++REPAIR WELDS+++RV BELTLINE REGION REPAIR WELOS+++ITEM NUMBERS 82.XX THROUGH 89.XX APPEAR AFTER 816.20++++++EXAMINATION CATEGORY 8-K-1++++++PIPING+++
~tttttttttttttttttt                        tttttttttttttttt ttttttttttttttt NUTECH                                                           PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING             tttttttttttttttttt DATA ELEMENT : EXSCHD                  PAGE       64 REVISION RRS1 DATE 85/12/04 tttttttttttttttttt    tttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                           DESCRIPTION AE              ACOUSTIC EMISSION TEST ET              EDDY CURRENT TEST MT              MAGNETIC PARTICLE TEST PT              PENETRANT TEST RT              RADIOGRAPHIC TEST RT-RCP          MINAC RADIOGRAPHIC TEST SUR            SURFACE EXAMINATION, TEST NOT SPECIFIED NOTE: THIS MUST BE UPDATED TO A PT OR MT BEFORE THE EXAM    IS SCHEDULED UC-45L          ULTRASONIC CIRCUMFERENTIAL SCAN-45 DEGREE LONGITUDINAL UT-IN           ULTRASONIC TEST IN-PLACE, CATEGORY   B-G-1, BOLTING UT-L            ULTRASONIC LAMINATION TEST UT-OUT          ULTRASONIC TEST WHEN REMOVED (OUT), CATEGORY  B-G-1, BOLTING UT-RVN          REACTOR VESSEL NOZZLE MECHANIZED ULTRASONIC TEST UT-RVS          REACTOR VESSEL SHELL MECHANIZED ULTRASONIC TEST UT-SN1          ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE NOZZLE SIDE WITH THE NOZZLE CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 000 DEGREES
81W-01810.
10 PIPING INTEGRALLY WELDED ATTACHMENTS 81W-01810.
2+++PUMPS+++
81W-01810.
20 PUMP INTEGRALLY WELDED ATTACHMENTS 81W-01810.
3+++VALVES+++
81W-01810.30 VALVE INTEGRALLY WELDED ATTACHMENTS 81W-01812.
81W-01812.
1+++PUMPS+++
+++EXAMINATION CATEGORY 8-L-1+++444444444444444444C4444444444444444%444444ftf44f4444f44'4444'44440444444ffO t+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttktttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt t DATA ELEMENT: ITEMNO PAGE.119 REVISION'RRS1 DATE 85/12/05<<tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-01812.
10 PUMP CASING WELDS 81W-01812.
2+++EXAMINATION CATEGORY 8-L-2+++8 1W-01812.20 PUMP CASING 81W-01812.
3+++EXAMINATION CATEGORY 8-M-1+++81W-01812.
3A+++VALVES+++
81W-01812.30 VALVES, NOMINAL PIPE SIZE<4 IN.VALVE BODY WELDS 81W-01812.40 VALVES, NOMINAL PIPE SIZE>=4 IN.VALVE BODY WELDS 81W-01812.
5+++EXAMINATION CATEGORY 8-M-2+++81W"01812.50 VALVE BODY, EXCEEDING 4 IN.NOMINAL PIPE SIZE 8 I W-01813.81W-01813.
1+++EXAMINATION CATEGORY 8-N-1++++++REACTOR VESSEL+++81W-01813.
10 RV VESSEL INTERIOR 81W-01813.
2+++EXAMINATION CATEGORY 8-N-2+++81W-01813.
2.+++REACTOR VESSEL (BWR)+++81W-01813.20 RV INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (BWR)ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO t PRISIM 44f 444444444444444 PAGE.120 REVISION RRS1 DATE 85/12/05 444444444444t44c0444444444844444444444444tf444404444444444 REFERENCE KEY DESCRIPTION 81W-01813.21 RV INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (BWR)81W-01813.
22 RV CORE SUPPORT STRUCTURE (BWR)81W-01813.
3+++EXAMINATION CATEGORY 8-N-3+++81W-01813.
3.+++REACTOR VESSEL (PWR)+++81W-01813.30 INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (PWR)81W-01813.31 INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (PWR)81W-01813.32 RV CORE SUPPORT STRUCTURE (PWR)81W-01814.
81W-01814.
1+++EXAMINATION CATEGORY 8-0++++++REACTOR VESSEL+++81W-01814.10 RV WELDS IN PERIPHERAL CRD HOUSING 8 1W-01815.81W" 01815.EX+++EXAMINATION CATEGORY 8-P+++EXEMPT CLASS 1 PRESSURE RETAINING COMPONENTS 1)IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.2)EXEMPT CLASS 1 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.(E.G~WELDS<=1" NPS)81W-01815.
1+++REACTOR VESSEL+++444444444tt484ftkf44444ttf4ffkt4444444444t444440444t4444444444f4444444fkt44 0~+444444444444444444444404444444f44444444tft444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 44444444444444444
+44444444444444 PRIS IM 4444444444t4444444 PAGE 121 REVISION RRS 1 DATE 85/12/05 REFERENCE KEY DESCRIPTION 8IW-01815.10 RV PRESSURE RETAINING BOUNDARY-OPERATIONAL 81W-01815.11 RV PRESSURE RETAINING BOUNDARY-STATIC 81W-01815.
2+++PRESSURIZER+++
81W-01815.20 PRZ PRESSURE RETAINING BOUNDARY-OPERATIONAL 81W-01815.
21 PRZ PRESSURE RETAINING BOUNDARY-STATIC 81W-01815.
3++~STEAM GENERATORS+++
81W-01815.30 SG PRESSURE RETAINING BOUNDARY-OPERATIONAL 81W-01815.31 SG PRESSURE RETAINING BOUNDARY-STATIC 81W-01815.
4+++HEAT EXCHANGERS+++
81W-01815.40 HX PRESSURE RETAINING BOUNDARY-OPERATIONAL 81W-01815.41 HX PRESSURE RETAINING BOUNDARY-STATIC 8 1W-01815.5+++PIPING+++
81W-01815.50 PIPING PRESSURE RETAINING BOUNDARY-OPERATIONAL 81W-01815.51 PIPING PRESSURE RETAINING BOUNDARY-STATIC 8 1W-0 18'I 5.6+++PUMPS+++
444444444444444f444444444444444t44f444444444444444444444f40f4444t44'444444t4


+~4444444444444444444444444444444444444044444f4444444fff44 44f4k4f4k44440f NUTECH PRISIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44444444444444444t DATA ELEMENT: ITEMNO PAGE 122 REVISION RRS1 DATE-85/12/05 444444444444444444444844444444444444444444444444444444444444444444404444444 REFERENCE KEY DESCRIPTION 8 IW-01815.60 PUMP PRESSURE RETAINING BOUNDARY-OPERATIONAL 81W-01815.61 PUMP PRESSURE RETAINING BOUNDARY-STATIC 81W-01815.
ttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH                                                       PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING           tttttttttttttttttt DATA ELEMENT : EXSCHD                PAGE       65 REVISION RRS1 ttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                         DESCRIPTION UT-SN2        ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE NOZZLE SIDE WITH THE NOZZLE CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 045 DEGREES UT-SP1        ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE PIPING SIDE WITH THE PIPING CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 000 DEGREES UT-SP2        ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE PIPING SIDE WITH THE PIPING CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 045 DEGREES UT-T          ULTRASONIC THICKNESS TEST UT-00        ULTRASONIC 0 DEGREE TEST UT-30S        ULTRASONIC 30 DEGREE TEST-SHEAR UT-41L        ULTRASONIC 41 DEGREE TEST  - LONGITUDINAL UT-41R        ULTRASONIC 41 DEGREE TEST  REFRACTED LONGITUDINAL UT-41S        ULTRASONIC 41 DEGREE TEST  SHEAR UT-45        ULTRASONIC 45 DEGREE TEST  (TO BE SPECIFIED)
7+++VALVES+++
UT-45L        ULTRASONIC 45 DEGREE TEST  LONGITUDINAL UT-45R        ULTRASONIC 45 DEGREE TEST  REFRACTED LONGITUDINAL
8 1W-01815.70 VALVE PRESSURE RETAINING BOUNDARY-OPERATIONAL 81W-O'1815.71 VALVE PRESSURE RETAINING BOUNDARY-STATIC 81W-01816.
81W-01816.
1 81W-01816.
10 8'1 W-0 1816.20 81W-0182.81W-0182.1 81W-0182.10 81W-0182.11 81W-0182.12+++EXAMINATION CATEGORY B-Q++++++STEAhl GENERATORS+++
+++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN STRAIGHT TUBE DESIGN++++++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN U-TUBE DESIGN++++++EXAMINATION CATEGORY B-B++++++PRESSURIZER+++
+++SHELL-TO-HEAD WELDS+++PZR CIRCUMFERENTIAL SHELL-TO-HEAD WELDS PZR LONGITUDINAL SHELL-TO-HEAD WELDS 44444444444f444444444444f444444444444f444ft44444444444444444f4444f444444
~~tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING t REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: ITEMNO PAGE 123 REVISION RRS 1 DATE 85/12/05 ttttttt REFERENCE KEY DESCRIPTION 81W-0182.20 81W-0182.21 81W-0182.22 81W-0182.3 81W-0182.30 81W-0182.31 81W-0182.32 81W-0182.40 81W-0182.5 81W" 0182.50 81W-0182.51 81W-0182.52 81W-0182.53 81W" 0182.6 81W-0182.60+++HEAD WELOS+++PRZ CIRCUMFERENTIAL HEAD WELDS PRZ MERIDIONAL HEAD WELOS+++STEAM GENERATORS (PRIMARY SIDE)++++++HEAD WELDS+++SG PRIMARY SIDE CIRCUMFERENTIAL HEAD WELDS SG PRIMARY SIDE MERIDIONAL HEAD WELDS SG PRIMARY SIDE TUBESHEET-TO-HEAD WELDS+++HEAT EXCHANGERS (PRIMARY SIDE)++++++SHELL(OR HEAD)WELDS+++HX PRIMARY SIDE CIRCUMFERENTIAL SHELL (OR HEAD)WELDS HX PRIMARY MERIDIONAL SHELL (OR HEAD)WELD HX PRIMARY LONGITUDINAL SHELL (OR HEAD)WELD+++SHELL (PRIMARY SIDE)+++TUBESHEET-TO-SHELL (OR HEAD)WELDS NUTECH PRISIM eeeeeeeeeeeeeeeeee PAGE 124 REVISION RRS1 DATE 85/12/05 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO e eeeeeeeeeeeeeeeeeeeeeee I, seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeekeeeeeeeee eeeeeeeeeeeeeee REFERENCE KEY DESCRIPTION 81W-0182.61 81W-0183 81W-0183.81W-0183.1 TUBESHEET-TO-SHELL WELDS+++EXAMINATION CATEGORY 8-DA++++++PROGRAM A REQUIREMENTS+++
1ST INTERVAL=3 YEARS 2ND INTERVAL=7 YEARS 3RD INTERVAL=13 YEARS 4TH INTERVAL=17 YEARS+++REACTOR VESSEL+++81W-0183.10 RV NOZZLE-TO-VESSEL WELDS-PROGRAM A 81W-0183.20 RV NOZZLE INSIDE RADIUS SECTION-PROGRAM A 81W-0183.3+++PRESSURIZER+++
81W-0183.30 PRZ NOZZLE-TO-VESSEL WELDS-PROGRAM A 81W-0183.40 PRZ NOZZLE INSIDE RADIUS SECTION-PROGRAM A 81W-0183.5+++STEAM GENERATORS (PRIMARY SIDE)+++81W-0183.50 SG PRIMARY NOZZLE-TO-VESSEL WELDS-PROGRAM A 81W-0183.60 SG PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM A 81W-0183.7+++HEAT EXCHANGERS (PRIMARY SIDE)++~eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee NUTECH CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNI NG REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRISIM PAGE , 125 REVISION RRS1 DATE 85/12/05 444444484'444444444444t4444444444444444444444t444444444444444444444444 REFERENCE KEY DESCRIPTION 81W-0183.70 HX PRIMARY NOZZLE-TO-VESSEL WELDS-PROGRAM A 81W-0183.80 HX PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM A 81W-0183.9 81W-0183.9.+++PROGRAM 8 1ST INTERVAL 2ND INTERVAL 3RD INTERVAL 4TH INTERVAL REQUIREMENTS+++
10 YEARS 10 YEARS 10 YEARS 10 YEARS+++EXAMINATION CATEGORY 8-08+++81W-0183.9A+++REACTOR VESSEL+++81W-0183.98 81W-0183.9S RV NOZZLE-TO-VESSEL WELDS, EXAM FROM NOZZLE BORE-PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZlE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.RV NOZZLE-TO-VESSEL WELDS, EXAM FROM RV SHELL-PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.
NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 444444444444444444444444t4444444444444444444 44444444444444 PRISIM 444444444444444444 PAGE 126 REVISION RRS1 DATE 85/12/05 44444444444444tf4444f4444f444444t44444444444444t4444t444ttt4t44f44444444444 REFERENCE KEY DESCRIPTION 81W-0183.90 RV NOZZLE-TO-VESSEL WELDS-PROGRAM 8 81W-0183.100 RV NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 81W-0183.11+++PRESSURIZER+++
81W-0183.110 PZR NOZZLE-TO-VESSEL WELDS-PROGRAM 8 81W-0183.120 PZR NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 81W-0183.13~++STEAM GENERATORS (PRIMARY SIDE)+++81W-0183.130 SG PRIMARY NOZZLE-TO-VESSEL WELDS-PROGRAM 8 81W-0183.140 SG PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 81W-0183.15+++HEAT EXCHANGERS (PRIMARY SIDE)+++81W-0183.150 HX PRIMARY NOZZLE-TO-VESSEL WELDS-PROGRAM 8 81W-0183.160 HX PRIMARY NOZZLE INSIDE RADIUS SECTION-PROGRAM 8 81W-0184 81W-0184.10 81W-0184.11 81W-0184.12+++EXAMINATION CATEGORY 8-E++++++PARTIAL PENETRATION WELDS+++VESSEL NOZZLE PARTIAL PENETRATION WELDS CONTROL ROD DRIVE NOZZLE PARTIAL PENETRATION WELDS 444444444444444flf444444f44444f44404404f444444444444444444444444444


044444444444 444444444444444 PRISIM 444444444444444444 PAGE 127 REVISION RRS1 DATE 85/12/05 44444404044044r444444 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 4444444444444t44444444444444444444f044t4444444
44ICf 4444f 44 NUTECH                                                              PRISIM CAROLINA POWER     8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING               444440444044444444 DATA ELEMENT : EXSCHD                    PAGE      ,
+~44444444444444f444f4444444444444444444444444 NUTECH REFERENCE KEY DESCRIPTION 81W" 0184.13 81W-0184.2 81W-0184.20 81W-0185.8 IW-0185.1 81W-0185.10 INSTRUMENTATION NOZZLE PARTIAL PENETRATION WELDS+++PRESSURIZER+++
66 REVISION   RRS1 DATE   85/12/04 4444444444444t4444444444444t4444t4444444t4444444444444444444444444444444444 REFERENCE KEY                               DESCRIPTION UT-45S          ULTRASONIC 45 DEGREE TEST  SHEAR UT-50S          ULTRASONIC 50 DEGREE TEST  SHEAR UT-53S          ULTRASONIC 53 DEGREE TEST  SHEAR UT-60           ULTRASONIC 60 DEGREE TEST  (TO BE SPECIFIED)
PRZ HEATER PENETRATION WELDS+++EXAMINATION CATEGORY 8-F++++++REACTOR VESSEL+++RV NOZZLE-TO-SAFE END BUTT WELDS.NPS>=4 INCHES WHEN DONE CONCURRENTLY WITH CATEGORY 8-D EXAMINATIONS 81W-0185.10 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS>=4 INCHES 81W-0185.2D RV NOZZLE-TO-SAFE END BUTT WELDS, NPS<4 INCHES WHEN DONE CONCURRENTLY WITH CATEGORY 8-D EXAMINATIONS 81W-0185.20 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS<4 INCHES 81W-0185.3D RV NOZZLE-TO-SAFE END SOCKET WELDS WHEN DONE CONCURRENTLY WITH CATEGORY 8-D EXAMINATIONS 81W-0185.30 RV NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185.4+++PRESSURIZER+++
UT-60L          ULTRASONIC 60 DEGREE TEST  LONGITUDINAL UT-60R          ULTRASONIC 60 DEGREE TEST    - REFRACTED LONGITUDINAL UT-60S          ULTRASONIC 60 DEGREE TEST    - SHEAR UT-62S          ULTRASONIC 62 DEGREE TEST-SHEAR UT-70S          ULTRASONIC 70 DEGREE TEST-SHEAR UTAUTO          ULTRASONIC MECHANIZED 0 DEGREE EXAMINATION VIS            GENERAL VISUAL TEST VOL            VOLUMETRIC EXAMINATION, TEST NOT SPECIFIED NOTE: THIS MUST BE UPDATED TO AE, RT, OR UT BEFORE THE THE EXAMINATION IS SCHEDULED VT-1           VISUAL TEST  1 PER  IWA-2210 (77W AND LATER ADDENDA)
444444444444t4%444444444444tt4444444444444444444444440444444444 4w4444444t44444444444444444444t4t444444444440444444t4444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 444444444444444 PRISIM 1 PAGE 128 REVISION RRS1 DATE 85/12/05 4444444444444444444 REFERENCE KEY DESCRIPTION 81W-0185.40 PZR NOMINAL PIPE SIZE>=4 IN.NOZZLE-TO-SAFE END BUTT WELDS 81W-0185.50 PRZ NOMINAL PIPE SIZE<4 IN.NOZZLE-TO-SAFE ENO BUTT WELDS 81W-0185.60 PRZ NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185.7+++STEAM GENERATOR+++
VT-2           VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA)NOTE:
81W-0185.70 SG NOMINAL PIPE SIZE>=4 IN.NOZZLE-TO-SAFE END BUTT WELDS 81W-0185.80 SG NOMINAL PIPE SIZE<4 IN.NOZZLE-TO-SAFE END BUTT WELDS 81W-0185.90 SG NOZZLE-TO-SAFF END SOCKET WELDS 81W-0185.10+++HEAT EXCHANGERS+++
VT-2 IS APPLICABLE TO CATEGORY B-E AND CATEGORY B-P, C-H.
81W-0185.100 HX NOMINAL PIPE SIZE>=4 IN.NOZZLE-TO-SAFE ENO BUTT WELDS 81W-0185.110 HX NOMINAL PIPE SIZE<4 IN.NOZZLE-TO-SAFE END BUTT WELDS 81W-0185.120 HX NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185.13+++PIPING+++
D-A, D-B, AND D-C IF THE ITEM NUMBER IS B15.EX, C7.EX, D1.EX, D2.EX OR D3.EX
81W-0185.130 NOMINAL PIPE SIZE>=4 IN.DISSIMILAR METAL PIPING BUTT WELD 81W-0185.140 NOhlINAL PIPE SIZE<4 IN.DISSIMILAR METAL PIPING BUTT WELD 81W-0185.150 DISSIMILAR METAL PIPING SOCKET WELDS 4t44f4444444444444'4444040ff444444ff404444444rtt44f44444 44444444444t4444444444444444444f 4444444f 44444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRI SIM UNIT 1 444444444444444444 PAGE129 REVISION RRS1 DATE 85/12/05 444844444444444444444404444404tt4444444444444444444444444444444444444404404 REFERENCE KEY DESCRIPTION 81W-0186.+++EXAMINATION CATEGORY 8-G-1+++81W-0186.1+++REACTOR VESSEL+++81W-0186.10 RV CLOSURE HEAD NUTS (>2")81W-0186.20 RV CLOSURE STUDS, IN PLACE (>2")81W-0186.30 RV CLOSURE STUDS, WHEN REMOVED (>2")81W-0186.40 RV THREADS IN FLANGE (>2")81W-0186.50 RV CLOSURE WASHERS, BUSHINGS (>2")81W-0186.6+++PRESSURIZER+++
81W-0186.60 PRZ BOLTS AND STUDS (>2")81W-0186.70 PRZ FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")81W"0186.80 PRZ NUTS, BUSHINGS, AND WASHERS (>2")81W-0186.9+++STEAM GENERATORS+++
81W-0186.90 SG BOLTS AND STUDS (>2")81W-0186.100 SG FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")81W-0186.110 SG NUTS, BUSHINGS, AND WASHERS (>2")4444444444444444444444444444444444444444444444444ff44f444444444444444044f44 0
4m+444444$
444f4444r44444444t4444t4444444444444444ftt4444444 44444444fk44444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444440444440444444 DATA ELEMENT: ITEMNO PAGE 130 4 REVISION RRS1 DATE 85/12/05 44444444444444444444t4444r444444440444444f4fft444444444444440irt4444f REFERENCE KEY DESCRIPTION 81W-0186.12,,+++HEAT EXCHANGERS+++
81W-0186.120 HX BOLTS AND STUDS (>2")81W-0186.130 HX FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")81W-0186.140 HX NUTS, BUSHINGS, AND WASHERS (>2")81W-0186.15+++P I P I N 6+++81W-0186.150 PIPING BOLTS AND STUDS (>2")81W-0186.160 PIPING FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")81W-0186.170 PIPING NUTS, BUSHINGS, AND WASHERS (>2")81W-0186.18+++PUMPS+++
81W-0186.180 PUMP BOLTS AND STUDS (>2")81W-0186.190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED
(>2")81W-0186.200 PUMP NUTS, BUSHINGS, AND WASHERS (>2")81W-0186.21+++VALVES+++
81W-0186.210 VALVE BOLTS AND STUDS (>2")8 IW-0186.220 VALVE FLANGE SURFACE WHEN CONNECTION DISIASSEMBLED
(>2")4444444444444444444444444444444444444444444t444444444444f444t444f4444444444


0++4444444444444444444444444f444f4444444C4f'444444444f4$
4444444444 eesseeeee+eeeeeeeessseseeeeeeesseseeeeeeeesees        +seetsessesseee>>
44 NUTECH CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 4444444444444t4444f4444444444444444444t444444444444t PRISIM PAGE 131 REVISION RRS1 DATE 85/12/05 REFERENCE KEY DESCRIPTION 81W-0186.230 VALVE NUTS, BUSHINGS, AND WASHERS (>2")81W-0187.81W-0187.1 81W-0187.10 81W-0187.2 81W-0187.20 81W-0187.3 81W-0187.30 81W" 0187.4 81W-0187.40 81W-0187.5 81W-0187.50 81W-0187.6 81W-0187.60 81W-0187.7+++EXAMINATION CATEGORY 8-G-2++++++REACTOR VESSEL+++REACTOR VESSEL BOLTS, STUDS, AND NUTS (<=2")+++PRESSURIZER+++
NUTECH                                                                   PRISIM 4                    CAROLINA POWER     8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                 444444444444444444 DATA ELEMENT : EXSCHD                    PAGE         67 +
PRESSURIZER BOLTS, STUDS, AND NUTS (<=2")+++STEAM GENERATORS+++
REVISION   RRS1 DATE   85/12/04 44tf44044444444404444f44444f04044f REFERENCE KEY                                 DESCRIPTION VT-20T          VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA)
STEAM GENERATOR BOLTS, STUDSI AND NUTS (<=2")+++HEAT EXCHANGERS+++
OPERATIONAL PRESSURE TESTING NOTE: VT-20T IS APPLICABLE TO ITEM NUMBERS  815.10, 815.20, 815.30, 815.40, 815.50, 815.60, 815.70, C7.10, C7.20, C7.30, C7.40, D1.10, D2.10, 03.10 VT-2ST          VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA)
HEAT EXCHANGER BOLTS, STUDS, AND NUTS (<=2")+++PIPING+++
STATIC PRESSURE TESTING          NOTE: VT-2ST IS APPLICABLE TO ITEM NUMBERS  815.11, 815.21, 815.31, 815.41, 815.51, 815.61, 815.71, C7.11, C7.21, C7.31, C7.41, D1.11, 02.11, C3.11 VT-3            VISUAL TEST 3 PER IWA-2210 (77W AND LATER ADDENDA)
PIPING BOLTS, STUDS, AND NUTS (<=2")+++PUMPS+++
VT-4            VISUAL TEST 4 PER IWA-2210 (77W AND LATER ADDENDA) 444444444444444444444444444444444444444404444444444404404404440440440444444
PUMP BOLTS, STUDS, AND NUTS (<=2")t++VALVES+++
444444$444444444444044044444444444040440444444444444444444444t4444444444444


t+4444'44444444444444444444444444444444444444444444f 444444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44t444444444444444 DATA ELEMENT: ITEMNO PAGE 132 REVISION RRS1 DATE 85/12/05 444444444444f4440444444f4tf44444444tf444tf444444444444444444404444444 REFERENCE KEY DESCRIPTION 81W-0187.70 VALVE BOLTS, STUDS, AND NUTS (<=2")81W-0187.8
EXAM REQUXPEMENT SOURCE a) ANN-NN
+++CRD HOUSING+++
      ~Interval      Number Program  Number Type  of  Program Example:  P01"01 Preservice Section XX Program Interval - 1: Preservice is considered to be an  interval for computer purposes ~
81W-0187.80 CRD HOUSING BOLTS, STUDS, AND NUTS (<=2")8 1W-0188.+++EXAMINATION CATEGORY 8-H+++81W-0188.1+++REACTOR VESSEL+++81W-0188.10 RV INTEGRALLY WELDED ATTACHMENTS 81W-0188.2+++PRESSUR I ZER+++81W-0188.20 PZR INTEGRALLY WELDED ATTACHMENTS 81W-0188.3+++STEAM GENERATORS+++
P02-01 Preservice Augmented Program B02-03.
81W-0188.30 SG INTEGRALLY WELDED ATTACHMENTS 81W-0188.4+++HEAT EXCHANGERS+++
Xnservice Augmented Program corresponding to P02-01 b) 81M-01
81W-0188.40 HX INTEGRALLY WELDED ATTACHMENTS 81W-0189.+++EXAMINATION CATEGORY 8-J+++81W-0189.1+++PIPING+++
      ~Interval      Number f'r Xnservice Code Addendum                    Program
81W-0189.10+++NOMINAL PIPE SI2E>=4 IN.+++4444444444444444444444t444f444444444404tt440tfff444f4444


+++44444444444444444444444444444444f 4f 44f 44 NUTECH 444444444444444 444444444444444 PRISIM 444444444444044444 PAGE , 133 REVISION, RRS1 DATE 85/12/05 CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 44444~4444444444444444444404444t044444tf444tf444444444444444444 REFERENCE KEY DESCRIPTION 81W-0189.11 81W-0189.12 81W-0189.20 81W-0189.21 81W-0189.22 81W-0189.30 8 1W-0189.31 81W-0189.32 81W" 0189.40 81W-0189.99 81W-01C1.81W-01C1.1 81W-01C1.10 81W-01C1.20 81W-01C1.30 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE>=4 IN.LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE>=4 IN.+++PIPING NOMINAL PIPE SIZE<4 IN.+++CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE<4 IN.LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE<4 IN.+++BRANCH PIPE CONNECTION WELDS+++BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE>=4 IN.BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE<4 IN.PIPE SOCKET WELDS+++ITEM NUMBERS 810.XX THROUGH 816.XX APPEAR AFTER 81.51++++++EXAMINATION CATEGORY C-A++++++PRESSURE VESSELS+++
44404444444444444444444444444444444444t4444 NUTECH                                                               PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT     1 PLANNING REFERENCE CLUSTER LISTING               444444444444444444 DATA ELEMENT : EXREQ                    PAGE         34 REVISION   RRS 1 DATE   85/12/04 REFERENCE KEY                           DESCRIPTION
PRESSURE VESSEL SHELL CIRCUMFERENTIAL WELDS PRESSURE VESSEL HEAD CIRCUMFERENTIAL WELDS PRESSURE VESSEL TUBESHEET-TO-SHELL WELD 4444444444444444444444444f44444f444f440444444tf4444444444444444444444444444 NUTECH 44444444 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 444tt4444444t44f44444f444444f 444444444444444 PRI SIM 4444444444t4444f44 PAGE 134 REVISION RRS 1 DATE 85/12/05 444444444444444444444444444444444444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 81W-01C2.81W-01C2.1 81W-01C2.10 81W-01C2.11 81W-01C2.20 81W-01C2.21 81W-01C2.22 81W-01C2.30 81W-01C2.31 81W-01C2.32 81W-01C2.32A 81W-01C2.32 I+++EXAMINATION CATEGORY C-B++++++PRESSURE VESSELS+++
              ++  ALL ENTRIES IN THE EXREQ REFERENCE DESCRIPTION SHOULD BE CENTERED  LIKE A REPORT TITLE. THIS DESCRIPTION IS USED IN COMPONENT  LISTING (AND 10 YEAR PLAN), THE (INSERVICE)
+++NOZZLES IN VESSELS<=1/2 IN.NOMINAL THICKNESS+++
INSPECTION STATUS REPORT, AND VARIOUS OTHER REPORTS IN THE REPORT TITLE. +++
NOZZLES-TO-SHELL(OR HEAD)WELD+++NOZZLES WITHOUT REINFORCING PLATE IN VESSELS 1/2 IN.NOMINAL THICKNESS+++
              +++ EXREQ'S WITH A FIRST CHARACTER OF "A" ARE USED TO TRACK INSPECTION PROGRAMS KNOWN AS ADDITIONAL EXAMINATIONS.
NOZZLE-TO-SHELL(OR HEAD)WELD NOZZLE INSIDE RADIUS SECTION IN VESSELS+++NOZZLES WITH REINFORCING PLATE IN VESSELS 1/2 IN.NOMINAL THICKNESS+++
IF UNACCEPTABLE INDICATIONS ARE FOUND IN A COMPONENT, OTHER (ADDITIONAL) COMPONENTS MUST BE EXAMINED IN ACCORDANCE WITH ASME SECTION XI, IWB-2430 AND IWC-2430, (81W) .       +++
REINFORCING PLATE WELDS TO NOZZLE AND VESSEL+++NOZZLE-TO-SHELL (OR HEAD)WELDS+++INSIDE OF VESSEL ACCESSIBLE, NOZZLE-TO-SHELL (OR HEAD)WELD INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM.CAT.C-F WHEN THE INSIDE OF THE VESSEL IS ACCESSIBLE.
              +++ EXREQ'S WITH A FIRST CHARACTER OF "8" ARE USED TO TRACK EXAMINATION PROGRAMS THAT ARE REQUIRED BY A REGULATORY BODY SUCH AS THE NRC. THESE AUGMENTED EXAMINATION PROGRAMS ARE NOT BASED ON SECTION XI. +++
INSIDE OF VESSEL INACCESSIBLE, NOZZLE-TO-SHELL(OR HEAD)WELD I INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM.CAT.C-F WHEN THE INSIDE OF THE VESSEL IS INACCESSIBLE.
802-01        802-01  AUGMENTED EXAMINATION COMPONENT LISTING  INTERVAL 01 REACTOR COOLANT PUMP FLYWHEEL INTEGRITY PER REGULATORY GUIDE 1. 14 802-01 AUGMENTED EXAMINATION STATUS REPORT  INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS    : APPLICABLE, 40 MONTHS LONG 803-01        AVAILABLE FOR FUTURE USE 804-01        804-01  AUGMENTED EXAMINATION COMPONENT LISTING  INTERVAL 01 AUGMENTED EXAMINATION OF CLASS 2 PIPING FROM PENETRATION TO CONTAINMENT ISOLATION VALVE PER FSAR SECTION      6.6.8.
444tlff44444444t44444444f444444t44f44t444444444444 e e
804-01 AUGMENTED EXAMINATION STATUS REPORT  INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE 44444444f4444440444444044t44444fJf440444444f44444444444
+44444444444444f444444444444440444444444444444f44444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 4444440t44 PRISIM 444444044444444444 PAGE 135 REVISION'RRS1 DATE 85/12/05 44444f844t4 REFERENCE KEY DESCRIPTION 81W-01C3.81W-01C3.1 81W-01C3.10 81W-01C3.2 81W-01C3.20 81W-01C3.3 81W-01C3.30 81W-01C3.4 81W-01C3.40 81W-01C4.81W-01C4.1 81W-01C4.10 81W-01C4.2 81W-01C4.20 81W" 01C4.3+++EXAMINATION CATEGORY C-C++++++PRESSURE VESSELS+++
PRESSURE VESSEL INTEGRALLY WELDED ATTACHMENTS
+++PIPING+++
PIPING INTEGRALLY WELDED ATTACHMENTS
+++PUMPS+++
PUMP INTEGRALLY WELDED ATTACHMENTS
+++VA1VFS+++
VALVE INTEGRALLY WELDED ATTACHMENTS
+++EXAMINATION CATEGORY C-D++++++PRESSURE VESSELS+++
PRESSURE VESSEL BOLTS AND STUDS (>2")+++PIPING+++
PIPING BOLTS AND STUDS (>2")+++PUMPS+++
44444444444444444444404444444444444444444t44444444444t404444444444444444444


eeeeeeeteteeeeeeteeeeeeeeeeeeeeeeeeteeeeeeeeeeeeeee J e seeeeeeeeeeeeee NUTECH t CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee PRISIM PAGE 136 REVISION RRS1 DATE 85/12/05 eeeeeeeeeeeeeeeeee REFERENCE KEY DESCRIPTION 81W-01C4.30 81W-01C4.4 81W-01C4.40 81W-01CS.81W-01C5.I 81W-01CS.10 81W-01C5.11 81W-01C5.12 81W-01CS.20 81W-01C5.21 81W-01CS.22 81W-01CS.30 81W-01CS.31 81W-0 I C5.32 8 1W-01C6.PUMP BOLTS AND STUDS (>2")+++VALVES+++
tttttttttttttttttttttttttttttttttttttttttttttttttttttttt+ttttttttttttttt NUTECH                                                             PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT     1 PLANNING REFERENCE CLUSTER LISTING                       tttttttttt DATA ELEMENT : EXREQ                  PAGE         35 REVISION   RRS1 DATE 85/12/04 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                             DESCRIPTION 805-01          805-01  AUGMENTED EXAMINATION COMPONENT LISTING  INTERVAL 01 AUGMENTED ISI EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK EXCLUSION REGION PER FSAR SECTION    6.6.8.
VALVE BOLTS AND STUDS (>2")+++EXAMINATION CATEGORY C-F++++++PIPING+++
805-01 AUGMENTED EXAMINATION STATUS REPORT -INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE 806-01          806-01  AUGMENTED EXAMINATION COMPONENT LISTING INTERVAL 01 AUGMENTED ISI EXAMINATION OF PIPING: BETWEEN ISOLATION VALVES THROUGH PENETRATIONS PER FSAR SECTION    6.6.8.
+++PIPING WELDS<=1/2 IN.NOMINAL WALL THICKNESS+++
806-01 AUGMENTED EXAMINATION STATUS REPORT- INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE
PIPING CIRCUMFERENTIAL WELD<=1/2" NOMINAL WALL THICKNESS PIPING LONGITUDINAL WELD<=1/2" NOMINAL WALL THICKNESS+++PIPING WELDS>1/2 IN.NOMINAL WALL THICKNESS+++
                +++   EXREQ'S WITH A FIRST CHARACTER OF "E" ARE USED TO TRACK ASME SECTION XI EXAMINATION PROGRAMS FOR THE FIRST INTERVALS OF OLDER PLANTS WHERE THE 1971 EDITION OF ASME SECTION XI WAS THE CODE IN EFFECT AT THE START OF THE INTERVAL. +++
PIPING CIRCUMFERENTIAL WEI.D>1/2" NOMINAL WALL THICKNESS PIPING LONGITUDINAL WELD>1/2" NOMINAL WALL THICKNESS+++PIPING BRANCH CONNECTIONS+++
                +++   EXREQ'S WITH A FIRST CHARACTER OF "P" ARE USED TO TRACK ASME SECTION  XI PRESERVICE (PSI ) INSPECTION PROGRAMS. +++
PIPE BRANCH CONNECTION CIRCUMFERENTIAL WELD PIPE BRANCH CONNECTION LONGITUDINAL WELD+++EXAMINATION CATEGORY C-G+++eeeeeteeeeeetteeteeeeeeeeeeeeeeeeeteeeeeeeeteeeeeeteeeeeeeeeeeeeeeeeeeeeeee m~4'4444444444444444444444444444444444444444444'044444444444 44t44444t444444 NUTECH PRI SIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REF ERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ITEMNO PAGE , 137 REVISION RRS1 DATE 85/12/05 4444444f4044444444444444 REFERENCE KEY DESCRIPTION 81W-01C6.1 81W-01C6.10 81W-01C6.2 81W-01C6.20 8 IW-01C7.81W-01C7.EX 81W-01C7.1 81W-01C7.10+++PUMPS+++
P01-01          P01-01 PRESERVICE INSPECTION    COMPONENT LISTING  INTERVAL 01 PRESERVICE INSPECTION OF COMPONENTS BASED ON SECTION XI 1980 EDITION THROUGH AND INCLUDING THE WINTER 1981 ADDENDA P01-01 PRESERVICE INSPECTION STATUS REPORT  INTERVAL 01 INTERVAL PERIODS:     NOT APPLICABLE P02-01          P02-01 AUGMENTED EXAMINATION COMPONENT LISTING PSI REACTOR COOLANT PUMP FLYWHEEL INTEGRITY PER REGULATORY GUIDE  1.14 P02-01 AUGMENTED EXAMINATION STATUS REPORT  - PSI INTERVAL PERIODS:     NOT APPLICABLE
PUMP CASING WELDS+++VALVES+++
VALVE BODY WELDS+++EXAMINATION CATEGORY C-H+++EXEMPT CLASS 2 PRESSURE RETAINING COMPONENTS 1)IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.2)EXEMPT CLASS 2 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.(E.G.WELDS<=4" NPS)+++PRESSURE VESSELS+++
PRESSURE VESSEL PRESSURE RETAINING COMPONENTS
-OPERATIONAL 81W"01C7.20 PRESSURE VESSEL PRESSURE RETAINING COMPONENTS
-STATIC 81W-01C7.3 81W-01C7.30 81W-01C7.40 81W-01C7.5+++PIPING+++
PIPING PRESSURE RETAINING COMPONENTS
-OPERATIONAL PIPING PRESSURE RETAINING COMPONENTS
-STATIC+++PUMPS+++
44444444044444444444444444444444444444f4t44444444440444440444444f44444tf444 444404444444444444444444444444444444444+
NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444404444 DATA ELEMENT: ITEMNO PAGE 138 REVISION'RS1 4 DATE 85/12/05 4444444t444t44t444444t4444444444444444f444f444444444f4444 REFERENCE KEY DESCRIPTION 81W-01C7.50 PUMPS PRESSURE RETAINING COMPONENTS
-OPERATIONAL 81W-01C7.60 PUMPS PRESSURE RETAINING COMPONENTS
-STATIC 81W-01C7.7+++VALVES+++
81W-01C7.70 VALVES PRESSURE RETAINING COMPONENTS
-OPERATIONAL 81W-01C7.80 VALVES PRESSURE RETAINING COMPONENTS
-STATIC 81W-01D1+++EXAMINATION CATEGORY 0-A+++81W-0101.1+++SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION+++
81W-01D1.1EX 81W-01D1.100 81W-01D1.10S EXEMPT CLASS 3 CATEGORY D-A PRESSURE RETAINING COMPONENTS 1)IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.2)EXEMPT CLASS 3 COMPONENTS ENTEREO IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.(E.G.<=4" PIPE ATACHES)RV SHUTDOWN PRESSURE RETAINING COMPONENTS
-OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL.A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.OPERATIONAL:
SYS FUNCTIONAL, SYS INSERVICE, OR SYS LEAKAGE RV SHUTDOWN PRESSURE RETAINING COMPONENTS
-STATIC A SYSTEM STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL.STATIC: HYDROSTATIC OR PNEUMATIC 444444444444444444444444444t4444444444444444444444444444444444444444t444444
+sttttttttttttttttttttttttttttttttttttttttttttt,tttttttttt tttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY t SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING t t REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: ITEMNO PAGE 139 t REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-0101.20 81W-0101.30 81W-01D1.40 81W-0101.50 81W-0101.60 8 1W-0102.81W-0102.1 81W-0102.1EX 81W-01D2.100 RV SHUTDOWN INTEGRAL ATTACHMENTS
-SUPPORTS AND RESTRAINTS RV SHUTDOWN INTEGRAL ATTACHMENTS
-SNUBBERS RV SHUTDOWN INTEGRAL ATTACHMENTS
-MECHANICAL AND HYDRAULIC SNUBBERS RV SHUTDOWN INTEGRAL ATTACHMENTS
-SPRING TYPE SUPPORTS RV SHUTDOWN INTEGRAL ATTACHMENTS-CONSTANT LOAD TYPE SUPPORTS RV SHUTDOWN INTEGRAL ATTACHMENTS
-SHOCK ABSORBERS+++EXAMINATION CATEGORY D-8++++++SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL+++
I EXEMPT CLASS 3 CATEGORY 0-B PRESSURE RETAINING COMPONENTS 1)IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.2)EXEMPT CLASS 3 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.(E.G.<=4" PIPE ATACHES)ECCS, ETC.PRESSURE RETAINING COMPONENTS
-OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL.A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.OPERATIONAL:
SYS FUNCTIONAL, SYS INSERVICE~OR SYS LEAKAGE


4444444444t44f4444444f44444444444444444
44444444444444444440440 444444444444044444444t4444444444            444444444444444 NUTECH                                                                     PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT     - UNIT 1 PLANNING REFERENCE CLUSTER LISTING                 444444444444444444 DATA ELEMENT : EXREQ                      PAGE           36 REVISION   RRS1 DATE   85/12/04 444 '4 4444440444444  4444444444444444444444444444444444444444'44444'444f4 REFERENCE KEY                                 DESCRIPTION P03-0  I          AVAILABLE FOR FUTURE USE P04-01                P04-01 AUGMENTED EXAMINATION COMPONENT LISTING  PSI AUGMENTED EXAMINATION OF CLASS 2 PIPING FROM PENETRATION
+44444444444444 NUTECH PRISIM CAROLINA POWER&LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 4440t44t44044444 DATA ELEMENT: ITEMNO PAGE 140 REVISION RRS1 DATE 85/12/05 408004444444444444444444444444444444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 81W-01D2.10S ECCS, ETC.PRESSURE RETAINING COMPONENTS
                  'TO CONTAINMENT ISOLATION VALVE PER FSAR SECTION 6.6.8 P04"01 AUGMENTED EXAMINATION STATUS REPORT      - PSI INTERVAL PERIODS    : NOT APPLICABLE P05-01                P05-01 AUGMENTED EXAMINATION COMPONENT LISTING        - PSI AUGMENTED PSI EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK EXCLUSION REGION PER FSAR SECTION          6.6.8.
-STATIC A SYSTEM STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL.STATIC: HYDROSTATIC OR PNEUMATIC 81W-01D2.20 ECCS, ETC.INTEGRAL ATTACHMENTS
P05-01 AUGMENTED EXAMINATION STATUS REPORT  PSI INTERVAL PERIODS:NOT APPLICABLE P06-01            P06-0'I AUGMENTED EXAMINATION COMPONENT LISTING  PSI AUGMENTED PSI EXAMINATION OF PIPING: BETWEEN ISOLATION VALVES THROUGH PENETRATIONS PER FSAR SECTION 6.6.8 P06-01 AUGMENTED EXAMINATION STATUS REPORT- PSI INTERVAL PERIODS:NOT APPLICABLE
-SUPPORTS AND RESTRAINTS 81W-01D2.30 ECCS, ETC.INTEGRAL ATTACHMENTS
                  +++ EXREQ'S WITH A FIRST CHARACTER OF "R" ARE USED TO TRACK INSPECTIONS OF COMPONENTS THAT HAVE BEEN REPAIRED OR REPLACED. ESSENTIALLY, THIS IS A PRESERVICE INSPECTION OF THE "NEW- COMPONENT BEFORE IT IS PLACED IN SERVICE.           +++
-SNUBBERS ECCS, ETC.INTEGRAL ATTACHMENTS
                  +++ 'EXREQ'S WITH A FIRST CHARACTER OF "S" ARE USED TO TRACK REPEAT (SUCCESSIVE) INSPECTIONS OF COMPONENTS THAT HAVE BEEN EXAMINED IN THE PAST AND HAD CONDITIONALLY ACCEPTABLE INDICATIONS. SUCCESSIVE EXAMINATIONS ARE REQUIRED IN ACCORDANCE WITH ASME SECTION XI, IWB-2420 AND IWC-2420, (81W) . +++
-MECHANICAL AND HYDRAULIC SNUBBERS 81W-0102.40 ECCS, ETC.INTEGRAL ATTACHMENTS
44444444444444444f444f4444444'40f44444444f'4444tft444444444444
-SPRING TYPE SUPPORTS 81W-01D2.50 ECCS, ETC.INTEGRAL ATTACHMENTS
-CONSTANT LOAD TYPE SUPPORT 81W-01D2.60 ECCS, ETC.INTEGRAL ATTACHMENTS
-SHOCK ABSORBERS 81W-0103.+++EXAMINATION CATEGORY D-C+++81W-0103.1 81W-01D3.1EX+++SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM THE SPENT FUEL STORAGE POOL+++EXEMPT CLASS 3 CATEGORY D-C PRESSURE RETAINING COMPONENTS 1)IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY'SSIGN THIS ITEM NUMBER.2)EXEMPT CLASS 3 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER.(E.G.<=4" PIPE ATACHES)4'4444444444444tf44444444444f4444ftffff44440 444444444444444444444t444444444444 44444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444440444 DATA ELEMENT: ITEMNO PAGE.141 REVISION RRS1 DATE 85/12/05 4444444444444444f4f4f444f444ff444444f44f4ffOtf4f444444f444444444444ft44t4f4 REFERENCE KEY DESCRIPTION 81W-0103.100 81W-0103.10S RHR FROM SFS PRESSURE RETAINING COMPONENTS
-OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL.A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.OPERATIONAL:
SYS FUNCTIONAL, SYS INSERVICE, OR SYS LEAKAGE RHR FROM SFS PRESSURE RETAINING COMPONENTS
-STATIC A SYSTEM STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL.STATIC: HYDROSTATIC OR PNEUMATIC 81W-01D3.20 8 1W-0'I 03.30 81W-01D3.40 81W-01D3.50 8 1W-01D3.60 81W-01E1.81W-01E1.1 RHR FROM SFS INTEGRAL ATTACHMENTS
-SUPPORTS AND RESTRAINTS RHR FROM SFS INTEGRAL ATTACHMENTS
-SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS
-MECHANICAL AND HYDRAULIC SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS
-SPRING TYPE SUPPORTS RHR FROM SFS INTEGRAL ATTACHMENT-CONSTANT LOAD TYPE SUPPORTS RHR FROM SFS INTEGRAL ATTACHMENTS
-SHOCK ABSORBERS+++EXAMINATION CATEGORY E-A++++++PRESSURE RETAINING WELDS IN CONTAINMENT VESSELS+++
4444444t4444444t444444444444f444f44ff444444tf44
++'54444444444444444f 44444444444444444444444444444444444444 444444444444440 4 NUT ECH CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRISIM 4444444444444t444f PAGE: 142 REVISION RRS 1 DATE 85/12/05 44444444444444444444444404444404ir444444444444 REFERENCE KEY DESCRIPTION 81W-01E1.10 81W-01E1.11 81W-01E1.12 81W-01E1.20 81W-01E1.30 81W-01E1.40 81W-01E1.41 81W-01E1.42 81W-01E1.43 81W-01E1.50 81W"0 IE1.51 81W-01E1.52 81W-01E1.53 81W-01E2.81W-01E2.1+++SHELL WELDS IN CONTAINMENT VESSELS+++
LONGITUDINAL SHELL WELDS IN VESSELS (CATEGORY A)CIRCUMFERENTIAL SHELL WELDS IN VESSELS (CATEGORY 8)FLANGE WELDS IN VESSELS (CATEGORY C)NOZZLE-TO-SHELL WELDS IN VESSELS (CATEGORY D)+++INSERT PLATE WELDS+++INSERT PLATE-TO-SHELL WELDS LONGITUDINAL INSERT PLATE WELDS CIRCUMFERENTIAL INSERT PLATE WELDS+++VENT SYSTEM WELDS+++LONGITUDINAL VENT SYSTEM WELDS CIRCUMFERENTIAL VENT SYSTEM WELDS OTHER VENT SYSTEM WELDS+++EXAMINATION CATEGORY E-A-1++++++NONPRESSURE-RETAINING WELDS+++44444444t4444444f44t44f444444444t444444444t4444f44444tt4444444444444t444 44404f44t4t44f44444444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO 4044444444448444444444444444444444t44444444444t444t44t444 444440044444444 PRISIM PAGE 143 REVISION RRS 1 REFERENCE KEY DESCRIPTION 81W-01E2.10 81W-01E2.1 1 81W-01E2.12 81W-01E2.20 81W-01E3.81W-0163.1 81W-01E3.10 81W-01E3.1 I 81W-01E3.12 81W-01E3.13 81W-01E4.81W-01E4.1+++REINFORCING STRUCTURE WELDS+++CONTAINMENT VESSEL ATTACHMENT REINFORCING STRUCTURE WELDS OTHER REINFORCING STRUCTURE WELDS REINFORCING STRUCTURE ATTACHMENT WELDS+++EXAMINATION CATEGORY E-8++++++PRESSURE RETAINING WELOS IN CONTAINMENT PENETRATIONS+++
+++CONTAINMENT PENETRATION WELDS+++LONGITUDINAL CONTAINMENT PENETRATION WELDS CIRCUMFERENTIAL CONTAINMENT PENETRATION WELDS FLUED HEAD AND BELLOWS SEAL CIRC WELDS JOINED TO THE PENET FLUED HEAD AND BELLOWS SEAL CIRCUMFERENTIAL WELDS JOINED TO THE PENETRATION.
+++EXAMINATION CATEGORY E-C++++++PRESSURE RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES+++
81W-01E4.10+++AIRLOCK WELDS+++444444444444444444444444444444444448444444444444444444444444444444444444444 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO PRISIM tttttttttttttttttt PAGE 144 REVISION RRS 1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-01E4.11 81W-01E4.12 81W-01E4.20 81W-01E4.21 81W-01E4.22 81W"01ES.81W-01E5.1 81W-01ES.10 81W-01E5.20 81W-01E6.81W-01E6.1 81W-01E6.10 8 1W-0 I Ej.81W-01E7.1 81W-01E7.10 LONGITUDINAL AIRLOCK WELDS CIRCUMFERENTIAL AIRLOCK WELDS+++EQUIPMENT HATCH WELDS+++LONGITUDINAL EQUIPMENT HATCH WELDS CIRCUMFERENTIAL EQUIPMENT HATCH WELDS+++EXAMINATION CATEGORY E-D++++++SEALS AND GASKETS+++
SEALS GASKETS+++EXAMINATION CATEGORY E-E++++++INTEGRAL ATTACHMENTS+++
INTEGRAL ATTACHMENT WELDS+++EXAMINATION CATEGORY E-F++++++PRESSURE RETAINING DISSIMILAR METAL WELDS+++DISSIMILAR METAL WELDS


~44444444444444444t4444444444t44444444444444444444444$
t ttttttttttttttttttttttttttttttttttttttttttt NUTECH                                                           PRISIM CAROLINA POWER, 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT   I PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : EXREQ                  PAGE       37 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                           DESCRIPTION
4 NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: ITEMNO+4444444444444t PRISIM 444444444444844444 PAGE 145 REVISION RRS1 DATE 85/12/05 444444444t4ftt44t44444440tt4444444444444444r444044444tt044444t4444t REFERENCE KEY DESCRIPTION 81W-01EB.+++EXAMINATION CATEGORY E-G+++81W-01EB.1+++PRESSURE RETAINING BOLTING+++
              +++ EXREQ'S WITH A FIRST CHARACTER OF   "V" ARE USED TO TRACK VOLUNTARY INSPECTION PROGRAMS.   +++
81W-01EB.10+++BOLTED CONNECTION VISUAL EXAMINATION+++
V01-01                V01-01 VOLUNTARY EXAMINATION COMPONENT LISTING VOLUNTARY EXAMINATION-CLASS 1,2,83 COMPONENTS PSI AND 1ST INTERVAL ISI V01-01 VOLUNTARY EXAMINATION STATUS REPORT INTERVAL:
81W-01EB.10A 81W-01EB.10D BOLTED CONNECTION VISUAL EXAMINATION ALL VISIBLE SURFACES SHALL BE EXAMINED.BOLTING MAY REMAIN IN PLACE UNDER TENSION WHEN DISASSEMBLY IS NOT OTHERWISE REQUIRED.BOLTED CONNECTION VISUAL EXAMINATION EXAMINATION OF BUSHINGS, THREADS, AND LIGAMENTS IN BASE MATERIAL OF FLANGES IS REQUIRED ONLY WHEN THE CONNECTION IS DISASSEMBLED.
PERIODS  : NOT APPLICABLE
81W-01E8.20
              +++  EXREQ'S WITH A FIRST CHARACTER THAT IS NUMERIC (N) ARE USED TO TRACK THE ASME SECTION XI EXAMINATION PROGRAM(S)
+++BOLTED CONNECTION BOLT TORQUE OR TENSION TEST+++81W-01E8.20A 8 IW-01EB.20D BOLTED CONNECTION BOLT TORQUE OR TENSION TEST ALL VISIBLE SURFACES SHALL BE EXAMINED.BOLTING MAY REMAIN IN PLACE UNDER TENSION WHEN DISASSEMBLY IS NOT OTHERWISE REQUIRED.BOLTED CONNECTION BOLT TORQUE OR TENSION TEST I EXAMINATION OF BUSHINGS, THREADS, AND LIGAMENTS IN BASE MATERIAL OF FLANGES IS REQUIRED ONLY WHEN THE CONNECTION IS DISASSEMBLED.
APPLICABLE TO EACH INSPECTION INTERVAL. (SEE EXREQ'S STARTING WITH "E" FOR THE ONLY EXCEPTION TO THIS RULE) +++
4f4444f4444444444444444444444f4444444f44444444t4444ft4444444444444444444444
12W-04        TESTING OF THE FOURTH INTERVAL 81W-01              COMPONENT LISTING AND ISI 10 YEAR PLAN: 81W-01 ASME SECTION XI, 1980 EDITION THROUGH AND INCLUDING THE WINTER 1981 ADDENDA, INTERVAL 01 ONLY INSERVICE INSPECTION STATUS REPORT: 81W-01 90W-02        TESTING OF SECOND INTERVAL 99W-03        TESTING OF THE THIRD INTERVAL ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt
+4ft4444444444444444444444444t4tt4444f44444444444444t444 44444444444'444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: ITEMNO PAGE,1 46 REVISION RRS1 DATE 85/12/05 44444$4444444444f444444444ft44t44t44444444444$
44f44044444f44444404fft444444 REFERENCE KEY DESCRIPTION 81W-01E9.81W-01E9.EX 81W-01E9.1 81W-01E9.10 81W-01E9.11 81W-01E9.12 81W-01E9.20 81W-01E9.30 81W-01E9.40 81W-01F1.81W-01F1.EX 81W-01F1.1+++EXAMINATION CATEGORY E-P+++EXEMPT CLASS MC PRESSURE RETAINING COMPONENTS
+++ALL PRESSURE RETAINING COMPONENTS+++
+++PRESSURE RETAINING BOUNDARY+++
10-CFR-50 APPENDIX J TEST OF CONTAINMENT BOUNDARY SYS LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY SYSTEM LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY.CONTAINMENT PENET BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST)CONTAINMENT PENETETRATION BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST).AIRLOCKS (10CFR50 APPENDIX J TYPE 8 TESTS)SEALS AND GASKETS (10CFR50 APPENDIX J TYPE 8 TESTS)+++EXAMINATION CATEGORY F-A+++EXEMPT CLASS 1, 2, OR 3 CATEGORY F-A COMPONENT SUPPORTS+++PLATE AND SHELL TYPE SUPPORTS+++
4444444t4444444444444fft440f4444f444444f4444f+444444404t44444444444444f44t4
+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt t NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 t PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: ITEMNO PAGE, 147 REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-01F1.10 81W-01F1.-20 81W-01F1.30 8 1W-01F 1.40 8 1W-01F2.81W-0 I F2.EX 81W-01F2.1 81W-01F2.10 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE WELDED CONNECTIONS TO BUILDING STRUCTURE WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS DISPLACEMENT SETTINGS'ISALIGNMENT'ND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS+++EXAMINATION CATEGORY F-8+++EXEMPT CLASS 1, 2, OR 3 CATEGORY F-8 COMPONENT SUPPORTS+++LINEAR TYPE SUPPORTS+++
MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING I MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE 81W"01F2.20 WELDED CONNECTIONS TO BUILDING STRUCTURE ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH tttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-'NIT 1 t PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: ITEMNO PAGE 148 REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-01F2.30 81W-01F2.40 81W-01F2.50 81W-01F3.81W-0 I F3.EX 81W-01F3.1 81W-01F3.10 81W-01F3.20 81W-01F3.30 WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS INVALID ITEMNO ttt THIS ITEMNO IS INVALID+++EXAMINATION CATEGORY F-C+++EXEMPT CLASS 1, 2, OR 3 CATEGORY F-C COMPONENT SUPPORTS+++COMPONENT STANDARD SUPPORTS+++
MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT ANO BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE WELDED CONNECTIONS TO BUILDING STRUCTURE WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD ANO MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS ee,e4444444444444444444444444444448444444444444444444404444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444404 DATA ELEMENT: ITEMNO PAGE 149 REVISION RRS1 DATE 85/12/05 444444444444444444444444444440440040004004404444044044444444444444444404440 REFERENCE KEY DESCRIPTION 81W-01F3.40 81W-01F3.50 DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT I COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS SPRING, CONSTANT, SHOCK ABSORBER, AND SNUBBER SUPPORTS SPRING TYPE SUPPORTS, CONSTANT LOAD TYPE SUPPORTS, SHOCK AB-SORBERS, HYDRAULIC AND MECHANICAL TYPE SNUBBERS 444ff4444444444444404444444444f4444tt44f4444444444444444t44ff4
~tttttttttttttttttt NUTECH tttttttttttttttttt CAROLINA POWER L LIGHT COMPANY SYSTEM tttttttttttttttt ttttttttttttttt PRISIM REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT: EXSCHD PAGE 64 REVISION RRS1 DATE 85/12/04 tttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION AE ET MT PT RT RT-RCP SUR UC-45L UT-IN UT-L UT-OUT UT-RVN UT-RVS UT-SN1 ACOUSTIC EMISSION TEST EDDY CURRENT TEST MAGNETIC PARTICLE TEST PENETRANT TEST RADIOGRAPHIC TEST MINAC RADIOGRAPHIC TEST SURFACE EXAMINATION, TEST NOT SPECIFIED NOTE: THIS MUST BE UPDATED TO A PT OR MT BEFORE THE EXAM IS SCHEDULED ULTRASONIC CIRCUMFERENTIAL SCAN-45 DEGREE LONGITUDINAL ULTRASONIC TEST IN-PLACE, CATEGORY B-G-1, BOLTING ULTRASONIC LAMINATION TEST ULTRASONIC TEST WHEN REMOVED (OUT), CATEGORY B-G-1, BOLTING REACTOR VESSEL NOZZLE MECHANIZED ULTRASONIC TEST REACTOR VESSEL SHELL MECHANIZED ULTRASONIC TEST ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE NOZZLE SIDE WITH THE NOZZLE CALIBRATION BLOCK.ULTRASONIC BEAM ANGLE=000 DEGREES ttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT: EXSCHD ttttttttttttttttttttttttttttttttttttttttttttttttttt PRISIM tttttttttttttttttt PAGE 65 REVISION RRS1 REFERENCE KEY DESCRIPTION UT-SN2 UT-SP1 UT-SP2 ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE NOZZLE SIDE WITH THE NOZZLE CALIBRATION BLOCK.ULTRASONIC BEAM ANGLE=045 DEGREES ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE PIPING SIDE WITH THE PIPING CALIBRATION BLOCK.ULTRASONIC BEAM ANGLE=000 DEGREES ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE PIPING SIDE WITH THE PIPING CALIBRATION BLOCK.ULTRASONIC BEAM ANGLE=045 DEGREES UT-T UT-00 UT-30S UT-41L UT-41R UT-41S UT-45 UT-45L UT-45R ULTRASONIC THICKNESS TEST ULTRASONIC 0 DEGREE TEST ULTRASONIC 30 DEGREE TEST-SHEAR ULTRASONIC 41 DEGREE TEST-LONGITUDINAL ULTRASONIC 41 DEGREE TEST-REFRACTED LONGITUDINAL ULTRASONIC 41 DEGREE TEST-SHEAR ULTRASONIC 45 DEGREE TEST-(TO BE SPECIFIED)
ULTRASONIC 45 DEGREE TEST-LONGITUDINAL ULTRASONIC 45 DEGREE TEST-REFRACTED LONGITUDINAL 44ICf 4444f 44 NUTECH PRISIM REFERENCE CLUSTER LISTING 444440444044444444 DATA ELEMENT: EXSCHD PAGE , 66 REVISION RRS1 DATE 85/12/04 CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4444444444444t4444444444444t4444t4444444t4444444444444444444444444444444444 REFERENCE KEY DESCRIPTION UT-45S UT-50S UT-53S UT-60 UT-60L UT-60R UT-60S UT-62S UT-70S UTAUTO VIS VOL VT-1 VT-2 ULTRASONIC 45 DEGREE TEST-SHEAR ULTRASONIC 50 DEGREE TEST-SHEAR ULTRASONIC 53 DEGREE TEST-SHEAR ULTRASONIC 60 DEGREE TEST-(TO BE SPECIFIED)
ULTRASONIC 60 DEGREE TEST-LONGITUDINAL ULTRASONIC 60 DEGREE TEST-REFRACTED LONGITUDINAL ULTRASONIC 60 DEGREE TEST-SHEAR ULTRASONIC 62 DEGREE TEST-SHEAR ULTRASONIC 70 DEGREE TEST-SHEAR ULTRASONIC MECHANIZED 0 DEGREE EXAMINATION GENERAL VISUAL TEST VOLUMETRIC EXAMINATION, TEST NOT SPECIFIED NOTE: THIS MUST BE UPDATED TO AE, RT, OR UT BEFORE THE THE EXAMINATION IS SCHEDULED VISUAL TEST 1 PER IWA-2210 (77W AND LATER ADDENDA)VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA)NOTE:
VT-2 IS APPLICABLE TO CATEGORY B-E AND CATEGORY B-P, C-H.D-A, D-B, AND D-C IF THE ITEM NUMBER IS B15.EX, C7.EX, D1.EX, D2.EX OR D3.EX


4444444444 NUTECH 4 eesseeeee+eeeeeeeessseseeeeeeesseseeeeeeeesees
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PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT: EXSCHD PAGE 67+REVISION RRS1 DATE 85/12/04 44tf44044444444404444f44444f04044f REFERENCE KEY DESCRIPTION VT-20T VT-2ST VT-3 VT-4 VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA)OPERATIONAL PRESSURE TESTING NOTE: VT-20T IS APPLICABLE TO ITEM NUMBERS 815.10, 815.20, 815.30, 815.40, 815.50, 815.60, 815.70, C7.10, C7.20, C7.30, C7.40, D1.10, D2.10, 03.10 VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA)STATIC PRESSURE TESTING NOTE: VT-2ST IS APPLICABLE TO ITEM NUMBERS 815.11, 815.21, 815.31, 815.41, 815.51, 815.61, 815.71, C7.11, C7.21, C7.31, C7.41, D1.11, 02.11, C3.11 VISUAL TEST 3 PER IWA-2210 (77W AND LATER ADDENDA)VISUAL TEST 4 PER IWA-2210 (77W AND LATER ADDENDA)444444444444444444444444444444444444444404444444444404404404440440440444444 EXAM REQUXPEMENT SOURCE a)ANN-NN~Interval Number Program Number Type of Program Example: P01"01 Preservice Section XX Program Interval-1: Preservice is considered to be an interval for computer purposes~P02-01 Preservice Augmented Program B02-03.Xnservice Augmented Program corresponding to P02-01 b)81M-01~Interval Number Code Addendum f'r Xnservice Program NUTECH CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: EXREQ 44404444444444444444444444444444444444t4444 PRISIM 444444444444444444 PAGE 34 REVISION RRS 1 DATE 85/12/04 REFERENCE KEY DESCRIPTION 802-01 803-01 804-01++ALL ENTRIES IN THE EXREQ REFERENCE DESCRIPTION SHOULD BE CENTERED LIKE A REPORT TITLE.THIS DESCRIPTION IS USED IN COMPONENT LISTING (AND 10 YEAR PLAN), THE (INSERVICE)
INSPECTION STATUS REPORT, AND VARIOUS OTHER REPORTS IN THE REPORT TITLE.++++++EXREQ'S WITH A FIRST CHARACTER OF"A" ARE USED TO TRACK INSPECTION PROGRAMS KNOWN AS ADDITIONAL EXAMINATIONS.
IF UNACCEPTABLE INDICATIONS ARE FOUND IN A COMPONENT, OTHER (ADDITIONAL)
COMPONENTS MUST BE EXAMINED IN ACCORDANCE WITH ASME SECTION XI, IWB-2430 AND IWC-2430, (81W).++++++EXREQ'S WITH A FIRST CHARACTER OF"8" ARE USED TO TRACK EXAMINATION PROGRAMS THAT ARE REQUIRED BY A REGULATORY BODY SUCH AS THE NRC.THESE AUGMENTED EXAMINATION PROGRAMS ARE NOT BASED ON SECTION XI.+++802-01 AUGMENTED EXAMINATION COMPONENT LISTING-INTERVAL 01 REACTOR COOLANT PUMP FLYWHEEL INTEGRITY PER REGULATORY GUIDE 1.14 802-01 AUGMENTED EXAMINATION STATUS REPORT-INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: APPLICABLE, 40 MONTHS LONG AVAILABLE FOR FUTURE USE 804-01 AUGMENTED EXAMINATION COMPONENT LISTING-INTERVAL 01 AUGMENTED EXAMINATION OF CLASS 2 PIPING FROM PENETRATION TO CONTAINMENT ISOLATION VALVE PER FSAR SECTION 6.6.8.804-01 AUGMENTED EXAMINATION STATUS REPORT-INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE 44444444f4444440444444044t44444fJf440444444f44444444444 tttttttttttttttttttttttttttttttttttttttttttttttttttttttt
+ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttt DATA ELEMENT: EXREQ PAGE 35 REVISION RRS1 DATE 85/12/04 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 805-01 806-01 P01-01 P02-01 805-01 AUGMENTED EXAMINATION COMPONENT LISTING-INTERVAL 01 AUGMENTED ISI EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK EXCLUSION REGION PER FSAR SECTION 6.6.8.805-01 AUGMENTED EXAMINATION STATUS REPORT-INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE 806-01 AUGMENTED EXAMINATION COMPONENT LISTING-INTERVAL 01 AUGMENTED ISI EXAMINATION OF PIPING: BETWEEN ISOLATION VALVES THROUGH PENETRATIONS PER FSAR SECTION 6.6.8.806-01 AUGMENTED EXAMINATION STATUS REPORT-INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE
+++EXREQ'S WITH A FIRST CHARACTER OF"E" ARE USED TO TRACK ASME SECTION XI EXAMINATION PROGRAMS FOR THE FIRST INTERVALS OF OLDER PLANTS WHERE THE 1971 EDITION OF ASME SECTION XI WAS THE CODE IN EFFECT AT THE START OF THE INTERVAL.++++++EXREQ'S WITH A FIRST CHARACTER OF"P" ARE USED TO TRACK ASME SECTION XI PRESERVICE (PSI)INSPECTION PROGRAMS.+++P01-01 PRESERVICE INSPECTION COMPONENT LISTING-INTERVAL 01 PRESERVICE INSPECTION OF COMPONENTS BASED ON SECTION XI 1980 EDITION THROUGH AND INCLUDING THE WINTER 1981 ADDENDA P01-01 PRESERVICE INSPECTION STATUS REPORT-INTERVAL 01 INTERVAL PERIODS: NOT APPLICABLE P02-01 AUGMENTED EXAMINATION COMPONENT LISTING-PSI REACTOR COOLANT PUMP FLYWHEEL INTEGRITY PER REGULATORY GUIDE 1.14 P02-01 AUGMENTED EXAMINATION STATUS REPORT-PSI INTERVAL PERIODS: NOT APPLICABLE 44444444444444444440440 NUTECH 4 4 4'4 4 4 4 4 4 4 0 4 4 4 4 4 4 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: EXREQ 444444444444044444444t4444444444 444444444444444 PRISIM 444444444444444444 PAGE 36 REVISION RRS1 DATE 85/12/04 4444444444444444444444444444444444444444'44444'444f4 REFERENCE KEY DESCRIPTION P03-0 I P04-01 P05-01 P06-01 AVAILABLE FOR FUTURE USE P04-01 AUGMENTED EXAMINATION COMPONENT LISTING-PSI AUGMENTED EXAMINATION OF CLASS 2 PIPING FROM PENETRATION
'TO CONTAINMENT ISOLATION VALVE PER FSAR SECTION 6.6.8 P04"01 AUGMENTED EXAMINATION STATUS REPORT-PSI INTERVAL PERIODS: NOT APPLICABLE P05-01 AUGMENTED EXAMINATION COMPONENT LISTING-PSI AUGMENTED PSI EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK EXCLUSION REGION PER FSAR SECTION 6.6.8.P05-01 AUGMENTED EXAMINATION STATUS REPORT-PSI INTERVAL PERIODS:NOT APPLICABLE P06-0'I AUGMENTED EXAMINATION COMPONENT LISTING-PSI AUGMENTED PSI EXAMINATION OF PIPING: BETWEEN ISOLATION VALVES THROUGH PENETRATIONS PER FSAR SECTION 6.6.8 P06-01 AUGMENTED EXAMINATION STATUS REPORT-PSI INTERVAL PERIODS:NOT APPLICABLE
+++EXREQ'S WITH A FIRST CHARACTER OF"R" ARE USED TO TRACK INSPECTIONS OF COMPONENTS THAT HAVE BEEN REPAIRED OR REPLACED.ESSENTIALLY, THIS IS A PRESERVICE INSPECTION OF THE"NEW-COMPONENT BEFORE IT IS PLACED IN SERVICE.++++++'EXREQ'S WITH A FIRST CHARACTER OF"S" ARE USED TO TRACK REPEAT (SUCCESSIVE)
INSPECTIONS OF COMPONENTS THAT HAVE BEEN EXAMINED IN THE PAST AND HAD CONDITIONALLY ACCEPTABLE INDICATIONS.
SUCCESSIVE EXAMINATIONS ARE REQUIRED IN ACCORDANCE WITH ASME SECTION XI, IWB-2420 AND IWC-2420, (81W).+++44444444444444444f444f4444444'40f44444444f'4444tft444444444444 ttttttttttttttttttt t NUTECH tttttttttttttttttttttttt PRISIM PAGE 37 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttt CAROLINA POWER, 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT-UNIT I PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT: EXREQ REFERENCE KEY DESCRIPTION V01-01 12W-04 81W-01 90W-02+++EXREQ'S WITH A FIRST CHARACTER OF"V" ARE USED TO TRACK VOLUNTARY INSPECTION PROGRAMS.+++V01-01 VOLUNTARY EXAMINATION COMPONENT LISTING VOLUNTARY EXAMINATION-CLASS 1,2,83 COMPONENTS PSI AND 1ST INTERVAL ISI V01-01 VOLUNTARY EXAMINATION STATUS REPORT INTERVAL: PERIODS: NOT APPLICABLE
+++EXREQ'S WITH A FIRST CHARACTER THAT IS NUMERIC (N)ARE USED TO TRACK THE ASME SECTION XI EXAMINATION PROGRAM(S)
APPLICABLE TO EACH INSPECTION INTERVAL.(SEE EXREQ'S STARTING WITH"E" FOR THE ONLY EXCEPTION TO THIS RULE)+++TESTING OF THE FOURTH INTERVAL COMPONENT LISTING AND ISI 10 YEAR PLAN: 81W-01 ASME SECTION XI, 1980 EDITION THROUGH AND INCLUDING THE WINTER 1981 ADDENDA, INTERVAL 01 ONLY INSERVICE INSPECTION STATUS REPORT: 81W-01 TESTING OF SECOND INTERVAL 99W-03 TESTING OF THE THIRD INTERVAL ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt
,')1 E.}}

Latest revision as of 01:42, 18 March 2020

Test Rept on Electrical Separation Verification Testing for CP&L for Use in Shearon Harris Nuclear Power Plant.
ML18019A494
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 11/21/1985
From:
WYLE LABORATORIES
To:
Shared Package
ML18019A493 List:
References
47879-02, 47879-2, NUDOCS 8511260458
Download: ML18019A494 (633)


Text

TEST REPORT ON ELECTRICAL SEPARATION VERIFICATIONTESTING POR THE CAROLINA POWER AND LIGHT COMPANY POR USE ZN THE SHEARON HARRIS NUCX EAR POWER PLANT Por Carolina Power and Light Company Shearon Harris Nuclear Power Plant New Hill, North Carolina 27562 85i f 260458 851123.

PDR ADOCH, 05000400, FDa

0)

Page No. ii Test Report No. 47879-02 TABLE OF CONTENTS Section Paae TEST REPORT

SUMMARY

1.0 CUSTOMER 2.0 TEST SPECIMEN "

3.0 ABSTRACT 4.0

SUMMARY

5.0 REFERENCES

6.0 TEST SPECIMEN DESCRIPTION TEST PROGRAM DESCRIPTION 7.1 Control Cable Screening Tests 7.2 Power Cable Screening Tests 8 7.3 Configuration Number 1 Test 10 7.4 Configuration Number 2 Test 12 7.5 Configuration Number 3 Tests 15 8.0 QUALITYASSURANCE 20 9.0 TEST EQUIPMENT AND INSTRUMENTATION 20 TABLE I. TEST RESULTS

SUMMARY

21 WYLE LABORATORIES Huntsville Facility

Page No. iii Test Report No. 47879-02 TABLE OF CONTENTS (Continued)

Section Paae SECTION I CONTROL CABLE SCREENING OF IGNITION CAPABILI'FYOF TEST'DETERMINAT1ON CONTROL CABLES IN A CABLE TRAY) 1.0 REQUIREMENTS 1.1 Acceptance Criteria 2.0 PROCEDURES 2.1 'est Specimen Identification I-2 2.2 Test Specimen Preparation I-2 2.3 Instrumentation Setup I-3 2.4 Baseline Functional Tests I-4 2.5 Overcurrent Test I-5 2.6 Post-Overcurrent Test Functional Test I-6 3.0 RESULTS I-7 APPENDIX I Test Specimen Inspection Sheets I-9 APPENDIX II Instrumentation Equipment Sheets I-13 APPENDIX III Test Setup Photographs I-17 APPENDIX IV Control Cable Screening Test Setup Figure I-21 APPENDIX V Individual Test Data I-23 Control Cable Screening Test Nl I-25 Control Cable Screening Test N2 I-35 Control Cable Screening Test 03 I-45 Control Cable Screening Test N4 I-55 Control Cable Screening Test g5 I-65 WYLE LABOAATORIES Huntsville Facility

Page No. iv Test Report No. 47879-02 TABLE OE CONTENTS (Continued)

Section ~Pa e SECTION II POWER CABLE SCREENING TESTS (DETERMINATIONOP WORST CASE CABLE AND HORIZONTAL CABLE TRAY TO CONDUIT SEPARATION TEST) 1.0 REQUIREMENTS 1.1 Acceptance Criteria 2.0 PROCEDURES II-2'I-2 2.1 Test Specimen Preparation 2.2 Instrumentation Setup 2.3 Baseline Functional Tests II-4 2.4 Overcurrent Test II-5 2.5 Post-Overcurrent Test Functional Test lI-6

.,3.0 RESULTS APPENDIX I Notice of Anomaly APPENDIX II Test Setup Figure II-15 APPENDS III Individual Test Data Power Cable Screening Test ¹1 H-19 Power Cable Screening Test ¹2 II-27 Power Cable Screening Test ¹3 11-35 Power Cable Screening Test ¹4 II-43 Power Cable Screening Test ¹5 II-53 WYLE LABORATORlES Huntsville Facility

Page No. v Test Report No. 47879-02 TABLE OP CONTENTS (Continued)

Section Paae SECTION III CONFIGURATION NO. 1 TEST (FREE AIR SEPARATION WITHOUT BARRIERS) 1.0 REQUIREMEN'IS 1.1 Acceptance Criteria 2.0 PROCEDURES 2.1 Test Specimen Preparation 2.2 Instrumentation Setup 2.3 Baseline Functional Tests III-3 2.4 Overeurrent Test 2.5 Post-Overcurrent Test Functional Test III-5 3.0 RESULTS III-6 APPENDIX I Configuration Number-1 Test Data SECTION IV CONFIGURATION NO. 2 TESTS (CONDUIT-TCH ONDUIT AND CABLE IN FREE AIR SEPARATION TES'IS) 1.0 REQUIREMENTS IV-1 1.1 Acceptance Criteria 2.0 PROCEDURES IV-2 2.1 Test Specimen Preparation IV-2 2.2 Instrumentation Setup 2.3 Baseline Functional Tests 2.4 Overeurrent Test IV-6 2.5 Post-Overeurrent Test Functional Test 3.0 RESULTS IV-8 APPENDIX I Configuration Number 2 Test No. 1 Data IV-11 APPENDIX II Configuration Number 2 Test No. 2 Data IV-27 WYLE LABOAATOAIES Huntsville Facility

Page No. vi Test Report No. 47879-02 TABLE OF CONTENTS (Continued)

Section Paae SECTION V CONFIGURATION NO. 3 TESTS (2-TRAY HORIZONTAL STACK WITH VERTICALTRAY AND CONDUITS OR FREE AIR SEPARATION TESTS) 1.0 REQUIREMENTS V-1 1.1 Acceptance Criteria V-1 2.0 PROCEDURES V-2 2.1 Test Specimen Preparation V-2 2.2 Instrumentation Setup V-3 2.3 Baseline Functional Tests 2.4 Overcurrent Test V-10 2.5

~ Post-Overcurrent Test Functional Test V-12 3.0

~ RESULTS V-12 APPENDIX I Configuration Number 3, Test No. 1 Data V-15 APPENDIX II Configuration Number 3, Test No. 2 Data V-33 APPENDIX III Configuration Number 3, Test No. 3 Data V-53 SECTION VI WYLE LABORATORIES TEST PROCEDURE NO. 47879-01, REVISION A WYLE LABORATORlES Huntsville Facility

Test Report i.'s-REPORT NO.

4?879-02

'..tr,',.",c 47879 WYLE JOB NO.

CUSTOMER P. O. NO.

H-61740 E

~~ r PAGE 10F PAGE REPORT t j DATE October 11, 1985 SPECIFICATION (S)

See References in Section 5.0.

1.0 CUSTOMER Carolina Power and Li ht Com an ADDRESS Shearon Harris Nuclear Power Plant New Hill NC 27562

.0 TEST SPECIMEN Power, Control, and Instrumentation Cables as described in Paragraph 6.0

('3.0 ABSTRACT The test program described herein was conducted for Carolina Power and Light Company's Shearon Harris 5'uclear Power Plant to support compliance with Regulatory Guide 1.75, Revision 1, "Physical Independence of Electrical Systems", and with Section 5.1.1.2 of IEEE Standard 384-1974, "IEEE Trial-Use Criteria for Separation of Class 1E Equipment and Circuits", which allows the use of testing and analyses to justify separation of less than the spatial requirements of Sections 5.1.3 and 5.1.4 of IEEE Standard 384-1974.

(jmk) sTATE oF ALABAMA coUNTY oF MAolsoN

)

i *'eg. Alabama Professional Eng.

Gerald R. Carbonneau No. 13475 wyte shas have no riabiaty for damages or any trtnd to coneertrrenaat damages, PREPARED BY hom 0>>

or property.inctrrrang special or o--S covered by this report

.H ne deposes and says: The Information contained In this report ls the result of complete and carefully conducted tests and Is to th t of s knowledge true and correct In APPROVED rtlptIs ecfs. . ~ld-J 0-JP~ 'O- -8 WYLE Q. A.

SUBS RIBED ~and sworn to

~

fo e thl day of , tg ay 1g Notary blic in and for the State of Alabama t large.

My Commission expires t3 LABORATORIES SCIENTIFIC SERVICES & SYSTEMS GROUP HUNTSVILLE, ALABAMA .-

Page No. 2 Test Report No. 47879-02 4.0

SUMMARY

Prior to initiation of the testing phase of the program, Harris Plant Engineering Section (HPES) and Wyle Laboratories personnel developed Test Procedure 47879-01, Revision A (see Section VI). Selection of overcurrent conditions, test.configuratiops, tray fill, test initial conditions, and functional test are based on the following:

a) Overcurrent Condition All test currents were based on failure of a circuits primary overcurrent protection, and are that current level just below the pickup setting (+1096 for power panel and motor control center circuits) of the circuits secondary overcurrent protection. Test currents were conservatively maintained at a constant value as the circuits impedance increased due to conductor temperature- rise.

b) ConQgurations Test configurations were conservatively developed based on actual field installations. HPES/Wyle personnel developed test configurations after inspecting actual Shearon Harris Nuclear Power Plant (SHNPP) as-built conditions.

e) Tray FiI1 Trays were conservatively filled to the top of the side rails.

d) ~

Test Initia1 Conditions Actual cable operating conditions were established prior to the fault current test by energizing the fault cable and several adjacent cables.

e) Functional Tests All functional tests were based on industry-accepted standards. Visual inspections and temperature monitoring were also recorded and performed on all test specimens.

f) Cables All cables were from SHNPP stock.

The results of the test program and the test procedure are detailed in the appropriate sections as listed below:

e Section I Control Cable Screening Tests (Determination of ignition capability of control cables in a cable tray) o Section II Power Cable Screening Tests (Worst case cable determination and horizontal tray to parallel conduit)

~ Section III Configuration Number 1 Test (Free Air Separation Test without barriers)

~ Section IV Configuration Number 2 Tests (Conduit to Conduit and Cable in Free Air Tests) e Section V Configuration Number 3 Tests (2-Tray horizontal st ack with vertical tray, conduits and a free air cable)

~ Section VI Wyle Laboratories'est Procedure 47879-01, Revision A INYI.E LABORATORIES Huntsville Facility

Page No. 3 Test Report No. 47879-02

SUMMARY

(Continued)

Each of the configuration tests was'a conducted in the following sequence:

Baseline Functional Tests Overcurrent Test Post-Overcurrent Test Functional Tests One anomaly occurred during this test program. This anomaly is discussed briefly below and in more detail in Section II of this report.

Notice of Anomaly No. Date Desc tion 08/30/85 Documents the failure of the Twisted Pair 16 AWG target cable during the Post-Overcurrent Test Functional Tests for Power Cable Screening Test Number 4. This cable was installed inside a 1-inch rigid steel conduit mounted 1 inch above the faulted Triplex 4/0 AWG cable. The fault cable ignited and the target cable was exposed to temperatures of 644.8oF inside the conduit. It was judged that 1-inch vertical separation was inadequate physical independence, and the remaining Power Cable Screening Tests were conducted successfully using 12-inch vertical separation.

5.1 Wyle Laboratories Technical Proposal for Cable Separation Test Program for Carolina Power and Light Company, No. 543/3737/GH.

5.2 Wyle Laboratories'est Procedure 47879-01, Revision A, "Electrical Raceway Separation Verification Testing for the Carolina Power and Light for use in the Shearon Harris Nuclear Power Plant".

5.3 IEEE Std. 383-1974, "IEEE Standard for Type Test of Class lE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations."

5.4 IEEE Std. 384-1974, "IEEE Trial Use Standard Criteria for Separation of Class 1E Equipment and Circuits."

5.5 United States Nuclear Regulatory Commission Guide 1.?5, Revision 1, "Physical Independence of Electric Systems."

5.6 IEEE Std. 323-1974, "IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations."

5.7 Code of Federal Regulations, Section 10, Part 21.

Code of Federal Regulations, Section 10, Part 50, Appendix B.

WYLE LABORATORIES Huntsville Facility

Page No. 4 Test Report No. 47879-02 6.0 TEST SPECIMEN DESCRIPTION All cables used in this test program were qualified to meet the requirements of IEEE Standard 383-1974, "IEEE Standard for Type Test of Class 1E Electrical Cables, Field Splices, and Connections for Nuclear Power Generating Stations". The test specimens consisted of the following cables instaQed into the various configurations as described in Sections I through V of this report and were provided to Wyle Laboratories from Shearon Harris Nuclear Power Plant stock.

Cable* COL Item No. Desc tion B/M*+'25-11 1/C 500 MCM P Triplex 350 MCM P D25-10 Triplex 4/0 AWG P D25-08 1/C 2 AWG P D25-05 1/C 6 AWG P D25-03 1/C 10 AWG P D25-01 1/C 6 AWG C D59-03 1/C 10 AWG C D59-02 2/C 10 AWG C D50-01 10 2/C 12 AWG C D50-06 11 2/C 16 AWG C D50-11 12 1 Pair 16 AWG L D60-01 P Power Type Cable C Control Type Cable L -- Low Energy Type Cable B/M Bill of iMaterials Number WYLE LABORATORIES Huntsville Facility

Page No. 5 Test Report No. 47879-02 TEST PROGRAM DESCRIPTION-Ve1 Control Cable Screening Tests VJ.J.'urpose The purposes of these tests were to:

1. Demonstrate that the worst case electrical fault, in a control cable tray, does not have the potential to support combustion or have the capability to generate enough heat to adversely affect the operation of any cabling located 1 inch or more from a faulted cable in a control tray prior to open-circuiting and thus separation distances less than those specified in IEEE Standard 384-1974 and Nuclear Regulatory Guide 1.75 are acceptable.
2. Demonstrate the adequacy of'esign where a cable/raceway of one safety division is located within 1 inch of a. faulted NNS control cable, or a control cable of a redundant safety division, in a tray.

The Control Cable Screening Tests consisted of five tests to determine the ignition and heat eration capability of control-type cables in a filled ladder rung. cable tray. The fault was mounted as the top centerline cable in the tray. A 1-inch rigid steel conduit, with misted Pair 16 AWG target cable, and three thermocouple arrays were mounted 1 inch vertically above the faulted cable.

The cables tested and the currents- applied in the Control Cable Screening Tests were as

.follows:

Test No. Cable Size Warm Currents* Pault Current 2/C 16 AWG 18A, 25A 139A Initially**'80A 2/C 12 AWG 30A, 41A 2/C 10 AWG 40A, 50A 180A 3-1/C 10 AWG 40A, SOA 180A 3-1/C 6 AWG VSA, VSA 180A Initial warmup current and current at 90oC +SoC conductor temperature.

See Paragraph 3.0, Table I, Note 1 on Page I-7.

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Page No. 6 Test Report No. 47879-02 7.0 TEST PROGRAM DESCRIPTION (Continued) 7.1'ontrol Cable Screening Tests (Continued) 7.1.3'esulte The results of the five Control Cable Screening Tests are briefly summarized in the following table:

Maximum Fault Maximum Temp. TIIne To Test No. Fault Cable Size Cable Jacket Tem . 1 Inch Above en Circuit*

2/C 16 AWG 409.4oF 128.5oF 55.12 sec 2/C 12 AWG 519.1oF 128.0oF 118.15 sec 2/C 10 AWG 672.9oF 172.6oF (1) 3-1/C 10 AWG 963.4oF 231.8 F 324.4 sec 5 3-1/C 6 AWG 934.4oF 219.1'F (2)

After application of fault current to the fault cable.

Notes:

(1) Fault cable did not open-circuit. After approximately 358 seconds, the conductors shorted together and the temperature then dropped from 1464.3oF to 317.3oF. This test was terminated at the customer's request after 767.75 seconds (12.8 minutes). Based on the results of the previous tests, which did open-circuit, the conductor temperatures recorded indicated that the fault cable was on the verge of open-circuiting.

(2) Fault cable did not open-circuit. This test was terminated after the heat-up rate fell to less than 10 F in 15 minutes (from an initial heatup rate of 18 F per minute) which indicates that steady-state conditions had effectively been reached. Total duration, with 180 amperes applied, was'10,802.32 seconds (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />).

There were no ignitions inside the cable tray area during any of the Control Cable Screening Tests.

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Page No. 7 Test Report No. 47879-02 TEST PROGRAM DESCRIPTION (Continued)

Control Cable Screening Tests (Continued) 7.1.4 Conclusions The above results generated the following conclusions:

The acceptability of design was demonstrated where a rigid steel conduit passes 1 inch vertically above and parallel to a faulted control cable in a cable tray when the worst case electrical fault occurred in the cable tray. The maximum observed temperature to the jacket of the Twisted Pair 16 AWG cable inside the 1-inch rigid steel conduit was 185.8oF (Test No. 4) which is below the rated temperature of the cables insulation system (90oC).

2. The amount of heat released to the environment by a faulted control-type cable, at the Shearon Harris Nuclear Power Plant, is not capable of adversely affecting the operation of cabling located 1 inch or greater away during electrical fault conditions. Therefore, the spatial separation distances of IEEE 384-1974 can be reduced between control-type raceways/cable. The tested configuration demonstrated that separation distances of one inch or greater are adequate.

It was demonstrated that the worst case electrical fault, in a control-type tray, does not generate sufficient heat to cause ignition of a faulted cable's insulation system., Therefore, configuration testing was not required.

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Page No. 8 Test Report No. 47879-02 7.0 TEST PROGRAM DESCRIPTION (Continued) 7.2 Power Cable Screening Tests 7.2.1 Purpose The purposes of these tests were to:

1. Determine the worst case electrical fault and cable size. This worst case cable was based on a combination of time to ignition, insulation burn time, and observed temperatures.

Once the worst-case cable was determined, this cable was used as the faulted cable in all subsequent configuration tests.

2. Demonstrate the adequacy of design where a 1-inch conduit runs parallel to and 1 inch above a faulted cable in a power-type cable tray. (Subsequent to failure during Test No. 4, which was run out of sequence at the customer's request, the separation distance was revised to 12 inches vertically.)

The Power Cable Screening Tests consisted of six tests between a faulted power-type cabl and a 1-inch rigid steel conduit mounted above the faulted cable. The conduit was mount 12 inches above the fault cable for Tests No. 1, 2, 3, 5 and 6, and 1 inch above the fau

'cable for Test No. 4.

,The cables tested and the currents applied in the Power Cable Screening Tests were as follows:

Test No. Cable Size Warm Currents* Pault Current 3-1/C 10 AWG 40A, 50A 620 A Initially**

3-1/C 6 AWG 75A, 75A 704A 3-1/C 2 AWG 130A, 130A 704A Triplex 4/0 AWG 260A, 285A 4200A Triplex 350 iMCM 350A, 370A 4200A 3-1/C 500 MCM 430A, 476A 4200A Initial warmup current and current at 90oC +SoC conductor temperature.

See Paragraph 3.0, Table I, Note 1 on Page II-7.

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Page No. 9 Test Report No. 47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.2 Power Cable Screening Tests (Continued) 7.2.3 Results The results of the six Power Cable Screening Tests are briefly summarized in the following table:

Maximum Temperature Test Fault Cable- Fault Target Time to Insulation Time-to Open*

No. Size Cable Cable ltutition Burn Time Circuit 1 3-1/C 10 AWG 1136.2cF '08.1cF 160 sec 1 min 160.64 sec (1) 2 3-1/C 6 AWG 1060.7oF 99.0oF None N/A 105.7 sec 3 3-1/C 2 AWG 2141.5oF 166.5oF 410 sec 9 min 598.0 sec (2) 4 Triplex 4/0 AWG 1673.4oF 644.8oF 83 sec 8 min 93.0 sec (3) 5 Triplex 350 MCM 1600.3oF 251.6oF 154 sec 7 min, 183.25 sec 6'-1/C 500 MCM 1534.0oF 210.1oF -

441 sec 6 min 459.07 sec (4)

After application of fault current to the fault cable.

Notes: (1) Fault cable conductor shorted together after 10 seconds.

(2) Fault cable conductors shorted together after 338 seconds.

(3)- 1-inch conduit mounted 1 inch above fault cable for'this test only.

(4) Fault cable conductors shorted together after 320 seconds.

7'.2.'4 Conclusions The above results generated the following conclusions:

The Triplex 350 MCM cable was selected as the worst case cable. This selection was based on the fact that the Triplex 4/0 AWG and the Triplex 350 MCiM generated similar jacket temperatures and insulation burn times. However, the Triplex 350 MCM sustained the fault current for a longer period of time and visually was a more violent fire than either the Triplex 4/0 AWG cable or the 3-1/C 500 MCM cable.

2. The acceptability of design where a 1-inch rigid steel conduit is mounted 1 inch above a faulted power cable was not demonstrated by these tests. The size of the fire and the intensity of the heat generated during the electrical fault for Test No. 4 severely damaged the target cable in the 1-inch rigid steel conduit.

(See Notice of Anomaly No. 1 in Section lI of this report.) Consequently, this cable did not possess sufficient integrity to pass the Post-Overcurrent Test Functional Tests.

3. The acceptability of design where a 1-inch rigid steel conduit is mounted 12 inches above a faulted power cable tray was demonstrated by Tests 1, 2, 3, 5, and 6. During these tests, the maximum observed jacket temperature was 251.6oF (Test No. 5). There was no visible damage to the Twisted Pair 16 AWG target cable, and the target cable passed the Post-Overcurrent Test Functional Tests.

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Page No. 10 Test Report No. 4VSV9-02 V.O TEST PROGRAM'DESCRIPTION (Continued)

V;3 ConQguration Number 1 Test Configuration Number 1 Test consisted of a test between a free air faulted Triplex 350 MCM cable and a free air Twisted Pair 16 AWG'arget cable separated by 6 inches horizontally.

V.3.1 Purpose The purpose of the Configuration Number 1 Test was to demonstrate the acceptability of design where two cables in free air pass 6 inches horizontally from each other when the worst case electrical fault occurs- to one of these cables. This configuration represents field installation of free air cables going from:

a.. Tray to tray b.. Tray to conduit

c. Conduit to conduit.
d. Tray/conduit to equipment.

.The cables tested and electrical powering were as follows:

Cable Size Function Location Powe Triplex 350 MCM Fault Cable Free Air- 350A, 510A, 4200A*

Twisted Pair 16 AWG Target Cable Free Air 50 VAC, 1A Initial Warmup Current, Final Warmup Current, and Fault Current.

V.3.3 Results The results of the Configuration Number 1 Test are briefly summarized in the following table:

Cable Size Function Location Maximum Jacket Tem .

Triplex 350 MCM Fault Cable Free Air 1489.6oF Twisted Pair 16AWG Target Cable Free Air 580 3oF Time to Ignition: 105 seconds at 4200A Time to Open Circuit: 148.29 seconds at 4200A WYLE LABOAATOAIKS Huntsville Facility

Page No. 11 Test Report No. 47879-02 TEST PROGRAM DESCRIPTlON (Continued) 7.3 Configuration Number 1 Test (Continued) 7.3.4 Conclusions These results generated the conclusion that the Twisted Pair 16 AWG target cable possessed sufficient integrity to continue to conduct 1 ampere at 50 VAC throughout this test and to successfully complete the Post-Overcurrent Test Functional Tests. Therefore, the cable met the established test acceptance criteria. However, the jacket was scorched in several locations from exposure to the flames from the fault cable. Thus, it was.decided that the 6-inch horizontal separation was not adequate and a free air separation of 12 inches was evaluated during Configuration No. 3, Test 3 (see Paragraph 7.5.4).

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Page No. 12 Test Report No. 47879-02 V.O TEST PROGRAM DESCRIPTION (Continued) 7.4'onQguration Number-2. Test Configuration Number 2 consisted of two tests between a free air cable, a cable in rigid steel conduit, and a cable in flexible conduit. The faulted Triplex 350 MCM cable was in free air for Test No. 1 and the separation was 6 inches verticaQy to the conduits. The faulted Triplex 350 MCM was inside the flexible conduit for Test No. 2 and the separation was 1 inch to the free air and rigid steel conduit.

V.4J. Pur~se The purposes of the Configuration Number 2 Tests were to:

1., Demonstrate the acceptabiTity of design where a free air cable, a rigid steel conduit, and a flexible steel conduit are separated by 6 inches vertically when the worst case electrical fault occurs to the free air cable.

2. Demonstrate the acceptability of design where a free air cable, a rigid steel conduit, and a flexible steel conduit are separated by 1 inch when the worst case electrical fault occurs to the cable inside the flexible steel conduit.

-':-V.4.2 Descr tion The cables tested and the electrical powering were as follows:

,'7.4;2J. Test No. 1 Cable Size Function Location Power Triplex 350 MCM 'ault Cable Free Air 350A, 505A, 4200A*

2/C 16 AWG Target Cable 1" Flexible 50 VAC, 1A Steel Conduit 3-1/C'10 AWG Target Cable 1" Flexible 480 VAC, 40A Steel Conduit Initial Warmup Current, Final Warmup Current, and Fault Current.

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Page No. 13 Test Report No. 47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.4 ConQguration-Number 2 Test (Continued) 7.4.2.2 Test No. 2.

Cable Size Function Location Power Triplex 350 MCM Fault Cable 4" Flexible 350A, 425A, 4200A*

Conduit 2/C 16 AWG Target Cable 1" Rigid Steel 50 VAC, 1A Conduit 3-1/C 10 AWG Target Cable Free Air 480 VAC, 40A Initial Warmup Current, Final Warmup Current, and Fault Current.

V.4.3 Results The results of these tests are briefly summarized in the following tables.

Test No. 1 Maximum Temperatures Cable Size Function Lccaticu Jacket Conduit Triplex 350 MCM Fault Cable Free Air 1312.3oF N/A 2/C 16 AWG Target Cable 1" Flexible 751.7 F 777.6 F Steel Conduit 3-1/C 10 AWG Target Cable 1" Rigid 490 6oF 719 4oF Steel Conduit Time to Ignition: 126 seconds at 4200A Time to Open Circuit: 167.57 seconds at 4200A WYLE LABORATORlES Huntsville Facility

Page No. 14 Test Report No. 47879-02 V.O TEST PROGRAM DESCRIPTION (Continued) 7.4 ConQguration Number 2 Test (Continued) 7.4.3 Results (Continued) 7.'4.3.2 Test No. 2 Maximum Temperatures Cable Size Function Location Jacket Conduit Triplex 350 MCM Fault Cable 4" Flexible 1593 9oF 509.5oF Steel Conduit 2/C 16 AWG Target Cable 1" Rigid 131.6 F 141.0 F Steel Conduit 3-1/C 10 AWG Target Cable Free Air 169.8oF N/A Time to Ignition: None Time to Open Circuit: 231.63 seconds at 4200A 7.4.4 Conclusions The above results generated the following conclusions:

1. The acceptability of design was demonstrated where a free air cable, a 1-inch flexible steel conduit, and a 1-inch rigid steel conduit are mounted 6 inches apart when the worst case electrical fault occurs to the free air cable. During this test, relatively high temperatures were observed inside the flexible steel and rigid steel conduits (751.V F and 490.6 F, respectively). However, damage to the target cables was limited to the jackets only. In addition, both cables possessed sufficient integrity to successfully maintain continuity of power and to complete the Post-Overcurrent Test Functional Tests. Due to the high temperatures observed on the target cable jackets, this separation distance will not be permitted, without interposing barriers, in design at the Shearon Harris Nuclear Power Plant.
2. The acceptability of design was demonstrated where a free air cable, a 1-inch rigid steel conduit, and a 4-inch flexible steel conduit are mounted 1 inch apart, when the worst case electrical fault occurs inside the flexible steel conduit. The flexible steel conduit acted as an effective thermal barrier and suppressed the ignition of the Triplex 350 MCM fault cable.

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Page No. 15 Test Report No. 47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.'5 Configuration Number 3 Tests Configuration Number 3 consisted of three tests between two horizontal trays, a vertical tray, a parallel conduit or free air cable, and a perpendicular conduit. The horizontal trays were separated by 36 inches vertically and the vertical tray was separated by 12 inches horizontally. The faulted Triplex 350 MCM cable was in the upper horizontal tray for Test No. 1, the lower horizontal tray for Test No. 2, and the vertical tray for Test No. 3.

7.5.1 Purpose The purposes of the Configuration Number 3 tests were to:

1. Demonstrate the acceptability of design where three horizontal cable trays are separated by 36 inches {from the top of one tray to the bottom *of the next tray) when the worst case electrical fault occurs in either cable tray.
2. Demonstrate the acceptability of design where a horizontal cable tray passes 12 inches from a vertical cable tray when the worst case electrical fault occurs in either tray.
3. Demonstrate the acceptability of design where a 1-inch rigid steel conduit passes:
1) 1 inch below and perpendicular to a faulted cable in a ladder rung cable tray, or
2) 1 inch horizontaQy away from and parallel to the siderail wall of a ladder rung cable tray, or
3) 1 inch horizontally away from and perpendicular to the siderail wall of a ladder rung cable tray.
4. Demonstrate the acceptability of design where a free air cable passes 12 inches horizontally away from and parallel to a faulted cable in a ladder rung cable tray when the worst case electrical fault occurs in the cable tray.

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Page No. 16 Test Report No. 4V8V9-02 V.D TEST PROGRAM DESCRIPTION (Continued)

V.5 Configuration Number 3 Tests. (Continued)

The cables tested and the electrical powering were as follows:

V.5.2.1 Test No. I Cable Size Punction Location Povrerin Triplex 350 MCM Fault Cable Upper Horizontal 350A, 415A, 4200A*

Tray 3-1/C 10 AWG Target Cable Vertical Tray 480 VAC, 40A 2/C'16 AWG Target Cable Parallel Conduit 120 VAC, 10A 2/C 16 AWG Target Cable Perpendicular 120 VAC, 10A Conduit-Below Upper Tray Initial Warmup Current, Final Warmup Current, and Fault Current.

V.5.2.2. Test No. 2 Cable Size Punction Location Powerin Triplex 350 MCM Fault Cable Lower Horizontal 350A, 440A, 4200A*-

Tray 3-1/C 10 AWG Target Cable Upper Horizontal 480 VAC, 40A Tray 3-1/C 10 AWG Target Cable Vertical Tray 480 VAC, 40A 2/C 16 AWG Target Cable Parallel Conduit 120 VAC, 10A 2/C 16 AWG Target Cable Perpendicular 120 VAC, 10A Conduit Initial Warmup Current, Final Warmup Current, and Fault Current.

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Page No. 17 Test Report No. 47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.5 ConQguration Number 3 Tests (Continued) 7.5;2.3 Test No..3 Cable Size Function Location- Powerin Triplex 350 MCM Fault Cable Vertical Tray 350A, 465A, 4200A~

3-1/C 10 AWG Target'Cable Upper Horizontal 480 VAC, 40A Tray 3-1/C 10 AWG Target Cable Lower Horizontal 480 VAC, 40A Tray 2/C 16 AWG Target Cable Parallel Free-Air 120 VAC, 10A Initial Warmup Current, Final Warmup Current, and Fault Current.

V.'5.3 Results

'results from the three Configuration Number 3 Tests are briefly summarized in the wing tables.

7.5.3Z Test No. 1 Maximum Temperatures Cable Size Function Location ~Ci l7 Triplex 350 MCM Fault Cable Upper Horizontal 1554.4oF N/A Tray 3-1/C 10 AWG Target Cable Vertical Tray 202.1 F 154.3oF 2/C 16 AWG Target Cable Parallel 365.4 F 454.2oF Conduit 2/C 16 AWG Target Cable Perpendicular 262.3oF 415.7oF Conduit-Below Upper Tray Time to Ignition: 183 seconds at 4200A Time to Open Circuit: 266.13 seconds at 4200A WYLE LASORATORIES Huntsville Facility

Page No. 18 Test Report No. *47879-02 7.0 TEST PROGRAM DESCRIPTION (Continued) 7.5, ConQguration Number 3 Tests (Continued) 7.54.2, Test No. 2 Cable Size Function Location ~PI Maximum Temperatures Triplex 350 MCM Fault Cable Lower Horizontal 1372.4oF 942.4oF Tray 3-1/C 10 AWG Target Cable Upper Horizontal 236.2oP 378.7oP Tray 3-1/C 10 AWG Target Cable Vertical Tray 203.7oP N/A 2/C 16 AWG Target Cable Parallel 223.9oF 382.9op Conduit 2/C 16 AWG Target Cable Perpendicular 248.5 F 539.9 F Conduit Time to Ignition: 160 seconds at 4200A Time to Open Circuit: 223.98 seconds at 4200A

, 7.5.3.3 Test No. 3 Maximum Temperatures Cable Size Function Loeatim k ~/~

~M Triplex 350 MCM Fault Cable Vertical Tray 1514.7oF N/A 3-1/C 10 AWG Target Cable Upper Horizontal 132.4oF 135.8op Tray 3-1/C 10 AWG Target Cable Lower Horizontal 133.0oF 130.7 P Tray 2/C 16 AWG Target Cable Free Air 166.4oP N/A Time to Ignition: 193 seconds at 4200A Time to Open Circuit: 201.16 seconds at 4200A WYLE LABORATORIES Huntsville Facility

Page No. 19 Test Report No. 47879-02 TEST PROGRAM DESCRIPTION (Continued) 7.5'onfiguration Number 3 Tests (Continued) 7.5.4. Conclusions The above results generated the following conclusions:

The acceptability of design was demonstrated for the following physical separation distances:

36-inch-vertical separation between two ladder rung cable trays with the worst case electrical fault. in either tray.

2. 12-inch horizontal separation between a vertical and a horizontal cable-tray with the worst electrical fault in either tray; 3'. 1-inch horizontal separation between the siderail walls of a horizontal tray and a 1-inch rigid steel conduit when the worst case electrical fault occurs in the tray.

4, 1-inch vertical separation between a ladder rung cable tray and a perpendicular 1-inch conduit below the tray when the worst case electrical fault occurs in the tray..

1-inch horizontal separation between a horizontal ladder rung cable tray and a perpendicular vertical 1-inch rigid steel conduit when the worst case electrical fault'occurs in the tray.

6.- 12-inch horizontal separation between a vertical free air cable parallel to a vertical ladder rung cable tray when the worst case electrical fault occurs in the tray.

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Page No. 20 Test Report No. 47879-02 8.0 QUALITYASSURANCE All work performed on this test. program was done in accordance with Wyle Assurance Program, which complies with the applicable requirements of 10 CFR 50, Laboratories'uality Appendix B; ANSI N45.2', and the "daughter" standards. Defects are reported in accordance with the requirements of 10 CFR Part 21.

9.0 TEST EQUIPMENT AND INSTRUMENTATION All. instrumentation, measuring, and test equipment used in the performance of this test program were calibrated in accordance with Wyle Laboratories Quality Assurance Program, which complies with the requirements of Military Specification MIL-STD-45662. Standards used in performing all calibrations are traceable to the National Bureau of Standards by report number and date. When no national standards exist, the standards are traceable to international standards or the basis for calibration is otherwise documented.

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Page No. 21 Test Report No. 47879-02 TABLE L TEST RESULTS

SUMMARY

nflgurat ion Description Design Minimum Physical Separation Tested Spacing est Number

'anmum Temperature a t axrmum arget Temperature Control Instrument 1" H Control Cable (4) >>

Tray ln V Screening 963.4oP 185.8oF to 3n Tests No. 1-5 Conduit Power Tray 4n H Power Cable (3) (5) to, 12n V Screening 2141.5oP 251.6oP Conduit 2n V Tests 1,2,3,5 6r 6 12" H Free Air (Power Cables) Configuration to 6n H 6n H 1489.6oP 551.3oF Pree Air (Control/instrument No. 1 Cables Cables)

Power 12" H Free Air 12n H Configuration 2 (F) 751.7oF to 12" H 6" V 1312.3oF Plex. 4r R/S 36" V Test No. 1 (R/S) 490.6oF Conduit Plexible Conduit 1" H Configuration 2 (FA) 131,6oP to ln V 1593.9oF Pree Air dc 1n V Test No. 3 (R/S) 169.8oF R/S Conduit r Tray 12 H 12n H Configuration 3 (2) (V) 236.2op to 1554,4op ower Tray 36" V 36n V Tests 1, 2 Cc 3 H) 203 7o Horizontal Power Tray ln V Configuration 3 to 12n V (Perpendicular 1554.4op 262 3op Conduit Crossing X-Z Plane) Test No. 1 Under Tray Horizontal Power Tray 1" H Configuration 3 (1) to Conduit 4n H (Conduit Parallel 1554 4OP 365.4oF Parallel to To Tray SideraQ) Tests 1 2 2 Tray Horizontal Power Tray 4n H ln H Configuration 3 to (Perpendicular 1372.4oP 248.5oF Conduit 12n V Crossing Z-Y Plane) Test Vo. 2 Riser Riser Tray to 12n H Configuration 3 Parallel 12n H 1514 7oP 166.4oF Pree Air 36n V Test No. 3 Cable KEY: Refers to test number of data when multiple tests conducted.

H = Horizontal Distance V = Vertical Distance R/S = Rigid Steel Conduit P = Flexible Steel Conduit PA P = Free Air Cable

Page No. I-1 Test Report No. 47879-02 SECTION I CONTROL CABLE SCREENING TESTS (DETERMINATIONOP IGNITION CAPABILITYOP CONTROL CABLES IN A CABLE TRAY) 1.0 REQUIREMENTS Acceptance Criteria 1.1 J. Insulation Resistance Test Insulation resistance on all "target cables"* shall be greater than 1.6 x 106 ohms with a potential of 500 VDC'applied for 60 seconds. Before testing insulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an

. ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the

'vercurrent Test.

T ere shall be no evidence of insulation breakdown or flashover with a potential of VAC applied for one minute.

1..3= Cable Continui Test Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 50 VAC before, during, and after the overcurrent test.

Cable No. CPRL Cable Rated Size Conductors LD. Nu. Volt~e Current 16 AWG 1 Tw. Pr. D60-01 L 50 VAC 1A 1.1.4 Tolerance s All target cable voltages specified in this procedure shall be maintained within a +3%

tolerance. All target cable currents shall be maintained within a+10% tolerance.

All fault cable currents shall be maintained within a+3% tolerance.

The term "target cable" refers to energized and monitored nonfault cables used in this program.

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Page No. I-2 Test Report No. 47879-02 2.0 PROCEDURES 2.1 Test Specimen Identification An inspection was performed upon receipt of the test specimen components at 'Wyle Laboratories. This inspection ensured that the test specimens were as described in Paragraph 6.0 of the Summary section. Applicable manufacturer, model, part, and serial numbers were verified and recorded. The test specimens were labeled to facilitate identification throughout the test program.

Test Specimen Receipt Inspection forms are presented in Appendix I of this section.

2.2 Test Specimen Preparation The test setup for the five Control Cable Screening Tests was identical except as noted in the following paragraphs.

The test specimens. were mounted to the unistrut frame of Figure 1 of Section VI; This apparatus was assembled to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following guidelines were observed with regard to the materials and construction of this assembly:

P

1. The faulted cable was one of the following cables from CP*L stock:

Test No. Fault Cable Size COL LD. No.

2/C 16 AWG D50-11 2/C 12 AWG D50-06 2/C 10 AWG D50-01 3-1/C 10 AWG D59-02 (D25-01) 3-1/C 6 AWG D59-03 (D25-03)

The fault cable was the top centermost cable inside an 8' 24" x 4" ladder rung cable tray filled to the top of the siderails with de-energized control-type cables.

2. Nine 1/C 10 AWG cables were mounted underneath and around the faulted cable per Figure I-1. These cables were energized and their conductor temperatures increased prior to applying the fault current to the fault cable. This was done to simulate the heat which the fault cable would experience in a cable tray of

'nergized cables.

3. The ends of the faulted cable from their termination to the edge of the cable tray were wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape. This was done as a safety measure to ensure that any ignition that might occur was contained to the cable tray area.

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Page No. I-3 Test Report No. 47879-02 PROCEDURES (Continued) 2.2 Test Specimen Preparation (Continued)

4. A 9-foot long, 1-inch rigid steel conduit was mounted parallel to and 1 inch above the fault cable. This conduit contained a single pair 16 AWG target cable (CPRL I.D. No. D60-01). The 1-foot section of this conduit which extended past the cable tray was wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape.
5. A wind barrier was installed around the unistrut frame to eliminate the effects of wind on the heat transfer of the fault cable.
6. Photographs were taken of the test setup.
7. A 1/2-inch VHS recording was taken of the Overcurrent Test encompassing the entire application of the test current.

2.3'nstrumentation Setup 2.3;1 Thermoco le Locations A total of 35 Type "K" thermocouples were utilized for these tests. These thermocouples

-mounted as described below:

Channel No. Location 1-8 Mounted to the jacket of the fault cable. These thermocouples were spaced approximately 12 inches apart.

9@10 Mounted to the conductors of the fault cable. These thermocouples were applied by cutting the cable insulation, approximately 12 inches from the series connection points, forcing the thermocouple into the conductor strands and then taping the area with 3M No. 69 glass tape.

11-16 Mounted to the conductors of the nine cables adjacent to the faulted cable. The six thermocouples were mounted with three thermocouples at each end of these cables in three of the four series connections.

17-24 Mounted to the jacket of the single pair 16 AWG target cable inside the 1-inch conduit. These thermocouples were spaced approximately 12 inches apart and were even with the eight fault cable thermocouples.

25 2 26 Mounted underneath the 1-inch conduit.

27-35 Mounted 1 inch above and 1 inch horizontally from the fault cable in three groups of three thermocouples.

thermocouples were monitored using a Fluke Datalogger feeding a high-speed printer.

atalogger was operated at its maximum rate throughout the Overcurrent Test. The t erature data is plotted versus time in Appendix V of this section.

WYLE LABORATORIES Huntsville Facility

Page No. I-4 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.3 Instrumentation Setup (Continued) 2.3.2 Electrical Monitor The voltage and current of the target cable and the fault cable current were continuously monitored with an osciQograph recorder. The oscillograph was operated at the O.l-inch per minute rate throughout the Overcurrent Test. The oscillograph channels were as specified in the following table:

Channel No. S Location Current Tw. Pr. 16 AWG Voltage Tw. Pr. 16 AWG Current Fault Cable A digital multimeter was utilized to measure voltage and current of the target cable prior to, during, and after the Overcurrent Test. This data was recorded to provide accurate

~

evidence of the specimen's capability to conduct rated current at 50 VAC throughout the Overcurrent Test and is presented in Appendix V of this section.

2 .4 Baseline Functional Tests

>The baseline functional tests consisted of Insulation Resistance and High Potential measurements on each of the target cables. These tests were performed as described below:

2.4.1 Insulation Resistance Test

1. All power and instrumentation leads were disconnected from the target cable.
2. Shield continuity to the conduit was measured with a digital multimeter.
3. Using a megohmmeter, a potential of 500 VDC was applied and the minimum insulation resistance indicated after a period of 60 seconds was recorded between the following test points:

Phase-to-Phase Phase-toW round*

1to2 1 to conduit 2 to conduit

  • Shield tied to conduit.

For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 1.1.1, i.e., greater than 1.6 x 10 WYLE LABORATORIES Huntsville Facility

Page No. I-5 Test Report No. 47879-02 PROCEDURES (Continued) 2.4 Baseline Functional Tests (Continued) 2.4.2 H h Potential Test

1. Using a Hi-Pot Test Set, a potential of 1600 VAC was applied and the leakage current observed after a period of 60 seconds was recorded between the following test points:

Phase-to-Phase Phase-to-Ground*

1 to 2 1 to conduit 2 to conduit

  • Shield tied to conduit.

flasho

2. Power and instrumentation leads were reconnected to the target cable.

For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 1.1.2, i.e., there shall be no evidence of insulation breakdown or ve.

2.5 Overcurrent Test, vercurrent. Test was conducted in two sequential phases with no intentional time delay een phases. The first phase consisted of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90 C +5 C. The second phase consisted of energizing the fault cable with the test current until the cable open-circuited, temperatures stabilized or decreased, or the test was terminated at the customer's request.

The"target cable was energized at rated current and 50 VAC throughout the Overcurrent Test. The Overcurrent Test was conducted using the following procedure:

1. Nine 1/C 10 AWG cables were installed adjacent to the fault cable per Figure I-1.
2. The fault cable (see the table on following page) was connected to the copper bus bars.
3. A single pair 16 AWG target cable was installed in the 1-inch rigid steel conduit per Figure I-1.

4, The single pair 16 AWG target cable were connected to the instrumentation and power supplies of Figure 11 of Section VI.

=5. The nine 1/C 10 AWG cables were connected to the power supply per Figure 8 of Section VI.

'he 6. single pair 16 AWG cable were energized with 1 ampere at 50 YAC.

The nine 1/C 10 AWG cables, adjacent to the fault cable, were energized with 40 amperes at reduced voltage.

WYLE LABORATORIES Huntsville Facility

Page No. I-6 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.5 Overcurrent Test (Continued)

8. The fault cable was energized with the initial currents listed in the table below.
9. Target cable voltage and current, fault cable current and initial eonduetor temperature, and adjacent cable current were recorded.
10. Pault cable and adjacent cable currents were slowly increased to achieve a fault cable conductor temperature of 90 C +5oC for a period of 15 minutes.
11. Target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current were recorded.
12. The fault cable current was increased to the test current value in the table below.
13. Target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current were recorded.
14. The fault cable was allowed to conduct the test current until either the cable open-eircuited (Tests 1, 2 and 4), temperatures stabilized or decreased (Test 5},

or the test was terminated at the customer's request (Test 3).

15. Time to open-circuit or stabilized temperature was recorded, as applicable.
16. Target cable voltage and current and adjacent cable current were recorded.
17. The target cables, adjacent cables, and the Multi-Amp Test Set were de-energized.
18. Post-test conditions were photographed..

Por all performances of this test, the observed target cable operation was compared to the acceptance criteria, Paragraph 1.1.3, i.e., they maintained continuity of power.

Pault Cable Sizes and Currents Test CPRL Initial Test No. Pault Cable Size LD. No. C Current 1 2/C 16 AWG D50-11 18A 136A 2 2/C 12 AWG D50-06 30A 180A 3 2/C 10 AWG D50-01 40A 180A 4 3-1/C 10 AWG D59-02 (D25-01} 4QA 180A 5 3-1/C 6 AWG D59-03 (D25-03) 75A 180A 2.6 Post-Overcurrent Test Functional Test The. functional tests of Paragraph 3.2.4 were repeated on the target cable as soon as t smoke cleared in the test chamber. In addition, the target cable jacket temperature w recorded.

WYLE LABORATORIES Huntsvllte Facility

Page No. I-7 Test Report No. 47879-02 The five Control Cable Screening Tests were conducted per Paragraph 2.0 and successfully met the Acceptance Criteria of Paragraph 1.0. There was no visual evidence of damage to the Twisted Pair 16 AWG target cable inside the 1-inch rigid steel conduit, mounted 1 inch above the faulted cable, in any of these tests. In addition, the target cable did not exhibit electrical degradation as evidenced by the results of the Insulation Resistance and High Potential test results. There were no ignitions of the fault cable, in the test area, during the five Control Cable Screening Tests.

The results of the five individual tests are summarized in the following tables.

TABLE L CURRENTS APPLIED AND TIME TO OPEN CIRCUIT NEC Current at Test Fault Cable Rated 90oC +5 Conductor Test Time to No. Size Current Tem erature Current 0 en Circuit*

2/C 16 AWG 18A 25A 139A (1) 55.12 sec 2/C 12 AWG 30A 41A 180A 118.12 sec 2/C 10 AWG 40A SOA 180A (2) 3-1/C 10 AWG 40A 50A 180A 324.4 sec 3-1/C 6 AWG 75A 75A, 180A After application of test current.

Notes: (1) The Multi-Amp 'CB8130 test set was not capable of delivering 180A to this cable due to the high impedance of the cable which increased as the conductors were brought to 90oC. The machine was capable of delivering this current on a cable at ambient temperature. However, this condition is judged to be representive of actual plant conditions.

(2) The fault cable did not open-circuit during this test. After approximately 358 seconds, at 180 amperes, the fault cable conductors shorted together which decreased the effective length of the cable as well as added an additional heat sink. Consequently, conductor temperature dropped from a maximum <<1464 F to 375 F over a period of approximately 6 minutes. At this point, the test was terminated. Based on the results of the previous tests which did open-circuit, the conductor temperatures recorded indicated that the fault cable was on the verge of open-circuiting.

(3) The fault cable did not open-circuit during this test. This test was terminated after 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> when the heat-up rate had decreased to approximately 0.5oF per minute (from a maximum rate of approximately 18oF per minute) indicating that steady-state conditions had been reached.

WYLE LABORATORIES Huntsville Facility

Page No. I-8 Test Report No. 47879-02 3.0 RESULTS (Continued)

TABLE II. MAXIMUMTEMPERATURES Test Fault Cable Target Cable 1-Inch Above No. Size Fault Cable Jacket Fault Cable 2/C 16 AWG 521.9oF 96.3oF 128.5oF 2/C 12 AWG 1043.3oF 100.8oF 128.0oF 3 2/C 10 AWG 1464.3oF 118.2 F 172.6oF

4. 3-1/C 10 AWG 963.4oF e 185.8oF 231.8oF 3-1/C 6 AWG 934.4oF* 179.8oF 219.1oF Jacket temperatures.

In order to enhance the clarity of this report, the data has been separated into appendices which cover all testing and appendices'hich are specific to an individual test. The

,appendices contain the following data:

Appendix L Test Specimen Inspection Sheets which document materials received fr CPRL to conduct the entire test program.

Appendix If: Instrumentation Equipment Sheets which list the equipment utilized to take data for all phases of testing.

Append+ lfi. Overall test setup photographs.

Appendix IV: Figure I-1 which illustrates the test setup for the Control Cable Screening Tests.

Appendix V: Individual test data. This data is grouped into individual sections for each test. Each section contains: (1) Photographs of the test setup and post-test conditions; (2) A narrative of the test; (3) A plot of temperatures versus time; and, (4) Data Sheets which document Baseline Functional Tests, the Overcurrent Test, and the Post-Overcurrent Test Functional Test Data.

WYLE LABORATORIES Huntsville Facility

Page No. I-9 Test Report No. 47879-02 APPENDIX I TEST SPECIMEN INSPECTION SHEETS WYLE LABORATORIES Huntsville Facility

Page No. I-10 Test Report No. 47879-02 TEST SPECIMEN 1NSPECTION CHECK AS APPROPRIATE CUSTOMER JOB NO.

SPECIFICATION DATE ~P +0 o

ITEM 0 NO. DESCRIPTION MANUF. PART/MODEL NO. 0 yi Co Pc 1&A~ Q E'ea(re WO-II ( WO' (ooo V Cgg~

ZPRi4 Ibd'~4 C~ ( O-ol Qoz v'piebg ~M Q.I QQ. ~M58oL /t=.

HHM QI 5C'.. PZxcEk OOO 0%$ il

>C CoWQ (7, X

IO'hSQ I 5M//cQ NOTES'L(BC'babu 4" oD x x IQ' o'&fC i 7?

l~ E.F:I.

7c Specimen Failed Specimen Passed Inspected B Date: ~/E~

7.~<-

Witness Date:

NOA Written Sheet No. ol Approved

Page No. I-11 Test Report No. 47879-02 TEST SPECIMEN INSPECTlON CHECK AS APPROPRIATE USTOMER OB NO.

SPECIFICATION v'~

DATE ITEM NO. DESCRIPTION MANUF. PART/MODEL NO.

PC/VL oo u'. CAGM 0.o I g 3m Ncvvt M gcK 4o 4m V CI48M

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l o 'OHw -0 I 9~WN LCO V &t6u=

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NOTES:

Specimen Failed Inspected By ecimen Passed Witness A Written Sheet No. oi Approved g ~Q

Page Vio. I-12 Test Report No. 47879-02 TEST SPECIMEN INSPECT1ON CHECK AS APPROPRIATE CUSTOMER JOB NO.

SPECIFICATION DATE o~

O ITEM 0 NO. DESCRIPTION MANUF. PART/MODEL NO.

"c8 JD'vA(54)4

~Qf i &kl(i E Ldmns -j-

~A A.~ ( o~.beer

. 7 C.FP.'~ia45 "oi xylo'RÃr

/M C'0~84t'~~( e, NOTES:

Specimen Failed Inspected B Dnie: ~7-Specimen Passed Witness Date:

NOA Written Sheet No. of Approved s

Page No. 1-13 Test Report No. 47879-02 APPENDIX II INSTRUMENTATIONEQUIPMENT SHEETS WYLE LABORATORIES Huntsville Facility

INSTRUMENTATION EQUIPMENT SHEET Page~ of Date W-Z -g< Job No. cw Technician Customer ~ 4. Test 78'ype Model Serial Wyle or Calibration Instrument Manufacturer No. No. Gov't No. Range Accuracy On Due

/Z// 9 PS

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strumentation ~:Checked & Received By

'llH 10, Rev. A ll/82

INSTRUMENTATIO QUIPMENT SHEET Date Job No. Test Area

~ 4 Customer Type Test

<4'echnician o 8 7 Model Serial Wyle or Calibration No. Instrument Manufacturer No. No. Gov't No. Range Accuracy On Due

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I Wylo )g-Zg-g5 A

Instrumentation Checked 8 Received Sy iiH 1029, Rev. A 11/82

INSTRUMENTATION EQUIPMENT SHEET Oate Job No. 7 7 Test Area dauSrid Technician Customer Type Test Model Serial Wyle or Calibration Instrument Manufacturer No. No. Gov't No. Range Accuracy On Due 5 >>rci o b <rPAgC' )hP oo E/< c oui~~~

Qc+7 P P o 8/d4 p'jcrri'c 2/A a CH4 Y o 07 l r rrrCr A 'P oo co CD I

CD Wyle, trumentation A

Checked & Received By ~ 5-rZ-Z HH 10 -, Rev. A 11/82

Page No. I-17 Test Report No. 47879-02 APPENDIX IH TEST SETUP PHOTOGRAPHS WYLE LABORATORIES Huntsville Facility

Page No. I-18 Test Report No. 47879-02 t ' 1 go

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  • I PHOTOGRAPH NO I"1 INSTRUMENTATIONSETUP SHOWING FLUKE 2200C DATALOGG~

LEAR SIEGLER 300 LINB PRINTER, AND HONEYWELL 1508 OSCILLOGRAPHS Illttt1 'I' l

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,,*5 PHOTOGRAPH NO. I-2 MULTI-AMPCB8130 TBSI'.SET USED TO POWBR FAULT CABLE

Page No. 1-19 Test Report No. 47879-02

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greg phobe PHOTOGRAPH NO. I-3 ELECTRICAL SETUP FOR TARGET INSTRUMENT CABLES 0

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PHOTOGRAPH NO. IM ELECTRICAL SETUP FOR ADJACENT CABLES

Page No. I-20 Test Report No. 47879-02 This'age Left Intentionally Blank.

WYLE LABORATORIES Huntsville Facility

Page No. I-21 Test Report No. 47879-02 APPEND& IV CONTROL CABLE SCREENING TEST SETUP FIGURE WYLE LABORATORIES Huntsville Facility

Page No. I-22 Test Report iso. 4787 J-02 LAST 12""OF CONDUIT WRAPPED TW. PR. 16 AWG WITH WT-65/3M 69 TARGET CABLE S CONDUIT (10 FEET)

+t" I" +

y+ lX, 14 TYPE "K" THERM-RS CONDUIT OCOUPLES

,TW. PR. 16 MOUNTED AWG TARGET UNDER CONDUIT

~II)(+f g

+

FAULT CABLE %96 ~a ADJACENT CABLES Oi TARGET CABLE 90" SUPPORT WITH UNISTRUT CABLE TRAY FILLED TO A 60% FILL LEVEL FRONT VIEW TOP VIEW (WITHOUT CABLES IN TRAY)

FIGURE I-l. CONTROL CABLE SCREENING TEST SETUP

Page No. I-23 Test Report No. 47879-02 APPENDIX V INDIVIDUALTEST DATA WYLE LABORATORIES Huntsville Facility

Page No. I-24 Test Report No. 47879-02 This Page Left Intentionally Blank.

WYLE LABORATQRIES Huntsville Facility

Page No. I-25 Test Report No. 4V879-02 CONTROL CABLE SCREENING TEST 81 Photographs Pigures Data Sheets WYLE LABORATORIES Huntsville Faclllty

Page No. 1-26 Test Report No. 4'78Z9-02 j"-::g/z/'((

PHOTOGRAPH NO. 1-5 OVERALLVIEW OF TEST SETUP FOR CONTROL CABLE SCREENING TESI'l l" t A

1 5 I 4(

(

s jj PHOTOGRAPH NO. IW HEAT RISE TESI'l CLOSEUP VIEW SHOWING SERIES CONNECTIONS OF ADJACENT CABLES, WRAPPED END OF FAULT CABLE, AND 1-INCH CONDUIT LOCATION

Page No. I-27 Test Report No. 47879-02 C

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PHOTOGRAPH NO. I-7 SIDE VIEW OF TEST SETUP SHOWING WIND SHIELD

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<ra<rarer ~ I g L I'rrj. (err. +pl ae w -B4 ~/i-

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PHOTOGRAPH NO. IW CLOSEUP VIEW OF POST-TEST DAMAGE FROM CONTROL CABLE SCREENING TESI'l

Page No. I-28 Test Report No. 47879-02 AeJ ETC<

gg+5 PHOTOGRAPH NO. I-9 CLOSEUP VIEW OF LOCA'QON OF OPEN CIRCUIT ON 2/C 16 AWG FAULT CABLE

~

Control Cable Screening Test 1 J>':i ifli ;i!I

! II IEGENDs Fault Cable Jacket Temperature (T/Cs 1-8) DRAM(j BYs j

Fault Cable conductor Temperature (T/Cs 9 6 10) jhl t .j Cf(ECXED BYs 1500 }tii Target Cable Jacket Temperature (T/CS 17-24) iH Conduit Temperature (T/CS 25 a 26) 1 400 Array Temperature (T/CS 21-35) Hl !1:

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}fax. Temp. Recordeds 521.9 F (T/C 69) at 139.3 min !h 1300 !t 1 lil jf Ambient Temp.s 82 F ili

ti Dates August 5, 1985

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Page No. I-30 Test Report No. 47879-02 CONTROL CABLE SCREENING TEST 41 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 97 P 85 F Energized Fault Cable with 18A 32.5 min 196 F 126 F Energized Fault Cable with 16A 38 min 201 F 120 P Energized Fault Cable with 14A 41 min 209 F 119 F Energized Fault Cable with 10A 44 min 216 F ill F De-energized Fault Cable 71.5 min 217 P 87 P Energized Fault Cable with 10A 92 min 195 P 107 P Energized Fault Cable with 18A 102 min 195 F 125 F Energized Fault Cable with=21A 107 min 196 F 135 F Energized Fault Cable with 25A 138.4 min 210 F 173 F Energized Pault Cable with 139A decreasing to 117A 139.3 min 325 P 521.9 F Open circuit indicated by multi-amp test set. Peak recorded conductor temperature.

140 min 409.4 F 435 F Peak Jacket Temperature WYLE LABORATORIES Huntsville Faclllty

Page No. I-31 Test Report No. 47879-02 DATA SHEE7 Customer VVYLE LABORATORiES Specimen Ca bl es Part No. Various Amb. Temp. Job No Spec. W TP 47 7 - 1 Photo Report No. 47879-02 Para. 3.2.4.1 Test Med. Air S/N Specimen Temp. 7 GSI No Test Titie FUNCTIONAL TEST o~rg g~ SCREENING TEST NO Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 6

1.6xl0 J2. with 500 VDC applied for 60 seconds.

Cabl e Test Point Reading Tw. Pr. 16 AWG ~

1 to2 7X/o" oH 1 to conduit* c" 2 to conduit* 3 o 6HNL

~, or Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds.

Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 t38 CR Am s 1 to conduit* OO i Ro A 2 to conduit* op t ie'

  • Shield tied to conduit.

Tested By oare:~rS Witness Date:

tice of Sheet No. of omaiy Approved Wylo Form WH OllA, Rw, APR 'Ol

Page No. I-32 Test Report No. 47879-02 DATA SHEET Customer CP8L Specimen Part No. Various Amb. Temp. ~cP + Job No,- 47879-01 Spec. Photo Report-No.

Para. 3.3.5 Test Med, Air Start Date S/ N No GSI Test Title NT7 T SCREENING TEST NO. A Fault Cable Size: ~/C et Cable: / It /

No ~ Conductors:

Tar Addacent Cab'le:r 7~.

p gd jd ~ ('.

Initial readings with current applied.

Tar et Cable Fault Cable Adjacent Cables

~ ~b V~ CurrentD 8 Current:

Current: 0 f/' Conductor Temp.: + gap Conductor Temp.: +. fa+

ll. Readin s at 90 +5'C conductor temperature.

Tar et Cable Faul t Cable Adjacent Cabl es Vol tage: ~, $ kg Current: Current:

Current: /.04 8 Conductor Temp.: g+y up Conductor Temp.: /0+4 E

12. Readings with faul t current applied.

Target Cable Faul t Cable Adjacent Cabl es Volta e: 4D.4 >AC Current: /gg 9 ~M Current: p+p

~ /,cu'7 8 C nductor Tem .: d . F Conductot Temp.: /A S/

~

Tested By Date: ~~~~

Witness Date:

Notice of Anomaly Wyl~ Form WH liteA, Aev. APrA '8d Sheet Approved of r -$ j

a a w y~

Page No. I-33 Test Report No. 47879-02 DATA SHEET CPKL Customer WYLELABORATORIES Specimen Cabl

.PwrLNo Various Amb. Temp. Job No" ,47879.-01

--- - =- -

.Spec. M TP 4 87 -01 Photo Yes Report No; 47879-02 --- ~

Para. 3.3.5 Test Med. Air No S/N 0

GSI Test Title.. OVERCURREHT TEST Continued

15. 8 16. Post-Test Readin s Target Cables:

Voltage: +O. pP~

Current: .0 Fault Cable:

Time to Open Circuit: +Q /g ~~g 4~ gag g Time to Ignition:

Time to Stable Tem T R rded.

Adjacent Cables:

Current:

Maximum Temp. Recorded:

yg g >Q Tested Sy Witness Dala: ~>~

Dafe:

tice of Sheet o. of omaly Approved - -zS wylo Foam YIH 014A. Hev. ApR '94

Page No. I-34 Test Report No. 47879-02 DATA SHEET Customer VVYLELASORATORIES --

Specimen Ca bl e part No. Vari ous Amb. Temp.

'7879 Spec W TP 4 7 -0 Photo Y s Para. 3 2*'4'/N Test Med Air Specimen Temp.

GSi Test Title P~l- DO /I'~7 fUNCTIONAL TEST SCREENING TEST NO.

Insulation Resistance Test Acce tance Criteria: Measured insulation resistance. shall be reater.than.

6 1.6xl0 C2. with 500 VOC applied for 60 seconds.

Cable Test Point Reading Tw. Pr. 16 AMG 1 to2 g.ox/o ~

1 to conduit* /.O Xr'0'.,

2 to conduit* 10 ld Hi h Potential Test cc tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds.

Cable Test Point Reading Tw. Pr. 16 AMG 1 to2 1 to conduit*

2 to conduit* flrrr ~g

  • Shield tied to conduit.

Tested Sy ate:~~~

Witness Date:

Notice of Anomaly Sheet No.

Approved -r-fF of Wyl~ Form WH yllAA. Roy. APR '3A

Page No. I-35 Test Report No. 47879-02 CONTROL CABLE SCREENING TEST N2 Photographs Pigures Data Sheets WYLE LABORATORIES Huntsville Facility

Page No. 1-,36 Test Repor t No. 47879-02

<<,1( ~

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<<4'HOTOGRAPH NO. I-10 FRONT VIEW OF TEST SFfUP FOR CONTROL CABLE SCREENING TEST 42 PHOTOGRAPH NO. I-11 SIDE VIEW OF TEST SETUP FOR CONTROL CABLE SCREENING TEST 02

Page No. I-37 Test Report No. 47879-02

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~ PHOTOGRAPH NO. I-12 OVERALL VIEW OF DAMAGE FROM CONTROL CABLE SCREENING TEST 02

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PHOTOGRAPH NO. I-13 CLOSEUP VIEW OF LOCATION OF THE OPEN CIRCUIT

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,1! j

,'!p { :li hi(!

LEGEND) Fault Cable Jacket TeaPerature (T/CS 108) DRA))N BY:

Fault Cable Conductor Tesperature (T/CS 9 6 l0) ll jiii  !)1 )hl rjjj ,(tf C((ECKED BY:

150 Target Cable Jacket Teaperature T/CS 11-24)

H(i!

Itn 1!

~1 jl! $

Conduit Teaperature <T/CS 25 6 26) ii h)jj( h 1 1400 Array Tesperature (T/CS 21-35) ( hli

!'1' h Hi! H i; H F:1" 1: ri:! 1;

~ I.

<<I I!'1 Max. Tesp. Recordedi 1043.3 F (T/C 99) at 106.6 st)n i( i

'1 tbf jij! !j!! i!I; 1(

1300:: '. I At!!blent Teap.: 13 F fit II (h

1,'I Date: August 6, 1985 ri 'I i.

1200 I 'ICORE )!1

'h! Ihf i il n

1100 Ilr; "ill h!! 'fp  !!h jnf,'1 L'(

I

!ifi!j!( Iht 1

!1 ~

!,l. iii! j!j! 1'!

1000 i .:1 !0 fr( iil! j!j', tjfj iCH fi iHi 8 hfi iH! !Ii jih fj iltj (fl!  !',! I

'! I!

ji ill tp

!l if ,n 900 ii: it jl j!h Hhii lh I Ih JI  !!n iii,i ,rn I; r}11 'fin I 1! ifh I<<'11

.'1,'(ti j

800 i!j !jrj li), !j(i j.'j! h IH f

Hi ,p!

1 t f! '(

tn: f!

j 700.:j! !iij  !<<

!111 1

h  !

!hi i!

I '1 i(F ilh

!H!j t!i; FH !18lt". if<< Ilfl i hl QQ)j 1 JIL) i it sso Hj (5 (p. nh j(fi ihi th t N! (i!!

!i

<<i ihi h! jh ,fH!j 11 600 ",;! ii !HFI '.

I it(

I'Ei Lj th ih( it

)

i'I j i! j!i! !H 'i! ijj diff i At I 'r 1 hI) 1~ .

o o

'J lri sso f 8 i it i..! dht ihl(i tir ;hf jhj I h Iln i. i 1

rh iit I'i! A3i, oo

<<!1 fiL'H!

~It I

5  !>>ij iii. jijj )I ro 500 I!Sf:

1 I in fj 1 !Fjt )

ro 1

!!i( ilr. !Hi t it :h(  ! 11

'it '. ii' <<!i 10 450 i!h!jii IIfr; j(,) p

<<1 in tritii 'pFj(':,jp. n Fi LrH 'i!>>)0 j i tt 400 n (ij  !,I!jh !jr:

Hi( 1

)!i P 8 iP E Igr Ij')

I jrf !F! j f( p ) I:

350 !H  !,8 'th 1!tjt 1 i

! i.!I Hf h n

1!

n 11 11 Jjf rj j f' <<fr <<(I )ip I'h'H li i h1 300 iFFiH Ff1! f'j'!ip'lfhl (i1( fl iL} . 1!!!j I Fni 0

~

'50 i<<i I'L! i!j!!!fi t,ij t<<B!!(

1P l.i i<< itt it) H 8

<<I I!1 ter.

rf I  !

)$ jf )

Lit j il Hr, I(f1 it!1

<<Jli nil jH Jr} ip  !

Hl I( ttH

( 8 200 '<<1:

if' jih ih Iih r hr qf ili) ) '(h i 8 Hit

!F 4F I)!i li 11 iH!

150 ':= .;1'in

!H!!!1! Im r1 n )H jr r'!L jdj )i;! ii J>> f if 'lp 1)

',I 4j.

100 .-.:

Jf! 'F'!j )Hi it'it'h (r

ii Hf I 50

!" f<<! Fri

=i!!ff!)(ljHt! ftj j! I 11', I (it! IQ ijf, Ii. f), hl

'Qf'A lfh :i !l'i j ):h t'q !i( ijil tip i!f )

lhr( t~t) m 5 !H t! .i ji l((! <<

5'1 s(i f(i.!!t',

r MP.. I! !1 ' !ltj jl( fi 8 (! ihl; nij,'i 0 j :t:i 'i 0!i tt) 40' !i!I !It) jtn i! 0 i)F, 0

t)F) fti! /~I f I! jif I i!<< h(

il ti rhi  ! !l "j)It

! i 'iii ') ii Hi

Page No. I-39 Test Report No. 47879-02 CONTROL CABLE SCREENING TEST 42 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 90 F 90 P Energized Fault Cable with 30A 13 min 126 F 126 F Energized Fault Cable with 35A 29.7 min 153 153 F Energized Fault Cable with 37A F'71 49.7 min F 171 P Energized Fault Cable with 38.5A 69.7 min 183 P 174 P Energized Fault Cable with 40A 79.7 min 191 P 175 F Energized Fault Cable with 41A 104.7 min 201 P 185 F Energized Fault Cable with 180A 104.9 min 275 P 450 P Light Smoke (off gassing) 106.6 min 519.1 F 1043.3 F Open circuit inicated by multi-amp test set. Peak recorded conductor and jacket temperature.

WYLE LABORATORIES Huntsville Facility

Fage No. I-40 Test Report No. 47879-02 GATA SHEET Customer CPSL WYLE LA8ORATORIES Specimen Ca bl es Part No. Various Amb. Temp. 47879 Job N Spec. WLTP 47 7 - 1 Photo Yes Para. 3.2.4.1 Test Med. Air Start Date rrryup S/N Specimen Temp.

GSI No Test Title FUNCTIONAL TEST SCREENING TEST NO.

Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 1.6x10 A with 500 VDC applied for 60 seconds.

6 Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to 2 Q.og/0 ~

1 to conduit* /d 2 to conduit" /, d p's' Hi h Potential Test Acce tance Criteria'here shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds.

Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to conduit* FdD ~A 2 to condui t* foe ~g

  • Shield tied to conduit.

Tested Sy Witness Notice of Sheet No.

Anomaly Approved Wyl~ Farm wH 6r4A, Rev. APA '54

Page No. 1-41 Test Report No. 47879-02 DATA SHEET Customer CpgrL WYLE LA8ORATORIES Specimen Part'No. Various Amb. Temp. J bN 47879-01 Spec. D 1

Photo Report No.

Para. 3.3.5 Test Med. A~ r Start Date S/N No GSI TestTitie V RC RR NT T T SCREENING TEST NO.

Fault Cable Size:

No. Conductors:

Tar et Cable:

Adjacent Cable:

Mk/.. t

9. Initial readings with current applied.

k Tar et Cable Faul t Cable Adjacent Cables 1 a~a

~

Current 5 0 A8 5 Current: 3 Current: Conductor Temp.: /7 /t Conductor Temp.:

ll. Readings at 90 ~5'C conductor temperature.

Tar get Cable Fault Cable Ad iacent Cables Voltage: Current: / g+ 5 Current:

Current: Conductor Temp Q~t7~ Conductor Temp.: ~~of

/8'2 4' /W/u'<

12. Readings with fault current applied.

Target Cable Fault Cable Adjacent Cables Volta e: V. ry a/r Current: /g Cu 'ren r ..C7d4 Conductor Temp.: Conductor Temp.: 157 / /

Teste Date:

Witness mate: <-<-8 tice of Sheet No. of nomaly Approved 8&

vryle Form vrR 6reA, Reu. AraR ee

Page No. I-42 Test Report No. 47879-02 DATA SHEET Customer CPSL WYLE LA8ORATOAIES Specimen Ca bl es Part No. Various Amb. Temp. Job No Spec. W TP 47 79-01 Photo Yes Report No. 47879-02 Para. 3.3.5 Test Med. Air Start Date No S/N Specimen Temp See Bel ow GSI Test Title OVERCURRENT TEST Continued

15. 5 16. Post-Test Readin s Target Cables:

Voltage:

Current: /, 00 2-Faul t Cable:

Time to Open Circuit: // / wcmhs Ar / 08 Time to Ignition:

Time to Stable Tem .: Nor 8 @ATE<

im rded:

Adjacent Cables:

Current:

Maximum Temp, Recorded: gg $ 'aQ Tested Witness Notice of Sheet No.

Anomaly Approved rNyr ~ Form wH 51@A. pov. ApR 64

Page Vio. I-43 Test Report No. 47879-02 DATA SHEET Customer WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. JobNo.

Spec. Itl TP 47 7 - 1 Photo Y s No. <7879-02

'eport Para. 3.2.4.1 Test Med. Air J

0 SlN Specimen Temp.

No GSI Test Title 0<'~~~ J 85T FUNCTI0NAL TEST SCREEHING TEST NO.

Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 1 .6xl0 JZ, with 500 VOC applied for 60 seconds .

Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 0 1 to conduit* 8 >xio "~

2 to conduit* $ o g/0'i h Potential Test Acceptance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds.

Cable Test Point Reading Tw. Pr. 16 AMG 1 to2 1 to conduit*

2 to conduit*

  • Shield tied to conduit.

Tested By tice ot Sheet No.

omaly Approved Wyle Fo(m WH SteA. Rev, APR 'Se

Page No. I-44 Test Report No. 47879-02 This Page Left Intentionally Blank.

WYLE LABORATORIES Huntavilta Facility

Page No. I-45 Test Report No. 47879-02 CONTROL CABLE SCREENING TEST 03 Photographs Pigures Data Sheets WYLE LABORATORIES Huntsville Facility

Page No. 1-46 Test Report No. 47879-02 o

PHOTOGRAPH NO. I-14 OVERALL VIEW OF THE TEST SEFOP FOR CONTROL CABLE SCREENING TEST 03 hh'I jl 1

t PHOTOGRAPH NO. I-15 CLOSEUP VIEW OF THE CABLE TERMINATIONS AT THE MULTI-AMPCB8130 TEST SET

Page No. I-47 Test Report No. 47879-02 ti ZI I

z>>

PHOTOGRAPH NO. I-16 FRONT VIEW OF THE POST-TEST CONDITIONS h

lob ov. <vsse rnstonier gp~L PHOTOGRAPH NO. I-17 CLOSEUP VIEW OF THE RUPTURE IN THE FAULT CABLE JACKET AFTER THE OVERCURRENT TEST

jih 'I

~

ii !I i il P  !

Control Cable Screen(ng Test 3 Hj lf li I jr; !I

(!

!F1 H

ij LEGEND: Pault Cable Jacket Teaperature (T/CS 1-8) pault cable conductor Tenperature (T/Cs 9 6 10) jfj j

Cl!ECKED BY j

I Target Cable Jacket Teuperature (T/CS 17-24) IIIi iij :i'I ll'4 Conduit Teeperature (T/CS 25 6 26) i lip' ll'li

!i!i hrray Tenperature (T/CS 27-35) r)H

!ij !I,l  !,'jjt Ff jr 1

);

Nac. Tenp. Recorded: 1464 P (T/C 810) at 77.3 n(n fti!

4 (8 hnbient Tenp.: 74 P j ilh Hfl !I 4h!

ih Date) hugust 8, 1985 j~j Lj II!

hl! IJU PIG}tRE I-5 !li

,'4 lij

! I.

IF jliH:

I,PI Hli rd1 1 h ifi',4 I 1

tL}i I li H "f'l) hl !if IH !fh h!i

' !4" ').r 4) )

IIP jh lth i.l

!1L!

f i !h) hli HO

'! h

'!ii 5'j i di' Hl )P ji )lj Ut I jrj , L!

l tth ih jf;I jj 4) i) i j 44 Ijll 0 0 I iii T...i!5 I )1 4 jul

)r -il I)" d f)ji . )l hrA ) ill' ti'!

)U f: 4

)L ,'HI i LL! j jI 4j "if 5!) !H

' Co cr)

U)

U) v 41'I i!if!!H 1) jdj rfh ifh )

f! ~)tf 1

41) V 4 li rr
iii i!i I I ilii n .ii :!i i Bi l11! leg) tlh ',Hij ffL) I i ll i C flit ! ;tl litt I fil fi d!

'ti t

1I UI f ji .' lg IH

!h f1 I W

! jj'I

!f 1! 4:! 4 1 $ 4H I I it! Pj"r fi lii

~ ) ljff B

Z r i 't, l 4

) 4! Ijfil r f

, )H I li 0 'fc i'ii'V)

I Uj j,i fr:i i r.,'jj! !hl ii! !1L HI I I HU I I!!h a ,I'l 1 IB )!P I

I '!'4V 1

1 I)  !

jj' j!

4 !I H'lhi j7J ip 't.i V

.:jlt!Hi rill 4" i: I i !ti lu rl rl tr! t!4,!

in 'i ', if

')ll 1:.1 Li iilf Hl! 1 th,  ! I

!! 'i.l 44:"!H ti '1!h i!p.!

IH !di UIFI I

8 ilr )V Hi 1 i.

l i!4 I Il i!il I4 ')V 4r. 4i iji! " i' I )'

f'

LiI htl It I 'i Hl (MIN)

Page iVo. I-49 Test Report iVo. 47879-02 CONTI'ABLE SCKKNING TEST f3 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 80 F 80 P Energized Pault Cable with 40A 18.3 min 130 P 130 F Energized Fault Cable with 50A 71.3 min 217 P 224 F Energized Fault Cable with 180A 72 ~ 3 Illin 235 P 300 F Light smoke rate 74.5'in 390 F 675 F Fault cable jacket swelling, then rupturing. Heavy smoke rate.

77 ~ 3 m1n 6'7 F 1464.3 F Fault cable conductors shorting together. Peak conductor temperature.

78.3 min 672.9 P 1350 F Peak jacket temperature 84.2 min 375 P 375 P Test shut down at Client's request.

WYLE LABORATORIES Huntsville Facility

Page No. I-50 Test Report No. 47879-02 DATA SHEET CPSL Customer WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. Job No.

Spec. WLTP 47 7 - 1 Photo Para. 3.2.4.1 Test Med. Air Start Date S/N Specimen Temp. 2 GSI iso Test Title FUNCTIONAL TEST p~~(~ ~ SCREENING TEST NO.

Insulation Resistance Test Acce tance Criteria: ivieasured insulation resistance shall be reater than 6

1.6x10 l2. with 500 VDC applied for 60 seconds.

Cable Test Point Reading Tw. Pr. 16 AWG 1 to 2 go~ ~

1 to conduit*

2 to conduit*

Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds.

Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to condui t* I 2.+ o &A, 2 to condui t* l2.5a Mh.

  • Shield tied to conduit.

Tested By Witness Notice ot Sheet No.

Anomaly , Approved Vlyie Form WM 41cA, Rov @FR '44

Page No. I-51 Test Report No. 47879-02 DATA SHEET Customer CPSL VI/YLELABORATORIES Specimen 0 Part No. Various Amb. Temp. Job No. 47879-01 Spec. I D O Photo Report No. 4 Para. 3.3.5 Med. Air YE'est Start Date S/ N Ho IO GSI TestTitle 'l IIC AP T T ST rrarrr&D G68ac SCREENCNG TEST NO. D Fault Cable Size:

Conductors:

~ 2 0 A'/o.

Tar Adjacent et Cable: ~W6 cable: g /r leer.rd.

ggrrcoC

/6 ~

9. 1nitial readings with current applied.

Tar set Cable Fault Cable Adjacent Cables

~or a~u

~ 5>. I Ijo lke current cb A Current: 90 3 Current:,gg le g Conductor Temp.: g f+ Conductor Temp.: p$ ++

ll. Readin s at 90 +O'C conductor temperature.

Tar et Cable Faul t Cable Adjacent Cables l Voltage: g I > Current: Current: zjcg ~@5 Current: Conductor Temp.: fg j~/- Conductor Temp.: g~gop

12. Readings with fault current applied.

Target Cable Faul t Cable Adjacent Cables Volta e: Current: / 0A Current:

Conductor Tem .: M8 O'F Conductor Tem .: /~ 6 /

Tested By Witness ~~

Gare:

Date:

~r~

tice of Sheet No. of nomaly Wyre EOrm WH 3taA. Rev AraR '3a

Page No. I-52 Test Report No. 47879-02 DATA SHEET, Customer CPSL WYLE LABORATORIES Specimen Ca les Part No. Various Amb. Temp. 47879-01 Job No Spec. W TP 47 -01 Photo Yes Report No 47879-02 Para.

S/N GSI 3.3.5 No 0

Test Med, Specimen Temp. ~~~

Air

/Og'p Start Date 4 Test Title 0VERCURRENT TEST Continued

15. 5 16. Post-Test Readin s Target Cables:

Voltage:

Current:

Fault Cable:

Time to Open Circuit:

Time to Ignition:

Time to Stable Tem .: )JD~ 8 p~r'-kh(yo I+Pc>49 F ~ D Adjacent Cables:

Current:

Maximum Temp. Recorded:

@~ g op

)90 A-14A..3 F & SV ~

4P kd m~

,P

~o~~

/rroa I~I W Qa eA~

LUQd.

~CgrvLM.

Tested By Date: ~-

Witness r2 o MX'ate:

Notice of Sheet No. of Anomaly Approved wyl~ Form wH 61sA, Rw, ApA 'so

Page No. 1-53 Test Report Nn ~ 87870 n'y DATA SHEET Customer CPSL WYLE LABORATORlES Specimen Cabl es Part No. Various Amb. Temp. '7879 Spec. W TP 47 7 - 1 photo Yes Para. 3.2.4.1 Test Med. Air Start Date S/N Specimen Temp. /04 "/-

GSl No Test Title i- CQ~Q8~g /~ FUNCTIONAL TEST SCREENING TEST NO.

Insulation Resistance Test Acceptance Criteria: Measured insulation resistance shall be reater than 6

1.6xl0 J2. with 500 VOC applied for 60 seconds.

Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 1 o conduit*

2 to conduit*

Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds.

Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to conduit*

  • Shield tied to conduit.

2 Q / ~

to conduit*

Tested By Witness t ice ot Sheet No.

.anomaly Approved wyle fccm wH OciA, Aev, ApR '44

Page No. I-54 Test Report No. 47879-02 This Page Left Intentionally Blank.

WYLE LABOAATOAIES Huntsville Facility

Page No. I-55 Test Repor t No. 47879-02 CONTROL CABLE SCREENING TEST N4 Photographs Pigures Data Sheets WYLE LABORATORIES Huntsville Facility

Page No. 1-56 Test Report No.. 47879-02 PHOTOGRAPH NO. I-18 PHOTOGRAPH NO. I-19 OVERALL VIEW OF THE TEST SETUP FOR CLOSEUP VIEW OF THE TESI'ETUP CONTROL CABLE SCREENING TEST 44 SHOWING THE 1-INCH SEPARATION BETWEEN THE FAULT CABLE AND THE CONDUIT

Page No. I-57 Test Report No. 47879-02 4 L.". i%~

i 1

t

/

I 0

0 (i~

PHOTOGRAPH NO. I-20 OVERALL VIEW OF POST-TEST DAMAGE FROM CONTROL CABLE SCREENING TEST 04 PHOTOGRAPH NO. 1-21 CLOSEUP VIEN OF POST-TEST DAMAGE TO FAULT CABLE

'I'.. .Irj ;Ir

~ 4,," ',,

ri ' t!jj:Itlrji! ij hl jit'i Iii :!

Control Cable Screening Test 4 j I }

'.I', w Ij I

} I I'. ',", '.;

LEGEND: Pault cable Jac}aet Temperature (T/cs pault Cable Conductor Temperature (T/Cs 1-8):.I it,'i!)Vt 'i,'i q)+Ijjj<<}:jf}1;i ~gjl.;IJ}, j i"t vi,','j i ji j'j:

flI 'I'"! iTl" "'"

1500::!! I!): Ht}

Cable Jacket Temperature (T/CS 17-24) 9 4 10);ji ite(!',t! >$ t,,f',(!1! '.Bj ',jet Hf:,!', !'I,! ',!'.Jt'! I J);JI ',

)j ) $)( ")I! Jt(

'};;,:r, ft,r conduit Temperature (T/cs 26 4 26)

'arget j>> i 'Vr Im I ii ir'! I << ij

',"; I":,; 'flj T~i I"}I 7!! ~~r;:fj ~ft [1 [V(t,~~

vj I I ijrt JI i; 0,'ti IHHH )Hi!!il! '}!}!I!i!)Hil' Bj'1 Ii!""!}(1': B} ':: il!":!Lf'".

') j

<400 '.:..::,:.:;;f Ht) jt)iH(V)(H 7array Temperature (T/CS 27-35) it v e;I la atj jf!I !)I. I}jt ftr) Illj v f

)

i jj'.ij )aff i

' ' iii )!'r i)'j ill} Jj!'r}i I'i: !' ial! "i.'i(j i(i }ii! (!:

tfv 'H "i'} '.'

e

'., i'B,i Mr}x. Temp. Recordedz 963.4 P (T/C 44) at 87.6 min I'1 jt)I j tt 'tjf f!H 1,;i! (tff ff!i 'fj H' i ~}t !i! iffi 't Ff t!B I I I l 'N I ff IFi qt

'fV tt'} f)'<<r HVI f['f i i'fi')!IVI 7 I" I')!

t}mb(ent Temp.t 83 P

'300 Date: )august 8, 1985 )

r'I'r IH(1 J I'j (j)i Hj )i') ' ifj ift;;it!,')H i)![((!i)itl J't ti i .. I,'i::a<<,r tti>>;:.:...,;:..n 1200 '! 1}:.':!(1 (Hj!1,! )j 't 1 ')Ir .Hat} Ih! !H)!ti I 'I (H't(! I; )! H!)h L! II I H l I!Ii ffH I ! ) ff i ff ) 1 J( I

') fj )'.ll iHI i(!!!f!)(IHfj )tH ffjt HT! H! I}H ifH!)it i!i': '.f:::.)':.:

J ':::!

1100 1::: I".':;I'V'":!I!1!I lj(! (g!V 'At:(6:.'A Bi,'11).

i<<: i" '<<f,,t:Jt ir}, aa(a 1

it

}l ii(t Ai

',!ir rr,

'ia(11(V

. II Bii'!IB ii}i (B>> ti iiV.:iiiBV }B} B

.ti'I)'}Viga lgi r, Bit ijii !air I

m ttt>>ri ff)!l JI},f!tiff'fJ(fl!ftV} Iffi '!!f~)Pfl )IJJ)TJ!

'!I: 7!B( !ter <<j' r)jj!"' t I<<j Hri: V ~

te I f~l!

t I Vt)

I, I

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t 'lit'I) " I lit!') V )I t ) jr) Bff 1"t(j!( )))(f'fr))(}t(fail'(Jjj:}'1:6Bj: <<j!'ij BB:9:1}

i!,';-" Hi! ' 'i<< ti'"!!lii): iij! '!'li!,',I;i}iif'i !fat 'rjj ijii 'ii i:fi f f! '"j (Ha i)i[ Hti i)ti ii'f!1 t! ij j '1 t)i

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I I I I: r ', H. )I I[t )H! It!> (B tji( )IB Hf, lr H I L}f H)i Hii,}ie }!JI (Hi II)i Bi.'V(,'t,j f:t!,'H! (taa ftt

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'l> Ht;! jl gl!<<!

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ijli H!'tj'. ".Ai (H hii i"H;i', IH!Jf '." i'! )gi iti i>i' '(ii }J!j il! 1(t 'fig!'. 'it; .'!'r!I }J! (  ! i Htr I "tt aaf jt 'J I lll, (Ji I !I(}(! iV:,:l I 3); ),;,

'!.IV: ip}l 'ji'>f VA('tH) h pal! [ )I!gl',Ha:j I ) t,' (H( ',

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Page No. I-59 Test Report No. 47879-02 I t COPI.'ROL CABLE SCEKENING TEST f4 APPROXIMATE TEMPERATURE 'PPROXIMATE TEST TIME JACKET CONDUCTOR OBSERVATION 93 F 93 F Energized Fault Cable with 40A 10 min 125 F 125 P Energized Fault Cable with 50A 82.2 min 216 P 186 F Energized Fault Cable with 180A 894.0 min 341 F 387 P Light smoke rate 84.9 min 455 F 510 F Pault cable jacket swelling, then rupturing. 85.8 min 560 F 615 F Heavy smoke rate I 87.5 min 832.0 P 963.4 F Open circuit indicated test set. Peak jacket by multi-amp and conductor temperature. WYLE LABORATORIES Huntsville Facility

Page No. I-60 Test Report Ho. 47879-02 DATA SHEE'F CPS'ustomer WYLE LABORATORIES="-- Specimen Ca bl es Part No, Various Amb. Temp. Job No.

                                                                                                         '7879 Spec.             WLTP 4                7   1                   Photo Para.            3.2.4.1                                       Test Med. Air                Start Oate S/N               N                                                             ~/

No Gsi Test Title FUNCTIONAL TEST O~Ro4 ~ SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance. shall. be. reater..than 1.6xl0 & with 500 VDC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 0 /tie ~42-1 to conduit* 2 to conduit" Hi h Potential Test cc tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to conduit* 2 to conduit*

         *Shield tied to conduit.                       ~.   /I'~

I Tested By.<~ Witness Oate: Notice of Sheet No. of F Anomaly Approved V+I~ FOrm WH 6144. Rtv. APR 'Si

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Page No. I-62 Test Report No. 47879-02 QATA SHEET Customer WYLE LABORATORIES -.- .- Specimen C es part No. Various Amb. Temp. 47879-01 Job No. S P ec. W TP 4 79 01 Photo Yes Report No. 47879-02 Para. 3.3.5 Test Med, Air -P No Specimen Temp. See Bel ow. o I GSI Test Title OVERCURRENT TEST Continued

15. 8 16. Post-Test Readin s t

Tar ge Ca bl es: Vol tage: ~~ Q J~ Current: . 7g Fault Cable: Time to Open Circuit: Time to Ignition: Nous Time to Stable Temo.: Akr Ag LI<H~

                                              ,d d. Vdl-'       ~

Adjacent Cables: Current: Maximum Temp. Recorded: QQJ P~~ Tested By Notice ol Sheet No. Anomaly Approved <Ny< ~ Form <rrr<< IllA.Rr<rr. <<PR 'I4

Page No. I-63 Test Report No. 47&79-02 DATA SHEET CP&L WYLE LABORATORIES Customer Specimen Cables Part No. Various Amb. Temp. Job No. Spec. W TP 47 7 - Photo Yes

                                                                                                         ~f.

1 Para. 3.2.4.1 Test Med. Air ,

                                                                                    '1 rrM S/N                                                        Specimen Temp.

GSI No Test Title ~- OU&QQ~~g /~( FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: pleasured insulation resistance shall be reater .than .. 1.6x10 N with 500 VOC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 3. 0 M lo 1 to conduit* ,5 IO' 2 to conduit" frO X IQ Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cabl e Test Point Reading Tw. Pr ..16 AWG 1 to2 l55 ~fo 1 to conduit* lloo Lt,A, 2 to condui t>> ) )Da i%A,

            *Shield tied to conduit.                    Q.G~

Tested By @ D.te: ~-<- ~S Witness Date: tice of Sheet No. of I omaly '."ryro Form wrr OllA, Ror. ArrR 'll

Page No. I-64 Test Report No. 47879-02 This Page Left IntentionaIly Blank. WYLE LABORATORIES Huntsville Facility

Page No. I-65 Test Report No. 47879-02 CONTROL CABLE SCREENING TEST 05 Photographs P jpIres Data Sheets WYLE LABORATORIES Huntsville Facility

Page No. I-66 Test Report No. 478Z9-02 l // PHOTOGRAPH NO. I-22 OVERALL VIEW OP THE TESI'ETUP POR CONTROL CABLE SCREENING TEST 05 PHOTOGRAPH NO. I-23 POST-TEST SIDE VIEW OP CONTROL CABLE SCREENING TEST 05

Page No. I-67 Test Report No. 47879-02

  <<s     <<.,479'la     =---

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                             '  ',r     .   ~~/ W'.','~ W'>,0     i, PHOTOGRAPH NO. I-24 CLOSEUP VIEW OF DAMAGE TO FAULT CABLE d,fat,I<5

((t. ', (/ I 1 lr I 0 r PHOTOGRAPH NO. I-25 POST-TEST FRONT VIEW OF CONTROL CABLE SCREENING TEST N5

1500 'get LEGENO t ~ Control Cable Screening Test 5 Pault Cable Jacket Tet>Perature (T/CS 1-8) Pavlt Cable Conductor Tersperature (T/CS 9 Cable Jacket Teapef ature Conduit Tetttperature (T/CS 25 a 26) (T/CS 1 7 24) 4 10)

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Page iso. I-69 Test Report No. 47879-02 CONT!5K CABLE SCREENING TEST 45 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 82 P 82 F Energized Fault Cable with 75A 64 min 205 F 191 P Energized Fault Cable with 180A 73 min 362 P 350 F Light smoke at series connection at the buss bar end. 81.6 min 495 P 457 F Fault cable jacket swelling, then rupturing. 934.4 F 729.6 P. Steady state reached and test terminated per Client's request. Peak jacket and conductor temperature. WYLE LABORATORIES Huntsville Facility

Page No. I-70 Test Report Ho. 47879-02 DATA.SHEET CP&L VVYLELABORATORIES Customer Specimen Cabl es Various ' Part No. Amb. Temp. JobNo. Spec. W TP 47 7 - 1 Photo Ye Para. 3.2.4.1 Test Med. Start Date S/N Specimen Temp. No GSI Test Title FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 1 .6xl0 J2. with 500 VOC applied for 60 seconds . Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 1 2 to conduit* to condui t* 4.0 /0" ~ Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 to conduit* / 8O~ 2 to conduit* oo A

          *Shield tied to conduit, Tested By                   D..:Z DM Witness                     Date:

Notice of Sheet No. oE Anomaly Approved Wyie Covcv WH 41cA, Aov. APA '8c

Page No. 1-71 Test Report No. 47879-02 DATA SHEET Customer CP&L WYLE LABORATORIES Specimen r y Part No. Various Amb. Temp. Job No 47879 01 Spec. D 1 Photo Para. 3.3.5 Test Med. Air Start Date S/N Gsl Test Title V RR RT T ST SCREENING TEST NO. 4 Fault Cable Size: Tar et Cable: ~tJ. No . Conductors: Adjacent Cable:

9. Initial readings with current applied.

Tar aet Cable Fault Cable Adjacent Cables ol a 5i& Yo l 4 current: 5A 5 Current: D 5 Current:,Dg I p /o Conductor Temp.: +g op Conductor Temp.:

11. Readings at 90 +5'C conductor temperature.

Target Cable Faul t Cable Adjacent Cables Vol tage: gg.o t/gl" ~ Current: Current: Current: .g I GR Conductor Temp.: /r7'g JEST+ Conductor Temp.: gpss+<+

12. Readings with fault current applied.

Target Cable Fault Cable Adjacent Cables Vol ta e:,4 I/i4~ Current: )$ J/ jj Current:

                          ~

oo A. Conductor Tem N3/ Conductor Tem .: f772% Tested By Date: tice of nomaly gaytC? Witness Sheet No. Approved ol~ Date:

                                                                                                           -F-8s-Wyle FOrm WH lSTRA. Reu. AeR '84

Page No. I-72 Test Report No. 47879-02 DATA SHEET Customer CP5L WYLE LABORATORIES Specimen Cabl es Job No '7879-01 Part No. Various Amb. Temp. Spec W TP 47 7 -Ol Photo Report No. 47879-02 Para. Test Med. Ai r Start Date SIN Specimen Temp. See 8el ow= 0 GSI OVERCURRENT TEST Continued

15. 5 16. Post- Test Readinas Target Cables:

Vol tage: Current: Fault Cable: Time to Open Circuit: Time to Ignition:- Time to Stable Tem .: /0$ 'OA, BP ~o. (g //oua5 T rd d: Ad jacent Cables: Cur rent: Maximum Temp. Recorded:

                                              +II $ >p 7 g~             I S~InJ WY52) 57 C'CI K~4 QI~CFIO~ ~gI~g P~ ~R MA5 AldX/W~A o~ R W<~ oa W~ ~7- ~We 4'55 KRM I Q F Ie I 6 Pull/V<~es <r DC/M Cfj57 /4 WAS '7.               I    /        $ g4     p  p d. 7'r Tested By                    Date: ~+~~<K Date:

Notice of Anomaly N Sheet No. Approved of

                                                                                                    -5'-f4 wyle Fotm wH 41lA, Rev, APA '$4

Page No. I-73 Test Report No. 47879-02 DATA SHEET Customer CP&L WYLE LABORATORiES Specimen Cabl es O Par LNo. Various Amb. Temp. 47879. J bN Spec. Wi.TP 47 7 -01 Photo Yes Para. 3.2.4.1 Test Med. Start Date S/N Specimen Temp. GSI No Test Title n~ - BJ~~i /~ FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: measured insulation. resistance shall be reater than 6 1.6x10 l2. with 500 VOC applied for 60 seconds. Cable Test Point Reading Tu. Pr. 16 AWG 1 to 2 1 to conduit" 2 to conduit" sin Hi h Potential Test Acc tance Criteria There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr . 16 AWG 1 to2 1 to condui t* L12c U4, 2 to conduit* l )zoll@

           *Shield tied to conduit.

Tested By +~ Date: Mm~ Witness Date: Sheet No. oi Approved vry.'o Form AH 514A. Aov. ApA '84

Page iVo. I-74 Test Report iso. 47879-02 This Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Facility

Page No. II-1 Test Report No. 47879-02 SECTION II POWER CABLE SCREENING TESTS (DETERMINATIONOP WORST CASE CABI E AND HORIZONTAL CABLE TRAY TO CONDUIT SEPARATION TEST) 1.0 REQUIREMENTS Acceptance Criteria 1.1.1 Insulation Resistance Test Insulation resistance on all "target cables"* shall be greater than 1.6 x 106 ohms with a potential of 500 VDC applied for 60 seconds. Before testing insulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the Overcurrent Test. 1.1.2 H h Potential Test shall be no evidence of insulation breakdown or flashover with a potential of 1 VAC applied for one minute. ,1.1.3 Cable Continuity Test Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 50 VAC before, during, and after the overcurrent test. Cable No. CPRL Cable Rated Size Conductors LD. No. Voltage Current 16 AWG 1 Tw. Pr. D60-01 L 50 VAC 1A 1.1.4 Tolerances All target cable voltages specified in this procedure shall be maintained within a +3% tolerance. All target cable currents shall be maintained within a +10% tolerance. All fault cable currents shall be maintained within a+3% tolerance. The term "target cable" refers to energized and monitored nonfault cables used in this program. WYLE LABORATORIES Huntsville Facility

Page No. II-2 Test Report No. 47879-02 2.0 PROCEDURES 2.1 Test Specimen Preparation The test setup for the six Power Cable Screening Tests was identical except as noted in the following paragraphs. The test specimens were mounted to the unistrut frame of Figure 1 of Section VI. This apparatus was assembled to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following guidelines were observed with regard to the materials and construction of this assembly:

1. The faulted cable was one of the following cables from CPRL stock:

Test No. Pault Cable Size CPtst:L LD. No. 3-1/C 10 AWG D25-01 3-1/C 6 AWG D25-03 3-1/C 2 AWG D25-05 Triplex 4/0 AWG D25-08 Triplex 350 MCM D25-01 3-1/C 500 MCM D25-11 The fault cable was the top centermost cable inside an 8' 24" x 4" ladder ru cable tray filled to the top of the sideraQs with de-energized power-type cables.

2. Nine 1/C 10 AWG cables (Tests 1-4) and nine 1/C 6 AWG cables (Tests 5 and 6) were mounted underneath and around the faulted cable per Figure II-1. These cables were energized and their conductor temperatures increased prior to applying the fault current to the fault cable. This was done to simulate the heat which the fault cable would experience in a cable tray of energized cables.
3. The ends of the faulted cable from their termination to the edge of the cable tray were wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape. This was done as a safety measure to ensure that any ignition that might occur was contained to the cable tray area.
4. A. 9-foot long, 1-inch rigid steel conduit was mounted parallel to and 1 inch above (12 inches for Tests 1-3, 5 and 6) the fault cable. This conduit contained a single pair 16 AWG target cable (CPRL I.D. No. D60-01). The 1-foot section of this conduit which extended past the cable tray was wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a.single layer, 50% overlap, of 3M No. 69 glass tape.

WYLE LABORATORIES Huntsville Facility

Page No. II-3 Test Report No. 47879-02 PROCEDURES (Continued) 2.1 Test Specimen Preparation (Continued)

5. A wind barrier was installed around the unistrut frame to eliminate the effects of wind on the heat transfer of the fault cable.
6. Photographs were taken of the test setup.
7. A 1/2-inch VHS recording was taken of the Overcurrent Test encompassing the entire application of the test current.

2.2 Instrumentation Setup 2.2.1 Thermoco le Locations A total of 26 Type "K" thermocouples were utilized for these tests. These thermocouples were mounted as described below: Channel No. Location 1-8 Mounted to the jacket of the fault cable. These thermocouples were spaced approximately 12 inches apart. 9 R 10 Mounted to the conductors of the fault cable. These thermocouples were mounted to the conductors by lifting the insulation and applying the ther mocouple between the conductor strands. The termination was then wrapped with the WT-65/3M No. 69 tapes. Mounted to the conductors of the nine cables adjacent to the faulted cable. Three thermocouples were mounted to each end of these cables. 17-24 Mounted to the jacket of the single pair 16 AWG target cable inside the 1-inch conduit. These thermocouples were spaced approximately 12 inches apart and were even with the eight fault cable thermocouples. 25 4 26 Mounted underneath the 1-inch conduit and spaced 2 feet from the center of the conduit. These thermocouples were monitored using a Fluke Datalogger feeding a high-speed printer. . The datalogger was operated at its maximum rate throughout the Overcurrent Test. Data from these thermocouples has been plotted versus time and is contained in Appendix II of this section. WYLE LABORATORIES Huntsville Facility

Page No. II-4 Test Report iVo. 47879-02 2.0 PROCEDURES (Continued) 2.2 Instrumentation Setup (Continued) 2.2.2 Electrical Monitor The voltage and current of the target cable and the fault cable current were continuously monitored with an oscillograph recorder. The oscillograph was operated at the 0.1-inch per minute rate throughout the Overcurrent Test. The oscillograph channels were as specified in the following table: Channel No. Si Location Current Tw. Pr. 16 AWG Voltage Tw. Pr. 16 AWG Current Fault Cable A digital multimeter was utilized to measure voltage and current of the target 'cable prior - to, during, and after the Overcurrent Test. This data was recorded to provide accurate evidence of the specimen's capability to conduct rated current at 50 VAC throughout the Overcurrent Test and is presented in Appendix II of this section. 2.3 Baseline Functional Tests The baseline functional tests consisted of Insulation Resistance and High Potentia measurements on each of the target cables. These tests were performed as described below:

2.3.1 Insulation Resistance Test
1. All power and instrumentation leads were disconnected from the target cable.
2. Shield to conduit resistance was measured with a digital multimeter.
3. Using a megohmmeter, a potential of 500 VDC was applied and the minimum insulation resistance indicated af ter a period of 60 seconds was recorded between the following test points:

Phase-to-Phase Phase-to-Ground* 1to2 1 to conduit 2 to conduit

  • Shield tied to conduit.

For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 WYLE LABORATORIES Huntsville Facility

Page No. II-5 Test Report No. 47879-02 PROCEDURES (Continued) 2.3 Baseline Functional Tests (Continued) 2.3.2 H Potential Test

1. Using a Hi-Pot Test Set, a potential of 1600 VAC was applied and the leakage current observed after a period of 60 seconds was recorded between the following test points:

Phase-to-Phase Phase-to-Ground~ 1to2 1 to conduit 2 to conduit

  • Shield tied to conduit.
2. Power and instrumentation leads were reconnected to the target cable.

For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shall be no evidence of insulation breakdown or flasho ver. Overcurrent Test vercurrent Test was conducted in two sequential phases with no intentional time delay between phases. The first phase consisted of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90 C +5 C. The second phase consisted of energizing the fault cable with the test current until the cable open-circuited. The .target cable was energized at rated current and 50 VAC throughout the Overcurrent Test. The Overcurrent Test was conducted using the following procedure: The fault cable (see the table on following page) was connected to the copper bus bars per Figure 7 of Section VI.

2. A single pair 16 AWG target cable was installed in the 1-inch rigid steel conduit per Figure 1I-1.
3. Viine 1/C 10 AWG cables (Tests 1-4) or nine 1/C 6 AWG cables (Tests 5 and 6) were installed adjacent to the fault cable per Figure II-1.
4. The single pair 16 AWG target cable were connected to the instrumentation and power supplies of Figure 11 of Section VI.
5. The nine adjacent cables were connected to the power supply per Figure 8 of Section VI.

The single pair 16 AWG cable was energized with 1 ampere at 50 VAC. The nine 1/C 10 AWG cables (Tests 1-4) or nine 1/C 6 AWG cables (Tests 5 and 6) were energized with 40 amperes (Tests 1-4) or 75 amperes (Tests 5 and 6) at reduced voltage. WYLE LABORATORIES Huntsville Facility

Page No. II-6 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.4 Overcurrent Test (Continued)

8. The fault cable was energized with the initial currents listed in the table below.
9. Target cable voltage and current, fault cable current and initial eonduetor temperature, and adjacent cable current were recorded.
10. Fault cable current was slowly increased to achieve conductor temperature of 90oC +5oC for a period of 15 minutes.

ll. Target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current were recorded.

12. The fault cable current was increased to the test current value in the table below.
13. Target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current were recorded.

14: The fault cable was allowed to conduct the test current until the cable open-cireuited.

15. Time to ignition and open-circuit were recorded.
16. Target cable voltage and current and adjacent cable current were recorded.
17. The target cables, adjacent cables, and the Multi-Amp Test Set were de-energized.
18. Post-test conditions were photographed.

For all performances of this test, the observed target cable operation was compared to the acceptance criteria, Para raph 2.1.3, i.e., they maintained continuity of power. Fault Cable Sizes and Currents Test CPRL Initial Test No. Fault Cable Size I.D. No. Warm Current Current 1 3-1/C 10 AWG D25-01 40A 704A 2 3-1/C 6 AWG D25-03 75A 704A 3 3-1/C 2 AWG D25-05 130A 704A 4 Triplex 4/0 AWG D25-08 260A 4200A 5 Triplex 350 MCM D25-10 350A 4200A 6 3-1/C 500 MCM D25-11 430A 4200A 2.5 Post-Overeurrent Test Functional Test The functional tests of Paragraph 3.3.4 were repeated on the target cable as soon as t smoke cleared in the test chamber. In addition, the target cable jacket temperature w recorded. WYLE LABORATORIES Huntsville Facility

Page No. II-7 Test Report No. 47879-02 The six Power Cable Screening Tests were conducted per Paragraph 2.0. One anomaly occurred during these tests on Power Cable Screening Test No. 4 with the Triplex 4/0 AWG fault cable and the 1-inch rigid steel conduit mounted 1 inch above the fault cable. During this test, the fault cable ignited after 83 seconds, with 4200 amperes applied, and the flames engulfed the 1-inch rigid steel conduit. The exterior of the conduit reached temperatures of 929.3oF and the Twisted Pair 16 AWG target. cable inside reached temperatures of 644.8oF. The Twisted Pair 16 AWG target cable did maintain sufficient integrity to conduct 1 ampere at 50 VAC throughout this test, but was severely damaged and did not pass either the Post-Test Insulation Resistance or High Potential Tests (see Notice of Anomaly No. 1 in Appendix I of this section). This test demonstrated that 1-inch vertical separation between a 1-inch conduit and a horizontal cable tray is insufficient physical separation for the worst case electrical fault at the Shearon Harris Nuclear Power Plant. Consequently, the conduit placement was moved to 12 inches vertically above the tray for Power Cable Screening Tests 1-3, 5 and 6. (Power Cable Screening Test 4 was conducted out of sequence at the custo mer's request.) The remaining Power Cable Screening Tests successfully met the Acceptance Criteria of Paragraph 1.0 and demonstrated that a 12-inch vertical separation distance was adequate. The Twisted Pair 16 AWG target cable showed no evidence of visual degradation during these tests and successfully completed the Post-Overcurrent Test Functional Tests. esults of the six Power Cable Screening Tests are summarized in the following tables: TABLE L CURRENTS APPLIED AND TIME TO OPEN CIRCUIT NEC Current at Test Fault Cable Rated 90oC +5 Conductor Test Time to No. Size Current Tem erature Current 0 en-Circuit 3-1/C 10 AWG 40A 50A 620A (1) 160.64 sec 3-1/C 6 AWG 75A 75A 704A 105.7 sec 3-1/C 2 AWG 130A 130A 704A 598.0 sec (2) Triplex 4/0 AWG 260A 285A 4200A 93.0 sec (3) Triplex 350 MCM 350A 370A 4200A 183.25 sec 3-1/C 500 MCM 430A 476A 4200A 459.07 sec Notes: (1) The Multi-Amp CB8130 test set was not capable of delivering 704A to this cable due to the high impedance of the cable at elevated conductor temperatures. The machine was capable of delivering the 704 amperes with conductor temperatures at ambient conditions. The fault cable conductors shorted together after approximately 10 seconds at 620 amperes during this test. (2) Fault cable conductors shorted together after approximately 598 seconds at 704 amperes during this test. (3) Fault cable conductors shorted together after approximately 320 seconds at 4200 amperes during this test. WYLE LABORATORIES Huntsville Facility

Page No. II-8 Test Report No. 47879-02 3.0 RESULTS (Continued) TABLE IL MAXIMUMTEMPERATURES Test Fault Cable Pault Cable Target Cable 1-Inch No. Size Jacket Jacket Conduit 3-1/C 10 AWG 1136.2oF 108.1oP 118.0oF 3-1/C 6 AWG 1060.7oF 99.0oF 106,3oP 3-1/C 2 AWG 2141.5 P 166.5op 209 9oF Triplex 4/0 AWG 1673.5oF 644.8oF(1) 929 9oP Triplex 350 MCM 1600.3oF 251 6oF 477.3oF 3-1/C 500 MCM 1534.0oP 210.1 F 230.4oF Notes: (1) 1-inch conduit mounted 1 inch above fault cable for this test. For all other tests, the conduit was 12 inches above the fault cable. TABLE IIL TIME TO IGNITION AND BURN TIMES Test Fault Cable Time to Approximate No. Size Ignition Burn Time 3-1/C 10 AWG 160 seconds 1 minute 3-1/C 6 AWG None N/A 3-1/C 2 AWG 410 seconds 9 minutes Triplex 4/0 AWG 83 seconds 8 minutes Triplex 350 MCM 154 seconds 7 minutes 3-1/C 500 iYICM 441 seconds 6 minutes Based on observed fault cable tempei'atures, times to ignition and open circuit, and insulation burn time, the Triplex 350 MCi>I cable was selected as the worst case cable size with the fault current of 4200 amperes. This cable was utilized as the faulted cable for the subsequent configuration tests. WYLE LABORATORIES HuntsvtIte'Facility

Page No. II-9 Test Report No. 47879-02 RESULTS (Continued) Appendices I, II and III contain the following data from these tests: Appendix L Notice of Anomaly No. 1 which documents failure of the Twisted Pair 16 AWG target cable during Test No. 4. Appendix II: Figure IH-1 which illustrates the test setup for the Power Cable Screening Tests. Appendix III: Individual test data. This data is separated into individual sections for each test conducted. Each section contains: (1) Photographs of the test setup and post-test conditions; (2) A narrative of the test; (3) A plot of temperature data versus time; and, (4) Data Sheets which record Baseline Functional Tests, the Overcurrent Test, and the Post-Overcurrent Test Functional Test Data. WYLE LABORATORIES Huntsville Facility

Page No. II-10 Test Report No. 47879-02 This Page Left Intentiona11y Blank. WYLE LABORATORIES Huntsville Facility

Page No. II-ll Test Report No. 47879-02 AFFENDIX I NOTICE OP ANOMALY WYLE LABORATORIES Huntsville Facility

Page No. 11-12 Test Report Np. 47879-02 LABOAATORlKS (Eastern Operations) DATE: NOTICE OF ANOMALY 8/30/85 NOTICE NO: 1 P.O.NUMBER: H-61740 CONTRACT Np: N/A CUSTOMER: Carolina Power a Li ht WYLE JOB Np: 47879 NOTIFICATIONMADETO. Matt Petrizzo Alex Carloman o NpTIFICATIpNDATE. 8 6 85 NpTIRCATIpN MADE BY J. Hazeltine yIA; Verbal/On-Site "CATEGORY: 2 SPECIMEN '3 PROCEDURE 0 TEST EQUIPMENT DATE OF ANOMALY: 8/6/85 PART NAME. AIW Twisted Pair 16 AWG PART Np D60-01 TEST: Post-Overcurrent Test Functional Test I.D. Np. 12. 0 SPECIFICATION. WLTP 47879-01 PARA. Np. REQUIREMENTS:

l. Insulation resistance on all target cables shall be greater than 1.6xl0 ohms with a potential of 500 VDC applied for 60 seconds,
2. There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 1 minute.

DESCRIPTION OF ANOMALY: Insulation resistance from conductor-to-conduit was greater than 10 ohms, wh indicates a lost of shield to drain continuity.

2. The cable could not hold 1600 VAC from conductor-to-conductor or conductor-to-conduit, which indicates insulation breakdown.

DISPOSITION - COMMENTS - RECOMMENDATIONS: Thc triplex 4/0 AWG fault cable ignited 'after S3 seconds at 4200 amperes. The flames engulf ed the conduit mounted 1 inch above the fault cable and resulted in peak temperatures of 929.9 F outside the conduit and 644.S F inside the conduit. f The post-test visual inspection revealed that the outer jacket on the cable was severely damaged along the entire length. Several areas existed where a bare conductor was visible. This test demonstrated that 1-inch vertical separation between a cable subjected to the worst case fault at the Shearon Harris Nuclear Power Plant and a 1-inch rigid steel conduit is insufficient physical separation.

NOTE
IT IS THE CUSTOMER'S RESPONSIBILITY Tp ANALY2EANOMALIES AND COMPLY WITH 10 CFR PART 21.

y ERIF I CATION: PROJECT ENGINEER: WITNESS. Matt Petrizzo/Alex Carlomango

                                                                                    /'EST PROJECT MANAGER REPRESENTING:      C   ro         o e ~ ig              INTERDEPARTMENT COORDINATION:

L 5 QUALITYASSURANCE: p Wyle Form WH 1068, Rev. JAN '85 1 of 2 Page

Page No. II-13 Test Report No. 47879-02 NOTICE OF ANOMALY NOA NO. 1 J/N 47879 8/30/85 Page 2 of 2 DISPOSITION - COMMENTS - RECOMMENDATIONS: (Continued) Since this test was run out of sequence, it was decided to conduct the remaining Power Cable screening Tests with 12-inch vertical separation between the faulted cable and the 1-inch rigid steel conduit containing the twisted pair 16 AWG target cable. Testing was continued i QI YLE LABORATORIES FORM 1066A Huntsville Facility

Page No. 11-14 Test Report No. 47879-02 This Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Facility

Page No. II-15 Test Report No. 47879-02 APPENDIX II TEST SETUP PIGURE WYLE LABORATORIES Huntsville Facility

Page No. 11-16 Test Report No. 47879-02 LAST 6 INCHES OF CONDUIT WRAPPED WITH WT-65/3M 69

                                                                                          ~

UNIST RUT SUPPORTS

  • (1 INCH FOR TEST 84 ONLY) 24" x 4" x 96" LADDER RUNG TRA 1 INCH RIGID STEEL CONDUIT TYPE "K" THERNOC U LES TWISTED PAIR MOUNTED U DER CON U T 16 AWG-TARGET Y CABLE FAULT CABLE ADJACENT CABLES e g go 0000 24 I I II 3O FAULT RAY FILLED TO TOP OF ITS SIDERAILS CABLE ITH POWER TYPE CABLES FRONT VIEW TARGET CABLE TOP VIEW FIGURE I I-l: POWER CABLE SCREENING TEST SETUP

Page No. II-17 Test Report No. 47879-02 APPENDIX III INDIVIDUALTEST DATA WYLE LABORATORIES Huntsville Facility

Page No. 11-18 Test Report No. 47879-02 This Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Facility

Page No. 11-19 Test Report No. 47879-02 POWER CABLE SCREENING TEST 01 Photographs Pictures Data Sheets WYLE LABORATORIES Huntsville Facility

Page No. II-20 Test Report No. 47879-02

    /   J PHOTOGRAPH NO. II-1                                 PHOTOGRAPH NO. II-2 PRE-TESI'ETUP VIBW OP POWER CABLE                     OVBRALLVIEW SHOWING DAMAGE SCREENING TEST 41                               AFTER OVBRCURRENT TEST v~4.~ <

Iv + PHOTOGRAPH NO. II-3 SIDE VIEW OP POST-TEST DAMAGE

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              'I LEGEND:   ~

Po((er Cable Screening Test 1 Pault Cable Jacket Testperaturo (T/CS 1-8) pault cable conductor Teaperature iT/cs 9 Target Cable Jacket Teaperature IT/CS 17-24) 6 10) jj DRf}}}NBY CIIECKED BY

              'i!                                    conduit Tenperature IT/cs 25 6 26)                                         IIIi i    J j4ax. Tesp. Recorded(    1262.0 P IT/C 49) at 54.2 (sin
    }iii I<<   rl j                                           Anbient Teap.r 91 P 43                                                        Date: august 12, 1985 I';

I  %,P<< tj PIGURE II-2 I!!9 H! I I

                                                                                                                                        <<t f1  5 Hj Idden IH Hl i&i I<<ll              j  <<

0 0 gj v  !!H s r '<< rd I.'(Ij I I tt 1 e

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      <<1                           Hjj                                                                                               IH ii Z

I 0 f HL ~ '\ !ik 'll i<< I( (ill i!ji flit

    .i<<

1(I: .<<

    "I'i     .'! (6          I I  I  <<j
                                   <<I I   ~

I'I I Hr .1<<j 1<< t<<I ig i "rj!!!Iirf. TIME (MIN)

Page No. II-22 Test Report No. 47879-02 POHER CABLE SCREENING TEST jl APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTGOR OBSERVATION 94 F 94 F Energized fault cable with 40A 8.7 min 129 F 129 F Energized fault cable with 50A 30.3 min 195 F 180 F Energized fault cable with 45A 36.5 min 198 F 180 F Energized fault cable with 50A 51.5 min 212 F 191 F Energized fault cable initially with 620A, decreasing to 250A 53.7 min 1106.9 F 1106 F Peak recorded jacket temperature. 54.2 min 965 F 1262 F Open circuit indicated by multi-test set. Peak recorded conducto temperature. Ignition of fault cable. 55.2 min Fire out. WYLE LABORATORIES Huntsville Facility

Page No. II-23 Test Report No. 47879-02 DATA SHEET Customer CPSL VVYLE LA8ORATORIES Specimen Ca bl es Part No. Various Op Amb. Temp. Job No Spec. WLTP 4787 - 1 Photo Report No. a787 -02 Para. 3.2.4.1 Test Med. Air Start Date S/N Or o~ Specimen Temp. GSI No Test Title FUNCTIONAL TEST DLO~ ~~ SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 6 1.6xl0 JZ, with 500 VOC applied for 60 seconds. Cable Test Point, Reading Tw. Pr . 16 AWG 1 to2 o xro~~ 1 to condui t* gD /D 2 to conduit* Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2

                                            '    to condui  t" 2  to conduit*
          *Shield tied to conduit.

tice of

                                                                      ...,.,~k:.,

Witness Sheet No.

                                                                                  ~~,//i/Zz....r-
                                                                                       /

Date:

                                                                                                           ~

oi nomaly Approved z-8S vs< ~ Fwn 'oH el4A. 4tv. ApR '$4

Page No. II-24 Test Report No. 47879-02 DATA.SHEET Customer CPEL WYLE LABORATORIES Specimen Part No. Various Amb. Temp. 47879 01 Spec. I D Photo Para. 3.3.5 Test Med. Air Start Date S/N No GSI TestTitle V C R NT T T SCREENING TEST NO. Fault Cable Size: Tar et Cable: No. Conductors: Adjacent Cable: ~,u~ j~

                                                                                                                 ~
9. Initial readings with current applied.

Target Cable Fault Cable Adjacent Cables Current; 90 A 5 Current: Current: ay ~ q COnduCtar TemP.: CP+,S e+ CanduCtar TemP.: CP 1 1 . Readin s at 90 +5'C conduc tor tempera ture. Tar et Cable Faul t Cable Adjacent Cables Voltage: Current: orl Current: 3 Og Current: /. gg g, Conductor Temp.: /Tgp pop Conductor Temp.: /$g g~~

12. Readings with fault current applied.

Tar get Cable Fault Cable Adjacent Cables Ilolta e: r5W C/ K/Vy Current: ggOyl md~i uuu Current: J P/2-' nductor Tem .: 4-id Conductor Tem .: / Tested By Notice of Sheet No. Anomaly Approved 'Lyyl~ Porrra vdae Inlet, Reu. ARR 'Tld

Page No. II-25 Test Report No. 47879-02 DATA SHEET CP&L Customer WYLE LABORATORIES Specimen Ca les-Part No. Various Amb. Temp. 4787901 Job No Spec. Iai TP 47879-01 Photo Yes Report No. 47879-02 Para. 3.3.5 Test Med. Start Date No S/N Specimen Temp See Bel ow

                      <0 GSI Test Titie           OVERCURREHT TEST        Continued
15. & 16. Post-Test Readin s Target Cables:

vol tage: 5 +. $ 6/o /g Current: ~ S5 4Afg Fault Cable I'ime to Open Circui t: /gal. $ g ~~ Time to Ignition: ~ /50,mc.. Time to Stable Tem y") c.rC c7c'8 e i T o R c rded: /a+4O+ Adjacent Cables: CUI'eeoa: Maximum Temp. Recorded:

                                                                       ...,...,~// - w~u~~., e '-r~

Sheet No. Approved of~

                                                                                                 $ -/ z -5m wyle Foehn wH sgaA. Rey. ApR '3e

Page No. II-26 Test Report No. 47879-02 DATA SHEET. Customer CP8L WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. Job No. Spec. W TP 47 7- Photo "es 3.2.4.1 Air Para. S/N GSI No Test Med. Specimen Temp. ~llvr Start Date Test Title Pc@. DVIcsQCcCAA?6V, l~ FUNCTIONAL TEST Ry ~A3CS SCREEi'lIRG TEST NG. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than. 1,6x10 A with 500 VDC applied for 60 seconds . 6 Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 /, 4~/o',0 1 to condui t" Y(o' 2 to condui t" c) )(/0 c? Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 i <WE 1 to conduit* 9+nu A. 2 to conduit*

            *Shield tied to conduit.

Tested By

                                                                                         'itness Notice of                                                                       Sheet No.

Anomaly Approved r,I VITIG Goriyl VIII OllA. Aev, AlyII OG

Page No. II-27 Test Report No. 47879-02 POWER CABLE SCREENING TEST N2 Photographs Pigures Data Sheets WYLE LABORATORIES Huntsville Facility

Page No. II-28 Test Report No. 47879-02 7 t Ef (, 0 I (f~X~ I ho P Off' L. I (

  '(I
                                  ,I PHOTOGRAPH NO. II-4                            PHOTOGRAPH NO. II"5 FRONT VIEW OF TEST SETUP FOR                     FRONT VIEW OF POST-TEST DAMAGE POWER CABLE SCREENING TEST N2 I

C l I j

                                                                           -r'-

C ffL ~ 1 PHOTOGRAPH NO. II% CLOSEUP VIEW OF DAMAGE TO FAULT CABLE AFTER OVERCURRENT TEST

luit I li

                                   ~

LEGS!f0: ~ Power Cable Screen)ng Test 2 Fault Cable Jacket TesPerature (T/CS l-8) Fault cable conductor Tesperature {T/cs 9 a Target Cable Jacket Tesperature fT/CS 17-24)

10) I
                                                                                                                        !It j  1 i}i IH
                                                                                                                                                }If
                                                                                                                                                . I   nRAffN  sv(

cfiscjfzn nvi I Condu)t Tesperture {T/CS 25 I 26)

                .I   I
                                                       )fax. Tesp. Recorded( 1202.7 P fT/ir tln) at 55.1 s)n
I I Asb)ent Tesp.z 86'P iii! Dater August 13, 1985
II! IIH=!

fr IH FIGURE II-3 I lu I;! I I :0 fiji!i li I f f1 Ff ji!! IHI! I !H Hl i .HII 1 Hl 1;fi 'iii !'il

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                                                                                                                                                                                  'XA OO iH!

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                                      ! ii li! l '1 Q

Hi nr !i:". iii: , I! 0: if tf

                        ;>>!; II 0"
>>i iiji "!i TIME (M}N)

Page No. H-30 Test Report No. 47879-02 POKDt CABLE SCREENING TEST 42 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 89 F 89 F Energized fault cable with 75A 53.3 min 208 F 196 F Energized fault cable initially with 704A, decreasing to 480A. 55.1 min 772 F 1202.7 F Open circuit indicated by multi-amp test set. Peak recorded conductor temperature. 57.6 min 1060.7 F 820 F Peak recorded jacket temperature. WYLE LABORATORIES Huntsville Facility

Page No. 11-31 Test Report No. 47879-02 DATA SHEET Customer WYLE LABORATORIES Specimen Ca bl es Part No. Various Amb. Temp. Job No. Spec, WLTP 4787 -0 Photo Report No. 47879-02 para 3.2.4.1 Test Med. Air Start Date S/N Specimen Temp. GSI No Test Title FUNCTIONAL TEST Rove C48 SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 1 .6xl0 A with 500 VOC applied for 60 seconds . 6 Cable Test Point Reading IO Tw. Pr. 16 AWG 1 to 2 t. o 1 to conduit* 7.~ X/o 2 to conduit* 7 +Y/D Hi h Potential Test Acce tance Criteria There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr . 16 AWG 1 to2 1 to condui t* 2 to conduit*

          *Shield tied to conduit.

Tested By Date: Witness Date: ice of Sheet No. oI omaly Approved -r8-8& vryre Form vrH dyeA, Aey A FR 'de

Page No. II-32 Test Report No. 47879-02 DATA SHEET Customer CPIt L WYLE LABORATORIES Specimen Part No. Yarious Amb. Temp. Job No 47879-01 Spec. Photo Vr. R Para. 3.3.5 Test 51 ed. S/N No

                           <  0 GSI Test Title         Y RC     RR NT       T" T      tc>M<=K      CAB        . <=                       SCREENING TEST NO.             2 Fault, Cable Size:                                                    Tar      et Cable:

No. Conductors: - '/c Adjacent Cab<a: <A<~ ~/<

9. Initial readings with current applied.

Tar et Cable Fault Cable Adjacent Cables m ~A ac@ ~+ 8 >f7 > Current />@~PS Current:

                                                                                ~g 1

Current: +/Q ~ Conductor Temp.: / Conductor Temp.: ll. Readin s at 90 +5'C conductor temperature. Yo 1 Target Cabl tage: Current: g e j Fault Cable Current: Conductor Temp.: 9gg,/ j-Adjacent Cables Current: Conductor Temp.: ygq ~~ 12 . Readings with fault current applied . Target Cable Faul t Cable Adjacent Cables

     </o! ta e:            3 LZ
                                 ~ A'82 H~            Current:                  /~j y r Fy/g C.          Cu  r r e n t:

s Cond<jc or Temp.: .SC ~0 d< Conductor Temp.: J ~7 << Teste~ r-~+~ ~- ~ Date: d ~+ Notice of Anomaly Witness Sheet No. Approved ~ ~ ejr

                                                                                                                         ~    ate:

of c-y Wy< ~ Form W<< 5<eA. Ree. APR 'Sa

Page No. II-33 Test Report Vio. 47879-02 DATA SHEET Customer VVYLE LABORATORIES Specimen Ca les ee Part No. Various Amb. Temp. Job No Spec. WLTP 47879-01 Photo Yes Report No. 47879-02 Para. 3.3.5 Test Med. Air Start Date S/N fio Specimen Temp See Bel ow GSI OVERCURREIIT TEST (Continued

15. & 16. Post-Test Readin s Target Cables:

Voltage: ~+, 5/y g Current: I . DO 2 Fault Cable Time to Open Circuit: Ig4. 7+MCGwM. gy/>4 rwfyii}z~t '7M(- 3 ggiw gi/c Time to Ignition: BNE k'$ <H /Ik~< k> S~r&c&i Time to Stable Temp.: PDl 9 C/~8K~ i mTm rdd: ~P~7F /0 Adjacent Cables: Current: Maximum Temp. Recorded: +/+. Q '/t= Tested By-Witness . Sheet No. Yggie fera wag SteA. Rev. @pat 'ee

                                                                                              ~  ~      ~    ~
         ~ ) I   ~
                                     ~     ~             jr                   ~ ~       ~
                                                                                                       ~   ~
                                                                                 ~ ~
                                                                                       ~ .
                                                                                  ~        ~

II I . ~ ~ ) ~ ~ I - ) ~

                                                                                          ~      ~
                                 ~ ~   ~
                                 ~ ~   )
   ~   ~
     ~
         ~                               ~   ~           ~         ~               ~         ~     ~   ~ ~     ~
                                                ~ )   -      .     ~   ~ II   '          ~   ~     - ~     ~   ~ I
                         ~   ~
                         ~
                           ~                                                 ~       ~
                       ~   ~   )
                       ~   ~   ~
           )   ~   ~ ~

~ ~

                                                  ~ ~   ~            @TED

Page No. II-35 Test Report No. 47879-02 POWER CABLE SCREENING TEST N3 Photographs Pigures Data Sheets WYLE LASORATORIES Huntsville Facility

Page No. II-36 Test Report No. 4?8?9-02 y".<z'AP'if PHOTOGRAPH NO. II-? NO. II-8

                                                                           'h'HOTOGRAPH OVERALL VIEW OP TEST SETUP POR                    PRONT VIEW OF POST-TEST DAMAGE POWER CABLE SCREENING TEST 02
                                                              ~l+1P%PPF i: ~a,~+

PHOTOGRAPH NO. II-9 SIDE VIEW OF DAMAGE TO FAULT CABLE APTER OVERCURRENT TESI'

                                                                                                                                                                                                                                                                                                    ~

th  !! i,i II Power Cable Screen(ng Test 3 I! '1)' ;jf: jn B PRAWN j}Y) 5)1  !,)

                                                                                                                                                        )i!                                                       i!f                                      Ih
                                                                                          /                                            1 ~
                                                                                                                                            ',h jl:

uh !I LEGENO) Pault Cable Jacket Temperature (T/CS l-8) I"-. 1!.l 1! Il fi h f'1 Qjf

                                                                                                                                                '!      )!                                                                                                                                                    Pault Cable Conductor Temperature (T/CS 9 s 10)-

1 CtfECKED RY h', 4 1500  !! "tl lit! 1 8;j fri f' j Target Cable Jacket Temperature (T/CS 17-24) ij B jij!if fjti '11'!If Conduit Temperature (T/CS 25 4 26)

                                                                                                                       !II        f!                                                                                                                                         lff 1400                                                                                                                                             If!i
                                                    'Ij! 114                                        '): jj:j il!!      "jf 1 1 jl                                                                                Max. Temp. Recorded)              2141.5 P (T/C 42) at 71.4 min jt
                                                                                                                                                                                                         'ii 1

f! ) 5! IB

                                                                                                                                 'I!                                                                                4              "1)                                                                                     Amb(ent Temp.) 89 P 1300                             4~4B ih lf!i                                        ! Ij!I    l!i'i!              h                                                                                                ili                                                                                    Date) August 13, 1985
                                             !jh                                                                                                                                                                                            j!!                                  h 1200 :j:th                             '
1:! i i~j
                                                                                                                                                                                                                                                                                 '1 PIG!}RE      II-4
j:: :1!! ,'h fjf, 41 I j!j! h i if i)B , I ij.j <<)1 [1 rr'f! i:. ",1 ) bi 1100 .)h 41 j!'I fl 8 h jl 8 'h 4! Bj "I! 'fjj '!'f ),l'ft!

jjj  ! I

                                                                                                                                                    .1 h       'i!                                             !Bj     jfjl lgj.                      hi 1000              't:            j)4 !!jj j:tj       ',1: f                                                                 i:
! ',1!! 0 8  !!T! j!jj h !').'. "1)

BB I:;:

                                                                              'I!1 114                                                                                      '1j hl                                                  h                                                                                               i!          4 8               111:    1       II 900                             Llj                                    j}!1 !!!1
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i'.j) f4 <<itl 14 B. B, ih 'th 1 1 1 L44 8 450 jj':r '1'1 8! 1 l! 1 }i!

                                                                                                                                                             '1 11 ih     jTt                                                                                                                jl 1   ir4 ',!                                                                                                                     8                                                                                                                                                                                                           8 v,r                                  '1'ih                                                 j'n                                                                                                              h 400                  1!    111!

L!I h 1! f!i: jffj  ! In f'i 7f; I<<; h

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I:i! !jll 1,:I  !!)j tj, 50 41, th f1 8 h  ! h 1!

                                             !j:j j!1!:!l'                                            !jpj h

I j: i:.1l)'.if!i!jrli l}20:1 t I "lf j'tt 1)40!j fB )'j! jc: Bt'rj uf tent! B lj h'f B.

Page No. II-38 Test Report No. 47879-02 POWER CABER SCR193NING TEST 4 3 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 101 F 101 F Energized fault cable with 130A 65 min 215 F 196 F Energized fault cable with 704A 69 min 680 F 680 F Very heavy smoke (off-gassing7) 70 min 995 F 880 F Ignition of fault cable 71.4 min 2141.5 F 1110 F Peak recorded jacket temperature 75'in 1672 F 1411.5 F Open circuit indicated by multi-amp test set. Peak recorded conductor temperature. WYLE LABORATORIES Huntsville Facility

Page No. II-39 Test Report No. 47879-02 QATA SHEET CPIy L Customer WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. Spec. W TP 47 7- Photo Yes Para. S/N GSI 3.2.4.1 Test Med. Air Specimen Temp. ~! Start Date + ~~ Test Title FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 1 .6xl0 & with 500 VOC applied for 60 seconds. 6 Cail e Test Point Reading Tw. Pr. 16 AWG 1 to 2 1 to conduit* 2 to conduit* 7.agio Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cabl e Test Point Tw. Pr. 16 AWG to2 conduite'eading 1 1 to conduit* 2 to

         *Shield tied to conduit.

Tested By Date: MC-'Ll;5 Witness Date: tice of Sheet No. of nomaly Approved Wyl~ Farm wH ByeA, Rev. A FR 'Be

Fage No. II-40 Test Report No. 47879-02 DATA SHEET Customer CPSL VVYLELABORATORIES Specimen Part No. Various Amb. Temp. 47879-01 Spec. o o Photo Para. 3.3.5 Test Med. Air Start Date S/N No GSI Test Title R T T SCREENING TEST NO. Fault Cable Size: Tar et Cable: TA P . 1 Ld No. Conductors: Adjacent Cable: 4f I < O p+~

9. Initial readings with current applied.

Tar et Cable Fault Cable Adjacen. Cables 1 aa Current. l3D A PS Current: 39.R 8& Current: Conductor Temp.: PP. Conductor Temp,: 5+ 3'~~

11. Readings at 90 +5'C conductor temperature.

Tar et Cable Fault Cable Adjacent Cables Voltage: Current: Current:g q Current: /, @gal g5 Conductor Temp.: Q ~

                                                                            </I    Conductor Temp.: gpss       p~
12. Readings with fault current applied.

Target Cable Faul t Cable Adjacent Cables

                                            ~                                                              gQ~

1 Vol ta e: 9, O 4 Current: 7 Curr ent: PD Conductor Temp.: 08 t t- Conductor Temp.: Notice of

                            /vs Tested B Witness Sheet No.

Date: Date: of

                                                                                                           ~~

g-r7-fs Anomaly Approved Wyl~ Form VrH elsA. Aov. APA '8l

Page No. II-41 Test Report No. 47879-02 DATA SHEET CPSL Customer WYLE LABORATORIES Specimen Ca es Part No. Various Amb. Temp. Job No 47879-01 Spec. W TP 47879-01 Photo Report No. 47879-02 Para. 3.3.5 Test Med. Start Date Ho Bel ow S/N Specimen Temp See GSI Test Titie OVERCURRE'NT TEST Continued

15. 8 16. Post-Test Readin s Target Cables:

Voltage: Qg Q 4jp Current: . Nay lfP+5 Faul t Cable: Time to Open Circuit: Time to Ignition: ~ +/0 ~Co&hS'ime to Stable Tem .: WD< g'/C/&AS~

               'm       T              rd d:        Pl+-E          I Adjacent Cables:

Current: Maximum Temp. Recorded: Tested By Date: Witness Date: Sheet No. of Approved Wyl~ Foam WH 6leA, Aev, APA '84

Page No. II-42 Test Report No. 47879-02 DATA SHEET. CPSL Customer WYLE LABORATORIES Specimen Cabl es Part No. Various Amb. Temp. Job N Spec. WTP 77-01 Photo ReportNo.47 7 -o Para. 3.2.4.1 Test Med. Air ,~e S/N Specimen Temp. No GSI Test Title FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 6 1.6xl0 J2. with 500 VDC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 jc'~ to conduit* /0 1 2 to conduit* /O lo'~ JO Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to conduit" to conduit*

         *Shield tied to conduit.

2 2 9

                                                      ~
                                                            ~

Tested By D.te: ~-'~- >> Witness Date: Notice of Sheet No. 'of Anomaly Approved -IZ-8~ wyl~ Form wH OleA, Rov. AyrR 84

Page No. II-43 Test Report No. 47879-02 PONER CABLE SCREENING TEST N4 Photographs Pigures Data Sheets WYLE LABORATORIES Huntsvilla Facility

Page No. II-44 Test Report No. 47879-02 1 I

      >j 8',
  • PHOTOGRAPH NO. II-10 OVERALL VIEW OF TEST SETUP FOR POWER CABLE SCREENING TEST 04 cy W PHOTOGRAPH NO. II-11 CLOSEUP VIEW OF TEST SETUP SHOWING 1-INCH SEPARA'IION FROM FAULT CABLE TO 1-INCH CONDUIT

0'age No. Test Report No. II-45 47879-02

                            'v'HOTOGRAPH PHOTOGRAPH NO. Ii-13 CLOSEUP VIEN OF DAMAGETO NO. 11-12                                 PAULT CABLE AND HORIZONTALTRAY PRONT VIEW OF DAMAGBFROM                         (Note: The Pire Self-Bxtinguished and Then Smoldered in the POWER CABLB SCREENING TEST 04 Cable Tray Causing Extensive Damage to Surrounding Cables)
                                                                  /

( j ( PHOTOGRAPH NO. II-14 POST-TEST VIEW OP DAMAGE TO TWISTBD PAIR 16 AWG CABLE FROM 1-INCH CONDUIT. THE CABLE'S SHIELD WAS VISIBLE IN TNO LOCATIONS BUT THE INDIVIDUALCONDUCTORS WERE SHLL PROTECTED.

[673.5 1500 1" I.

             'I'ip I

HP I: !: Pover Cable Screening Test 4 LEGEHD) ~ Fault Cable Jacket Teaperature (T/CS 1-8) Pault Cable Conductor Tesperature (T/CS 9 6 1(}) Target Cable Jacket Tesperature (T/CS 17-24) I tt llt!,'f"li i p I Li li I hli

                                                                                                                                                                                                                                                                                                                }[H li li D})At!It BY CHECKED BY:

CI I"!

t. Condu(t Tenperature (T/CS 25 s 26)

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1400 Nax. Tenp. Recordedi 1673.5 P (T/C 82) at 117.8 n(n I I I.  !!H!!1: :I:. A)Lb(ent Tesp.: 82 P ii ih! II'

                                                                                                                                                                                                                                                                  !1 L't                                                                                                        !IH 1
                   "I'                                                                                           Dates August 6, 1985                                                                                                  f1 I pif                                                                                   !!h                                        j'ilj ii! !hI 1300 i,'!

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Page No. II-47 Test Report No. 47879-02 POKgt CABLE'CREENING TEST 44 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 85 F 85 P Energized fault cable with 260A 5 min 97 F ,97 P Energized fault cable with 275A 67.2 min 185 F 170 P 'nergized fault cable with 280A 87.2 min 197 P 180 P Energized fault cable with 116. 3 'min fault cable initially 285A'nergized 210 F 191 P with 4200A decreasing to 1000A ','; 116.8 min 450 F 450 P Light off-gassing 117.7 min 1000 F 850 P Ignition of fault cable 117.8 min 1673.5 P 1077.4 F Open circuit indicated by multi-amp test set. Peak recorded jacket and conductor temperature. 125 min 1055 P 696 P Pire out WYLE LABORATORIES Huntsville Facility

Page No. II-48 Test Report No. 47879-02 DATA SHEET CP&L WYLE LABORATORIES Customer Specimen Ca bl es Part No. Various Amb. Temp. Pe Job No; 47879 Spec W TP 47 7 - 1 Photo Ye Para. 3.2.4.1 Test Med Air Start Date S/N Specimen Temp. GSI No FUNCTIONAL TEST Test Title SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall. be reater than 1.6xl0 C2. with 500 VOC applied for 60 seconds, Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 D )c/0 1 to conduit" g.o 2 to conduit* Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 /Po 1 to conduit* SIMBA. 2 to conduit*

         *Shield tied to conduit.

Tested By Witness Notice of Sheet No. Anomaly Approved Wyle Form WH Ree. APA 'Sa

Page No. II-49 Test Report No. 47879-02 DATA SHEET'P&L Customer WYLE LABORATORiES Specimen -"-PartNo:- -- .. Various Amb. Temp. 8 Job No." 47879-01.-- Spec Photo v Para. 3.3.5 Test Med. Air Start Oate B 6-8m S/ N No GSI TestTitle OV RR NT T T SCREENING TEST N0.4 Fault Cable Size: No. Conductors:

                                             +10  ~M                               Tar et-C-able:

Adjaceet Cab,le:. lu).k. /b f

                                                                                                                   ~
                                                                                                          . /c icl ~el@             ,
9. Initial readings with current applied.

Tar et Cable Fault Cable Adjacent Cables 1 a ~ ~ t ~< e Current: 46 0 8'urrent: 4D Current: [, Ly] $ Conductor Temp.: gQ. g /- Conductor Temp.: +$.4~/= ll. Readings at 90 +5'C conductor temperature. Taraet Cable Fault Cable Adjacent Cables Vol tage: g, jt pA~ Current: Current: Current: /. g g /I Conductor Temp.: /f/ / ~E Conductor Temp.:

                                                                                                                        /3.gjjp'2.

Readings with fault current applied. Target Cable Fault Cable Adjacent Cables Volta e: D. 9 VHC Current: gA)O 8 Current: g++ g o.'Q$ ' Conductor Tem .: g4A-4 t Conductor Temp.: 4/9 / r7dofgM ~o ~ DAoo4 rw 5c zedo~9 Tested By ogive:9 ~-F~ Witness Oale: S ~-~ tice of Sheet No. oi nomaly Approved -6WM wyla Foam wH 51AA, Rev, AFR 'jba

Page No. II-50 Test Report No. 47879-02 DATA SHEET. CP&L Customer WYLE LABORATORIES .- Specimen Cal s Part No. Various Amb. Temp. 4787901 Job No Spec. W TP 4 7 01 Photo Report No. 47879-02 Para. 3.3.5 No Test Med. Air , ~H-S/N Specimen Temp. See Below 0 GSI Test Title 0VERCURREHT TEST Continued

15. & 16. Post- Test Readin s Target Cables:

Voltage: ~-9 V8C. Current: g. 9 R A Faul t Cable: Time to Open Circuit: fg, gg ~go~~ Time to Ignition: Time to Stable Tem .: AJo7 Atg&C-gcgck'm Adjacent Cables: Current: Maximum Temp. Recorded:

                                               // gg $ 'P
 ~ R~sli)i~                      7R~         AH~~ H~AmW mdL/r Cei                        OM Tested~

Witnes Notice of Sheet No. Anomaly Approved Wylt Form WH 514A. Aev, APA '8l

Page No. 11-51 Test Repot't No. 47879-02 GATA SHEET Qi Customer WYLE.LABORATORIES,. Specimen Cabl es part No Various Amb, Temp. 47879 Job No Spec QLTP 4 7 01 Photo para. 3.2-4.1 Test Med. Air Start Date S/N Specimen Temp. GSi Test Title DS<" FUNCTIONAL TEST OQ3g SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 1.6xl0 & with 500 VOC applied for 60 seconds. 6 Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to condui t" 2 to conduit*

                          &LE4 r80            7$ 5      r4 4dr<c- 0/&3 g~rA?Cu(FEB Hi h     Potential Test Acce tance      Criteria:     There shall be no evidence      of insulation breakdown or flashover with    a  potential of 1600 VAC applied for 60 seconds.

Cabl e Test Point . Reading Tw. Pr. 16 AWG 1 to2 1 2 to condui to conduit* t* 9 @ bs'o~P E yoaoc~< Poove ~

          *Shield tied to conduit.

g/~ ~p pffft P/J /Q~cAr- WrrrWur 2F~p&/wr' ~4, Lecc guzi n> o~rw + 8'&Dr~ Tested By D.te: ~-'-~~ Witness Date: tice of Sheet No. of omaly Approved -c-sa Wylt Porm WH 8llA. Rev,APA '8l

Page No. II-52 Test Report No. 47879-02 This Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Facility

Page No. II-53 Test Report No. 47879-02 POWER CABLE SCREENING TEST N5 Photographs Figures Data Sheets WYLE LABORATORIES Huntsville Facility

Page No. II-54 Test Report No. 47879-02 0 PHOTOGRAPH NO. II-15 PHOTOGRAPH NO. II-16 OVERALL VIEW OF TEST SETUP FOR OVERALL VIEW OF DAMAGE POWER CABLE SCREENING TEST N5 AFTER THE OVERCURRENT TEST PHOTOGRAPH NO. II-17 CLOSEUP VIEW OF DAMAGE INSIDE TRAY. NOTE THE LOCATION OF THE OPEN CIRCUIT.

                                                          ~
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            !jr              Po)ter Cable Screening Test 5                                                                                                                                                                       ,:'j.

f 1!ft !Hf t I Lt) 1

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DRhW}f }}I LEGE}(D) Pault Cable Jacket Temperature }T/CS 1-8) H 1 I 1>> paula cable conductor Temperature [T/cs 9 6 10) jJjl tf I Cj}ECKED DY)

                                                                                                                                                                                                                                 'I!,                                                                                          .(i Target Cable Jacket Temperature [T/CS 17-24)                                                                                                                 h fr.r if!j                                                                 Conduit Temperature                               {T/CS 25               6    26)                                                                                                                                                             HI
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                                                               }4ax. Temp. Recorded)                                    1600.3 P [T/C 65) at 121.9 min
            !.t:                                                                                        hmblent Temp.r 87 P                                                                                                                      lit      ![ii                                                                                             h Date) hugust 14, 1985                                                                                                                               [r(H(

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Page iVo. II-56 Test Report No. 47879-02 POKER CABLE SCREENING TEST $ 5 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 85 F 85 F Energized fault cable with 350A 28.3 min 120 F 120 F = Energized fault cable with 360A 59 min 155 F 155 F Energized fault cable with 365A 75 min 169 P 169 F Energized fault cable with 370A 118.8 min 197 F 187 F Energized fault cable with 4200A 119.8 min 250 P 560 Light off-gassing 120.8 min 950 P 950 F Heavy off-gassing 121. 4'in 1160 F 1158.4 F Ignition of fault cable. Peak recorded conductor temperature. 121. 9 min 1600.3 F 1140 P Open circuit indicated by multi-amp test set. Peak recorded jacket temperature. 127 min 1215 P 920 F Fire out WYLE LABORATORIES Huntsville Facility

Page No. II-57 Test Repot t No. 47879-02 DATA SHEET CPIyL Customer WYLE LABORATORIES Specimen Cables O Part No. Various Amb. Temp. bN 47879 Spec. W TP 47 7 Photo Para. 3.2.4.1 Test Med. Air Start Date S/N Specimen Temp. y/nZ 7 GSI No Test Title FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than

                                                      .6x10 A with 500 VDC applied for 60 seconds .

6 1 Cabl e Test Point Reading Tw. Pr. 16 A'WG 1 to2 1 to conduit* /O)C/O 2 to conduit* /o (o Hi oh Pote nti al Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AIIG 1 to2 1 to conduit* 2 to conduit*

          *Shield tied to conduit.

Tested By ~>4+'~~~'>~+~- '~ ~-~

                                                                                        /"'              Date:

tice of Witness Sheet No.

                                                                                       +
                                                                                             ~       '

Date: of

                                                                                                             - Z-
                                                                                                                  /,

nomaly Approved 'Vylt Form v(tt SylA. Aiv, APR '8l

Page No. II-58 Test Report No. 47879-02 DATA SHEET Customer CPSL WYLE LABORATORIES Specimen Part No. Various Amb. Temp. Job No. 47879-01 Spec Photo Report No. Para. 3.3.5 Test Med Ai r Start Date S/N Ho GSI Test Title RC RR NT T Fault Cable Size: Conductors: T

                                              '~-1T-t FcCX Tar SCREEHING TEST NO.

et Cable: 7Z 8-Adjacent Cable:

                                                                                                  ~ /6 rjO  /c" A~'o.
9. Initial readings with current applied.

Tar et Cable Fault Cable Adjacent Cables 1 a Current: D0 / Current: 7%4 Current: /t, 0/g PQ Conductor Temp.: gg P Conductor Temp.: ll. Readings at 90 +5'C conductor temperature. Tar et Cable Faul t Cable Adjacent Cables

    '/ol tage:          ~.f /           td/p,Q     Current:     Q T7gp                  Current:     r7Dp Current:            ). D  9 R               Conductor Temp.:                     Conductor Temp.:       /gfF.p<~
12. Readings with fault current applied.

Target Cable Volta e: 53 6'urr Fault Cable ent: Conductor 20 Tem .: D$ 9% Adjacent Cables Current: Conductor Temp.:

g. L7
                                                                                                               /f8 Tested By Witness Notice of                                                                Sheet No.

Anomaly Approved wyr ~ Form wre dldA. Tteu. AtrA 'dd

Page No. II-59 Test Report No. 47879-02 DATA SHEET CPSL Customer WYLE LABORATORIES Specimen Ca les Part No. Various Amb. Temp. Job No 47879 01 Spec. W TP 47 79-01 Photo Report No. 47879-02 Para. 3.3.5 Test Med. Start Date S/N IIo See Bel ow Specimen Temp. GSI Test Title OVERCURRENT TEST Continued

15. 8 16. Post-Test Readin s Target Cables:

voltage: Q. ice /P~

                                                  'urrent:

Fault Cable: Time o Open Circuit: t Q.g+~~~~ i Time to Ignition: ~ /+ Time to Stable Temo.: 4ai g/L,CAc9< i T m R rded /400,3 Adjacent Cables: Current: Tested By Witness tice of Sheet No. nomaiy Approved vv'yr ~ perm wH 5reA, rrev, ApR 'le

Page No. II-60 Test Report No. 47879-02 DATA SHEET Customer CPSL WYLE LABORATORIES Specimen Ca bl es Part No. Various Amb. Temp. o~ J bN 47879 Spec. Para. S/N W TP 47 7 3.2.4.1

                                  -0                    Photo Test M ed.

Specimen Temp. Air ~v Report No. 47879-02 GSI No Test Title ~t GU~ AiY J~ FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall .be reater than ... 1.6x10 & with 500 VOC applied for 60 seconds. 6 Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 9.&grd 1 to conduit* g.~geo' 2 to condui t" Z> x/0' Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 g7&~A 1 to conduit* 2 to conduit*

         *Shield tied to conduit.              Q.g A-Tested By Witness                      Date:

Notice of Sheet No. oi I Anomaly Approved -z4-8s Wyl~ Fo(m WH 514A. Rev. APR 'SA

Page No. II-61 Test Report No. 47879-02 POWER CABLE SCREENING TEST 06 Photographs, Pigures Data Sheets WYLE LASORATORIES Huntsville Facility

Page No. H-62 Test Report No. 478Z9-02 PHOTOGRAPH NO. II-19 PHOTOGRAPH NO. II-18 POST-TEST FRONT VIEW SHOWING OVERALL VIEW OF TEST SETUP FOR DAMAGEAFTER THE OVERCURR T T POWER CABLE SCREENING TEST N6

 /   W/

PHOTOGRAPH NO. II-20 CLOSEUP VIEW OF DAMAGETO FAULT CABLE IN HORIZONTALTRAY

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Page No. G-64 Test Report No. 47879-02 POSER CABLE SCREENING TEST 46 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 97 F 97 F Energized fault cable with 430A 15 min 108 F 108 F Energized fault cable wtih 440A 30 min 125 F 125 F Energized fault cable with 450A 66.7 min 154 F 162 F Energized fault cable with 460A 77.5 min 160 F 170 P Energized fault cable with 465A 87.2 min 165 F 175 F Energized fault cable with 470A 97.2 min 170 F 180 F Energized fault cable with 475A 106 min 172 F 185 F Energized fault cable with 476A 121 min 176 F 188 F Energized fault cable with 4200A 123.8 min 465 F 750 F Light off-gassing 124.8 min 561 F 990 F Fault cable jacket rupturing. Heavy off-gassing. 125 min 575 F 1007.6 P Fault cable conductors shorting together. Peak recorded conductor temperature. 128.3 min 1100 P 945 F Ignition of fault cable jacket. 128.6 min 1220 P 940 F Open circuit indicated by multi-amp test set. 130 min 1534 F 922 P Peak recorded jacket temperature WYLE LABORATOAlES Huntsville Facility

Page No. II-65 Test Report No. 47879-02 DATA SHEET CPSL Customer WYLE LABORATORiES, Specimen Cables Part No. Various Amb. Temp. bN 47879 Spec. W TP 4 7 -0 Photo Para. 3.2.4.1 Test Med Air Start Date

                                                                                %or~

S/N GSI No Test Title FUNCTIONAL TEST SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 6 1.6x10 J2. with 500 VDC applied for 60 seconds. Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to 2 1 to conduit* -,I 2 to conduit" ggi'i h Pot:ential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 4/aPA 1 to conduit* /o/a AA 2 to conduit* /eaoQR

         *Shield tied to conduit.

Tested By . ~&a. Date: tice of Sheet No. of nomaly Approved wyr~ corm vrH sr AA, Rov. APA 's4

Page No. 0-66 Test Report No. 47879-02 DATA SHEET Customer CPSL WYLELABORATORIES Specimen Part No. Various Amb. Temp. Job No. 47879-01 Spec. Photo Para. 3.3.5 Test Med At r S/N No Gsi Test Title C R T T T SCREENING TEST NO. Fault Cable Size: No. Conductors: 5 MCN- Tar et Cable: 7~, P~. dt'5 Adjacent Cable:~gIAJ+

                                                                                                                  ~
9. Initial readings with current applied, Tar et Cable Fault Cable Adjacent Cables ol ao ~ H~' HnCurr'ent: &'urrent: 7> ~WE Current: It, Odg Ify'5 C nductor Temp.: 5pd'I Conductor Temp.:

ll. Readinas a 90 +6'C conductor temoerature. Target Cable Fault Cable Adjacent Cables Vol tage: +g. I Current: +gg g Current: current: cy g r6 Q conductor Temp.: jpgmym'onductor Temp.: /argo~

12. Readings with fault current applied.

Tar get Cable Fault Cable Adjacent Cables Volta e: 4'RC Current: Current:

                                                                  ~'onductor Temp                 Conductor   Temp     /9g Tested Sy               w, sr=

Witness Date: Notice of Sheet No. of Anomaly Approved lyyl'e FOrm WH 0 1eA, Reu. raPR 'rye

Page No. II-67 Test Report No. 47879-02 DATA SHEET CPKL Customer WYI.E LABORATORIES ---- Specimen Cabl e Part No. Various Amb. Temp. Job No 47879-01 Spec. W TP 47879-01 Photo Report No. 47879-02 Para. 3.3.5 Test Med. Start Date No See Bel ow S/N Specimen Temp GSI Test Titie OVERCURRENT TEST Continued

15. Il 16. Post-Test Readin s Ta r ge t Ca bl es:

Voltage: Current: /. O 8 A" Fault Cable . Time te Open Circuit: rrr / Mcmn M XIV Time to Ignition: Time t;o Stable Tem .: Ak)f g8g4.~84~

               'm      T          R   ord d.      /~+DE                  7 Adjacent Cables:

Current: Maximum Temp. Recorded: g gag Tested By Date:~~M~ Witness Date: oticeof Sheet No. of nomaiy W~F Approved Wyle Farm WH OteA Reu. AprR '84

Page No. II-6& Test Report No. 47879-02 DATA'HEET CPEL Customer WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. 4 787 9 7-Spec. Para. S/N W TP 47 3.2.4.1 Photo Test Med. Specimen Temp. Y s Air ....,;~e No GSI FUNCTIONAL TEST Test Title SCREENING TEST NO. Insulation Resistance Test Acce tance Criteria: Measured insulation resistance shall be reater than 1 .6xl0 A with 500 VDC applied for 60 seconds . Cable Test Point Reading T. P 16AWG 1 to2' cg.o (O~~ to conduit" 2 to conduit* 'F.o x iD~~ Hi h Potential Test Acc tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to conduit*

         *Shield tied to conduit.

2 g / ~ to conduit* Tested By Date: ~y Date: Notice of Sheet No. of ~ Anomaly Approved -r~-ss Wyre Perm WH eraA. Aov. AAA '84

Page No. III-1 Test Report No. 47879-02 SECTION III CONPIGURATION NUMBER 1 TEST {FREE AIR SEPARATION WITHOUT BARRIERS) 1.0 REQUIREMENTS Acceptance Criteria 1.1.1 Insulation Resistance Test Insulation resistance on all "target cables"* shall be greater than 1.6 x 106 ohms with a potential of 500 VDC applied for 60 seconds. Before testing insulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the Overcurrent Test. '1.1.2 H Potential Test eree shall be no evidence of insulation breakdown or flashover with a potential of 00 YAC applied for one minute. 1.1.3 Cable Continui Test Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 50 VAC before, during, and after the overcurrent test. Cable No. CPBcL Cable Rated Size Conductors Current 16 ANG 1 Tw. Pr. D60-01 L 50 VAC 1A 1 1.4 Toleranees All target cable voltages specified in this procedure shall be maintained within a +3% tolerance. All target cable currents shall be maintained within a +10% tolerance. All fault cable currents shall be maintained within a+3% tolerance. The term "target cable" refers to energized and monitored nonfault cables used in this program. WYLE LABORATORIES Huntsville Facility

Page No. III-2 Test Report No. 47879-02 2.0 PROCEDURES 2.1 Test Specimen Preparation The test specimens were mounted to the unistrut frame assembly as shown in Figure 1 of Section VI. This apparatus was assembled to the indicated dimensions by Wyle technicians using materials supplied by CPttt:L. The following guidelines were observed with regard to the materials and construction of this assembly:

1. The faulted cable was a Triplex 350 MCM cable from CPRL stock.
2. The ends of the faulted cable from their termination at the copper bus bar to the edge of the unistrut frame were wrapped with a single layer of HAVEG SILTEMP WT-65 covered with a single layer of 3M No. 69 glass tape. This wrapping was done as a safety measure to ensure that any ignition that might occur was contained to the test area.
3. The horizontally separated target cable was a single pair 16 AWG cable from CPA:L stock. This cable shall be mounted such that the cable was 6 inches horizontally away from the faulted cable.
4. Photographs were taken of the test setup.
5. A 1/2-inch VHS recording was taken of the Overcurrent Test encompassing entire application of the test current.

2.2 Instrumentation Setup 2.2.1 Therm oco le Locations A total of 18 Type "K" thermocouples were utilized for these tests. These thermocouples were mounted as described below: Channel No. Location 1-8 Mounted to the jacket of the fault cable. These thermocouples were spaced approximately 6 inches apar t. 9@10 Mounted to the conductor of the fault cable at the two series connections. These thermocouples were mounted by prying back the fault cable insulation at the series connection points and placing the thermocouple in the strands of the fault cable conductor. 11"18 Mounted to the jacket on the horizontally separated target cable. These thermocouples were mounted approximately 6 inches apart and even with the fault cable thermocouples. These thermocouples were monitored using a Fluke Datalogger feeding a high-speed printe The datalogger was operated at its maximum rate throughout the Overcurrent Test. D from these thermocouples has been plotted versus time and is contained in Appendix I of t. section. WYLE LABORATORIES Huntsville Faclllty

Page No. III-3 Test Report No. 47879-02 PROCEDURES (Continued) 2.2 Instrumentation Setup (Continued) II I 2.2.2 'lectrical Monitor The voltage and current of the target cable and the fault cable current were continuously monitored with an oscillograph recorder. The oscillograph was operated at the 0.1-inch per minute rate throughout the Overcurrent Test. The oscillograph channels were as specified in the following table: Channel No. Si Location Current Tw. Pr. 16 AWG Voltage Tw. Pr. 16 AWG Current Fault Cable 4-16 Skipped N/A

 ;A digital multimeter was utilized to measure voltage and current of the'target cable prior
 'to, during, and after the Overcurrent Test. This data was recorded to provide accurate evidence of the specimen's capability to conduct rated current at 50 VAC throughout the vercurrent Test and is presented in Appendix I of this section.
    .3         BaseIine Functional Tests The baseline functional tests consisted of Insulation Resistance and High Potential

- measurements on each of the target cable. These tests were performed as described below: t 2.3.1 Insulation Resistance Test

1. All power and instrumentation leads were disconnected from the target cable.
2. The shield to conduit resistance was measured with a digital multimeter.
3. Using a megohmmeter, a potential of 500 VDC was applied and the minimum insulation resistance indicated after a period of 60 seconds was recorded between the following test points:

Phase-to-Phase Phase-to-Ground* 1 to 2 1 to shield 2 to shield

  • Shield tied to ground.

For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10~ ohms. WYLE LABORATORIES Huntsville Facility

Page No. III-4 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.3 Baseline Functional Tests (Continued) 2.3.2 H Potential Test

1. Using a Hi-Pot Test Set, a potential of 1600 VAC was applied from each conductor to ground and between conductors on the multiconductor cable and the leakage current was recorded after a period of one minute.

Phase-to-Phase Phase-to-Ground* lto2 1 to shield* 2 to shield

  • Shield tied to ground.
2. Power and instrumentation leads were reconnected to the target cable.

For all performances of this test, the measured values were compared to the acceptance .criteria, Paragraph 2.1.2, i.e., there shall be no evidence of insulation breakdown or flashover. Overcurrent Test The Overcurrent Test was conducted in. two sequential phases with no intentional time delay .between phases. The first phase consisted of powering the fault cable with rated current and increasing this current until temperatures of 90oC +5oC were indicated for 15 minutes on the fault cable conductor. The second phase consisted of energizing the fault cable with the test current until the cable open-circuited. The target cable conducted rated current at 50 VAC thioughout the Overcurrent Test. The Overcurrent Test was conducted using the following procedure:

1. The Triplex 350 MCM fault cable was connected to the copper bus bars per Figures 4 and 7 of Section VI.
2. A Twisted Pair 16 AWG target cable was installed per Figure III-1.
3. The Twisted Pair 16 AWG target cable were connected to the instrumentation and power supplies of Figure 11 of Section VI.
4. The Twisted Pair,16 AWG target cable was energized with 1 ampere at 50 VAC.
5. The fault cable was energized with 350 amperes per phase=(rated current) from the Multi-Amp Test Set.

WYLE LABORATORIES Huntsville Facility

Page No. III-5 Test Report No. 47879-02 PROCEDURES (Continued) 2.4 Overcurrent Test (Continued)

6. Target cable voltage and current and the fault cable current were recorded.
7. The fault cable current was slowly increased until thermocouple Channels 9 and/or 10 indicated 90 C +5oC conductor temperature.
8. The conductor temperature was maintained at 90oC +5oC for 15 minutes.
9. The fault cable current and conductor temperature were recorded.
10. The Multi-Amp Test Set output was increased to 4200 amperes (test current).
11. Target cable voltage and current and the fault cable current were recorded.
12. The fault cable was allowed to conduct 4200 amperes until the cable open-circuited.

13 ~ Time to ignition and open-circuit, and maximum fault cable temperature were recorded.

14. Target cable voltage and current were recorded.
15. The target cable and the Multi-Amp Test Set were de-energized.
16. Photographs were taken of the post-test conditions.

'-'!'-IFor all performances of this test, the observed target cable operation was compared to the acceptance criteria, Paragraph 2.1.3, i.e., it maintained continuity of power. 2.5 Post-Overcurrent Test Punctional Test The functional tests of Paragraph 3.4.4 were repeated as soon as the smoke cleared in the test chamber. In addition, the target cable jacket temperature was recorded. WYLE LABORATORIES Huntsville Facility

Page No. III-6 Test Report No. 47879-02 3.0 RESULTS The Configuration Number 1 Test was performed per Paragraph 2.0 and successfuQy met the Acceptance Criteria of Paragraph 1.0. The 4200 ampere fault current was applied for 148.29 seconds until the Triplex 350 MCM fault cable open-circuited. The fault cable ignited after 105 seconds and burned all of the available insulation in approximately 7 minutes. The fault cable fire was approximately 2 feet high and 6 to 8 inches wide. The maximum observed fault cable temperature was 1489.6 F The faulted cable moved toward the target cable when the 4200 ampere test current was initially applied. This movement reduced the free air gap to approximately 2 inches and the test was terminated at approximately 20 seconds at the customer's request. The fault cable was then taped in place with 2-inch strips of 3M No. 69 glass tape applied every 12 inches and the cable temperatures allowed to cool to approximately 250 F with 510 amperes on the cable. At this point, the 4200 amperes was reapplied until the cable open-circuited. The Twisted Pair 16 AWG target cable, mounted 6 inches horizontally from the fault cable, maintained its electrical integrity and conducted 1 ampere at 50 VAC through the Overcurrent Test and to pass the Post-Overcurrent Test Functional Tests. However, the edges of the flames from the fault cable did reach the target cable and the jacket was visibly scortched in a 36-inch section of the cable (see Photograph III-5). It did not appear that the target cable jacket actually ignited during the test and damage was limited to the jacket. Although the cable met the established test acceptance criteria, it was judged the CPttt:L Technical Representative that the 6-inch separation was not adequate phy independence between free air power cables, and a free air separation of 12 inches was evaluated in Configuration Number 3, Test 3. Although the target cable jacket was damaged during this test, these results can be used to support a separation distance of 6 inches in free air from a faulted control-type cable. This conclusion is acceptable because:

1. None of the control-type cables ignited during the Control Cable Screening Tests (see Section I) and the radiated heat was insufficient to adversely affect cables located 1 inch above the faulted cable.
2. The control-type cable has less insulation available for combustion. Thus, should a control-type cable ignite as the power-type cable ignited, the flame size would be smaller.
3. The energy, dissipated as heat, in a worst case electrical fault for a control-type cable is considerably less than the energy available in a worst case electrical fault for a power-type cable (180 amperes versus 4200 amperes).

Appendix I contains the following data from this test: 1) Figure IH-1 which illustrates the test setup; 2) Photographs III-1 through lII-6 which show the pre-test and post-test conditions; 3) A narrative of this test; 4) A plot of temperatures versus time; and,

5) Data Sheets containing Baseline Functional Test, Overcurrent Test and Post-Overcurrent Test data.

WYLE LABORATORIES Huntsville Facility

Page No. III-7 Test Report No. 47879-02 APPENDIX I CONFIGURATION NUMBER 1 TEST. DATA WYLE LABORATORIES Huntsville Facility

Page No. III-8 Test Report No. 47879-02 LAST 6 INCHES OF FAULT CABLE TO BE WRAPPED WITH WT-65/3M 69 12" UNI STRUT

                                                            'UPPORTS,.

WCC SUPPORT T, . FAULT CABL UNI STRUT WITH CERA I TIE, CORDS..., TW. PR; TYPE "K" THERMO-16 AWG, " ~COUPL'ES TARGET MOUNTED 7 2 IL ~

                                  "'ABL'E    "                          , ...,..., EYERY..1.2",,

4" x 3/8" COPPER BUS BAR

                                                                                           -  jo  !

4 II 16" 12 On 6 "~l 2 I COPPER'"'-"-- BUS BARS

                                                                                               '      H FIGURE I I I-1: CONFIGURATION NO.        1 TEST SETUP

Page No. III-9 Test Report No. 47879-02 O. j 9 j'e VVV PHOTOGRAPH NO. III-1 OVERALL VIEW OF TEST SETUP FOR THE CONFIGURATION NUMBER 1 TEST lL VI,' PHOTOGRAPH NO. III-2 CLOSEUP VIEW SHOWING 6-INCH HORIZONTALSEPARATION BETWEEN TRIPLEX 350 MCM FAULT CABLE AND TWISTED PAIR 16 AWG TARGET CABLE

Page No. IH-10 Test Report No. 47879-02 V 1 t I I PHOTOGRAPH NO. III-3 OVERALL VIEW OF POST-TEST CONDlTIONS PHOTOGRAPH NO. Illa'LOSEUP FRONT VIEW SHOWING LOCATION OF FAULT CABLE OPEN CIRCUIT

Page No. HI-11 Test Report No. 47879-02

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                                                                                   ~

io IV 1 I P l 0. t ~ PHOTOGRAPH NO. III'IEW OF PIECE OF FAULT CABLE CONDUCTOR, WHICH MELTED AND FELL OFF THE CABLE WHEN IT OPENWIRCUITED

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Page No. III-13 Test Report No. 4Z8Z9-02

                           ,.CONFIGDEIATIOM 41, TEST APPROXIMATE   APPROXIMATE     TEMPERATURE TEST TIME      JACKET         CONDUCTOR                            OBSERVATION 76 F             76 P                Energized fault  cable with 350A 5     min      82 F             82 F                Energized fault  cable with 351A 10     min       87 F             87 F                Energized fault  cable with 366A 20     min       96oP             96 F                Energized fault cable with 365A 30    min      102 P            102 F                 Energized fault cable with 380A 46.7  min'5 113 F            113 F                 Energized fault cable wtih 395A min      119 F            123 F                 Energized fault cable with 410A 65'in          120 F           131 F                 Energized fault cable with 425A min      123 F           135 F                 Energized fault cable with 440A 80    min      130 F           140 F                 Energized fault cable with 455A 90    min    '37    F          149 F                 Energized fault cable with 470A 100    min      141 F           155 F                 Energized fault cable with 485A 110    min      150 F           163 F                 Energized fault cble with 500A 133.3 min       155 F           175 F                 Energized fault cable with 505A 145.8 min       162 F           181 F                 Energized fault cable with 510A 173.6 min       240 F           256 P                 Energized fault cable with 4200A 175.4 min       950 F           950 F                 Ignition of fault cable jacket 175.8 min       1100 F         1066.1      P           Peak recorded conductor temperature 176.1 min       1350 F           991 F                 Open  circuit indicated by multi-amp test set 176.9 min      1489.6 F          960 F                 Peak recorded  jacket temperature
    .4 min     1280 F           840 F                 Fire out WYLE LABORATORIES Huntsvllte Facility

Page No. 111-14 Test Repot t No. 47879-02 DATA SHEET Customer L WYLE LABORATORIES Specimen Ca bl es part No Various Amb. Temp. Job No. Spec. W TP 47 7 -01 Photo Yes para 3.2.4 1 Test Med. Air Start Date S/N Specimen Temp. No Test Title FUNCTIONAL TEST QOA3 RGZC. pit frOAJ X 755~/ Insulation Resistance Test Acceptance Criteria: treasured insulation resistance shall be reater than 1.6x10 A with 500 VOC applied for 60 seconds. 6 Cabl e Test Point Reading Tw. Pr. 16 AWG 1 to 2 1 to conduit* 2 to condui t* Hi h Potential Test Acce tance Criteria: There shall be no evidence of insulation breakdown or flashover with a potential of 1600 VAC applied for 60 seconds. Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to conduit* / du+ 2 to conduit*

          *Shield tied to conduit.

Tested By Witness Date: Notice of Sheet No. oI Anomaly Approved F-Pr-rs Ivyle Form vlH 61IA, Rev, ApR '3e

Page No. 111-15 r - r Test Report No. 47879-02 DATA SHEET Customer Ci SL WYLE LABORATORIES Specimen Part No. Various Amb. Temp. Job No 47879-01 Spec. D Photo Para. 3.3.5 Test Med. Start Date No S/N Jol GSI Test Title V CURR NT T T CAD/-/GQgi9VC4 g 7857 L Fault Cable Size: Tar et Cable: m. Pi2. l4 No. Conductors: ~1 p~g

9. InitiaI readings with current applied.

Tar et Cable Fault Cable Current. 3SD Current: g.99' Conductor Temp.:

11. Readings at 90 +5'C conductor temperature.

Tar et Cable Faul t Cable Voltage:

                            ~gD. 4  + VA<

J. 0 P Current: +/ 0 Conductor Temp.: 8'urrent:

12. Readings with fault current applied.

Target Cable Fault Cable Volta e: 5V. &Du'4+ Current: fg00 A

           ~         ~

D ND A Conductor Temp.: 40 Wyl~ Form Wrf 5fiA, Rav. APR'84 Tested By Witness Sheet No. Approved Date: Date: of ~ z7-d"4

                                                                                                                    ->7NW

Page iVo. 111-16 Test Report No. 47879-02 DATA SHEET Customer CP8L WYLE LABORATORIES Specimen C le Part No. Various Amb. Temp. 47879 01 Spec. WTP 77-1 photo Yes Report No. 47879-O2 Para. 3.3.5 Test Med. Start Date No S/N GSI Test Title OVERCURRENT TEST Continued

15. 5 16. Post-Test Readin s Target Cables:

Voltage: +0, jggpQ Current: Fault Cable: Time to Open Circuit: /P$ Pg ~~ goo A Time to Ignition: c.'ime to Stable Temp.: oi C/C cF m m r d. Tested By Date: Witness Date:~-~ -~~ Notice of Sheet No. of Anomaly Approved Wyle Forn WH 014A. Rem. APA '84

Page No. 111-17 Test Report No. 47879-02 DATA SHEET CP&L er - WYLE LASORATORIES Specimen Cables Part No. Various Amb. Temp. Job No Spec. WLTP 47 7 -01 Photo 'eport No. 47879-02. Para. ~.2,4.1 Test Med Air Start Date S/N Specimen Temp. GSI No Test Title FUNCTIONAL TEST QouPg Cubt, IFCgJ 2 7@7 Insulation Resistance Test Acceptance Criteria: Measured insulation resistance shall be reater than 1.6xl0 & with 500 VDC applied for 60 seconds. 6 Cabl e Test Point Reading

        .'Tw. Pr . 16          AWG                   1  to2                                    .o x/o~     ~

1 to conduit* .0 i0 2, to conduit* 4 05/D

       '"'Hi h     Potential Test Acce tance       Criteria:    There shall be no evidence     of insulation breakdown or flashover with    a  potential of 1600 VAC applied for 60 seconds.

Cable Test Point Reading Tw. Pr. 16 AWG 1 to2 1 to conduit* 2 to conduit*

         *Shield tied to conduit.

Tested ate:l~ Witness I llr Date + Z7 Notice of SheetN . of Anomaly Approved Wyre FOrm Wr4 814A, Aev. APA '44

Page No. ill-18 Test Report No. 47879-02 This. Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Facility

Page No. IV-1 Test Report No. 47879-02 SECTION IV CONFIGURATION NUMBER 2 TESTS (CONDUIT-T~ONDUITAND CABLE IN PREE AIR SEPARATION TESTS) 1.0 REQUIREMENTS 1J. Acceptance Criteria 1.1.1 Insulation Resistance Test Insulation resistance on all "target cables"* shall be-greater than 1.6 x 106 ohms with a potential of 500 VDC applied for 60 seconds. Before testing insulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the .Overcurrent Test. 1.1.2 H Potential Test e shan be no evidence of insulation breakdown or flashover with a potential, of VAC applied for one minute. Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 480 YAC (120 VAC for control cables) before, during, and after the overcurrent test. Cable No. CPRL Cable Rated Size Conductors LD. No. Voltage Current 16 AWG 2/C D50-11 C 120 VAC 10A 10 AWG 3-1/C D25-01 P 480 VAC 40A Tolerance s All target cable voltages specified in this procedure shall be maintained within a +3% tolerance. AH target cable currents shall be maintained within a +10% tolerance. All fault cable currents shall be maintained within a+3% tolerance. The term "target cable" refers to energized and monitored nonfault cables used in this program. WYLE LABbRATbRIES Huntsville Facility

Page No. IV-2 Test Report No. 47879-02 2.0 PROCEDURES 2.1 Test Specimen Preparation The test specimens were mounted into the test assembly of Figure 1 of Section VI. This apparatus was manufactured to the indicated dimensions by Wyle technicians using materials supplied by CPdcL. The following guidelines were observed with regard to the materials and construction of the assembly:

1. The faulted cable was a Triplex 350 MCM cable from CPRL stock and mounted in Location 3 of Figure IV-1 or IV-3 for both tests.
2. The ends of the faulted cable were wrapped from their termination on the copper bus bar to the edge of the test assembly. This wrap consisted of a single layer of HAVEG SILTEMP WT-65 covered with a single layer of 3M No. 69 glass tape.

This wrapping was done-as a safety measure to ensure that any ignition that might occur was contained to the cable tray test area.

3. A 3-1/C 10 AWG target cable from CPRL stock was mounted in Location 2 of Figure IV-1 or IV-3 for both tests.
4. A 2/C 16 AWG target control cable from CPRL stock was mounted in Location 1 of Figure IV-1 or IV-3 for both tests.
5. The target cables were wrapped with HAVEG SILTEMP WT-65 covered with No. 69 glass tape as they exited the conduit test area in order to prevent damage to them from Games outside the test area.
6. The conduits and the free air cable were orientated as described below:

Test No. Location I Location 2 Location 3 1 Flexible Conduit Rigid Conduit Free Air Cable 2 = Rigid Conduit Free Air Cable Flexible Conduit

7. The conduits and cable were mounted within 6 inches of each other for Test 1 and within 1 inch of each other for Test 2.
8. Photographs were taken of the test setup.
9. A 1/2-inch VHS recording was taken of the Overcurrent Test encompassing the entire application of the test current.

WYLE LABORATORIES Huntsville Facility

Page No. IV-3 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.2 Instrumentation Setup 2.2.1 Thermoco le Locations A total of 24 Type "IV'hermocouples were utilized for these tests; These thermocouples were mounted as described below: Channel No. Location 1-8 Mounted to the jacket on the fault cable. These thermocouples were mounted approximately 12 inches apart. 9 R 10 Mounted to the conductor of the fault cables at the two series connections., These thermocouples were mounted by prying the insulation up at the series connection point and then mounting the thermocouples between the strands of the fault cable conductor. 11-18 Mounted to the jacket of the target cable in Location 1. These ther mocouples were mounted approximately 12 inches apart. 19-26 Mounted to the jacket of the target cable in L'ocation 2. These thermocouples were mounted approximately 12 inches apart. 27k 28 Mounted to the outside of the flexible conduit on the side towards the rigid conduit. 29 R 30 Mounted to the outside of the rigid conduit on the side towards the flexible conduit. These thermocouples were monitored using a Fluke Datalogger feeding a high-speed printer. The datalogger was operated at its maximum rate throughout the Overcurrent Test. The temperature data has been plotted versus time and is presented in Appendices I and II of this section. WYLE LABORATORIES Huntsville Facility

Page No. IV-4. Test Report No. 47879-02 2.0 (Continued) 2.2'.2.2'ROCEDURES Instrumentation Setup (Continued) Electrical Monitor All phase-to-phase voltages and phase currents of the target cables and the fault cable current were fed into oscillograph recorders. The oscillograph was operated at the 0.1-inch per minute rate throughout the overcurrent test. The oscillograph channels were as specified in the following table. Channel No. Siinal Cable Current 2/C 16 AWG Target Cable Voltage 2/C 16 AWG Target Cable Current-Phase A 3-1/C 10 AWG Target Cable Current-Phase B 3-1/C 10 AWG Target Cable 5 Current-Phase C 3-1/C 10 A WG Target Cable 6 Voltage A-B 3-1/C 10 AWG Target Cable 7 Voltage AM 3-1/C 10 AWG Target Cable 8 Voltage B-C 3-1/C 10 AWG Target Cable 9 le: 10 Skipped N/A 11 Current Pault Cable 12-16 Skipped A digital multimeter was utilized to measure voltage and current of the target cable prior to, during, and after the Overcurrent Test. This data was recorded to provide accurate evidence of the specimen's capability to conduct rated current at 480 VAC (120 VAC for control cables) throughout the Overcurrent Test and is presented in Appendices I and II of this section. 2.3 Baseline Punctional Tests The baseline func tional tests consisted of Insulation Resistance and High Potential measurements on each of the target cables. These tests were performed as described below: 2.3 J. Insulation Resistance Test

1. All power and instrumentation leads were disconnected from the target cables.
2. Using a megohmmeter, a potential of 500 VDC was applied and the minimum insulation resistance indicated after a period of 60 seconds was record between the following test points:

WYLE LABORATORIES Huntsville Facility

Page No. IV-5 Test Report No. 47879-02 PROCEDURES (Continued) 2;3 Baseline Functional Tests (Continued) 2.3.1 Insulation Resistance Test (Continued) Tar et Power. Cable: Phase-to-Phase Phase-to-Ground lto2 1 to unistrut or conduit lto3 2 to unistrut or conduit 2to3 3 to unistrut or conduit Tar et Control Cable: Phase-to-Phase Phase-to-Ground 1to2 1 to conduit or unistrut 2 to conduit or unistrut Forkball performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 ohms. Hi Potential Test

1. Using a Hi-Pot Test Set, a potential of 2200 VAC was applied and the leakage current observed after a period of 60 seconds was recorded between the following test points:

Tar et Power Cable: Phase-to-Phase Phase-to-Ground 1to2 1 to unistrut or conduit 1to3 2 to unistrut or conduit 2to3 3 to unistrut or conduit Tar et Control Cable: Phase-to-Phase Phase-to-Ground lto2 1 to conduit or unistrut 2 to conduit or unistrut

2. All power and instrumentation leads were reconnected.

r For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.2, i.e., there was no evidence of insulation breakdown or flashover. WYLE LABORATORIES Huntsville Facility

Page No. IV-6 Test Report No. 47879-02 PROCEDURES (Coatiaued) 2.'4 Overcurreat Test The Overcurrent Test was conducted in two sequential phases with no intentional time delay between phases. The first phase consisted of powering the fault 'cable with rated current and increasing this current until temperatures of 90oC +5oC were indicated for 15 minutes on the fault cable conductor. The second phase consisted of energizing the fault cable with the test current until the cable open-circuited. The target cable conducted rated current at 480 VAC (power cables) or 120 VAC (control cables) throughout the Overcurrent Test. The Overcurrent Test was conducted using the following procedure:

1. The Triplex 350 MCM fault cable was connected to the copper bus bars per Figure IV-1 or IV-3.
2. A 2/C 16 AWG target cable was installed per Figure IV-1 or IV-3.
3. A 3-1/C 10 AWG target cable was installed per Figure IV-1 or IV-3.
4. The 3-1/C 10 AWG target cable was connected to the instrumentation and power supplies of Figure 9 of Section YI.
5. The 2/C 16 AWG target cable was connected to the instrumentation and po supplies of Figure 10 of Section VI.
6. The 3-1/C 10 AWG target cable was energized'ith 40 ampere at 480 YAC.
7. The 2/C 16 AWG target cable was energized with 10 ampere at.120 VAC.
8. The fault cable was energized with 350 amperes per phase (rated current) from the Multi-Amp Test Set.
9. Target cable voltages and currents and the fault cables current were recorded.
10. Fault cable current was slowly increased until thermocouple Channels 9 and/or 10 indicated a 90oC +5oC conductor temperature.
11. The conductor temperature was maintained at 90 C +5 C for 15 minutes.
12. Fault cable current and conductor temperature were recorded.
13. The Multi-Amp Test Set output was increased to 4200 amperes (test current).
14. Target cable voltages, currents and the fault cable current were recorded.

WYLE LASORATORIES Huntsville Facility

Page No. IV-7 Test Report No. 47879-02 PROCEDURES (Continued) 2.4 Overcurrent Test (Continued)

15. The fault cable was allowed to conduct 4200 amperes until the cable open-circuited.
16. Time to ignition and open-circuit, and maximum fault cable temperature were recorded.
17. Target cable voltages and currents were recorded.
18. The target cables and the Multi-Amp Test Set were de-energized.
19. Photographs were taken of the post-test conditions.

Por all performances of this test, the observed target cable operation was compared to the acceptance criteria, Paragraph 2.1.3, i.e., it maintained continuity of power. 2."5 Post Overcurrent Test Punctional Test'he functional tests of Paragraph 3.5.4 were repeated as soon as the smoke cleared in the cchamber. In addition, the target cable jacket. temperature was recorded. WYLE LABORATORIES Huntsville Facility

Page No. IV-8 Test Report No. 47879-02. 3.0 RESULTS 3.1 Results of Test No. 1 Configuration Number 2, Test No. 1, with a Triplex 350 MCM fault cable in free air, a 2/C 16 AWG target cable inside a 1-inch flexible steel conduit, and a 3-'1/C 10 AWG cable inside a 1-inch rigid steel conduit, was conducted in accordance with Paragraph 2.0 and successfully met the Acceptance Criteria of Paragraph 1.0. The 4200 ampere fault current was applied, until the fault cable open-circuited in 167.57 seconds. The fault cable ignited after 126 seconds and burned all of the available insulation in approximately 7 minutes with flames approximately 18 inches high. The peak temperature of 1312.3 F was recorded on the fault cable during this test. The 2/C 16 AWG and 3-1/C 10 AWG target cables maintained their electrical integrity and conducted 10 amperes at 120 VAC and 40 amperes at 480 VAC, respectively, throughout the Overcurrent Test. In addition,, the target cables successfuQy completed the Post-Overcurrent Test Functional Tests. The peak temperatures observed on the target cables were: Jacket Conduit Cable Conduit Tem erature 2/C 16 AWG 3-1/C 10 AWG Flexible Conduit Rigid Steel Conduit 751.7oF 490.6oF 777 6oF 719.4oF ---"The exposure to these temperatures did result in physical damage to the cable jackets. The

                                                                                                    ~

3-1/C 10 AWG target cable jacket deformed and was slightly charred in several areas (see Photograph IV-7 in Appendix I). There was no area where the jacket integrity was ruptured on this cable. The 2/C 16 AWG cable suffered an unusual phenomenon, due to its exposure to high temperatures. The outer jacket swelled and became very spongy, which protected the individual conductors by separating them from the conduit walls (see Photographs IV-8 and IV-9 in Appendix I). The flames from the fault cable engulfed both conduits and the outer coating of the Anaconda Sealtite Type E.F.P. flexible conduit melted and ignited. These flames were approximately 1 inch high and self-extinguished once the fault cable flames deer eased. Although both target cables successfully met the Acceptance Criteria, this separation distance will not be permitted, without interposing barriers, in design at the Shearon Harris Nuclear Power Plant. The results of this test were judged to be acceptable by the CPA L Technical Representative. Appendix I contains the following data from this test: 1) Figure IV-1 which Qlustrates the test setup; 2) Photographs IV-1 through IV-8 which show the pre-test and post-test conditions; 3) A narrative of this test; 4) A plot of temperatures versus time; and,

5) Data Sheets which contain Baseline Functional Test, Overcurrent Test, and Po Test Functional Test data. 'vercurrent WYLE LABORATORIES Huntsville Facility

Page No. IV-9 Test'eport No. 47879-02 RESULTS (Continued) 3.2 Results of Test No. 2't I Configuration Number 2, Test No. 2, with a Triplex 350 MCM fault cable inside a 3-inch flexible steel conduit, a 2/C 16 AWG target cable inside a 1-inch rigid steel conduit, and a 3-1/C 10 AWG target cable in free air was conducted in accordance with Paragraph 2.0 and successfully met the Acceptance Criteria of Paragraph 1.0. The 4200 ampere fault current was applied until the fault cable open-circuited in 231.63 seconds. The fault cable or the coating on the flexible steel conduit did not ignite during this test. A peak temperature of 1593 9 F was recorded on the fault cable. The 2/C 16 AWG and 3-1/C 10 AWG target cables maintained their electrical integrity and conducted 10 amperes at 120 VAC and 40 amperes at 480 VAC, respectively, throughout the Overcurrent Test. In addition,. the target cables successfully completed the Post-Overcurrent Test Functional Tests. The peak temperatures observed on the target cables were:. Jacket Conduit Cable Conduit Tem erature Tem rature 2/C 16 AWG Rigid Steel Conduit 131.6oF 141.0oF 3-1/C 10 AWG Free Air 169.8oF N/A There=was no visual evidence of degradation to the jackets of either target cable afater this test.'ppendix II contains the following data from this test: 1) Figure IV-3 which illustrates the test setup; 2) Photograohs IV-9 through IV-13 which show the pre-test and post-test conditions; 3) A narrative of the Overcurrent Test; 4) A plot of temperatures versus time; and, 5) Data Sheets which contain Baseline Functional Test, Overcurrent Test, and Post-Overcurrent Test Functional Test data. WYLE LABORATORIES Huntsville Facility

Page No. IV-10 Test Report No. 47879-02 This Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Facility

Page No. IV-11 Test Report No. 47879-02 APPENDIX I CONFIGURATION NUMBER 2, TEST NO. 1 DATA WYLE LABOAATOAIES Huntsville Facility

Page No. IV-12 Test Report No. 47879-02 UNIST RUT SUPPORTS FLEX CONDUIT 1 INCH FLEXIBLE INCH RIGID STEEL CONDUIT STEEL CONDUIT FAULT w/T.P. 16 AMG w/3-1/C 10 AWG CABLE 96 II RIGID CONDUIT T RIPLEX 350 T 6 II 3 2 MCM FAULT CABLE FAULT CABLE TIED WITH CERAMIC CORDS EVERY 12 INCHE 19" II 3O SIDE VIEW TOP VIEW FIGURE IV-I: CONFIGURATION 2 TEST 1 TEST SETUP

Page No. IV-13 Test Report No. 4787S-02 I

                                                       )I)

I 0 y V l I PHOTOGRAPH NO. IV-1 OVERALL VIEW OF TEST SETUP FOR THE CONFIGURATION NUMBER 2, TEST NO. 1 h 4 il a PHOTOGRAPH NO. IV-2 SIDE VIEW OF TEST SETUP SHOWING 6-INCH VERTICALSEPARA'QON FROM THE FAULT CABLE TO THE CONDUITS

Page No. IV-14 Test Report No. 47879-02 PHOTOGRAPH NO. IV-3 PHOTOGRAPH NO. IV& OVERALL VIEW OF POST-TEST CONDITIONS CLOSEUP VIEW OF LOCATION OF CONFIGURATION NUMBER 2, TEST NO. 1 OPEN CIRCUIT ON THE FAULT CABLE n)) $ $ 'l wI k)

                                                                              ,5 PHOTOGRAPH NO. IV-5 TOP VIEW OF FLEXIBLESTEEL AND RIGID STEEL CONDUITS AFTER OVERCURRENT TESF

Page No. IV-15 Test Report No. 4Z879-02 PHOTOGRAPH NO. IV% POST-TEST CONDITION OF 3-1/C 10 AWG TARGET CABLE REMOVED FROM THE 1-INCH RIGID STEEL CONDUIT (Note Deformation of Insulation in Bottom of Photograph) PHOTOGRAPH NO. IV-Z POST-TEST CONDITION OF 2/C 16 AWG TARGET CABLE REMOVED FROM THE 1-INCH FLEXIBLE STEEL CONDUIT cP'HOTOGRAPH NO. IV-8 CLOSEUP VIEW OF THE 2/C 16 AWG TARGET CABLE SHOWING THE SWOLLEN AND SPONGY OUTER JACKET

Configuration 2 - Test 1  :!

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Page No. IV-17 Test Report No. 47879-02 CONFIGURATION 42 TEST 41 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 81 F 81 F Energized fault cable with 350A 5 min 86 F 86 F Energized fault cable with 400A 10 min 91 P 91 F Energized fault cable with 450A 15 min 101 F 101 F Energized fault cable with 500A 76.7 min 170 F 182 F Energized fault cable with 505A 96.3 min 178 P 191 P Energized fault cable with 4200A 97.6 min 625 P 625 F Light off-gassing 98.2 min 720 F 720 P Heavy off-gassing 98.3 min 755 F 755 P Fault cable jacket rupturing. Ignition of fault cable. 98.8 min 1045 F 1040.2 P Peak recorded conductor temperature 99.1 min 1312.3 F 1020 P Open circuit indicated by multi-amp test set. Peak recorded jacket temperature. 105 min 1150 F 781 P Fire out WYLE LABORATORIES Huntsville Facility

Page No. IV-18 Test Report Ho. 47879-02 DATA SHEET Customer WYLELABORATORIES Cah 1 es Specimen part No. Various Amb. Temp. Job No MLTP 47879-01 Photo ort No>>9-02 Para. Test Med Ai Start Date No S/N Specimen Temp. No GSI Test Title FUNCTIONAL TEST CONFIGURATION 2 TEST NO. J INSULATION RESISTANCE TEST ACCEPTANCE CRITERIA: Measured insulation resistance shall be greater than 1.6 X 10 0 with 5&VDC applied for 60 seconds. TARGET CABLE LOCATION TEST POINT READING 3-1/C 10 AMG I" l f5&~ 1 to 2 a. Z x/uq~

                                                  "AGOr/e       1 to  3
                                     ~c      cAGcC              2 to  3 1 to  GNO*

2 to GND* 3 to GNO* 2/C 16 AWG I /-LE/..o'er r 1 to 2

                                     "+booe    ~<               1 to  GNO*

Cwhl~ 2 to GNO* $3

                                  *Conduit tied to unistrut frame.

Tested By Dat'.WMK Witness Date: Notice of Sheet No. of Anomaly Approved 'Ply ~ Fora 'lYH IliA,Rev, APR '9l

Page No. IV-19 Test Report No. 47879-02 QATA SHEET Customer WYLE LABORATORIES Specimen Cab 1 es Part No Spec. WLTP Various 4787 -01 Amb. Temp. Photo

                                                                'es                  Job No Report No. 47879 02

'ara. Test Med. Start Date + +8 No S/N Specimen Temp. GSI No Test Title FUNCTIONAL TEST CONFIGURATION 2 TEST NO. + HIGH POTENTIAL TEST ACCEPTANCE CRITERIA: There shall be no evidence of insulation breakdown or flashover with a potential of 2200 VAC applied for 60 seconds. TARGET CABLE LOCATION TEST POINT 3-'1/C 10 AWG 1 to2, Q&~ A eu~b~tr 1 to3GNO*'EAOING m7~A 2 to 3 1 to GNO* 2 to IDy~~A 3 to GNO* 1DDDw A 2/C 16 AWG 4" FC&!. &uDW7 gts~A 1 to GNO* 2 to GNO*

                                 *Conduit tied to unistrut frame.

Tested By Witness Sheet No. Approved Date: Date: oi

                                                                                                      ~

'.Vyle FOvm WH 0144. Pev, aPR 'Sl

Page No. IV-20 Test Report No. 47879-02 DATA SHEET Customer CP8L WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. F J 0N 47879 Spec. WLTP 47879-01 Photo Report No. Para. 3.5.5 Test Med. Start Date S/N No Specimen Temp. No GSI OVERCURRENT TEST CONFIGURATION 2 TEST NO. Q

9. READINGS WITH RATED CURRENT ON FAULT CABLE CABLE LOCATION 3-1/C 10 AWG I" ~5 2/C 16 AWG j FLEX tW.+ l0.09 TRIP 350 iICH Q" jg/og)

FAULT CABL CONDUCT T MP A R: BO. 3 Tested By Witness Notice of Sheet No. Anomaly Approved WylO Fo(nl YIH OllA. tv. APR '$4

Page No. IV-21 Test Report No. 47879-02 QATA SHEET Customer CP8L WYLE LABORATORIES

                                                             ., ~v Specimen               Cables Part No.              Various                                                             Job No. 47879 Spec.            WLTP      47879-01                  Photo                                 Report No. 47879-02 Para.                                              Test Med.      Air                     Start Date SIN                    No                            Specimen Temp.

GSI No Test Titie OVERCURRENT TEST CONFIGURATION 2 TEST NO.

12. READINGS AT 90'C + 5'C CONDUCTOR TEMPERATURE VOL'TAGE VAC CURRENT AMPS C T 3-1/C 10 AWG I" ~/g 2/C 16 AWG l95 9.R'RIP 350 MCM (o" &o~
                                  ~0abu<~

MS'AULT CABLE CONDUCTOR TEMPERATURE: 9 Tested By Witness + ~ Sheet No. Approved 'A'v)e Perm YSH 41'. Aev A pR 'se

Page No. IY-22 Test Report No. 47879-02 DATA SHEET Customer CP8rL WYLE LABORATORIES-- Specimen Cables Part No. Various

  • ob No 47879 ..

Spec. WLTP 47879-01 Photo Yes Report No. Para. 3.5.5 Test Med. S/N No Specimen Temp. GSI Test T(t(e OYERCURRENT TEST CONFIGURATION 2 TEST NO. +

14. READINGS WITH fAULT CURRENT ON FAULT CABLE 3-1/C 10 ArrG I '/5 3'$.2- .I +I 2.

C l AWG .9o TRIP 350 MCN (y 18I~Q 300 fAULT CABI.E CONDUCTOR TEMPERATURE: DD. 9 / Tested By D.t.:~'~

                                                                                                    ~~8~

Witness oara: Notice of Sheet No. of Aaamaty Approved 8-z8-8 Vryro Form'/rH o'laA. Rw. Aoh '3a

Page No. IV-23 Test Report No. 47879-02 DATA SHEET Customer CP8iL WYLE LABORATORIES Specimen Cables Part.No Various Amb. Temp. MLTP 47879-01 Yes ort. No 47879-02 Spec Photo Para. 3.5.5 Test Med. Air ,~PIP R SiN iVo Specimen Temp. GSI No OVERCURRENT TEST CONFIGURATION 2 TEST NO.

16. 5 17. REAOINGS AFTER FAULT CABLE OPEiV CIRCUITED VOLTAGE VAC CURRENT AMPS 3-1/C 10 AWG I" R/5 2/C 16 AMG /jf.

TRIP 350 NCiN (y" ge(ou)

                                    &wbLttt5 MAXIMUM FAULT CABLE TEMPERATURE:                  ISIS F TINE      TO OPEN         CIRCUIT:   /$ g g'7 ~c~~2)g rb        +cg>O  Q Tested By                    Date: Z ><~~

Witness Date: ~~MR Sheet No. oI Approved a-za-8s-iVyie Form 'IIH 61iA. Rev, APR "84

Page No. IV-24 Test Report No. 47879-02 DATA SHEET Customer WYLE LABORATORiES-Cables part No. Various Amb. Temp. Job No WLTP 47879-01 photo Yes Report No Air Para. S/N No Test Med

                                                             . ~*- /
                                                               /b >cud.

o+ Start Date GSI Test Title i- Dt/ re& le r FUNCT IONAL TEST CONFIGURATION 2 TEST NO. INSULATION RESISTANCE TEST ACCEPTANCE CRITERIA: Measured. insulation resistance shall be greater than 1.6 X 10 Q with SOOVDC applied for 60 seconds. TARGET CABLE LOCATION TEST PO INT READING 3-1/C 10 AWG (" gg/j) kg~ 1 to 2 .Oy. (O~m CoeiXltT' "AkauE 1 to 3 a.r /o8m Qua- Ca&/e 2 to 3 /08M 1 to GND* S x/os 2 to GND* 4 Og/D~~ 3 to GND* I //x/0~M 2/C 16 AWG . Cb~bu(r 1 to 2 p.pg/0 fn ~< ~cZ 484P 1 to GND* I. 0 x/o "~ 2 to GND* p4 </O "m

                      *Conduit tied to unistrut frame.

Tested 8 D.t..l'-ZZZ-.8< Witness ' Notice of l Sheet No. of Z Anomaly Approved g-z8-8

Page No. IV-25 Test Report No. 47879-02 DATA SHEET Customer WYLE LABORATORIES specimen Cab 1 es Various Amb. Temp. ~ + Job No.- Spec WLTP 47879-01 Photo Yes Report No. 47B79 0 Para. 3.5,4 Test Med. >> r Start Date S/N No Specimen Temp. / GSI No

                  ~M- Qj+PQtbQg=yUI          7Eg   FUNCTIONAL TEST CONFIGURATION 2 TEST NO.      4 HIGH POTENTIAL TEST ACCEPTANCE CRITERIA:       There shall be no evidence     of insulation breakdown or flashover with    a  potential of 2200 VAC applied for 60 seconds.

TARGET CABLE LOCATION TEST POINT READING 3-1/C 10 AMG " 8 /DM<6R. to 2 Q)(ok' ( 1 to3 2 to 3 1 to GNO* 2 to GND* 3 to GNO* 2/C 16 AMG I" ~ p~pg(( 1 1 to2 to GNO* 2 to GNO*

                               *Conduit tied to unistrut frame.

Tested By

                                                                            ~a tice of
.oomaIy Sheet No.

Approved or~ Daia:(t 8-z8-8s-

                                                                                                        ~<<<

Wyie Porn Wv 61IA, Rey. APR 'S4

Page No. IV-26 Test Report No. 47879-02 This Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Facility

Page No. IV-27 Test Report No. 47879-02 APPENDIX II CONFIGURATION NUMBER 2, TEST NO..2 "DATA WYLE LABORATORIES Huntsville Facility

Page No. IV-28 Test Report No. 47879-02 UNIST RUT SUPPORTS 1 INCH R/S CONDUIT 3 INCH FLEX 1 INCH RIGID 3-1/C 10 AWG CONDUIT STEEL CONDUIT FREE AIR CABLE FREE AI v/T.P.'16 AWG CABLE 3 INCH FLEX CONDUIT w/TRIPLEX SO MCM FAULT CABLE ll 3O FRONT VIEW TOP VIEW FIGURE IV-3: CONFIGURATION 2 TEST 2 TEST SETUP

Page No. IV-29 Test Report No. 47879-02 PHOTOGRAPH NO. IV-9 PHOTOGRAPH NO. IV-10 SIDE VIEW OF TEST SETUP SHOWING 3-INCH FLEXIBLE COh RATION NUMBER 2, TEST NO. 2 CONDUIT CONTAINING THE TRIPLEX 350 MCM FAULT CAB PHOTOGRAPH NO. IV-11 SIDE VIEW SHOWING 1-INCH SEPARATION FROM FLEXIBLECONDUIT TO RIGID STEEL CONDUIT

Page No. IV-30 Test Report No. 47879-02 E( I

                                    /t 4p PHOTOGRAPH NO. IV-12 OVERALL VIEW OF POST-TESI'ONDITIONS FOR CONFIGURATION NUMBER 2, TEST NO. 2 PHOTOGRAPH NO. IV-13 CLOSEUP VIEW SHOWING MELTED COATING ON THE ANACONDASEALTITE 3-INCH FLEXIBLECONDUIT

i:i

                                                       ~           -

I I Configuration 2 Test 2 Ii IIj I 111 LECENDi Fault Cable Jacket Teetperature (T/CS 1-8) DRAM!t BY1 pault Cable Conductor Tenperature (T/CS 9 6 10) 1'l!ECKED BY-' (5 Target Cable (2/C l6 ANG) Jacket Testperature (T/CS 11-1S) l Target Cable (3-1/C 10 AMC) Jacket Teeperature (T/CS 19-26) ii Teaperature of 3 plex Conduit (T/CS 27 a 28) Teaperature of l" R(gld Steel Condu(t (T/CS 29 a 30) jp ul I }tax. Teep. Recordedi 1593.9 P (T/C 43) at 80.5 st(n Ii i ili At!lb(ent Teapir 78 P

                        '!II                                               Date} Septenber 3. 1985 I

PXCI!E 1V-3 I I

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Page No. IV-32 Test Report No. 47879-02 CONFIGURATION f2 TEST 42 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 81 F 81 F Energized fault cable with 350A 5 min 89 F 89 F Energized fault cable with 400A 10 min 97 F 97 F Energized fault cable with 450A 15 min 107 F 107 F Energized fault cable with 500A 51.7 min 191 F 177 F Energized fault cable with 475A 57.7 min 201 F 185 F Energized fault cable with 450A 65 min 210 F 191 F Energized fault cable with 425A 76.7 min 220 F 199 F Energized fault cable with 4200A 78 min 760 F 1076.5 F Peak recorded conductor temperature 79 min 575 F 910 F Heavy smoke and flex conduit melting 80.5 min 1593.9 F 999 F Open circuit indicated by multi-amp. test set. Peak recorded jacket temperature. WYLE LASORATORIES Huntsville Facility

Page No. IV-33 Test Report No. 47879-02 QATA SHEET Customer WYLE LABORATORIES Cables Specimen part No. Various Amb. Temp. bN 47879 WLTP 47879-01 Photo Re ortNo Para. Test Med. S/N No Test Title 5F/ /U FUNCTIONAL TEST CONFIGURATION 2 TEST NO.

                                                            "   P INSULATION RESISTANCE TEST ACCEPTANCE     CRiTERIA:     Heasured   insulation resistance shall           be  greater than 1.6  X 10   2 with    50 VOC  applied for       60 seconds.

TARGET CABLE LO CAT IOi"i TEST POINT RERDfRG 3-1/C 10 AWG 1 to2 2. 2 x'O 1 to3 >.{' lO -~ 2 io 3 I,(. x Lo't. 1 to GNO* g,.9 lO 2 to GNO* (O 3 to GNO* <.'L X lO 2/C 16 AWG 1 to2 .Ox(c -~ 1 to GiVO* 1. 7. x' 0 2 to GiVO* M iO

                                       *Conduit tied to unistrut frame.

Tested B " ~~~!~e- ~f Date:~~~ L~>~ ! witness

                                                                                         '                      Oate:
                                                                                       ~

otice ot I!-I<C! Sheet No. -' - of c~ nomaly ~o Approved vr ! tp pprrh vite tel 4A, psvAppf 'e4

Page No. IV-34 Test Report No. 47879-02 DATA SHEET Customer WYLE LASORATORIES Specimen Cables P,t N Various Amb. Temp 47879 WLTP 47879 Ol Photo Yes Report No 47879-02 Spec Para. 3.5. 4 Test Med. Ai" No GSI No Test Title AQSa.n.K FUNCTIONAL TEST CONFIGURATION 2 TEST NO. g-HIGH POTENTIAL TEST ACCEPTANCE CRITERIA: There shall be no evidence of insulation breakdown or flashover with a potential of 2200 VAC applied for 60 seconds. TARGET CASLE LOCATION TEST POINT READING 3-1/C 10 AWG 1 to2 >OO r/A 1 to3 2 to 3 ,w o~(A 1 to GNO" /n+ 2 to GNO" Jn 80. 3 to GNO* 't5 a 2/C 16 AWG 1 to2 Ou4 1 to GNO* 'I op 2 to GNO* 'Ioo iA

                                  *Conduit tied to unistrut frame.

Wjr ) 7 r Tested Date: 3~~LE> Witness Date: Notice of Sheet No. of Anomaly ~-zw-8 'JVyti Poem Wh Otic, Rtv, APR 'S4

Page No. IV-35 Test Repot t No. 47879-02 DATA SHEET Customer CPSL WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. 78 /-" Job No. 47879 Spec. WLTP 47879-01 Photo Report No. 47879 02 Para. 3.5.5 Test Med. Air Start Date SIN No Specimen Temp. vA@oud No GSI Test Title 0VERCURRENT TEST CONFIGURATION 2 TEST NO . g cP-

9. READINGS WITH RATED CURRENT ON FAULT CABLE CABLE LOCATION 3-1/C 10 AWG FFX AI 2/C 16 AWG l ~IS TRIP 350 ~C~I 3 Fi.E-.X FAULT CABLE C NDUCT R TiMP AT R Io Tested otice of Sheet No.

Anomaly Apprcved 'yyy!0 ~arm v/H O'I4A, Rei, App'$4

Page No. IV-36 Test Report No. 47879-02 DATA SHEET Customer CP&L WYLE LABORATORIES Specimen Cables Various 0 Part No. Amb. Temp. Job No. Spec. WLTP 47879-01 Photo Report No. 47879-02 Para. Test Med. Air Start Date SIN No GSI No OVERCURRENT TEST CONFIGURATION 2 TEST NO.

12. REAOINGS AT 90'C + 5'C CONDUCTOR TEMPERATURE VOLTAGE VAC CURRENT AMPS 3-1/C 10 AWG 3 2/C 16 AWG TRIP 350 MCM FAULT CABLE CONOUCTOR TEMPERATURE:

Tested By Date:~+ Witness Date: Notice of Sheet No. of Anomaly Approved / $0 '.vying i'arm V/h 5liA, Rov, APR '5s

Page Vio. IV-37 Test Report No. 47879-02 QATA SHEET'ustomer CPSL VItYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. Job No. Spec. MLTP 47879-01 photo Yes Report No. 47879 02 Para. 3.5.5 Test Med. Start Date S/N No Specimen Temp 4'0 S GSI i'lo Test Title OVERCURREiNT TFST CONFIGURATION 2 TEST NO.

14. READINGS MITH FAULT CURREi'IT ON FAULT CABLE 3-1/C 10 AMG 2 C 1 AMG TRIP 350 iviCf4l 4 0'AULT CABLE CONDUCTOR TEMPERATURE:

( Tested By Date:2 nomaly

                                   'IA Witness Sheet No.

Approved l~ ef~ g-.E -89 tfe'ytt etytm AH 6 l AA, ffeV. APR

Fage No. IV-38 Test Report No. 47879-02 QATA SHEE7 CPSL WYLE LABORATORIES Customer Specimen Cables Various Part No. Spec. WLTP 47879-01 Amb. Temp. Photo

                                                        'es                 Job No.

Re ortNo Para. 3.5.5 Test Med. Air Start Date SIN No Specimen Temp. GSI No OVERCURRENT TEST CONFIGURATION 2 TEST NO.

16. Fa 17. READINGS AFTER FAULT CABLE OPEN CIRCUITED VOLTAGE VAC CURRENT AMPS 3-1/C 10 AWG 2/C 16 AWG TRIP 35O MCM MAXIMUM FAULT CABLE TEMPERATURE: /SV.

TIME TO OPEN CIRCUIT: Q/. Q Tested By ~ Date: ~~'J Witness Date: Notice ot Sheet No. ot Anomaly -8c

Page No. IV-39 Test Report No. 47879-02 DATA SHEET Customer NYLE LABORATORIES Specimen Cables

.part No.              Various
  • Job No.

WLTP 47879 01 Spec Fhoto Report No. Para. Test Med. Air Start Date S/N No lu 34@ - l~ / "/- Test Title ' FUNCTIONAL TEST CONFIGURATION 2 TEST RO. ~vt Ii'iSULATION RESISTANCE TEST ACCEPTANCE CRITERIA: Measured insulation resistance shall be grea.er than 1.6 X 10 Q with 500VOC applied for 60 seconds. TARGET CABLE LOCATION TEST POINT READING 3-1/C 10 to2 Ogf

                                                                                      'o' AWG                              1 1 to3                   ~

2 to 3 1O" >a to GND* X I0'l2 2 to GNO* S.3, X fo'OX 3 to GIVD* )6 2/C 16 AWG 1 to2 0 1 to GiVO* 5.0 X'o' 2 to GND* 10'Conduit tied to unistrut frame. Tested By Dat.:~~~ Witness Date: oticeof Sheet No. of nomaly Approved 3w Yl)It Ftvm VIH OTCA, Rtv. APIR 'SA

Page No. IV-40 Test Report No. 47879-02 DATA SHEET Customer V/YLE LABORATORIES Specimen Cab 1 es Various Amb. Temp. Job No. Spec WLTP 4787 O'I Photo Report No. 47879 02 Para Test Med. Air Start Date SIN GSI No /0 i4~ -/~go~ Test Title s FUNCTIONAL TEST CONFIGURATION 2 TEST NO. HiGH POTENTIAL TEST ACCEPTANCE CRITERIA: There shall be no evidence of insulation breakdown. or flashover with a potential of 2200 VAC applied for 60 seconds. TARGET CABLE LOCATION TEST POINT READING 3-1/C 10 AMG 1 to2 1 to3 2 to 3 1 to GND* 2 to GND* 3 to GND* 00 2/C 16 AWG 1 to2 1 to GND* 2 to GND*

                             *Conduit tied to unistrut frame.

Tested By Date:~i Date: Notice of Sheet No. of C Anomaly Approved Yak Potm WH iillA.Asv. APA +4

Page No. V-l Test Repor t No. 47879-02 SECTION V CONFIGURATION NUMBER 3 TESTS (2-TRAY HORIZONTAL STACK WITH VERTICAL TRAY AND CONDUlTS OR FREE AIR SEPARATION TESTS) 1.0 REQUIREMENTS Acceptance Criteria Insulation Resistance Test Insulation resistance on all "target cables" a shall be greater than 1.6 x 10 ohms with a potential of 500 VDC applied for 60 seconds. Before testing insulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an .ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the Overcurrent Test. 1.1.2 H Potential Test shall be no evidence of insulation breakdown or -flashover with a potential of VAC applied for one minute. 1.1.3 Cable Continuit Test Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 480 VAC (120 VAC for control cables) before, during, and after the overcurrent test. Cable No. CPS L Cable Rated Size Conductors iD. No. ~e ~Volta e Current 16 AWG 2/C D50-11 C 120 VAC 10A 10 AWG 3-1/C D25-01, P 480 VAC 40A 1.1.4 Tolerances All target cable voltages specified in this procedure shall be maintained within a +3% tolerance. All target cable currents shall be maintained within a+10% tolerance. All fault cable currents shall be maintained within a +3% tolerance. The term "target cable" refers to energized and monitored nonfault cables used in this program. WYLE LABORATORIES Huntsville Facility

Page No. V-2 Test Report No. 47879-02 2.0 PROCEDURES 2.1 Test Specimen Preparation The test specimens were mounted into the test assembly of Figure 1 of Section VI. This apparatus was manufactured to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following guidelines were observed with regard to the materials and construction of the assembly: The faulted cable was a Triplex 350 MCM cable from CPRL stock.

2. For Test No. 1, the faulted cable was located in the right hand lower corner of Tray Tl, as shown in Figure V-1. For Test No. 2, the faulted cable was located in the top layer of the cable of Tray T2, as shown in Figure V-4. For Test No. 3, the faulted cable was located in the bottom layer of cable at the centerline of Tray T3, as shown in Figure V-7..

3., The ends of-the fault cable were wrapped from their termination on the copper bus bar to the edge of their cable tray. This wrap consisted of a single layer of HAVEG SILTEMP WT-65 covered with a single layer of 3M No. 69 glass tape. This wrapping was done as a safety measure to ensure that any ignition that might occur was contained to the cable tray test area.

4. The vertical cable tray was mounted such that the rungs are toward the the horizontal trays and separated by 12 inches horizontally.

sider'f

5. The horizontal cable trays (Tl and T2) were mounted such that there are 36 inches between the top of the sideraQ of one tray to the bottom of the siderail of the next cable tray.
6. The cable. trays were filled to the top of their siderails with de-energized power-type cables from CPRL stock. The target cable tray contained one energized 3-1/C 10 AWG cable located in the bottom layer of cables for Trays Tl and T3, or the top layer of cables for Tray T2, as applicable. For Test 1, the lower horizontal tray contained only de-energized lengths of power-type cable.
7. The conduits, Cl (parallel) and C2 (perpendicular), were 1-inch rigid steel conduits and contained 2/C 16 AWG target cables. For Test No. 3, no conduits were utilized. The 2/C 16 AWG cable was mounted in free air for this test.
8. The nine cables adjacent to the fault cable in the fault cable tray were energized with rated current throughout the Overcurrent Test. This was done to simulate the heat that the fault cable would experience in an energized cable tray. The adjacent cables were 1/C 6 AWG cables for Test 1 and 1/C 2 AWG cables for Tests 2 and 3.
9. Photographs were taken of the test setup prior to each test.
10. A 1/2-inch VHS recording was taken of the Overcurrent Test encompassing t entire duration the test current is applied.

WYLE LABORATORIES Huntsville Facility

Page No. V-3 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.2 Instrumentation Setup 2.2.1 Thermocou le Locations 2.2.1.1 Test No. 1 A total of 46 Type "E" thermocouples were utilized for these tests. These thermocouples were mounted as described below: Channel No. Location 1-8 Mounted to the jacket on the fault cable in Tray T1. These thermocouples were mounted approximately 12 inches apart. 9 8c 10 Mounted to the conductor of the fault cables at the two series connections. These thermocouples were applied by prying up the insulation at the series connections and then mounting the thermocouples in the strands of the cable conductors. 11-16 Mounted to the conductors of the cables adjacent to the fault cable in the fault cable tray. These thermocouples were applied by prying up the insulation at the series connections and then mounting the thermocouples in the strands of the cable conductors. 17-24 Mounted to the jacket on the target cable inside Conduit C1. These thermocouples were mounted approximately 12 inches apart. 25-30 Mounted to the jacket on the target cable inside Conduit C2. These ther mocouples were mounted approximately 12 inches apart. 31 2 32 Mounted to the outside of Conduit C1. These thermocouples were spaced approximately 36 inches apart. 33 R 34 Mounted to the outside of Conduit C2. These thermocouples were mounted within 2 inches of the location of the fault cable. 35-40 Mounted 'to the jacket on the target cable in Tray T3. These thermocouples were mounted approximately 6 inches apart starting at the top of Tray T3. 41-44 Mounted to the jacket on the top layer of cable in Tray T2. These thermocouples were mounted approximately 24 inches apart. 45 446 Mounted to the rungs of Tray T3. These thermocouples shall be mounted to two rungs at the same height as Tray Tl. WYI.E LABORATORIES Huntsville Facility

Page No. V-4 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.2 Instrumentation Setup (Continued) 2.2.1.2 Test No. 2 A total of 50 Type "K" thermocouples were utilized for these tests. These thermocouples were mounted as described below: Channel No. Location 1-8 Mounted to the jacket on the fault cable in Tray T2. These thermocouples were mounted approximately 12 inches apart. 9 dc 10 Mounted to the conductor of the fault cables at the two series connections. These thermocouples were applied by prying up the insulation at the series connections and then mounting the thermocouples in the strands of the cable conductors. 11-16 Mounted to the conductors of the cables adjacent to the fault cable in the fault cable tray. These thermocouples were applied by prying up the insulation at the series connections and then mounting the thermocouples in the strands of the cable conductors. 17-24 Mounted to the jacket on the target cable inside Tray Tl. These thermocouples were mounted approximately 12 inches apart. 25-30 Mounted to the jacket on the target cable inside Tray T3. These thermocouples were mounted approximately 6 inches apart starting at the bottom end of the tray. 31-36 Mounted to the jacket on the target cable inside Conduit C1. These thermocouples were mounted approxi-mately 15 inches apart. 37-42 Mounted to the jacket on the target cable inside Conduit C2. These thermocouples were mounted approximately 6 inches apart starting at the bottom end of the conduit. 43 244 Mounted to the exterior of Conduit Cl. These thermocouples were mounted 24 inches away from the centerline of the conduit. 45 R 46 Mounted to the exterior of Conduit C2. Thermocouple No. 45 shall be mounted even with the height of Tray T2, and Thermocouple No. 46 shall be mounted 6 inches above the height of Tray T2. 47 R 48 Mounted to the sideraQ lip on Tray T2 adjacent to the fault cable. 49 8( 50 Mounted to two rungs underneath Tray Tl and directly above the fault cable. WYLE LABORATORIES Huntsville Faclllty

Page No. V-5 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.2 Instrumentation Setup (Continued) 2.2.1.3 Test No. 3 A total of 42 Type "K" thermocouples were utilized for these tests. These thermocouples were mounted as described below: Channel No. Location 1-8 Mounted to the jacket on the fault cable in Tray T3. These thermocouples shall be mounted approximately 9 inches apart., 9 2 10 Mounted to the conductor of the fault cables at the two series connections. These thermocouples were applied by prying up the insulation at the series connections and then mounting the thermocouples in the strands of the cable conductors.. 11-16 Mounted to the conductors of the cables adjacent to the fault cable in the fault cable tray. These thermocouples were applied by prying up the insulation at the series connections and then mounting the thermocouples in the strands of the cable conductors. 17-24 Mounted to the jacket on the target cable inside Tray Tl. These thermocouples were mounted approximately 4 inches apart. spanning the area where the vertical tray passed Tray T1. 25-32 Mounted to the jacket'n the target cable inside Tray T2. These thermocouples were mounted approximately 4 inches apart spanning the area where the vertical tray passed Tray T2. 33-40 ttIIounted to the jacket on the target cable in free air. These thermocouples were mounted approximately 9 inches apart. 41 itilounted to the siderail lip of Tray Tl at the location where the fault cable passed this tray. 42 Mounted to the siderail lip of Tray T2 at the location where the fault cable passed this tray. These ther mocouples were monitored using a Fluke Datalogger feeding a high-speed printer. The datalogger was operated at its maximum rate throughout the Overcurrent Test. The temperature data has been plotted versus time and is presented in Appendices I through III of this section. WYLE LABORATORIES Huntsville Facility

Page No. V-6 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.2 Instrumentation Setup (Continued) 2.2.2 Electrical Monitor All phase-to-phase voltages and phase currents of the target cables and the fault cable current were continuously monitored by oscillograph recorders. - The oscillograph was operated at the 0.1-inch per minute rate throughout the Overcurrent Test. The oscillograph channels were as specified in the following table. 2.2.2.1 Test No. 1 Channel No. Si Cable/Location Voltage A-B 3-1/C 10 AWG/T3 Voltage A-C 3-1/C 10 AWG/T3 Voltage B-C 3-1/C 10 A WG/T3 Current-Phase A 3-1/C 10 AWG/T3 Current-Phase B 3-1/C 10 AWG/T3 Cur rent-Phase C 3-1/C 10 A WG/T3 Voltage 2/C 16 AWG/Cl 8 Current 2/C 16 AWG/C1 9 Voltage 2/C 16 AWG/C2

                     , 10                          Current             2/C 16 AWG/C2 11                          Skipped                   N/A 12                         .Current             Fault Cable/T1 WYLE LABORATORIES Huntsville Facility

Page No. V-7 Test Report No. 47879-02 PROCEDURES (Continued) 2.2 Instrumentation Setup (Continued) 2.2.2.2'est No. 2 OscBl h No. 1 Channel No. Si Cable/Location Voltage A-B 3-1/C 10 AWG/T3 Voltage A-C 3-1/C 10 AWG/T3 Voltage B-C 3-1/C 10 AWG/T3 Current-Phase A 3-1/C 10 AWG/T3 Current-Phase B 3-1/C 10 AWG/T3 Current-Phase C 3-1/C 10 AWG/T3 7 Voltage A-B 3-1/C 10 AWG/T1 8 Voltage A-C 3-1/C 10 AWG/T1 9 Voltage B-C 3-.1/C 10 AWG/T1 10 Current-Phase A 3-1/C 10 AWG/T1 Current-Phase B 3-1/C 10 AWG/Tl 12 Current-Phase C 3-1/C 10 AWG/Tl OscBl h No. 2 Channel No. Si Cable/Location Voltage 2/C 16 AWG/C1 Current 2/C 16 AWG/Cl Voltage 2/C 16 AWG/C2 Current 2/C 16 AWG/C2 5-8 Skipped N/A Current Fault Cable/T2 10-11 Skipped N/A WYLE LABORATORIES Huntsville Facility

Page No. V-8 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.2'nstrumentation Setup (Continued) 2.2.2.3 Test No. 3 OscB1 a h No. 1 Channel No. S Cable/Location Voltage A-8 3-1/C 10 AWG/T3 2 Voltage A-C 3-1/C 10 AWG/T3 3 Voltage 8-C 3-1/C 10 A WG/T3 4, Current-Phase A 3-1/C 10 AWG/T3 5 Current-Phase 8 3-1/C 10 A WG/T3 6 Current-Phase C 3-1/C 10 AWG/T3 7 Voltage A-8 3-1/C 10 A WG/Tl 8 Voltage A-C 3-1/C 10 AWG/T1 9 Voltage 8-C 3-1/C 10 A WG/T1 10 Current-Phase A 3-1/C 10 AWG/Tl 11 Current-Phase 8 3-1/C 10 AWG/T1 12 Current-Phase C 3-1/C 10 AWG/T1 Oscill h No. 2 Channel No. Si Cable/Location Voltage 2/C 16 AWG/Free Air Current 2/C 16 AWG/Free Air 3-8 Skipped N/A Current Fault Cable/T3 10-11 ~ Skipped N/A A digital multimeter was utilized to measure all phase-to-phase or phase voltages and phase currents of the target cables prior to, during, and after the Overcurrent Test. This data was recorded to provide accurate evidence of the specimen's capability to conduct rated current at 480 VAC (power cable) or 120 VAC (control cables) throughout the Overcurrent Test and is presented in Appendices I through III of this section. WYLE LABORATORIES Huntsville Facility

Page No. V-9 Test Report No. 47879-02 PROCEDURES {Continued) 2.3 Baseline Functional Tests The baseline functional tests consisted of Insulation Resistance and High Potential measurements on each of the target cables. These tests were performed as described below: 2.3.1 Insulation Resistance Test All power and instrumentation leads were disconnected from the-target cables. Using a megohmmeter, a potential of 500 VDC was applied and the minimum insulation resistance indicated after a period of 60 seconds was recorded between the following test points: Tar et Power Cable Phase-to-Phase Phase-to-Ground lto2 1 to tray 1to3 2 to tray 2 to 3 3 to tray Tar et Control Cable Phase-to-Phase Phase-to-Ground lto2 1 to conduit 2 to conduit For aQ performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 ohms. 2.3.2 H Potential Test Using a Hi-Pot Test Set, a potential of 2200 VAC was applied and the leakage current observed af ter a period of 60 seconds was recorded between the following test points: Tar et Power Cable: Phase-to-Phase Phase-to-Ground lto2 1 to tray 1to3 2 to tray 2 to 3 3 to tray WYLE LABORATORIES Huntsville Facility

Page No.. V-10 Test Report No. 47879-02 2.0 (Continued) 2.3.2'ROCEDURES 2.3 Base1ine Functional Tests (Continued) h Potential Test (Continued) Tar et Control Cable Phase-to-Phase Phase-to-Ground 1to2 1 to conduit 2 to conduit

2. All power and instrumentation leads were reconnected.

For all performances of this test, the measured values were compared to the acceptance criteria, Paragraph 2.1.2, i.e., there was no evidence of insulation breakdown or flashover. Overcurrent Test The Overcurrent Test was conducted in two sequential phases with no intentional time delay

,between phases. The first phase consisted of a warmup period with the fault cable current
.slowly increased to achieve conductor temperatures of 90 C +5 C. The second phas
  • "consisted of energizing the fault cable with the test current until the cable open-circuit The three adjacent cables (to the fault cable) were energized at rated current and
,target cables were energized at rated current and 480 VAC or 120 VAC throughout the

'vercurrent Test. The Overcurrent Test was conducted using the following procedure:

1. The Triplex 350 MCKI fault cable was connected to the copper bus bars per Figures V-l, V-4, V-7 and 7 of Section VI.
2. 2/C 16 AWG and 3-1/C 10 AWG target cables were installed in the target cable raceways per Figures V-l, V-4 or V-7, as applicable.
3. Nine 1/C 6 AWG (Test 1) or 1/C 2 AWG (Tests 2 and 3) cables, adjacent to the fault cable, were installed per Figures V-1, V-4 or V-7, as applicable.

4, The 10 AWG target cables were connected to the instrumentation and power supplies of Figure 9 of Section VI.

5. The 2/C 16 AWG cables were connected to the instrumentation and power supplies of Figure 10 of Section Vl.
6. The nine adjacent cables were connected to the power supply per Figure 8 of Section VI.

WYLE LABOAATOAIES Huntsville Facility

Page iso. V-11 Test Report iso. 47879-02 PROCEDURES (Continued) 2.4 Overcurrent Test (Continued)

7. The 2/C 16 AWG target cables were energized with 10 amperes at 120 VAC.
8. The 3-1/C 10 AWG target cables were energized with 40 amperes at 480 VAC.
9. The nine 1/C 6 AWG (Test 1) or 1/C 2 AWG (Tests 2 and 3) cables, adjacent to the fault cable, were energized with 75'amperes (Test 1) or 100 amperes (Tests 2 and 3) at reduced voltage.
10. The Triplex 350 MCM fault cable was energized with 350 amperes (rated current) from the Multi-Amp Test Set.
11. Target cable voltage and current, fault cable current and initial conductor temperature, and adjacent cable current and initial conductor temperature were recorded.
12. The fault cable and adjacent cable currents were slowly increased to achieve fault cable conductor temperature of 90oC +5oC for a period of 15 minutes.

Target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures were recorded.

14. The Triplex 350 MCM fault cable current was increased to 4200 amperes (test current).
15. Target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures were recorded.
16. The fault cable was allowed to conduct 4200 amperes until the cable open-circuited.
17. Time to ignition and open-circuit were recorded.
18. Target cable voltage and current and adjacent cable current and conductor temperatures were recorded.
19. The target cables, adjacent cables, and the iMulti-Amp Test Set were de-ener gized.
20. Photographs were taken of the post-test conditions.

Por all performances of this test, the observed target cable operation was compared to the acceptance criteria, Paragraph 2.1.3, i.e., it maintained continuity of power. WYLE LABORATORIES Huntsville Facility

Page No. V-12 Test Report No. 47879-02 2.0 PROCEDURES (Continued) 2.5 Post Overeurrent Test Functional Test The functional tests of Paragraph 3.6.4 were repeated as soon as. the smoke cleared irl the test chamber. In addition, the target cable jacket temperature was recorded. 3.0 RESULTS. 3J. Results of Test No. I Configuration Number 3, Test No. 1,. with the Triplex 350 MCM fault cable in the upper horizontal tray vertically separated by 36 inches from the lower horizontal tray (T2) and by 1 inch from a perpendicular 1-inch conduit (C2) and horizontally separated by 12 inches from the vertical tray (T3) and by 1 inch from. a parallel conduit (CI), was conducted in accordance with Paragraph 2.0 and met the Acceptance Criteria of Paragraph 1.0. The 4200 ampere fault current was applied until the cable open-cireuited in 266.13 seconds. The fault cable ignited after 183 seconds and burned for approximately 9 minutes prior to self-extinguishing. The flames were approximately 6-8 inches high and appeared to be suppressed by the cables on top of the fault cable. The flames did extend horizontally past the tray siderail edge and were observed around the 1-inch parallel conduit. The peak fault cable temperature during this test was 1554.4oF. All of the target cables maintained their electrical integrity and conducted 40 amperes 480 VAC or 10 amperes at 120 VAC throughout the Overcurrent Test and to successfully complete the Post-Overcurrent Test Functional Tests. The peak temperatures recorded on the target cable jackets and raceways were: Jacket Tray or Conduit Cable Conduit Tem erature 3-1/C 10 A WG T3 Bottom Layer 202.1oF 154.3oF 2/C 16 AWG Cl 365.4oF 454.2oF 2/C 16 AWG C2 262.3oF 415.7oF N/A T2 Top Layer N/A 132.6oF There was no visual evidence of degradation to any of the target cables following this test.. Appendix I contains the following data from this test: 1) Figure V-1 which illustrates the test setup; 2) Photographs V-1 through V-8 which show the pre-test and post-test conditions; 3) A narrative of the Overeurrent Test; 4) Two plots of temperatures versus time: The first plot shows target cable jacket temperatures and the fault cable, and the second plot shows target cable raceway temperatures; and, 5) Data Sheets which contain Baseline Functional Test, Overcurrent Test, and Post-Overcurrent Test Functional Te data. VlYLE LABOAATOAtES Huntsville Faclllty

Page No. V-13 Test Report No. 47879-02 RESULTS (Continued) 3.2 Results of Test No. 2 Configuration Number 3, Test No. 2, with the Triplex 350 MCM fault cable in the lower horizontal tray vertically separated by 36 inches from the lower. horizontal tray (T2) and horizontally separated by 12 inches from the vertical tray (T3) and by 1 inch from the two parallel conduits, was conducted in accordance with Paragraph 2.0 and met the Acceptance Criteria of Paragraph 1.0. The 4200 ampere fault current was applied until the fault cable opencircuited in 223.98 seconds. The fault cable ignited after 160 seconds and burned for approximately 8 minutes prior to self-extinguishing. The flames were approximately 30 inches high, did not reach the upper horizontal tray but did reach the vertical conduit mounted 1-inch horizontally from the lower tray siderail lip. The peak fault cable temperature during this test was 1372.4 F. All of the target cables maintained their electrical integrity and conducted 40 amperes at .480 VAC or 10 amperes at 120 VAC throughout the Overcurrent Test and to successfully complete the Post-Overcurrent Test Functional Tests. The peak temperatures recorded on the target cable jackets and raceways were: Jacket Tray or Conduit Cable Conduit Tem erature 3-1/C 10 AWG T3 Bottom Layer 203.7oF N/A 2/C 16 AWG Cl 223.9oF 382.9oF 2/C 16 AWG C2 248.5oF 539.9oF 3-1/C 10 AWG Tl Bottom Layer 236.2oF 378.7oF There was no visual evidence of degradation to any of the target cables following this test other than a light smoke deposit on the cables in the upper vertical tray. The test results on Tray Tl also support a 36-inch vertical separation distance from a free air faulted cable to a flexible steel conduit. Appendix II contains the following data from this test: 1) Figure V-4 which illustrates the test setup; 2) Photographs V-9 through V-15 which show the pre-test and post-test conditions; 3) A narrative of the Overcurrent Test; 4) Two plots of temperatures versus time: The first plot shows target cable jacket temperatures and the fault cable, and the second plot shows target cable raceway temperatures; and, 5) Data Sheets which contain Baseline Functional Test, Overcurrent Test, and Post-Overcurrent Test. Functional Test data. WYLE LABORATORIES Huntsville Facility

Page No. V-14 Test Report No. 47879-02 3.0 RESULTS (Continued) 3.3 Results of Test No. 3 Configuration Number 3, Test No. 3, with the Triplex 350 lIICM fault cable in the vertical tray horizontally separated by 12 inches from two horizontal trays (T1 and T2) and a free air 2/C 16 AWG target cable, was conducted in accordance with Paragraph 2.0 and met the Acceptance Criteria of Paragraph 1.0. The 4200 ampere fault current was applied until the fault cable open-circuited in 201.16 seconds. The fault cable ignited after 193 seconds and burned for approximately 5 minutes prior to self-extinguishing. The flames were approximately 12 inches high and 6 inches wide, and appeared to be suppressed by the other cables in the vertical tray. The peak fault cable temperature during this test was 1514.7 F All of the target cables maintained their electrical integrity and conducted 40 amperes at 480 VAC or 10 amperes at 120 VAC throughout the Overcurrent Test and to successfully complete the Post-Overcurrent Test Functional Tests. The peak temperatures recorded on the target cable jackets and raceways were: Jacket Tray or Conduit Cable Conduit Tem erature 3-1/C 10 AWG Tl Bottom Layer 132.4oF 135.8oF 2/C 16 AWG Free Air Cable 166.4oF N/A 3-1/C 10 AWG T2 Top Layer 133.0 F 130.7oF There was no visual evidence of degradation to any of the target cables following this test other than a light smoke deposit on the cables in the upper vertical tray. These test results also support a 12-inch horizontal separation distance between free air cables. Appendix III contains the following data from this test: 1) Figure V-7 which illustrates the test setup; 2) Photographs V-16 through V-18 which show the pre-test and post-test conditions; 3) A narrative of the Overcurrent Test; 4) Two plots of temperatures versus time: The first plot shows target cable jacket temperatures and the fault cable, and the second plot shows target cable raceway temperatures; and, 5) Data Sheets which contain Baseline Functional Test, Overcurrent Test, and Post-Overcurrent Test Functional Test data. WYLE LABORATORIES Huntsvilte Facility

Page. No. V-15 Test Report No. 47879-02 APPENDIX I CONFIGURATION NUMBER 3, TEST NO. 1 DATA WYLE LABORATORIES HuntSville Facility

Page No. V-16 Test Report No. 47879-02 3-1/C 10 AWG TARGET CABLE Cl ADJACENT CABLES FAULT CABLE T3 FAULT CABLE Tl ooacaooooo ooPoooOOdoo Cl OOOOO 0 80 C2 T3 00, Oo. 000 1" SEPARATION 600 oo pO 36". OP 1" RIGID ALL TRAYS FILLED TO TOP STEEL CONDUIT OF SIDERAILS WITH 2/C 16 AHG TARGET CABLE T2 ggo Q oo Oo ooo oo QQ ooo 0 Oo ooze 24" 1 2ll 24" X 4" X 96" CABLE TRAY FRONT VIEW TOP VIEW PIQUBE V-1 CONPIGURATICN 3 TEST HO 1 SETOP

Page No. V-17 Test Report No. 47879-02 Iq +pl.t t

                                   )

PHOTOGRAPH NO. V-1 FRONT VIEW OF TEST SETUP FOR THE CONFIGURATION NUMBER 3, TEST NO. 1 I

                                                           <<J PHOTOGRAPH NO. V-2 SIDE VIEW OF TEST SETUP SHOWING VERTICALTRAY AND 1-INCH CONDUlT BELOW TRAY Tl (Note: This Conduit was Repositioned after this Photograph to be 1-inch Below the Upper 'I2ay)

Page No. V-18 Test Report No. 47879-02 rr fr Pr

                               -3 V

( rr PHOTOGRAPH NO. V-3 FRONT VIEW OF TEST SETUP PROM THE MULTI-AMPTEST SET END 4j

                                  ,/j'f
                   ) ~    I~ r 1,

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                                            )[hajj c'lrt,r.r IIr'HOTOGRAPH NO. VH SIDE VIEW SHOWING POSITIONING OF CONDUITS Cl and C2 AND THE VERTICALTRAY WITH RESPECT TO THE UPPER TRAY I

Page No. V-19 Test Report No. 4ZSZS-02 1

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                                                         >1 PHOTOGRAPH NO. V-5 POST-TEST VIEW OF FAULT CABLE AS IT EXITED UPPER TRAY AND CONDUIT C1 o )

I ($ 44>>" t PHOTOGRAPH NO. V-6 SIDE VIEW SHOWING SMOKE AND FLAME DAMAGE TO CONDUIT C1. THE FAULT CABLE FLAMES MOVED HORIZONTALLYOVER THIS CONDUIT.

Page No. V-20 Test Report No. 47879-02

              't 5

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ti PHOTOGRAPH NO. V-7 ~ POST-TEST VIEWS OF THE UPPER TRAY AND THE PERPENDICULAR CONDUIT C2 PHOTOGRAPH NO. V-8 POST-TEST VIEW OF THE LOWER TRAY SHOWING CARBONIZED JACKET FROM THE FAULT CABLE THAT FELL INTO THE LOWER TRAY. THERE WERE NO BURNING PIECES THAT FELL INTO THIS TRAY.

guratlon 3 - Test 1 Hli LEGEfiDt Pault Cable Jacket Tcaperature (T/CS 1-8) Pault Cable Conductor Teapcrature (T/CS 9 4 10) (I ItII tt ll I DRAMN BY: Target Cable (Cl-2/C 16 AWC) Jacket Teaperature (T/CS 17-24). fIt 11 i. ~ 1500 Target Cable (C2-2/C 16 AljO) Jacket Teaperature (T/CS 25-30) I I CfjECKED BY Target Cable (T3-3-1/C 10 Allo) Jacket Teaperature (T/CS 35-40) 1 I Ill 1400 Nax. Teap. Recorded: 1554.4 P (T/C 85) at 165.4 aln 1 'hi j 1 'j'1 'll'lfijilt 'l" "1" i'" Aablent Teap.s 85 P 1 p!l Date: Septeaber 6, 1985 PIGURE V-2 1 li ii ;1 lh ll t'jt 1 1100  !'I li 1000 li 1 I rl, ij if i fjl ill I I I lit 1 il ig'jg I. }H 1 tfg Ih ll I.p

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I Iii Conf)gurat)on - Test il tl)l LEGEND: 3 1 Pault Cable Jacket Tesperature {T/CS 1-8)

                                                                                                                                                                              'il: llj               B Il     DRAWN BY:

i

                      'I I                                                                                                                                                             '!in Pault Cable Jacket Tesperature (T/CS 9 4 10)                                                                              CHECKED BY 1 1500                                                                        Tesperature of Condu)t Cl (T/CS 31 4 32)                                                            I  I Tesperature Of COndutt C2 <T/CS 33 4 34)                                                     il   i.        I 1400   I,!I,I                                                               Tesperature In Tray T2 - upper layer rT/CS 41-44)                                            !It j   1, I 1
l. 1 I!h 't 'fji'"ljj tn'1 j

Tesperature of Rungs on Tray T3 {T/CS 45 4 46) t t ll Il Tesp. Recorded: 1554.4 P fT/C )5) at. 165.4 s)n 1 1 1 14ax Asblent Tesp.t 85 P I 1 II)1 Date: Septesber 6. 19SS I I ll ) I i i'll 'ifi V-3 tnI I I'.'jj PICURE 4100

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Page No. V-23 Test Report No. 47879-02 f ~ )rq~sr. CONFIGURATION 43 TEST fl APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 85 F 85 F Energized fault cable with 350A 5 min 100 F 92 F Energized fault cable with 360A 10 rain 110 F 100 P Energized fault cable with 370A 30 min 136 F 116 F Energized fault cable with 375A 37.5 min 146 F 127 F Energized fault cable with 380A 80 min 180 F 156 F Energized fault cable with 390A 109.2 min 195 F 170 F Energized fault cable with 400A 128.3 min 202 F 179 F Energized fault cable with 410A 138.3 min 205 F 182 F Energized fault cable with 415A 161 min 212 F 193 F Energized fault cable with 4200A 163.7 min 850 F 850 F Heavy off-gassing 164 min 1050 F 957.5 F Ignition of fault cable. Peak recorded conductor temperature. 165.4 min 1554.4 F 873 F Open circuit indicated by multi-amp test set. Peak recorded jacket temperature. 173 min 970 F 635 F Fire out WYLE LABORATORlES Huntsvilte Facillry

Page No. V-24 Test Report No. 47879-02 DATA SHEET Customer WYLE LABORATORIES Specimen Cab 1 es Part No. Various Amb. Temp. Job No. Spec WLTP 47879 01 ~ IPR 3 photo Report No. Para. Test Med. Start Date S/N No Specimen Temp. Various GSI No fUNCTIONAL T ST CONFIGURATI N 3 T ST N . 1 INSULATiON RESISTANCE TEST ACCEPTANCE CRITERIA; Heasured insulation resistance shall be greater than 1.6 X 10 Ohms with 500 VOC a lied for 60 seconds TARGET CABLE LOCATION TEST POINT REAOING 3-1/C 10 AWG T3 1 to2 4;ex/0 ~ 1 to3 4 0 x /0 2 to 3 8 ~ 1 to tray .7 x,~'~ 2 to tray . ~ r./O~m 3 to tray +3 xylo~~ 2/C 16 AWG Cl to2

                                                                                                             ~

1 1 to conduit 8. ~ P'/0 2 to conduit 7.G </0 M 2/C 16 AWG C2 1 to2 o~-'7 </g ~ 1 to conduit 2 to conduit Notice of Tested By Witness I

                                                                                                  ~+< D.ie Date:
                                                                                                             ~~

Sheet No. of Anomaly -7 ~/ ivi i ~ 0'm 'ivy Sls*, Pew AD% 9 Approved

                                                                                +'W/

Page No. V-25 Test Report No. 47879-02 DATA SHEET Customer WYLE LABORATORiES Specimen Cabl es part.wo. Various Amb. Temp. 47879 Spec WLTP 47879 01 IPR 3 Photo Yes Report No. 47879-02 Para. 3.6 Test Med. Air Start Date /-8-SA S/ N No Specimen Temp. Various GSI No Test Title FUNCTIONAL TESTS CONFIGURATION 3 TEST 1 HIGH POTENTIAL TEST ACCEPTANCE CRITERIA: There shall be no evidence of insulation breakdown or flashover with 2200 VAC applied for 60 seconds. TARGET CABLE LOCATION TEST POINT READING 3-1/C 10 AWG T3 1 to 2 47 uP 1 to3 KDD ~Q 2 to 3 MD>(3 1 to tray /DS"D.~A 2 to tra /r /d.uA 3 to trav /@go~.4 2/C 16 AWG Cl to 2 1 to conduit .oc~A 2 to conduit 2/C 16 AWG C2 1 to2 1 to conduit 2 to conduit Tested By ~:=;~i. Z ~ D,. 9/-gg Witness Date: gr Sheet No. of uomatI A!pl& Aporoved ~l k ir-(~~~ C' -g~ use'e sotre tvse dtaa !see atsR 'da

Page No. Y-26 Test Report No. 47879-02 DATA. SHEET.'ustomer CP8 L NYLE LABORATORtES Specimen Cables Part No. Various Amb. Temp. Job No. 47879 Spec WLTP 47879-01, IPR-3 Photo Yes . '7BK42-Para. 3.6.5 Test M ed. A ir Start Date S/N No Specimen Temp. Various GSI Test Title OVERCURRENT TEST CONFIG RAT ON

11. Readings with Rated Current on Fault Cable VOLTAGE (VAC CURRENT AMPS LOCATION A-8 A-C 8-C Phase A Phase 8 Phase C 3-1/C 10 AWG T3 478 +88 +l.o S7. 3 2/C 16 AWG /.'8 2/C 16 AWG C2 TRIP 350 MCM NINE 1/C 6 AWG FAULT CABLE CONOUCTOR TEMPERATURE: 9Q~ F iested 6y .~'~-'i '+~ i Date:~~

Date: Notice of

  • DA%.,! of Anomaly

'Vwly igtw lYH Ql jA, Iyy %PA '3c (/

Page No. Y-27 Test Report No. 47879-02 DATA SHEET Customer WYLE LABORATORIES Specimen Cab 1 es tf part Qo

            'LTPVari               ous 47879-01,       IPR-3 Amb. Temp.

Photo Job No. Report No. Para. 3. 6 ~ 5 Test Med. At r Start Date SIN No GSI No OVERCURREN T TES T CONFIGURATiON 3 TEST 1 1 3~ Readings with 90'C + 5'C Conductor Temperature VOLTAGE ( VAC) CURRENT (AMPS) CABLE LOCATION A-8 A-C 8-C Phase A Phase 8 Phase C 3-1 /C 10 AWG T3 +/+ +9'/ +9+ W '7 2/C 1 6 AWG C 1

                                                              / u. 0                             /D.  />>

2/C 1 6 AWG C2 /rg / '7 TRI P 350 MCI I NINE 1 /C 6 AWG FAULT CA8LE ND T gD. 3 otice of nomaiy Vlvlt ~0<% Ah 5 I 4>, >tv AIR C4 Tested By Witness Sheet No. Approved

                                                                                     ~+~-
                                                                                         ~<<J
                                                                                               'f
                                                                                         ~~~~>M~,
                                                                                                ++' /    Date:

Date:

k Page No. V-28 Test Report No. 47&79-02 DATA SHEET Cpff4L Customer WYLE LABORATORlES Specimen Cab 1 es 5Pro~ Part No. Various Amb. Temp. Job No Spec WLTP 47879-Ql IPR-3 Photo Para. 3' ' Test Med. Air Start Date No SIN Specimen Temp. GSI No OVERCURRENT TEST 0NF IGURAT 3

                                                                                                      "   T Test Title                                                                                       N
15. Readings with Fault Current on Fau'it Cable VOLTAGE (VAC) CURRENT (ANPS)

CABLE LOCATION A-8 A-C B C P ase A Phase 8 Phase C 3-1/C 1 0 AWG T3 +$ 9 +S 2/C 1 6 AWG Cl It/ I /0. /Z 2/C 1 6 AWG C2 lm. TRIP 350 Meri NINE 1/C 6 AWG FA Tested B Witness Date: Notice of Sheet No. of Anomaly Approved 0 fS VVyl4 r40rrrr VVfr /f44. R4v4ffA "$4

Page No. V-29 Test Report No. 47879-02 DATA, SHEET'ustomer CPSL WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. Job No. Spec WLTP 47879-01, IPR-3 photo Yes Report No. Para. 3.6.5 Test Med. Air Start Date S/N No Specimen Temp. Various No GSI Test Title OVERCURRENT TEST CONFIGURATION 3 TEST 1

17. 8 18. Readings After Fault Cable Open Circuited VOLTAGE (VAC) CURRENT (AMPS)

CABLE LOCATION A-B A-C B-C Phase A Phase B . Phase C 3-1/C 10 AWG T3 2/C 16 AWG

                                                            /Po /                                       /D,/Z 2/C'6         AWG                 C2 TRIP 350           MCM NINE      1   C    6 AWG          Tl                                                                /0A MAXIMUM FAULT CABLE TEMPERATURE:                     g4 $                  /

TIME TO IGNITION: ( Tested By Witness oticeof DVC Sheet No. oI ~ 9-6-8W Anomaly Approved l>>r>>le Form Mrre 6reA, r>>e>> Apr>>'3 ~

Page No. V-30 Test Report 1%o. 47879-02 DATA SHEET Customer KYLELABORATORIES Specimen Cab 1 es part No. Various Amb. Temp. Job No. Spec WLTP 47879 01 y IPR 3 Photo Yes Report No. Para. Test Med. Start Date S/N No Specimen Temp Various No GSI TE5 i ~z. ~o~. 3~K I Tit( p~ - Q)tcQGudPGV( " FUNCTIONA T STS T9 /ASWl CONfIGURATION 3 T ST N . 1 INSULATION RESISTANCE TEST ACCEPTANCE CRITERIA; Measured insulation resistance shall be greater than 1.6 X 10 Ohms with 500 VOC ao lied for 60 seconds TARGET CABLE LOCATION TEST POINT REAOING 3-1/C 10'NG T3 1 to2 gr ro~m 1 to3 a.o gry~W 2to3 e.> xrc ~~ 1 to tray 2 to tray 3 to tray 2/C 16 AHG Cl 1 to2 1 to conduit 2 to conduit 2/C 16 AitIG C2 1 to2 to conduit /.P- x/O'

                                                                                                      ~

1 2 to conduit I >pro Tested By Notice of Witness Sheet No. Date Date: of~

                                                                                                      ~=

Anomaly Approved u-

Page No. V-31 Test Report No. 47879-02 OATA. SHEET CP8IL Customer WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. bN 47879 Spec WLTP 47879-01. IPR-3 Photo Yes eport No 47879-02 Para. 3.6 Test Med. Start Date No S/N GSI Test Title No Specimen Temp. FUNCTIONAL TESTS Q/ Q~ ~

                                                                               ~l'   dp gO+

CONFIGURATION 3 TEST 1 HIGH POTENTIAL TEST ACCEPTANCE CRITERIA: There shall be no evidence of insulation breakdown or flashover with 2200 VAC applied for 60 seconds. TARGET CASLE LOCATION TEST POINT READING 3-1/C 10 AWG T3. 1 to2 1 to3 2 to 3 Woo~~f 1 to tray 2 to tra 3 to tra / ydderi 2/C 16 AWG 1 to2

                                                               'i  to conduit 2   to conduit 2/C 16      AWG                      C2                  1   to2 1   to conduit 2   to conduit u'~

Tested By Date: Witness . Date: Sheet No. of Approved V/vl~ NOmv IDH 51IA, IIev APIR GA

Page No. V-32 Test Report No.. 47879-02 This Page Left Intentionally Blank. WYLE LABORATORIES Huntsville Fecllity

Page No. V-33 Test Report iso. 47879-02 APPENDIX II CONPIGURATION NUMBER 3, TEST NO. 2 DATA WYLE LABORATORIES Huntsville Facility

Page No. U-34 Test Report No. 47879-02 ALL TRAYS FILLED TO T3 C1 TOP OF SIDERAILS FAULT CABLE IN T2 Tl oooo 0 opo octo8 oooo'oopp T3 Ogg

                .3-1/C 10  AMG                                                    Ooo TARGET CABLE                                                     oOU 1" HORIZONTAL         Ooo SEPARATION       C2  Og o

36 II 00 1" RIGID STEEL CON- OO DUIT MITH 2/C 16 AMG TARGET CABLE 3-1/C 10 AMG TARGET CABLE FAULT CA LE ADJACENT CABLES T2 ooo0000oa~a, QGOOO POo C) o Q () o

                                ~ (1 24"  X   4" X  96" 24"                     12" TRAY FRONT Y IEM                                            TOP YIEM FIGURE  V-4. CONFIGURATION 3  TEST HO     2 SETUP

Page No. V-35 Test Report No. 47879-02 ilk'HOTOGRAPH NO. V-9 PHOTOGRAPH NO. V-10

'VERALLVIEW OF TEST SETUP FOR                         SIDE VIEW OF TEST SETUP SHOWING CONFIGURATION NUMBER 3, TEST NO. 2                PARALLELAND PERPENDICULAR CONDUITS V>,L)jlLij!,'ijll.JIIJHjj I

i ~if Q$ (l)$ h PHOTOGRAPH NO. V-11 SIDE VIEW OF TEST SETUP SHOWING VERTICALTRAYS VERTICALCONDUIT, AND LOWER HORIZONTALTRAY

Page No. V-36 Test Report No. 47879-02 lj t gQ~+0 j PHOTOGRAPH NO. V-12 OVERALL VIEW OF POST-TEST CONDITIONS

                            '4.

PHOTOGRAPH NO. V-13 SIDE VIEW SHOWING FAULTED CABLE AND PARALLELCONDUIT

Page No. V-37 Test Report No. 47879-02 ii 1J I )

   )

PHOTOGRAPH NO. V-14 SIDE VIEW SHOWING SMOKE DEPOSIT ON THE VERTICALCONDUIT i$ PHOTOGRAPH NO. V-15 BOTTOM VIEW OF UPPER HORIZONTALTRAY SHOWING SMOKE DEPOSIT ON CABLES

                                                                                                                                                                                                                                                                                                                                             'j iH!:,!

i '0! I Co nflguratlon 3 LEGEN Dl ~ - Test 2 Pault Cable Jacket Teaperature (T/CS 1-8) pault cable conductor Tettperature (T/cs 9 Target Cable (Tl-3-1/C 10 At}6) Jacket 6 10) Testperature (T/CS 17 24) I I I I I tl Il i tlj I I I if I I i i I fil I P I I' I I I DRA'lf}f BY: CIIECKED BY: ill

      " ! I                                                                   Target      Cable (T3-3-1/C 10 AWG) Jacket                                                          Testperature                (T/CS 25-30)                                I         ! I                                                           j I

ilH i

                                                                                                                                                                                                                                                                                                                                                                                                  'I
                                                                                                                                                                                                                                                     !               j Target         Cable (Cl-2/C 16 h}IC) Jacket                                                        Tetttperatuce               (T/Cs 31-36)                        f1 tl     I I I! I          'll             I          ljH      i   I   Il I.                 !              Ii Hif!,        I       I!Hh'I       I! I  IH'!iH                          I  il jP!:!Itl:H:!!!I irj'lj                                                                     Target         Cable (C2-2/C 16 h}IQ) Jacket                                                        Tettperature Hilt'll (T/CS 37 42)                           I    f       I J I

j I I i I I H!r fl I !rI fi

                .1 Max. Teup. Recorded:                                                  1372.4 P (T/C 45)

Atttb(ent Teap.l 84 P at 155.3 ttt(n If >>I I t, I,, J':! ll ,I I i!'I I Pi! Ii I  ! I i I

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g1'onfiguration LEGEND) Pault Cable Jacket Tes)perature IT/CS l-8) I 4>>v DRhmf BY f[5 Pault Cable Tesperature Conductor Tesperature IT/CS 9 a lO) of Tray T2 ILips) IT/cs 41 4 48)  :. 1:"ij I I ltt) tj Cl)ECKED BY Hi) Tesperature of Butters Rungs on Tray Tl IT/CS 49 4 50) I hij Tenperature of Conduit Cl IT/CS 43 a 44) i Tesperature of Conduit C2 IT/CS 45 4 46) Jlj )fir

                                                                                                                                                                                                                                                                                       ! h
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IS Nax. Tesp. Recordedt 1372.4 P IT/C 05) at 155.3 sin h" I lit) 1 r habient Tenp.: 84 P li

       !                                                                                  Date:           Septes)ber        9, 1985                                                                                rj PICDRE      V-6                                                                                                           Lj li                                                                                                                                               1)                           I)
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Page No. U-40 Test Report No. 47879-02 CONFIGURATION 43 - TEST'2 APPROXIMATE APPROXIMATE TEMPERATURE TEST TIME JACKET CONDUCTOR OBSERVATION 85 P 85 F Energized fault cable with 350A 10 min 95 F 95 P Energized fault cable with 375A 25 min 110 F 110 P Energized fault cable with 390A 60 min 150- P 140 P Energized fault cable with 410A 75 min 162 150 F Energized fault cable with 420A F'74 90 min P 160 F Energized fault cable with 430A 105 min 185 F 170 F Energized fault cable with 440A 150.8 min 210 F 192 P Energized fault cable with 420 153.3 min 700 F 700 F Heavy smoke 153.5 min 900 F 934.0 F Ignition of fault cable. Peak recorded conductor temperature. 154.6 min 1293 F 911 F Open circuit indicated by multi-amp test set. 155.3 min 1372.4 F 890 F Peak recorded jacket temperature 161.5 min 1035 F 770 F Pire out WYLE LABORATORIES Huntsville Faclttty

Page No. V-41 Test Report No. 47879-02 DATA SHEET Customer I CPSL WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. Job No. MLTP 47879-01, IPR-3 Photo Report No Para. 3.6.4 ~ Test Med. Air Start Date S/N No Specimen Temp. '/ari ous GSI No Test Title FUNCT IONA TESTS CONFIGURATiON 3 TEST 2

   '.iVSULATION RESISTANCE TEST ACCEPTANCE  CRITERIA:    Measured   insulation resistance shall be greater than 6

1.6 X 10 Ohms with 500 VOC applied for 60 seconds. TARGET CABLE LOCATION TEST POINT REAOING 3-1/C 10 AWG 1 to2 to 3 2 to 3 1 to tray 2 to tra 3-1/C 10 AMG T3 1 to2 1 to3 2 to 3 1 o trav 2 to tra 3 to ra Tested By otice of / No.

                                                                         'heet nomaly            AD~m                                        .Approved

Page No. V-42 Test Report No. 47879-02 DATA SHEET CP&L Customer WYLE LABORATORffS Specimen Cab1es Part No. Yarious Amb. Temp. F Job No 47879 Spec. MLTP 47879-01, IPR-3 Photo Report No. 47879-02 Para. 3.6.4 Test Med. Start Date S/N No Specimen Temp. GSI No Test Title FUNCTIONAL TESTS CONFIGURATION 3 TEST 2 INSULATiON RESISTANCE TEST (Continued) TARGET CABLE LOCATION TEST POINT REAO ING 2/C 16 A'ltfG C1 1to2 1 to cond it 2 to conduit 90 )t,'/0 2/C 16 AMG C2 I to2 1 to conduit 2 to conduit Tested By v

                                                                                         )
                                                                                           <<y          Dste:~~

Notice of Sheet No. - '+ of Anomaly Approved 'Vtd Pydvye VV>> te'e4, eteV <<+tt vtd

Page No. V-43 Test Report No. 47879-02 DATA SHEET ustomer CP8L WYLE LABORATORIES Specimen Cables Various 'mb. Temp. 0~ 47879 Part No; Job No. Spec. WLTP 47879-01, IPR-3 Photo Report No. 47879-2 Para. 3.6.4 Test Med Air Start Date SIN No Specimen Temp. Vari ous GSI Test Title MMH8 FUNCTIONAL TEST CONFIGURATION 3 TEST 2 HIGH POTENTIAL TEST ACCEPTANCE CRITERIA: There shall be no evidence of insulation breakdown or flashover with 2200 VAC applied for 60 seconds. TARGET CABLE LOCATION TEST. POINT REAOING 3-1/C 10 AWG 1 to2 1 to3 2 to 3 1 to tra zo .4 2 to tra /go <3 3 to tra 7, d~A 3-1/C 10 AWG T3 1 to2 1 to3 bmwA 1 to tra /9DO.c tA Aea, t-4 3 to tray /~d8,ug Tested By Date: ~~

 'ce of maly Witness Sheet No.                         OI~

Date:

                                                                                              -8'-8S

Page Vi o. V-44 Test Report No. 47879-02 DATA SHEET Customer CPSL WYLE LA8ORATORIES Specimen Cables Part No. Various Amb. Temp. Job No. WLTP 47879-01, IPR-3 Photo Report No. 47879-02 Para. 3.6.4 Test Med. Start Date S/N Specimen Temp. Various GSI No Test Title FUNCTIONAL TESTS CONFIGURATION 3 TEST 2 HIGH POTENTIAL TEST (Continued) TARGET CABLE LOCATION TEST POINT REAOING 2/C 16 AWG Cl 1 to 2 1 to conduit C5 m4 nd i Cdx(~( 2/C 16 AWG C2 1 to2 1 to conduit Tested Sy

                                                                                      )

Witness Date: Notice of Sheet No. of Anomaly Vttttt Fo ee ',ttte dtaA. Roe 4pR'ac

Page No. V-45 Test Report No. 47879-02 DATA SHEET CP8tL Customer WYLE LABORATORIES Specimen abl Part No. Various Amb. Temp. F W LTP 47879-01, IPR-3 Photo Yes Report No. 47879-02 Para. Test Med. Air Start Date S/N No Specimen Temp Various GSI No OVERCURRENT TEST CONFIGURATION 3 TEST 2 ll. Readings with Rated Current on Fault Cable VOLTAGE (VAC) CURRENT (NPS) CABLE LOCATION A-8 A-C 8-C Phase A Phase B Phase C 3-1/C 10 AWG 3-1/C 10 AWG T3 4o.< +.o 2/C 16 AWG Cl /L7.d 1 2 C 16 AWG C2 TRIP 350 HCI1 T2 FAULT CABLE CONDUCTOR TEMPERATURE'. 8+ I Tested By D.t.: Witness Date: Sheet No. Approved >>tt>>te Form>>:>>) 51lk ate>> At>>R "5a

Page No. V-46 Test Report No. 47879-02 DATA SHEET Customer CP8L NYLE LABORATORIES Specimen Part No. ar.i Amb. Temp. Job No 47879 Spec MLTP 47879<<01 IPR-3 Photo Yes Para. Test Med. Start Date SIN No GSI Test Title OVERCURRENT TEST CONFIGURATION 3 TEST 2 13, Readings with 90'C + 5'C CONDUCTOR TEMPERATURE VOLTAGE (VAC) CURRENT (AMPS) CABLE LOCATION A-8 A-C B-C Phase A Phase 8 Phase 3-1/C 10 AWG >7 3-1/C 10 AWG T3 +vo 2/C 16 AWG C1 /os. 5 /o. /2 2/C 15 AMG C2 TRIP 350 MCM T2 NINE. 1/C 6 AWG T2 FAULT CABLE CONOUCTOR TEMPERATURE. g/go Tested By Date:

                                                                                                             '~

Witness Date: Notice oI ] J~~ Sheet No.

                                                                                     ~ )

oI + Anomaly Approved e'Vlf FO<Pl VPH g'l jA Agv APR

Page No. V-47 Test Report No. 47879-02 DATA SHEET Customer CP8L WYLE LABORATORIES Specimen Cables Part'No. Various Amb. Temp. ++ Job No. S WLTP 47879-01, IPR-3 Photo , Report No 47879-02 Para. 3.6.5 Test Med. Air Start Date S/N No Specimen Temp Vario us GSI No Test Title OVERCURRENT TEST'ONFIGURATION 3 TEST 2

15. Readings with Fault Current on Fault Cable VOLTAGE (VAC) CURRENT (AMPS)

CABLE LOCATION A-8 A-C 8-C Phase A Phase 8 Phase C 3-1/C 10 AWG 47o +VV 81. 3-1/C 10 AMG T3 2/C 16 AMG Cl w~. 0 2/C 16 AWG C2 TRiP 350 HCM Tz NINE 1/C 6 AMG T2 /98.+ FAULT CABLE CONOUCTOR TEMPERATURE: Tested By Witness otice of Sheet No. nomaly Approved

Page LAIo. V-48 Test Report Ho. 47879-02 DATA. SHEET* Customer CP8IL VfYLE LABORATORlES Specimen Cables Part No. Various Amb. Temp. ++ 47879 WLTP 47879-01, IPR-3 Photo Para. 3.6.5 Test Med Air Start Date S/N No Specimen Temp Various Gsl OVERCURREiNT TEST CONFIGURATION 3 TEST 2

17. 8 18. Readings after Fault Cable Open-Circuited VOLTAGE (VAC) CURRENT (AMPS)

CABLE LOCATION A-B A-B A-C Phase A Phase B Phase C 3-1/C 10 AWG WB 3-.1/C 10 AWG T3 1 AWG 2/C 16 AWG TRIP 350 MCM T2 NINE 1/C 6 AWG T2 iiAXIMUM FAULT CABLE TEMPERATURE: /~~f1 $ </c-TIi41E TO IGNITION: /60 Mdo~ TIME TO OPEiV CIRCUIT: ~B. 5 ~~~ mfa Tested B Witness Notice oi i Sheet No. Anomaly Approved 'esse Fores TNps OIBA, ehe ApR Ba

Page No. V-49 Test Report No. 47879-02 DATA SHEET Customer CP&L WYLE LABORATORIES Cables Specimen Part No. Various Amb. Temp. ~+ Job No. Spec WLTP 47879-01, IPR-3 photo Yes 47879-02 Report No. Para. 3.6.4 Test Med. Air S/N No Specimen Temp. Various No lr r>'/.g~v GSI (Bd.w I Test Title M8~ /CQi FUNCTIONA TESTS a/ c2 b .b~i-CONFIGURATiON 3 TEST 2 INSULATION RESISTANCE TEST ACCEPTANCE CRITERIA: measured insulation resistance shall be greater than 6 1.6 X 10 Ohms with 500 VDC applied for 60 seconds. TARGET'ABLE LOCATION TEST POINT READING 3-1/C 10 AWG 1 to2 .4 x.rD"~ 1 to3 g.g //./d".M 2 to 3 4-A)ud "M 1 to tray 9 uM~' 2 to tra g.A~id' g.d g/~ 3-1/C 10 AWG T3 1 1 to2 to3

                                                                                 /3   Og/d b xro'M 2  to  3                     l, +xi>"~

1 to rav g /ad'~ 2 to tra .zg / ru'~m 3 to tra 2-8'/D '-~ Tested By Date: 'Notice ot Witness Date: i~ Sheet No. nomaly Uu~ Approved r- -8~

Page No. V-50 Test Repor t No. 47879-02 DATA SHEET'ustomer CP&L WYLE LABORATORIES Specimen Cables Part No. Various Amb. Temp. + r- . Job No. 47879 47879-01, IPR-3 Spec. Para. SIN NLTP

3. 6.4 No Photo Test Med.

Specimen Temp. Ai r ,.,~f'5 Report No 47879-02 GSI No Test Title ~y= Q.~MWr l~i FUNCTIONAL TESTS CONF IGURAT ION 3 TEST 2 INSULATION RES IS TANG E TEST ( Continued) TARGET CABLE LOCATION TEST POINT READING 2/C 1 6 AMG C1 1 to 2 iu "A-1 to condui )c/u " 2 to conduit J. b x~D 2/C 1 6 AI,IG C2 1 to 2 .axe~

        / b'~                                               to conduit                                  'D zC
                                                                                                           '~

1 2 to condui t Tested By ... ~P8 Witness Date: Notice of Sheet No. oI Anomaly o~ Approved "'v>> < tn V/h QI44 Ay> 4PR 'J4

Page No. V-51 Test Report No. 47879-02 DATA SHEET'ustomer CPSL WYLE LABORATORIES Cables Specimen Part No. Yarious Amb. Temp.

                                                                            ~oN         Job No.      47879 Spec.      WLTP    47879-01, IPR-3            Photo                                      Report No. 47879-2 Para.               3.6.4                     Test Med.                   Air            Start Date SIN                   No GSI                   No
           ,~ ( - Dg     ~p~g(      (~g,  FUNCTIONAL TEST CONFIGURATION 3 TEST 2 HIGH POTENTIAL TEST ACCEPTANCE     CRITERIA:   There shall be no evidence                 of insulation   breakdown  or flashover with       2200 YAC           applied for 60 seconds.

TARGET CABLE LOCATION TEST. POINT REAOING 3-1/C'0 AWG 1 to2 1 to3 2 to 3 1 to tra 2 to tra 3 to trav 3-1/C 10 AWG T3 1 to2 1 to3 1 to tra d.+ 2 3 to tray Tested By Witness otice of Sheet No. nomaly Approved

Page'No. V-52 Test Report Ho. 47879-02 QATA SHEET Customer WYLE LABORATORIES Specimen Cabl es Part No. Vari ous Amb. Temp: F Job No. Spec WLTP 47879 01 o IPR 3 Photo Report No. 47879-02 Para. 3. 6.4 Test Med. Air Start Date No SIN Specimen Temp. No

      ~
            ~= ~~p~t,"7 y~               FUNCTIONAL TESTS CONFiGURATION 3 TEST 2 HIGH POTENTIAL TEST      (Continued)

TARGET CABLE LOCATION TEST'OINT REAOING 2/C 16 AWG C1 1 to2 1 to conduit to ond i 2/C 16 AWG C2 1 to2 1 to conduit bS'a~~/

                                                                    /+r. gAA Tested By Date:

Notice ot Sheet No. of + Anomaly Approved

Page No. V-53 Test Report No. 47879-02 APPENDIX IH CONFIGURATION NUMBER 3, TEST NO. 3 DATA WYLE LABORATORIES Huntsville Facility

Page No. V-54 Test Report No. 47879-02 ALL TRAYS FILLEO TO TOP OF S IDERAILS I ( I oOOOOOOO 0 popo+OQOOe5 < 0 po d t T3 I p~O 3-1/C 10 I ooo AWG'ARGET CABLES Op l

                                                                                    '<o I

I 2/C 16 AWG ~o l FREE AIR CABLF ~Op 3611 2/C 16 AWG FAULT CABLE FREE AIR, CAB I Og) I 0 AOJACEHT CABLES 0 I 0 00 12'3 l T2 I 0 CO O,O OOOO

     <opop Op                 poop0pOOO     po               !

I

                         ,"   24"                       I        24"  X  4" X 96" TRAY FRO HT VIEW                                              TOP VIEW PIGURE V-7 CONPIGURATIOR 3  TBST NO    3 SBTOP

Page No. V-55 Test Report No. 47879-02 4 "). LM PHOTOGRAPH NO. V-16 PHOTOGRAPH NO. V-17 VERALLVIEW OF TEST SETUP FOR CLOSEUP VIEW OF VERTICALTRAY, NFIGURATION NUMBER 3, TEST NO. 3 FREE AIR CABLE, AND LOWER HORIZONTALTRAY PHOTOGRAPH NO. V-18 SIDE VIEW SHOWING FAULT CABLE IN THE VERTICALTRAY AND 2/C 16 AWG FREE AIR TARGET CABLE

Page No. V-56 Test Report No. 47879-02 PHOTOGRAPH NO. V-19 OVERALL VIEW OF DAMAGE FROM CONFIGURATION NUMBER 3, TEST NO. 3 PHOTOGRAPH NO. V-20 VIEW OF VERTICALTRAY AFTER THE OVERCURRENT TEST (Note the Limited Damage to Cables in the Tray) PHOTOGRAPH NO. V-21 VIEW OF VERTICALTRAY AND FREE AIR CABLE AFTER THE OVERCURRENT TEST

Test

          !Il
          !   1 PRAWN BY ~

Cj!ECKED BY 1)J C5 5 4 ii 1 I'onfiguration LEGENDt 3 3 Fault Cable Jacket Temperature (T/CS'1-8) Fault Cable Conductor Temperature (T/CS 9 4 10) Target Cable (Tl-3-1/C 10 AWG) Jacket Temperature I (T/CS 17-24) Target Cable (T2-3>>1/C 10 AWG) Jacket Temperature (T/CS 25-32) Free Alr Target Cable (2/C 16 AWG) Jacket Temperature (T/CS 33-40) In'.I!II j:I 41 Ii Nax. Temp. Recordedt 1514.7 P (T/C $ 7) at 143.3 min

         !I      rl:!                                                                                                                            Amb(ent Temp.i 80 F Dater September 11, 1985 FIGURE  V-b 1100                                                                              N 1000 4t nit I i i!i!

I }4 41 7OO if l !j, 16 650 4; 60

                                                                                                                                                                                                        'g 4 0 0 550                                                                                                                                                                                                i I

500 ij4 ~1 Iiij 1

       .4I                                                                                                                                                                                              Cl 450
       'm:. ij i                                                   0!                                  12                                                                                           C4 V! ijli e       .rgti    nil 400 z  350                                                                             I   .j".

I:j flu Z j gll I

       .!5 i'L                                                                      lb'l o                                                                                  i

~I lk4 t!f 250 ji dj'n m 1 (I t

       .:i".    !r5                                                            14
                                                                    ,in 4      I                                               f I4 I  'I:gj I'lr
                                                               ! 4r t it'I                         4  ld 14 nt:                     i 4

Il 3 A'lii Ii!!

                                                    '0                                                 ft
                                                                                                 'il, ftt 44I ii      I tif jr il I TIME(MIN)

t ili I

               ~

LEGEND> ~ Configuration 3 - Test 3 Fault cable Jacket Tcaperaturo (T/cs 1-8) Fault Cable Conductor Teaperature (T/CS 9 4 10) Teaperature of Tray Tl - Lip (T/C 41) DRANN BY: Cl!ECKED BY: Teaperature of Tray T2 - Lip (T/C 42) 1400 )fax. Teap. Recorded: 1514.7 0F (T/C l7) at 143.3 ain il Aab(ent Teap.r 80 F Date: Septeaber 11, $ 985 I FIGORE VW 1100 fh f'1 it

          >>.i     ii. If!":

f,i i>>!:!!i

               .11 i... H~i
                           'l                                       h     I
               !i,! !!if ftf
                                            !>>I'I                                               !                       ill!

ki h 't! i, ih h

                                                                                                                        ~
                                                                                                                          >>I lhi f

1 700 ffr tfd I"' "1

                           'I     , ll Ih'  }
                                                       '                                                   Id li 4%%1
                                                'iff 650
               ,",il fill'f                     ~
                                                  !i 11  I 11 I  I               '!1 Ihi fj t>>                                                     !    I!i 550
                                            !I    I I    I
          !>> !ill fftl I                                                                                 I      I
               >>>> >>>>                                                if>> ll tt 450 x            I IiF>>~ ~~1                          hi   I I!>>tH 1.'H e        -Hj
               !Ii: HKP i 400
t. Iff tj Z

o 300 250 i h 'ht'iiff ilh: I>>l:, Id fjh iH. ihl I iih lhl I h I IH il7jj it;"I hi Hl'rl!!Iji iif~ i>>~~jht Ift IH irH I>>

                                                                                                                  !Q IIII 0:
                                              'I

Page No. VI-I Test Repot't No. 47879-02 TEST PROCEDURE S01ENT1EC SEAYCES TEST PROOEOURE RO. ~4TETR"O

              . 8 SYSTEMS ATQAIES QAQVP
   . Box 1008, Honlsvl0e, Al SMOT TWX 1910> 9914888. Phene 1205) 8974411                                                           DATE:          AU    t1     198 Revision A k 1  >>.a ELECTRICAL RACEWAY SEPARATION VERIFICATIONTESTING POR THE CAROLINA POWER AND LIGHT COMPANY POR USE IN THE SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 APPROVED BY PROJECT MANAGER:                                          -/-     S
                                                                                                          . Johnson APPROVED BY QUALITYENGINEER:

ayne'Hight PREPARED BY PROJECT ENGINEER:

                                                                                                        . Hazeltin
                                                                                                                       /N REVISIONS                           (jmk)           FORM 1054-1 Rev. 4/74 REV. NO.           DATE                PAGES AFFECTED            BY     APP'L                 DESCRIPTION OF CHANGES 9/30/B5           4  10" 11P 14 16P19 22          T                Revised to Enter Interim Procedure and 27-51                                /o-/-   Revisions 1, 2 and 3.

COPYRIGHT BY WYlE LABORATORIES. THE RIGHT TO REPRODUCE, COPY, EXHIBIT, OR OTHERWISE UTILIZE ANY OF THE MATERIAL CONTAINED HEREIN WITHOUT THE EXPRESS PRIOR PERMISSION OF WYLE LABORATORIES IS PROHIBITED. THE ACCEPTANCE OF A PURCHASE ORDER IN CONNECTION WITH THE MATERIAl CONTAINED HEREIN SHALL BE EQUIVALENT TO EXPRESS PRIOR PERMISSION.

Page No. VI-2 Test Report No. 47879-02 Page No. 1 Test Procedure No. 47879-01 SCOPE This document has been prepared by Wyle Laboratories for the Carolina Power and Light Company (CPRL) and encompasses the testing of physical separation, with respect to electrical faults, between Class 1E and non-Class lE electrical systems in representative configurations at Shearon Harris Nuclear Power Plant (SHNPP) Unit 1. Objectives The purpose of this procedure is to present the requirements, procedures, and sequence to test the design adequacy of worst case configurations in the following electrical separation situations:

      ~     Horizontal cable tray to parallel conduit (see Figures       2 and 3)
      ~:    Free Air Separation without barriers (see Figure 4)
      ~     Conduit to conduit and free air (see Figure 5)
      ~     Vertical cable tray to horizontal cable tray (see Figure 6)

Applicable Documents Wyle Laboratories Technical Proposal for Cable Separation Test Program for Carolina Power and Light Company, No. 543/3737/GH, dated May 15, 1985. IEEE Std. 383-1974, "IEEE Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations." IEEE Std. 384-1974, "IEEE Trial Use Standard Criteria for Separation of Class 1E Equipment and Circuits." United States Nuclear Regulatory Commission Guide 1.75, Revision 1, "Physical Independence of Electric Systems." IEEE Std. 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations." Code of Federal Regulations, Section 10, Part 21. Code of Federal Regulations, Section 10, Part 50, Appendix B. WYLE LABORATORIES Huntsville Facility

Page No. VI-3 Test Report No. 47879-02 Page No. 2 Test Procedure No. 47879-01 SCOPE (Continued) Equipment Description This test procedure encompasses testing of the following IEEE Std. 383-1974 qualified power, control, and instrumentation cables as descr ibed below. Cable* CPRL Item No. Desc tion Mark No. 1 1/C 500 MCM p D25-11 2 Triplex 350 MCM p D25-10 3 Triplex 4/0 AWG p D25-08 4 1/C 2 AWG p D25-05 5 1/C 6 AWG p D25-03 6 1/C'10 AWG p D25-01 7 1/C 6 AWG C D59-03 8 1/C 10 AWG C D59-02 9 2/C 10 AWG C D50-01 10 2/C 12 AWG C D50-06 11 2/C 16 AWG C D50-11 12 1 Pair 16 AWG L D60-01 P Power. Type Cable C Control Type Cable L Low Energy Type Cable Test Sequence The test program shall be performed in the following sequence: o Test specimen identification ~' Control Cable Screening Tests (determination of ignition capability of control cables in a cable tray) Power Cable Screening Tests (worst case cable determination and horizontal tray to parallel conduit) Configuration Number 1 Test (Free Air Separation Test without barriers) r Configuration Number 2 Tests (Conduit to Conduit and Cable in Free Air Tests) ~r Configuration Number 3 Tests (2-Tray Stack with vertical tray) WYLE LABORATORIES Huntsville Facility

Page No. VI-4 Test Repor t No. 47879-02 Page No. 3 Test Procedure No. 47879-01 2.0 TEST REQUIREMENTS 2.1 Acceptance Criteria 2;1.1 Insulation Resistance Test resistance on all "target cables"* shall be greater than 1.6 x 10 ohms with a potential of 500 VDC applied for 60 seconds. Before testing insulation 2.1.2'nsulation resistance from phase to conduit (shield), the shield to conduit continuity shall be measured with an ohmmeter. All Insulation Resistance Tests shall be performed as soon as practical after the Overcurrent Test. H h Potential Test There shall be no evidence of insulation breakdown or flashover with a potential of 2200 VAC (1600 VAC for Twisted Fair 16 AWG cables) applied for one minute. 2.1.3 Cable Continui Test Energized specimens in the target raceway shall conduct 100% of NEC-rated currents (see table below) at 480 VAC (120 VAC for control cables and 50 VAC for instrument cables) before, during, and after the overcurrent test. Cable No. CPRL Cable Rated Size Conductors LD. No. Ttpe Volt~e Current 16 AWG 1 Tw. Pr. D60-01 50 VAC 16 AWG 2/C D50-11 C 120 VAC 10A 10 AWG 3-1/C D25-01 p 480 VAC 40A 500 MCM 3-1/C D25-11 p 480 VAC 430A 2.1.4 Tolerances All target cable voltages specified in this procedure shall be maintained within a

       +3% tolerance.        All target cable currents shall be maintained within a +10%

toler ance. AQ fault cable currents shall be maintained within a+3% tolerance. The term "target cable" refers to energized and monitored nonfault cables used in this program. WYLE LABORATORIES Huntsville Facility

Page No. VI-5 Test Report No. 47879-02 Page No. 4 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM 3.1 Test Specimen Identification An inspection shall be performed upon receipt of the test specimen components at Wyle Laboratories. This inspection will ensure that the test specimens are as described in Paragraph 1.3. Applicable manufacturer, model, part and serial numbers shall be verified and recorded on a Test Specimen Inspection Sheet. The test specimens shall be labeled to facilitate identification throughout the test program. 3.2 Control Cable Screening Tests Five tests shall be conducted in cable tray with various cable overloads to determine whether or not the control-type cables have the potential to support combustion or have the capability to generate enough heat to adversely affect the operation of any cabling located 1 inch or more from a faulted cable in a control tray. A 1-inch conduit, with a single pair 16 AWG target cable inside, shall be mounted 1 inch above the faulted cable. 3.2.1 Pt~ose The purposes of these tests are- to:

1. Demonstrate that the worst case electrical fault, in a control cable tray, does not have the potential to support combustion or have the capability to generate enough heat to adversely affect the operation of any cabling located 1 inch or more from a faulted cable in a control tray prior to open-circuiting and thus separation distances less than those specified in IEEE Standard 384-19?4-and Nuclear Regulatory Guide 1.75 are acceptable.
2. Demonstrate the adequacy, of design where a cable/raceway of one safety division is located within 1 inch of a faulted NNS cable, or a cable of a redundant safety division, in a control tray.

3.2.2 Test ecimen Pre aration The test specimens shall be mounted to the unistrut frame of Figure 1. This apparatus shall be assembled to the indicated dimensions by Wyle technicians using materials supplied by CPtst:L. The following guidelines shall be observed with regard to the materials and construction of this assembly:

1. The faulted cable shall be one of the following cables from CPRL stock:

Test No. Fault Cable Size CPRL LD. No. 2/C 16 AWG D50-11 2/C 12 AWG D50-06 2/C 10 AWG D50-01 A 3-1/C 10 AWG D59-02 (D25-01) A 3-1/C 6 AWG D59-03 (D25-03) A WYLE LABORATORIES Huntsville Facility

Page iNo. VI-6 Test Report No. 47879-02 Page No.. 5 Test Procedure No. 47879-01 3.0 TEST PROGRAM (Continued) Control Cable Screening Tests (Continued) 3;2'.2.2 Test S ecimen Pre aration (Continued) The fault cable shall be the top centermost cable inside an 8' 24" x 4" ladder rung cable tray filled to the top of the siderails with de-energized contr ol-type cables.

2. Nine 1/C 10 AWG cables shall be mounted underneath and around the faulted cable per Figure 2. These cables shaQ be energized. and their conductor temperatures increased to 90oC +5oC prior to applying the fault current to the fault cable. This shall be done to simulate the heat which the fault cable would experience in a cable tray of energized cables.
3. The ends of the faulted cable from their termination to the edge of the cable tray shall be wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape per'Figure 7. This shall be done as a safety measure to ensure that any ignition that might occur is contained to the cable tray area.

0

4. A 10-foot long, 1-inch rigid steel conduit shall be mounted parallel to and 1 inch above the fault cable. This conduit shall contain a single pair 16 AWG target cable (CPRL I.D. No. D60-01). The 1-foot section of this conduit which extends past the cable tray shall be wrapped with a single layer, 50% overlap, of SILTEMP,WT-65 covered with a single layer, 50%

overlap, of 3M No. 69 glass tape. 5; Photographs shall be taken of the test setup.

6. A 1/2-inch VHS recording shall be taken of the Overcurrent Test encompassing the entire application of the test current.

3.2.3 Instrumentation Setu 3.2.3.1 Thermoco le Locations A total of 35 Type "K" thermocouples shall be utilized for these tests. These thermocouples shall be mounted as descr ibed below: Channel No. Location 1-8 Mounted to the jacket of the fault cable. These thermocouples shall be spaced approximately 12 inches apart. 9 2 10 Mounted to the conductors of the fault cable at the two series connections. WYLE LABORATORIES Huntsville Facility

Page No. VI-7 Test Repor t No. 47879-02 Page No. 6 Test Procedure No. 47879-01 3.0 TEST PROGRAM (Continued) 3;2'. Control. Cable Screening Tests (Continued) 3.2.3 Instrumentation Se (Continued) Channel No. Location 11-16 Mounted to the conductors of the three cables adjacent to the faulted cable. Two thermocouples shall be mounted to each cable with one thermocouple at each series connection. 17-24 Mounted to the jacket of the single pair 16 AWG target cable inside the 1-inch conduit. These thermocouples shall be spaced approximately 12 inches apart and shall be even with the eight fault cable thermocouples. 25 ttt: 26 Mounted underneath the 1-inch conduit per Figure 2. 27-35 Mounted 1 inch above and 1 inch horizontally from the fault cable in three groups of three thermocouples per Figure 2. These ther mocouples shall be monitored using a Fluke Datalogger feeding a high-speed printer. The datalogger shall be operated at its maximum rate throughout the-Overcurrent Test. , 3-2.3.2 Electrical Monitorin The voltage and current of the target cable and the fault cable current shall be continuously monitored with an oscillograph recorder. The oscillograph shall be operated at the O.l-inch per minute rate throughout the Overcurrent Test. The oscillograph channels shall be as specified in the following table: Channel No. S al Location Current Tw. Pr. 16 AWG Voltage Tw. Pr. 16 AWG Current Fault Cable A digital multimeter shall be utilized to measure voltage and current of the target cable prior to, during, and after the Overcurrent Test. This data shall be recorded to provide accurate evidence of the specimen's capability to conduct rated current at 50 VAC throughout the Overcurrent Test. WYLE LABORATORIES Huntsville Facltlty

Page No. VI-8 Test Repor t No. 47879-02 Page No. 7 Test PIocedure No. 47879-01 3.'0 TEST PROGRAM (Continued) 3.2 Control Cable Screening Tests (Continued) 3.2.4 Baseline Functional Tests The baseline functional tests shall consist of Insulation Resistance and High Potential measurements on each of the target cables. These tests shall be performed as described below: 3.2.4.1 Insulation Resistance Test

1. Disconnect all power and instrumentation leads from the target cable.

2.. Using a megohmmeter, apply a potential of 500 VDC and record the minimum insulation resistance indicated after a period of 60 seconds between the following test points: Phase-to-Phase Phase-to-Ground* 1to2 1 to conduit 2 to conduit

  • Shield tied to conduit.

For all performances of this test, the measured values shaH btcompared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 ohms. 3.2.4.2 Hi h Potential Test

1. Using a Hi-Pot Test Set, apply a potential of 1600 YAC and record the leakage current observed after a period of 60 seconds between the foQowing test points:

Phase-to-Phase Phase-to-Ground* 1 to 2 1 to conduit 2 to conduit

  • Shield tied to conduit.
2. Reconnect power and instrumentation leads to the target cable.

For aQ performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shaQ be no evidence of insulation breakdown or flashover. WYLE LABdRATdRIES Huntsville Facility

Page No. VI-9 Test Report No. 47879-02 Page No. 8 Test Procedur e No. 47879-01 3.0 TEST PROGRAM (Continued) 3".2 Control Cable Screening Tests (Continued) 3D.5 Overcurrent Test The Overcurrent Test shall be conducted in two sequential phases with no intentional time delay. The first phase consists of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90oC

     +SOC. The second phase consists of energizing the fault cable with the test current until the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request. The conductor temperatures on the three adjacent cables (to the fault cable) shall be maintained in a 90oC +5oC band and the target cable shall be energized at rated current and 50 VAC throughout the Overcurrent Test. The Overcurrent Test shall be conducted using, the following procedure:
1. Connect the fault cable (see the table on following page) to the copper bus bars per Figures 2 and 7.
2. Install a single paiI 16 AWG target cable in the 1-inch rigid steel conduit per Figure 2.
3. Install nine 1/C 10 AWG cables adjacent to the fault cable per Figure 2.
4. Connect the single pair 16 AWG target cable to the instrumentation and power supplies of Figure 11.
5. Connect the nine 1/C 10 AWG cables to the oower supply per Figure 8.
6. Energize the single pair 16 AWG cable with 1 ampere at 50 VAC.
7. Energize the nine 1/C 10 AWG cables, adjacent to the fault cable, with 40 amperes at reduced voltage.
8. Energize the fault cable with the initial currents listed in the table on the following page.
9. Record target cable voltage and current, fault cable current and initial conductor temperature, and adjacent cable current and initial conductor temperature.
10. Slowly increase fault cable and adjacent cable currents to achieve conductor temperature of 90oC +SOC for a period of 15 minutes.

ll. Record target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures. WYLE LABORATORIES Huntsville Facility

Page No. VI-10 Test Report No. 47879-02 Page No. 9 Test Procedure No. 47879-01 3.0 TEST PROGRAM (Continued) 3.2 Control Cable Screening Tests (Continued) 3.2.5 Overcurrent Test (Continued)

12. Increase the fault cable current to the test current value in the table below.
13. Record target cable voltage and current, fault cable current and conductbr temperature, and adjacent cable current and conductor temperatures.
14. Allow the fault cable to conduct the test current until either the cable openmircuits, temperatures stabilize or decrease, or the test is terminated at the customer's request.
15. Record time to ignition, open-circuit, or stabilized temperature as applicable.
16. Record target cable voltage and current and adjacent cable current and conductor temperatures.
17. De-energize the target cables, adjacent cables, and the Multi-Amp Test Set.
18. Photograph the post-test conditions.

For all performances of this test, the observed target cable operation shall be compared to the acceptance criteria, Paragraph 2.1.3, i.e., they shall maintain continuity of power. Fault Cable Sizes and Currents Test CPRL Initial Test No. Fault Cable Size iD. No. Current 2/C 16 AWG D50-11 18A 180A 2/C 12 AWG D50-06 30A 180A 2/C 10 AWG D50-04 40A 180A 2-1/C 10 AWG D59-02 (D25-01) 40A 180A 2-1/C 6 AWG D59-03 (D25-03) 75A 180A 3.2.6 Post-Overcurrent Test Functional Test The functional tests of Paragraph 3.2.4 shall be repeated on the target cable. WYLE LABORATORIES Huntsville Facility

Page No. VI-11 Test Report No. 47879-02 Page No. 10 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.3 Power Cable Screening Test Six tests shall be conducted in cable tray with various cable overloads to determine the cable, when subjected to the worst case electrical fault at the Shearon Harris Nuclear Power Plant, that delivers the maximum amount of heat to the environment. In addition, a 1-inch conduit, with a single oair 16 AWG target cable inside, shall be mounted 1 inch above (Test 4) and 12 inches above A (Tests 1-3, 4 and 5) the faulted cable to evaluate conduit-to-tray spatial separation. 3.3.1 Pur~e

1. Determine the worst case electrical fault and cable size. This worst case cable shall be based on the following selection criteria:

A. If the cables ignite, a combination of time to ignition, insulation burn time, and observed temperatures shall be utilized to determine the worse-case cable. B. If no cables ignite, the cable which is the last to open-circuit (or does not open) shall be considered the worse-case cable. C. If no cables ignite and two or more do not openmircuit, the-cable with the highest, continuous temperatures achieved during the test shall be considered the worse-case cable. Once the worse-case- cable has been determined, this cable shall be the faulted cable in all subsequent configuration tests. 2., Demonstrate the adequacy of design where a 1-inch conduit runs parallel to and 1 inch above a faulted cable in a power-type cable tray. 3.3.2" Test ecimen Pre aration The test specimens shall be mounted to the unistrut frame of Figure 1. This apparatus shall be assembled to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following guidelines shall be observed with regard to the materials and construction of this assembly:

1. The faulted cable shall be one of the following cables from CPRL stock:

Test No. Fault Cable Size COL LD. No. 1 3-1/C 10 AWG D25-01 2 3-1/C 6 AWG D25-03 3 3-1/C 2 AWG D25-05 4 Triplex 4/0 AWG D25-08 5 Tr iplex 350 itIICM D25-01 6 Triplex 500 MCM D25-11 WYIE LASORATORIES Huntsville Facility

Page No. VI-12 Test Report No. 47879-02 Page No. 11 Test Procedure No. 47879-01, Revision A 3.0 PROGRAM (Continued) 3.3'- Power Cable Screening Test (Continued) 3.3.2'EST Test S imen Pre ation (Continued) The fault cable shall be the top centermost cable inside an 8' 24" x 4" ladder rung cable tray filled to the top of the siderails with de-energized power-type cables.

2. Nine 1/C 10 AWG cables (Tests 1-4) and nine 1/C 6 AWG cables (Tests 5 and 6) shall be mounted underneath and around the faulted cable per Figure 3. These cables shall be energized and their conductor temperatures increased to 90oC'+5oC prior to applying the fault current to the fault cable; This shall be done to simulate the heat which the fault cable would experience in a cable tray of energized cables.
3. The ends of the faulted. cable from their termination to the edge of the cable tray shall be wrapped with a single layer; 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape per Figure 7. This shaQ be done as a safety measure to ensure that any ignition that might occur is contained to the cable tray area.

4, A 10-foot long, 1-inch rigid steel conduit shall be mounted parallel to and 1 inch above (Test 4) and 12 inches above (Tests 1-3, 5 and 6) the fault cable. This conduit shall contain a single pair 16 AWG target cable (CP@L I.D. No. D60-01). The 1-foot section of this conduit which extends past the cable tray shall be wrapped with a single layer, 50% overlap, of SILTEMP WT-65 covered with a single layer, 50% overlap, of 3M No. 69 glass tape.

5. Photographs shall be taken of the test setup.
6. A 1/2-inch VHS recording shall be taken of the Overcurrent Test encompassing the entire application of the test current.,

Instrumentation Set 3.3.3'.3.3.1 Thermocou le Locations A total of 26 Type "K" thermocouples shall be utilized for these tests. These thermocouples shall be mounted as described below: Channel No. Location 1-8 Mounted to the jacket of the fault cable. These thermocouples shall be spaced approximately 12 inches apart. 9@10 Mounted to the conductors of the fault cable at the two series connections. WYLE LABORATORIES Huntsville Facility

Page No. VI-13 Test Report No. 47879-02 Page No. 12 Test Procedure No. 47879-01 3.0 TEST PROGRAM (Continued) 3.3 Power Cable Screening Test (Continued) 3.3.3 Instrumentation Set (Continued) Channel No. Location 11-16 Mounted to the conductors of the three cables adjacent to the faulted cable. Two thermocouples shall be mounted to each cable with one thermocouple at each series connection. 17-24 Mounted to the jacket of the single pair 16 AWG target cable inside. the 1-inch conduit. These thermocouples shall be spaced approximately 12 inches apart and shall be even with the eight fault cable thermocouples. 25@ 26 iMounted underneath the 1-inch conduit and spaced 2 feet from the center of the conduit. These thermocouples shall be monitored using a Fluke Datalogger feeding a high-speed printer. The datalog er shall be operated at its maximum rate throughout the Overcurrent Test.

.3.3.2 Electrical Monitorin The voltage and current     of the target cable and the fault cable current shall be continuously monitored with an oscillograph recorder. The oscillograph shall be operated at the O.l-inch per minute rate throughout the Overcurrent Test. The oscillograph channels shall be as specified in the following table:

Channel No. Si Location Current Tw. Pr. 16 AWG Voltage Tw. Pr. 16 A WG Current Fault Cable A digital multimeter shall be utilized to measure voltage and current of the target cable prior to, during, and after the Overcurrent Test. This data shall be recorded to provide accurate evidence of the specimen's capability to conduct rated current at 50 VAC throughout the Overcurrent Test. WYLE LABORATORIES Huntsville Facility

Page No. VI-14 Test Report No. 47879-02 Page No. 13 Test Procedure No. 47879-01 3.'0 TEST PROGRAM (Continued) 3;3 Power Cable Screening Test (Continued) 3.3.4- Baseline Functional Tests baseline functional tests shall consist of Insulation Resistance and High Potential measurements on each of the target cables. These tests shall be performed as described below: 3.3.4.1'he Insulation Resistance Test

1. Disconnect all power and instrumentation leads from the target cable.

2; Using a megohmmeter, apply a potential of 500 VDC and record the minimum insulation resistance indicated after a period of 50 seconds between the following test points: Phase-to-Phase Phase-to-Ground* 1to2 1 to conduit 2 to conduit

  • Shield tied to conduit.

For all performances of this test, the measured values shall bq compared to the acceptance criteria, Paragraph 2.1.1, i.e,, greater than 1.6 x 10 ohms. 3.3.4.2 Hi h Potential Test

1. Using a Hi-Pot Test Set, apply a potential of 1600 VAC and record the leakage current observed after a period of 60 seconds between the following test points:

Phase-to-Phase Phase-to-Ground* 1 to 2 1 to conduit 2 to conduit

                    'e Shield tied to conduit.
2. Reconnect power and instrumentation leads to the target cable.

For all performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shall be no evidence of insulation breakdown or flashover. WYLE LA8ORATORIES Huntsville Facility

Page No. VI-15 Test Repor t No. 47879-02 Page No. 14 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.3 Power Cable Screening Test (Continued) 3.3.5 Overcurrent Test The Overcurrent Test shall be conducted in two sequential phases with no intentional time delay. The first phase consists of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90OC

      +5oC. The second phase consists of energizing the fault cable with the test current until the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request. The conductor temperatures on the three adjacent cables'(to the fault cable) shall be maintained in a 90oC +5oC band and the target cable shall be energized at rated current and 50 the Overcurrent Test. The Overcurrent Test shall be conducted using       %AC'hroughout the following procedure:
1. Connect the fault cable (see the table on following page) to the copper bus bars per Figures 3 and 7.
2. Install a single pair 16 AWG target cable in the 1-inch rigid steel conduit per Figure 3.
3. Install nine- 1/C 10 AWG cables (Tests 1-4) or nine 1/C 6 AWG cables A (Tests 5 and 6) adjacent to the fault cable per Figure 3.
4. Connect the single pair 16 AWG target cable to the instrumentation and power supplies of Figure 11.
5. Connect the nine 1/C 10 AWG cables (Tests 1-4) or nine 1/C 6 AWG cables A (Tests 5 and 6) to the power supply per Figure 8.

6.. Energize the single pair 16 AWG cable with 1 ampere at 50 VAC. 70 Energize the nine 1/C 10 AWG cables (Tests 1-4) or nine 1/C 6 AWG cables (Tests 5 and 6), adjacent to the fault cable, with 40 amperes (Tests 1-4) or 75 amperes (Tests 5 and 6) at reduced voltage.

8. Energize the fault cable with the initial currents listed in the table on the following page.
9. Record target cable voltage and current, fault cable current and initial conductor temperature, and adjacent cable current and initial conductor temperature.
10. Slowly increase fault cable and adjacent cable currents to achieve conductor temperature of 90 C +5 C for a period of 15 minutes.
11. Record target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures.

WYLE LAHORATORIES Huntsville Facility

Page No. VI-16 Page No. 15 Test Repor t No. 47879-02 Test Procedure iVo. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.3 Power Cable Screening Test (Continued) 3.3.5 Overcurrent Test (Continued)

12. Increase the fault cable current to the test current value in the table below.
13. Record target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures.
14. Allow the fault cable to conduct the test current until either the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request.
15. Record time to ignition, open-circuit, or stabilized temperature as applicable.
16. Record target cable voltage and current and adjacent cable current and conductor temperatures.
17. De-energize the target cables, adjacent cables, and the Multi-Amp Test Set.
18. Photograph the post-test conditions.

For all performances of this test, the observed target cable operation shall be compared to the acceptance criteria, Paragraph 2.1.3, i.e., they shall maintain continuity of power. Fault Cable Sizes and Currents Test CPtst:L Initial Test No. Fault Cable Size LD Nu.. Warmu Current Current 1 3-1/C 10 AUG D25-01 40A 704A 2 3-1/C 6 AWG D25-03 75A 704A 3-1/C 2 AWG D25-05 130A 704A Triplex 4/0 AWG D25-08 . 260A 4200A A Triplex 350 iMCM D25-10 350A 4200A A 3-1/C 500 MCM D25-11 430A 4200A A 3.3.6 Post-Overcurrent Test Functional Test The functional tests of Paragraph 3.3.4 shall be repeated on the target cable. WYLE LASORATORIES Huntsville Facility

Page No. VI-17 Test Report No. 47879-02 Page No. 16 Test Procedure No. 47879-01, Revision A 3;0 TEST PROGRAM (Continued) 3.4 ConQguration Number.1 Test Configuration Number 1 shall consist of a test in free air between a faulted Triplex 350 MCM cable, and a 1-inch parallel horizontally separated single pair 16 AWG target cable. 3.4.'1. Purpose The purpose of the Configuration Number 1 Test is to: Demonstrate the acceptability of design where two cables in free air pass 1 inch horizontally from each other when the worst case electrical fault occurs to one of these cables. This configuration represents field installation of free air cables going from:

a. Tray to tray
b. Tray to conduit
c. Conduit to conduit
d. Tray/conduit to equipment.

Test ecimen Pre aration The test specimens shall be mounted to the unistrut frame assembly as shown in Pigure 1. This apparatus shall be assembled to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following shall be observed with regard to the materials and construction of the assembly:

1. The faulted cable shall be a Triplex 350 MCM cable from CPdcL stock.
2. The ends of the faulted cable from their termination at the copper bus bar to the edge of the unistrut frame shall be wrapped with a single layer of HAVEG SILTEMP WT-65 covered with a single layer of 3M No. 69 glass tape. Th'is wrapping shall be done as a safety measure to ensure that any ignition that might occur is contained to the test area.
3. The horizontally separated target cable shall be a single pair 16 AWG cable from COL stock. This cable shall be mounted such that the cable is 1 inch horizontally away from the faulted cable.

WYLE LABORATORIES Huntsvt tie Facility

Page No. VI-18 Test Report No. 47879-02 Page No. 17 Test Procedure No. 47879-01 3.0 TEST PROGRAM (Continued) 3'.4. Configuration Number 1 Test (Continued) 3.4.2 Test S ecimen Pre aration (Continued)

4. Photographs shaQ be taken of the test setup prior to each test.

5, A 1/2-inch VHS recording shall be taken of the Overcurrent Test encompassing the entire duration the test current is applied to the fault cable. 3.4.3 Instrumentation Se 3.4.3.1 Therm oco le Locations A total of 18 Type "K" thermocouples shall be utilized for this test. 'These thermocouples shall be mounted as described below. Channel No. Location. 1"8 Mounted to the jacket on the fault cable. These ther mocouples shall be mounted approximately 6 inches apart. 9 dc 10 Mounted to the conductor of the fault cables at the two series connections. 11"18 Mounted to the jacket on the horizontally separated target cable. These thermocouples shall be mounted approximately 6 inches apart and even with the fault cable thermocouples. The thermocouples shall be monitored by a Fluke Datalogger feeding a high-speed printer. The datalogger shaQ be operated at its maximum rate throughout the Overcurrent Test. WYLE LABORATORIES Huntsville Facility

Page No. VI-19 Test Report No. 47879-02 Page No. 18 Test Procedure No. 47879-01 I 3 0 TEST PROGRAM (Continued) 3'.4. Configuration Number 1 Test'Continued) 3.4.3 The voltage and current of the target cable and the fault cable current shall be continuously monitored by an oscillograph recorder. The oscillograph shall be operated at the 0.1-inch per minute rate throughout the Overcurrent Test. The oscillograph channels shall be as specified in the following table: Channel No. Si Location Current Tw. Pr. 16 AWG Voltage Tw. Pr; 16 AWG Current WCC fault cable, 4-16 Skipped N/A A digital multimeter shall be utilized to measure voltage and current of the

          ~

target cable prior to, during, and after the Overcurrent Test. This data shall be recorded to provide accurate evidence of the specimen's capability to conduct rated current at 50 VAC throughout the Overcurrent Test. Baseline Functional Tests The baseline functional tests shall consist of insulation resistance and high potential measurements on the target cable. These tests shall be performed as described below. 3.4.4.1 Insulation Resistance Test 1~ Disconnect all power and instrumentation leads from the target cable.

2. Using' megohmmeter, apply a potential of 500 VDC and record the
            ~

minimum insulation resistance indicated after a period of 60 seconds between the following test points: Phase-to-Phase Phase-to-Ground 1 to 2 1 to shield* 2 to shield

  • Shield tied to ground.

For all performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 ohms. WYLE LABORATORIES Huntsville Facility

Page No. VI-20 Test Report No. 47879-02 Page No. 19 Test Procedure No. 47879-01, Revision A 3.'0 TEST PROGRAM (Continued) Configuration Number 1 Test (Continued) 3.'4'.4.4 Baseline Functional Tests (Continued) 3.4.4.2- Potential Test

1. Using a Hi-Pot Test Set, a potential of 1600 VAC shall be applied from each conductor to ground and between conductors on multiconductor cable for a period of one minute.

Phase-to-Phase Phase-to-Ground 1to2 1 to shield* 2 to shield

  • Shield tied to ground.
2. Reconnect all power and instrumentation leads.

For all performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shall be no evidence of insulation breakdown or flashover. 3.4.5 Overcurrent Test The overcurrent test shall. be conducted in two sequential steos with no intentional time delay. The first phase consists of powering the fault cable with rated current and increasing this current until temperatures of 90oC +5oC are indicated for 15 minutes on the fault cable. The second phase consists of energizing the fault cable with the test current until the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer' request. The target cable shall conduct rated current at 50 VAC thr oughout the Overcurrent Test. The Overcurrent Test shaD be conducted using the following procedure: 1.. Connect the Triplex 350 MCiM fault cable to the copper bus bars per A Figures 4 and 7. 2.. Install a Tw. Pr. 16 AUG target cable per Figure 7.

3. Connect the Tw. Pr. 16 AUG target cable to the instrumentation and power supplies of Figure 11.
4. Energize the Tw. Pr. 16 AWG target cable with 1 ampere at 50 YAC.

WYLE LABORATORIES Huntsville Facility

Page No. VI-21 Test Repor t No. 47879-02 Page No. 20 Test Procedure No. 47879-01, Revision A 3.0 " TEST PROGRAM'Continued) 3.4: ConQguration Number 1 Test. (Continued) 3.4.5 Overcurrent Test (Continued)

5. Energize the fault cable with 350 amperes per phase (rated current) from A the Multi-Amp Test Set.
6. Record target cable voltage and current and the fault cable current.
7. Slowly increase fault cable current until thermocouple Channels 9 and/or 10 indicate 90 C +5oC conductor temperature.
8. Maintain the conductor temperature at 90 C +5 C for 15 minutes.
9. Record fault cable current and conductor temperature.
10. Increase the Multi-Amp Test Set output to 4200 amperes (test current).
11. Record target cable voltage and current and the fault cable current.
12. Allow the fault cable to conduct 4200 amperes until either the cable open- A circuits, temperatures stabilize or decrease, or the test is terminated by the customer's request.
13. Record time to ignition (or open-,circuit), maximum fault cable temperature recorded, and time current was applied to the fault cable.
14. Record target cable voltage and current.
15. De-energize the target cable and the iMulti-Amp Test Set.
16. Photograph the post-test condition.

For all performances of this test, the observed target cable operation shall be compared to the acceptance criteria, Paragraph 2.1.3, i.e., it shall maintain continuity of power. 3.4.6 Post-Overcurrent Test Functional Test The functional tests of Paragraph 3.4.4 shall be repeated. WYLE LABORATORIES Huntsville Facility

Page No. VI-22 Test Report No. 47879-02 Page No. 21 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3;5i ConQguration Number 2 Tests Configuration Number 2 shall consist of tests between flexible conduit, rigid conduit, and cable in free air mounted within 1/4-inch of each other. For Test No. 1, the faulted cable shall be the bare cable.. For Test No. 2, the. faulted cable shall be in the flexible conduit. 3.5.1 ~Pur ose The purpose of the Configuration Number 2 tests is to: Demonstrate the acceptability of design where a rigid conduit, flexible conduit, and a cable in free air are separated by less than 1/4-inch from each other (but not in contact), w'hen the worse-ease electrical fault occurs in the flexible conduit or to the bare cable. 3.5.2'est S cimen Pre tion The test specimens shall be mounted into the test assembly of Figure 1. This apparatus shall be manufactured to the indicated dimensions by Wyle technicians using materials supplied by CPRL. The following guidelines shall be observed with regard to the materials and construction of the assembly:

1. The fault cable shall be a Triplex 350 MCN cable from CPRL stock and A-mounted in Location 3 of Figure 5 for both tests.
2. The ends of the faulted cable shall be wrapped from their termination on the copper bus bar to the edge of the test assembly. This wrap shall consist of a single layer of HAVEG SlLTEMP WT-65 covered with a single layer of 3M No. 69 glass tape. This wrapping shall be done as a safety measure to ensure that any ignition that might occur is contained to the cable tray test. area.,

3.. A- 3-1/C 10 AWG target cable from CPdcL stock shall be mounted in Location 2 of Figure 5 for both tests.

4. A 2/C 16 AWG target control cable from CPttt:L stock shall be mounted in
           . Location 1 of Figure 5 for both tests.
5. The conduits and free air cable shall be orientated as described below:

Test No. Location 1 Location 2. Location 3 1 Flexible Conduit Rigid Conduit Free Air Cable A Rigid Conduit Free Air Cable Flexible Conduit WYLE LABORATORIES Huntsville Facility

Page No. VI-23 Test Report No. 47879-02 Page No. 22 Test Procedure No. 47879-01, Revision A 3;0 TEST'ROGRAM (Continued) 3.5 Configuration Number 2 Tests- (Continued) 3.5.2'. Test S imen Pre tion (Continued)

6. The conduits and cable shall be mounted 6 inches apart for Test 1 and 1 inch A apart for Test 2.

7; Photographs shall be taken of the test setup prior to each test.

8. A 1/2-inch VHS r ecording shall be taken of the Overcurrent Test encompassing the entire application of test current.

3.5;3" Instrumentation Set 3.5.3.'1 Thermoco le Locations A total of 24 Type "K" thermocouples shall be utilized for this test. These thermocouples shall be mounted as described below. Channel No. Location 1-8 Mounted to the jacket on the fault cable. These thermocouples shall be mounted approximately 12 inches apart. 9 etc 10 Mounted to the conductor of the fault cables at the two series connections. 11-18 Mounted to the jacket of the target cable in Location l. These thermocouples shall be mounted approximately 12 inches apart. 19-26 Mounted to the jacket of the target cable in Location 2. These thermocouples shall be mounted approximately 12 inches apart. 27 hatt: 28 Mounted to the outside of the flexible conduit on the side towards the rigid conduit. 29 4 30 Mounted to the outside of the rigid conduit on the side towards the flexible conduit. The thermocouples shall be monitored by a Fluke Datalogger feeding a high-speed printer. The datalogger shall be operated at its maximum rate throughout the Overcurrent Test. WYLE LABORATORIES Huntsville Facility

Page No. VI-24 Test Report No. 47879-02 Page No. 23 Test Procedure No. 47879-01 3.0 TEST PROGRAM (Continued) 3.5 Configuration Number 2 Tests (Continued) 3.5.3.2 Electrical Monitorin AQ phase-to-phase voltages and phase currents of the target cables and the fault cable current shall be fed into oscillograph recorders. The osciQograph shall be operated at the O.l-inch per minute rate throughout the overcurrent test. The oscillograph channels shall be as specified in the following table. Channel No. ~Si al Cable 1 Current 2/C 16 AWG Target Cable 2' Voltage 2/C 16 AWG Target Cable Current-Phase A 3-1/C 10 AWG Target Cable Current-Phase B 3-1/C 10 AWG Target Cable Current-Phase C 3-1/C 10 AWG Target Cable Voltage A-B 3-1/C 10 AWG Target Cable Voltage A-C 3-1/C 10 AWG Target Cable Voltage B-C 3-1/C 10 AWG Target Cable 9 4 10 Skipped N/A Current Pault Cable 12-16 Skipped N/A A digital multimeter shall be utilized to measure aQ phase-to-phase or phase voltages and phase currents of the target cables prior to, during, and after the overcurrent test. This data shall be recorded to provide accurate evidence of the specimen's capability to conduct rated current at 480 VAC (120 VAC for control cables) throughout the Overcurrent Test. 3.5.4 Baseline Punctional Tests The baseline functional tests shall consist of insulation resistance and.high potential measurements on each of the target cables. These tests shall be per for med as described below. 3.5.4.1 Insulation Resistance Test

1. Disconnect aQ power and instrumentation leads from the target cables.

WYLE LABORATORIES Huntsville Facility

Page No. VI-25 Test Report No. 47879-02 Page No. 24 Test Procedure No. 47879-01 3.0 PROGRAM (Continued) 3.5 Configuration Number 2 Tests (Continued) 3.5.'4'EST Baseline Functional Tests (Continued)

2. Using a megohmmeter, apply a potential of'00 VDC and record the minimum insulation resistance indicated after a period of 60 seconds between the following test points:

Tar et Power Cable: 3'hase-to-Ground Phase-to-Phase 1 to 2 1 to unistrut or conduit 1 to 3' 2 to unistrut or conduit to 3 to unistrut or conduit Tar et Control Cable: Phase-to-Phase Phase-tcH round 1to2 1 to conduit or unistrut 2 to conduit or unistrut For all performances-of this. test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 ohms. 1.. Using a Hi-Pot Test Set, apply a potential of 2200 VAC and record the leakage current observed af ter a period of 60 seconds between the following test points: Tar et Power Cable: Phase-to-Phase Phase-to-Ground 1 to 2' 1 to unistrut or conduit to 3 2 to unistrut or conduit 2 to 3 3 to unistrut or conduit Tar et Control Cable: Phase-to-Phase Phase-to-Ground 1to2 1 to conduit or unistrut 2 to conduit or unistrut

2. Reconnect all power and instrumentation leads.

For all performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shall be no evidence of insulation breakdown or flashover. WYLE LABORATORIES Huntsville Facility

Page iNo. VI-26 Test Repor t No. 47879-02 Page No. 25 Test Procedure No. 47879-01, Revision A 3.0 PROGRAM (Continued) 3.'5'EST ConQguration Number 2 Tests (Continued) 3.5.5 Overcurrent Test The Overcurrent Test shall be conducted in two sequential steps with no intentional time delay. The first phase consists of powering the fault cable with rated current and increasing this current until temperatures of 90oC +5oC are indicated for 15 minutes on the fault cable. The second phase consists of energizing the fault cable with the test current until the cable open-circuits, temperature stabilize or decrease, or the test is terminated at the customer' request. The target cables shall conduct rated current at 480 VAC (power cables) or 120 VAC (control cables) throughout the Overcurrent Test. The Overcurrent Test shall be conducted using the following procedure:

1. Connect the Triplex 350 MCM fault cable to the copper bus bars per A Figures 5 and 7.
2. Install a 2/C 16 AWG target cable per Figure 5.
3. Install a 3-1/C 10 AWG target cable per Figure 5.
4. Connect the 3-1/C 10 AWG target cable to the instrumentation and power supplies of Figure 9.
5. Connect the 2/C 16 AWG target, cables to the instrumentation and power supplies of Figure 10.
6. Energize the 3-1/C 10 AWG target cable with 40 amperes at 480 VAC.
7. Energize the 2/C 16 AWG target cable with 10 amperes at 120 VAC.
8. Energize the Triplex 350 MCM fault cable with 350 amperes (rated current) A from the Multi-Amp Test Set.
9. Record target cable voltages and currents and the fault cables current.
10. Slowly increase fault cable current until thermocouple Channels 9 and/or 10 indicate a 90oC +5 C conductor temperature.
11. Maintain the conductor temperature at 90oC +SoC for 15 minutes.
12. Record fault cable current and conductor temperature.

WYLE LABORATORIES Huntsvtlla Facility

Page No. VI-27 Test Report No. 47879-02 Page No. 26 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued)

                                 %4 3;5    Configuration Number    2  Tests (Continued) 3.5'.5 Overcurrent Test (Continued)
13. Increase the iVIulti-AmpTest Set output to 4200 amperes (test current).
14. Record target cable voltages,,currents and the fault cable current.
15. ADow the fault cable to conduct 4200 amperes until either the cable open- A circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request.
16. Record time to ignition (or- open-cir cuit),. maximum. fault cable temperature recorded, and time current was applied to the fault cable.
17. Record target cable voltages and currents.
18. De-energize the target cables and the Multi-Amp Test Set.
19. Photograph the post-test condition.

For all performances of this test, the observed target cable operation shall be compared to the acceptance criteria, Paragraph 2.1.3, i.e., they shall maintain continuity of power. '3.5.6 Post-Overcurrent Test Functional Test The functional tests of Paragraph 3.5.4 shall be repeated on the target cables. WYLE LABORATORIES Huntsville Facility

Page No. VI-28 Test Report No. 47879-02 Page No. 27 Test Procedure No. 47879-01, Revision A 3.0'."6'ESI'ROGRAM (Continued) Configuration Number 3 Tests Configuration Number 3 shall consist of three tests between two vertically separated horizontal cable trays and a horizontally separated vertical cable tray and conduits. For Test No. 1, the faulted cable shall be in the lower horizontal cable tray. For Test No. 2, the faulted cable shall be in the upper horizontal cable tray. For Test No. 3, the faulted cable shall be in the vertical cable tray. 3.6.1 The purposes of the Configuration Number 3 tests are to:

1. Demonstrate the acceptability of design where three horizontal cable trays are separated by 36'-inches (from the top of one tray to the bottom of the next tray) when the worst case electrical fault occurs in the either cable tray.
2. Demonstrate the acceptability of design where a horizontal cable tray passes 12 inches from a vertical cable tray when the worst case electrical fault occur's in either. tray.

3.. Demonstrate the acceptability of design where a 1-inch rigid steel conduit passes:

1) 1 inch below and perpendicular to a faulted cable in a ladder rung cable tray, or
2) 1 inch horizontally away from and parallel to the siderail wall of a ladder rung cable tray, or
3) 1 inch horizontally away from and perpendicular to the siderail wall of a ladder rung cable tray.
4. Demonstrate the acceptability of design where a free air cable passes 12 inches horizontally away from and parallel to a faulted cable in a ladder rung cable tray when the worst case electrical fault occurs in the cable tray.

3.6.2 Test S ecimen Pre aration The test specimens shall be mounted into the test assembly of Figure 1. This apparatus shall be manufactured to the indicated dimensions by Wyle technicians using materials supplied by CPdcL. The following guidelines shall be observed with regard to the materials and construction of the assembly:

1. The fault cable shall be a Triplex 350 MCM cable from CPRL stock.

WYLE LABORATORIES Huntsville Facility

Page No. VI-29 Test Report No. 47879-02 Page No. 28 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.6 ConQguration Number 3 Tests (Continued) 3.6.2 Test ecimen Pre ation (Continued)

2. For Test No. 1, the faulted cable shall be located in the right hand lower corner of Tray Tl, as shown in Figure 6A. For Test No. 2, the faulted cable shall be located in the top layer of the cable of Tray T2, as shown in Figure 6B. For Test No. 3, the faulted cable shall be located in the bottom layer of cable at the centerline of Tray T3, as shown in Figure 6C.
3. The ends of the fault cable shall be wrapped from their termination on the copper bus bar to the edge of their cable tray. This wrap shall consist of a single layer of HAVEG SILTEMP WT-65 covered with a single layer of 3M No. 69 glass tape. This wrapping shall be done as a safety measure to ensure that any ignition that might occur is contained to the cable tray test area.
4. The vertical cable tray shall be mounted such that the rungs are toward the siderails of the horizontal trays and separated by 12 inches horizontally.

5t The horizontal cable trays shall be mounted such that there are 36 inches between the top of the siderail of one tray to the bottom of the siderail to the next higher cable tray.

6. The cable trays shall be filled to the top of their siderails with de-energized power-type cables from CPkL stock. The target cable tray shall contain one energized 3-1/C 10 AWG cable located in the bottom layer of cables for Trays Tl and T3, or the top layer of cables for Tray T2, as applicable..

The conduits, Cl and C2, shall be 1-inch rigid steel conduits and shall contain 2/C 16 AWG target cables. For Test No. 3, no conduits shall be utilized. The 2/C 16 AWG cable shall be mounted in free air for this test.

8. The nine cables adjacent to the fault cable in the fault cable tray shall be energized with rated current throughout the Overcurrent Test. This shall be done to simulate the heat that the fault cable would experience in an energized cable tray.
9. Photographs shall be taken of the test setup prior to each test.
10. A 1/2-inch VHS r ecording shaQ be taken of the Overcurrent Test encompassing the entire duration the test current is applied.

WYLE LABORATORlES Huntsville Facility

Page No. VI-30 Test Repor t No. 47879-02 Page No. 29 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.6 ConQguration Number 3 Tests (Continued) Instrumentation Set 3.6.3'.6.3.1 Ther moco le Locations 3.6.3.1.1 Test No. 1 A total of 46 Type "K" thermocouples shall be utilized for this test. These thermocouples shall be mounted as described below. Channel No. Location 1-8' Mounted to the jacket on the fault cable in Tray Tl. These thermocouples shall be mounted approximately 12 inches apart. tst: 10 Mounted to the conductor of the fault cables at the two series connections. 11-16 Mounted to the conductors of the cables adjacent to the fault cable in the fault cable tray. These ther mocouples shall be mounted at the series connections. 17-24 Mounted to the jacket on the target cable inside Conduit Cl. These thermocouples shall be mounted approximately 12 inches apart. 25-30 Mounted to the jacket on the target cable inside Conduit C2. These thermocouples shall be mounted approximately 12 inches apart. 31 '2 iMounted to the outside of Conduit Cl., thermocouples shall be spaced approximately 36 inches These apart. 33 4 34 Mounted to the outside of Conduit C2. These thermocouples shall be mounted within 2 inches of the location of the fault cable. 35-40 Mounted to the jacket on the target cable in Tray T3. These thermocouples shall be mounted approximately 6 inches apart starting at the top of Tray T3. 41-44 Mounted to the jacket on the top layer of cable in Tray T2. These thermocouples shall be mounted approximately 24 inches apart. 45 ltt: 46 iMounted to the rungs of Tray T3. These thermocouples shall be mounted to two rungs at the same height as Tray Tl. WYLE LASORATORIES Huntsville Facility

Page No. VI-31 Test Report No. 47879-02 Page No. 30 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.6 ConQguration.Number 3 Tests. (Continued) 3.6.3.1.2 Test No. 2' total of 50 Type "I4" thermocouples shall be utilized for this test. These thermocouples shall be mounted as described below. Channel No. Location 1-8 Mounted to the jacket on the, fault cable in Tray T2. These thermocouples shall be mounted approximately 12 inches apart. 9 2 10 Mounted to the conductor-of the fault cables at the two series connections. 11-16 Mounted to the conductors of the cables adjacent to the. fault cable in the fault cable tray. These thermocouples shall be mounted at the series connections. 17-24 Mounted to the jacket on the target cable inside Tray T1. These ther mocouples shall be mounted approximately 12 inches apart. 25-30 Mounted to the jacket on the target cable inside Tray T3. These thermocouples shall be mounted approximately 6 inches apart starting at the bottom end of the tray. 31-36 Mounted to the jacket on the target cable inside Conduit Cl. These thermocouples shall be mounted approximately 15 inches apart. 37-42 iVIounted to the jacket on the target cable inside Conduit C2. These thermocouples shall be mounted approximately 6 inches apart starting at the bottom end of'the conduit. 43 2 44 Mounted to the exterior of Conduit Cl. These thermocouples shall be mounted 24 inches away from the centerline of the conduit. 45 4 46 iVIounted to the exterior of Conduit C2. Thermocouple No. 45 shall be mounted even with the height of Tray T2, and Thermocouple No. 46 shall be mounted 6 inches above the height of Tray T2. 47 est: 48 Mounted to the siderail lip on Tray T2 adjacent to the fault cable. 49

  • 50 Mounted to two rungs underneath Tray T1 and directly above the fault cable.

WYLE LABORATORIES Huntsville Faclllty

Page No. VI-32 Test Report No. 47879-02 Page No. 31 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.6 ConQguration Number 3 Tests (Continued) 3.6.3.1.3 Test No. 3 A total of 42 Type "K" thermocouples shall be utilized for this test; These A thermocouples shall be mounted as described below. Channel No. Location 1-8 Mounted to the jacket on the fault cable in Tray T3. These thermocouples shall be mounted approximately 9 inches apart. 9 k 10 Mounted to the conductor of the fault cables at the two series connections. 11-16 Mounted to the conductors of the cables adjacent to the fault cable in the fault cable tray. These thermocouples shall be mounted at the series connections. 17-24 Mounted to the jacket on the target cable in Tray T1. These thermocouples shall be mounted approximately 4 inches apart spanning the area where the vertical tray passes Tray Tl. 25-32 Mounted to the jacket on the target cable in Tray T2. These thermocouples shall be mounted approximately 4 inches apart spanning the area where the vertical tray passes Tray T2. 33-40 Mounted to the jacket on the target cable in free air. These thermocouples shall be mounted approximately 9 inches apart. 41 Mounted to the siderail lip of Tray Tl at the location where the fault cable passes this tray. 42 Mounted to the siderail lip of Tray T2 at the location where the fault cable passes this tray. The thermocouples shall be monitored by a Fluke Datalogger feeding a high-speed printer. The datalogger shall be operated at its maximum rate throughout the overcurrent test. WYLE LABORATORIES Huntsville Facility

Page No. VI-33 Test Report No. 47879-02 Page No. 32 Test Procedure No. 47879-01, Revision A 3.0' TEST PROGRAM (Continued) 3.6 Configuration Number 3 Tests (Continued) 3.6.3. Instrumentation Set (Continued) 3.6.3.2, Electrical Monitor All phase-to-phase voltages and phase currents of the target cables and the fault cable current shall be continuously monitored by oscillograph recorders. The oscillograph shall be operated at the O.l-inch per minute rate throughout the Overcurrent. Test. The oscillograph channels shall be as specified in the following table: 3.6.3.2."1 Test No. 1" Channel No. Si Cable/Location 1 Voltage A-B 3-1/C 10 AWG/T3

2. Voltage A-C 3-1/C 10 A WG/T3 3 Voltage B-C 3"1/C 10 AWG/T3 4 Current-Phase A 3-1/C 10 AWG/T3 Current-Phase B 3-1/C 10 AWG/T3 6 Current-Phase C 3-1/C 10 AWG/T3 7' Voltage 2/C 16-AWG/C1 Current 2/C 16 AWG/C1 9> Voltage 2/C 16 AWG/C2 10 Current 2/C 16 AWG/C2
11. Skipped N/A 12 Current Fault Cable/Tl WYLE LABORATORIES Huntsville Facility

Page No. VI-34 Test Repor t No. 47879-02 Page No. 33 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3'.6 Configuration Number-3 Tests (Continued) 3.6.3.2.2 Test No. 2 Channel No. Si Cable/Location Voltage A-B 3-1/C 10 AWG/T3 Voltage A-C 3"1/C 10 AWG/T3 Voltage B-C 3-1/C 10 AWG/T3 Current-Phase A 3-1/C 10 A WG/T3 Current-Phase B 3-1/C'10 A WG/T3 Current-Phase C 3-1/C 10 AWG/T3 Voltage A-B 3-1/C 10 AWG/Tl Voltage A-C 3-1/C 10 AWG/Tl Voltage B-C 3-1/C 10 AWG/T1 10 Current-Phase A 3-1/C 10 AWG/T1 11 Current-Phase B 3-1/C 10 AWG/T1 12 Current-Phase C 3"1/C 10 AWG/T1 OscB1 h No. 2 Channel No. S Cable/Location Voltage 2/C 16 AWG/C1 Current 2/C 16 AWG/C1 Voltage 2/C 16 AWG/C2 Current 2/C 16 AWG/C2 5-8 Skipped N/A Current Fault Cable/T2 10-11 Skipped N/A WYLE LABORATORIES Huntsville Facility

Page No. VI-35 Test Repor t No. 47879-02 Page No. 34 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3;6 Configuration Number 3 Tests (Continued) 3.6.3.2.3 Test. No. 3 OscBl h No. 1 Channel No. Cable/Location Voltage A-B 3-1/C 10 AWG/T3 Voltage A-C 3-1/C 10 AWG/T3 Voltage B-C 3-1/C 10 AWG/T3 Current-Phase A 3-1/C 10 AWG/T3 Current-Phase B 3-1/C'0 AWG/T3 12'i Current-Phase C 3-1/C'0 AWG/T3 Voltage A-B 3-1/C'10 AWG/T1 8 Voltage A-C 3-1/C 10 AUG/T1 9 Voltage B-C 3-1/C 10 AUG/T1 10 Current-Phase A 3-1/C 10 AWG/Tl 11 Current-Phase B 3-1/C 10 AWG/T1 Current-Phase C 3-1/C 10 AWG/T1 Oscill h No. 2 Channe1 No. Si Cable/Location Voltage 2/C 16 AWG/Free A'ir Current 2/C 16 AWG/Free Air 3-8 Skipped N/A Current Fault Cable/T3 10-11 Skipped N/A A digital'ultimeter shall be utilized to measure all phase-to-phase or phase voltages and phase currents of the target cables prior to, during, and after the Overcurrent Test. This data shall be recorded to provide accurate evidence of the specimen's capability to conduct rated current at 480 VAC (power cable) or 120 VAC (control cables) throughout the Overcurrent Test. WYLE LABORATORIES Huntsville Facility

Page No. VI-36 Test Report No. 47879-02 Page No. 35 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.6 Configuration Number 3 Tests (Continued). 3.6.4 Baseline Functional Tests The baseline functional tests shall consist of insulation resistance and high potential measurements on each of the target cables. These tests shall be performed as described below: 3.6.4.1 Insulation Resistance Test

1. Disconnect all power and instrumentation leads from the target cables.
2. Using, a megohmmeter, apply a potential of 500 VDC and record the minimum insulation resistance indicated after a period of 60 seconds between the following test points:

Tar et Power Cable Phase-to-Phase Phase-to-Ground 1to2 1 to tray lto3 2 to tray 2 to 3 3 to tray Tar et Control Cable Phase-to-Phase Phase-to-Ground 1to2 1 to conduit 2 to conduit all performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.1, i.e., greater than 1.6 x 10 ohms. 3.6.4.2'or Hi Potential Test

l. Using a Hi-Pot Test Set, apply a potential of 2200 VAC and record the leakage current observed afteI a period of 60 seconds between the following test points:

Tar et Power Cable Phase-to-Phase Phase-to-Ground 1to2 1 to tray 1to3 2 to tray 2to3 3 to tray WYLE LABORATORIES Huntsville Facility

Page No. VI-37 Test Report No. 47879-02 Page No. 36 Test Procedure No. 47879-01, Revision A 3.0 PROGRAM'Continued) 3.'6 ConQguration Number 3 Tests (Continued) 3.6.4.2'EST Tar et Control Cable Phase-to-Phase Phase-to-Ground 1to2 1 to conduit 2 to conduit

2. Reconnect aQ power and instrumentation leads to the target cables.

For all performances of this test, the measured values shall be compared to the acceptance criteria, Paragraph 2.1.2, i.e., there shall be no evidence of insulation breakdown or flashover. 3.6.5 Overcurrent Test The Overcurrent Test shall be conducted in two sequential phases with no intentional time delay. The first phase consists of a warmup period with the fault cable current slowly increased to achieve conductor temperatures of 90 C

        +5 C. The second phase consists of energizing the fault cable with the test current until the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request. The three adjacent cables (to the fault cable) shall be energized at rated current and the target cables shall be energized at rated current and 480 VAC or 120 VAC throughout the Overcurrent Test. The Overcurrent Test shall be conducted using the following procedute:
1. Connect the Triplex 350 NCM fault cable to the copper bus bars per Figures 6A, 6B, 6C, and 7, as applicable.
2. Install 2/C 16 AWG and 3-1/C 10 AWG target cables in the target cable raceways per Figures 6A, 6B or 6C, as applicable.
3. Install nine 1/C 6 AWG (Test 1) or 1/C 2 AWG (Tests 2 and 3) cables A adjacent to the fault cable per Figures 6A, 6B or 6C, as applicable.
4. Connect the 10 AWG target cables to the instrumentation and power supplies of Figure 9.
5. Connect the 2/C 16 AWG cables to the instrumentation and power supplies of Figure 10.
6. Connect the nine adjacent cables to the power supply per Figure 8.

WYLE LABORATORIES Huntsville Faclllty

Page No. VI-38 Test Report No. 47879-02 Page No. 37 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) Configuration Number 3 Tests (Continued) 3;6'.6;5 Overcurrent Test (Continued)

7. Energize the 2/C 16 AWG target cables with 10 amperes at 120 VAC.
8. Energize the 3-1/C 10 AWG target cables with 40 amperes at 480 VAC.
9. Energize the nine 1/C 6 AWG (Test 1) or 1/C 2 AWG (Tests-2 and 3) cables, A adjacent to the fault cable, with 75amperes (Testl) or 100amperes (Tests 2 and 3) at reduced voltage.

10.. Energize the Triplex 350 MCM fault cable with 350 amperes (rated current) from the Multi-Amp Test Set.

11. Record target cable voltage and current, fault cable current and initial conductor temperature, and adjacent cable current and initial conductor temperature.
12. Slowly incr ease fault cable and adjacent cable curr ents to achieve conductor temperature of 90 C+5 C for a Period of 15 minutes.
13. Record target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures.
14. Increase the Triplex 350 iVICM fault cable current to 4200 amperes (test current).
15. Record target cable voltage and current, fault cable current and conductor temperature, and adjacent cable current and conductor temperatures.
16. Allow the fault cable to conduct 4200 amperes until either the cable open-circuits, temperatures stabilize or decrease, or the test is terminated at the customer's request.
17. Record time to ignition, open-circuit, or stabilized temperature as applicable.
18. Record target cable voltage and current and adjacent cable current and conductor temperatures.
19. De-energize the target cables, adjacent cables, and the Multi-Amp Test Set.
20. Photograph the post-test conditions.

WYI.E LABORATORIES Huntsville Facility

Page No. VI-39 Test Report No. 47879-02 Page No. 38 Test Procedure No. 47879-01, Revision A 3.0 TEST PROGRAM (Continued) 3.'6i ConQguration Number 3 Tests. (Continued) 3.6.5 Overcurrent Test (Continued) For. all performances of this test, the observed target cable operation shall be compared to the acceptance criteria, Paragraph 2.1.3, i.e., they shall maintain continuity of power. 3.6.6 Post-Overcurrent Test Functional Test The functional tests of Paragraph 3.6.4 shall be repeated on the target cables. 3.7" All test equipment and instrumentation to be used in the performance of this test program will be calibrated in accordance with Wyle Laboratories'Eastern Operations) Quality Assurance =Program Manual, which conforms to the applicable portions of ANSI N45.2, 10 CFR 50 Appendix B, 10 CFR 21, and ttiiilitary Specification MIL-STD-45662. Standards used in performing all calibrations are traceable to the National Bureau of Standards. , Report'en copies of the test report and one reproducible copy shall be issued, describing the test requirements, procedures, and results. The report shall be prepared in accordance with the requirements of Section 8, Documentation, of IEEE Std. 323-1974, as applicable. WYLE LABORATORIES Huntsville Facility

Page No. VI-40 Test Report No. 47879-02 Page No. 39 Test Procedure No. 47879-01, Revision A + BuS BAg Su.ppaRV (33S)

                                ~/g" x 4-   Coppec'us      PA@

I"x I" x 3/8" sI ~cW

                               ~  x6" l8" NM<~i+t               Gu. pf'I       TIE  COROS II TW, PR.

TYPE "K" THERMO-16 Il AWG TARGET,

                                                  ~COUPLES h10UNTEO 6 II EVERY 12" o     CABLE I

II 4" x 3/8" II II COPPER BUS BAR il 6] II II 0 COPPER 12 BUS BARS FIGURE 4: CONFIGURATION NO. 1 TEST SETUP

Page No. YI-44 Test Report No. 47879-02 Page No. 43 Test Procedure No. 47879-01, Revision A =**TARGET CABLE CONDUITS 10 FEET LONG FOR TEST 1 AND 7 FEET LONG FOR TESTS 2 AND 3. FAULT CABLE CONDUITS 10 FEET LONG FOR TESTS 2 AND 3. uul5~ eu.p pc455 1 I l O

                                                 ~~s Ill I"
                                                )f II CONDUITS/CABLE. SEPARATED         Idyll BY )Ou  B'UT   ~j/4u FRONT VIEW                                               TOP VIEW TEST NO.         LOCATION    1                        LOCATION 2                 LOCATION
     'l        FLEX  - 2/C 14              1" RIGID STEEL      - 3 1/C 10    fREE AIR  - WCC 2      FREE AIR - 2/C 14              FLEX    - 3  1/C 10               3" RIGID STEEL -  WCC 3      1" RIGID STEEL - 2/C 14        1" FREE AIR - 3 1/C 10            3" FLEX - WCC FIGURE   5:  CONFIGURATION 2 TEST SETUP

Page No. VI-45 Test Report No. 47879-02 Page No. 44 Test Procedure No. 47879-01, Revision A 3-1/C 10 AWG TARGET CABLE Cl ADJA ENT CABLES FAULT CABLE T3 FAULT CABLE Tl oc)c)oooooooo oPo 00 OOOo oOoooo Cl 0 Ooo C2 T3 OQ Oo

                 .1"                                                                         i%I SEPARATION Fo pO OP 36 II                                                                                         000 000 1" RIGID                         o00 ALL TRAYS FILLED TO TOP                           STEEL CONDUIT OF SIDERAILS                                   llITH 2/C 16 AWG TARGET CABLE T2 QQOQ o ae Oo  ooo ooooo  do gp          oo oooo 24"                  12"                24"   X 4" X 96" CABLE TRAY FRONT VIEW                                          TOP VIEW FIGURE 6A. CONFIGURATION 3 TEST NO. 1  SETUP

Page No. VI-46 Test Report No. 47879-02 Page No. - 45 Test Procedure No. 47879-01, Revision A ALL TRAYS FILLED TO T3 Cl TOP OF SIDERAILS FAULT CABLE IN T2 Tl OOOQ 0 OQO Oe 0 00000<@ 0

                                      'o00<O T3 3-1/C 10      AWG'ARGET CABLE                                             1" HORiZONTAL                    000 Opp.

S EPARAT ION C2 Op o 1" RIGID STEEL CON-00 DUIT WITH 2/C 16 AMG pp0 TARGET CABLE 3-1/C 10 AWG TARGET CABLE FAULT CA LE ADJACENT CABLES T2 ooaaooaoo~o. oooo@ QoGoc 9 Odooo o Cl 12" 24" X 4" X 96" 24 I I TRAY FRONT VIEW TOP VIEW FIGURE 6B. CONFIGURATION 3 TEST NO. 2 SETUP

Page No. VI-47 Test Repor t No. 47879-02 Page No. 46 Test Procedure No. 47879-01, Revision A ALL TRAYS FILLED TO TOP OF S IDERAILS I I I I Tl d <OOOOO QQC)Oat 1

     <QQ OOOO'Po       pock                      l T3 I

I 0+0 3-1/C 10 AWG 0O TARGET CABLES o(>(' I I 2/C 16 AWG I FREE AIR CABLF Q II 2/C 16 AWG I FAULT CABLE opt) 36 FREE AIR CABL OPO OOO ADJACENT CABLES Ooa I 00 12'3 T2 I ocoeoocoogQ OO

      <GOO'OOO Oo            ocPo 0 op                      I 24"                             I        24" X  4" X 96" TRAY FRONT VIEW                                        TOP VIEW FIGURE 6C. CONFIGURATION 3 TEST NO. 3 SETUP

Fault Cable in Tray, Conduit, or Free Air K

                                                                                                 'tS 0

O To Hul ti- g, 'tf amp Test 1/4" x 3/8" x 100" Copper Bus Bar lD Set FQ 0 0

  • The three phases of the fault cable shall be connected in series. Thermocouples 9 and 10 mounted at the series connection.
                        "-~  The fault cable shall be wrapped with a single layer of Siltemp I:T No. 65 covered with 3N No.

69 glass tape from the edge of the test area to the bus bar. FIGURE 2: TYPICAL FAULT CABlE CONNECTIONS

                                +       "K" TYPE     THERMOCOUPLES tlOUNTED AT SERIES CONNECTIONS 15A VARIAC CURRENT XMFR R,M C

m QQ 2l O O Z

                                                                                         -+  BRIBE HUT CONNECTORS  M    OO CO I
                                                                                                       %0 A

C I 0 0 + 0 O ~'

                                                                                                                ~ UQ(D Z40 O

FIGURE 8: TYPICAL ELECTRICAL CONNECTIONS FOR ENERGIZED CABLES ADJACENT TO TNE FAULT CABLE A oo ( < CD CD I CD

A .1/4A 480 VAC Input 8 480 vAc

  • PT3 PT = Potential 1/4A Trans former I:.

480 VAC 1/4A 3 11 Variac 3 Phase Transformer 8'Y Transformer CD

                                                                          *   *To Oscil lograph Recorder 0

CD Set to Rated CD Pov>er Cabl e Current CD CD 480 VAC input 0 0 lg Variac Trans former M CD OD 1 CD Set to Rated 0 I CO Current 480 VAC CII Input 0 Eight Type "K" Thermocouples CD Mounted to Cable Jacket Set to Rated Current 480 YAC O Input rt (g CD Current Trans forIIer g4 0 0 FIBuRE 9: FLECTRICAL CONNECTIONS FOR ENERGIZEn POWER CABLE

                                                                                                                                     ~I
                                                                                                                                 ~o OO
                                                                                                                                 ~I

2/C 14 Al<G TARGET CABLE 1 EIGHT TYPE "K" THERMOCOUPLES I1OUNTED TO CABLE JACKET 15A I w QR (b

                        ~TRANSFORMER POTENTIAL                                                      44 0 0 120 VAC SET TO  10 ANPS I

CURRENT TRANSFORMER e (D 5'

+ TO OSCILLOGRAPH RECOROER lO tD O (g m   tb w4  l4 0 0 FIGURE   10:   ELECTRICAL CONNECTIONS FOR TYPE C CABLES                               00 I~
                                                                                                    ~l I

C) t4

Page No. VI-52 Test Report No. 47879-02 Page No. 51 Test Procedure No. 47879-01, Revision A UJ C O Rl K UJ UJ Y IC (D UJ r YC CC C CD I D I O UJ IC ~ CD (/l I CA CD UJ O (0 C CY gp I U (JJ UJ I X C UJ O D M I yC

            )

CD LA A CU VO C O CD O UJ I R 0

tt4 ~ i

     ~     o ~ ~ it4  ~ ~ ~ 4 1 i4 ii1 i4 i ii
                                         ~       4 4 ~ ii ~ 4 ~ i ~ 4 ~ 4 i ii
                                                                            ~     ~ ~ 4 II~   ~ iii ~ 4 ~ i C      I\4   ~ ~ 4 tat 4l
                                                                                                                                    ~     ~ 4444404      ~ i ~ 4101 ~ ~ ~ ~ 01 ~ ~ ~ ~ i ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ I l I           ~ ~ ~ ~ ~ ~

12/02 IIUT6CI I/ I'A I l>h>>j: i 4 QUtlIY IIESPOIISE ALPOfIT Cpa.L IIAARIS AEL1 EF AEQUEST A I-00 +ii++++i' i ~ i+ ~ ~ ~ ~ ~ ~ 0i ~ i ~ I ~ ~ Iii\44 ~ 4i ~ 44i 4I ~ I: 4i4 ~ i ~ ~ i bi i ii COMPOIIEIIl'S AEQUES TEO FOR RELIEF j j ii41 4i ~ ~ ~ ~ 0 ~ 4 ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

                                                                ~       ~ ~ ~ 4 ~ i ~ 4 4 ~ 4 4 ~              ~   ~ ~ ~   ~ ~ ~ ~    ~ ~ ~ ~ ~ ~ ~  ~   ~ ~ ~ ~      ~ ~ ~                                              ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

COMPXOEX SYSTEM COMPOES CATEGORY ITEMNO EXSCHO EXAEQ 11-SI-022SI-SW-DS Sl PF LR -PC PIPE U-J AO.II UT-83S PO I-O I ISO Meld System Component Descript.ion Exam Required Number Number See (h To B) See Tah 9 See See Tab 5 See Tab 6 Tab Tab 2 6 3 Section XI Category or Section XI Item Ho. or Exam Requirement Source invented augmented invented Item No. to fit a) ANN-NN category to Section XI format fit Section XI format Interval Program Number Number Example for Aug~anted: Type of Program Example for Augmented: 6.6.8B FSAR See Tab 8 Example I P01 "01 See Tab 7 Preservice Section XI Progra~ Interval - 1: Preservice is considered to he an interval for computer purposes. P02-01 Preservice Augmented Program B02"01 Inservice Augmented Program corresponding to P02-01 b) 81M-01 Interval Humber Code Addendum for Inservice Program See Tab 10 8601130340-

CAROLINA POWER IL LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-001 PRESERVICE EXAHINATION PROGRAH REQUEST FOR RELIEF FROH ASHE SECTION XI SYSTEHS CODE REQUIREHENTS COHPONENTS OR ITEN ASHE XI CODE CODE CODE CLASS CATEGORY ITEN PRESSURE RETAINING PIPING WELDS CLASS 1 8-J B9. 11 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREHE TS: ASHE Section XI, Table IWB-2500-1 requires surface and/or volumetric examinations to be performed as applicable on pressure retaining welds. RELIEF RE VESTED: Relief is requested from examinations on Class 1 pressure retaining welds due to structural interferences such as: permanent hangers, saddle plates, support structures, or intervening members for other systems. ALTERNATE EXAMINATIO S: To the maximum extent possible volumetric examinations were performed. Where the weld was identified as being inaccessible to the volumetric examination, surface examinations were used in lieu of the volumetric examinations. Visual examinations (VT-1) were performed on components which required surface examination, when accessible. Where access precluded or limited the examination, that fact was documented on the Preservice Baseline Data Sheet.

CAROLINA POWER L LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-002 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM PRESSURE RETAINING PIPING WELDS CLASS 1 F-C F3. 50 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREME TS: Table IWF-2500-1 defines the testing and inspection criteria for snubbers. RELIEF RE VESTED: Relief is requested from the functional test requirements for snubbers per article IWF-5000. ALTER ATE EXAMINATIO All Shearon Harris component support snubbers will be selected, inspected, and functionally tested per Section 3/4.7.8 of the Shearon Harris Technica I Specifications.

CAROLINA POWER 8c LIGHT SNEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-003 PRESERV ICE EXAHI NAT ION PROGRAM REQUEST FOR RELIEF FROM ASHE SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY I TEH .PRESSURE RETAINING PIPING WELDS CLASS 1 8-J B9. 11, B9.31 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREME TS: ASHE Section XI, Table IWB-2500-1 requires volumetric and surface examinations on ~ 4" nominal pipe size circumferential and longitudinal pressure retaining welds, including branch connections. RELIEF RE UESTED: ASHE Section XI requires essentially 100/ of the weld length be volumetrically examined. Due to piping weld configurations ( reducer to tee, pipe to tee, pipe to flange etc.) volumetric examinations of 100$ of the weld length was sometimes not feasible. Relief "A" is requested based on weld configurations not being conducive to 100$ volumetric examination ( see additiona I deta I Is on Attachment to this relief request). ALTER ATE EXAHI ATIO Pressure reta ining welds were surface examined for essentially 100$ of the weld length where possible. Volumetric examinations were performed to the maximum extent possible on physical limitations. Where the component configuration or access precluded or limited this examination, that fact and to the extent was documented on the Preservice Baseline Data Sheet.

Attachment A Page 1 of 2 RELIEF REQUEST NO: Rl-003 EXAMINATIONS Ultrasonic examinations were conducted to inspect as much of the examination zone as was practical, within geometric, metallurgical, and physical limitations. When the required ultrasonic examination volume or area could not be examined 100 percent, the examination was considered to be partial and was so noted on the applicable component Data Sheet. Generally, partial examinations were done at fitting to fitting assemblies (explained under limitations) and in areas where integrally welded supports, lugs, etc., preclude access to some part of the examination area. Ultrasonic examinations that produced indications 50 percent of DAC or greater from geometric or metallurgical origin were recorded. Examples of areas that generally produced such indications are as follows:

1. Inside diameter weld preparation or root configuration and the outside diameter down overlay or toe.
2. The inside diameter radius of the tube sheet weld of the steam generators where examined from the tube sheet side.
3. The metallurgical structure of austenitic materials.
4. Signal responses from the thread areas of bolting.

LIMITATIONS Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examinations requirements of Section XI of the 1980 Code could be applied; consequently, some examinations are limited or not practical due to geometric configuration or accessibility. Generally these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length. The limitations exist to a lesser degree at pipe to fitting assemblies, particularly where the weld is not ground flush with the pipe O.D. surface. At these joints examinations can be conduced from the pipe side; however, the fitting again limits precludes examination from the opposite side. In most cases, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code required area or volume (generally,'the weld and base metal of 1 "T" on each side) as possible. However, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100 percent. These areas where complete examination of 100 percent of the required volume of area could not be achieved were indicated and noted to the extent on the examiner's Data Sheet, and the limiting cause noted.

Attachment A Page 2 of 2 RELIEF REQUEST'NO: R1-003 The principal basis for partial examinations is to identify the inability to .examine 100 percent of the, required base metal volume for the 1 "T" distance beyond the edge of the weld on a fitting or component. Examples are (1) ultrasonic examination of a pipe to elbow assembly, where scanning on the intrados of the elbow causes de-coupling of the sound beam and (2) a pipe to flange or valve assembly where scanning the entire volume on the fitting or component side is limited by configuration. The resulting coverage is such that examination of the weld, heat affected zone and base metal for 1 "T" on indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc. However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by code. In either case, 100 percent of this 1 "T" volume cannot be assured, thus a partial examination is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical. Specific limitations and restrictions for all examinations are as indicated on the specific report Data Sheet.

CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-004 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM PRESSURE RETAINING WELDS IN REACTOR VESSEL CLASS 1 8-A 81.11'1.21'1.40'1. 12, 81.22 PRESSURE RETAINING WELDS IN VESSELS OTHER THAN CLASS 1 B-B 82. 11, 82. 12, 82.40 REACTOR VESSEL ( PRESERVICE/INSERVICE APPLICABLE} CODE RE UIREMENT: Table IWB-2500-1 defines the volume of materia I which should be covered during the volumetric examinations. RELIEF RE UESTED: . In instances where component configuration or limited access resulted in the examination of less than 100%%u of the code required volume, a Iternate examination techniques were considered and if, feasible, used. ALTERNATE EXAMINATIO The ultrasonic examinations were performed to the maximum extent possible. Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of materia I not fully examined were defined.

CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-005 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASHE SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASHE XI CODE CODE CODE CLASS CATEGORY ITEM PUMP CASINGS CLASS 1 8" L-2 B12. 20 VALVE BODIES'XCEEDING 4 IN. NOMINAL PIPE SIZE CLASS 1 8"M-2 B12.50 ( PRESERVICE APPLICABLE) CODE RE UIREME T; ASME Section XI, Table IWB-2500-1 requires visual examinations (VT-3) be performed, as part of the Preservice Program, on the Internal surfaces of pump casings and valve bodies, exceeding 4 in. nominal pipe size. RELIEF RE VESTED: Relief is requested from the ASHE Section XI requirements for visual examinations (VT-3) of internal surfaces of pumps and valves. Disassembly of these components would not be practical as unnecessary damage may occur from the disassembly process. ALTERNATE EXAMINATIO S: Manufactures records will be utilized as the recorded condition of internal surfaces for Preservice. No relief Is requested for the Inservice Program.

i CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-006 PRESERVICE EXAMINATIOII PROGRAM REQUEST FOR RELIEF FROH ASME SECTION XI SYSTEMS CODE REQUIREMENTS COHPONENTS OR ITEM ASHE XI CODE CODE CODE CLASS CATEGORY ITEM FULL PENETRATION WELDS OF NOZZLES IN VESSELS CLASS 1 B-D B3. 110, 83. 120

83. 9, B3. 130 PRESSURE RETAINING DISSIMILAR METAL WELDS CLASS 1 B-F 85.40

( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREMENT: Table IWB-2500-1 defines the volume of material which should be covered during the volumetric examinations. ,RELIEF RE'ESTED: In instances where component configuration or limited access resulted in the examination of less than 100$ of the code required volume, alternate examination techniques were considered and, if feasible, used. ALTERNATE EXAMINATIO The ultrasonic examinations were performed to the maximum extent possible. Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of mater ial not ful ly examined were defined.

CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-007 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASHE SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASHE XI CODE CODE CODE CLASS CATEGORY ITEM PRESSURE RETAINING PIPING WELDS CLASS 1 8-J 89. 31 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREHENT: ASME Section XI, Table IWB-2500-1 requires volumetric and surface examinations of 4" nominal pipe size circumferential and longitudinal pressure retaining weld, including branch connections. RELIEF RE VESTED: Re lief is requested for performing u I trason ic examination on branch connections with nozzle weld configurations not conducive to volumetric examinations. These nozzle welds are on line RC27$ -6SN ( ISO: 1- ISI-FW-HS-RC-2) and line: RC275-3SN ( ISO: 1-ISI-FW-HS-RC-l), and are identified on attached computer listings. ALTERNATE EXAMINATIO These pressure retaining welds were surface examined for essentially 100$ of the weld length where possible.

                                                                                 ,                                        These welds will be subjected to hydrostatic as well as leakage pressure tests on periodic intervals.

CAROLINA POWER Ec LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-008 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM INTEGRAL ATTACHMENTS FOR VESSELS CLASS 1 B-H B8.20 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREME T: ASME Section XI, Table IWB-2500-1 requires volumetric or surface examinations, as applicable on integrally welded attachments for vessels. Examinations are limited to attachment weld joining the attachment to the pressure retaining membrane of the components and where the attachment base material design thickness is 5/8 in. or greater. RELIEF RE VESTED: ASME Section XI requi red essentially 100% of the length of the weld be examined. Due to the design of some Integral attachments, examination of 100% of the weld length was sometimes not feasible. Relief is requested based on weld configuration not being conducive to 100% surface or volumetric examination, as applicable. ALTER ATE EXAMINATIO Integral attachment welds for vessels were surface examined for essentially 100% of the weld length where possible. Where the component configuration or access precluded or limited this examination, that fact and to the extent was documented on the Preservice Baseline Data Sheet.

CAROLINA POWER Ec LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-009 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM PRESSURE RETAINING BOLTING, 2IN. AND LESS CLASS 1 B-G-2 B7. 60 IN DIAMETER (PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREME T: ASME Section XI, Table IWB-2500-1 requires a visual examination (VT-1) on al I pressure retaining bolting 2 in. and less in diameter, located on Class 1 components. Bolting may be examined; in place under tension, when the connection is disassembled or when the bolting is removed. RELIEF RE VESTED: Relief is requested from visual examination (VT-1) on two (2) capscrews that are covered by the reactor coolant pump shaft proximity probe mount, and are not accessible for examination. This condition exist on a II three (3) reactor coolant pumps. Tota I of six (6) capscrews that are not accessible. ALTER AT EXAMINATIO Should the reactor coolant pumps be disassembled for other activities, the inaccessible capscrews will be examined (VT-1). In addition, the reactor coolant pumps are subject to hydrostatic tests and system leakage tests.

CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-001 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM PRESSURE RETAINING PIPING WELDS CLASS 2 C-C C3.20 C" F C5. 12'5.32 ( PRESERVICE/INSERVICE APPLICABLE) C5 ~ 21p C5.11 CODE RE UIREMENTS: ASME Section XI, Table IWC-2500-1 requires surface and/or volumetric examinations to be performed as applicable on pressure retaining welds, and surface examinations on welded pipe attachments (WPA's) meeting the design criteria for examination of IWC-2500-1. RELIEF RE VESTED: Relief is requested from examinations on Class 2 pressure reta ining welds and/or welded pipe attachments (WPA') due to structura I interferences such as: permanent hangers, saddle plates, support structures, or intervening members for other systems. ALTERNATE EXAMINATION: To the maximum extent possible volumetric examinations were performed. Where the weld was identified as being inaccessible to the volumetric examination, surface examinations were used in lieu of the volumetric examinations. Visual examinations (VT-1) were performed on components which required surface examinations, when accessible. Where access precluded or limited the examination, that fact was documented on the Preservice Baseline Data Sheet.

CAROLINA POWER L LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-002 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASHE XI CODE CODE CODE CLASS CATEGORY ITEM COMPONENT SNUBBERS CLASS 2 F" C F3. 50 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREME T: Table IWF-2500-1 defines the testing and inspection criteria for snubbers. RELIEF RE VESTED: Relief is requested from the functional test requirements for snubbers per article IWF-5000. ALTERNATE EXAMI ATIO Al I Shearon Harris component support snubbers wil I be selected, inspected, and functiona I ly tested per Section 3/4.7.8 of the Shearon Harris Technical Specifications.

0 CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-003 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASHE SECTION XI SYSTEMS CODE REQUIREMENTS COHPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM PRESSURE RETAINING PIPING WELDS CLASS 2 C-F C5.21'5. 11 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREME T: ASHE Section XI, Table IWC-2500-1 requires volumetric and surface examinations on circumferential and longitudinal pressure retaining welds, including branch connections. RELIEF RE VESTED: ASHE Section XI requires essentially 100$ of the weld length be volumetrically examined. Due to piping weld configurations ( reducer to tee, pipe to tee, pipe to flange, etc.) volumetric examinations of 100%%u of the weld length was sometimes not feasible. Relief is requested based on weld configurations not being conducive to 100$ volumetric examination ( see additional details on Attachment "A" to this relief request). ALTER ATE EXAMI ATION: Pressure retaining welds were surface examined for essential ly 100$ of the weld length where possible. Volumetric examinations were performed to the maximum extent possible based on physical I imitations. Where the component configuration or access precluded or I imited this examination, that fact and to the extent was documented on the Preservice Basel lne Data Sheet.

Attachment A Page 1 of 2 RELIEF REQUEST NO: R2-003 EXAHINATIONS Ultrasonic examinations were conducted to inspect as much of the examination zone as was practical, within geometric, metallurgical, and physical limitations. When the required ultrasonic examination volume or area could not be examined 100 percent, the examination was considered to be partial and was so noted on the applicable component Data Sheet. Generally, partial examinations were done at fitting to fitting assemblies (explained under limitations) and in areas where integrally welded supports, lugs, etc., preclude access to some part of the examination area. Ultrasonic examinations that produced indications 50 percent of DAC or greater from geometric or metallurgical origin were recorded. Examples of areas that, generally produced such indications are as follows:

1. Inside diameter weld preparation or root configuration and the outside diameter down overlay or toe.
2. The inside diameter radius of the tube sheet weld of the steam generators where examined from the tube sheet side.
3. The metallurgical structure of austenitic materials.
4. Signal responses from the thread areas of bolting.

LIHITATIONS Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examinations requirements of Section XI of the 1980 Code could be applied; consequently, some examinations are limited or not practical due to geometric configuration or accessibility. Generally these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length. The limitations exist to a lesser degree at pipe to fitting assemblies, particularly where the weld is not ground flush with the pipe O.D. surface. At these joints examinations can be conduced from the pipe side; however, the fitting again limits precludes examination from the opposite side. In most cases, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code required area or volume (generally, the weld and base metal of 1 "T" on each side) as possible. However, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100 percent. These areas where complete examination of 100 percent of the required volume of area could not be achieved were indicated and noted to the extent on the examiner's Data Sheet and the limiting cause noted.

Attachment A Page 2 of 2 RELIEF REQUEST NO: R2-003 The principal basis for partial examinations is to identify the inability to examine 100 percent of the required base metal volume for the 1 T distance beyond the edge of the weld on a fitting or component. Examples are (1) ultrasonic examination of a pipe to elbow assembly, where scanning on the intrados of the elbow causes de-coupling of the sound beam and (2) a pipe to flange or valve assembly where scanning the entire volume on the fitting or component side is limited by configuration. The resulting coverage is such that examination of the weld, heat affected zone and base metal for 1 "T" on indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc. However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by code. In either case, 100 percent of this 1 "T" volume cannot be assured, thus a partial examination is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical. Specific limitations and restrictions for all examinations are as indicated on the specific report Data Sheet.

CAROLINA POWER K LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-004 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM, PRESSURE RETAINING WELDS LOCATED INSIDE OF CLASS 2 C-C C3.20 CONTAINMENT PENETRATIONS C-F C5. 11 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREME T: ASME Section XI, Table IWC-2500-1 requires surface and/or volumetric examination on circumferential and longitudinal piping welds. RELIEF RE UESTED: Relief is requested from ASME Section XI requirements as these welds are located inside of conta inment penetrations and are not physically accessible for examination. ALTER ATE EXAMI ATIO None. Hydrostatic tests and system leakage pressure tests will be performed as required by ASME Section XI requirements.

CAROLINA POWER & LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-005 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM PRESSURE RETAINING WELDS IN PRESSURE VESSELS CLASS 2 C-A C1.20, C1.10 C1.30 PRESSURE RETAINING NOZZLE WELDS IN VESSELS CLASS 2 C-B C2. 21, C2. 22 C-C C3. 10 CODE RE UIREMENT: ASME Section XI, Table IWC-2500-1 requires surface and/or volumetric examinations be performed on pressure retaining we lds and pressure retaining nozzle welds in pressure vessels. BASIS: In instances where component configuration or limited access resulted in the examination of less than 100$ of the code required volume, alternate examination techniques were considered and if, feasible, used. ALTERNATE EXAMINATIO The ultrasonic examinations were performed to the maximum extent possible. Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of material not fully examined were defined.

CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R3-001 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENTS OR ITEM ASME XI CODE CODE CODE CLASS CATEGORY ITEM COMPONENT SNUBBERS CLASS 3 F-C F3.50 ( PRESERVICE/INSERVICE APPLICABLE) CODE RE UIREM T: Table IWF-2500-1 defines the testing and inspection criteria for snubbers. RELIEF RE UESTED: Relief is requested from the functional test requirements for snubbers per article IWF-5000. ALTERNATE EXAMINATION: All Shearon Harris component snubbers wIII be selected, inspected, and functionally tested per Section 3/4.7.8 of the Shearon Harris Technlca I Specifications.

44f 444 44444444444444444444444444444444444444414444444444444 44444444444444 12/02xs5 NUTECH/PRI iM 4 QUERY RESPONSE REPORT CP8L HARRIS RELIEF REQUEST R1-001: COMPONENTS REQUESTED FOR RELIEF 44444444444444444444444444444t444444444444444444444444444444444444O444444t40O44444 444444444444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SI-02251-SW-DS SI PE, LR -PC, PIPE B-J 89.11 UT-53S P01-01

44 444444444444044444444444444444444t4444444444444444444 44444444444 444444444444444444444444440444444444444444 4 12/05/ NUTECH/PRIS PAGE: QUERY RESPONSE REPORT CPSL-HARRIS RELIEF REQUEST Rl-003: COMPONENTS REQUESTED FO R RELIEF 4et+t4444444t44444044444%844i88440444444444444044444444444444444444444ftt4444444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-CS-007SI-FW-25 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 II-FMR-01RC-10-17-FW-2 RC PE,RED -VNOZ1AI 8-J 89. 11 UT-45L Po1-01 I I-FMR-01RC-10-17-FW-3 RC VNOZ1AO-PE,LR 8-J 89.11 UT-45L Po1-01 I I-FMR-01RC-10-17-FW-8 RC PE,LR -VNOZ1AI 8-J 89.11 UT-45L Pol-01 I I -FMR-01RC-10-17-SW-L2 RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L P01-01 I I-FMR-01RC-10-17-SW-L3 RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L P01-01 I I-FMR-01RC-10-17-SW-PS RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L Pol-01 I I-FMR-01RC-10-17-SW-PB RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L Po 1-01 I I -FMR-02RC-10-18-FW-2 RC PE,RED -VNOZ1BI 8-J 89. 11 UT-45L P01-01 I I-FMR-02RC-10-18-FW-3 RC VNOZ180-PE,LR 8-J 89. 11 UT-45L P01-01 I I -FMR-02RC-10-18-FW-8 RC PE,LR -VNOZ1BI 8-J 89. 11 UT-45L P01-01 I I-FMR-02RC-10-18-SW-K2 RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L Po 1-01 I I-FMR-02RC-10-18-SW-KB RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L Pol-01 I I-FMR-02RC-10-18-SW-LS PC,PIPE-PC,NOZ 8-J 89. 31 UT-45S P01-01 I I-FMR-02RC-10-18-SW-L7 RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45S Po 1-01 I I-FMR-03RC-10-19-FW-2 RC PE,RED -VNOZ1CI 8-J 89.11 UT-45L Pol-01 I I-FMR-03RC-10-19-FW-3 RC VNOZ1CO-PE,LR 8-J 89.11 UT-45L P01-01 I I-FMR-03RC-10-19-FW-5 RC VNOZ1CO-PC,PIPE 8-J 89.11 UT-45L Po 1-01 I I-FMR-03RC-10-19-FW-8 RC PE,LR -VNOZlCI 8-J 89.11 UT-45L Pol-01 I I-FMR-03RC-10-19-SW-N2 RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L Po 1 -0 'I I I-FMR-03RC-10-19-SW-N3 RC PC,PIPE-PC,NOZ 8-J 89. 31 UT-45L Pol-01 I I-FMR-03RC-10-19-SW-04 RC PC,PIPE-PC,NOZ 8-J 89. 11 UT-45S P01-01 I I -FMR-03RC-10-19-SW-05 RC PCrPIPE PCiNOZ 8-J 89. 11 UT-45L Po 1-01

44W444 44tf4ff4440 f4'4f444f44444444444f444444 44$ 444ft4444t44444444tS t44t44 12/05 cs5 NUTECH/PRI PAGE: 2 QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R1-003: COMPONENTS REQUESTED FOR RELIEF 444444444444444444444r4444444444444444444444444444444444444444444444444444444444444444444444444 44444444f 444444444444f 4444444444444444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-RC-009RC-FW-1 RC PC,NOZ -PC,PB 8-J 89. 11 UT-45S P01-01 II-RC-022RC-SW-A6 RC PE,LR -PC,PIPE 8-J 89. 11 UT-45S P01-01 II-RC-023RC-FW-322 RC PC,PIPE-PC,VLV 8-J 89. 11 UT-45S P01-01 Ii-RC-023RC-FW-323 PC,VLV -PC,PIPE 8-J 89. 11 UT-455 P01-01 II-RC-023RC-FW-325 PC,VLV -PC,PIPE 8-J 89. 11 UT-45S P01-01 II-RC-023RC-FW-326 RC PC,PIPE-PC,VLV 8-J 89. 11 UT-455 P01-01 II-RC-023RC-FW-327 RC PBCC,T -PC,PB 8-J 89. 11 UT-45S P01-01 II-RC-023RC-SW-84 RC PC,PIPE-PBCC,T 8-J 89. 11 UT-45S P01-01 II-RC-023RC-SW-85 RC PBCC,T -PC,PIPE 8-J 89. 11 UT-45S P01-01 II-RC-023RC-SW-86 RC PC,PIPE-PC,RED 8-J 89. 11 UT-455 P01-01 II-RC-023RC-SW-C13 RC PBCC,TR-PC,PIPE 8-J 89. 11 UT-45S P01-01 II-RC-023RC-SW-C9 PC,PIPE-PBCC,TR 8-J 89.11 UT-455 P01-01 Ii-RC-023RC-SW-D12 RC PBCC,T -PC,PIPE 8-J 89.11 UT-455 P01-01 II-RC-023RC-SW-DB RC PC,PIPE-PBCC,T 8-J 89.11 UT-45S P01-01 II-RC-023RC-SW-09 RC PBCC,T -PC,PIPE 8-J 89.11 UT-45S P01-01 II-RC-023RC-SW-E11 RC PC,PIPE-PBCC,T 8-J 89.11 UT-45S P01-01 II-RC-023RC-SW-E7 RC PBCC,T -PC,PIPE 8-J 89. 11 UT-455 P01-01 C II-RC-023RC-SW-EB RC PBCC,T -PC,PIPE 8-J 89. 11 UT-455 P01-01 II-RC-023RC-92-2-SW-1 RC PC,PIPE-PBCC,TR 8-J 89. 31 UT-45S P01-01 II-RC-024RC-FW-318 RC PBCC,T -PC,PIPE 8-J 89. 11 UT-45S P01-01 II-RC-025RC-FW-331 RC PC,NOZ -PC,PIPE 8-J 89. 11 UT-45S P01-01 II-RC-025RC-SW-A3 RC PC ~ PIPE PE LR 8-J 89. 11 UT-45S P01-01 II-RC-025RC-SW-A4 RC PE,LR -PC,PIPE 8-J 89. 11 UT-455 P01-01

tf44444444444444f44444444r4444444444444444444444f44 44f4444t44f444444444t4444444 4444444444444444444444444 444f44 12/05/a5 NUTECH/PRIS PAGE: QUERY RESPONSE REPORT CP8 L-HARRIS 4 RELIEF REQUEST R1-003: COMPONENTS REQUESTED FOR RELIEF 4 4 4 4 4 4 4 4 4 44 0 4 4 0 44 4 4 0 4 4 4 4 4 0 444 44 4 444O4444444444444 0 0 444 ff 444 4 0 t 0 4444 4444444 i t'0 f t 4 4 O4 4444'4444 44O 4 COMPNOEX SYSTEM COMPOES CATEGORY ITEMNO EXSCHD EXREQ II-RC-027RC-SW-A11 RC PC,PIPE-PF,WN 8-J 89. 11 UT-45S P01-01 II-RC-027RC-SW-812 PC,PIPE-PF,WN 8-J 89. 11 UT-45S PO 1-01 II-RC-027RC-SW-C3 RC PC,PIPE-PF,WN 8-J 89. 11 UT-45S P01-01 II-RH-009RC-FW-291 RC PC,PIPE-PC,VLV 8-J 89. 11 UT-50S P01-01 II-RH-009RC-FW-292 RC PCeNOZ -PCePIPE 8-J 89. 11 UT-505 P01-01 II-RH-009RC-SW-A4 RC PE,LR -PC,PIPE 8-J 89.11 UT-50S P01-01 II-RH-009RC-SW-AS RC PC,PIPE-PE,LR 8-J 89.11 UT-50S P01-01 II-RH-009RC-SW-A6 RC PE,LR -PC,PIPE 8-J 89.11 UT-50S PO 1-01 II-RH-009RH-FW-200 RH PC,PIPE-PC,VLV 8-J 89. 11 UT-SOS P01-01 II-RH-009RH-FW-204 RH PC,VLV -PC,PIPE 8-J 89. 11 UT-50S P01-01 I I-RH-010RH-FW-194 RH PC,PIPE-PC,VLV 8-J 89. 11 UT-535 P01-01 I I-RH-010RH-FW-198 RH PC,VLV -PC,PB 8-J 89. 11 UT-53S P01-01 I I-SI -017RC-FW-297 RC PC,PIPE-PBC,S 8-J 89. 11 UT-45S P01-01 II-SI-017SI-FW-604 SI PSW,VLV-PC,PIPE 8-J 89. 11 UT-45S P01-01 I I-S I-017SI-FW-605 SI PC,PIPE-PSW,VLV 8-J 89. 11 UT-455 P01-01 II-SI-021RC-FW-300 RC PC,PIPE-PC,NOZ 8-J 89. 11 UT-535 P01-01 I I-SI-021SI-FW-547 SI PC,VLV -PC,PIPE 8-J 89. 11 UT-505 P01-01 I I-SI-021SI-FW-549 SI PC,PIPE-PC,VLV 8-J 89. 11 UT-53S P01-01 I I-SI-021SI-FW-550 RC PC,VLV -PCoPIPE 8-J 89. 11 UT-SOS P01-01 II-SI-022RC-FW-301 RC PC,PIPE-PC,NOZ 8-J 89. 11 UT-53S P01-01 I I-SI-022SI-FW-551 SI PC,VLV -PC,PIPE 8-J 89. 11 UT-535 P01-01 II-SI-022SI-FW-553 SI PC,PIPE-PC,VLV 8-J 89. 11 UT-535 P01-01 II-SI-022SI-FW-554 RC PC,VLV -PC,PIPE 8-J 89. 11 UT-53S P01-01

444444 444444444444i884444444f444444444444f44444444f4t444404 44444444444444 444440t444444444444444444'444444444444444 12/03/ NUTECH/PR I 5 PAGE: 1 QUERY RESPONSE REPORT CP8 L-HARRIS RELIEF REQUEST Rl-004: COMPONENTS REQUESTED FOR RELIEF 444444444'44444444444488444444444444044444444444440444044j44444ir44444400044444444 40444444444444444444440004 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-PZR-01LSW-06 RC VLSW 8-8 82. 12 UT-00 F01-01 II-PZR-01LSW-06 RC VLSW B-B 82. 12 UT-45S Pol-01 II-PZR-01LSW-06 RC VLSW 8-8 82. 12 UT-605 Pol-01 II-PZR-01STHW-01 RC VSTHW B-B 82. 11 UT-00 P01-01 II-PZR-01STHW-01 RC VSTHW 8-8 82. 11 UT-45S F0 1-01 II-PZR-01STHW-01 RC VSTHW 8-8 82.11 UT-60S P01-01 II-PZR-01STHW-04 RC VSTHW 8-8 82.11 UT-00 Po 1 -01 II-PZR-01STHW-04 RC VSTHW 8-8 82.11 UT-455 P01-01 II-PZR-01STHW-04 RC VSTHW 8-8 82.11 UT-60S Pol-01 II-RV-001CHW-RV-17 RC VCHW 8-A 81. 21 UT-RVS P01-01 II-RV-001CSW-RV-02 RC VCSW 8-A 81. 11 UT-RVS P01-01 II-RV-001FTHW-RV-18 RC VFTHW 8-A 81. 40 UT-00 Po 1-01 I I-RV-001FTHW-RV-18 VFTHW 8-A 81.40 UT-455 P01-01 I I-RV-001FTHW-RV-18 RC VFTHW 8-A 81.40 UT-60S P01-01 I I-RV-001LSW-RV-05 RC VLSW 8-A Bl. 12 UT-RVS Pol-01 II-RV-001LSW-RV-06 RC VLSW 8-A 81. 12 UT-RVS Po 1 -01 II-RV-001MHW-RV-'ll RC VMHW 8-A Bl . 228 UT-RVS Pol-01 I I-RV-001MHW-RV-12 RC VMHW 8-A 81. 228 UT-RVS Pol-01 I I-RV-001MHW-RV-13 RC VMHW 8-A 81. 228 UT-RVS Pol-01 II-RV-001MHW-RV-14 RC VMHW 8-A 81. 228 UT-RVS P01-01 II-RV-001MHW-RV-15 RC VMHW 8-A 81. 228 UT-RVS Pol-01 I I-RV-001MHW-RV-16 RC VMHW 8-A 81. 228 UT-RVS P01-01 I I-RV-001STHW-RV"04 RC VSTHW 8-A Bl. 11 UT-RVS P01-01

44444444444444ff44444444t4ff84444t44t44444444440t44f4 4444400044444t 444444444444tt44444444444444444444444444 12/03 5 NUTECH/PRIS PAGE: 2 4 QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R1-006: COMPONENTS REQUESTED FOR RELIEF 4 444444444440404444t44044444'444444t4444444f44444f4440044404f44444444t40fktfOt440444 4444440444444444444444444444+444444444444444440044 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-PZR-0 INTHW-12 RC VNTVWO 8-DB 83. 110 UT-45S P01-01 I I-PZR-01NTHW-'1 2 RC VNTVWO 8-DB 83. 110 UT-605 P01-01 I I-PZR-01NTHW-13 RC VNTVWO 8-DB 83. 110 UT-00 P01-01 I I-PZR-01NTHW-13 RC VNTVWO 8-DB 83.110 UT-45S P01-01 I I-PZR-01NTHW-13 RC VNTVWO 8-08 83.110 UT-60S P01-01 I I-RV-001RVNOZAI-N-01 RC VNOZ 8-DB 83. 9S UT-RVS P01-01 II-RV-001RVNOZAO-N-06 RC VNOZ 8-DB 83. 9S UT-RVS P01-01 II-RV-001RVNOZBO-N-02 RC VNOZ 8-DB 83. 95 UT-RVS P01-01 II-RV-001RVNOZCO-N-04 RC VNOZ 8-DB 83. 95 UT-RVS P01-01 II-SG-001SGA-CLMWTHW-15 RC VMTHW 8-DB 83. 130 UT-00 P01-01 II-SG-001SGA-CLMWTHW-15 RC VMTHW 8-08 83. 130 UT-45S P01-01 II-SG-001SGA-CLMWTHW-15 VMTHW 8-DB 83. 130 UT-60S P01-01 II-SG-001SGA-CLNTVW-12 RC VNTVWO 8-DB 83. 130 UT-00 F01-01 II-SG-001SGA-CLNTVW-12 RC VNTVWO B-DB 83. 130 UT-45S P01-01 II-SG-001SGA-CLNTVW-12 RC VNTVWO 8-DB ~

83. 130 UT-60S P01-01 II-SG-001SGA-HLMWTHW-14 RC VMTHW 8-08 83. 130 UT-00 P01-01 II-SG-001SGA-HLMWTHW-14 RC VMTHW 8-DB 83. 130 UT-45S P01-01 II-SG-001SGA-HLMWTHW-14 RC VMTHW 8-DB 83. 130 UT-605 P01-01 II-SG-001SGA-HLNTVW-07 RC VNTVWI B-DB 83. 130 UT-00 P01-01 II-SG-001SGA-HLNTVW-07 RC VNTVWI 8-08 83. 130 UT-45S P01-01 II-SG-001SGA-HLNTVW-07 RC VNTVWI 8-DB 83. 130 UT-60S P01-01 II-SG-001SGB-CLMWTHW-15 RC VMTHW B-DB 83. 130 UT-00 P01-01 I I-SG-001SGB-CLMWTHW-15 RC VMTHW 8-DB 83. 130 UT-45S P01-01

0 ttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttttttttttttttttttttttttttttttttttttttttt tttttt 12/03 5 NUTECH/PRI PAGE: 3 QUERY RESPONSE REPORT CP8 L-HARRIS REQUEST R1-006: tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt RELIEF COMPONENTS REQUESTED FOR tttttttttttttttttttttttttttttttttttttttttttttttttt RELIEF COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I-SG-001SGB-CLMWTHW-15 RC VMTHW 8-DB 83. 130 UT-60S P01-01 I I-SG-001SGB-CLNTVW-12 RC VNTVWO 8-DB 83. 130 UT-00 P01-01 I I-SG-001SGB-CLNTVW-12 RC VNTVWO 8-08 83.130 UT-45S P01-01 II-SG-001SGB-CLNTVW-12 RC VNTVWO 8-08 83. 130 UT-60S P01-01 II-SG-001SGB-HLMWTHW-14 RC VMTHW B-DB 83. 130 UT-00 P01-01 II-SG-001SGB-HLMWTHW-14 RC VMTHW 8-DB 83. 130 UT-45S P01-01 II-SG-001SGB-HLMWTHW-14 RC VMTHW B-DB 83. 130 UT-60S P01-01 II-SG-001SGB-HLNTVW-07 RC VNTVWI 8-DB 83. 130 UT-00 P01-01 II-SG-001SGB-HLNTVW-07 RC VNTVWI B-DB 83. 130 UT-45S P01-01 II-SG-001SGB-HLNTVW-07 RC VNTVWI 8-08 83. 130 UT-60S P01-01 II-SG-001SGC-CLMWTHW-15 RC VMTHW 8-DB 83. 130 UT-00 P01-01 II-SG-001SGC-CLMWTHW-15 RC VMTHW 8-DB 83. 130 UT-45S P01-01 II-SG-001SGC-CLMWTHW-15 RC VMTHW B-OB 83. 130 UT-60S P01-01 II-SG-001SGC-CLNTVW-12 VNTVWO 8-DB 83. 130 UT-00 P01-01 II-SG-001SGC-CLNTVW-12 RC VNTVWO 8-DB 83. 130 UT-45S P01-01 II-SG-001SGC-CLNTVW-12 RC VNTVWO B-DB 83. 130 UT-60S P01-01 II-SG-001SGC-HLMWTHW-14 RC VMTHW 8-DB 83. 130 UT-00 P01-01 II-SG-001SGC-HLMWTHW-14 RC VMTHW B-OB 83. 130 UT-45S P01-01 II-SG-001SGC-HLMWTHW-14 RC VMTHW 8-DB 83. 130 UT-60S P01-01 II-SG-001SGC-HLNTVW-07 RC VNTVWI 8-08 83. 130 UT-00 P01-01 II-SG-001SGC-HLNTVW-07 RC VNTVWI B-OB 83. 130 UT-45S P01-01 II-SG-001SGC-HLNTVW-07 RC VNTVWI 8-DB 83. 130 UT-60S P01-01

4444444444444444444444t4444444444444444444444444444444 444t4444tt444444444444 12/03 5 NUTECH/PRI PAGE: 1 QUERY RESPONSE REPORT CPS L-HARRIS RELIEF REQUEST R'1-007: COMPONENTS REQUESTED FOR RELIEF 44444444444444f4f444444404444f4f444f440t44440044fftfffft44ft44440444044444 44404444tt4444t444444444f44444444440440444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I-FMR-01RC-10-17-SW-P4 RC PC,PIPE-PC,NOZ 8-J B9. 31 UT-455 P01-01 I I-FMR-02RC-10-18-SW-L4 RC PCoPIPE-PCoNOZ B9.31 UT-455 P01-01

44444t ++++444444444444444 4444444444444444444444444440444440 44444444440440400440 44044444444444444444044t444444444 444444 12/02 5 NUTECH/PRI PAGE: 1 QUERY RESPONSE REPORT CPS L-HARR I S RELIEF REQUEST R1-008: COMPONENTS REQUESTED FOR RELIEF S08444444+4404444444444444444 44444404444t44444444444440444444044444404444440044t44440444 44444444444444444444044444444444444444444444 COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I -P ZR-01 SBW-A 1A RC VI, PSB 8-H 88.20 MT P01-01 I I-PZR-01SBW-A18 RC VI, PSB 8-H 88.20 MT P01-01 I I-PZR-01SBW-AZA RC VI, PSB 8-H 88.20 MT P01-01 II-PZR-01SBW-A28 RC VI, PSB 8-H 88.20 MT P01-01 II-PZR-01SBW-A3A RC VI, PSB 8-H 88.20 MT P01-01 I I-PZR-01 SBW-A38 RC VI, PSB 8"H 88.20 MT P01-01 II-PZR-0 ISBW-A4A RC VI, PSB 8-H 88.20 MT P01-01 II-PZR-01SBW-A48 RC VI,PSB 8-H 88.20 MT P01-01

44+++++<44444444444444444444444444444404t44t444t444444 44444444444444 444444444444444444444444444'444444444444 444444 12/02i4$ 5 NUTECH/PR I S PAGE: 1 QUERY RESPONSE REPORT CPS L-HARRIS RELIEF REQUEST R1-009: COMPONENTS REQUESTED FOR RELIEF 4 ef444t+44f44444488f88448t48t84444t80444444ff004444444444f444444444f444fft444tf4 4444444440444444444444444444444444444444444444444t COMPNOEX SYSTEM COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-RCP-01RCPA-SBOLT(8) RC BPSB B-G-2 87. 60 VT-1 P01-01 II-RCP-01RCPB-SBOLT(8) RC BPSB B-G-2 87.60 VT-1 P01 01 II-RCP-01RCPC-SBOLT(8) RC BPSB B-G-2 87.60 VT-1 P01-01

4444444444444444444444 44444$ 444444444444444f 4444t4f O4 44444440444044448444444444 444444444444444444444444 4 4 4 '4 4 4 12/04 5 NUTECH/PRI PAGE: 1 QUERY RESPONSE REPORT CP8 L-HARRI5 4 RE) IEF REQUEST R2-001: COMPONENTS REQUESTED FOR RELIEF 44444444444444444444444444t44444 4444$ 444444444444444444444404444444440444444444444044444444444444 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4I il 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-AF-006AF-FW-245 AF PC,PIPE-PBCC,T FSAR 6.6.88 UT-45S P04-01 II-CS-001CT-SW-J3 CT PE,LR -PC.PIPE SER 250.1S PT P03-01 II-CS-001CT-SW-J3A CT PLSW,P SER 250. 1S PT P03-01 II-CS-006CS-SW-I4 CS PCeRED -PCiPIPE SER 250. IV UT-455 P03-01 II-CS-006CS-SW-J6 CS PC, PIPE-PC, PIPE SER 250. 1V UT-455 P03-01 II-CS-007CS-SW-A4 CS PC,RED -PC,PIPE SER 250.1V UT-45S P03-01 II-CS-021CS-FW-111A CS PLSW,P C-F C5. 12 PT P01-01 II-CS-021CS-FW-211A CS . PLSW,P C-F C5. 12 PT F01-01 II-CS-021CS-H-0011I(4) CS PC,PIPE-PI,LUGN C-C C3.20 PT P01-01 II-CS-021RH-SW-86A RH PLSW,P C-F CS. 12 PT P01-01 II-CT-007CT-FW-35A CT PLSW,P C-F C5.32 PT P01-01 II-CT-014CT-FW-174 CT PI,FHI -PE,LR SER 250.1V UT-455 P03-01 II-CT-016CT-SW-A3 CT PE,LR -PC,PIPE SER 250. 1V UT-45S P03-01 II-FMR-01FW-H-0212I(8) FW PC,PIPE-PI,LUGN C-C C3.20 MT P01-01 II-FMR-01MS-FW-229 MS PC,PIPE-PI,FHI C-F C5.21 UT-45S P01-01 II-FW"002AF-FW-257 AF PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S P04-01 II-FW-002AF-FW-258 PC,PIPE-PC,VLV FSAR 6.6.88 UT-455 P04-01 II-FW-003AF-FW-269 AF PC,PIPE-PC,VLV FSAR 6.6.88 UT-45S P04-01 II-FW-004AF-FW-277 AF PC,PIPE-PC,VLV C-F C5.11 MT P01-01 II-FW-004AF-FW-277 AF PC,PIPE-PC,VLV FSAR 6.6.88 UT-45S P04-01 I I-RH-001SI-FW-6A SI PLSW,P C-F C5. 12 PT P01-01 I I-S I-OOBRH-SW-K3A RH PLSW,P C-F CS. 11 PT P01-01 I I-SI-009CT-FW-96 CT PE,LR -PC,PIPE SER 250. 1S PT P03-01

444444444f4444444t444444444444444444 444444444444444444 12/04 5 NUTECH/PRI ..c PAGE: QUERY RESPONSE REPORT CP&L-HARRIS RELIEF REQUEST R2-001: COMPONENTS REQUESTED FOR RELIEF 4 \ 44 4 4 4 4 4 4 4 44 4 4 4 4 4 4 4 4 4 4 4 4 44 f444444444444404404444t44444444444444f44444f44ff4444404t4444444ff4444ff4f4f4444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ I I-SI-027SI-H-0181 I (8) SI PC, PIPE-PI, LUGN C-C C3.20 PT P01-01 I I-SI-032SI-FW"979 SI PC,PIPE-PSW,VLV SER 250.1S PT P03-01 II-SI-032SI"SW-C3 SI PF>WNO -PCsPIPE SER 250. 1S PT P03-01

44444444 444444444444444444444444444444444444444444444 44444444444 444444444444444444444044444444444444444444 444444 12/04>a5 NUTECH/PRI PAGE: 1 QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 444444444444444444 '444f4ff4404tft444tf4'44f444ffftttt44ffff44f 44444444444844444444444444444444444440 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-AF-005AF-FW-249 AF PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S P04-01 II-AF-005AF-FW-251 AF PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S P04-01 II-AF-006AF-FW-246 AF PC>VLV -PCePIPE FSAR 6.6.88 UT-455 P04-01 II-AF-007AF-FW-239 AF PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S P04-01 II-AF-007AF-FW-241 AF PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S P04-01 II-CS-006CS-FW-102 CS PC,PIPE-PC,VLV SER 250. 1V UT-45S P03-01 II-CS-006CS-FW-103 CS PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01 II-CS-006CS-FW-104 CS PCoPIPE-PCoVLV SER 250.1V UT-45S P03-01 II-CS-006CS-FW-105 CS PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01 II-CS-006CS-FW-106 CS PC,PIPE-PBCC,T SER 250.1V UT-45S P03-01 II-CS-006CS-FW-122 CS PC,PIPE-PC,VLV SER 250. 1V UT-45S P03-01 II-CS-.006CS-FW-123 CS PC,VLV -PC,PIPE SER 250. IV UT-45S P03-01 II-CS-006CS-FW-124 CS PC,PIPE-PC,VLV SER 250. 1V UT-45S P03-01 II-CS-006CS-FW-125 CS PC,VLV -PC,PIPE SER 250.1V UT-45S P03-01 II-CS-006CS-FW-126 CS PC,PIPE-PBCC,TR SER 250. 1V UT-45S P03-01 II-CS-006CS-FW-130 CS PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01 II'-CS-006CS-FW-132 CS PC,VLV -PC,PIPE SER 250.1V UT-45S P03-01 II-CS-006CS-FW-201 CS PC,PIPE-PC,VLV SER 250. 1V UT-45S P03-01 II-CS-006CS-FW-202 CS PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01 II-CS-006CS-SW-A3 CS PF,RFWN-PC,RED SER 250.1V UT-45S P03-01 II-CS-006CS-SW-D4 CS PBCCoTR PC.PIPE SER 250. 1V UT-45S P03-01 II-CS-006CS-SW-D5 CS PC,PIPE-PBCC,TR SER 250. 1V UT-45S P03-01 II-CS"006CS-SW-F3 CS PBCC,TR-PC,PIPE SER 250. 1V UT-45S P03-01

eeee4e 4f4444ee444444444044440444444444444444444444044444444 44444444444 44444444444444t444444444444444444444444444 444444 12/04/ 5 NUTECH/PRI PAGE: 2 QUERY RESPONSE REPORT CPSL-HARRIS 4 RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 4 444444444440444444444444444444444444444t44444444444444044444444444444444t444440 44444444444444444444444444444444444444444444444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-CS-006CS-SW-F4 CS PC,PIPE-PBCC,TR SER 250. 1V UT-455 P03-01 II-CS-007CS-FW-203 CS PCoPIPE-PCiVLV SER 250. 1V UT-455 P03-01 II-CS-007CS-FW-204 CS PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01 II-CS-007CS-FW-205 CS PC,PIPE-PC,VLV SER 250. 1V UT-45S P03-01 II-CS-007CS-FW-92 CS PC,PIPE-PC,VLV SER 250.1V UT-455 P03-01 II-CS-007CS-FW-93 CS PC,VLV -PC,PIPE SER 250.1V UT-455 P03-01 II-CS-007CS-FW-94 CS PC,PIPE-PC,VLV SER 250. 1V UT-455 P03-01 II-CS-007CS-FW-95 CS PCJVLV -PC,PIPE SER 250. 1V UT-45S P03-01 II-CS-007CS-FW-96 CS PC,PIPE-PC,RED SER 250. IV UT-455 P03-01 II-CS-007CS-SW-A3 CS PF,RFWN-PC,RED SER 250. 1V UT-45S P03-01 II-CS-007CS-SW-D3 CS PBCC AT -PC,PIPE SER 250. 1V UT-45S P03-01 II-CS-007CS-SW-D4 CS PC,PIPE-PBCC,T SER 250. 1V UT-455 P03-01 II-CS-007CS-SW-D5 CS PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 II-CS-007CS-SW-06 CS PC,RED -PBCC,T SER 250. 1V UT-455 P03-01 II-CS-007CS-SW-D7 CS PBCC,T -PC,RED SER 250.1V UT-45S P03-01 II-CS-022CS-FW-561 CS PC,VLV -PC,PIPE FSAR 6.6.88 UT-455 P04-01 II-CS-022CS-FW-562 CS PC,PIPE-PI,FHB FSAR 6.6.88 UT-45S P04-01 II-CS-022CS-SW-85 CS PBCC,T -PC,RED SER 250. 1V UT-455 P03-01 II-CS-022CS-SW-86 CS PC,PIPE-PBCC,T SER 250. 1V UT-455 P03-01 II-CS-092CS-FW-3029 CS PC,PIPE-PC,VLV FSAR 6.6.88 UT-455 P04-O'I II-CT-001CT-FW-1 CT VNOZ180-PC,PIPE SER 250. 1V UT-45S P03-01 II-CT-001CT-FW-8 CT PC,PIPE-PC,VLV SER 250. 1V UT-45S P03-01 II-CT-001CT-FW-9 CT PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01

444444 +44444t4444444444444444 4444444444444444444444444444444 44444444444 44$ f044444444444444444444444444 12/04 u5 NUTECH/PRI PAGE: - 4 QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 444'44444t4444444444444440444444444044'444444444 4044044444044444444444444448%444444444444444444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-FW-004FW-FW-572 FW PC,VLV -PC PIPE

                                                ~         FSAR      6.6.8C       UT-45S 805-01 II-FW-004FW-SW-C3              FW    PC,PIPE-PE,LR         FSAR      6.6.8C       UT-455 P05-01 II-MS-001MS-FW-258A            MS    PLSW,P                FSAR      6.6.8C       UT-455 P05-01 II-MS-001MS-FW-259A            MS    PLSW,P                FSAR      6.6.8C       UT-455 P05-01 I I-MS-001MS-SW-A   1 I        MS    PC,PIPE-PC,NOZW       FSAR      6.6.8C       UT-455 POS-01 I I -MS-001MS-SW-81   1        MS    PC,PIPE-PC,NOZW       FSAR      6.6.8C       UT-45S P05-01 I I-MS-001MS-SW-C 1   1              PC,PIPE-PC,NOZW       FSAR      6.6.8C       UT-455 P05-01 II-MS-001MS-SW-K2A             MS    PLSW,P                FSAR      6.6.8C       UT-455 P05-01 II-MS-001MS-SW-M28             MS    PLSW,P                FSAR      6.6.8C       UT-455 P05-01 II-MS-002MS-FW-566             MS    PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-455 P05-01 II-MS"002MS-FW-567             MS    PC,VLV -PC,PIPE       FSAR      6.6.8C       UT-45S P05-01 II-MS-002MS-FW-568             MS    PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-45S POS-01 II-MS-002MS-FW-690             MS    PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-455 P05-01 II-MS-002MS-FW-691             MS    PC,VLV -PC,PIPE       FSAR      6.6.8C       UT-45S POS-01 II-MS-002MS-FW-692                   PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-455 P05-01 II-MS-007MS-FW-678             MS    PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-455 P05-01 II-MS-009MS-FW-583             MS    PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-45S P05-01 II-MS-009MS-FW-586             MS    PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-455 P05-01 II-MS-009MS-FW-589             MS    PC,PIPE-PC,VLV        FSAR      6.6.8C       UT-45S P05-01 II"RH-001RH-FW-8                RH   PE, LR  -VNOZ 1 A I   SER       250. 1V      UT-45S P03-01 II-RH-001RH-FW-9                RH   PBCC,T -PC,PIPE       SER       250. 1V      UT-45S P03-01 II-RH-001RH-SW-EB               RH   PBCC,T -PF,WNO        SER       250. 1V      UT-455 P03-01 II-RH"002RH-FW-21               RH   PE, LR   -VNOZ1BI     SER       250. 1V      UT-455 P03-01

444444444444f4444444t444444444444444444f4444f444t4444 44444444444 444444444444444444t44444444444444444 12/04 5 NUTECH/PRI PAGE: 7 QUERY RESPONSE REPORT CP8 L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 4'44f44f4444444444444444444444444444044444444%4444404444f44040444404444444404 4444044r444444444444444444444444444444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SI-010SI-SW-Cj SI PC e PIPE-PC i PIPE SER 250. 1V UT-45S P03-01 I I-S I-010S I-SW-CB SI PC,PIPE-PBCC,T SER 250. 1V UT-455 P03-01 I I-SI-010SI-100-FW-275 SI PC,RED -PC,PIPE SER 250. 1V UT-45S P03-01 I I-SI-010SI-100-FW-276 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 I I-SI-010SI-99-FW-269 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 I I-SI -0105 I-99-FW-270 SI PC,PIPE-PC VLV~ SER 250. 1V UT-45S P03-01 I I -S I-0 105 I-99-FW-271 SI PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01 I I-SI-011SI-FW-475 SI PC,PIPE-PC,VLV SER 250. 1V UT-455 P03-01 I I-SI-01 1SI-FW-476 SI PC,VLV -PC,PIPE SER 250. 1V UT-45S P03-01 I I -SI-016SI-FW-36 SI PC,PIPE-PBCC,T SER 250. 1V UT-45S P03-01 I I-SI-016SI-SW-D4 SI PBCCrT PC ~ PIPE SER 250. 1V UT-45S P03-01 II-SI-016SI-SW-05 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 I I-SI-019SI-SW-04 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 II-SI-019SI-SW-05 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 I I-SI-019SI-14-FW-276 SI PI,FHI -PC,PIPE SER 250. 1V UT-45S P03-01 I I-SI-019SI-14-FW-277 SI PC,PIPE-PBCC,T SER 250. 1V UT-45S P03-01 II-SI-021SI-FW-557 SI PC,VLV -PC,PIPE C-F CS. 21 UT-53S P01-01 I I-SI-0215 I-FW-558 SI PC,PIPE-PC,VLV C-F CS. 21 UT-50S P01-01 II-SI-022SI-FW-559 SI PC,PB -PC,VLV C-F C5. 21 UT-53S P01-01 I I-SI-022SI-FW-564 SI PC,VLV -PC,PIPE C-F C5.21 UT-53S F01-01 I I-SI-023SI-FW-562 SI PC,VLV -PC,PIPE C-F C5.21 UT-53S P01-01 I I-SI-023SI-FW-563 SI PC,PIPE-PC,VLV C-F C5. 21 UT-50S P01-01 I I-SI-024SI-213-FW-573 SI PC,PB -PC,VLV C-F C5. 21 UT-45S P01-01

444444 44444444t44444844444444 0444444440444444444444444r4444 4444444444444444 444444444444444444444444448444044444 444444 12/04 5 NUTECH/PRI PAGE: 8 QUERY RESPONSE REPORT CPS L"HARRI S 4 RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RE LIEF 444444444t4444444f444f4444f4444444444444444f44444444444444444444444444444444444440444 44444044444444444444444444t44444444444444t44444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHO EXREQ I I-SI-025SI-FW-574 SI PC,VLV -PC,PIPE C-F CS. 21 UT-60S P01-01 II-SI-025SI-FW-575 SI PC,PIPE-PC,VLV C-F CS. 21 UT-605 P01-01 II-SI-025SI-FW"576 SI PI, FHI -PC, PIPE C-F C5. 21 UT-605 Po 1-01 II-SI-025SI-FW-577 SI PBCC,TR-PC,PIPE C-F CS. 21 UT-455 P01-01 II-SI-025SI-FW-578 SI PC,PB -PC,VLV C-F C5.21 UT-455 P01-01 II-SI-025SI-FW-579 SI PC,VLV -PC,PB C-F C5.21 UT-45S P01-01 I I-SI-025SI-FW-580 SI PC,VLV -PC,PIPE C-F C5.21 UT-455 P01-01 II-SI-025SI-FW-583 SI PBCC,T -PC,PIPE C-F C5.21 UT-45S P01-01 II-SI-025SI-FW-584 SI PCoPB -PCeVLV C-F C5.21 UT-455 Po 1-01 I I-SI-025SI-SW-A6 SI PFeRWNR-PCePIPE C-F C5.21 UT-455 Po 1-01 II-SI"025SI-SW-83 SI PC,PIPE-PF,RFWN C-F C5.11 UT-605 Pol-O'I II-SI-025SI-SW-84 SI PBCC,TR-PC,PIPE C-F C5.21 UT-60S P01-01 II-SI-025SI-SW-B5 SI PC,PIPE-PBCC,TR C-F C5.21 UT-605 Pol-01 II-SI-025SI-SW-05 SI PC ~ PIPE PE LR

                                                  ~                  C5.21       UT-455 Pol-01 II-SI-025SI-SW-06               SI    PE,LR    -PC,PIPE    C-F        C5.21       UT-455 Pol-01 II-SI-025SI-SW-E3               SI    PC,PB    -PBCC,T     C-F        CS. 21      UT-45S P01-Ol II-SI-025SI-SW-E4               SI    PC,PIPE-PBCC,T       C-F        CS. 21      UT-45S Pol-01 I I-SI-025SI-SW-F5              SI    PC,PB    -PF,RFWN    C-F        C5.21       UT-455 Po 1-01 II-SI-025SI-SW-G3               SI    PF,RFWN-PC,PB        C-F        C5.21       UT-455 P01-01 II-SI-026SI-FW"581              SI    PC,PIPE-PC,VLV       C-F        C5.21       UT-45S Pol-01 II-SI-026SI-FW-582              SI    PBCC,T -PC,PIPE      C-F        C5.21       UT-455 Po 1-01 II-SI-02651-FW-590              SI    PC,VLV -PC,PIPE      C-F        C5.21       UT-60S P01-01 I I -SI-026SI-FW-591             SI   PC,PIPE-PC,VLV       C-F        C5.21       UT-605 P01-01

4 444444 4444444444444444444444444t444444444444444404t44444444 44404444444 4444444444444444444444444444 4r 4444444444444 4 404404 12/04/a5 NUTECH/PRIS PAGE: 9 QUERY RESPONSE REPORT CP8L-HARRIS RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 44444444444444444444444444r44444444444444444440044444444440444444ft4444444444444 444444444t4444t444444444t4cf4444%4r44444rtttkt4tktkt4444 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SI-026SI-FW-592 SI PI,FHI -PC,PIPE C-F C5. 21 UT-60S P01-01 II-SI-026SI-FW-594 SI PC,PB -PC,VLV C-F C5. 21 UT-45S P01-01 II-SI-026SI-SW-G3 SI PC,PIPE-PF,RED C-F C5.21 UT-60S P01-01 II-SI-026SI-SW-G5 SI PC,PIPE=PBCC,TR C-F C5. 21 UT-605 P01-01 II-SI-027SI-FW-606 SI PC,PB -PC,VLV C-F C5. 21 UT-45S P01-01 II-SI-027SI-SW-K3 SI PC,PB -PBCC,T SER 250.1V UT-60S P03-01 II-SI-027SI-SW-K5 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 II-SI-027SI-SW-K6 SI PBCCeT -PCoPIPE SER 250. 1V UT-45S P03-01 II-SI-028SI-FW-608 SI PC,RED -PC,PIPE C-F C5.21 UT-605 P01-01 II-SI-028SI-FW-609 SI PI FHI -PC, PIPE

                                       ~

C-F C5.21 UT-60S P01-01 I I "SI-028SI-FW-610 SI PC,PB -PC,VLV C-F C5.21 UT-455 P01-01 II-SI-028SI-SW-A5 Sj PC,PIPE-PBCC,T C-F C5.21 UT-60S P01-01 II-SI-028SI-SW-A6 SI PBCC,T -PC,PIPE C-F C5.21 UT-60S P01-01 II-SI-028SI-SW-A7 SI PC,PIPE-PC,RED C-F C5.21 UT-60S P01-01 II-SI-028SI-SW-AB SI PBCC,T -PC,PIPE C-F C5.21 UT-605 P01-01 II-SI-028SI-SW-A9 SI PC,PIPE-PC,RED C-F C5.21 UT-60S P01-01 II-SI-029SI-SW-C10 SI PC,PIPE-PBCC,T SER 250. 1V UT-45S P03-01 I I-SI-029SI-SW-C1 1 SI PBCC,T -PC,RED SER 250.1V UT-45S P03-01 I I-SI-0295 I-SW-C12 SI PBCCsT -PC>PIPE SER 250. 1V UT-455 P03-01 I I-SI-029SI-SW-C14 SI PC,PIPE-PBCC,T SER 250. 1V UT-455 P03-01 II-SI-029SI-SW-C4 SI PBCC,T -PC,PIPE SER 250. 1V UT-45S P03-01 II-SI-029SI-SW-C5 SI PBCC,T -PC,PIPE SER 250. IV UT-45S P03-01 II-SI-029SI-SW"C7 SI PCsPIPE-PBCCeT SER 250. 1V UT-45S P03-01

0

0 0

444 444444444444t44f4444444f4444f444444444444444444t44444 44444444444444444444444444444444 4444444 444444 12/04 5 NUTECH/PRI PAGE: - 2 QUERY RESPONSE REPORT CPB L-HARRI S RELIEF REQUEST R2-005: COMPONENTS REQUESTED FOR RELIEF 4444f4444444444444f4ff4t4f4444f44444444444444444444444t44044044ff0f4444444444444444444444f4444444404 COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-RHX-01CHTSW-04 CS VCHW C-A C1. 20 UT-45L P01-01 II-RHX-01CHTSW-05 CS VCHW C-A C1. 20 UT-00 P01-01 II-RHX-01CHTSW-05 CS VCHW C-A C1. 20 UT-45L P01-01 II-RHX-01CHTSW-06 CS VCHW C-A C1. 20 UT-00 P01-01 II-RHX-01CHTSW-06 CS VCHW C-A C1. 20 UT-45L P01-01 II-RHX-01HSTSW-A'I CS VI,LUG C-C C3. 10 PT P01-01 II-RHX-01TSTSW-07 CS VTSTVW C-A C1.30 UT-00 P01-01 II-RHX-O'ITSTSW-07 CS VTSTVW C-A C1. 30 UT-45L P01-01 II-RHX-01TSTSW-07 CS VTSTVW C-A C1. 30 UC 45L P01-01 II-RHX-01TSTSW-08 CS VTSTVW C-A C1.30 UT-OO P01-01 II-RHX-01TSTSW-08 CS VTSTVW C-A CI .30 UT-45L P01-01 II-RHX-01TSTSW-08 CS VTSTVW C-A C1. 30 PT P01-01 II-RHX-01TSTSW-08 CS VTSTVW C-A C1.30 UC-45L P01-01 II-RHX-01TSTSW-09 CS VTSTVW C-A C1. 30 UT-00 P01-01 II-RHX-01TSTSW-09 CS VTSTVW C-A C1. 30 UT-45L P01-01 I I-RHX-01TSTSW-09 CS VTSTVW C-A C1.30 UC-45L P01-01 II-RHX-01TSTSW-10 CS VTSTVW C-A C1.30 UT-00 P01-01 II-RHX-01TSTSW-10 CS VTSTVW C-A C1. 30 UT-45L P01-01 I I-RHX-01TSTSW-10 CS VTSTVW C-A C1. 30 UC-45L P01-01 II-RHX-01TSTSW-11 CS VTSTVW C-A C1.30 UT-00 P01-01 II-RHX-01TSTSW-11 CS VTSTVW C-A C1.30 UT-45L P01-01 II-RHX-01TSTSW-11 CS VTSTVW C-A C1.30 PT P01-01 I I -RHX-01TSTSW-1 1 CS VTSTVW C-A C1.30 UC-45L P01-01

e

44444t ++*<44444ft4444444f4f444444444444444444f44f44f4t44ft4 Otktkff444444444444444444444444444444444f44444444f4tf4 44444f 12/04/ a5 NUTECH/PRI 5 PAGE: 5 QUERY RESPONSE REPORT 4 CP8 L-HARRIS RELIEF REQUEST R2-005: COMPONENTS REQUESTED FOR RELIEF 4 4444440444444444444444444f4444f4f444f44444444440t444f4444444444t44t4444t44t4444444f44444444++ COMPNOEX SYSTE COMPDES CATEGORY ITEMNO EXSCHD EXREQ II-SG-001SGC-FWNTSW-05 RC VNTVWI C-B C2.21 UT-00 Po 1-01 II-SG-001SGC-FWNTSW-05 RC VNTVWI C-B C2.21 UT-45S P01-01 II-SG-001SGC-FWNTSW-05 RC VNTVWI C-B C2.21 UT-60S P01-Ol II-SG-001SGC-MSNIR-15 RC VNIR C-B C2.22 VOL P01-01 II-SG-001SGC-MSNTHW-01 RC VNTVWO C-B C2.21 UT-00 Pol-01 II-SG-001SGC-MSNTHW-01 RC VNTVWO C-B C2.21 UT-455 P01-01 II-SG-001SGC-MSNTHW-01 RC VNTVWO C-B C2.21 UT-60S P01-01 II-SG-001SGC-STHW-02 RC VSTHW C-A C 1 . 20 UT-00 Pol-01 II-SG-001SGC-STHW-02 RC VSTHW C-A Cl . 20 UT-455 Pol-01 II-SG-001SGC-STHW-02 RC VSTHW C-A C 1 . 20 UT-605 PO'1-01 II-SG-001SGC-TSTSW-09 RC VTSTVW C-A Cl . 30 UT-00 P01-01 II-SG-001SGC-TSTSW-09 RC VTSTVW C-A Cl . 30 UT-455 Pol-01 II-SG-001SGC-TSTSW-09 RC VTSTVW C-A C1.30 UT-605 Pol-01

ISOMETRIC DRAMING II-AF-00100 Revision Number <Does not appear as part of component number) ISO Number (Appears as first nine characters of component number)

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++44444444444444444444444444444444444t444444444f4444fff4fv +f444444444444tf NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 41 '4 REVISION, RRS1 DATE 85/12/04 44444444444444444444'44t444444ff4444ffff4t4f444444f444 REFERENCE KEY DESCRIPTION I I-BD-01200 BLOW DOWN ISI ISOMETRIC SHEET NO. 012 REVISION NO. 00 I I-BIT-0100 BORON INJECTION TANK II-CC-00100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-CC-00200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-CC-00300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-CC-00400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 II-CC-00600 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 006 REVISION NO. 00 II"CC-00700 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-CC-00800 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 II-CC-00900 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 II-CC-01000 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 444444444444t4444444f4444444444f444444044444444444444444444444444444t44444

~~4444t444000444484444f400444444f44444444444444444t44444fa +f444444tf44444f NUTECH PRISIM 4 CAROLINA POWER L'LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE,.RRS142 REVISION DATE, 85/12/04 44444444444444444444tt44f44444444444444444f444f444444444tf444f444444444444t REFERENCE KEY DESCRIPTION II-CC-01100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 011 REVISION NO. 00 I I-CC-01200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 012 REVISION NO. 00 II-CC-01300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 013 REVISION NO. 00 I I-CC-01400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 014 REVISION NO. 00 I I-CC-01500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 II-CC-02100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 021 REVISION NO. 00 II-CC-02200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 022 REVISION NO. 00 II-CC-02300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 023 REVISION NO. 00 II-CC-02400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 024 REVISION NO. 00 II-CC-02500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 025 REVISION NO. 00 OS4444444444444444404444444444444444444444f4f4f4444444444444444444444444444

w+4444444444444444f444ff44ff444444444444444444fffkt4'444444 444'4ff444444444 NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 4440444444440444 DATA ELEMENT : ISONO PAGE . 43 4 REVISION RRS1 4 DATE 85/12/04 444444444t4444444444444f444444444444t444f444444f4444444444444f444ff4f44f444 REFERENCE KEY DESCRIPTION I I-CC-02700 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 027 REVISION NO. 00 I I-CC-02900 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 029 REVISION NO. 00 I I-CC-03000 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 030 REVISION NO. 00 I I-CC-03100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 031 REVISION NO. 00 I I-CC-03200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 032 REVISION NO. 00 II-CC-03300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 033 REVISION NO. 00 II-CC-03400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 034 REVISION NO. 00 I I CC-03700 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 037 REVISION NO. 00 I I-CC-03900 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 039 REVISION NO. 00 II-CC-04300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 043 REVISION NO. 00 44404444444444f44444f4f44f44444f44444t44444 44444444444444 4444444444 t44 0 f 0 44

+w t t t t t t t t t t t t t t t t t t t t t t t t t t tt t t tttt t t t t t t t t t t t t tt t tttt t t t tt t t t t t tt t t t t t t t NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 44 REVISION . RRS 1 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt DATE REFERENCE KEY DESCRIPTION II-CC-04400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 044 REVISION NO. 00 I I-CC-04500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 045 REVISION NO. 00 II-CC-04600 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 046 REVISION NO. 00 II-CC-04700 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 047 REVISION NO. 00 II-CC-04800 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 048 REVISION NO. 00 II-CC-04900 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 049 REVISION NO. 00 II-CC-05000 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 050 REVISION NO. 00 II-CC-05100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 051 REVISION NO. 00 II-CC-05200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 052 REVISION NO. 00 II-CC-05300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 053 REVISION NO. 00

+~4444444444444444444444444444444t4444t4t44444tbStd'444444t~~4444444444444t4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444044444444444 DATA ELEMENT : ISONO PAGE ...45 REVISION RRS 1 DATE 85/12/04 44444444f444444444444444444444fkkf44$ 44440444f4444044444f444444f44444444444 REFERENCE KEY DESCRIPTION I I-CC-05400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 054 REVISION NO. 00 I I-CC-05500 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 055 REVISION NO. 00 II-CC-05600 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 056 REVISION NO. 00 II-CC-05800 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 058 REVISION NO. 00 II-CC-05900 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 059 REVISION NO. 00 II-CC-06000 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 060 REVISION NO. 00 I I-CC-06100 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 061 REVISION NO. 00 II-CC-06200 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 062 REVISION NO. 00 II-CC-06300 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 063 REVISION NO. 00 II"CC-06400 COMPONENT COOLING WATER ISI ISOMETRIC SHEET NO. 064 REVISION NO. 00 444444fftt44t444fft444t444tt444444t44444444448444f44f444tkf444444tt44444ttt

4404444ft4444404+ +Of44t4444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444444444f4444444 DATA ELEMENT : ISONO PAGE .. 46 4 REVISION RRS1 DATE 85/12/04 44444444444444444$ 444444444444444tff4444444444444444t44f44444444f4444444 REFERENCE KEY DESCRIPTION II-CE-00100 CONDENSATE ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 -II-,CE-00200 CONDENSATE ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 I I-CH-00100 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-CH-00200 CHILLED WATER SUPPLY IS I ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-CH-00300 CHILLED WATER, SUPPLY ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-CH-00400 CHILLED WATER SUPPLY IS I ISOMETRIC SHEET NO. 004 REVISION NO. 00 II-CH-00500 CHILLED WATER SUPPLY IS I ISOMETRIC SHEET NO. 005 REVISION NO. 00 II-CH-00600 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 006 REVISION NO. 00 II-CH-00700 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-CH-00800 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 444fftkff4444ff4044444444t44444444444444444f4444444444444444444444t444f4444

4444f4444ff4444444444444444444444444444444444444444444 444444'444444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 47 REVISION RRS1 DATE 85/12/04 4444440448%444tt4444444444444444444$ 44444444t4444444444t44444tbt4444444'444t REFERENCE KEY DESCRIPTION II-CH-00900 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 II-CH-01000 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 II-CH-01100 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 011 REVISION NO. 00 II-CH-01200 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 012 REVISION NO. 00 II-CH-01300 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 013 REVISION NO. 00 II-CH-01400 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 014 REVISION NO. 00 II-CH-01500 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 II-CH-01600 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 016 REVISION NO. 00 II-CH-01900 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 019 REVISION NO. 00 II-CH-02000 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 020 REVISION NO. 00 444444444444t44444444444044444444444444 044 f 404 f 44444444444

t~tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 48 REVI S ION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION II-CH-02100 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 021 REVISION NO. 00 II-CH-02300 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 023 REVISION NO. 00 II-CH-02400 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 024 REVISION NO. 00 II-CH-02500 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 025 REVISION NO. 00 II-CH-02600 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 026 REVISION NO. 00 II-CH-03300 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 033 REVISION NO. 00 II-CH-03400 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 034 REVISION NO. 00 II-CH-03500 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 035 REVISION NO. 00 II-CH-03600 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 036 REVISION NO. 00 II-CH-03700 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 037 REVISION NO. 00

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++4444444444444444444444444444444444444444440444440444fff 4+ 4444444444444'44 NUTECH PRI RIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444444444444444t4 DATA ELEMENT : ISONO PAGE 50 REVISION RRS1 DATE 85/ 12/04 4444444444444444f 4t4444444t4f 44f 4444444f 44444444444444f 44 REFERENCE KEY DESCRIPTION II-CH-05800 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 058 REVISION NO. 00 II-CH-06100 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 061 REVISION NO. 00 II-CH-06400 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 064 REVISION NO. 00 II-CH-06500 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 065 REVISION NO. 00 II-CH-07000 CHILLED WATER SUPPLY I SI ISOMETRIC SHEET NO. 070 REVISION NO. 00 I I-CH-07100 CHILLED WATER SUPPLY I SI ISOMETRIC SHEET NO. 071 REVISION NO. 00 II-CH-07300 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 073 REVISION NO. 00 II-CH-07500 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 075 REVISION NO. 00 II-CH-07700 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 077 REVISION NO. 00 II-CH-07800 CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 078 REVISION NO. 00 444444444444444444444484444t4444444444444f44444444444444f4'44t444444ft444444

 +444f 4444f 4444 44f f 4444 t4444f 44f f 44444f 44444444444                             +044C44444444444 NUTECH                                                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT                        -   UNIT PLANNING REFERENCE CLUSTER LISTING                                 4444t44t44t4444444 DATA ELEMENT : ISONO                                     PAGE              . S 1 REVISION, RRS           1 DATE 85/12/04 44 4'4444 4444 44 44 4 4 4 44 4 44 0 f 4 4 4 0 4 44 444 t 444444 4 4 4 44 t 444I 444444 444 4I 4 44 444 4 4 4 0 44 4 4 REFERENCE KEY                                                DESCRIPTION II-CH-07900          CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 079                REVISION NO. 00 II-CH-08000          CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 080                REVISION NO. 00 I I-CH-08100         CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 081                REVISION NO. 00 II-CH-08200          CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 082                REVISION NO. 00 II-CH-08300          CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 083                REVISION NO. 00 II-CH-08600          CHILLED WATER SUPPLY ISI ISOMETRIC SHEET NO. 086                REVISION NO. 00 II-CS-00100          CHEMICAL AND VOLUME CONTROL SYSTEM                        ISI  ISOMETRIC SHEET NO. 001                REVISION NO. 00 II-CS-00200          CHEMICAL AND VOLUME CONTROL SYSTEM                        ISI  ISOMETRIC SHEET NO. 002                REVISION NO. 00 II-CS-00300          CHEMICAL AND VOLUME CONTROL SYSTEM                        ISI  ISOMETRIC SHEET NO. 003                REVISION NO. 00 II-CS-00400          CHEMICAL AND VOLUME CONTROL SYSTEM                        ISI   ISOMETRIC SHEET NO. 004                REVISION NO. 00

444444444444444444 +444444444444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE ,52 REVISION RRS1 DATE 85/12/04 44444444444444444444444444444 4444444444444444444f44444444f44 REFERENCE KEY DESCRIPTION II-CS-00500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00 II-CS-00600 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 006 REVISION NO. 00 II-CS-00700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-CS-00800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 II-CS-00900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 II-CS-0 1000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 I I-CS-01100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 011 REVISION NO. 00 II-CS-01300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 013 REVISION NO. 00 II-CS-01500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 I I -CS-01900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 019 REVISION NO. 00 44444t444t44444'44444444444444444444444444444444f4444444t444444444444444t444

aa04444444444440844444044444484t4444444444444t444444444404++44444444444444t NUTECH PRISIM 4 CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING t4444f44444444 DATA ELEMENT : ISONO PAGE, . 53 REVISION RRS1 DATE 85/12/04 44444444f'4444tf4tt44444f4444t44444444f4444444444444444444444444f44444f44444 REFERENCE KEY DESCRIPTION II-CS-02000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 020 REVISION NO. 00 h I I-CS-02100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 021 REVISION NO. 00 II-CS-02200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 022 REVISION NO. 00 I I-CS-02400 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 024 REVISION NO. 00 II-CS-02500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 025 REVISION NO. 00 II-CS-02600 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 026 REVISION NO. 00 II-CS-02700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 027 REVISION NO. 00 II-CS-02800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 028 REVISION NO. 00 II-CS-02900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 029 REVISION NO. 00 II-CS-03000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 030 REVISION NO. 00 444 44444 44444444444444444444444444444 f 44444444444t444444444 444444 04444444

t+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt+ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE ',, 54 REVISION,, RRS 1 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttt,tttttttttttttttttttttttt DATE REFERENCE KEY DESCRIPTION II-CS-03100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 031 REVISION NO. 00 II-CS-03300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 033 REVISION NO. 00 II-CS-03400 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 034 REVISION NO. 00 II-CS-03600 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 036 REVISION NO. 00 II-CS-03700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 037 REVISION NO. 00 II-CS-03800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 038 REVISION NO. 00 II-CS-03900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 039 REVISION NO. 00 II-CS-04100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 041 REVISION NO. 00 11-CS"04700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 047 REVISION NO. 00 II-CS-04800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 048 REVISION NO. 00

4444444f444tf4444ttt444444444f4444~+4444t44484fktent NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE 55 REVISION RRS 1 REFERENCE KEY DESCRIPTION I I-CS-04900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 048 REVISION NO. 00 I I-CS-05700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 057 REVISION NO. 00 I I-CS-05800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 058 REVISION NO. 00 I I-CS-06000 CHEMICAL AND VOLUNME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 060 REVISION NO. 00 II-CS-06100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 061 REVISION NO. 00 II-CS-06200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 062 REVISION NO. 00 I'I-CS-06300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 063 REVISION NO. 00 II-CS-06500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 065 REVISION NO. 00 II-CS-06700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 067 REVISION NO. 00 I I-CS-07500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 075 REVISION NO. 00 4 t t 44 4 0 0 44 44 0 0 44 0'0 4 0 0 44 t4 4 44 44 444 0 4 444 44 44 4 0 4 44 0 4 444 0 0 4 44 4 0 4 0 44 f 444 44 0 44444

44r44444f444444844ff44t444444f44044444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING REFERENCE CLUSTER LISTING 444444440444444444 DATA ELEMENT : ISONO PAGE 56 REVISION RRS1 DATE 85/12/04 4400444444t44444444444444440444444444444044444044444444444044f444440044t440 REFERENCE KEY DESCRIPTION I I-CS-07600 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 076 REVISION NO. 00 II-CS-07700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 077 REVISION NO. 00 II-CS-07800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 078 REVISION NO. 00 I I-CS-07900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 079 REVISION NO. 00 I I "CS-08000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 080 REVISION NO. 00 II-CS-08100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 081 REVISION NO. 00 II-CS-08200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 082 REVISION NO. 00 I I-CS-08300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 083 REVISION NO. 00 II-CS-08400 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 084 REVISION NO. 00 I I-CS-08500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 085 REVISION NO. 00 4444444444444444444f4f44tf4444f4444444444ft4444444444444444444444444444444f

. - ~ 44444444444444444444444 4' 444444444 4444444444444444444444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT l PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 57 REVISION RRS 1 DATE 85/12/04 REFERENCE KEY DESCRIPTION II-CS-08700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 087 REVISION NO. 00 II-CS-08800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 088 REVISION NO. 00 II-CS-08900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 089 REVISION NO. 00 II-CS-09200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 092 REVISION NO. 00 II-CS-09300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 093 REVISION NO. 00 II-CS-09400 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 094 REVISION NO. 00 II-CS"09500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 095 REVISION NO. 00 II-CS-09600 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 096 REVISION NO. 00 II-CS-09700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 097 REVISION NO. 00 II-CS-09800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 098 REVISION NO. 00 444tftt44444f444444444444tf44f444444ttt4444444444f44tt44444444444f44444444'0

f t f ++ 0 0 4444 0 0 4 0 0 IF 0 4 0 0 44'444 0 0 0 0 4 4 0 0 0 0 4444 0 0 4f 4 0 0 0 44 0 0 0 0 0 4444+ s 0 0 4 0 44 444 44 0 0 0 NUTECH PRISIM 4 CAROLINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE 58 REVISION RRS1 DATE 85/12/04 44444f444444444444444tf44444444444f44444tf44444444fff4444444f44444f44444444 REFERENCE KEY DESCRIPTION II-CS-09900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 099 REVISION NO. 00 II-CS-10000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 100 REVISION NO. 00 II-CS-10200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 102 REVISION NO. 00 II-CS-10300 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 103 REVISION NO. 00 II-CS-10400 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 104 REVISION NO. 00 II-CS-10500 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 105 REVISION NO. 00 II-CS-10600 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 106 REVISION NO. 00 II-CS-10700 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 107 REVISION NO. 00 I I-CS-10800 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 108 REVISION NO. 00 II-CS-10900 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 109 REVISION NO. 00 Ct44f.44444844444444444444444044444444444444444

++tttttttttttttttftttttttttftttttffttttttttttttttttttttftt+ ttttttttttttttt NUTECH PRI SIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 59 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttt tttttttttttttttfttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION II-CS-11000 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 110 REVISION NO. 00 II-CS-11100 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 111 REVISION NO. 00 II-CS-11200 CHEMICAL AND VOLUME CONTROL SYSTEM ISI ISOMETRIC SHEET NO. 112 REVISION NO. 00 II-CT-00100 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-CT-00200 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-CT-00300 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-CT-00400 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 II-CT-00500 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00 II-CT-00700 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-CT-00800 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00

4i44$ 440444444408444444444444444844444444444444444444444444+444444444t44444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 4 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE 60 REVISION RRS1 DATE 85/12/04 44444444444444444444444444t44444044444f444444ttff444444ft44444ir444f444444f4 REFERENCE KEY DESCRIPTION II-CT-00900 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 I I-CT-01000 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 II-CT-01400 CONTAINMENT SPRAY I SI ISOMETRIC SHEET NO. 014 REVISION NO. 00 I I-CT-01500 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 II-CT-01600 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 016 REVISION NO. 00 II-CT-01700 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 017 REVISION NO. 00 I I-CT-01800 CONTAINMENT SPRAY ISI ISOMETRIC SHEET NO. 018 REVISION NO. 00 II-CX-00'100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-CX-00200 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-CX-00300 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 444844844444444444444444444444444f 4t'44f 4f t444'4444444f 044444f tt4f 04444444444

 ~004444044444444444444444444444444444444044444444444444       +444tt44t44t444e NUTECH                                                            PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT   1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO                   PAGE;", 61 REVISION   RRS1 DATE  85/12/04 4444t44444f444444f4444tkkt44t44t44444444444444448444f4t444440444444t444t REFERENCE KEY                              DESCRIPTION II-CX-00400       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 004    REVISION NO. 00 II-CX-00500       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 005    REVISION NO. 00 II-CX-00600       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 006    REVISION NO. 00 II-CX-00800       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 008    REVISION NO. 00 II-CX-01000       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 010    REVISION NO. 00 II-CX-01100       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 011    REVISION NO. 00 I I-CX-01300      CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 013    REVISION NO. 00 I I ,CX-01400    CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 014    REVISION NO. 00 Ii-CX-01500       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 015    REVISION NO. 00 ii-CX-01600       CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 016    REVISION NO. 00

0 4444ttf4444444444f444444444444444444444444444t4+ 444f44444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUClEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE 62 REVISION RRS1 DATE 85/12/04 4 44 4 4 0 4 S 44 4 4 4 0 4 0 4 4 4 0 0 444444444444 REFERENCE KEY DESCRIPTION II-CX-01700 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 017 REVISION NO. 00 II-CX-01800 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 018 REVISION NO. 00 II-CX-01900 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 019 REVISION NO. 00 II-CX"02000 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 020 REVISION NO. 00 11-CX-02100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 021 REVISION NO. 00 II-CX-02300 CHILLED WATER RETURN I SI ISOMETRIC SHEET NO. 023 REVISION NO. 00 II-CX-02500 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 025 REVISION NO. 00 11-CX-02700 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 027 REVISION NO. 00 11-CX-03100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 031 REVISION NO. 00 II-CX-03300 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 033 REVISION NO. 00 444444444444t444444f4444444444'444444444444444444444t44444444440

~444444f44484884f44f4444444f4444444444f8444444ftt NUTECH                                                                                 PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT                   UNIT  1 PLANNING REFERENCE CLUSTER LISTING                                44444444444444 DATA ELEMENT : ISONO                               PAGE               63 REVISION       RRS1 DATE     85/12/04 4444 004 44 4 f 444444t f 0 444 0 4 f 44 0 4r 00 44444444 f 4444444 444 444444$ 44 0 t44 444 44 t 444 4 0 REFERENCE KEY                                            DESCRIPTION II-CX-03400         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 034              REVISION NO. 00 II-CX-03800         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 038              REVISION NO. 00 II-CX-03900         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 039              REVISION NO. 00 II-CX-04000         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 040              REVISION NO. 00 II-CX-04100         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 041              REVISION NO. 00 II-CX-04200         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 042              REVISION NO. 00 II-CX-04300         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 043              REVISION NO. 00 II-CX-04400         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 044              REVISION NO. 00 II-CX-04500         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 045              REVISION NO. 00 II-CX-04600         CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 046              REVISION NO. 00 44t444444444444444444444444f444444444444444444444444444444444f4444444444ff4

0 +~44444444444444444444444444f44 4f444t4444t44~ 444444444444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE 64 REVISION RRS 1 DATE 85/12/04 44444444f4444444444444+f44t4444 44444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION II-CX-04700 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 047 REVISION NO. 00 II-CX-04800 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 048 REVISION NO. 00 Ii-CX-04900 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 049 REVISION NO. 00 II-CX-05200 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 052 REVISION NO. 00 II-CX-05900 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 059 REVISION NO. 00 II-CX-06000 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 060 REVISION NO. 00 II-CX-06100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 061 REVISION NO. 00 II-CX-06500 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 065 REVISION NO. 00 II-CX-06900 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 069 REVISION NO. 00 II-CX-07100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 071 REVISION NO. 00

++4444444t 4444f44444f444f4444444444444t444444ftff4444t4444 44t444444444444 NUTECH PRI SIM CAROlINA POWER 8 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE 65 REVISION RRS1 DATE 85/12/04 44444444444444fkf444f44444 REFERENCE KEY DESCRIPTION I I-CX-07700 CHILLEO WATER RETURN ISI ISOMETRIC SHEET NO. 077 REVISION NO. 00 II-CX-07800 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 078 REVISION NO. 00 II-CX-07900 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 079 REVISION NO. 00 II-CX-08100 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 081 REVISION NO. 00 II-CX-08300 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 083 REVISION NO. 00 II-CX-08400 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 084 REVISION NO. 00 II-CX-08700 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 087 REVISION NO. 00 II-CX-08800 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 088 REVISION NO. 00 II-CX-08900 CHILLED WATER RETURN ISI ISOMETRIC SHEET NO. 089 REVISION NO. 00 II-DW-00100 DEMINERALIZED WATER ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 4444tkkt$ 44444444f44444444444444444444444fkf4444f444440f4444t4f444f44444444

 +444040444t4444'44'44444O444444444444444444444444444440444       %44444444444444f NUTECH                                                                 PRISIM CAROLINA POWER 8 LIGHT COMPANY                              4 SHEARON HARRIS NUCLEAR POWER PLANT     - UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444444444444444 DATA ELEMENT : ISONO                     PAGE          66 REVISION . RRS1 DATE   85/12/04 444444444444044444444444444444444444444444444444444444044t404444444 REFERENCE KEY                               DESCRIPTION II-DW-01000       DEMINERALIZED WATER ISI ISOMETRIC SHEET NO. 010     REVISION NO. 00 I I-EA-00100      DIESEL STARTING AIR ISI ISOMETRIC SHEET NO. 001     REVISION NO. 00 II-EA-00200       DIESEL STARTING AIR ISI ISOMETRIC SHEET NO. 002     REVISION NO. 00 II-EA-00300       DIESEL STARTING AIR ISI ISOMETRIC SHEET NO. 003     REVISION NO. 00 II-EA-01200       DIESEL STARTING AIR ISI ISOMETRIC SHEET NO. 012     REVISION NO. 00 I I-EA-01300      DIESEL STARTING AIR ISI ISOMETRIC SHEET NO. 013     REVISION NO. 00 I I-EA-01400      DIESEL STARTING AIR ISI ISOMETRIC SHEET NO. 014     REVISION NO. 00 I I-EL-00100      EXCESS LETDOWN HEAT EXCHANGER II-FMR-0100       FEEDWATER, MAIN STEAM, AND REACTOR COOLANT      ISI ISOMETRIC SHEET NO. 01    REVISION NO. 00 II-FMR-0200       FEEDWATER, MAIN STEAM, AND REACTOR COOLANT      ISI ISOMETRIC SHEET NO. 02    REVISION NO. 00 II-FMR-0300       FEEDWATER, MAIN STEAM, AND REACTOR COOLANT      ISI ISOMETRIC SHEET NO. 03    REVISION NO. 00 4444444444444444844440444444444rttf4444444t44444444f044404444
+44444444444t4444                           444444444404444444444444w NUTECH                                                                                   PRI SIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT                     I PLANNING REFERENCE CLUSTER LISTING                            44444444t444444444 DATA ELEMENT : ISONO                                 PAGE                67 REVISION         RRS1 DATE 85/12/04 f

44 0 4444 f 0 0 0 44 0 44 4444 444 444444 44444 0 0 0 444 0 44 44 0 44 444 tlat 444 4IIS 0 f 444 f 0 REFERENCE KEY DESCRIPTION II-FO-00100 FUEL OIL ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-FO-00200 FUEL OIL ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-FO-00300 FUEL OIL ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-FO-00500 FUEL OIL ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00 II-FO-11400 FUEL OIL ISI ISOMETRIC SHEET NO. 114 REVISION NO. 00 II-FO- 11600 FUEL OIL ISI ISOMETRIC SHEET NO. 116 REVISION NO. 00 II-FO-12200 FUEL OIL ISI ISOMETRIC SHEET NO. 122 REVISION NO. 00 II-FO-12300 FUEL OIL ISI ISOMETRIC SHEET NO. 123 REVISION NO. 00 II-F0-.12400 FUEL OIL ISI ISOMETRIC SHEET NO. 124 REVISION NO. 00 II-FO-12500 FUEL OIL ISI ISOMETRIC SHEET NO. 125 REVISION NO. 00 44444444f44444'444444444444444444444f4444444444444444t4484444444444444444f44

+~444444444444444444'44t44444444444444444t444 444444444'4t 44444444444f444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 68 REVISION RRS1 DATE 85/12/04 44444444444444444444444444444444444444444ttk 44444t44444444f444tt44444444440 REFERENCE KEY DESCRIPTION I I-FP-00500 FIRE PROTECTION ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00 II-FP-00700 FIRE PROTECTION ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-FP-04900 FIRE PROTECTION ISI ISOMETRIC SHEET NO. 049 REVISION NO. 00 II-FP-05100 FIRE PROTECTION ISI ISOMETRIC SHEET NO. 051 REVISION NO. 00 I I-FW-00100 FEEDWATER ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-FW-00200 FEEDWATER ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-FW-00300 FEEDWATER ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-FW-00400 FEEDWATER ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 II-FW-00700 FEEDWATER ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-FW-00800 FEEDWATER ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 44444444444444444444444444444444444444444444444444+t444444444444444444t4444

v+44t4444444444444f44444444 444444444444444 4 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44 444444 4 444444 4 44 DATA ELEMENT : ISONO PAGE .', 69 REVISION RRS1 DATE 85/12/04 444444444444444f44444f44444444444f'4444444444 REFERENCE KEY DESCRIPTION I I-FW-00900 FEEDWATER ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 I I-FW-01000 FEEDWATER ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 I I-FW-01200 FEEDWATER ISI ISOMETRIC SHEET NO. 012 REVISION NO. 00 I I-FW-01300 FEEDWATER Isi ISOMETRIC SHEET NO. 013 REVISION NO. 00 I I-IA-00100 INSTRUMENT AIR ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 I I-IA-00300 INSTRUMENT AIR ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 I I-MD-00300 MISCELLANEOUS DRAINS ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-MD-00700 MISCELLANEOUS DRAINS ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II "MS-00100 MAIN STEAM ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 I I-MS-00200 MAIN STEAM ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 4444444444444444444444444444444t444444444f444t444t444444444444ft444444444'44

++ttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING t t t tt t t t t t t t t t t t t t DATA ELEMENT : ISONO PAGE 70 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION II-MS"00300 MAIN STEAM ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-MS-00700 MAIN STEAM ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-MS-00800 MAIN STEAM ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 II-MS-00900 MAIN STEAM ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 II-MS-01500 MAIN STEAM ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 II-MS-02400 MAIN STEAM ISI ISOMETRIC SHEET NO. 024 REVISION NO. 00 II-PZR-0100 PRESSURIZER II-RC-00100 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-RC-00200 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-RC-00300 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-RC-00800 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00

~eeeeeeeee44444444444444444444444444444444444 044404444444+i4444t44404400444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ISONO PAGE 71 REVISION RRS1 DATE 85/12/04 444444444440444444t4444444444444444444444t444 REFERENCE KEY DESCRIPTION II-RC-00900 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 I I-RC-01000 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 II-RC-01100 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 011 REVISION NO. 00 II"RC-01200 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 012 REVISION NO. 00 II"RC-01300 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 013 REVISION NO. 00 I I-RC-01400 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 014 REVISION NO. 00 II-RC-01500 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 II-RC-0'1700 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 017 REVISION NO. 00 I I-RC-01800 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 018 REVISION NO. 00 II-RC-01900 REACTOR COOLANT ISI ISOMETRIC SHEET NO. 019 REVISION NO. 00

              '444444444f444444444444444444444444444444f4'44444444444444444444
~ee444444t44444444444444444444444444444444444444t NUTECH                                                             PRI SIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT   1 PLANNING REFERENCE CLUSTER LISTING               <<e4444444444444444 DATA ELEMENT : ISONO                   PAGE          72 REVISION    RRS1 DATE   85/12/04 4440444t4444444444444f44444f4444444444f444444f444444f44f44444f444 REFERENCE KEY                            DESCRIPTION II-RC-02000     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 020    REVISION NO. 00 II-RC-02200     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 022    REVISION NO. 00 II-RC-02300     REACTOR COOLANT I SI ISOMETRIC SHEET NO. 023    REVISION NO. 00 II-RC-02400     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 024    REVISION NO. 00 II-RC-02500     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 025    REVISION NO. 00 II-RC-02700     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 027    REVISION NO. 00 II-RC-02800     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 028    REVISION NO. 00 II-RC-02900     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 029    REVISION NO. 00 II-RC-03000     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 030    REVISION NO. 00 II-RC-10000     REACTOR COOLANT ISI ISOMETRIC SHEET NO. 100    REVISION NO. 00

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~+44444444444tkf44444444f4444f4444444444444444r44444444444W 444444444t4440f NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444 444 444444 444 44 DATA ELEMENT : ISONO PAGE,. REVISION RRS1 73 DATE 85/12/04 444444t44f4444ff444444f4f4404 REFERENCE KEY DESCRIPTION II-RCP-0100 REACTOR COOLANT PUMPS II-RH-00100 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 I I-RH-00200 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 I I-RH-00400 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 I I-RH-00500 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00 I I-RH-00600 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 006 REVISION NO. 00 I I-RH-00700 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 I I-RH-00800 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 I I-RH-00900 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 I I-RH-01000 RESIDUAL HEAT REMOVAL ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 I I-RHR-0100 RESIDUAL HEAT REMOVAL HEAT EXCHANGERA88 444444444444444444444444444444444444444444444440444444444444444404440444444

wm $$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$ $$$$$$$$$$$$$$$ $ NUTECH PRISIM $ CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 74 REVISION RRS 1 DATE 85/12/04 $ 4 $ $ $ $ $'$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ 4 $ $ $ $ $ $ 0 0 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ f$ $ $ $ $ $ $ f 0 $ $ REFERENCE KEY DESCRIPTION I I-RHX-0100 REGENERATIVE HEAT EXCHANGER II-RV-00100 DESCRIPTION TM BE ADDED BY SHNPP I I-SA-00100 SERVICE AIR ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 I I-SA-00300 SERVICE AIR ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-SC-00100 SCREEN WASH ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-SC-00200 SCREEN WASH ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-SC-00700 SCREEN WASH ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-SF-00100 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-SF-00200 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-SF-00400 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 II-SF-00500 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00

w~44444444444444 44444444t44444444444444t44444444444444444 444444444444444 NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE -,- 75 REVISION RRS1 .* DATE 85/12/04 4f 4444t44444 f 4444444f 44444f 444444f 444f 444444f AIOt4444444444444f4444444444444 REFERENCE KEY DESCRIPTION II-SF-00600 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 006 REVISION NO. 00 II-SF-00700 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 II-SF-00800 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 II-SF-00900 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 II-SF-01000 SPENT FUEL POOL COOLING AND CLEANUP ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 II-SG-00100 STEAM GENERATORS A,B,& C II-SI-00100 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-SI-00200 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-SI-00300 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-SI-00400 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 II-SI-00500 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00 4444444444444444444444444ff44444444f4444444444444f444444f44444444f444444

w+ tttt tttt tttttttttttttttttta +ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY t SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ISONO PAGE 76 REVISION, RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION I I-SI-00600 SAFETY INJECTION ISI ISOMETRIC SHEET. NO. 006 REVISION NO. 00 II-SI-00800 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 II-SI-00900 SAFETY INJECTION I SI ISOMETRIC SHEET NO. 009 REVISION NO. 00 II-SI-01000 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 II-SI-01100 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 011 REVISION NO. 00 I I-SI-01200 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 012 REVISION NO. 00 I I-SI-01300 SAFETY INJECTION I SI ISOMETRIC SHEET NO. 013 REVISION NO. 00 I I-SI-01400 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 014 REVISION NO. 00 I I-SI-01600 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 016 REVISION NO. 00 I I-SI-01700 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 017 REVISION NO. 00 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt

+~444444444'44444f4444444444 s44444444444444f NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE 77 REVI SION RRS 1 DATE 85/12/04 4444444444444444444t444t44f 4444404444444444444444444444444440t4444444444440 REFERENCE KEY DESCRIPTION II-SI-01800 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 018 REVISION NO. 00 II-SI-01900 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 019 REVISION NO. 00 II-SI-02000 SAFETY INJECTION IS I ISOMETRIC SHEET NO. 020 REVISION NO. 00 I I-SI-02100 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 021 REVISION NO. 00 II-SI-02200 SAFETY INJECTION I SI ISOMETRIC SHEET NO. 022 REVISION NO. 00 II-SI-02300 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 023 REVISION NO. 00 II-SI-02400 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 024 REVISION NO. 00 II-SI-02500 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 025 REVISION NO. 00 II-SI-02600 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 026 REVISION NO. 00 II-SI-02700 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 027 REVISION NO. 00 tvi444444444444444f44444444444444444ff4444444444444444f4444f4f4444444444444

0 ~~44444444444444444444t44444444444tt4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE,;RRS178 REVISION 4 DATE 85/12/04 444444444t444444444444444444444 4444f4444444f444444444444t44ttkft44444 REFERENCE KEY DESCRIPTION II-SI-02800 SAFETY INJECTION ISI ISOMETRIC SHEET NO; 028 REVISION NO. 00 II-SI-02900 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 029 REVISION NO. 00 II-SI-03000 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 030 REVISION NO. 00 II-SI-03100 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 031 REVISION NO. 00 II-S1-03200 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 032 REVISION NO. 00 II-SI-03300 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 033 REVISION NO. 00 II-SI-03400 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 034 REVISION NO. 00 II-SI-03500 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 035 REVISION NO. 00 II-SI-03600 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 036 REVISION NO. 00 II-SI-03700 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 037 REVISION NO. 00 4444444444444444f44'44f4444444404444f44flf4f444fftff4f4444444444444444444444

ttttttttttttttttttttttttttttttt+ ttttttttttttttt NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ISONO PAGE 79 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttt t t tt t t t t t t t t t t t t t t REFERENCE KEY DESCRIPTION II-SI-03800 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 038 REVISION NO. 00 II-SI-03900 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 039 REVISION NO. 00 II-SI-04000 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 040 REVISION NO. 00 II-SI-04100 SAFETY INJECTION ISI ISOMETRIC SHEET NO. 041 REVISION NO. 00 II-SI"04200 SAFETY. INJECTION ISI ISOMETRIC SHEET NO. 042 REVISION NO. 00 II-SP-00100 SAMPLING (NUCLEAR) ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-SP-00200 SAMPLING (NUCLEAR) ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 II-SP-00300 SAMPLING (NUCLEAR) I SI ISOMETRIC SHEET NO. 003 REVISION NO. 00 I I "SP-00400 SAMPLING (NUCLEAR) ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 II-SP-00700 SAMPLING (NUCLEAR) I SI ISOMETRIC SHEET NO. 007 REVISION NO. 00

+++ttttttttttttttttttttttttttttttttttttttttttttttttttttttt+tttttttt NUTECH PR ISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t PLANNING REFERENCE CLUSTER LISTING t t tt t t DATA ELEMENT : ISONO PAGE 80 REVISION RRS1 DATE 85/ ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION II-SP-00800 SAMPLING (NUCLEAR) ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 II-SP-00900 SAMPLING (NUCLEAR) ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 I I-SP-01400 SAMPLING (NUCLEAR) ISI ISOMETRIC SHEET NO. 014 REVISION NO. 00 I I-SP-01500 SAMPLING (NUCLEAR) ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 I I-SP-01600 SAMPLING (NUCLEAR) I SI ISOMETRIC SHEET NO. 016 REVISION NO. 00 I I-SW-00100 SERVICE WATER ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 II-SW-00200 SERVICE WATER ISI ISOMETRIC SHEET NO. 002 REVISION NO. 00 I I-SW-00300 SERVICE WATER ISI ISOMETRIC SHEET NO. 003 REVISION NO. 00 II-SW-00400 SERVICE WATER ISI ISOMETRIC SHEET NO. 004 REVISION NO. 00 I I-SW-00500 SERVICE WATER ISI ISOMETRIC SHEET NO. 005 REVISION NO. 00 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt

tttttttttttttttttttttttttttttttttttttttttttttttttttttttttt~tttttttttttttttt O'UTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY t SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ISONO PAGE 81 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION I I-SW-00800 SERVICE WATER ISI ISOMETRIC SHEET NO. 008 REVISION NO. 00 I I-SW-00900 SERVICE WATER ISI ISOMETRIC SHEET NO. 009 REVISION NO. 00 II-SW-01000 SERVICE WATER ISI ISOMETRIC SHEET NO. 010 REVISION NO. 00 II-SW-01100 SERVICE WATER ISI ISOMETRIC SHEET NO. 011 REVISION NO. 00 I I-SW-01200 SERVICE WATER ISI ISOMETRIC SHEET NO. 012 REVISION NO. 00 I I-SW-01300 SERVICE WATER ISI ISOMETRIC SHEET NO. 013 REVISION NO. 00 I I-SW-01400 SERVICE WATER ISI ISOMETRIC SHEET NO. 014 REVISION NO. 00 I I-SW-01500 SERVICE WATER ISI ISOMETRIC SHEET NO. 015 REVISION NO. 00 I I-SW-01600 SERVICE WATER ISI ISOMETRIC SHEET NO. 016 REVISION NO. 00 I I-SW-01700 SERVICE WATER ISI ISOMETRIC SHEET NO. 017 REVISION NO. 00 t t t tt tt t t t t t t t t t t \ t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t

++4444444444444444444444444444444444f444444444444444444444 +44444444444444f NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING REFERENCE CLUSTER LISTING 44 4 0 4 4 44 444 444 4444 DATA ELEMENT : ISONO PAGE .82 REVISION .RRS1 DATE 85/12/04 44444$ 44444440404t44t4444f444444444444ftff44tflf4444444444444 REFERENCE KEY DESCRIPTION II-SW-01800 SERVICE WATER ISI ISOMETRIC SHEET NO. 018 REVISION NO. 00 II-SW-01900 SERVICE WATER ISI ISOMETRIC SHEET NO. 019 REVISION NO. 00 II-SW-02000 SERVICE WATER ISI ISOMETRIC SHEET NO. 020 REVISION NO. 00 II-SW-02100 SERVICE WATER ISI ISOMETRIC SHEET NO. 021 REVISION NO. 00 II-SW-02200 SERVICE WATER ISI ISOMETRIC SHEET NO. 022 REVISION NO. 00 II-SW-03000 SERVICE WATER ISI ISOMETRIC SHEET NO. 030 REVISION NO. 00 I I-SW-03100 SERVICE WATER ISI ISOMETRIC SHEET NO. 031 REVISION NO. 00 II-SW-03700 SERVICE WATER ISI ISOMETRIC SHEET NO. 037 REVISION NO. 00 II-SW-04000 SERVICE WATER ISI ISOMETRIC SHEET NO. 040 REVISION NO. 00 II-SW"04200 SERVICE WATER ISI ISOMETRIC SHEET NO. 042 REVISION NO. 00 44444444444444444t4444t4444444444444444444444444444444444444444444444t44444

4444444444444444444444444444444t44444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44t4444fkff44f444t DATA ELEMENT : ISONO PAGE 83 REVISION RRS1 OATE 85/12/04 44444444444r444444444444444f44444444fft4444444444t44444444444444444444444444 REFERENCE KEY 0ESCRIPTION II-SW-04300 SERVICE WATER ISI ISOMETRIC SHEET NO. 043 REVISION NO. 00 II-SW-04800 SERVICE WATER ISI ISOMETRIC SHEET NO. 048 REVISION NO. 00 I I-SW-05100 SERVICE WATER ISI ISOMETRIC SHEET NO. 051 REVISION NO. 00 II-SW-05700 SERVICE WATER ISI ISOMETRIC SHEET NO. 057 REVISION NO. 00 II-SW-06200 SERVICE WATER ISI ISOMETRIC SHEET NO. 062 REVISION NO. 00 II-SW-06300 SERVICE WATER ISI ISOMETRIC SHEET NO. 063 REVISION NO. 00 II-SW-07200 SERVICE WATER ISI ISOMETRIC SHEET NO. 072 REVISION NO. 00 II-SW-08200 SERVICE WATER ISI ISOMETRIC SHEET NO. 082 REVISION NO. 00 II-SW-08600 SERVICE WATER ISI ISOMETRIC SHEET NO. 086 REVISION NO. 00 II-SW-08700 SERVICE. WATER IS I ISOMETRIC SHEET NO. 087 REVISION NO. 00 f4444v44444414f444f44444t44f4444444f444444444444444t4f44444444444f44

++4444444f4444444444444444444444444444444%44444444 44444444444444f NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44444$ 4444444444ft DATA ELEMENT : ISONO PAGE 84 + REVISION RRS 1

                                                             ~ DATE   85/12/04
  • 44444444444444444444444444444440t484444404444444444444444484444444444444444 REFERENCE KEY DESCRIPTION II-SW-08800 SERVICE WATER ISI ISOMETRIC SHEET NO. 088 REVISION NO. 00 II-SW-08900 SERVICE WATER ISI ISOMETRIC SHEET NO. 089 REVISION NO. 00 II-SW-09000 SERVICE WATER ISI ISOMETRIC SHEET NO. 090 REVISION NO. 00 II-SW-09100 SERVICE WATER ISI ISOMETRIC SHEET NO. 091 REVISION NO. 00 II-SW-09200 SERVICE WATER ISI ISOMETRIC SHEET NO. 092 REVISION NO. 00 II-SW-09300 SERVICE WATER ISI ISOMETRIC SHEET NO. 093 REVISION NO. 00 II-SW-09400 SERVICE WATER ISI ISOMETRIC SHEET NO. 094 REVISION NO. 00 II-SW-09500 SERVICE WATER ISI ISOMETRIC SHEET NO. 095 REVISION NO. 00 II-SW-09900 SERVICE WATER ISI ISOMETRIC SHEET NO. 099 REVISION NO. 00 II-SW-10000 SERVICE WATER ISI ISOMETRIC SHEET NO. 100 REVISION NO. 00 4444444f44444444404444444444444444444f4444f444f4444444444t4t444444444444444

ttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING tttttttttttttttttt REFERENCE CLUSTER LISTING DATA ELEMENT : ISONO PAGE REVISION

                                                                       '5 RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                           DESCRIPTION II-SW-10'100   SERVICE WATER  ISI ISOMETRIC SHEET NO. 101   REVISION NO. 00 I I-SW-10200   SERVICE WATER  ISI ISOMETRIC SHEET NO. 102    REVISION NO. 00 II-SW-10300    SERVICE WATER  ISI ISOMETRIC SHEET NO. 103    REVISION NO. 00 II-SW-10400    SERVICE WATER  ISI ISOMETRIC SHEET NO. 104    REVISION NO. 00 II-SW-10500    SERVICE WATER  ISI ISOMETRIC SHEET NO. 105    REVISION NO. 00 II-SW-10600    SERVICE WATER  ISI ISOMETRIC SHEET NO. 106    REVISION NO. 00 II"SW-10700    SERVICE WATER  ISI ISOMETRIC SHEET NO. 107    REVISION NO. 00 II-SW-10800    SERVICE WATER  ISI ISOMETRIC SHEET NO. 108    REVISION NO. 00 II-SW-11000    SERVICE WATER  ISI ISOMETRIC SHEET NO. 110    REVISION NO. 00 II-SW-11200    SERVICE WATER  ISI ISOMETRIC SHEET NO. 112    REVISION NO. 00

444444444444444444+ 4 NUTECH PRI SIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 4 DATA ELEMENT : ISONO PAGE 86 REVISION RRS1 DATE 85/12/04 444444400444444440444440t4444444444tff444444044444444444444444044ft44t44 REFERENCE KEY DESCRIPTION II-SW-11700 SERVICE WATER ISI ISOMETRIC SHEET NO. 117 REVISION NO. 00 I I-SW-12000 SERVICE WATER ISI ISOMETRIC SHEET NO. 120 REVISION NO. 00 I I-SW-12600 SERVICE WATER ISI ISOMETRIC SHEET NO. 126 REVISION NO. 00 I I-SW-12700 SERVICE WATER ISI ISOMETRIC SHEET NO. 127 REVISION NO. 00 I I-SW-12800 SERVICE WATER ISI ISOMETRIC SHEET NO. 128 REVISION NO. 00 I I-WG-00600 WASTE PROCESSING (GAS) ISI ISOMETRIC SHEET NO. 006 REVISION NO. 00 II-WG-02200 WASTE PROCESSING (GAS) ISI ISOMETRIC SHEET NO. 022 REVISION NO. 00 I I-WL-00100 WASTE PROCESSING (LIQUID) ISI ISOMETRIC SHEET NO. 001 REVISION NO. 00 I I-WL-00700 WASTE PROCESSING (LIQUID) ISI ISOMETRIC SHEET NO. 007 REVISION NO. 00 REFERENCE DUMMY: USED TO ACCOUNT FOR NON-APPLICABLE CODE ITEMS 444044444444 t44 44444444 444440444 44 4444444 444 44 4I 4444444444444444444444444444

444444444t4t444444444f444ft4f44ft44444t444444444t44444 44444444444 4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : SYSTEM PAGE,165 REVISION RRS1 DATE 85/12/04 REFERENCE KEY DESCRIPTION AC AUXILIARY STEAM CONDENSATE AE AIR EVACUATION AF AUXILIARY FEEOWATER AS AUXILIARY STEAM BD SLOWDOWN BR BORON RECYCLE CA CAUSTIC AND ACID CB CONTAINMENT BUILDING VACUUM, RELIEF CC COMPONENT COOLING WATER CD HVAC CONDENSATE WASTE CE CONDENSATE CF CHEMICAL FEED CG CARBON DIOXIDE CH CHILLED WATER SUPPLY CL CHLORINATION

 +44444444444444444444f      444444444444444444444444444444444m     444444444444444 NUTECH                                                                  PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT      UNIT  1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : SYSTEM                   PAGE  '66 44440444444400 REVISION DATE RRS 85/12/04 1

4 44444 4 444444444444 f 444 4444444444444444444444444444$ 444444444 REFERENCE KEY DESCRIPTION CONTAINMENT BUILDING HYDROGEN CONTROL CO COMPRESSED AIR CP CONTAINMENT BUILDING PURGE CS CHEMICAL AND VOLUME CONTROL CT CONTAINMENT SPRAY CW CIRCULATING WATER CX CHILLED WATER RETURN OW DEMINERALIZED WATER EA DIESEL STARTING AIR ES EXTRACTION STEAM PRIMARY FILTER MAKE-UP WATER FO FUEL OIL FP FIRE PROTECTION FEED WATER HD HEATER DRAIN 44444444444444444444444444444444ft4444444444444444444444444444

44444t44444444ff'444444444444444444t4444tt44444440444t+ 444444t44444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44444f444444444444 DATA ELEMENT : SYSTEM PAGE ',167 4 REVISION RRS 1 DATE 85/12/04 444444444444t4444444444t44t4444444444444444444444444444040444404444444444t4 REFERENCE KEY DESCRIPTION HV HEATER VENTS HY HYDROGEN IA INSTRUMENT AIR LO LUBE OIL LT LEAK RATE TESTING LU STEAM GENERATOR WET LAY UP MISCELLANEOUS DRAINS COOLING TOWER MAKE UP PLANT WATER 1 MS MAIN STEAM NI NITROGEN OX OXYGEN PM REACTOR MAKE UP WATER PP PENETRATION PRESSURIZATION PW POTABLE WATER RC REACTOR COOLANT 444tkt444444444440444f4844444ff4f444tt44444444f444444t4444444444

444444t444444f440f4444844444444444440440440400444444440 444444444044044 4 NUTECH PRISIM 4 CAROLINA POWER 6 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : SYSTEM PAGE 168 4 REVISION RRS1 DATE 85/12/04 '044444444444440044444444444444440044440044444444444444444444444444444444404 REFERENCE KEY DESCRIPTION RH RESIDUAL HEAT REMOVAL SA SERVICE AIR SC SCREEN WASH SF SPENT FUEL POOL COOLING AND CLEANUP SI SAFETY INJECTION SP SAMPLING (NUCLEAR) SW SERVICE WATER TB COOLING TOWER SLOWDOWN VL VALVE LEAKOFF WC WASTE PROCESSING BUILDING COOLING WATER WG WASTE PROCESSING (GAS) WL WASTE PROCESSING (LIQUID) WS SECONDARY WASTE TREATMENT 44444444444444444444f4444444444444444f444444444444444f44444tftkf444444

~

  , 44444444444444444444444444444444444444                                 4444444t4444444 NUTECH                                                                       PRISIM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                         PAGE           5 REVISION   RRS1 DATE  85/12/04 440444444444444444444444444440     t4 4 4 4 4 4 4 4 4                84448444444t44444444 REFERENCE KEY                       VALVE COMPONENT DESCRIPTION
                  +                                                                        +
                  ++++++++++++++++++++++++             VALVES  +tt+++++++++++++++++++++++
                  +   EXAMINATION CATEGORIES            B-L-1, B-L-2,  AND C-G (81W)       +

AVALINT VAL I NT VALVE INTERNAL (INSIDE) SURFACES AVBW VAL BDY VALVE BODY WELD , PRESSURE RETAINING WELD IN THE VALVE BODY OR VALVE BONNET 4444444f44444444444tkf4444444444444444444444404444444

0 44k+++444f44444f444444f444f44444f444f444444444444444444 440444t44444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY 4 SYSTEM 4 REFERENCE CLUSTER LISTING 4444444444t4444444 DATA ELEMENT : COMPDES PAGE , 6 REVISION . RRS 1 DATE 85/12/04 44444444t4404444444444t444444444444444444444t444444444044 REFERENCE KEY BOLTING COMPONENT DESCRIPTION

              +                                                                 +
              ++++++++++++++++++++++++      BOLTS  +++++++++++++++++++++++++++
              +    EXAMINATION CATEGORIES B-G-1, B-G-2, AND C-D (81W)           +

BBOLT BOLT BOLT (B-G-1, C-D) BBOLT,S SH BOLT BOLT, SOCKET HEAD (B-G-1, C-D) BBUSH BUSHING BUSHING (B-G-1, C-D) BCONO C BOLT CONOSEAL BOLTING (8-G-2) BFBC FLG CON FLANGE BOLTED CONNECTION (8-G-2) BFLGSUR FLG SUR FLANGE SURFACE (B-G-1, C-D) BFSC FLG CON FLANGE STUD CONNECTION (2 NUTS PER STUD) BFT FLG THR FLANGE THREADS (B-G-1, C-D) BLIG LIGAMNT LIGAMENT (B-G-1, C-D) LIGAMENT APPEARS IN THE OLDER EDITIONS OF THE CODE. THE NEW TERM IS FLANGE SURFACE FOR THE 1" ANNULUS 8 EACH STUD. 4t44444444f44448444444

 +444444444444444444tfff444444ft4444f44ff44fflf444444444f        444444444444f4f NUTECH                                                               PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING               44t444444444444444 DATA ELEMENT : COMPDES                  PAGE        x  7 REVISION   RRS1 4 DATE   85/12/04 444844444'404444444444404004444444444444444444444440444440444 REFERENCE KEY                    BOLTING COMPONENT DESCRIPTION BNUT           NUT NUT   (B-G-1, C-D)

BPHB HOS BLT PUMP HOUSING BOLTING (8-G-2) BPSB SEL BLT PUMP SEAL BOLTING (8-G-2) BSTUD STUD STUD (B-G-1, C-D) BVBB BON BLT VALVE BONNET BOLTING (8-G-2) BVPB PAK BLT VALVE PACKING BOLTING (8-G-2) BWASH WASHER WASHER (B-G-1, C-0) 444444444444444440404444f444444444444444444444444444444t4444t444444444440t4

4444444444444444444444444444444444404444444+ 444444444444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : COMPDES PAGE ,. 8 REVISION RRS1 REFERENCE KEY PRESSURE TESTING ZONE COMPONENT DESCRIPTION

               +                                                                +
               +++++++++++++++    PRESSURE  TESTING ZONES   +++++++++++++++++++
               + EXAMINATION CATEGORIES B-P, C-H, D-A, D-B, AND D-C (81W) +

EEX?5SN EX COMP COMPONENTS EXEMPT FROM ALL SECTION XI NON-DESTRUCTIVE EXAMINATION EXCEPT VT-2. SEE ITEMNO 75S-01CSOEX FOR CLASS 2 COMPONENTS AND 75S-01050EX FOR CLASS 3 COMPONENTS FOR EXAMPLE : THE FIRST WELD ON A BRANCH LINE LESS THAN 4 NOMINAL PIPE SIZE COULD BE ENTERED IN THE DATA BASE WITH ITEMNO ===> 75S-01CSOEX EEX75S1 EX COMP COMPONENTS EXEMPT FROM ALL SECTION XI NON-DESTRUCTIVE EXAMINATION EXCEPT VT-2. SEE ITEMNO 755-0181. 19, 75S-0182.10, 75S-0183. 9, 755-0184.11, 75S-0185. 8, AND 755-0186. 8 FOR ISI CLASS 1 COMPONENTS FOR EXAMPLE: PRESSURIZER CIRCUMFERENTIAL SHELL WELDS BETWEEN SHELL COURSES ===> 755-0182. 10 EEX78S EX COMP COMPONENTS EXEMPT FROM ALL SECTION XI NON-DESTRUCTIVE EXAMINATION EXCEPT VT-2. SEE ITEMNO 78S-O?815.EX FOR CLASS 1 COMPONENTS; 78S-O?C7.EX FOR CLASS 2 COMPONENTS; AND 78S-0? D. 1EX, 78S-O?0.2EX, AND 78S-O?0.3EX FOR CLASS 3 COMPONENTS. FOR EXAMPLE : PRESSURIZER CIRCUMFERENTIAL SHELL WELDS BETWEEN SHELL COURSES ===> 78S-O?815.EX EEX81W EX COMP COMPONENTS EXEMPT FROM ALL SECTION XI NON-DESTRUCTIVE EXAMINATION EXCEPT VT-2. SEE ITEMNO 81W-01815.EX FOR CLASS 1; 81W"01C7.EX FOR CLASS 2; 81W-0101.EX, 81W-0102.EX, AND 81W-01D3.EX FOR CLASS 3; AND 81W-01E9.EX FOR CLASS MC (IWE) FOR EXAMPLE: PRESSURIZER CIRCUMFERENTIAL SHELL WELDS BETWEEN SHELL COURSES ===> 81W-01815.EX 4444444'4444444t44440444f44444444tlf4444444444f44444444440444044444444444444

44444444444fft4844048444444444t44tt44t444444t44444444ft ff4444444440444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 4 4 4 '0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 DATA ELEMENT : COMPDES PAGE 9 REVISION RRS1 DATE 85/12/04 444444444444444444444444444444444444444444444444444444444444444444444444444 REFERENCE KEY PRESSURE TESTING ZONE COMPONENT DESCRIPTION EZONE,O OP ZONE OPERATIONAL PRESSURE TESTING ZONE EZONE,S ST ZONE STATIC PRESSURE TESTING ZONE 4444444440044444444444444444444444444444444444444444444444444444444t4444444

S ++444t4444444444f444t44f44044f4444444f4444t4444444444f4f44 44f444444f44f44 NUTECH PRISIM 4 CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES PAGE , - 10 REVISION RRS 1 e

                                                             ~ DATE  85/12/04 44444444444'44444444444444444444 REFERENCE KEY   HANGERS  (ALL TYPES INCLUDING SNUBBERS)   COMPONENT DESCRIPTION
               +                                                                  +
               +++++++++++++++++++++++   HANGERS   ++++++++++++++++++++++++++
               +      EXAMINATION CATEGORIES F-A, F-B, AND F-C (81W)

HA ++% DIRECTIONS AND MOMENTS AS NOTED IN THE FUNCTIONAL DESCRIPTIONS FOR EACH TYPE OF HANGER CORRESPOND TO THE PRINCIPAL FORCES (+8- FX, +8- FY, AND +L- FZ) AND PRINCIPAL MOMENTS (MX, MY, AND MZ). A HANGER THAT RESTRICTS FORCES IN A "DIRECTION" WOULD BE RIGID IN TENSION AND COMPRESSION IN THAT DIRECTION. +++ HANCM ANCHOR ANCHOR (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 3 DIRECTIONS AND 3 ROTATIONAL MOMENTS HANCW ANCHOR ANCHOR (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 3 DIRECTIONS AND 3 ROTATIONAL MOMENTS HARSM ADJ STR ADJUSTABLE RIGID STRUT (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. HARSW ADJ STR ADJUSTABLE RIGID STRUT (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. HBTWM 3WY BOX THREE WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 3 DIRECTIONS (TENSION AND COMPRESSION) 40444444444t444444044444444444444444tf0444444444444444444444444444444t44444

4444f444484444404444404444444044444444t44f444444f4444444 440444044f44f44 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 44t44444 DATA ELEMENT : COMPDES PAGE , 11 REVISION RRS1 DATE 85/12/04 444444444444444444444444444444444444444444444440444444t4444044t4444444t REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS) COMPONENT DESCRIPTION HBTWW 3WY BOX THREE WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 3 DIRECTIONS (TENSION AND COMPRESSION) HCONM CONSTNT CONSTANT (MECHANICAL ATTACHMENT TO COMPONENT) ACTS IN TENSION ONLY, SPRING/LEVER ASSEMBLY PROVIDES CONSTANT RESTRAINING FORCE HCONW CONSTNT CONSTANT (WELDED ATTACHMENT TO COMPONENT) ACTS IN TENSION ONLY, SPRING/LEVER ASSEMBLY PROVIDES CONSTANT RESTRAINING FORCE HGUDM GUIDE GUIDE (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION) HGUDW GUIDE GUIDE (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION) HHSBM HSNUBBR HYDRAULIC SNUBBER (MECHANICAL ATTACHMENT TO COMPONENT) HHSBW HSNUBBR HYDRAULIC SNUBBER (WELDED ATTACHMENT TO COMPONENT) HMSBM MSNUBBR MECHANICAL SNUBBER (MECHANICAL ATTACHMENT TO COMPONENT) 444444444'4444t444444444444444444444444440444444f444444444444444444404044444

 ~

e

+ 444444404t4404444444t4t444444444444444444444f4444444f444 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4 DATA ELEMENT : COMPDES PAGE,RRS112 REVISION DATE 85/12/04 444444444f444444ftt404440444444444ff444f4444f44444444444444444f444f44f44444 REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS) COMPONENT DESCRIPTION HMSBW MSNUBBR MECHANICAL SNUBBER (WELDED ATTACHMENT TO COMPONENT) HOWBM 1WY BOX ONE WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. HOWBW 1WY BOX ONE WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. HRESM RESTRNT RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. E.G.) A STRUT HRESW RESTRNT RESTRAINT (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. E.G.) A STRUT HRRSM R STRUT RIGID ROD STRUT (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS) . RIGID IN TENSION AND COMPRESSION. HRRSW R STRUT RIGID ROD STRUT (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. 4444444444444444444444444444444444444444444t40444444444444444044t444

 +444444444444444444 4444444444444440444444404440444t4f444+                                                             4444444444tff44 NUTECH                                                                                                                         PRISIM          4 CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING                                                  4444444 44 444444444 DATA ELEMENT : COMPDES                                                     PAGE                    13 REVISION            RRS1 DATE        85/12/04 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 '4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 REFERENCE KEY                 HANGERS         (ALL TYPES INCLUDING SNUBBERS)                                 COMPONENT DESCRIPTION HRTSM                         T STRUT RIGID TELESCOPING STRUT (MECHANICAL ATTACHMENT TO COMPONENT)

RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. HRTSW T STRUT RIGID TELESCOPING STRUT (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN ONE DIRECTION (ALONG ITS AXIS), RIGID IN TENSION AND COMPRESSION. HSSAM ARRESTR SHOCK AND SWAY ARRESTOR (MECH. ATTACHMENT TO COMPONENT) A PRECOMPRESSED SPRING THAT PROVIDES A RESTRICTING FORCE PROPORTIONAL TO DEFLECTION IN BOTH TENSION AND COMPRESSION. NOTE: SOME SNUBBERS ARE CALLED SHOCK AND SWAY ARRESTORS. 00 NOT USE HSSAM FOR SNUBBERS HSSAW ARRESTR SHOCK AND SWAY ARRESTOR (WELDED ATTACHMENT TO COMPONENT) A PRECOMPRESSED SPRING THAT PROVIDES A RESTRICTING FORCE PROPORTIONAL TO DEFLECTION IN BOTH TENSION AND COMPRESSION. NOTE: SOME SNUBBERS ARE CALLED SHOCK AND SWAY ARRESTORS. DO NOT USE HSSAW FOR SNUBBERS HSUPM SUPPORT SUPPORT (MECHANICAL ATTACHMENT TO COMPONENT) A HANGER THAT ACTS IN TENSION ONLY, OR COMPRESSION ONLY E.G. 1) A DEAD WEIGHT HANGER RIGID IN TENSION ONLY E.G. 2) A STANCHION ON A SLIDING PAD RIGID IN COMPRESSION 44444t44444444444444444444f4444444444f44444444t444444444444444444444444

tttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRI SIM CAROLINA POWER 8 LIGHT CO MPANY t SYSTEM REFERENCE CLUSTER LISTING tttttttttttttttttt

                                                                      '14 DATA ELEMENT : COMPDES                PAGE REVISION   RRS1 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt DATE REFERENCE KEY HANGERS   (ALL TYPES INCLUDING SNUBBERS) COMPONENT DESCRIPTION HSUPW         SUPPORT SUPPORT (WELDED ATTACHMENT TO COMPONENT)

A HANGER THAT ACTS IN TENSION ONLY, OR COMPRESSION ONLY E.G. 1) A DEAD WEIGHT HANGER RIGID IN TENSION ONLY E.G. 2) A STANCHION ON A SLIDING PAD RIGID IN COMPRESSION HTWBM 2WY BOX TWO WAY BOX RESTRAINT (MECHANICAL ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION) HTWBW 2WY BOX TWO WAY BOX RESTRAINT (WELDED ATTACHMENT TO COMPONENT) RESTRICTS FORCES IN 2 DIRECTIONS (TENSION AND COMPRESSION) HUBTM U-BOLT U-BOLT (MECHANICAL ATACHMENT TO COMPONENT) HUBTW U-BOLT U-BOLT (WELDED ATACHMENT TO COMPONENT) HVARM VARABLE VARIABLE (MECHANICAL ATTACHMENT TO COMPONENT) ACTS IN TENSION ONLY, A SPRING ASSEMBLY WHERE THE RESTRICTING FORCE IS PROPORTIONAL TO DEFLECTION HVARW VARABLE VARIABLE (WELDED ATTACHMENT TO COMPONENT) ACTS IN TENSION ONLY, A SPRING ASSEMBLY WHERE THE RESTRICTING FORCE IS PROPORTIONAL TO DEFLECTION

0

444444444444444444444444444444444t44444444444 444t44f44t444f4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING %4f44444t44444 4 DATA ELEMENT : COMPDES PAGE 15 REVISION RRS1 DATE 85/12/04 4444444444t444f444444444444444444t444440444444t44444f44 REFERENCE KEY HANGERS (ALL TYPES INCLUDING SNUBBERS) COMPONENT DESCRIPTION HWHPM WHI PRES WHIP RESTRAINT (MECHANICAL ATTACHMENT) A HANGER DESIGNED FOR PIPE BREAK EVENTS THAT IS CHARACTERIZED BY LARGE GAPS ( > 1/8 INCH ) AND ENERGY ABSORBING (CRUSHABLE) MATERIALS EXEMPT FROM EXAMINATION BY INTERPRETATION XI-80-02 SEE ITEMNO 81W-01F1.EX, 81W-01F2.EX, AND 81W-01F3.EX HWHPW WHIPRES WHIP RESTRAINT (WELDED ATTACHMENT TO COMPONENT) A HANGER DESIGNED FOR PIPE BREAK EVENTS THAT IS CHARACTERIZED BY LARGE GAPS ( > 1/8 INCH ) AND ENERGY ABSORBING (CRUSHABLE) MATERIALS EXEMPT FROM EXAMINATION BY INTERPRETATION XI-80-02 SEE ITEMNO 81W-01F1.EX, 81W-01F2.EX, AND 81W"01F3.EX HXXXX TEMPORARY COMPONENT DESCRIPTION VALIDATION CHECK FOR HANGER LOAD 4444444444444t444444444f444440444444f4f4ff44444f444tff4404444444440

a~44444444444444444444444444444444444444444444444444444444 444444444404444 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES PAGE 16 REVISION ,RRS1 4 DATE 85/12/04 4444444444444444444444444444t44t444t444044444444444444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION

               +++++++++++++t++++++++++    PIPING   +++t++++++++++++++++++++++
               +   EXAMINATION CATEGORIES   B-F, B-J, B-K-1, C-C, C-F,         +
               +                    D-A, D-B,  AND 0-C (81W)                   +

PBC, +++ A BRANCH CONNECTION WITHOUT CIRCUMFERENTIAL WELDS +++ PBC,A BC UNK BRANCH CONNECTION, TYPE UNKNOWN PBC,E ELBOWLT ELBOWLET PBC,HC HALFCPL HALF COUPLING PBC,LOL LATROLT LATEROLET PBC,LSP LSWEEPT LATERAL SWEEPOLET PBC,S SOCKOLT SOCKOLET PBC,SWP SWPOLET SWEEPOLET PBC,T THREDLT THREADOLET 4444444444444448t444ft444444444ft444444444044fffkf4f4444444444444444444444

44444444444444t44444444t4444444444444 4444444444444444444 C44444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : COMPDES PAGE 17 REVISION RRS1 DATE 85/12/04 440444440444444444444444444440444444f44 44444444r4444444444444044044444444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PBC,TE THERMOWELL TEMPERATURE ELEMENT PBC,W WELDOLT WELDOLET PBCC, +++ A BRANCH CONNECTION WITH CIRCUMFERENTIAL WELDS ONLY +++ PBCC,CR CROSS PBCC,EX EXTRUD PIPE EXTRUSION PBCC,L LATERAL PBCC,T TEE PBCC,TR RED TEE TEE, REDUCING PC, +++ CIRCUMFERENTIAL PIPING WELD +++ PC,ACC ACCUM ACCUMULATOR PC,CAP CAP PC,EXPJ EXP JNT EXPANSION JOINT 444444444444f4444444444444444t44t444444ff444t44f4444444

44444444444444444444444444f444444444444444444444444+ f44f444444444f4 4'UTECH PRISIM CAROLINA POWER 8 LIGHT COM PANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : COMPDES PAGE 18 REVISION RRS1 DATE 85/12/04 444444444W444444444444444444444444444444444444 4444444444444444t444f REFERENCE KEY PIPING COMPONENT DESCRIPTION PC,FE FLOW EL FLOW ELEMENT PC,MAN MANIFLD MANIFOLD PC,NOZ NOZZLE PC,NOZW NOZ WLD WELD IN NOZZLE FLANGE PC,PB P BEND PIPING BEND PC, PIPE PIPE PC,PUMP PUMP PC,RED REDUCER PC,REDI RED INS REDUCING INSERT PC,SDFP SUMP PL SUMP DRAIN FILTER PLATE PC,SE SAFEEND SAFE END PC,SEE SAFEEND SAFE END EXTENSION 44444444444444f444tf44444tt44444444444444444444444444f4f44f444444444t44444f

++44444444f444444444t4444f44444444444444f444f444444444444+ 444444444t44044 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4 DATA ELEMENT : COMPDES PAGE 19 REVISION RRS1 DATE 85/12/04 44444444444f444444444444444f44I44444444444444444444fff4444444f4044f44fff444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PC,TRS TRANS TRANSITION PIECE PC,TS T STRNR TEMPORARY STRAINER PC,VENC VENTURI CAVITATING VENTURI PC,VLV VALVE PE ~

               +++ ELBOWS +++

PE,ELR ELB ELR ELBOW, EXTRA LONG RADIUS PE,LR ELB LR ELBOW, LONG RADIUS PE,RED RED ELB REDUCING ELBOW PE,SR ELB SR ELBOW, SHORT RADIUS PELBOW ELBOW ELBOW, RADIUS UNKNOWN PF, +++ FLANGES +++ 044444444444444'444440t4444444444444'4004004440t444444t4044444444444440444444

  ~1 dl

440444444440044 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444044444 DATA ELEMENT : COMPDES PAGE ~. 20 REVISION RRS 1 DATE 85/12/04 444488444444444t4444444444t44444t44444444444444444444444f44444f44444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PF,A FLG UNK FLANGE, TYPE UNKNOWN PF,B FLG BLN FLANGE, BLIND PF,O FLG ORF FLANGE, ORIFICE PF,RED FLG RED FLANGE, REDUCING PF,RFWN FLG RFW FLANGE, RAISED FACE WELD NECK PF,RWNR FLG RWR FLANGE, RAISED FACE WELD NECK REDUCING PF,SO FLG SLP FLANGE, SLIP ON PF,SW +++ FLANGE, SOCKET WELDED (SHOULD BE ENTERED AS PSW,F) +++ PF,WN FLG WN FLANGE, WELD NECK PF,WNGF FLG WNG FLANGE, WELD NECK GROOVED FACE PF,WNO FLG WNO FLANGE, RAISED FACE WELD NECK ORIFICE 888444408040444t44444444444444444444444444444444444440444t44t44444t44444444

0 444444444444f44444444444444444444~ 444444f44444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES <<.PAGE 21 4 REVISION RRS1 DATE 85/12/04 4444448044444444444444444444444404444444f444444444t44444444444404t444tt4444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PF,WNTF FLG WNT FLANGE, WELD NECK TONGUE FACE PI +++ INTEGRALLY WELDED ATTACHMENTS +++ PI, +++ EXAMINATION CATEGORIES 8-K- 1, C-C, D-A, +++

              +++              D-B, AND D-C (81W)                 +++

PI, CL CENTER PIPE SUPPORT, CENTERING LUG PI, CLVN CLEVIS WELDED LUGS, FORMING A CLEVIS, NOT FULL PENETRATION PI, FHA TYPEI IA FLUED HEAD, TYPE IIA PI, FHB TYPEIIB FLUED HEAD, TYPE IIB PI, FHI TYPE I FLUED HEAD, TYPE I PI, HL HANGER PIPE SUPPORT, HANGER LUG PI,LUGF LUG, FP LUG, FULL PENETRATION WELD PI, LUGN LUG, PP LUG, NOT FULL PENETRATION (FILLET OR PARTIAL PENETRATION) e8884t8%4%444444444444tt4444404404444444444444444404044444444444444444444%4

~404444444444444444t444444444t44tt444444444404444440444'4 NUTECH                                                              PRISIM CAROLINA POWER    8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING               44444444 4 44444  444 4 DATA ELEMENT : COMPDES                PAGE,         ~ 22 REVISION '.RRSl DATE   85/12/04 4444444t4444tt444444444t44t444444t04444440444t44444444404444t444t4440444440 REFERENCE  KEY                    PIPING COMPONENT DESCRIPTION PI,PSU          SUPPORT PIPE SUPPORT,   TYPE UNKNOWN PI,R            RING RING SUPPORT PI, SADL        SADDLE PI, STAN        STANCHN STANCHION PI,TRUN         TRUNNON TRUNNION PLSW,           +++ LONGITUDINAL SEAM WELDS +++

PLSW,C CRSSEAM LONGITUDINAL SEAM WELD, CROSS PLSW,EI ELBSEAM LONGITUDINAL SEAM WELD'LBOW INSIDE ARC PLSW,EO ELBSEAM LONGITUDINAL SEAM WELD'LBOW OUTSIDE ARC PLSW,P LNGSEAM LONGITUDINAL SEAM WELD, PIPE PLSW,R REDSEAM LONGITUDINAL SEAM WELD, REDUCER 044t4444444t444444tttt4444444444444f4444444444444ft4444444404tt444f4444f4

i444t4444 eeyeekgeg4444444444444444444444f444f44444444444 s444444444444444 NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444404444 DATA ELEMENT : COMPDES PAGE 23 REVISION RRS 1 "2 DATE 85/12/04 4444440444444444444404404444444440444r4448448444444 REFERENCE KEY PIPING COMPONENT DESCRIPTION PLSW,T TEESEAM LONGITUDINAL SEAM WELD, TEE PP, +++ PENETRATION COMPONENTS +++

                + USE  PI,FHA  OR  PI,FHB FOR INTEGRAL ATTACHMENT FLUED HEADS +

PP,ENDP PPLATE PENETRATION END PLATE PP,FHS FL HEAD FLUED HEAD, SINGLE (WITH A WELD IN THE PENETRATION) PP,FHSI FL HEAD FLUED HEAD, SINGLE INTEGRAL (ALL ONE PIECE) PP,FHT FL HEAD FLUED HEAD, TRIPLE (WITH A WELD IN THE PENETRATION) PP,FHTI FL HEAD FLUED HEAD, TRIPLE INTEGRAL (ALL ONE PIECE) PP,PIPE PENPIPE PENETRATION PIPE (THE PIPE SUPPLIED BY THE CONTAINMENT SUPPLIER RATHER THAN THE PIPING SUPPLIER) PP PLT

   ~            PPLATE PENETRATION PLATE PP,TRP           PENPLT TORUS SHELL PENETRATION REINFORCEMENT PLATE 444444444444444t44f44444444444t4444t44444f444444f44444444444t44444tft44t4f4

ittttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : COMPDES PAGE 24 REVISION RRS 1 DATE 85/12/04 tttttttttttttttttttt ttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PIPING COMPONENT DESCRIPTION PSW, +++ SOCKET WELDS +++ PSW,C CAP PSW,CPL COUPLNG COUPLING PSW,CPR RCUPLNG REDUCING COUPLING PS' ELBOW PSW,F FLANGE PSW,FO ORIFICE FLANGE, ORIFICE PSW,HC HLF CUP HALF COUPLING PSW,MAN MANIFLD MANIFOLD PSW,P PIPE PSW,PB P BEND PIPING BEND PSW,RED REDUCER tttttttttttttttttttttttttttttttttttttttttttttttttttttttttt

444t4444444444444f44444044444 44t4444440444444444444444+ 444444t4t4f44f4 NUTECH PRISIM CAROLINA POWER 8 LIGHT CO MPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES PAGE 25 REVISION RRS1 DATE 85/12/04 44444444$ 444444444444444444444444444444fay f 444 4444444444444444444444440444t@4I REFERENCE KEY PIPING COMPONENT DESCRIPTION PSW, RIN RED INS REDUCING INSERT PSW,T TEE PSW,TR RED TEE REDUCING TEE PSW,UN UNION PSW,VLV VALVE 44444444444444444444444444444444444444444f44444444444444444f44444444444f44f

w+4444444%484844444444444404444404tf444440444444444f444444 44f444444t444ff NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : COMPDES PAGE = '26 REVISION RRS 1 DATE 85/12/04 4044444444f44444444404t444444f444444444t404444440404444t440440 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION

               +                                                                +
               +++++++++++++    PWR REACTOR VESSEL INTERNALS +++++++++++++++
               +        EXAMINATION CATEGORIES 8-N-1 AN B-N-2 (81W)             +

RAKUSP AKUSP ALIGNMENT KEYWAYS UPPER SUPPORT PLATE RAP ACC PLT ACCESS PLATE RBBBC BBBC BAFFLE BOLTING AND BAFFLE CORNERS RCBFFN CBFFN CORE BARREL FLANGE FLOW NOZZLES RCBMPGW CBMPGW CORE BARREL MID-PLANE GIRTH WELD RCBNVIS CBNVIS CORE BARREL OUTLET NOZZLE/VESSEL INTERFACE SURFACE RCRDGT CRDGT CONTROL ROD DRIVE GUIDE TUBE (INTERNAL INSPECTION OF GUIDE TUBE) RCRODS CRODS CONTROL RODS RCSC CSC CORE SUPPORT COLUMN 48444t444fkt444444444444444440444t404t444444444444444444f444444444444444404

0 44444444484444444444444t44444444444404444444444444044444 444444f40444f44 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 0444444444444444 DATA ELEMENT : COMPDES PAGE 27 REVISION RRS1 DATE B5/12/04 444444444444444444444444444444444444444044444444444444444444444444444444444 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION RCSPACB CSPACB CORE SUPPORT PLATE ATTACHMENTS TO CORE BARREL RCSS CSS CORE SUPPORT STRUCTURES RFTCBW FTCBW FLANGE TO CORE BARREL WELD RGTAUCP GTAUCP GUIDE TUBE ATTACHMENTS TO UPPER CORE PLATE RHAVAP HAVAP HEAD 8 VESSEL ALIGNMENT PINS (MATING SURFACES 8 ATTACHMENTS) RIGC IGC INSTRUMENT GUIDE COLUMNS RINT INT SUR INTERIOR SURFACE RISB ISB IRRADIATION SPECIMEN BASKETS RLCP LCP LOWER CORE PLATE RLCPFAP LCPFAP LOWER CORE PLATE FUEL ALIGNMENT PINS 44444444f444444f4444t444444444ff44fff4444444f44444444444t4444444444f4444444

444444444444444444444444 444444444444444'4444444444444444 444444444444444 NUTECH PRIS(M CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : COMPDES PAGE 28 REVISION RRS 1 DATE 85/12/04 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION RLCSC LCSC LOWER CORE SUPPORT COLUMNS RLCSCB LCSCB LOWER CORE SUPPORT COLUMN BOLTING RLSC LSC LOWER SUPPORT COLUMNS RNPLS NPLS NEUTRON PANEL LOCKING SCREWS RRCCADS RCCADS ROD CLUSTER CONTROL ASSEMBLY (RCCA) DRIVE SHAFTS RRCCAHS RCCAHS ROD CLUSTER CONTROL ASSEMBLY (RCCA) HUBS/SPIDERS RRS/LCS RS/LCS RADIAL SUPPORTS/LOWER CORE SUPPORTS RSCSA SCSA SECONDARY CORE SUPPORT ASSEMBLY RTC TC THERMOCOUPLE CONDUITS RTFM TFM THERMOCOUPLES AND FLOW MIXERS 444444444444444444444444444444440444f444f44tf4tffff4444t44444444f400t44ftf4

44444448%4444444444444444444444444404t444444 NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES PAGE 29 REVISION RRS1 DATE 85/12/04 St44444t4444444444444444ff44444444444444444444 44440444444444444440444444444 REFERENCE KEY PWR VESSEL INTERNAL COMPONENT DESCRIPTION RTSF TSF THERMAL SHIELD FLEXURES RUCPAK UCPAK UPPER CORE PLATE ALIGNMENT KEYWAYS RUCPFAP UCPFAP UPPER CORE PLATE FUEL ALIGNMENT PINS RUIAKCB UIAKC8 UPPER INTERNALS ALIGNMENT KEYS IN CORE 8ARREL RUSC USC UPPER SUPPORT COLUMNS RUSF USF UPPER SUPPORT FLANGE (LOCKING DEVICE WELDS) 4444444444f4444444444444444tbt44f4444444f44444444444444444444444t4444444044

tf44t4444t44t44444f4444444tff44444f4440444444+ 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444444444444044 DATA ELEMENT : COMPDES PAGE, REVISION 30 RRS1 DATE 85/12/04 4444444444444444444444444440444044444444444t4444444044444444444 REFERENCE KEY BWR VESSEL INTERNAL COMPONENT DESCRIPTION

               +                                                              +
               +++++++++++++   BWR REACTOR VESSEL INTERNALS +++++++++++++++
               +        EXAMINATION CATEGORIES 8-N-1 AND 8-N-3 (81W)

SCORES CORESUP REACTOR VESSEL CORE SUPPORT STRUCTURE SINT INT SUR REACTOR VESSEL INTERIOR SURFACES SINTBL INTATCH REACTOR VESSEL INTERIOR ATTACHMENTS - BELTLINE SINTNBL INTATCH REACTOR VESSEL INTERIOR ATTACHMENTS - NON BELTLINE 4444444444444444444444444444444t404t4444t44444444f4444440444444t444404f4f44

 +ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH                                                           PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM t

REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : COMPDES PAGE 31 REVISION RRS1 t DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PWR PUMP COMPONENT DESCRIPTION

             +++++++++++++++++++++   PWR PUMPS   +++++++++++++++++++++++++++
             +      EXAMINATION CATEGORIES B-M-1, B-M-2, AND C-G (81W)     +

TCHP1A CH PMPA CHARGING WATER PUMP A TCHP1 8 CH PMPB CHARGING WATER PUMP 8 TCHPlc CH PMPC CHARGING WATER PUMP C TFLYWHL FLYWHL FLYWHEEL TIFEET FEET PUMP SUPPORT FEET TPUINT PUMP INT PUMP INTERNALS TPUMPCW PUMPCW PUMP CASING WELD TRCP RC PMP REACTOR COOLANT PUMP TRCP1A RC PMPA REACTOR COOLANT PUMP A

+ 44f4f4444444444444 44444444444444444444444444444404444444 444844444484044 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444440444044444444 DATA ELEMENT : COMPDES PAGE " 32 REVISION RRS1 DATE 85/12/04 444444444444444444444444444444444444444444440444444444444444040444444444444 REFERENCE KEY PWR PUMP COMPONENT DESCRIPTION TRCP1B RC PMPB REACTOR COOLANT PUMP B TRCPlc RC PMPC REACTOR COOLANT PUMP C TRHP1A RH PMPA RESIDUAL HEAT REMOVAL PUMP A TRHPlB RH PMPB RESIDUAL HEAT REMOVAL PUMP B TRSP1A RS PMPA RECIRCULATION SPRAY PUMP A TRSP1B RS PMPB RECIRCULATION SPRAY PUMP B TRSP1C RS PMPC RECIRCULATION SPRAY PUMP C TRSP10 RS PMPD RECIRCULATION SPRAY PUMP D TSRCP S RCP SUPPORT, REACTOR COOLANT PUMP 444t4444444444f44f4tkf4f4404444444444444444444444t40444044

4444444444444t444t44t44ftf4f4 +44f44f444444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : COMPDES PAGE 33 REVISION RRS1 DATE BS/12/04 4444444444444444444 444'4f4444t4444444444444tkf444444444444f4444444444444444 REFERENCE KEY BWR PUMP COMPONENT DESCRIPTION

               +                                                                 +
               +++++++++++++++++++++    BWR PUMPS   +++++++++++++++++++++++++++
               +     EXAMINATION CATEGORIES B-M-1, B-M-2, AND C-G (81W)          +

UCSP1A CS PMPA CORE SPRAY PUMP A UCSP1B CS PMPB CORE SPRAY PUMP B UCSP1C CS PMPC CORE SPRAY PUMP C UCSP1D CS PMPD CORE SPRAY PUMP D UHPB HP 800S HIGH PRESSURE COOLANT INJECTION BOOSTER PUMP UHPCS HPCS HIGH PRESSURE CORE SPRAY UHPM HP MAIN HIGH PRESSURE COOLANT INJECTION MAIN PUMP UPUHL PUMPHL PUMP HANGER LUGS UPUINT PUMP INT PUMP INTERNALS 444444444444444444444444444444444444444440444444444444444444444444444444444

C4 44 4444 44444444444444444444444044444444444444444444404+ 444444444444444 NUTECH PRI SIM CAROLINA POWER a LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444404444 DATA ELEMENT : COMPDES PAGE , 34 REVISION RRS 1 DATE 85/12/04 4444444444444444444444444t44444444404440444444444t44444 REFERENCE KEY BWR PUMP COMPONENT DESCRIPTION UPUMPCW PUMPCW PUMP CASING WELD URCIC RCIC REACTOR CORE ISOLATION COOLING PUMP URHP1A RH PMPA RESIDUAL HEAT REMOVAL PUMP A URHP1B RH PMPB RESIDUAL HEAT REMOVAL PUMP B URHP 1 c RH PMPC RESIDUAL HEAT REMOVAL PUMP C URHP1D RH PMPD RESIDUAL HEAT REMOVAL PUMP D URRP1A RR PMPA REACTOR RECIRCULATION PUMP A URRP1B RR PMPB REACTOR RECIRCULATION PUMP 8 USLP1A SL PMPA STANDBY LIQUID CONTROL PUMP A USLP1B SL PMPB STANDBY LIQUID CONTROL PUMP B t eeeeee44444444t44444444ft44t4444ekee444444444ekff4444444444444444t444444444

t ttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt f NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM t REFERENCE CLUSTER LISTING ttttttttttttttttttt DATA ELEMENT : COMPDES PAGE ... 35 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION

             +                                                                 +
             ++++++++++++++++++   PWR  PRESSURE VESSELS ++++++++++++++++++++
             + EXAMINATION CATEGORIES B-A, B-B, B-C, B-E, B-H, B-O, C-A +
             +                       C-8 AND C-C (81W)                         +

VAT1A A TANKA ACCUMULATOR TANK A VAT18 A TANKB ACCUMULATOR TANK 8 VAT1C A TANKC ACCUMULATOR TANK C VCHVP CHVP CLOSURE HEAD VENT PENETRATION VCHW C HEAD CIRCUMFERENTIAL HEAD WELD VCLADH CLAD HD CLADDING, HEAD VCLADV CLAD VS CLADDING, VESSEL VCRDHW CRDHW CONTROL ROD DRIVE HOUSING WELD VCRDTVW CRDTVW CONTROL ROD DRIVE TO VESSEL WELD

ttttttttttttttttttttttttt tttttttttttttttttttttttttttttt tttttttttttttttt NUTECH PRISIM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES PAGE 36 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VCSW C SHELL CIRCUMFERENTIAL SHELL WELD VELHE ELHE EXCESS LETDOWN HEAT EXCHANGER VFTHW FTHW FLANGE TO HEAD WELD VFTSW FTSW FLANGE TO SHELL WELD VHTRPEN HTR PEN HEATER PENETRATIONS (PRESSURIZER) VI, +++ INTEGRALLY WELDED ATTACHMENT +++ VI, LUG LUG VI,PSB PZR SUP BR PRESSURIZER SUPPORT BRACKET VI . PSC PZR COL PRESSURIZER SUPPORT COLLAR VI, SGSW SGSW STEAM GENERATOR SUPPORT WELD VI,SR SADDLE SADDLE REINFORCEMENT (NOZZLE, TRUNION, ETC.)

+~444444444444444444444444444444444444444444444t4444444444+ 444444444404444 NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 44444444444t 0 0 44 44 DATA ELEMENT : COMPDES PAGE, - 37 REVISION RRS1 DATE 85/12/04 44444444440444444404444f4404404444444f4444444f444ff44404444t44t4 REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VI ~ STAN STANCHN STANCHION VI, STVW SKIRT SKIRT TO VESSEL WELD VI, SWP WELDPAD SUPPORT WELD PAO VI o TRUN TRUNNON TRUNNION VI,WSUP PLATE WELDED SUPPORT PLATE VICINOZ ICI NOZ IN-CORE INSTRUMENTATION NOZZLES VINT INT SUR VESSEL INTERIOR SURFACE VLSW L SHELL LONGITUDINAL SHELL WELD VMHW M HEAD MERIDIONAL HEAD WELD VMTHW MANWAY MANWAY TO HEAD WELD (CIRCUMFERENTIAL WELD) t44t444f44444444f44444444444444444444444tff4444f444ft4444444444444444444f44

4444444f444444444444444t4444f44444444444444t444f$ 444444 4444444444444t4 NUTECH PRISIM CAROLINA POWER 8, LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444444444444444 4 DATA ELEMENT : COMPDES PAGE =,38 REVISION, RRS1 DATE 85/12/04 efee44444444004444444f444f444t444044444444f44f444444f4444f4444440444ftf44ff REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNIR NIR NOZZLE INNER RADIUS VNIR--- NIR NIR---; WHERE NIR INDICATES NOZZLE INNER RADIUS AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG. NIR1AO IS NOZZLE 1A, OUTLET NIR3BI IS NOZZLE 38, INLET VNIR1AI NIR1AI NOZZLE 1A (INLET) INNER RADIUS VNIR1BI NIR1BI NOZZLE 1B (INLET) INNER RADIUS VNIR1CI NIR1CI NOZZI.E 1C ( INLET) INNER RADIUS VNIR3AO NIR3AO NOZZLE 3A (OUTLET) INNER RADIUS VNIR3BO NIR3BO NOZZLE 3B (OUTLET) INNER RADIUS VNI R3CO NIR3CO NOZZLE 3C (OUTLET) INNER RADIUS VNOZ NOZZLE VNOZ--- NOZZLE NOZ--- ; WHERE NOZ INDICATES A VESSEL NOZZLE AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG. NOZIAO IS NOZZLE 1A, OUTLET NOZ3BI IS NOZZLE 3B, INLET 444444444444444444t4t.0444444f444ff4ff444f444f4f444444f44444444

44444444444444t44 s44444444444tt44 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM 4 REFERENCE CLUSTER LISTING 444444404444444444 DATA ELEMENT : COMPDES PAGE, s REVISION RRS1 39 e 4 DATE 85/12/04 4444444444444444444444C4444440444444444444444444444444444444444444444444444 REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNOZ1A I NOZ1AI NOZZLE 1A (INLET) VNOZ1AO NOZ1AO NOZZLE 1A (OUTLET) VNOZ1BI NOZ1BI NOZZLE 18 (INLET) VN02180 NOZ180 NOZZLE 18 (OUTLET) VNOZ1CI NOZ1CI NOZZLE 1C ( INLET) VNOZ1CO NOZ1CO NOZZLE 1C (OUTLET) VNOZ1XI VNOZ1XI NOZZLE 1X (INLET) VNOZ1XO NOZ1XO NOZZLE 1X (OUTLET) VNOZ3AI NOZ3AI NOZZLE 3A (INLET) VNOZ3AO NOZ3AO NOZZLE 3A (OUTLET) 444444444444444444444444444t444444444044404404f4404444f4444444444440444

 +444ff44f444f4444f4f4444f44f44f44f44444444f44444tf44f444+    4t4444ft4444444 NUTECH                                                           PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES               PAGE       ;, 40 REVISION   RRS1 4                                                             DATE  85/12/04 444444444444444444444444444444444f444f4444444444t4444444444444444444444f4t4 REFERENCE KEY      PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNOZ3BI          NOZ38I NOZZLE 38   (INLET)

VNOZ380 NOZ380 NOZZLE 38 (OUTLET) VNOZ3CI NOZ3CI NOZZLE 3C (INLET) VNOZ3CO NOZ3CO NOZZLE 3C (OUTLET) VNRHE NRHE NON-REGENERATIVE HEAT EXCHANGER VNTHW NOZZLE NOZZLE TO HEAD WELD VNTHWI NOZZLE NOZZLE TO HEAD WELD (INLET) VNTHWO NOZZLE NOZZLE TO HEAD WELD (OUTLET) VNTVW NOZZLE NOZZLE TO VESSEL WELD VNTVWI NOZZLE NOZZLE TO VESSEL WELD (INLET) 44444'4t44f44444ff444444444ft4444440444f4444444444444444440444f444fftf

~~444444444444444444044444444444444444444444444444444 444444044444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM

                                                                              '4 REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                PAGE       -<<41 REVISION   RRS1 0 DATE  BB/12/04 REFERENCE KEY     PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VNTVWO          NOZZLE NOZZLE TO VESSEL WELD (OUTLET)

VPRZ PRZ PRESSURIZER VRCF RCFILTR REACTOR COOLANT FILTER VREPAIR REPAIR REPAIR AREA IN BELTLINE REGION ONLY VRHE RHE REGENERATIVE HEAT EXCHANGER VRH1A RH HX A RESIDUAL HEAT REMOVAL HEAT EXCHANGER A VRH18 RH HX 8 RESIDUAL HEAT REMOVAL HEAT EXCHANGER 8 VRS1A RS CLRA RECIRCULATION SPRAY COOLER A VRS18 RS CLRB RECIRCULATION SPRAY COOLER 8 VRS1C RS CLRC RECIRCULATION SPRAY COOLER C 44f4440f444f404444444444f444444f0444444444444444444444044444f44444444444

444444440444ff4444444f44444t4f44f4444444f4f44444444f4f44 4f44t4044444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 44t444444444444444 DATA ELEMENT : COMPDES PAGE ,42 REVISION RRS1 DATE 85/12/04 4$ 44444444f444f4444444444448404404444044444f0440f4444f4444f4f4tf444444tfftt REFERENCE KEY PWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VRS10 RS CLRC RECIRCULATION SPRAY COOLER D VRV REACTOR REACTOR VESSEL VSE SAFEEND SAFE END VSGA SGA STEAM GENERATOR A VSGB SGB STEAM GENERATOR B VSGC SGC STEAM GENERATOR C VSG1A CHANGED TO VSGA VSG1B CHANGED TO VSGB VSG1C CHANGED TO VSGC VSTHW STHW SHELL TO HEAD WELD VSWHE SWHE SEAL WATER HEAT EXCHANGER 4444444444444444444444444t444tt44044444444444444t444444tkt4444404480t444444

+844t44444444444444444t444444f4448444444f44444444f444444       444444444444f44 NUTECH                                                             PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES                 PAGE         43 REVISION RRSl DATE  85/12/04 4444444444444044444t44444444t4t4444t44444   444444444444444440444444f44444 REFERENCE KEY     PWR  VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION VSWIFA          SWIFA SEAL WATER INJECTION FILTER A VSWIFB          SWIFB SEAL WATER INJECTION FILTER B VSWRF           SWRF SEAL WATER RETURN FILTER VTSTHW          TSTHW TUBE SHEET TO HEAD WELD VTSTVW          TSTVW TUBE SHEET TO VESSEL WELD VVCT            VC TANK VOLUME CONTROL TANK 4444t44444444444444444f4444444444444f444444f4444444444444444444404444404444

++444444t44ft444444444f4444444444444444444tf44444t44444444 +4444f44f4444444 4 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 4 4 4 4 4 4 4 4 4 4 '4 4 4 4 4 4 4 4 4 DATA ELEMENT : COMPDES PAGE -. 44 REVISION RRS1 DATE 85/12/04 444444444444444444404044444444f4444t444444444444f444444f444tkft4f0444440 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION

               ++++++++++++++++++   BWR PRESSURE VESSELS ++++++++++++++++++++
               + EXAMINATION CATEGORIES B-A, B-B, B-C, B-E, B-H, 8-0, C-A C-8 AND C-C (81W)                                       +

WCHW C HEAD CIRCUMFERENTIAL HEAD WELD WCLADH CLAD HD CLADDING, HEAD WCLADV CLAD VS CLADDING, VESSEL WCRDHW CRDHW CONTROL ROD DRIVE HOUSING WELD WCRDTVW CRDTVW CONTROL ROD DRIVE TO VESSEL WELD WCSW C SHELL CIRCUMFERENTIAL SHELL WELD WFTHW FTHW FLANGE TO HEAD WELD WFTSW FTSW FLANGE TO SHELL WELD WI, +++ INTEGRALLY WELDED ATTACHMENT +++ 444444t44444444$ 4444f44444t4444444444444444444444t444444444444444444444$ 44f

t tttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM REFERENCE CLUSTER LISTING t t t t tt t t t t t t t t t t t t DATA ELEMENT : COMPDES PAGE 45 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WI,LUG LUG WI,SR SADDLE SADDLE REINFORCEMENT (NOZZLE, TRUNION, ETC.) WI, STAN STANCHN STANCHION WI, STVW SKIRT SKIRT TO VESSEL WELD WI, SWP WELDPAD SUPPORT WELD PAD WI, TRUN TRUNNON TRUNNION WI CI NOZ ICI NOZ IN-CORE INSTRUMENTATION NOZZLES WINT INT SUR VESSEL INTERIOR SURFACE WLSW L SHELL LONGITUDINAL SHELL WELD WMHW M HEAD MERIDIONAL HEAD WELD WN I R NIR NOZZLE INNER RADIUS

+~44444444444444444444444444$ 44444f44444444f44444444444444 44444444t444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444404444444 DATA ELEMENT : COMPDES PAGE 46 REVISION RRSl DATE 85/12/04 44444444444t4044444444444t444444t4t444444t440444444444444444404444 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WNIR--- NIR--- NIR---; WHERE NIR INDICATES NOZZLE INNER RADIUS AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG. NIR1AO IS NOZZLE 1A, OUTLET NIR3BI IS NOZZLE 3B, INLET WNIR3AI NOZZLE INNER RADIUS - NOZZLE 3A, INLET WNIR3BI NOZZLE INNER RADIUS NOZZLE 3B, INLET WNIR4AO NOZZLE INNER RADIUS NOZZLE 4A, OUTLET WNI R4BO NOZZLE INNER RADIUS N022LE 4B, OUTLET WNOZ NOZZLE WNOZ--- NOZZLE N02--- ; WHERE NOZ INDICATES A VESSEL NOZZLE AND WOULD INCLUDE THE NOZZLE NUMBER AND AN INDICATION OF INLET OR OUTLET EG. N021AO IS N022LE 1A, OUTLET N023BI IS NOZZLE 38, INLET WN023AI VESSEL NOZZLE N022LE 3A, INLET WN023BI VESSEL NOZZLE NOZZLE 3B, INLET WN024AO VESSEL NOZZLE - NOZZLE 4A, OUTLET WN02480 VESSEL NOZZLE - NOZZLE 4Be OUTLET 04444f444f44t444f44444ff4444444444%44444444444444

+w4444444044444t4444044444444444444444440444444444'0444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : COMPDES PAGE 47 REVISION . RRS1 DATE 85/12/04 4444444444444444444444444t4444444444444444444444444444444 444444444444444444 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WNTHW NOZZLE NOZZLE TO HEAD WELD WNTS TSLEEVE NOZZLE THERMAL SLEEVE WNTVW NOZZLE NOZZLE TO VESSEL WELD WNTVWI NOZZLE NOZZLE TO VESSEL WELD (INLET) WNTVWO NOZZLE NOZZLE TO VESSEL WELD (OUTLET) WREPAIR REPAIR REPAIR AREA IN BELTLINE REGION ONLY WRH I A RH HX A RESIDUAL HEAT REMOVAL HEAT EXCHANGER A WRH18 RH HX 8 RESIDUAL HEAT REMOVAL HEAT EXCHANGER 8 WRV REACTOR REACTOR VESSEL WSE SAFEEND SAFE END 44ttf4444444f4444444444444tt4fff444444f4444444444444444ft4444444f444f444444

444444444444444444444444444404444444444444444 444444444444444 NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING DATA ELEMENT : COMPDES PAGE 48 REVISION RRS1 DATE 85/12/04 444444444444444444044444444444444444444444444444444444444444444 REFERENCE KEY BWR VESSEL (OTHER THAN INTERNALS) COMPONENT DESCRIPTION WSTHW STHW SHELL TO HEAD WELD WTSTVW TSTVW TUBE SHEET TO VESSEL WELD 4444t44444444444444f444t444444444t44ft444444444f444'4444t44f44444044f4440444

CATEGORY REFERENCE KEY: Example - P01-01B-B MHERE: P01-01 is the EXAM REQUIREMENT for PSI PSI is considered An Interval for computer purposes. P01 = PSI program 01

                      -01 =  Xnterval  01 B-B  -"  Section XX category NOTE:   If a category   has the same designation for program A and B the following method is employed:

B-DA = CATEGORY B-D Program A B-DB = CATEGORY B-D Program B AUGMENTED programs are assigned category and item numbers to reflect, as close as possible the source of the exam requirement. EXAMPLE: P04"01FSAR P04 = PSI program number 04

                                        -01  = Xnte val 01 FSAR  = Source of examination requirement
                                                                             'I

+~444444444444444444444444444444444444404444t4440444444444 44444444444444t NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 '4 DATA ELEMENT : CATEGORY PAGE 18 REVISION RRS1 DATE 85/12/05 444444444444444444444444044444444444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 802"01RG1. 14 REACTOR COOLANT PUMP FLYWHEEL INTEGRITY EXAMINATION 804-01FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8, PARAGRAPHS 8 AND E. 805-0'IFSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8, PARAGRAPHS C AND E. 806-01FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8, PARAGRAPHS D AND E. P01-018-A PRESSURE RETAINING WELDS IN REACTOR VESSEL Po 1-018-8 PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV I PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS P01-018-DA FULL PENETRATION WELDS OF NOZZLES IN VESSELS PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM A P01-018-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS PROGRAM 8 FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM 8 P01-018-E EXAMINATION CATEGORY 8-E IS NOT SUBJECT TO PSI 444444444444444f44f4444444444444f444t4f444t4444444444444f444$ ffffff44444f

4444444444444f44444ff44444444t44f4t044f44444444 NUTECH PRISIM CAROLINA POWER 1l LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING DATA ELEMENT : CATEGORY PAGE .19 REVISION RRSl DATE 85/12/05 4444444444444444444444444444444044444444444444444444444 44444444444044044444 REFERENCE KEY DESCRIPTION P01-018-F PRESSURE RETAINING DISSIMILAR METAL WELDS P01-018-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER P01-018-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER P01-018-H INTEGRAL ATTACHMENTS FOR VESSELS P01-018- J PRESSURE RETAINING WELDS IN PIPING P01-018-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES P01-018-L-1 PRESSURE RETAINING WELDS IN PUMP CASINGS P01-018-L-2 PUMP CASINGS P01-018-M-1 PRESSURE RETAINING WELDS IN VALVE BODIES P01-018-M-2 VALVE BODIES P01-018-N-1 INTERIOR OF REACTOR VESSEL P01-018-N-2 RV INTEGRALLY WELDED CORE SUPPORTS AND ATTACHMENTS (BWR) I INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS (BWR) P01-018-N-3 REMOVABLE CORE SUPPORT STRUCTURES (PWR) P01-018-0 PRESSURE RETAINING WELDS IN CONTROL ROD HOUSING PRESSURE RETAINING WELDS IN PERIHERAL CONTROL ROD DRIVE HOUSING 444'4444444444044t44444f444444f44440444444f444f444444444400444

4~444444444444444444f444444444444444404444444 4444444444444 44444444444444'4 NUTECH PRISIM i CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : CATEGORY PAGE ,20 REVISION RRS1 DATE 85/12/05 444444f444444ttff4444tt44f44ftkf4444444fftt444444444t4'444t4 REFERENCE KEY DESCRIPTION P01-01B-P +++EXAMINATION CATEGORY 8-P IS NOT SUBJECT TO PSI+++ P01-01B-Q +++FOR STEAM GENERATOR TUBING, SEE PRISIM-SST+++ P01-01C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS P01-01C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS P01-01C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES P01-01C-D PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER P01-01C-F PRESSURE RETAINING WELDS IN PIPING P01-01C-G PRESSURE RETAINING WELDS IN PUMPS AND VALVES P01-01C-H +++EXAMINATION CATEGORY C-H IS NOT SUBJECT TO PSI+++ P01-01D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION P01-01D-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEAN-UP, AND REACTOR RESIDUAL HEAT REMOVAL P01-01D-C SYSTEMS IN SUPPORT OF RHR FROM SPENT FUEL STORAGE POOL SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL 44444444444r4444448t444t4844444444444t44ttkf44444444444444444444

e

 +444444444444004444444f444444444444044ft44444444ff44444 NUTECH                                                               PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT    1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : CATEGORY                 PAGE          21 REVISION   RRS1 DATE   85/12/05 44444444444444t444444t4444444t444444444444444444444444444     404444444444444444 REFERENCE KEY                             DESCRIPTION P01-01E-A       PRESSURE  RETAINING WELDS IN VESSELS P01-01E-A-1     NONPRESSURE-RETAINING WELDS P01-01E-B       PRESSURE  RETAINING WELDS IN CONTAINMENT PENETRATIONS P01-01E-C       PRESSURE  RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES P01-01E-D       SEALS AND GASKETS P01-01E-E       INTEGRAL ATTACHMENTS P01-01E-F       PRESSURE  RETAINING DISSIMILAR METAL WELDS P01-01E-G       PRESSURE  RETAINING BOLTING P01-01E-P       ALL PRESSURE RETAINING COMPONENTS P01-01F-A       PLATE AND SHELL TYPE SUPPORTS P01-01F-B       LINEAR TYPE SUPPORTS P01-01F-C       COMPONENT STANDARD SUPPORTS P02-01RG1.14    REACTOR COOLANT PUMP FLYWHEEL INTEGRITY EXAMINATION P03-01SER       SAFETY EVALUATION REPORT,   SAFETY REVIEW QUESTION P04-01FSAR       FINAL SAFETY ANALYSIS REPORT  SECTION   6.6.8, PARAGRAPHS B AND E.

4444tkt44f4444444ff44444404444444444444f44444444t4444044f44444

+ 4+4+4+4444444ff4444444444t444f444f4444444t444044'44t44444 NUTECH PR I SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : CATEGORY PAGE 22 REVISION RRS1 DATE 85/12/05 444444444444844444444444'44444444r44444444 REFERENCE KEY DESCRIPTION P05-01FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8, PARAGRAPHS C AND E. P06-01FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8, PARAGRAPHS D AND E. V01-01C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS> AND VALVES 81W-018-A PRESSURE RETAINING WELDS IN REACTOR VESSEL 81W-018-8 PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS 81W-018-DA FULL PENETRATION WELDS OF NOZZLES IN VESSELS PROGRAM A FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM A 81W-018-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS PROGRAM 8 I FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM 8 81W-018-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS 81W-018-F PRESSURE RETAINING DISSIMILAR METAL WELDS 81W-018-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 444444'4444tf44440444t44440444'44444440t444444444444444044

ee444444444f44444444444f4444f4444f444404444444444444444 444f4444f444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 4 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : CATEGORY PAGE 23 REVISION RRS1 DATE 85/12/05 44444444444f4444444444444444444044f44444444tff444444444f44444 REFERENCE KEY DESCRIPTION 81W-018-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 81W-018-H INTEGRAL ATTACHMENTS FOR VESSELS 81W-01 8- J PRESSURE RETAINING WELDS IN PIPING 81W-018-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS> AND VALVES 81W-018-L-1 PRESSURE RETAINING WELDS IN PUMP CASINGS 81W-018-L-2 PUMP CASINGS 81W-018-M-1 PRESSURE RETAINING WELDS IN VALVE BODIES 81W-018-M-2 VALVE BODIES 81W-018-N-1 INTERIOR OF REACTOR VESSEL 81W-018-N-2 RV INTEGRALLY WELDED CORE SUPPORTS AND ATTACHMENTS (BWR) INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS (BWR) 81W-018-N-3 REMOVABLE CORE SUPPORT STRUCTURES (PWR) 81W 018 0 PRESSURE RETAINING WELDS IN CONTROL ROD HOUSING, PRESSURE RETAINING WELDS IN PERIHERAL CONTROL ROD DRIVE HOUSING

444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : CATEGORY PAGE " -

                                                                                -24 REVISION   RRS   1 DATE   85/12/05 4444444444444444444404444440444444444444444444444444444444444 REFERENCE KEY                              DESCRIPTION 81W-018-P       ALL PRESSURE RETAINING COMPONENTS 81W-01B-Q       +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T+++

81W-01C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS 81W-01C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS 81W-01C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES 81W-01C-D PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 81W-01C-F PRESSURE RETAINING WELDS IN PIPING 81W-01C-G PRESSURE RETAINING WELDS IN PUMPS AND VALVES 81W-01C-H ALL PRESSURE RETAINING COMPONENTS 81W-010-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION 81W-010-B ECCS, CHR, ACU ~ AND RHR SUPPORT SYSTEMS SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEAN-UP, AND REACTOR RESIDUAL HEAT REMOVAL 81W-01D" C SYSTEMS IN SUPPORT OF RHR FROM SPENT FUEL STORAGE POOL SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL 444t444444444444444tkt444f444444444444444444444f444444t4444444444444f

+ 44444444t444444'440440f44444tt4f4444444f4444f4444 4444404f44f'4444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING 4I REFERENCE CLUSTER LISTING 44044404444444t444 DATA ELEMENT : CATEGORY PAGE 25 REVI SION RRS 1 DATE 85/12/05 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 4 4 4 O4 4 4 4 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 REFERENCE KEY DESCRIPTION 81W-01E-A PRESSURE RETAINING WELDS IN VESSELS 81W-01E-A-1 NONPRESSURE-RETAINING WELDS 81W-01E-8 PRESSURE RETAINING WELDS IN CONTAINMENT PENETRATIONS 81W-01E-C PRESSURE RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES 81W-01E-0 SEALS AND GASKETS 81W-01E-E INTEGRAL ATTACHMENTS 81W-01E-F PRESSURE RETAINING DISSIMILAR METAL WELDS 81W-01E-G PRESSURE RETAINING BOLTING 81W-0 IE-P ALL PRESSURE RETAINING COMPONENTS 81W-01F-A PLATE AND SHELL TYPE SUPPORTS 81W-0 F-8 '1 LINEAR TYPE SUPPORTS 81W-01F-C COMPONENT STANDARD SUPPORTS 4444444444ff4444f444444f44444444444444f44444444tf444444444444

ITEM NO. REFERENCE KEY: Example P01"01B1.11 P01"01 is the EXAM REQUIREMENT for PSI MHERE: P01 PSI program 01

                -01    Interval 01 B1.11    is the Section XI    Xtem Number AUGMENTED  programs are assigned     item numbers to reflect the location,    as  close as possible, of the exam  requirement within the category.

Example: For category P04-01FSAR one Item No. is P04-016.6.8B Mhere: POC PSI program 04

                                     -01    Interval   01 6.6.8B     Paragraph number in category "FSAR".

+~ 44444444%44f448884fggg44444444444444444444444 44t444444 444f44444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE 87 REVISION RRS 1 DATE 85/12/05 444444444444444444444488444444+t4444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 802-0 'I +++ EXAMINATION CATEGORY RG1. 14 +++ 802-0180RE REACTOR COOLANT PUMP FLYWHEEL BORE UT 802-01FLYWHL REACTOR COOLANT PUMP FLYWHEEL -SURFACE AND UT 802-01KEYWAY REACTOR COOLANT PUMP FLYWHEEL KEYWAY UT 803-01 +++ EXAMINATION CATEGORY OPEN TO FUTUREUSE +++ 804-01 +++ EXAMINATION CATEGORY FSAR +++ 804-016.6.88 AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.88. (INSERVICE) 804-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. (INSERVICE) 805-01 +++ EXAMINATION CATEGORY FSAR +++ 805-016.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.8C. (INSERVICE) 805-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. (INSERVICE) 806" 0'1 +++ EXAMINATION CATEGORY FSAR +++ 806-016. 6. BD AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8D. (INSERVICE) 4444844444444444404440tkt4444444444tttkt444444448444444404444444444r444

44444f444444444444044444444444444f4t44444444444fStd 44444ftt4444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 440444448444444444 DATA ELEMENT : ITEMNO PAGE . 88 REVISION RRS 1 DATE 85/12/05 44444t444444044f4tt444444444440t44444t4444t44444444444 REFERENCE KEY DESCRIPTION 806-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. (INSERVICE) Po 1-0181 +++EXAMINATION CATEGORY 8-A+++ P01-0'I 81 . +++REACTOR VESSEL+++ P01-0181. 10 +++SHELL WELDS+++ P01-0181. 11 RV CIRCUMFERENTIAL SHELL WELDS P01-0181. 12 RV LONGITUDINAL SHELL WELDS P01-0181. 20 +++HEAD WELDS+++ P01-0181. 21 RV CIRCUMFERENTIAL HEAD WELDS Po 1-0181. 22 RV MERIDIONAL HEAD WELDS Po 1-0181. 228 RV MERIDIONAL BOTTOM HEAD WELDS RV MERIDIONAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL. Po 1 -0181. 30 RV SHELL-TO-FLANGE WELD P01-0181.40 RV HEAD-TO-FLANGE WELD P01-0181.50 +++REPAIR WELDS+++ 44444444444f44444444444444444444444f44444444444444444t44444444$ 4444444f4444

44444t44444444444444f444444t4444444t44444444444t44444444 f4444444444444 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE ,;. 89 REVISION RRS1 4 DATE 85/12/05 4444444444444444444 444444t44ftt44444444444444444444444t444444444444t444444t REFERENCE KEY DESCRIPTION Po 1 -0181. 51 RV BELTLINE REGION REPAIR WELDS P01-0181.99 +++ITEM NUMBERS 82.XX THROUGH 89.XX APPEAR AFTER 816.20+++ Po 1-01810 +++EXAMINATION CATEGORY 8-K-1+++ P01-01810. 1 +++PIPING+++ P01-01810.10 PIPING INTEGRALLY WELDED ATTACHMENTS Po 1-01810. 2 +++PUMPS+++ P01-01810.20 PUMP INTEGRALLY WELDED ATTACHMENTS P01-01810. 3 +++VALVES+++ P01-01810. 30 VALVE INTEGRALLY WELDED ATTACHMENTS P01-01812. +++PUMPS+++ P01-01812. 1 +++EXAMINATION CATEGORY 8-L-1+++ P01-01812. 10 PUMP CASING WELDS P01-01812. 2 +++EXAMINATION CATEGORY 8-L-2+++ P01-01812. 20 PUMP CASING Po 1-01812. 3 +++EXAMINATION CATEGORY 8-M-1+++ 4444444444 t4 4 4 f 4 4 4 4 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 f 4 4 0 4 4 4 4

s+ s s s s s s s s s s s ssssssssssssssssssssssssssssssssssssss sssssssssssssss s NUTECH PRIS IM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 s PLANNING REFERENCE CLUSTER LISTING ssssssssssssssssss DATA ELEMENT : ITEMNO PAGE - 90 REVISION RRS 1 DATE 85/12/05 ssssssssssssssssssssssssssssssssssssssssssssfsssssssssssssssss REFERENCE KEY DESCRIPTION P01-01812.3A +++VALVES+++ P01-01812.30 VALVES, NOMINAL PIPE SIZE < 4 IN. VALVE BODY WELDS Pol "01812.40 VALVES, NOMINAL PIPE SIZE >= 4 IN. VALVE BODY WELDS P01-01812. 5 +++EXAMINATION CATEGORY 8-M-2+++ P01-01812.50 VALVE BODY, EXCEEDING 4 IN. NOMINAL PIPE SIZE P01-01813. +++EXAMINATION CATEGORY 8-N-1+++ Po 1-01813. 1 +++REACTOR VESSEL+++ Po 1-01813. 10 RV VESSEL INTERIOR P01-01813. 2 +++EXAMINATION CATEGORY 8-N-2+++ P01-01813. 2. +++REACTOR VESSEL (BWR)+++ PO 1-01813.20 RV INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (BWR) P01-01813.21 RV INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (BWR) P01-01813.22 RV CORE SUPPORT STRUCTURE (BWR) P01-01813. 3 +++EXAMINATION CATEGORY 8" N-3+++ P01-01813. 3. +++REACTOR VESSEL (PWR)+++ ssssssssssssssssssssssssssssssss sssssssssssssssssssssssssssssssssssssss st sss

e 4~+4440444444444884888f044t0444444444f44444444444444444444 444444tkt444f4 NUTECH PRISIM CAROLINA POWER 6 LIGHT COMPANY 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING REFERENCE CLUSTER LISTING ee4444444444444404 DATA ELEMENT : ITEMNO PAGE 91 REVISION RRS1 DATE 85/12/05 44t444444404t4444444444t444444444444444444444444444404444444t444404 REFERENCE KEY DESCRIPTION P01-01813.30 INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (PWR) P01-01813.31 INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (PWR) P01-01813.32 RV CORE SUPPORT STRUCTURE (PWR) F01-01814. +++EXAMINATION CATEGORY 8-0+++ P01-01814. 1 +++REACTOR VESSEL+++ P01-01814.10 RV WELDS IN PERIPHERAL CRD HOUSING P01-01815. +++EXAMINATION CATEGORY 8-P IS NOT SUBJECT TO PSI+++ P01-01816. +++EXAMINATION CATEGORY B-Q+++ P01-01816. 1 +++STEAM GENERATORS+++ P01-01816. 10 +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN STRAIGHT TUBE DESIGN+++ P01-01816. 20 +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN U-TUBE DESIGN+++ P01-0182. +++EXAMINATION CATEGORY 8-8+++ P01-0182. 1 +++PRESSURIZER+++ P01-0182. 10 +++SHELL-TO-HEAD WELDS+++ 4t4444444444444444f444444444444444444444444444444444f4444tt44444444444f4444

ttttt tttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 1h LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE REVISION

                                                                          '2 RRS1 t DATE 85/12/05 t tttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE    KEY                            DESCRIPTION P01-0182. 11     PZR CIRCUMFERENTIAL SHELL-TO-HEAD WELDS P01-0182. 12     PZR LONGITUDINAL SHELL-TO-HEAD WELOS P01-0182.20       +++HEAD WELOS+++

P01-0182. 21 PZR CIRCUMFERENTIAL HEAD WELDS P01-0182. 22 PZR MERIDIONAL HEAD WELDS PO 1-0182. 3 +++STEAM GENERATORS (PRIMARY SIDE)+++ P01-0182. 30 +++HEAD WELOS+++ P01-0182. 31 SG PRIMARY SIDE CIRCUMFERENTIAL HEAD WELDS P01"0182.32 SG PRIMARY SIDE MERIDIONAL HEAD WELDS P01-0182.40 SG PRIMARY SIDE TUBESHEET-TO-HEAD WELDS P01-0182. 5 +++HEAT EXCHANGERS (PRIMARY SIDE)+++ P01-0182. 50 +++SHELL(OR HEAD) WELDS+++ P01-0182.51 HX PRIMARY SIDE CIRCUMFERENTIAL SHELL (OR HEAD) WELDS P01-0182. 52 HX PRIMARY MERIDIONAL SHELL (OR HEAD) WELD P01-0182.53 HX PRIMARY LONGITUDINAL SHELL (OR HEAD) WELD

~+tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt t DATA ELEMENT : ITEMNO PAGE 93 REVISION RRS 1 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt DATE REFERENCE KEY DESCRIPTION P01-0182. 6 +++ SHELL (PRIMARY SIDE) +++ P01-0182. 60 TUBESHEET-TO-SHELL (OR HEAD) WELDS P01-0182. 61 TUBESHEET-TO-SHELL WELDS Po 1-0183 +++EXAMINATION CATEGORY 8-DA+++ P01-0183. +++PROGRAM A REQUIREMENTS+++ 1ST INTERVAL 3 YEARS 2ND INTERVAL 7 YEARS 3RD INTERVAL 13 YEARS 4TH INTERVAL 17 YEARS P01-0183. 1 +++REACTOR VESSEL+++ P01-0183. 10 RV NOZZLE-TO-VESSEL WELOS PROGRAM A Pol-O'183. 20 RV NOZZLE INSIDE RADIUS SECTION - PROGRAM A Po 1 -0183. 3 +++PRESSURIZER+++ Pol-0183. 30 PRZ NOZZLE-TO-VESSEL WELDS PROGRAM A P01-0183. 40 PRZ NOZZLE INSIDE RADIUS SECTION PROGRAM A Po 1-0183. 5 +++STEAM GENERATORS (PRIMARY SIDE)+++ P01-0183. 50 SG PRIMARY NOZZLE-TO-VESSEL WELDS - PROGRAM A tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt

444f444444f44444tf44444f44444404444444t4444f444 44444444444t444 NUTECH PRI SIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444448444444 DATA ELEMENT : ITEMNO ~ PAGE 94 REVISION RRS1 DATE 85/12/05 444444t4440440'04t44444ttttftf404t4tt4tt444444t40f44 REFERENCE KEY DESCRIPTION P01-0183. 60 SG PRIMARY NOZZLE INSIDE RADIUS SECTION PROGRAM A P01-0183. 7 +++HEAT EXCHANGERS (PRIMARY SIDE)+++ Pol "0183. 70 HX PRIMARY NOZZLE-TO-VESSEL WELDS PROGRAM A P01-0183. 80 HX PRIMARY NOZZLE INSIDE RADIUS SECTION PROGRAM A P01-0183. 9 +++EXAMINATION CATEGORY 8-DB+++ Po 1 -0183. 9. +++PROGRAM 8 REQUIREMENTS+++ 1ST INTERVAL '10 YEARS 2ND INTERVAL 10 YEARS 3RD INTERVAL 10 YEARS 4TH INTERVAL 10 YEARS POl-0183. 9A +++REACTOR VESSEL+++ 1-0183. 98 RV NOZZLE-TO-VESSEL WELDS, EXAM FROM NOZZLE BORE PROGRAM 8 Po IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL. P01-0183. 9S RV NOZZLE-TO-VESSEL WELDS, EXAM FROM RV SHELL PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL. 44t444f4444444444444444f44444444444444444t4f444ft444444444t4444444444444444

e

  +444444f44444440f4444444444444444444f444444444f444444f44        444f44f444f4f44 NUTECH                                                                PRISIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT  UNIT      1 PLANNING REFERENCE CLUSTER LISTING                 44t4444444t444f44f DATA ELEMENT : ITEMNO                    PAGE         95 REVISION   RRS1 DATE  85/12/05
                                                                                  ~'444444t4444444444444444t44r44ft44444ttkt44444444444444444t44 REFERENCE KEY                             DESCRIPTION P01-0183. 90   RV NOZZLE-TO-VESSEL WELDS  PROGRAM 8 P01-0183.100     RV NOZZLE  INSIDE RADIUS SECTION   PROGRAM 8 P01-0183. 11   +++PRESSURIZER+++

P01-0183.110 PZR NOZZLE-TO-VESSEL WELDS - PROGRAM 8 P01-0183.120 PZR NOZZLE INSIDE RADIUS SECTION PROGRAM 8 P01-0183. 13 +++STEAM GENERATORS (PRIMARY SIDE)+++ P01-0183.130 SG PRIMARY NOZZLE-TO-VESSEL WELDS - PROGRAM 8 Po 1-0183. 140 SG PRIMARY NOZZLE INSIDE RADIUS SECTION PROGRAM 8 Po 1-0183. 15 +++HEAT EXCHANGERS (PRIMARY SIDE)+++ P01-0183.150 HX PRIMARY NOZZLE-TO-VESSEL WELDS PROGRAM 8 P01-0183.160 HX PRIMARY NOZZLE INSIDE RADIUS SECTION - PROGRAM 8 Po 1-0184 +++EXAMINATION CATEGORY 8-E IS NOT SUBJECT TO PSI+++ P01-0184. 11 VESSEL NOZZLE PARTIAL PENETRATION WELDS P01-0184. 12 CONTROL ROD DPIVE NOZZLE PARTIAL PENETRATION WELDS P01-0184. 13 INSTRUMENTATIMN NOZZLE PARTIAL PENETRATION WELDS 44444444444444t444444444444f4444t4f4444f44444444444444t

4++44t444444444444444444444444444444444444f44444444440444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY t SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 4 DATA ELEMENT : ITEMNO PAGE 96 REVISION RRS 1 DATE 85/12/05 44444444444444444f44t44444444f444444444r4444444t44444t44444444444444t4444444 REFERENCE KEY DESCRIPTION P01-0184.20 PRZ HEATER PELETRATION WELDS P01-0185. +++EXAMINATION CATEGORY 8-F+++ P01-0185. 1 +++REACTOR VESSEL+++ Pol-0185. 10 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS >= 4 INCHES Pol-0185. 20 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS < 4 INCHES P01-0185. 30 RV NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 4 +++PRESSURIZER+++ P01-0185. 40 PZR NOMINAL PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELDS POI-0185. 50 PZR NOMINAL PIPE SIZE < 4 IN. NOZZLE-TO-SAFE END BUTT WELDS Pol-0185. 60 PZR NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 7 +++STEAM GENERATOR+++ P01-0185. 70 SG NOMINAL PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELDS P01-0185. 80 SG NOMINAL PIPE SIZE < 4 IN. NOZZLE-TO-SAFE END BUTT WELDS Pol-0185. 90 SG NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 10 +++HEAT EXCHANGERS+++ eoeeeeeeeeeebeeeee44+eekebe4440444444t444444444444440444444t444444444444444

~+ttttttttttttttttttttttttttttttttttttttttttttttttttttttti ttttttttttttttt NUTECH PRISIM CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ITEMNO PAGE , 97 REVISION RRS1 t DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION r P01-0185. 100 HX NOMINAL PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELOS P01-0185.110 HX NOMINAL PIPE SIZE < 4 IN. NOZZLE-TO-SAFE END BUTT WELOS P01-0185.120 HX NOZZLE-TO-SAFE END SOCKET WELDS P01-0185. 13 +++PIPING+++ P01-0185.130 NOMINAL PIPE SIZE >= 4 IN. DISSIMILAR METAL PIPING BUTT WELD P01-0185. 140 NOMINAL PIPE SIZE < 4 IN. DISSIMILAR METAL PIPING BUTT WELD P01-0185. 150 DISSIMILAR METAL PIPING SOCKET WELOS P01-0186. +++EXAMINATION CATEGORY 8-G-1+++ P01-0186. 1 +++REACTOR VESSEL+++ P01-0186. 10 RV CLOSURE HEAD NUTS (> 2") POI-0186. 20 RV CLOSURE STUDS, IN PLACE (> 2") P01-0186. 30 RV CLOSURE STUDS, WHEN REMOVED (> 2") P01"0186. 40 RV THREADS IN FLANGE (> 2") P01-0186. 50 RV CLOSURE WASHERS, BUSHINGS (> 2") P01-0186. 6 +++PRESSURIZER+++

44t,f44tf44f44444fft444444444444444444444444444444 444444444ff444t NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 98 ~ REVISION RRS1 DATE 85/12/05 8444444444444444844444444f4444444444044444444444444444444444444444444444044 REFERENCE KEY DESCRIPTION P01-0186. 60 PZR BOLTS AND STUDS (> 2") P01-0 186. 70 PZR FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") P01-0186. 80 PZR NUTS, BUSHINGS'ND WASHERS (> 2") P01-0186. 9 +++STEAM GENERATORS+++ P01-0186. 90 SG BOLTS AND STUDS (> 2") P01-0186.100 SG FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") P01-0186. 110 SG NUTS, BUSHINGS, AND WASHERS (> 2") P01-0186. 12 +++HEAT EXCHANGERS++~ P01-0186. 120 HX BOLTS AND STUDS (> 2") P01-0186.130 HX FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") P01-0186.140 HX NUTS, BUSHINGS, AND WASHERS (> 2") P01-0186. 15 +++PIPING+++ P01-0186.150 PIPING BOLTS AND STUDS (> 2") P01-0186. 160 PIPING FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") P01-0186. 170 PIPING NUTS, BUSHINGS ~ AND WASHERS (> 2") 444444'4f044ff4444f444444444f44444444444444444444

444444444444444444 444444444444444444444f44444 +44440444444f44 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444440444444444 DATA ELEMENT : ITEMNO PAGE . 99 REVISION RRS1 DATE 85/12/05 44444444484444444444444444444444444444444444444t&4444444444444444444'4444444 REFERENCE KEY DESCRIPTION P01-0186. 18 +++PUMPS+++ P01-0186. 180 PUMP BOLTS AND STUDS (> 2") P01-0186. 190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") P01-0186.200 PUMP NUTS, BUSHINGS, AND WASHERS (> 2") P01-0186. 21 +++VALVES+++ P01-0186.210 VALVE BOLTS AND STUDS (> 2") P01-0186.220 VALVE FLANGE SURFACE WHEN CONNECTION DISIASSEMBLED (> 2") P01-0186.230 VALVE NUTS, BUSHINGS, AND WASHERS (> 2") P01-0187. +++EXAMINATION CATEGORY 8-G-2+++ P01-0187. 1 +++REACTOR VESSEL+++ P01-0187. 10 REACTOR VESSEL BOLTS, STUDS, AND NUTS (<= 2") P01-0187. 2 +++PRESSURIZER+++ P01-0187. 20 PRESSURIZER BOLTS, STUDS, AND NUTS (<= 2") PO\-0187.3 +++STEAM GENERATORS+++ P01-0187.30 STEAM GENERATOR BOLTS, STUDS, AND NUTS (<= 2") 444444f4444444f4444444t44f44444444tkf444444ft44444444444444444444f4444

tttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING ttttttttttttttttttt DATA ELEMENT : ITEMNO PAGE ,100 REVISION RRSl DATE 85/12/05 t t t t t t tt t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t REFERENCE KEY DESCRIPTION Pol-O'187.4 +++HEAT EXCHANGERS+++ P01-0187. 40 HEAT EXCHANGER BOLTS, STUDS, AND NUTS (<= 2") Po 1-0187. 5 +++PIPING+++ P01-0187. 50 PIPING BOLTS, STUDS, AND NUTS (<= 2") Po 1-0187. 6 +++PUMPS+++ Po 1-0187. 60 PUMP BOLTS, STUDS, AND NUTS (<= 2") P01-0187. 7 +++VAIVFS+++ P01-0187. 70 VALVE BOLTS> STUDS, AND NUTS (<= 2") Po 1-0187. 8 +++CRD HOUSING+++ P01-0187. 80 CRD HOUSING BOLTS, STUDS, AND NUTS (<= 2") P01-0188. +++EXAMINATION CATEGORY 8-H+++ P01-0188. 1 +++REACTOR VESSEL+++ P01-0188. 10 RV INTEGRALLY WELDED ATTACHMENTS P01-0188. 2 +++PRESSURIZER+++ P01-0188. 20 PZR INTEGRALLY WELDED ATTACHMENTS t t t tt t t t tt tt t t t t 4 t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t

0++44f4444444f444f44444444444444444444444444t44444f44t44t4 +44044444444f44 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE,,lRRS101 REVISION DATE 85/12/05 44444444444444444444444444444444444444444 444444444004444444'4444444444440444 REFERENCE KEY DESCRIPTION P01-0188.3 +++STEAM GENERATORS+++ P01-0188.30 SG INTEGRALLY WELDED ATTACHMENTS PO 1-0188.4 +++HEAT EXCHANGERS+++ P01-0188.40 HX INTEGRALLY WELDED ATTACHMENTS P01-0189. +++EXAMINATION CATEGORY 8- J+++ P01-0189. 1 +++PIPING+++ F0 1-0189. 10 +++NOMINAL PIPE SIZE >= 4 IN.+++ P01-0189.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4 IN. P01-0189.12 LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4 IN. P01-0189.20 +++PIPING NOMINAL PIPE SIZE < 4 IN.+++ P01-0189.21 CIRCUMFERENTIAL WELOS IN PIPING, NOMINAL PIPE SIZE < 4 IN. P01-0189.22 LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4 IN. P01-0189.30 +++BRANCH PIPE CONNECTION WELDS+++ P01-0189.31 BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE >= 4 IN. P01-0189.32 BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE < 4 IN. 4444444444f4444440444fft4444444444f444444ff44444444444444444440ff44

a~tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 102 REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION P01-0189. 40 PIPE SOCKET WELDS P01-0189. 99 +++ITEM NUMBERS 810.XX THROUGH 816.XX APPEAR AFTER 81.51+++ P01-01C1 . +++EXAMINATION CATEGORY C-A+++ P01-01C1. 1 +++PRESSURE VESSELS+++ P01-01C1. 10 PRESSURE VESSEL SHELL CIRCUMFERENTIAL WELDS P01-01C'I . 20 PRESSURE VESSEL HEAD CIRCUMFERENTIAL WELDS P01-01C1. 30 PRESSURE VESSEL TUBESHEET-TO-SHELL WELD P01-01C2. +++EXAMINATION CATEGORY C-8+++ P01-01C2. 1 +++PRESSURE VESSELS+++ P01-01C2. 10 +++NOZZLES IN VESSELS <=1/2 IN. NOMINAL THICKNESS+++ P01-01C2. 'I 1 NOZZLES-TO-SHELL(OR HEAD) WELD P01-01C2.20 +++NOZZLES WITHOUT REINFORCING PlATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++ P01-01C2. 21 NOZZLE-TO-SHELL(OR HEAD) WELD P01-01C2. 22 NOZZLE INSIDE RADIUS SECTION IN VESSELS P01-01C2. 30 +++NOZZLES WITH REINFORCING PLATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++

44444444404440444444444440 444444444444444 NUTECH PR I SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE 'I 03 REVISION RRS1 DATE 85/12/05 444444444444444444444448444444444444444444444444444444444444444444444440444 REFERENCE KEY DESCRIPTION P01-01C2. 3'I REINFORCING PLATE WELDS TO NOZZLE AND VESSEL P01-01C2. 31X +++NOZZLE-TO-SHELL (OR HEAD) WELDS+++ P01-01C2. 32 INSIDE OF VESSEL, NOZZLE-TO-SHELL (OR HEAD) WELD INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM. CAT. C-F P01-01C3. +++EXAMINATION CATEGORY C-C+++ P01-01C3. 1 +++PRESSURE VESSELS+++ P01-01C3. 10 PRESSURE VESSEL INTEGRALLY WELDED ATTACHMENTS P01-01C3. 2 +++PIPING+++ P01-01C3. 20 PIPING INTEGRALLY WELDED ATTACHMENTS P01-01C3. 3 +++PUMPS+++ P01-01C3. 30 PUMP INTEGRALLY WELDED ATTACHMENTS P01-0 IC3.4 +++VALVES+++ P01-01C3. 40 VALVE INTEGRALLY WELDED ATTACHMENTS P01-0 IC4. +++EXAMINATION CATEGORY C-D+++ P01-01C4. 1 +++PRESSURE VESSELS+++ 444444f4444444f44444444ft44444444444444444t444444444444444

44444444444444f4444444444 4 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE '.,1 04 REVISION RRS 1 DATE 85/12/05 44444444444444444444444444444444444444444444444444444444444444444444444444'0 REFERENCE KEY DESCRIPTION P01-01C4. 10 PRESSURE VESSEL BOLTS AND STUDS (> 2") P01-01C4. 2 +++PIPING+++ Po 1-01C4. 20 PIPING BOLTS AND STUDS (> 2") P01-01C4. 3 +++PUMPS+++ Po 1 -01C4. 30 PUMP BOLTS AND STUDS (> 2") P01-01C4. 4 +++VALVES+++ Po 1-01C4. 40 VALVE BOLTS AND STUDS (> 2") P01-01C5. +++EXAMINATION CATEGORY C-F+++ Po 1-01C5. 1 +++PIPING+++ P01-01CS. 10 +++PIPING WELDS <= 1/2 IN. NOMINAL WALL THICKNESS+++ P01-01CS. 11 PIPING CIRCUMFERENTIAL WELD <= 1/2" NOMINAL WALL THICKNESS Po 1-01C5. 12 PIPING LONGI TUDINAI WELD <= 1/2" NOMINAL WALL THICKNESS Po 1-01C5. 20 +++PIPING WELOS > 1/2 IN. NOMINAL WALL THICKNESS+++ P01-01C5. 21 PIPING CIRCUMFERENTIAL WELD > 1/2" NOMINAL WALL THICKNESS PO 1-0 C5. 22 1 PIPING LONGITUDINAL WELD > 1/2" NOMINAL WALL THICKNESS

4++4444444444444f444444 4444444t44404444444t44f44ftt44f4444 eft44444f44ff44 NUTECH PRISIM CAROLINA POWER It LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT ': ITEMNO PAGE 105 REVISION RRS1 DATE 85/12/05 440444444444444444044444 f4 t 4 t 4 4 4 4 4 4 4 '0 4440 t44 0444 04444444t4444444 t44 0 t04 44 44 REFERENCE KEY DESCRIPTION P01-01C5. 30 +++PIPING BRANCH CONNECTIONS+++ P01-01C5. 31 PIPE BRANCH CONNECTION CIRCUMFERENTIAL WELD P01-01C5. 32 PIPE BRANCH CONNECTION LONGITUDINAL WELD P01-01C6. +++EXAMINATION CATEGORY C-G+++ P01-01C6. 1 +++PUMPS+++ P01-01C6. 10 PUMP CASING WELDS P01-01C6. 2 +++VALVES+++ P01-01C6. 20 VALVE BODY WELDS P01-01C7. +++EXAMINATION CATEGORY C-H IS NOT SUBJECT TO PSI+++ PO'1-01D1. +++EXAMINATION CATEGORY D-A+++ P01-0101. 1 +++SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION+++ P01-01D1. 10 +++ITEM NUMBER D1.10 IS EXEMPT FROM PRESERVICE INSPECTION++~ P01-01D1. 20 RV SHUTDOWN INTEGRAL ATTACHMENTS - SUPPORTS AND RESTRAINTS P01-0101.30 RV SHUTDOWN INTEGRAL ATTACHMENTS SNUBBERS RV SHUTDOWN INTEGRAL ATTACHMENTS MECHANICAL AND HYDRAULIC SNUBBERS 4484444444484444444444444444444444444444ff44444444444444444444f444444444444

44444444k44444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE, 106 REVISION RRS1 DATE 85/12/05 4444444444444444f444444444'44t4444f4ff44444f4444f444444f4444t444444'4444 REFERENCE KEY DESCRIPTION P01-0101. 40 RV SHUTDOWN INTEGRAL ATTACHMENTS SPRING TYPE SUPPORTS P01-0101. 50 RV SHUTDOWN INTEGRAL ATTACHMENTS-CONSTANT LOAD TYPE SUPPORTS P01-0101 . 60 RV SHUTDOWN INTEGRAL ATTACHMENTS SHOCK ABSORBERS P01-0102. +++EXAMINATION CATEGORY D-8+++ P01-0102. 1 ++~SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL+++ P01-01D2. 10 +++ITEM NUMBER D2. 10 IS EXEMPT FROM PRESERVICE INSPECTION+++ P01-0102. 20 ECCS, ETC. INTEGRAL ATTACHMENTS SUPPORTS AND RESTRAINTS P01-0102. 30 ECCSo ETC. INTEGRAL ATTACHMENTS - SNUBBERS ECCS, ETC. INTEGRAL ATTACHMENTS MECHANICAL AND HYDRAULIC SNUBBERS P01-01D2. 40 ECCS, ETC. INTEGRAL ATTACHMENTS SPRING TYPE SUPPORTS P01-0102. 50 ECCS, ETC. INTEGRAL ATTACHMENTS - CONSTANT LOAD TYPE SUPPORT '01-01D2. 60 ECCS, ETC. INTEGRAL ATTACHMENTS SHOCK ABSORBERS P01-01D3. +++EXAMINATION CATEGORY D-C+++ P01-01D3. 1 +++SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM THE SPENT FUEL STORAGE POOL+++ 4444444444444444444444444444444444444f4444444f4444

44444444044440444444400t444444444f4fff44444f444444 4444444f4444t44 NUTECH PRISIM CAROLINA POWER lt LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE 107 REVISION . RRS 1 DATE 85/12/05 444044444444444444444444444444444444444444044r444444444444004444044444444444 REFERENCE KEY DESCRIPTION P01-0103.'10 +++ITEM NUMBER D3.10 IS EXEMPT FROM PRESERVICE INSPECTION+++ P01-0103.20 RHR FROM SFS INTEGRAL ATTACHMENTS SUPPORTS AND RESTRAINTS P01-01D3. 30 RHR FROM SFS INTEGRAL ATTACHMENTS SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS MECHANICAL AND HYDRAULIC SNUBBERS Po 1-01D3. 40 RHR FROM SFS INTEGRAL ATTACHMENTS SPRING TYPE SUPPORTS P01-01D3. 50 RHR FROM SFS INTEGRAL ATTACHMENT-CONSTANT LOAD TYPE SUPPORTS Po 1-01D3. 60 RHR FROM SFS INTEGRAL ATTACHMENTS - SHOCK ABSORBERS P01-01E1. +++EXAMINATION CATEGORY E-A+++ P01-01E1. 1 +++PRESSURE RETAINING WELDS IN CONTAINMENT VESSELS+++ P01-01E1. 10 +++SHELL WELDS IN CONTAINMENT VESSELS+++ P01-01E1. 11 LONGITUDINAL SHELL WELDS IN VESSELS (CATEGORY A) P01-01E1. 12 CIRCUMFERENTIAL SHELL WELDS IN VESSELS (CATEGORY B) P01-01E1. 20 FLANGE WELDS IN VESSELS ( CATEGORY C) P01-01E1. 30 NOZZLE-TO-SHELL WELDS IN VESSELS (CATEGORY 0) P01-01E1.40 +++INSERT PLATE WELDS+++ 44t4444444444t44f444f44f444444444444444444444f444444444t444f444444444444444

+~4444444f4444444f4t44444444444444444444 444444444444444444 444444444444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 108 REVISION RRS1 DATE 85/12/05 444444444444444440444444484444444444444444444444444440404444444444444444404 REFERENCE KEY DESCRIPTION P01-01E1. 41 INSERT PLATE-TO-SHELL WELDS P01-01E1. 42 LONGITUDINAL INSERT PLATE WELDS P01-01E1. 43 CIRCUMFERENTIAL INSERT PLATE WELDS P01-01E1. 50 +++VENT SYSTEM WELDS+++ P01-01E1. 51 LONGITUDINAL VENT SYSTEM WELDS P01-01E1. 52 CIRCUMFERENTIAL VENT SYSTEM WELDS P01-01E1. 53 OTHER VENT SYSTEM WELDS P01-01E2. +++EXAMINATION CATEGORY E-A-1+++ P01-01E2. 1 +++NONPRESSURE-RETAINING WELDS+++ P01-01E2. 10 +++REINFORCING STRUCTURE WELDS+++ P01-01E2.11 CONTAINMENT VESSEL ATTACHMENT REINFORCING STRUCTURE WELDS P01-01E2. 12 OTHER REINFORCING STRUCTURE WELDS P01-01E2. 20 REINFORCING STRUCTURE ATTACHMENT WELDS P01-01E3. +++EXAMINATION CATEGORY E-8+++ P01-01E3. 1 +++PRESSURE RETAINING WELDS IN CONTAINMENT PENETRATIONS+++ 44f$ 44444444444f44444f44444444444t4444444ftfff444444444444f4404f4444

E 4~44444444444444444444f4444444444f44f44404f44t44444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE .109 REVISION RRS1 DATE 85/12/05 444444444444444444444440444444444444444444444444440444444 44444444440444P444 REFERENCE KEY DESCRIPTION P01-01E3. 10 +++CONTAINMENT PENETRATION WELDS+++ PO I-01E3. 11 LONGITUDINAL CONTAINMENT PENETRATION WELDS P01-01E3. 12 CIRCUMFERENTIAL CONTAINMENT PENETRATION WELDS P01-01E3. 13 FLUED HEAD AND BELLOWS SEAL CIRC WELDS JOINED TO THE PENET FLUED HEAD AND BELLOWS SEAL CIRCUMFERENTIAL WELDS JOINED TO THE PENETRATION. P01-01E4. +++EXAMINATION CATEGORY E-C+++ P01-01E4. 1 +++PRESSURE RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES+++ P01-01E4. 10 +++AIRLOCK WELDS+++ P01-01E4. 11 LONGITUDINAL AIRLOCK WELDS P01-01E4.12 CIRCUMFERENTIAL AIRLOCK WELDS P01-01E4. 20 +++EQUIPMENT HATCH WELDS+++ P01-0IE4.21 LONGITUDINAL EQUIPMENT HATCH WELDS P01-01E4. 22 CIRCUMFERENTIAL EQUIPMENT HATCH WELDS P01-01E5. +++EXAMINATION CATEGORY E-0+++ 4444t444444444444444444444444ff444444444444444444444444444444444444444444+

0 444444444444444444t44444444t4444$ t44 44444444444444 4444444444444$ NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE . 110 REVISION RRS1 DATE 85/ 12/05 44444444444444444444444444f4tffttf4444t44444444ff4444444ff444444444404f04t4 REFERENCE KEY DESCRIPTION P01-01E5.1 +++SEALS AND GASKETS+++ P01-01E5.10 SEALS P01-01E5.20 GASKETS P01-01E6. +++EXAMINATION CATEGORY E-E+++ P01-01E6. 1 +++ INTEGRAL ATTACHMENTS+++ P01-01E6.10 INTEGRAL ATTACHMENT WELDS P01-01E7. +++EXAMINATION CATEGORY E-F+++ P01-01E7. 1 +++PRESSURE RETAINING DISSIMILAR METAL WELDS+++ P01-01E7.10 DISSIMILAR METAL WELDS Po 1-01EB +++EXAMINATION CATEGORY E-G+++ P01-01EB. +++PRESSURE RETAINING BOLTING+++ P01-01EB. 1 +++BOLTED CONNECTION VISUAL EXAMINATION+++ P01-01E8.10 BOLTED CONNECTION VISUAL EXAMINATION P01-01E8.2 +++BOLTED CONNECTION BOLT TORQUE OR TENSION TEST++~ P01-01E8.20 BOLTED CONNECTION BOLT TORQUE OR TENSION TEST 4444444444444$ 4444444444444444ff444444444444444444444444f4444444444444444f4

0++4444444444444f444448444444444444444444444444ft44444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNI T 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE .111 REVISION RRS 1 DATE 85/12/05 REFERENCE KEY DESCRIPTION P01-01E9. +++EXAMINATION CATEGORY E-P+++ Po 1-01E9. EX EXEMPT CLASS MC PRESSURE RETAINING COMPONENTS Po 1-01E9. 1 +++ALL PRESSURE RETAINING COMPONENTS+++ Po 1-01E9. 10 +++PRESSURE RETAINING BOUNDARY+++ Pol-01E9. 11 10-CFR-50 APPENDIX J TEST OF CONTAINMENT BOUNDARY P01-01E9. 12 SYS LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY SYSTEM LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY. P01-01E9. 20 CONTAINMENT PENET BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST) CONTAINMENT PENETETRATION BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST). P01-01E9.30 AIRLOCKS (10CFR50 APPENDIX J TYPE 8 TESTS) P01-01E9. 40 SEALS AND GASKETS (10CFR50 APPENDIX J TYPE 8 TESTS) P01-01F1. +++EXAMINATION CATEGORY F-A+++ P01-01F1. EX EXEMPT CLASS 1, 2, OR 3 CATEGORY F-A COMPONENT SUPPORTS Po 1-01F1. 1 +++PLATE AND SHELL TYPE SUPPORTS+++ 444444444444444444444444444t4444t444444444444444444444444444444444444440444

+ 44444t44444444444444444fff44tt44f44f444f4444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 112 REVISION RRS 1 DATE 85/12/05 t444444444444444ff444444t48444444f4444444444444f4444444444444t4444f44444444 REFERENCE KEY DESCRIPTION Po 1-01F 1. 10 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE P01-01F1. 20 WELDED CONNECTIONS TO BUILDING STRUCTURE P01-01F 1. 30 WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS Po 1-01F1. 40 DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS P01-01F2. +++EXAMINATION CATEGORY F-8++~ Po 1-01F2. EX EXEMPT CLASS 1, 2, OR 3 CATEGORY F-8 COMPONENT SUPPORTS P01-01F2. 1 +++LINEAR TYPE SUPPORTS+++ Po 1-01F2. 10 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE P01-01F2.20 WELDED CONNECTIONS TO BUILDING STRUCTURE 4444444444444ff48444444f44f444444fft4f444444f4444444444444f44I44f4fff444444

V

  +44444444444444444444444444444444404444440444                   4444444444444t4 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT     1 PLANNING REFERENCE CLUSTER LISTING                 044444444444444044
                      'ATA ELEMENT : ITEMNO                      PAGE       '113 REVISION   RRS I DATE   85/12/05 44444444444484444444444444444444444444404444444     4444444444444444444444444444 REFERENCE KEY                              DESCRIPTION PO 1,-01F2. 30   WELD 8 MECH CONNECTIONS   IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE       JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS PO)-01F2.40      DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS,       MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS P01-01F2.50      INVALID I TEMNO  +++   THIS ITEMNO IS INVALID P01-01F3.        +++EXAMINATION CATEGORY F-C+++

P01-0 I F3. EX EXEMPT CLASS 1, 2, OR 3 CATEGORY F-C COMPONENT SUPPORTS P01-01F3. 1 +++COMPONENT STANDARD SUPPORTS+++ P01-01F3. 10 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE P01-01F3. 20 WELDED CONNECTIONS TO BUILDING STRUCTURE P01-01F3. 30 WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS 444'44444444tt44444444t44444444444444t4444444444t4444444444r444444444tf444444

C +~4444444444444444444444t44444444444444f444444444t44044444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE 114 REVISION RRS 1 DATE 85/12/05 444444444444444444444444444444444404444444444444444444444444444444404444040 REFERENCE KEY DESCRIPTION P01-01F3.40 DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS Po 1 -01F3. 50 SPRING, CONSTANT, SHOCK ABSORBER, AND SNUBBER SUPPORTS SPRING TYPE SUPPORTS, CONSTANT LOAD TYPE SUPPORTS, SHOCK AB-SORBERS, HYDRAULIC AND MECHANICAL TYPE SNUBBERS P02-01 +++ EXAMINATION CATEGORY FSAR+++ P02-0180RE REACTOR COOLANT PUMP FLYWHEEL BORE UT P02-0 IFLYWHL REACTOR COOLANT PUMP FLYWHEEL SURFACE AND UT P02-01KEYWAY REACTOR COOLANT PUMP FLYWHEEL KEYWAY - UT P03-01250. 1S SAFETY EVALUATION REPORT, SAFETY- REVIEW QUESTION¹250. 1 SURFACE EXAM P03-01250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION ¹ 250. 1 VOLUMETRICEXAM P04-01 +++ EXAhlINATION CATEGORY FSAR +++ P04-016.6.88 AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.88. P04-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. 4444444444444444444444444444f44f44t44t44444t4444Std'444444t4f4444fff44f44444

4+s44tkt4tftf4444f4444444444444440444t44 4fkf44444f4400 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 115 REVISION RRS1 DATE 85/12/05 4 4 4 '4 4 4 4 4 4 4 4 4 t t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t 0 4 4 4 4 4 4 4 4 4 4 t 4 t t 0 4 4 4 4 4 4 4 4 4 t 4 4 tO 4 4 t t t t t 4 4 4 4 0 4 REFERENCE KEY DESCRIPTION P05-01 +++ EXAMINATION CATEGORY FSAR+++ P05-016.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR PARAGRAPH 6.6.8C. P05-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. P06-01 +++ EXAMINATION CATEGORY FSAR +++ P06-016.6.8D AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8D P06-016.6.8E AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR PARAGRAPH 6.6.8E. V01-01C3. 10 PRESSURE VESSEL INTEGRALLY WELDED ATTACHMENTS V01-01C3.20< VOLUNTARY EXAM INTEGRALWELDED PIPE ATTACHMENT LESS THAN 3/4 INCH THICK 250. 1S SAFETY EVALUATION REPORT 250. 1 SURFACE 250. 1V SAFETY EVALUATION REPORT 250.1 VOUMETRIC EXAM 81W-0181 +++EXAhlINATION CATEGORY 8-A+++ 81W-0181 . +++REACTOR VESSEL+++ 81W-0181. '10 +++SHELL WELDS+++ 44444t44444444f44ff4444444444444444ff444444444f444444fftf444444444

44444444444444440440444t444444404404444 44444444444440 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 116 REVISION RRS1 DATE 85/12/05 44444444444444444f 4444t44t44f 4f f tft444444444444444f t4 f 44f f 44tf 044444444 REFERENCE KEY DESCRIPTION 81W-0181.11 RV CIRCUMFERENTIAL SHELL WELOS 81W-0181.12 RV LONGITUDINAL SHELL WELDS 81W-0181. 20 +++HEAD WELDS+++ 81W-0181.218 RV CIRCUMFERENTIAL BOTTOM HEAD WELDS CIRCUMFERENTIAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL. 81W-0181.21T RV CIRCUMFERENTIAL TOP HEAD WELDS I CIRCUMFERENTIAL TOP HEAD WELD INSPECTION MUST BE PERFORMED DURING EACH PERIOD AND MAY NOT BE DEFERRED TO THE END OF THE INTERVAL. 81W-0181.228 RV MERIDIONAL BOTTOM HEAD WELDS RV MERIDIONAL BOTTOM HEAD WELD INSPECTION MAY BE DEFERRED TO THE END OF THE INSPECTION INTERVAL. 81W-0181.22T RV MERIDIONAL TOP HEAD WELDS I RV MERIDIONAL TOP HEAD WELD INSPECTION MUST BE PERFORMED DURING EACH PERIOD AND MAY NOT BE DEFERRED TO THE END OF THE INTERVAL. 81W-0181.30 RV SHELL-TO-FLANGE WELD 44444444404444444444444444f440444444444444444444444444444t444444444444444

%%4eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeee NUTECH PRIS IM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING eeeeeeeeeeeeeeeeee DATA ELEMENT : ITEMNO PAGE . 117 REVISION, RRS 1 DATE 85/12/05 eteeeeeeeeeeeeeeeeeteeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeefeeeeeeeeeeeeeee REFERENCE KEY DESCRIPTION 81W-0181.300 RV SHELL-TO-FLANGE WELD TESTING IN CONJUNCTION WITH CAT 8-D I EXAM OF SHELL-TO-FLANGE WELDS MAY BE PERFORMED DURING THE 1ST AND 3RD INSPECTION PERIOD IN CONJUNCTION WITH THE NOZZLE EXAM OF CAT. B-D (PROGRAM 8). AT LEAST 50k OF SHELL-TO-FLNGE WELDS SHALL BE EXAM BY THE END OF THE 1ST INSPECTION PERIOD, AND THE REMAINDER BY THE END OF THE 3RD INSPECTION PERIOD. 81W-0181. 30F RV SHELL-TO-FLANGE WELD PARTIAL EXAM FROM FLANGE FACE IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL. 81W-0181. 30V RV SHELL-TO-FLANGE WELD EXAM CONDUCTED FROM VESSEL WALL IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL. 81W-0181.40 RV HEAD-TO-FLANGE WELD 81W-0181.40F RV HEAD-TO-FLANGE WELD PARTIAL EXAM FROM FLANGE FACE IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE ~ THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL. eeeeeeeeeefeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee

e~44444444444444444444444444444444444444444444444444444444 C44444444444f44 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444044 DATA ELEMENT : ITEMNO PAGE '18 REVISION RRS1 DATE 85/12/05 40t44ftf44t44tf4444f44tf4444ft444444t44 REFERENCE KEY DESCRIPTION 81W-0181. 40V RV HEAD-TO-FLANGE WELD EXAM CONDUCTED FROM VESSEL WALL IF PARTIAL EXAMINATIONS ARE CONDUCTED FROM THE FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUC-TED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL. 81W-0181. 50 +++REPAIR WELDS+++ 81W-0181. 5'I RV BELTLINE REGION REPAIR WELOS 81W-0181 . 99 +++ITEM NUMBERS 82.XX THROUGH 89.XX APPEAR AFTER 816.20+++ 81W-01810 +++EXAMINATION CATEGORY 8-K-1+++ 8 IW-01810. 1 +++PIPING+++ 81W-01810. 10 PIPING INTEGRALLY WELDED ATTACHMENTS 81W-01810. 2 +++PUMPS+++ 81W-01810. 20 PUMP INTEGRALLY WELDED ATTACHMENTS 81W-01810. 3 +++VALVES+++ 81W-01810.30 VALVE INTEGRALLY WELDED ATTACHMENTS 81W-01812. +++PUMPS+++ 81W-01812. 1 +++EXAMINATION CATEGORY 8-L-1+++ 444444444444444444C4444444444444444%444444ftf44f4444f44'4444'44440444444ffO

t+ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttktttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ITEMNO PAGE .119 REVISION 'RRS1 DATE 85/12/05 <<tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-01812. 10 PUMP CASING WELDS 81W-01812. 2 +++EXAMINATION CATEGORY 8-L-2+++ 8 1W-01812. 20 PUMP CASING 81W-01812. 3 +++EXAMINATION CATEGORY 8-M-1+++ 81W-01812. 3A +++VALVES+++ 81W-01812.30 VALVES, NOMINAL PIPE SIZE < 4 IN. VALVE BODY WELDS 81W-01812.40 VALVES, NOMINAL PIPE SIZE >= 4 IN. VALVE BODY WELDS 81W-01812. 5 +++EXAMINATION CATEGORY 8-M-2+++ 81W"01812.50 VALVE BODY, EXCEEDING 4 IN. NOMINAL PIPE SIZE 8 I W-01813. +++EXAMINATION CATEGORY 8-N-1+++ 81W-01813. 1 +++REACTOR VESSEL+++ 81W-01813. 10 RV VESSEL INTERIOR 81W-01813. 2 +++EXAMINATION CATEGORY 8-N-2+++ 81W-01813. 2. +++REACTOR VESSEL (BWR)+++ 81W-01813.20 RV INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (BWR) ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt

t NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44f 444444444444444 DATA ELEMENT : ITEMNO PAGE . 120 REVISION RRS1 DATE 85/12/05 444444444444t44c0444444444844444444444444tf444404444444444 REFERENCE KEY DESCRIPTION 81W-01813.21 RV INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (BWR) 81W-01813. 22 RV CORE SUPPORT STRUCTURE (BWR) 81W-01813. 3 +++EXAMINATION CATEGORY 8-N-3+++ 81W-01813. 3. +++REACTOR VESSEL (PWR)+++ 81W-01813.30 INTERIOR ATTACHMENTS WITHIN BELTLINE REGION (PWR) 81W-01813.31 INTERIOR ATTACHMENTS BEYOND BELTLINE REGION (PWR) 81W-01813.32 RV CORE SUPPORT STRUCTURE (PWR) 81W-01814. +++EXAMINATION CATEGORY 8-0+++ 81W-01814. 1 +++REACTOR VESSEL+++ 81W-01814.10 RV WELDS IN PERIPHERAL CRD HOUSING 8 1W-01815. +++EXAMINATION CATEGORY 8-P+++ 81W" 01815. EX EXEMPT CLASS 1 PRESSURE RETAINING COMPONENTS

1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
2) EXEMPT CLASS 1 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER. (E.G ~ WELDS <= 1" NPS) 81W-01815. 1 +++REACTOR VESSEL+++

444444444tt484ftkf44444ttf4ffkt4444444444t444440444t4444444444f4444444fkt44

0~+444444444444444444444404444444f44444444tft444444 +44444444444444 NUTECH PRIS IM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444444444t4444444 DATA ELEMENT : ITEMNO PAGE 121 REVISION RRS 1 DATE 85/12/05 44444444444444444 REFERENCE KEY DESCRIPTION 8IW-01815.10 RV PRESSURE RETAINING BOUNDARY OPERATIONAL 81W-01815.11 RV PRESSURE RETAINING BOUNDARY - STATIC 81W-01815. 2 +++PRESSURIZER+++ 81W-01815.20 PRZ PRESSURE RETAINING BOUNDARY - OPERATIONAL 81W-01815. 21 PRZ PRESSURE RETAINING BOUNDARY - STATIC 81W-01815. 3 ++~STEAM GENERATORS+++ 81W-01815.30 SG PRESSURE RETAINING BOUNDARY - OPERATIONAL 81W-01815.31 SG PRESSURE RETAINING BOUNDARY - STATIC 81W-01815. 4 +++HEAT EXCHANGERS+++ 81W-01815.40 HX PRESSURE RETAINING BOUNDARY - OPERATIONAL 81W-01815.41 HX PRESSURE RETAINING BOUNDARY - STATIC 8 1W-01815. 5 +++PIPING+++ 81W-01815.50 PIPING PRESSURE RETAINING BOUNDARY - OPERATIONAL 81W-01815.51 PIPING PRESSURE RETAINING BOUNDARY - STATIC 8 1W-0 18 'I 5. 6 +++PUMPS+++ 444444444444444f444444444444444t44f444444444444444444444f40f4444t44'444444t4

+~4444444444444444444444444444444444444044444f4444444fff44 44f4k4f4k44440f NUTECH PRISIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 44444444444444444t DATA ELEMENT : ITEMNO PAGE 122 REVISION RRS1 DATE- 85/12/05 444444444444444444444844444444444444444444444444444444444444444444404444444 REFERENCE KEY DESCRIPTION 8 IW-01815.60 PUMP PRESSURE RETAINING BOUNDARY - OPERATIONAL 81W-01815.61 PUMP PRESSURE RETAINING BOUNDARY - STATIC 81W-01815. 7 +++VALVES+++ 8 1W-01815.70 VALVE PRESSURE RETAINING BOUNDARY - OPERATIONAL 81W-O'1815.71 VALVE PRESSURE RETAINING BOUNDARY - STATIC 81W-01816. +++EXAMINATION CATEGORY B-Q+++ 81W-01816. 1 +++STEAhl GENERATORS+++ 81W-01816. 10 +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN STRAIGHT TUBE DESIGN+++ 8 W-0 1816. 20

 '1             +++FOR STEAM GENERATOR TUBING, SEE PRISIM-S8T, STEAM GENERATOR TUBING IN U-TUBE DESIGN+++

81W-0182. +++EXAMINATION CATEGORY B-B+++ 81W-0182. 1 +++PRESSURIZER+++ 81W-0182. 10 +++SHELL-TO-HEAD WELDS+++ 81W-0182. 11 PZR CIRCUMFERENTIAL SHELL-TO-HEAD WELDS 81W-0182. 12 PZR LONGITUDINAL SHELL-TO-HEAD WELDS 44444444444f444444444444f444444444444f444ft44444444444444444f4444f444444

~~tttttttttttttttttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ITEMNO PAGE 123 REVISION RRS 1 85/12/05 DATE ttttttt REFERENCE KEY DESCRIPTION 81W-0182. 20 +++HEAD WELOS+++ 81W-0182.21 PRZ CIRCUMFERENTIAL HEAD WELDS 81W-0182. 22 PRZ MERIDIONAL HEAD WELOS 81W-0182. 3 +++STEAM GENERATORS (PRIMARY SIDE)+++ 81W-0182. 30 +++HEAD WELDS+++ 81W-0182. 31 SG PRIMARY SIDE CIRCUMFERENTIAL HEAD WELDS 81W-0182. 32 SG PRIMARY SIDE MERIDIONAL HEAD WELDS 81W-0182. 40 SG PRIMARY SIDE TUBESHEET-TO-HEAD WELDS 81W-0182. 5 +++HEAT EXCHANGERS (PRIMARY SIDE)+++ 81W" 0182. 50 +++SHELL(OR HEAD) WELDS+++ 81W-0182. 51 HX PRIMARY SIDE CIRCUMFERENTIAL SHELL (OR HEAD) WELDS 81W-0182. 52 HX PRIMARY MERIDIONAL SHELL (OR HEAD) WELD 81W-0182. 53 HX PRIMARY LONGITUDINAL SHELL (OR HEAD) WELD 81W" 0182. 6 +++ SHELL (PRIMARY SIDE) +++ 81W-0182. 60 TUBESHEET-TO-SHELL (OR HEAD) WELDS

seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeekeeeeeeeee I, eeeeeeeeeeeeeee NUTECH PRISIM CAROLINA POWER 8, LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING e REFERENCE CLUSTER LISTING eeeeeeeeeeeeeeeeee DATA ELEMENT : ITEMNO PAGE 124 REVISION RRS1 DATE 85/12/05 eeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee REFERENCE KEY DESCRIPTION 81W-0182. 61 TUBESHEET-TO-SHELL WELDS 81W-0183 +++EXAMINATION CATEGORY 8-DA+++ 81W-0183. +++PROGRAM A REQUIREMENTS+++ 1ST INTERVAL = 3 YEARS 2ND INTERVAL = 7 YEARS 3RD INTERVAL = 13 YEARS 4TH INTERVAL = 17 YEARS 81W-0183. 1 +++REACTOR VESSEL+++ 81W-0183. 10 RV NOZZLE-TO-VESSEL WELDS - PROGRAM A 81W-0183. 20 RV NOZZLE INSIDE RADIUS SECTION - PROGRAM A 81W-0183. 3 +++PRESSURIZER+++ 81W-0183. 30 PRZ NOZZLE-TO-VESSEL WELDS PROGRAM A 81W-0183. 40 PRZ NOZZLE INSIDE RADIUS SECTION PROGRAM A 81W-0183. 5 +++STEAM GENERATORS (PRIMARY SIDE)+++ 81W-0183. 50 SG PRIMARY NOZZLE-TO-VESSEL WELDS PROGRAM A 81W-0183. 60 SG PRIMARY NOZZLE INSIDE RADIUS SECTION PROGRAM A 81W-0183. 7 +++HEAT EXCHANGERS (PRIMARY SIDE)++~ eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee

NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE , 125 REVISION RRS1 DATE 85/12/05 444444484'444444444444t4444444444444444444444t444444444444444444444444 REFERENCE KEY DESCRIPTION 81W-0183. 70 HX PRIMARY NOZZLE-TO-VESSEL WELDS PROGRAM A 81W-0183. 80 HX PRIMARY NOZZLE INSIDE RADIUS SECTION PROGRAM A 81W-0183. 9 +++EXAMINATION CATEGORY 8-08+++ 81W-0183. 9. +++PROGRAM 8 REQUIREMENTS+++ 1ST INTERVAL 10 YEARS 2ND INTERVAL 10 YEARS 3RD INTERVAL 10 YEARS 4TH INTERVAL 10 YEARS 81W-0183. 9A +++REACTOR VESSEL+++ 81W-0183. 98 RV NOZZLE-TO-VESSEL WELDS, EXAM FROM NOZZLE BORE PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZlE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL. 81W-0183. 9S RV NOZZLE-TO-VESSEL WELDS, EXAM FROM RV SHELL PROGRAM 8 IF EXAMS ARE CONDUCTED FROM INSIDE THE COMPONENT AND NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF EACH INSPECTION INTERVAL.

444444444444444444444444t4444444444444444444 44444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE 126 REVISION RRS1 DATE 85/12/05 44444444444444tf4444f4444f444444t44444444444444t4444t444ttt4t44f44444444444 REFERENCE KEY DESCRIPTION 81W-0183. 90 RV NOZZLE-TO-VESSEL WELDS - PROGRAM 8 81W-0183.100 RV NOZZLE INSIDE RADIUS SECTION - PROGRAM 8 81W-0183. 11 +++PRESSURIZER+++ 81W-0183.110 PZR NOZZLE-TO-VESSEL WELDS - PROGRAM 8 81W-0183.120 PZR NOZZLE INSIDE RADIUS SECTION - PROGRAM 8 81W-0183. 13 ~++STEAM GENERATORS (PRIMARY SIDE)+++ 81W-0183.130 SG PRIMARY NOZZLE-TO-VESSEL WELDS - PROGRAM 8 81W-0183.140 SG PRIMARY NOZZLE INSIDE RADIUS SECTION PROGRAM 8 81W-0183. 15 +++HEAT EXCHANGERS (PRIMARY SIDE)+++ 81W-0183.150 HX PRIMARY NOZZLE-TO-VESSEL WELDS - PROGRAM 8 81W-0183.160 HX PRIMARY NOZZLE INSIDE RADIUS SECTION - PROGRAM 8 81W-0184 +++EXAMINATION CATEGORY 8-E+++ 81W-0184. 10 +++ PARTIAL PENETRATION WELDS+++ 81W-0184. 11 VESSEL NOZZLE PARTIAL PENETRATION WELDS 81W-0184. 12 CONTROL ROD DRIVE NOZZLE PARTIAL PENETRATION WELDS 444444444444444flf444444f44444f44404404f444444444444444444444444444

+~44444444444444f444f4444444444444444444444444 044444444444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE 127 REVISION RRS1 DATE 85/12/05 4444444444444t44444444444444444444f044t4444444 44444404044044r444444 REFERENCE KEY DESCRIPTION 81W" 0184. 13 INSTRUMENTATION NOZZLE PARTIAL PENETRATION WELDS 81W-0184. 2 +++PRESSURIZER+++ 81W-0184. 20 PRZ HEATER PENETRATION WELDS 81W-0185. +++EXAMINATION CATEGORY 8-F+++ 8 IW-0185. 1 +++REACTOR VESSEL+++ 81W-0185. 10 RV NOZZLE-TO-SAFE END BUTT WELDS. NPS >= 4 INCHES WHEN DONE CONCURRENTLY WITH CATEGORY 8-D EXAMINATIONS 81W-0185. 10 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS >= 4 INCHES 81W-0185. 2D RV NOZZLE-TO-SAFE END BUTT WELDS, NPS < 4 INCHES WHEN DONE CONCURRENTLY WITH CATEGORY 8-D EXAMINATIONS 81W-0185. 20 RV NOZZLE-TO-SAFE END BUTT WELDS, NPS < 4 INCHES 81W-0185. 3D RV NOZZLE-TO-SAFE END SOCKET WELDS WHEN DONE CONCURRENTLY WITH CATEGORY 8-D EXAMINATIONS 81W-0185. 30 RV NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185. 4 +++PRESSURIZER+++ 444444444444t4%444444444444tt4444444444444444444444440444444444

4w4444444t44444444444444444444t4t444444444440444444t4444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 128 REVISION RRS1 DATE 85/12/05 4444444444444444444 REFERENCE KEY DESCRIPTION 81W-0185. 40 PZR NOMINAL PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELDS 81W-0185. 50 PRZ NOMINAL PIPE SIZE < 4 IN. NOZZLE-TO-SAFE ENO BUTT WELDS 81W-0185. 60 PRZ NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185. 7 +++STEAM GENERATOR+++ 81W-0185. 70 SG NOMINAL PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE END BUTT WELDS 81W-0185. 80 SG NOMINAL PIPE SIZE < 4 IN. NOZZLE-TO-SAFE END BUTT WELDS 81W-0185. 90 SG NOZZLE-TO-SAFF END SOCKET WELDS 81W-0185. 10 +++HEAT EXCHANGERS+++ 81W-0185.100 HX NOMINAL PIPE SIZE >= 4 IN. NOZZLE-TO-SAFE ENO BUTT WELDS 81W-0185. 110 HX NOMINAL PIPE SIZE < 4 IN. NOZZLE-TO-SAFE END BUTT WELDS 81W-0185.120 HX NOZZLE-TO-SAFE END SOCKET WELDS 81W-0185. 13 +++PIPING+++ 81W-0185.130 NOMINAL PIPE SIZE >= 4 IN. DISSIMILAR METAL PIPING BUTT WELD 81W-0185.140 NOhlINAL PIPE SIZE < 4 IN. DISSIMILAR METAL PIPING BUTT WELD 81W-0185. 150 DISSIMILAR METAL PIPING SOCKET WELDS 4t44f4444444444444'4444040ff444444ff404444444rtt44f44444

44444444444t4444444444444444444f 4444444f 44444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE 129 REVISION RRS1 DATE 85/12/05 444844444444444444444404444404tt4444444444444444444444444444444444444404404 REFERENCE KEY DESCRIPTION 81W-0186. +++EXAMINATION CATEGORY 8-G-1+++ 81W-0186. 1 +++REACTOR VESSEL+++ 81W-0186. 10 RV CLOSURE HEAD NUTS (> 2") 81W-0186. 20 RV CLOSURE STUDS, IN PLACE (> 2" ) 81W-0186. 30 RV CLOSURE STUDS, WHEN REMOVED (> 2") 81W-0186. 40 RV THREADS IN FLANGE (> 2") 81W-0186. 50 RV CLOSURE WASHERS, BUSHINGS (> 2") 81W-0186. 6 +++PRESSURIZER+++ 81W-0186. 60 PRZ BOLTS AND STUDS (> 2") 81W-0186. 70 PRZ FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") 81W"0186. 80 PRZ NUTS, BUSHINGS, AND WASHERS (> 2") 81W-0186. 9 +++STEAM GENERATORS+++ 81W-0186. 90 SG BOLTS AND STUDS (> 2") 81W-0186.100 SG FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") 81W-0186. 110 SG NUTS, BUSHINGS, AND WASHERS (> 2" ) 4444444444444444444444444444444444444444444444444ff44f444444444444444044f44

0 4m+444444$ 444f4444r44444444t4444t4444444444444444ftt4444444 44444444fk44444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444440444440444444 DATA ELEMENT : ITEMNO PAGE 130 4 REVISION RRS1 DATE 85/12/05 44444444444444444444t4444r444444440444444f4fft444444444444440irt4444f REFERENCE KEY DESCRIPTION 81W-0186. 12,, +++HEAT EXCHANGERS+++ 81W-0186.120 HX BOLTS AND STUDS (> 2") 81W-0186. 130 HX FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") 81W-0186. 140 HX NUTS, BUSHINGS, AND WASHERS (> 2" ) 81W-0186. 15 +++ P I P I N 6+++ 81W-0186. 150 PIPING BOLTS AND STUDS (> 2") 81W-0186.160 PIPING FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") 81W-0186. 170 PIPING NUTS, BUSHINGS, AND WASHERS (> 2") 81W-0186. 18 +++PUMPS+++ 81W-0186. 180 PUMP BOLTS AND STUDS (> 2") 81W-0186. 190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2") 81W-0186.200 PUMP NUTS, BUSHINGS, AND WASHERS (> 2") 81W-0186. 21 +++VALVES+++ 81W-0186. 210 VALVE BOLTS AND STUDS (> 2") 8 IW-0186.220 VALVE FLANGE SURFACE WHEN CONNECTION DISIASSEMBLED (> 2") 4444444444444444444444444444444444444444444t444444444444f444t444f4444444444

0++4444444444444444444444444f444f4444444C4f'444444444f4$ 44 NUTECH PRISIM CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 131 REVISION RRS1 DATE 85/12/05 4444444444444t4444f4444444444444444444t444444444444t REFERENCE KEY DESCRIPTION 81W-0186.230 VALVE NUTS, BUSHINGS, AND WASHERS (> 2") 81W-0187. +++EXAMINATION CATEGORY 8-G-2+++ 81W-0187. 1 +++REACTOR VESSEL+++ 81W-0187. 10 REACTOR VESSEL BOLTS, STUDS, AND NUTS (<= 2") 81W-0187. 2 +++PRESSURIZER+++ 81W-0187. 20 PRESSURIZER BOLTS, STUDS, AND NUTS (<= 2") 81W-0187. 3 +++STEAM GENERATORS+++ 81W-0187. 30 STEAM GENERATOR BOLTS, STUDSI AND NUTS (<= 2") 81W" 0187. 4 +++HEAT EXCHANGERS+++ 81W-0187.40 HEAT EXCHANGER BOLTS, STUDS, AND NUTS (<= 2") 81W-0187. 5 +++PIPING+++ 81W-0187.50 PIPING BOLTS, STUDS, AND NUTS (<= 2") 81W-0187. 6 +++PUMPS+++ 81W-0187. 60 PUMP BOLTS, STUDS, AND NUTS (<= 2") 81W-0187. 7 t++VALVES+++ 444444$ 444444444444044044444444444040440444444444444444444444t4444444444444

t

  +4444'44444444444444444444444444444444444444444444f      444444     444444444444444 NUTECH                                                                    PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT      -  UNIT  1 PLANNING REFERENCE CLUSTER LISTING                  44t444444444444444 DATA ELEMENT : ITEMNO                      PAGE          132 REVISION    RRS1 DATE   85/12/05 444444444444f4440444444f4tf44444444tf444tf444444444444444444404444444 REFERENCE KEY                                DESCRIPTION 81W-0187.70      VALVE BOLTS, STUDS, AND NUTS (<=      2")

81W-0187.8 +++CRD HOUSING+++ 81W-0187.80 CRD HOUSING BOLTS, STUDS, AND NUTS (<= 2") 8 1W-0188 . +++EXAMINATION CATEGORY 8-H+++ 81W-0188. 1 +++REACTOR VESSEL+++ 81W-0188. 10 RV INTEGRALLY WELDED ATTACHMENTS 81W-0188. 2 +++ PRESSUR I ZER+++ 81W-0188. 20 PZR INTEGRALLY WELDED ATTACHMENTS 81W-0188. 3 +++STEAM GENERATORS+++ 81W-0188.30 SG INTEGRALLY WELDED ATTACHMENTS 81W-0188. 4 +++HEAT EXCHANGERS+++ 81W-0188.40 HX INTEGRALLY WELDED ATTACHMENTS 81W-0189. +++EXAMINATION CATEGORY 8-J+++ 81W-0189. 1 +++PIPING+++ 81W-0189. 10 +++NOMINAL PIPE SI2E >= 4 IN.+++ 4444444444444444444444t444f444444444404tt440tfff444f4444

+++44444444444444444444444444444444f 4f 44f 44 444444444444444 444444444444444 NUTECH PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444044444 DATA ELEMENT : ITEMNO PAGE , 133 REVISION, RRS1 DATE 85/12/05 44444 ~ 4444444444444444444404444t044444tf444tf444444444444444444 REFERENCE KEY DESCRIPTION 81W-0189. 11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4 IN. 81W-0189. 12 LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE >= 4 IN. 81W-0189. 20 +++PIPING NOMINAL PIPE SIZE < 4 IN.+++ 81W-0189. 21 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4 IN. 81W-0189. 22 LONGITUDINAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4 IN. 81W-0189.30 +++BRANCH PIPE CONNECTION WELDS+++ 8 1W-0189. 31 BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE >= 4 IN. 81W-0189. 32 BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE < 4 IN. 81W" 0189. 40 PIPE SOCKET WELDS 81W-0189. 99 +++ITEM NUMBERS 810.XX THROUGH 816.XX APPEAR AFTER 81.51+++ 81W-01C1. +++EXAMINATION CATEGORY C-A+++ 81W-01C1. 1 +++PRESSURE VESSELS+++ 81W-01C1. 10 PRESSURE VESSEL SHELL CIRCUMFERENTIAL WELDS 81W-01C1. 20 PRESSURE VESSEL HEAD CIRCUMFERENTIAL WELDS 81W-01C1. 30 PRESSURE VESSEL TUBESHEET-TO-SHELL WELD 4444444444444444444444444f44444f444f440444444tf4444444444444444444444444444

44444444 444tt4444444t44f44444f444444f 444444444444444 NUTECH PRI SIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444444444t4444f44 DATA ELEMENT : ITEMNO PAGE 134 REVISION RRS 1 DATE 85/12/05 444444444444444444444444444444444444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 81W-01C2. +++EXAMINATION CATEGORY C-B+++ 81W-01C2. 1 +++PRESSURE VESSELS+++ 81W-01C2. 10 +++NOZZLES IN VESSELS <=1/2 IN. NOMINAL THICKNESS+++ 81W-01C2. 11 NOZZLES-TO-SHELL(OR HEAD) WELD 81W-01C2. 20 +++NOZZLES WITHOUT REINFORCING PLATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++ 81W-01C2. 21 NOZZLE-TO-SHELL(OR HEAD) WELD 81W-01C2. 22 NOZZLE INSIDE RADIUS SECTION IN VESSELS 81W-01C2. 30 +++NOZZLES WITH REINFORCING PLATE IN VESSELS 1/2 IN. NOMINAL THICKNESS+++ 81W-01C2. 31 REINFORCING PLATE WELDS TO NOZZLE AND VESSEL 81W-01C2. 32 +++NOZZLE-TO-SHELL (OR HEAD) WELDS+++ 81W-01C2.32A INSIDE OF VESSEL ACCESSIBLE, NOZZLE-TO-SHELL (OR HEAD) WELD INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM. CAT. C-F WHEN THE INSIDE OF THE VESSEL IS ACCESSIBLE. 81W-01C2. 32 I INSIDE OF VESSEL INACCESSIBLE, NOZZLE-TO-SHELL(OR HEAD) WELD I INCLUDES ALL NOZZLES AT TERMINAL ENDS OF THOSE PIPING RUNS SELECTED FOR EXAMINATION UNDER EXAM. CAT. C-F WHEN THE INSIDE OF THE VESSEL IS INACCESSIBLE. 444tlff44444444t44444444f444444t44f44t444444444444

e e

 +44444444444444f444444444444440444444444444444f44444444 NUTECH                                                                PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT   -  UNIT  1 PLANNING REFERENCE CLUSTER LISTING                444444044444444444 DATA ELEMENT : ITEMNO                    PAGE         135 REVISION 'RRS1 DATE   85/12/05 4444440t44           44444f844t4 REFERENCE KEY                             DESCRIPTION 81W-01C3.       +++EXAMINATION CATEGORY C-C+++

81W-01C3. 1 +++PRESSURE VESSELS+++ 81W-01C3. 10 PRESSURE VESSEL INTEGRALLY WELDED ATTACHMENTS 81W-01C3. 2 +++PIPING+++ 81W-01C3. 20 PIPING INTEGRALLY WELDED ATTACHMENTS 81W-01C3. 3 +++PUMPS+++ 81W-01C3. 30 PUMP INTEGRALLY WELDED ATTACHMENTS 81W-01C3. 4 +++VA1VFS+++ 81W-01C3.40 VALVE INTEGRALLY WELDED ATTACHMENTS 81W-01C4. +++EXAMINATION CATEGORY C-D+++ 81W-01C4. 1 +++PRESSURE VESSELS+++ 81W-01C4. 10 PRESSURE VESSEL BOLTS AND STUDS (> 2") 81W-01C4. 2 +++PIPING+++ 81W-01C4. 20 PIPING BOLTS AND STUDS (> 2") 81W" 01C4. 3 +++PUMPS+++ 44444444444444444444404444444444444444444t44444444444t404444444444444444444

J eeeeeeeteteeeeeeteeeeeeeeeeeeeeeeeeteeeeeeeeeeeeeee e seeeeeeeeeeeeee NUTECH PRISIM t CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 136 REVISION RRS1 DATE 85/12/05 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeee REFERENCE KEY DESCRIPTION 81W-01C4. 30 PUMP BOLTS AND STUDS (> 2") 81W-01C4. 4 +++VALVES+++ 81W-01C4.40 VALVE BOLTS AND STUDS (> 2") 81W-01CS. +++EXAMINATION CATEGORY C-F+++ 81W-01C5. I +++PIPING+++ 81W-01CS. 10 +++PIPING WELDS <= 1/2 IN. NOMINAL WALL THICKNESS+++ 81W-01C5. 11 PIPING CIRCUMFERENTIAL WELD <= 1/2" NOMINAL WALL THICKNESS 81W-01C5. 12 PIPING LONGITUDINAL WELD <= 1/2" NOMINAL WALL THICKNESS 81W-01CS. 20 +++PIPING WELDS > 1/2 IN. NOMINAL WALL THICKNESS+++ 81W-01C5. 21 PIPING CIRCUMFERENTIAL WEI.D > 1/2" NOMINAL WALL THICKNESS 81W-01CS. 22 PIPING LONGITUDINAL WELD > 1/2" NOMINAL WALL THICKNESS 81W-01CS. 30 +++PIPING BRANCH CONNECTIONS+++ 81W-01CS. 31 PIPE BRANCH CONNECTION CIRCUMFERENTIAL WELD 81W-0 I C5. 32 PIPE BRANCH CONNECTION LONGITUDINAL WELD 8 1W-01C6. +++EXAMINATION CATEGORY C-G+++ eeeeeteeeeeetteeteeeeeeeeeeeeeeeeeteeeeeeeeteeeeeeteeeeeeeeeeeeeeeeeeeeeeee

m~4'4444444444444444444444444444444444444444444'044444444444 44t44444t444444 NUTECH PRI SIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REF ERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : ITEMNO PAGE , 137 REVISION RRS1 DATE 85/12/05 4444444f4044444444444444 REFERENCE KEY DESCRIPTION 81W-01C6. 1 +++PUMPS+++ 81W-01C6. 10 PUMP CASING WELDS 81W-01C6. 2 +++VALVES+++ 81W-01C6.20 VALVE BODY WELDS 8 IW-01C7. +++EXAMINATION CATEGORY C-H+++ 81W-01C7. EX EXEMPT CLASS 2 PRESSURE RETAINING COMPONENTS

1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
2) EXEMPT CLASS 2 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER. (E.G. WELDS <= 4" NPS) 81W-01C7. 1 +++PRESSURE VESSELS+++

81W-01C7. 10 PRESSURE VESSEL PRESSURE RETAINING COMPONENTS OPERATIONAL 81W"01C7.20 PRESSURE VESSEL PRESSURE RETAINING COMPONENTS STATIC 81W-01C7. 3 +++PIPING+++ 81W-01C7. 30 PIPING PRESSURE RETAINING COMPONENTS OPERATIONAL 81W-01C7. 40 PIPING PRESSURE RETAINING COMPONENTS STATIC 81W-01C7. 5 +++PUMPS+++ 44444444044444444444444444444444444444f4t44444444440444440444444f44444tf444

444404444444444444444444444444444444444+ NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444404444 DATA ELEMENT : ITEMNO PAGE 138 REVISION 'RS1 4 DATE 85/12/05 4444444t444t44t444444t4444444444444444f444f444444444f4444 REFERENCE KEY DESCRIPTION 81W-01C7.50 PUMPS PRESSURE RETAINING COMPONENTS - OPERATIONAL 81W-01C7.60 PUMPS PRESSURE RETAINING COMPONENTS - STATIC 81W-01C7. 7 +++VALVES+++ 81W-01C7.70 VALVES PRESSURE RETAINING COMPONENTS OPERATIONAL 81W-01C7.80 VALVES PRESSURE RETAINING COMPONENTS - STATIC 81W-01D1 +++EXAMINATION CATEGORY 0-A+++ 81W-0101. 1 +++SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION+++ 81W-01D1. 1EX EXEMPT CLASS 3 CATEGORY D-A PRESSURE RETAINING COMPONENTS

1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
2) EXEMPT CLASS 3 COMPONENTS ENTEREO IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER. (E.G. <= 4" PIPE ATACHES) 81W-01D1. 100 RV SHUTDOWN PRESSURE RETAINING COMPONENTS - OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL. A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.

OPERATIONAL: SYS FUNCTIONAL, SYS INSERVICE, OR SYS LEAKAGE 81W-01D1 . 10S RV SHUTDOWN PRESSURE RETAINING COMPONENTS STATIC A SYSTEM STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL. STATIC: HYDROSTATIC OR PNEUMATIC 444444444444444444444444444t4444444444444444444444444444444444444444t444444

+ sttttttttttttttttttttttttttttttttttttttttttttt,tttttttttt tttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY t SHEARON HARRIS NUCLEAR POWER PLANT UNIT ttttttttttttttttttt 1 PLANNING t REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 139 t REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-0101 . 20 RV SHUTDOWN INTEGRAL ATTACHMENTS SUPPORTS AND RESTRAINTS 81W-0101 . 30 RV SHUTDOWN INTEGRAL ATTACHMENTS - SNUBBERS RV SHUTDOWN INTEGRAL ATTACHMENTS - MECHANICAL AND HYDRAULIC SNUBBERS 81W-01D1.40 RV SHUTDOWN INTEGRAL ATTACHMENTS SPRING TYPE SUPPORTS 81W-0101. 50 RV SHUTDOWN INTEGRAL ATTACHMENTS-CONSTANT LOAD TYPE SUPPORTS 81W-0101. 60 RV SHUTDOWN INTEGRAL ATTACHMENTS - SHOCK ABSORBERS 8 1W-0102. +++EXAMINATION CATEGORY D-8+++ 81W-0102. 1 +++SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL+++ I 81W-0102. 1EX EXEMPT CLASS 3 CATEGORY 0-B PRESSURE RETAINING COMPONENTS

1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY, ASSIGN THIS ITEM NUMBER.
2) EXEMPT CLASS 3 COMPONENTS ENTERED IN THE4"DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER. (E.G. <= PIPE ATACHES) 81W-01D2. 100 ECCS, ETC. PRESSURE RETAINING COMPONENTS OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL. A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM.

OPERATIONAL: SYS FUNCTIONAL, SYS INSERVICE OR SYS LEAKAGE

                                                              ~

4444444444t44f4444444f44444444444444444 +44444444444444 NUTECH PRISIM CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 4440t44t44044444 DATA ELEMENT : ITEMNO PAGE 140 REVISION RRS1 DATE 85/12/05 408004444444444444444444444444444444444444444444444444444444444444444444444 REFERENCE KEY DESCRIPTION 81W-01D2. 10S ECCS, ETC. PRESSURE RETAINING COMPONENTS STATIC A SYSTEM STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL. STATIC: HYDROSTATIC OR PNEUMATIC 81W-01D2. 20 ECCS, ETC. INTEGRAL ATTACHMENTS - SUPPORTS AND RESTRAINTS 81W-01D2.30 ECCS, ETC. INTEGRAL ATTACHMENTS SNUBBERS ECCS, ETC. INTEGRAL ATTACHMENTS - MECHANICAL AND HYDRAULIC SNUBBERS 81W-0102.40 ECCS, ETC. INTEGRAL ATTACHMENTS SPRING TYPE SUPPORTS 81W-01D2.50 ECCS, ETC. INTEGRAL ATTACHMENTS - CONSTANT LOAD TYPE SUPPORT 81W-01D2.60 ECCS, ETC. INTEGRAL ATTACHMENTS SHOCK ABSORBERS 81W-0103. +++EXAMINATION CATEGORY D-C+++ 81W-0103. 1 +++SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM THE SPENT FUEL STORAGE POOL+++ 81W-01D3. 1EX EXEMPT CLASS 3 CATEGORY D-C PRESSURE RETAINING COMPONENTS

1) IF A COMPONENT CANNOT BE EXAMINED BY ANY EXAM TYPE OTHER THAN VT-2 AND A RELIEF REQUEST HAS BEEN WRITTEN FOR PRESSURE TESTING ONLY'SSIGN THIS ITEM NUMBER.
2) EXEMPT CLASS 3 COMPONENTS ENTERED IN THE DATA BASE SHOULD BE ASSIGNED THIS ITEM NUMBER. (E.G. <= 4" PIPE ATACHES) 4'4444444444444tf44444444444f4444ftffff44440

444444444444444444444t444444444444 44444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444440444 DATA ELEMENT : ITEMNO PAGE . 141 REVISION RRS1 DATE 85/12/05 4444444444444444f4f4f444f444ff444444f44f4ffOtf4f444444f444444444444ft44t4f4 REFERENCE KEY DESCRIPTION 81W-0103. 100 RHR FROM SFS PRESSURE RETAINING COMPONENTS OPERATIONAL AN OPERATIONAL PRESSURE TEST SHALL BE DONE EVERY PERIOD OR THREE TIMES EVERY INTERVAL. A SYSTEM STATIC PRESSURE TEST AND ACCOMPANING VT-2 EXAM ARE ACCEPTABLE IN LIEU OF THE OPERATIONAL PRESSURE TEST AND VT-2 EXAM. OPERATIONAL: SYS FUNCTIONAL, SYS INSERVICE, OR SYS LEAKAGE 81W-0103. 10S RHR FROM SFS PRESSURE RETAINING COMPONENTS STATIC A SYSTEM STATIC TEST SHALL BE DONE ONCE EVERY INSPECTION INTERVAL. STATIC: HYDROSTATIC OR PNEUMATIC 81W-01D3. 20 RHR FROM SFS INTEGRAL ATTACHMENTS SUPPORTS AND RESTRAINTS 8 1W-0 'I 03 . 30 RHR FROM SFS INTEGRAL ATTACHMENTS SNUBBERS RHR FROM SFS INTEGRAL ATTACHMENTS MECHANICAL AND HYDRAULIC SNUBBERS 81W-01D3. 40 RHR FROM SFS INTEGRAL ATTACHMENTS SPRING TYPE SUPPORTS 81W-01D3. 50 RHR FROM SFS INTEGRAL ATTACHMENT-CONSTANT LOAD TYPE SUPPORTS 8 1W-01D3. 60 RHR FROM SFS INTEGRAL ATTACHMENTS - SHOCK ABSORBERS 81W-01E1. +++EXAMINATION CATEGORY E-A+++ 81W-01E1. 1 +++PRESSURE RETAINING WELDS IN CONTAINMENT VESSELS+++ 4444444t4444444t444444444444f444f44ff444444tf44

++'54444444444444444f 44444444444444444444444444444444444444 444444444444440 4 NUT ECH PRISIM CAROLINA POWER L LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 4444444444444t444f DATA ELEMENT : ITEMNO PAGE  : 142 REVISION RRS 1 DATE 85/12/05 44444444444444444444444404444404ir444444444444 REFERENCE KEY DESCRIPTION 81W-01E1. 10 +++SHELL WELDS IN CONTAINMENT VESSELS+++ 81W-01E1. 11 LONGITUDINAL SHELL WELDS IN VESSELS (CATEGORY A) 81W-01E1. 12 CIRCUMFERENTIAL SHELL WELDS IN VESSELS (CATEGORY 8) 81W-01E1 . 20 FLANGE WELDS IN VESSELS ( CATEGORY C) 81W-01E1. 30 NOZZLE-TO-SHELL WELDS IN VESSELS (CATEGORY D) 81W-01E1. 40 +++INSERT PLATE WELDS+++ 81W-01E1. 41 INSERT PLATE-TO-SHELL WELDS 81W-01E1. 42 LONGITUDINAL INSERT PLATE WELDS 81W-01E1. 43 CIRCUMFERENTIAL INSERT PLATE WELDS 81W-01E1. 50 +++VENT SYSTEM WELDS+++ 81W"0 IE1. 51 LONGITUDINAL VENT SYSTEM WELDS 81W-01E1. 52 CIRCUMFERENTIAL VENT SYSTEM WELDS 81W-01E1. 53 OTHER VENT SYSTEM WELDS 81W-01E2. +++EXAMINATION CATEGORY E-A-1+++ 81W-01E2. 1 +++NONPRESSURE-RETAINING WELDS+++ 44444444t4444444f44t44f444444444t444444444t4444f44444tt4444444444444t444

44404f44t4t44f44444444444444 444440044444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : ITEMNO PAGE 143 REVISION RRS 1 4044444444448444444444444444444444t44444444444t444t44t444 REFERENCE KEY DESCRIPTION 81W-01E2. 10 +++REINFORCING STRUCTURE WELDS+++ 81W-01E2. 1 1 CONTAINMENT VESSEL ATTACHMENT REINFORCING STRUCTURE WELDS 81W-01E2. 12 OTHER REINFORCING STRUCTURE WELDS 81W-01E2. 20 REINFORCING STRUCTURE ATTACHMENT WELDS 81W-01E3. +++EXAMINATION CATEGORY E-8+++ 81W-0163. 1 +++PRESSURE RETAINING WELOS IN CONTAINMENT PENETRATIONS+++ 81W-01E3. 10 +++CONTAINMENT PENETRATION WELDS+++ 81W-01E3. 1 I LONGITUDINAL CONTAINMENT PENETRATION WELDS 81W-01E3. 12 CIRCUMFERENTIAL CONTAINMENT PENETRATION WELDS 81W-01E3. 13 FLUED HEAD AND BELLOWS SEAL CIRC WELDS JOINED TO THE PENET FLUED HEAD AND BELLOWS SEAL CIRCUMFERENTIAL WELDS JOINED TO THE PENETRATION. 81W-01E4. +++EXAMINATION CATEGORY E-C+++ 81W-01E4. 1 +++PRESSURE RETAINING WELDS IN AIRLOCKS AND EQUIPMENT HATCHES+++ 81W-01E4. 10 +++AIRLOCK WELDS+++ 444444444444444444444444444444444448444444444444444444444444444444444444444

NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ITEMNO PAGE 144 REVISION RRS 1 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttt DATE REFERENCE KEY DESCRIPTION 81W-01E4. 11 LONGITUDINAL AIRLOCK WELDS 81W-01E4. 12 CIRCUMFERENTIAL AIRLOCK WELDS 81W-01E4. 20 +++EQUIPMENT HATCH WELDS+++ 81W-01E4.21 LONGITUDINAL EQUIPMENT HATCH WELDS 81W-01E4. 22 CIRCUMFERENTIAL EQUIPMENT HATCH WELDS 81W"01ES. +++EXAMINATION CATEGORY E-D+++ 81W-01E5. 1 +++SEALS AND GASKETS+++ 81W-01ES. 10 SEALS 81W-01E5. 20 GASKETS 81W-01E6. +++EXAMINATION CATEGORY E-E+++ 81W-01E6. 1 +++INTEGRAL ATTACHMENTS+++ 81W-01E6. 10 INTEGRAL ATTACHMENT WELDS 8 1W-0 I Ej . +++EXAMINATION CATEGORY E-F+++ 81W-01E7. 1 +++PRESSURE RETAINING DISSIMILAR METAL WELDS+++ 81W-01E7. 10 DISSIMILAR METAL WELDS

  ~44444444444444444t4444444444t44444444444444444444444$    4    +4444444444444t NUTECH                                                               PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    - UNIT 1 PLANNING REFERENCE CLUSTER LISTING               444444444444844444 DATA ELEMENT : ITEMNO                   PAGE         145 REVISION   RRS1 DATE   85/12/05 444444444t4ftt44t44444440tt4444444444444444r444044444tt044444t4444t REFERENCE KEY                               DESCRIPTION 81W-01EB.        +++EXAMINATION CATEGORY E-G+++

81W-01EB. 1 +++PRESSURE RETAINING BOLTING+++ 81W-01EB. 10 +++BOLTED CONNECTION VISUAL EXAMINATION+++ 81W-01EB. 10A BOLTED CONNECTION VISUAL EXAMINATION ALL VISIBLE SURFACES SHALL BE EXAMINED. BOLTING MAY REMAIN IN PLACE UNDER TENSION WHEN DISASSEMBLY IS NOT OTHERWISE REQUIRED. 81W-01EB. 10D BOLTED CONNECTION VISUAL EXAMINATION EXAMINATION OF BUSHINGS, THREADS, AND LIGAMENTS IN BASE MATERIAL OF FLANGES IS REQUIRED ONLY WHEN THE CONNECTION IS DISASSEMBLED. 81W-01E8.20 +++BOLTED CONNECTION BOLT TORQUE OR TENSION TEST+++ 81W-01E8. 20A BOLTED CONNECTION BOLT TORQUE OR TENSION TEST ALL VISIBLE SURFACES SHALL BE EXAMINED. BOLTING MAY REMAIN IN PLACE UNDER TENSION WHEN DISASSEMBLY IS NOT OTHERWISE REQUIRED. 8 IW-01EB. 20D BOLTED CONNECTION BOLT TORQUE OR TENSION TEST I EXAMINATION OF BUSHINGS, THREADS, AND LIGAMENTS IN BASE MATERIAL OF FLANGES IS REQUIRED ONLY WHEN THE CONNECTION IS DISASSEMBLED. 4f4444f4444444444444444444444f4444444f44444444t4444ft4444444444444444444444

 +4ft4444444444444444444444444t4tt4444f44444444444444t444        44444444444'444 NUTECH                                                               PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT    - UNIT 1 PLANNING                                        4 REFERENCE CLUSTER LISTING               444444444444444444 DATA ELEMENT : ITEMNO                   PAGE,1RRS1 REVISION 46 DATE 85/12/05 44444$ 4444444444f444444444ft44t44t44444444444$  44f44044444f44444404fft444444 REFERENCE KEY                             DESCRIPTION 81W-01E9.       +++EXAMINATION CATEGORY E-P+++

81W-01E9. EX EXEMPT CLASS MC PRESSURE RETAINING COMPONENTS 81W-01E9. 1 +++ALL PRESSURE RETAINING COMPONENTS+++ 81W-01E9. 10 +++PRESSURE RETAINING BOUNDARY+++ 81W-01E9. 11 10-CFR-50 APPENDIX J TEST OF CONTAINMENT BOUNDARY 81W-01E9. 12 SYS LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY SYSTEM LEAKAGE PRESSURE TEST IWE-5220 OF CONTAINMENT BOUNDARY. 81W-01E9. 20 CONTAINMENT PENET BELLOWS (10CFR50 APPENDIX J TYPE 8 TEST) CONTAINMENT PENETETRATION BELLOWS ( 10CFR50 APPENDIX J TYPE 8 TEST). 81W-01E9. 30 AIRLOCKS (10CFR50 APPENDIX J TYPE 8 TESTS) 81W-01E9.40 SEALS AND GASKETS (10CFR50 APPENDIX J TYPE 8 TESTS) 81W-01F1. +++EXAMINATION CATEGORY F-A+++ 81W-01F1. EX EXEMPT CLASS 1, 2, OR 3 CATEGORY F-A COMPONENT SUPPORTS 81W-01F1. 1 +++PLATE AND SHELL TYPE SUPPORTS+++ 4444444t4444444444444fft440f4444f444444f4444f+444444404t44444444444444f44t4

+ t ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ITEMNO PAGE, 147 REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-01F1. 10 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE 81W-01F1.-20 WELDED CONNECTIONS TO BUILDING STRUCTURE 81W-01F1.30 WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS 8 1W-01F 1 . 40 DISPLACEMENT SETTINGS'ISALIGNMENT'ND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS 8 1W-01F2. +++EXAMINATION CATEGORY F-8+++ 81W-0 I F2. EX EXEMPT CLASS 1, 2, OR 3 CATEGORY F-8 COMPONENT SUPPORTS 81W-01F2. 1 +++LINEAR TYPE SUPPORTS+++ 81W-01F2.10 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT AND BUILDING I MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE 81W"01F2.20 WELDED CONNECTIONS TO BUILDING STRUCTURE ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt

tttttttttttttttttttttttttttttttttttttttttt ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT -'NIT 1 t PLANNING REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : ITEMNO PAGE 148 REVISION RRS1 DATE 85/12/05 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 81W-01F2.30 WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS 81W-01F2. 40 DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS 81W-01F2. 50 INVALID ITEMNO ttt THIS ITEMNO IS INVALID 81W-01F3. +++EXAMINATION CATEGORY F-C+++ 81W-0 I F3. EX EXEMPT CLASS 1, 2, OR 3 CATEGORY F-C COMPONENT SUPPORTS 81W-01F3. 1 +++COMPONENT STANDARD SUPPORTS+++ 81W-01F3. 10 MECHANICAL CONNECTIONS TO SUPPORTED COMPONENT ANO BUILDING MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE 81W-01F3. 20 WELDED CONNECTIONS TO BUILDING STRUCTURE 81W-01F3. 30 WELD 8 MECH CONNECTIONS IN SUPPORT INTERMEDIATE JOINTS WELD ANO MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL SUPPORTS

ee,e4444444444444444444444444444448444444444444444444404444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 4 REFERENCE CLUSTER LISTING 444444444444444404 DATA ELEMENT : ITEMNO PAGE 149 REVISION RRS1 DATE 85/12/05 444444444444444444444444444440440040004004404444044044444444444444444404440 REFERENCE KEY DESCRIPTION 81W-01F3. 40 DISPLACEMENT SETTINGS, MISALIGNMENT, AND ASSEMBLY OF SUPPORT I COMPONENT DISPLACEMENT SETTINGS OF GUIDES AND STOPS, MIS-ALIGNMENT OF SUPPORTS, ASSEMBLY OF SUPPORT ITEMS 81W-01F3. 50 SPRING, CONSTANT, SHOCK ABSORBER, AND SNUBBER SUPPORTS SPRING TYPE SUPPORTS, CONSTANT LOAD TYPE SUPPORTS, SHOCK AB-SORBERS, HYDRAULIC AND MECHANICAL TYPE SNUBBERS 444ff4444444444444404444444444f4444tt44f4444444444444444t44ff4

~tttttttttttttttttt                        tttttttttttttttt ttttttttttttttt NUTECH                                                           PRISIM CAROLINA POWER L LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING              tttttttttttttttttt DATA ELEMENT : EXSCHD                  PAGE        64 REVISION  RRS1 DATE 85/12/04 tttttttttttttttttt     tttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY                            DESCRIPTION AE              ACOUSTIC EMISSION TEST ET              EDDY CURRENT TEST MT              MAGNETIC PARTICLE TEST PT              PENETRANT TEST RT              RADIOGRAPHIC TEST RT-RCP          MINAC RADIOGRAPHIC TEST SUR             SURFACE EXAMINATION, TEST NOT SPECIFIED NOTE: THIS MUST BE UPDATED TO A PT OR MT BEFORE THE EXAM    IS SCHEDULED UC-45L          ULTRASONIC CIRCUMFERENTIAL SCAN-45 DEGREE LONGITUDINAL UT-IN           ULTRASONIC TEST IN-PLACE, CATEGORY   B-G-1, BOLTING UT-L            ULTRASONIC LAMINATION TEST UT-OUT          ULTRASONIC TEST WHEN REMOVED (OUT), CATEGORY   B-G-1, BOLTING UT-RVN          REACTOR VESSEL NOZZLE MECHANIZED ULTRASONIC TEST UT-RVS          REACTOR VESSEL SHELL MECHANIZED ULTRASONIC TEST UT-SN1          ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE NOZZLE SIDE WITH THE NOZZLE CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 000 DEGREES

ttttttttttttttttttttttttttttttttttttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING tttttttttttttttttt DATA ELEMENT : EXSCHD PAGE 65 REVISION RRS1 ttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION UT-SN2 ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE NOZZLE SIDE WITH THE NOZZLE CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 045 DEGREES UT-SP1 ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE PIPING SIDE WITH THE PIPING CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 000 DEGREES UT-SP2 ULTRASONIC TEST OF A SAFE END TO NOZZLE WELD FROM THE PIPING SIDE WITH THE PIPING CALIBRATION BLOCK. ULTRASONIC BEAM ANGLE = 045 DEGREES UT-T ULTRASONIC THICKNESS TEST UT-00 ULTRASONIC 0 DEGREE TEST UT-30S ULTRASONIC 30 DEGREE TEST-SHEAR UT-41L ULTRASONIC 41 DEGREE TEST - LONGITUDINAL UT-41R ULTRASONIC 41 DEGREE TEST REFRACTED LONGITUDINAL UT-41S ULTRASONIC 41 DEGREE TEST SHEAR UT-45 ULTRASONIC 45 DEGREE TEST (TO BE SPECIFIED) UT-45L ULTRASONIC 45 DEGREE TEST LONGITUDINAL UT-45R ULTRASONIC 45 DEGREE TEST REFRACTED LONGITUDINAL

44ICf 4444f 44 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444440444044444444 DATA ELEMENT : EXSCHD PAGE , 66 REVISION RRS1 DATE 85/12/04 4444444444444t4444444444444t4444t4444444t4444444444444444444444444444444444 REFERENCE KEY DESCRIPTION UT-45S ULTRASONIC 45 DEGREE TEST SHEAR UT-50S ULTRASONIC 50 DEGREE TEST SHEAR UT-53S ULTRASONIC 53 DEGREE TEST SHEAR UT-60 ULTRASONIC 60 DEGREE TEST (TO BE SPECIFIED) UT-60L ULTRASONIC 60 DEGREE TEST LONGITUDINAL UT-60R ULTRASONIC 60 DEGREE TEST - REFRACTED LONGITUDINAL UT-60S ULTRASONIC 60 DEGREE TEST - SHEAR UT-62S ULTRASONIC 62 DEGREE TEST-SHEAR UT-70S ULTRASONIC 70 DEGREE TEST-SHEAR UTAUTO ULTRASONIC MECHANIZED 0 DEGREE EXAMINATION VIS GENERAL VISUAL TEST VOL VOLUMETRIC EXAMINATION, TEST NOT SPECIFIED NOTE: THIS MUST BE UPDATED TO AE, RT, OR UT BEFORE THE THE EXAMINATION IS SCHEDULED VT-1 VISUAL TEST 1 PER IWA-2210 (77W AND LATER ADDENDA) VT-2 VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA)NOTE: VT-2 IS APPLICABLE TO CATEGORY B-E AND CATEGORY B-P, C-H. D-A, D-B, AND D-C IF THE ITEM NUMBER IS B15.EX, C7.EX, D1.EX, D2.EX OR D3.EX

4444444444 eesseeeee+eeeeeeeessseseeeeeeesseseeeeeeeesees +seetsessesseee>> NUTECH PRISIM 4 CAROLINA POWER 8 LIGHT COMPANY SYSTEM REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : EXSCHD PAGE 67 + REVISION RRS1 DATE 85/12/04 44tf44044444444404444f44444f04044f REFERENCE KEY DESCRIPTION VT-20T VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA) OPERATIONAL PRESSURE TESTING NOTE: VT-20T IS APPLICABLE TO ITEM NUMBERS 815.10, 815.20, 815.30, 815.40, 815.50, 815.60, 815.70, C7.10, C7.20, C7.30, C7.40, D1.10, D2.10, 03.10 VT-2ST VISUAL TEST 2 PER IWA-2210 (77W AND LATER ADDENDA) STATIC PRESSURE TESTING NOTE: VT-2ST IS APPLICABLE TO ITEM NUMBERS 815.11, 815.21, 815.31, 815.41, 815.51, 815.61, 815.71, C7.11, C7.21, C7.31, C7.41, D1.11, 02.11, C3.11 VT-3 VISUAL TEST 3 PER IWA-2210 (77W AND LATER ADDENDA) VT-4 VISUAL TEST 4 PER IWA-2210 (77W AND LATER ADDENDA) 444444444444444444444444444444444444444404444444444404404404440440440444444

EXAM REQUXPEMENT SOURCE a) ANN-NN

      ~Interval      Number Program   Number Type  of  Program Example:   P01"01 Preservice Section XX Program Interval - 1: Preservice is considered to be an  interval for computer purposes ~

P02-01 Preservice Augmented Program B02-03. Xnservice Augmented Program corresponding to P02-01 b) 81M-01

      ~Interval      Number f'r Xnservice Code Addendum                    Program

44404444444444444444444444444444444444t4444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : EXREQ PAGE 34 REVISION RRS 1 DATE 85/12/04 REFERENCE KEY DESCRIPTION

              ++   ALL ENTRIES IN THE EXREQ REFERENCE DESCRIPTION SHOULD BE CENTERED   LIKE A REPORT TITLE. THIS DESCRIPTION IS USED IN COMPONENT   LISTING (AND 10  YEAR PLAN), THE (INSERVICE)

INSPECTION STATUS REPORT, AND VARIOUS OTHER REPORTS IN THE REPORT TITLE. +++

              +++ EXREQ'S WITH A FIRST CHARACTER OF "A" ARE USED TO TRACK INSPECTION PROGRAMS KNOWN AS ADDITIONAL EXAMINATIONS.

IF UNACCEPTABLE INDICATIONS ARE FOUND IN A COMPONENT, OTHER (ADDITIONAL) COMPONENTS MUST BE EXAMINED IN ACCORDANCE WITH ASME SECTION XI, IWB-2430 AND IWC-2430, (81W) . +++

              +++ EXREQ'S WITH A FIRST CHARACTER OF "8" ARE USED TO TRACK EXAMINATION PROGRAMS THAT ARE REQUIRED BY A REGULATORY BODY SUCH AS THE NRC. THESE AUGMENTED EXAMINATION PROGRAMS ARE NOT BASED ON SECTION XI. +++

802-01 802-01 AUGMENTED EXAMINATION COMPONENT LISTING INTERVAL 01 REACTOR COOLANT PUMP FLYWHEEL INTEGRITY PER REGULATORY GUIDE 1. 14 802-01 AUGMENTED EXAMINATION STATUS REPORT INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS  : APPLICABLE, 40 MONTHS LONG 803-01 AVAILABLE FOR FUTURE USE 804-01 804-01 AUGMENTED EXAMINATION COMPONENT LISTING INTERVAL 01 AUGMENTED EXAMINATION OF CLASS 2 PIPING FROM PENETRATION TO CONTAINMENT ISOLATION VALVE PER FSAR SECTION 6.6.8. 804-01 AUGMENTED EXAMINATION STATUS REPORT INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE 44444444f4444440444444044t44444fJf440444444f44444444444

tttttttttttttttttttttttttttttttttttttttttttttttttttttttt+ttttttttttttttt NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING REFERENCE CLUSTER LISTING tttttttttt DATA ELEMENT : EXREQ PAGE 35 REVISION RRS1 DATE 85/12/04 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION 805-01 805-01 AUGMENTED EXAMINATION COMPONENT LISTING INTERVAL 01 AUGMENTED ISI EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK EXCLUSION REGION PER FSAR SECTION 6.6.8. 805-01 AUGMENTED EXAMINATION STATUS REPORT -INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE 806-01 806-01 AUGMENTED EXAMINATION COMPONENT LISTING INTERVAL 01 AUGMENTED ISI EXAMINATION OF PIPING: BETWEEN ISOLATION VALVES THROUGH PENETRATIONS PER FSAR SECTION 6.6.8. 806-01 AUGMENTED EXAMINATION STATUS REPORT- INTERVAL 01 INTERVAL: 10 YEARS COMMENCING WITH COMMERCIAL OPERATION PERIODS: NOT APPLICABLE

               +++   EXREQ'S WITH A FIRST CHARACTER OF "E" ARE USED TO TRACK ASME SECTION XI EXAMINATION PROGRAMS FOR THE FIRST INTERVALS OF OLDER PLANTS WHERE THE 1971 EDITION OF ASME SECTION XI WAS THE CODE IN EFFECT AT THE START OF THE INTERVAL. +++
               +++   EXREQ'S WITH A FIRST CHARACTER OF "P" ARE USED TO TRACK ASME SECTION   XI PRESERVICE (PSI ) INSPECTION PROGRAMS. +++

P01-01 P01-01 PRESERVICE INSPECTION COMPONENT LISTING INTERVAL 01 PRESERVICE INSPECTION OF COMPONENTS BASED ON SECTION XI 1980 EDITION THROUGH AND INCLUDING THE WINTER 1981 ADDENDA P01-01 PRESERVICE INSPECTION STATUS REPORT INTERVAL 01 INTERVAL PERIODS: NOT APPLICABLE P02-01 P02-01 AUGMENTED EXAMINATION COMPONENT LISTING PSI REACTOR COOLANT PUMP FLYWHEEL INTEGRITY PER REGULATORY GUIDE 1.14 P02-01 AUGMENTED EXAMINATION STATUS REPORT - PSI INTERVAL PERIODS: NOT APPLICABLE

44444444444444444440440 444444444444044444444t4444444444 444444444444444 NUTECH PRISIM CAROLINA POWER 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING REFERENCE CLUSTER LISTING 444444444444444444 DATA ELEMENT : EXREQ PAGE 36 REVISION RRS1 DATE 85/12/04 444 '4 4444440444444 4444444444444444444444444444444444444444'44444'444f4 REFERENCE KEY DESCRIPTION P03-0 I AVAILABLE FOR FUTURE USE P04-01 P04-01 AUGMENTED EXAMINATION COMPONENT LISTING PSI AUGMENTED EXAMINATION OF CLASS 2 PIPING FROM PENETRATION

                  'TO CONTAINMENT ISOLATION VALVE PER FSAR SECTION 6.6.8 P04"01 AUGMENTED EXAMINATION STATUS REPORT       -  PSI INTERVAL PERIODS     : NOT APPLICABLE P05-01                 P05-01 AUGMENTED EXAMINATION COMPONENT LISTING        -  PSI AUGMENTED PSI EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK EXCLUSION REGION PER FSAR SECTION          6.6.8.

P05-01 AUGMENTED EXAMINATION STATUS REPORT PSI INTERVAL PERIODS:NOT APPLICABLE P06-01 P06-0'I AUGMENTED EXAMINATION COMPONENT LISTING PSI AUGMENTED PSI EXAMINATION OF PIPING: BETWEEN ISOLATION VALVES THROUGH PENETRATIONS PER FSAR SECTION 6.6.8 P06-01 AUGMENTED EXAMINATION STATUS REPORT- PSI INTERVAL PERIODS:NOT APPLICABLE

                  +++ EXREQ'S WITH A FIRST CHARACTER OF "R" ARE USED TO TRACK INSPECTIONS OF COMPONENTS THAT HAVE BEEN REPAIRED OR REPLACED. ESSENTIALLY, THIS IS A PRESERVICE INSPECTION OF THE "NEW- COMPONENT BEFORE IT IS PLACED IN SERVICE.           +++
                  +++ 'EXREQ'S WITH A FIRST CHARACTER OF "S" ARE USED TO TRACK REPEAT (SUCCESSIVE) INSPECTIONS OF COMPONENTS THAT HAVE BEEN EXAMINED IN THE PAST AND HAD CONDITIONALLY ACCEPTABLE INDICATIONS. SUCCESSIVE EXAMINATIONS ARE REQUIRED IN ACCORDANCE WITH ASME SECTION XI, IWB-2420 AND IWC-2420, (81W) . +++

44444444444444444f444f4444444'40f44444444f'4444tft444444444444

t ttttttttttttttttttttttttttttttttttttttttttt NUTECH PRISIM CAROLINA POWER, 8 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT I PLANNING REFERENCE CLUSTER LISTING DATA ELEMENT : EXREQ PAGE 37 REVISION RRS1 DATE 85/12/04 ttttttttttttttttttttttttttttttttttttttttt REFERENCE KEY DESCRIPTION

              +++  EXREQ'S WITH A FIRST CHARACTER OF   "V" ARE USED TO TRACK VOLUNTARY INSPECTION PROGRAMS.   +++

V01-01 V01-01 VOLUNTARY EXAMINATION COMPONENT LISTING VOLUNTARY EXAMINATION-CLASS 1,2,83 COMPONENTS PSI AND 1ST INTERVAL ISI V01-01 VOLUNTARY EXAMINATION STATUS REPORT INTERVAL: PERIODS  : NOT APPLICABLE

              +++  EXREQ'S WITH A FIRST CHARACTER THAT IS NUMERIC (N) ARE USED TO TRACK THE ASME SECTION XI EXAMINATION PROGRAM(S)

APPLICABLE TO EACH INSPECTION INTERVAL. (SEE EXREQ'S STARTING WITH "E" FOR THE ONLY EXCEPTION TO THIS RULE) +++ 12W-04 TESTING OF THE FOURTH INTERVAL 81W-01 COMPONENT LISTING AND ISI 10 YEAR PLAN: 81W-01 ASME SECTION XI, 1980 EDITION THROUGH AND INCLUDING THE WINTER 1981 ADDENDA, INTERVAL 01 ONLY INSERVICE INSPECTION STATUS REPORT: 81W-01 90W-02 TESTING OF SECOND INTERVAL 99W-03 TESTING OF THE THIRD INTERVAL ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt

, ') 1 E.}}