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| | issue date = 09/29/1980 | | | issue date = 09/29/1980 |
| | title = Final Deficiency Rept Re Power Generation Control Complex/ Advanced Control Room Cable Connector.Insp Program Nearly Complete.All Unit 1 Cable Repairs Will Be Completed Prior to Fuel Load.Unit 2 Cables Will Be Installed & Repaired | | | title = Final Deficiency Rept Re Power Generation Control Complex/ Advanced Control Room Cable Connector.Insp Program Nearly Complete.All Unit 1 Cable Repairs Will Be Completed Prior to Fuel Load.Unit 2 Cables Will Be Installed & Repaired |
| | author name = CURTIS N W | | | author name = Curtis N |
| | author affiliation = PENNSYLVANIA POWER & LIGHT CO. | | | author affiliation = PENNSYLVANIA POWER & LIGHT CO. |
| | addressee name = GRIER B H | | | addressee name = Grier B |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | docket = 05000387, 05000388 | | | docket = 05000387, 05000388 |
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| {{#Wiki_filter:REGULA T I-'JFORHA I'IOlTI DISTRIBUT IO'I STE I (RIDS)ACCESSIO'I NOR'8010070086 DOC~DATE'0/09/29 iIOTARIZEO'uO DOCKET¹FACIL;Susquehanna Steam Electric Stationp Unit lp Pennsylva 05000387"38 Susquehanna Steam Electric StationE Jnit 2i Pennsylva 05000388 AUT~AUTHOR 4FF ILI ATION CURTIS',8~Pennsylvania Power It Light Co.~P[l RE C I P~u 4'4E RECIPIE'JT AFF ILIAT IO'J GR IER E B,n.Regi on 1 i Phi 1 adel phi ai Of f i ce of the Director | | {{#Wiki_filter:REGULA T I-'JFORHA I'IOlTI DISTRIBUT IO'I STE I (RIDS) |
| | ACCESSIO'I NOR'8010070086 DOC ~ DATE'0/09/29 iIOTARIZEO'uO DOCKET ¹ FACIL; Susquehanna Steam Electric Stationp Unit lp Pennsylva 05000387 "38 Susquehanna Steam Electric StationE Jnit 2i Pennsylva 05000388 AUT ~ AUTHOR 4FF ILIATION CURTIS',8 ~ Pennsylvania Power It Light Co. ~P [l RE C I P ~ u 4'4E RECIPIE'JT AFF ILIATIO'J GR IER E B,n. Regi on i Phi adel phi ai Of f i ce of the Director 1 1 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Final deficiency rept re power generation control complex/advanced control room cable connector, Inso program nearly complete.A11 Unit 1 cable reoairs will be completed orio,r to fuel loads Unit 2 cables will be installed 5 reoaried.DISTRIBUTION CODE: B019S COPIES RECEIVED:LTR g ENCL g SIZE:M TITLE: Construction Deficiency Report (10CFR50~55E)NOTES:Send IEE 3 copies FSAR 4 all amends'5000387 05000388 REC IP IETTIT ID CODE/.'PATE ACTIOI': A/0 LICEuSNG 04 RUSHBROOKP'DID 06 INTERNAL: AD/RC I/IE 17 ASLBP/J~HARD EDO 4 STAFF 19 IiYD/GEO BR 22 LIC QUAL BR 12'JRC PDR 02 REV 13 EG F I!-E 0 l 7 ORDS DEV 21 I COPIES L.rTR ENCL 1 1, 1 1-1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 REC IP IETVT ID CODE/'VANE YOUNGBLOODEB 05 STARKPR~07 AEOO 18 D/DIH HUM FAC15 EQUIP QUAL BR11 ICE 09!DIP A 20 OELD 21 QA BR 14 RUTHERFORDEH | | Final deficiency rept re power generation control complex/ |
| ~IE COPIES LTTR ETJCL 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 EXTERiuaL: | | advanced control room cable connector, Inso program nearly complete.A11 Unit 1 cable reoairs will be completed orio,r to fuel loads Unit 2 cables will be installed 5 reoaried. |
| ACRS EIS I C 16 16 16 08 1 1 1PDR 03 TOT AL'IU'LIBE JJ OF COPIES cl EQV IRED: LT TR 40 E VCL 40 I P"L.TWO NORTH N1NTM STREEt, ALLENTOWN, PA.1810)PHONE;(215)821~5151 September 29, 1980.'!r.Boyce H.Grier Director, Region I U.S.Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 SUSQUEPANNA STEP~M ELECTRIC STATION FINAL REPORT OF A DEFICIENCY ON PGCC/ACR CABLE CONNECTORS ERs 100450/100508 FILE 840-4/900-10 PLA-545 | | DISTRIBUTION CODE: B019S COPIES RECEIVED:LTR TITLE: Construction Deficiency Report (10CFR50 ~ 55E) g ENCL g SIZE:M NOTES:Send IEE 3 copies FSAR 4 all amends'5000387 05000388 I |
| | REC IP IETTIT COPIES REC IP IETVT COPIES ID CODE/.'PATE L.rTR ENCL ID CODE/'VANE LTTR ETJCL ACTIOI': A/0 LICEuSNG 04 1 YOUNGBLOODEB 05 1 RUSHBROOKP'DID 06 1, 1 STARKPR ~ 07 1 1 INTERNAL: AD/RC I/IE 17 1 -1 AEOO 18 1 1 ASLBP/J ~ HARD 1 1 D/DIH HUM FAC15 1 1 EDO 4 STAFF 19 1 1 EQUIP QUAL BR11 1 1 IiYD/GEO BR 22 1 1 ICE 09 2 2 LIC QUAL BR 12 1 1 !DIP A 20 1 1 |
| | 'JRC PDR 02 1 1 OELD 21 1 1 REV 13 1 1 QA BR 14 1 1 EG F I!-E 0 l 1 RUTHERFORDEH ~ IE 1 1 7 ORDS DEV 21 1 1 EXTERiuaL: ACRS 16 16 16 1PDR 03 EIS IC 08 1 1 TOT AL 'IU'LIBEJJ OF COPIES cl EQV IRED: LT TR 40 E VCL 40 I |
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| | P"L. |
| | TWO NORTH N1NTM STREEt, ALLENTOWN, PA. 1810) PHONE; (215) 821 5151 |
| | ~ |
| | September 29, 1980 |
| | .'!r. Boyce H. Grier Director, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 SUSQUEPANNA STEP~M ELECTRIC STATION FINAL REPORT OF A DEFICIENCY ON PGCC/ACR CABLE CONNECTORS ERs 100450/100508 FILE 840-4/900-10 PLA-545 |
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| ==References:== | | ==References:== |
| | PLA-437 dated January 8, 1980 PLA-301 dated November 14, 1978 |
| | |
| | ==Dear i!r. Grier:== |
| | |
| | This letter serves to provide the Commission with a final report of a |
| | 'deficiency on Power Generation Control Comp1.ex/Advanced Control Room (PGCC/ACR) cable connector deficiencies originally reported in PLA-301. |
| | The information is furnished pursuant to PP&L's obligations under of 10CFR50.55(e). the'rovisions The attachment to this letter describes the deficient condition along with its safety implications and the corrective action being taken to achieve resolution. |
| | He trust the Commission will find the information forwarded by this letter to be satisfactory. |
| | truly yours, 'ery N,''. Curtis Vice President-Engineering & Construction-Nuclear Attachment j |
| | FLU'. mk |
| | / / |
| | I 0XOopn pqg PENNSYLVANlA POWER 8, LIGHT COMPANY |
| | |
| | i'fr. Boyce H. Grier September 19, 1980 |
| | ': ello (15) |
| | D'".=.ctor-~'fiice of Inspection & Enforcement |
| | : uclear Regulatory Commission D C 20555 |
| | ;. YcDonald, Director Of='.'e of !!anagement information & Program Control L'. S. Nuclear Regulatory Commission 4'asnington, D.C. 20555 Nr. Robert .'f. Gallo U. S. nuclear Regulatory Commission P, Q. Box 52 Sh c!:.sninny, Pennsylvania 18655 |
| | |
| | ATTACHbKNT TO PLA 545 Page 1 of 3 PGCC/ACR CABLE PROBLEh/S FINAL REPORT C/ACR Cab'c P:oblems DESCRIPTION In letters from Bechtel Construction dated October 3, 1978, PP5L was informed that during implementation of General Electric's FDDR-KR1-521, Rev. 0 (General Cable Retrofit) rework, it was noted that numerous cases of |
| | -'nsulation damages were found and that one cable was found to have four (4) conductors pulled from their pin connectors. Due to the high percentage of damaged cable, the quality of all terminations was rendered indeterminate. |
| | NCR-3231 was generated to document the problems within the PGCC/ACR complex. t, was agreed to by PP5L, Bechtel and General Electric, that GE |
| | >>ould prepar an FDI which should have details of a complete inspection plan and an approved repair procedure. |
| | In Februarv, 1979, GE issued FDI-NJGO Rev. 0 to perform a 100'o inspection of all GE supplied SITS/FITS cables used in the Susquehanna 1 ACR control room, upper relay room and lower relay room for damaged insulation and suspect pin crimps. |
| | Approved methods of repair for damaged PGCC/ACR cable connectors identified during the inspections performed under FDI-t'fJGO were accomplished in accordance with GE FDDR-KRl-526. This FDDR was originally issued on Sept. 6, 1978 to control the repair of PGCC/ACR panel connectors. The Panel Ccnnector problems were explained in our PLA-506 dated July 8, 1980. |
| | The inspections, repair/rework and tests for the cables under FDI-ÃJGO, FDDR-KR1-526, their revisions and'ddendums are nearly complete. A total of 1762 cables have been inspected. The results of the inspection are as follows: |
| | ~Dame e guuant it |
| | : 1. Nicks to conductor insulation 264 Cuts to conductor insulation 346 Damaged or no shrink tubing 265 Pins pulled off during pull test or fell off 58 during depinning |
| | ."ot pinned in accordance with wire list or 78 ass ."..bly method V~ F !iled continuity 21 |
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| PLA-437 dated January 8, 1980 PLA-301 dated November 14, 1978
| | CAUSE |
| | {a} and ", nicks and cuts to conductor insulation; after having inves- |
| | =!~'..";~'.:,"-'arced con"uctor insulation within the T-'.lOD wiring "o a conne." sr, |
| | :.'~;e".."..ired by GE that during reassembly (i.e., pin insertion and ez-trac"icn u ing the standard Amphenol tooling for the termination modules) continual difficulty was experienced. The ferrule edge during extraction and the sharp insertion tool edge during assembly impacted on the densely packed w res at the connector area causing nicks, cuts and abrasions. |
| | (b) It~.. 3, damaged or no shrink tubing, can be broken into two (2) parts: (1) the damaged shrink tubing could have been caused at the factory during asse...bly of the cable or at the construction site during installation; and (2) the lack of shrink tubing was due to an oversight in manufacturing. |
| | (c) Item 4, pins pulled off during pull test or which fell off during depinning; it was determined that a combination of manufacturing personnel error and cr-'mping tool malfunction, due to inadequate QA coverage, was responsible for defective cr mps. This would account for pins failing pull tests or falling off during depinning. |
| | (d) Item 5, not pinned in accordance with wire list or assembly method, is a manufacturing error; i.e., the conductor might be pinned in hole A in a connector but in hole B in the connector on the opposite end of the cable. |
| | (e) Item 6, failed continuity, is a direct resul't of the conductor not pinned in accordance with the wire list or assembly method (Item 5). |
| | ANALYSIS OF SAFETY DPLICATIONS As the various problems are of a random nature and there are a number of Class 1E cables involved, the Safety Analysis is presented on an item by item basis as follows: |
| | (a) In items 1, 2 and 3, nicks and cuts to conductor insulation and damaged or no heat shrink tubing, if bare copper wire is exposed and left uncorrected, permit shorting of wires or introduction of external voltages into i'ould safety related circuits. Any of these conditions could prevent the circuits from performing the designed safety function. |
| | (b) Items 4, 5 and 6, pins pulled off during pull test or fell off during depinning, not pinned in accordance with wire list or assembly method and failed continuity, could affect the designed safety functions. If during a seismic event, the conductor vibrates loosely in the pin so that there is sporadic or no continuity between the pin and conductor, or if the conductor is not pinned correctly such that there is no continuity between the proper connector pins at each end of the table, the operation of the circuit could be adversely affected. |
| | Project Engineering has determined that the above items are reportable under 10CF?5C.55(e)., |
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| |
|
| ==Dear i!r.Grier:==
| | -3>> |
| This letter serves to provide the Commission with a final report of a'deficiency on Power Generation Control Comp1.ex/Advanced Control Room (PGCC/ACR) cable connector deficiencies originally reported in PLA-301.The information is furnished pursuant to PP&L's obligations under the'rovisions of 10CFR50.55(e).
| | CORRECTIVE ACTIONS The 100% inspection program for PGCC cable connectors and repair/rework for the problems listed in NCR-3231 is nearly complete. |
| The attachment to this letter describes the deficient condition along with its safety implications and the corrective action being taken to achieve resolution.
| | ...."= '.o prevent recur'rences of like p oh's ~ ".:t.~;e i'GCC couche connectors', and which are also applicable to the Susquehanna PGCC/ACR Unit 2 cables, are indicated by GE to be: |
| He trust the Commission will find the information forwarded by this letter to be satisfactory.
| | t (1) Appropriate training of personnel involved. |
| 'ery truly yours, N,''.Curtis Vice President-Engineering
| | (2) 'Revision of fabrication techniques. |
| &Construction-Nuclear Attachment FLU'.j mk//I PENNSYLVANlA POWER 8, LIGHT COMPANY 0XOopn pqg i'fr.Boyce H.Grier September 19, 1980': ello (15)D'".=.ctor-~'fiice of Inspection
| | (3) Increased/revised inspection activities. |
| &Enforcement
| | (4) GE has developed a supplemental reinspection instruction (GE Inspection Instruction CA-006) to identify damaged or nonconforming connectors prior to shipment. Satisfactory completion of this cable reinspection on Susquehanna Unit 2 cables was reverified by PPRL audit on Sept. 9-11, 1980 at the GE manufacturing facility in San Jose, CA. |
| : uclear Regulatory Commission D C 20555;.YcDonald, Director Of='.'e of!!anagement information
| | In addition, faulty crimping tools were repaired or replaced and periodic testing of crimping tools was increased. |
| &Program Control L'.S.Nuclear Regulatory Commission 4'asnington, D.C.20555 Nr.Robert.'f.Gallo U.S.nuclear Regulatory Commission P, Q.Box 52 Sh c!:.sninny, Pennsylvania 18655 ATTACHbKNT TO PLA 545 Page 1 of 3 PGCC/ACR CABLE PROBLEh/S FINAL REPORT C/ACR Cab'c P:oblems DESCRIPTION In letters from Bechtel Construction dated October 3, 1978, PP5L was informed that during implementation of General Electric's FDDR-KR1-521, Rev.0 (General Cable Retrofit)rework, it was noted that numerous cases of-'nsulation damages were found and that one cable was found to have four (4)conductors pulled from their pin connectors.
| | Construction site personnel have been given further instructions in the handling and installation of cables. The site electricians have been instructed to use a steady pull (not a yank) when making pull tests and the spring testers are calibrated every 30 days or sooner if deemed necessary. |
| Due to the high percentage of damaged cable, the quality of all terminations was rendered indeterminate.
| | CONCLUSIONS The repair/rework and testing of the Unit 1 PGCC/ACR cables is nearly complete. All Unit 1 PGCC/ACR cables will be completed prior to fuel load. |
| NCR-3231 was generated to document the problems within the PGCC/ACR complex.t, was agreed to by PP5L, Bechtel and General Electric, that GE>>ould prepar an FDI which should have details of a complete inspection plan and an approved repair procedure.
| | The Unit 2 PGCC/ACR cables will be installed and repaired or reworked as necessary. Discrepancies will be documented on an NCR. |
| In Februarv, 1979, GE issued FDI-NJGO Rev.0 to perform a 100'o inspection of all GE supplied SITS/FITS cables used in the Susquehanna 1 ACR control room, upper relay room and lower relay room for damaged insulation and suspect pin crimps.Approved methods of repair for damaged PGCC/ACR cable connectors identified during the inspections performed under FDI-t'fJGO were accomplished in accordance with GE FDDR-KRl-526.
| | For Unit 2 PGCC/ACR cables, field inspections of the equipment and additional GE fabrication personnel training, inspection and revised fabrication techniques should preclude recurrence of similar problems.}} |
| This FDDR was originally issued on Sept.6, 1978 to control the repair of PGCC/ACR panel connectors.
| |
| The Panel Ccnnector problems were explained in our PLA-506 dated July 8, 1980.The inspections, repair/rework and tests for the cables under FDI-ÃJGO, FDDR-KR1-526, their revisions and'ddendums are nearly complete.A total of 1762 cables have been inspected.
| |
| The results of the inspection are as follows:~Dame e guuant it 1.Nicks to conductor insulation 264 Cuts to conductor insulation Damaged or no shrink tubing 346 265 Pins pulled off during pull test or fell off during depinning 58."ot pinned in accordance with wire list or ass."..bly method 78 V~F!iled continuity 21 CAUSE{a}and", nicks and cuts to conductor insulation; after having inves-=!~'..";~'.:,"-'arced con"uctor insulation within the T-'.lOD wiring"o a conne." sr,:.'~;e".."..ired by GE that during reassembly (i.e., pin insertion and ez-trac"icn u ing the standard Amphenol tooling for the termination modules)continual difficulty was experienced.
| |
| The ferrule edge during extraction and the sharp insertion tool edge during assembly impacted on the densely packed w res at the connector area causing nicks, cuts and abrasions.(b)It~..3, damaged or no shrink tubing, can be broken into two (2)parts: (1)the damaged shrink tubing could have been caused at the factory during asse...bly of the cable or at the construction site during installation; and (2)the lack of shrink tubing was due to an oversight in manufacturing.(c)Item 4, pins pulled off during pull test or which fell off during depinning; it was determined that a combination of manufacturing personnel error and cr-'mping tool malfunction, due to inadequate QA coverage, was responsible for defective cr mps.This would account for pins failing pull tests or falling off during depinning.(d)Item 5, not pinned in accordance with wire list or assembly method, is a manufacturing error;i.e., the conductor might be pinned in hole A in a connector but in hole B in the connector on the opposite end of the cable.(e)Item 6, failed continuity, is a direct resul't of the conductor not pinned in accordance with the wire list or assembly method (Item 5).ANALYSIS OF SAFETY DPLICATIONS As the various problems are of a random nature and there are a number of Class 1E cables involved, the Safety Analysis is presented on an item by item basis as follows: (a)In items 1, 2 and 3, nicks and cuts to conductor insulation and damaged or no heat shrink tubing, if bare copper wire is exposed and left uncorrected, i'ould permit shorting of wires or introduction of external voltages into safety related circuits.Any of these conditions could prevent the circuits from performing the designed safety function.(b)Items 4, 5 and 6, pins pulled off during pull test or fell off during depinning, not pinned in accordance with wire list or assembly method and failed continuity, could affect the designed safety functions.
| |
| If during a seismic event, the conductor vibrates loosely in the pin so that there is sporadic or no continuity between the pin and conductor, or if the conductor is not pinned correctly such that there is no continuity between the proper connector pins at each end of the table, the operation of the circuit could be adversely affected.Project Engineering has determined that the above items are reportable under 10CF?5C.55(e).,
| |
| -3>>CORRECTIVE ACTIONS The 100%inspection program for PGCC cable connectors and repair/rework for the problems listed in NCR-3231 is nearly complete....."='.o prevent recur'rences of like p oh's~".:t.~;e i'GCC couche connectors', and which are also applicable to the Susquehanna PGCC/ACR Unit 2 cables, are indicated by GE to be: t (1)Appropriate training of personnel involved.(2)'Revision of fabrication techniques.
| |
| (3)Increased/revised inspection activities. | |
| (4)GE has developed a supplemental reinspection instruction (GE Inspection Instruction CA-006)to identify damaged or nonconforming connectors prior to shipment.Satisfactory completion of this cable reinspection on Susquehanna Unit 2 cables was reverified by PPRL audit on Sept.9-11, 1980 at the GE manufacturing facility in San Jose, CA.In addition, faulty crimping tools were repaired or replaced and periodic testing of crimping tools was increased. | |
| Construction site personnel have been given further instructions in the handling and installation of cables.The site electricians have been instructed to use a steady pull (not a yank)when making pull tests and the spring testers are calibrated every 30 days or sooner if deemed necessary. | |
| CONCLUSIONS The repair/rework and testing of the Unit 1 PGCC/ACR cables is nearly complete.All Unit 1 PGCC/ACR cables will be completed prior to fuel load.The Unit 2 PGCC/ACR cables will be installed and repaired or reworked as necessary. | |
| Discrepancies will be documented on an NCR.For Unit 2 PGCC/ACR cables, field inspections of the equipment and additional GE fabrication personnel training, inspection and revised fabrication techniques should preclude recurrence of similar problems.}} | |
|
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
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Initially Reported on 820316.Reversal of Valve Disks & Valves No Longer Considered Necessary PLA-2230, Final Deficiency Rept Re Electrical Separation Inside Multiple Div Junction & Pull Boxes.Initially Reported on 830721.Drawings Revised to Clarify &/Or Define Sparation Requirements for Use W/Junction & Pull Boxes1984-06-28028 June 1984 Final Deficiency Rept Re Electrical Separation Inside Multiple Div Junction & Pull Boxes.Initially Reported on 830721.Drawings Revised to Clarify &/Or Define Sparation Requirements for Use W/Junction & Pull Boxes PLA-2118, Final Part 21/deficiency Rept Re Clamps on CRD Insert/ Withdrawal Lines.Initially Reported on 831209.Outer Pedestal Modified Due to Lack of Sufficient Axial Restraint Capacity of Inner Pedestal Support1984-06-18018 June 1984 Final Part 21/deficiency Rept Re Clamps on CRD Insert/ Withdrawal Lines.Initially Reported on 831209.Outer Pedestal Modified Due to Lack of Sufficient Axial Restraint Capacity of Inner Pedestal Support PLA-2215, Final Deficiency Rept Re Base Metal Cracking & Bending of Angle Fittings Mfg by Unistrut,Powerstrut & B-Line Used on Class IE Electrical Raceways & Category 1 HVAC Supports. Initially Reported on 840206.Spec Revised1984-06-0101 June 1984 Final Deficiency Rept Re Base Metal Cracking & Bending of Angle Fittings Mfg by Unistrut,Powerstrut & B-Line Used on Class IE Electrical Raceways & Category 1 HVAC Supports. Initially Reported on 840206.Spec Revised PLA-2189, Final Part 21 Rept Re GE Reactor Mode Switch.Initially Reported on 830407.Mode Switch Design Modified,Per Franklin Inst Research Lab Recommendations1984-05-21021 May 1984 Final Part 21 Rept Re GE Reactor Mode Switch.Initially Reported on 830407.Mode Switch Design Modified,Per Franklin Inst Research Lab Recommendations ML20084C2851984-04-19019 April 1984 Final Deficiency Rept Re Waterhammer Loading of Scram Discharge Vol (SDV) Vent & Drain Lines After Opening SDV Vent & Drain Valves on Scram Reset.Initially Reported on 830628.Vent Line Supports Will Be Modified Prior to 841231 PLA-2180, Final Part 21/deficiency Rept Re Improper Relief Valve Settings,Design Pressures & Temps.Initially Reported on 831118.Calculations Performed Assure Lines Adequate for Intended Svc1984-04-19019 April 1984 Final Part 21/deficiency Rept Re Improper Relief Valve Settings,Design Pressures & Temps.Initially Reported on 831118.Calculations Performed Assure Lines Adequate for Intended Svc PLA-2166, Part 21 Rept Re Failure of Crosby IMF-2 Solenoids Supplied by Ge.Initially Reported on 840403.Licensee & GE Jointly Developed Test Procedures to Bench Test Spares & Solenoids on Both Units.Testing Complete on Unit 11984-04-0909 April 1984 Part 21 Rept Re Failure of Crosby IMF-2 Solenoids Supplied by Ge.Initially Reported on 840403.Licensee & GE Jointly Developed Test Procedures to Bench Test Spares & Solenoids on Both Units.Testing Complete on Unit 1 PLA-2137, Revised Final Deficiency Rept Re Fraying of Hydrogen Recombiner Cables.Initially Reported on 830728.Fraying Caused by Handling Process for Shipment,Installation & Testing.Cables Repaired1984-03-23023 March 1984 Revised Final Deficiency Rept Re Fraying of Hydrogen Recombiner Cables.Initially Reported on 830728.Fraying Caused by Handling Process for Shipment,Installation & Testing.Cables Repaired PLA-2140, Second Interim Deficiency Rept Re Base Metal Cracking in Angle Fittings.Initially Reported on 840206.Angle Fittings Added to Defective Device List & Conduit Installation Spec Revised.Also Reportable Per 10CFR211984-03-22022 March 1984 Second Interim Deficiency Rept Re Base Metal Cracking in Angle Fittings.Initially Reported on 840206.Angle Fittings Added to Defective Device List & Conduit Installation Spec Revised.Also Reportable Per 10CFR21 PLA-2074, Third Interim Deficiency Rept Re Electrical Separation Inside Multiple Division Junction & Pull Box.Initially Reported on 830721.Design Basis Criteria & Barrier Configuration Established.Also Reported Per Part 211984-03-20020 March 1984 Third Interim Deficiency Rept Re Electrical Separation Inside Multiple Division Junction & Pull Box.Initially Reported on 830721.Design Basis Criteria & Barrier Configuration Established.Also Reported Per Part 21 PLA-2120, Interim Part 21/deficiency Rept Re Base Metal Cracking in Fittings Used on Class IE Electrical Raceways & HVAC Supports.Initially Reported on 840206.Final Rept Expected Prior to Initial Criticality1984-03-0707 March 1984 Interim Part 21/deficiency Rept Re Base Metal Cracking in Fittings Used on Class IE Electrical Raceways & HVAC Supports.Initially Reported on 840206.Final Rept Expected Prior to Initial Criticality PLA-2103, Final Deficiency Rept Re Cavitation of Jet Pumps Due to Induction Heating Stress Improvement Cooling.Initially Reported on 831206.No Erosion Found.Also Reportable Per Part 21.Item Not Reportable Per 10CFR50.55(e)1984-03-0606 March 1984 Final Deficiency Rept Re Cavitation of Jet Pumps Due to Induction Heating Stress Improvement Cooling.Initially Reported on 831206.No Erosion Found.Also Reportable Per Part 21.Item Not Reportable Per 10CFR50.55(e) PLA-2075, Second Interim Deficiency Rept Re Improper Relief Valve Setting,Design Pressures & Design Temp within Several Sys. Initially Reported on 831118.Spec M-199 Revised & Code Data Repts Amended.Also Reported Per Part 211984-03-0202 March 1984 Second Interim Deficiency Rept Re Improper Relief Valve Setting,Design Pressures & Design Temp within Several Sys. Initially Reported on 831118.Spec M-199 Revised & Code Data Repts Amended.Also Reported Per Part 21 PLA-2089, Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling1984-02-27027 February 1984 Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling PLA-2062, Final Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Caused by Failure to Complete Required Cable Length Verification.Deficiency Not Reportable Per 10CFR50.55(e)1984-02-13013 February 1984 Final Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Caused by Failure to Complete Required Cable Length Verification.Deficiency Not Reportable Per 10CFR50.55(e) PLA-2073, Final Part 21 Rept Re Hydrogen Catalyst Used in Comsip Custom Line Model K-IV Containment Gas Monitoring Panels. Initially Reported on 840113.Comsip Redesigned Catalyst Will Be Installed1984-02-13013 February 1984 Final Part 21 Rept Re Hydrogen Catalyst Used in Comsip Custom Line Model K-IV Containment Gas Monitoring Panels. Initially Reported on 840113.Comsip Redesigned Catalyst Will Be Installed PLA-2063, Interim Part 21 Rept Re Safety Parameter Display Sys Model 156 Isolators Mfg by Technology for Energy Corp (Tec). Initially Reported on 840106.All Tec Isolators Reviewed for Corrective Actions1984-02-0606 February 1984 Interim Part 21 Rept Re Safety Parameter Display Sys Model 156 Isolators Mfg by Technology for Energy Corp (Tec). Initially Reported on 840106.All Tec Isolators Reviewed for Corrective Actions PLA-2045, Followup Deficiency Rept Re Mod of RHR Globe Valves F017A & FO17B to Enable Valves in Shutdown Cooling Mode to Perform W/O Adverse Cavitation & Vibration at Low Flow Rates.Initially Reported on 811112.Valves Replaced1984-01-25025 January 1984 Followup Deficiency Rept Re Mod of RHR Globe Valves F017A & FO17B to Enable Valves in Shutdown Cooling Mode to Perform W/O Adverse Cavitation & Vibration at Low Flow Rates.Initially Reported on 811112.Valves Replaced PLA-2033, Interim Deficiency Rept Re Clamps on Control Rod Drive Insert/Withdraw Lines Not Providing Axial Restraint. Initially Reported on 831209.Design Mod to Pedestal Support Initiated.Also Reportable Per Part 211984-01-12012 January 1984 Interim Deficiency Rept Re Clamps on Control Rod Drive Insert/Withdraw Lines Not Providing Axial Restraint. Initially Reported on 831209.Design Mod to Pedestal Support Initiated.Also Reportable Per Part 21 PLA-2026, Interim Deficiency Rept Re GE Reactor Mode Switch.Proposed Redesign of Mode Switch by GE Rejected,Based on Results of Testing Conducted at Franklin Inst Research Lab.Alternate Switch Ordered Through Electroswitch.Final Rept by Apr 19841984-01-12012 January 1984 Interim Deficiency Rept Re GE Reactor Mode Switch.Proposed Redesign of Mode Switch by GE Rejected,Based on Results of Testing Conducted at Franklin Inst Research Lab.Alternate Switch Ordered Through Electroswitch.Final Rept by Apr 1984 PLA-2009, Final Deficiency Rept Re Standby Gas Treatment Sys (SGTS) Performance Not as Described in Fsar.Fsar Change Prepared to Indicate SGTS May Be Required to Maintain Secondary Containment Integrity1984-01-0909 January 1984 Final Deficiency Rept Re Standby Gas Treatment Sys (SGTS) Performance Not as Described in Fsar.Fsar Change Prepared to Indicate SGTS May Be Required to Maintain Secondary Containment Integrity PLA-1990, Final Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Permanent Mod Consists of Rerouting Drywell & Wetwell Nitrogen Makeup Lines to Spare Penetrations.Divisionalized Isolation Valves Will Be Installed1983-12-30030 December 1983 Final Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Permanent Mod Consists of Rerouting Drywell & Wetwell Nitrogen Makeup Lines to Spare Penetrations.Divisionalized Isolation Valves Will Be Installed PLA-1946, Interim Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Bechtel Completed & Documented Required Cable Length Verification & Calculations1983-12-30030 December 1983 Interim Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Bechtel Completed & Documented Required Cable Length Verification & Calculations PLA-1991, Final Deficiency Rept Re Cracks in Pacific Scientific PSA-1 & PSA-3 Snubber Capstan Springs.Caused by Improper Spring Forming.Snubbers Will Be Corrected Prior to Completion of First Refueling Outage.Also Reported Per Part 211983-12-27027 December 1983 Final Deficiency Rept Re Cracks in Pacific Scientific PSA-1 & PSA-3 Snubber Capstan Springs.Caused by Improper Spring Forming.Snubbers Will Be Corrected Prior to Completion of First Refueling Outage.Also Reported Per Part 21 PLA-2000, Interim Deficiency Rept Re Electrical Sys Separation in Multiple Div Pull & Junction Boxes.One Box Identified Containing Redundant Channel C & D Circuits Insufficiently Separated by Approved Barrier1983-12-27027 December 1983 Interim Deficiency Rept Re Electrical Sys Separation in Multiple Div Pull & Junction Boxes.One Box Identified Containing Redundant Channel C & D Circuits Insufficiently Separated by Approved Barrier PLA-2006, Interim Part 21 Rept Re Improper Relief Valve Settings & Design Pressures & Temps Found in Hpci,Rcic,Rhr,Core Spray & Essential Svc Water Sys.Initially Reported on 831118. Hydrotests Performed1983-12-20020 December 1983 Interim Part 21 Rept Re Improper Relief Valve Settings & Design Pressures & Temps Found in Hpci,Rcic,Rhr,Core Spray & Essential Svc Water Sys.Initially Reported on 831118. Hydrotests Performed PLA-1987, Updated Interim Deficiency Rept Re Scram Discharge Vol Vent & Drain Valve Waterhammer.Testing & Subsequent Analysis Will Be Completed in Mar 1984.Util Will Submit Final Rept by Apr 19841983-12-14014 December 1983 Updated Interim Deficiency Rept Re Scram Discharge Vol Vent & Drain Valve Waterhammer.Testing & Subsequent Analysis Will Be Completed in Mar 1984.Util Will Submit Final Rept by Apr 1984 PLA-1967, Final Deficiency Rept Re Suppression Pool Temp Monitoring Sys (Spotmos).Initially Reported on 821015.Modified Installation Configuration Tested.Review of Test Results Will Be Completed by End of Mar 19841983-12-13013 December 1983 Final Deficiency Rept Re Suppression Pool Temp Monitoring Sys (Spotmos).Initially Reported on 821015.Modified Installation Configuration Tested.Review of Test Results Will Be Completed by End of Mar 1984 PLA-1968, Final Deficiency & Part 21 Repts Re Final Design of GE 7700 Series 250-volt Dc Control Ctrs.Plant Operating Procedures Revised to Include Methods of Clearing Obstructions as Provided by GE & Exam & Reforming of Draw Out Contacts1983-12-0505 December 1983 Final Deficiency & Part 21 Repts Re Final Design of GE 7700 Series 250-volt Dc Control Ctrs.Plant Operating Procedures Revised to Include Methods of Clearing Obstructions as Provided by GE & Exam & Reforming of Draw Out Contacts 1998-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML20206D3331999-04-27027 April 1999 SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20 ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML17164A8451998-10-31031 October 1998 SSES Unit 1 Tenth Refueling & Insp Outage ISI Outage Summary Rept. ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20217Q4891998-04-21021 April 1998 Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation ML18026A4931998-03-30030 March 1998 LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement ML18026A5401998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Susquehanna Steam Electric Station.W/980313 Ltr ML18026A4891997-11-17017 November 1997 LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed ML18017A2921997-10-28028 October 1997 1997 Nrc/Fema Observed Exercise. ML17158C1861997-06-0505 June 1997 Proceedings of Intl Topical Meeting on Advanced Reactors Safety Vol II, on 970601-05 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML18026A4781997-03-28028 March 1997 Rev 1 to Application of Anfb to ATRIUM-10 for Susquehanna Reloads. ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20155F7661996-07-25025 July 1996 Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment ML20155F7491996-07-24024 July 1996 Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML18026A5961996-01-0202 January 1996 LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr ML18017A0511995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for SSES Units 1 & 2. W/951215 Ltr ML20092H7641995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Susquehanna Ses ML17158A8771995-08-15015 August 1995 Exercise Manual. ML17158A8061995-07-14014 July 1995 Books 1 & 2 of ISI Outage Summary Rept SSES Unit 1 8th Refuel Outage. ML18017A0461995-07-0707 July 1995 LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation ML17164A6631995-04-11011 April 1995 Impact of Extending T-10 AOT from 3 to 7 Days. ML17164A5871995-01-31031 January 1995 Monthly Operating Repts for Jan 1995 for Susquehanna Ses ML18026A5351994-10-31031 October 1994 SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing ML17158A4821994-08-23023 August 1994 ISI Outage Summary Rept Unit 2 6th Refueling Outage, Books 1 & 2 of 2 ML17158A2391994-04-0505 April 1994 Books 1 & 2 of SSES Unit 1 Seventh Refueling & Insp Outage ISI Outage Summary Rept. ML18017A2701993-12-31031 December 1993 PP&L Annual Rept 1993. ML17158A2651993-12-31031 December 1993 Allegheny Electric Cooperative,Inc Annual Rept 1993. ML17158A1631993-12-0909 December 1993 Remote Indication of Spent Fuel Pool Level & Temperature. ML18026A4281993-08-16016 August 1993 PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2. ML18026A4261993-06-0909 June 1993 LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr ML17157C2441993-02-28028 February 1993 Monthly Operating Rept for Feb 1993 for Susquehanna Steam Electric Station,Units 1 & 2 ML18017A2031993-02-0101 February 1993 Books 1 & 2 of Unit 2 Fifth Refueling & Insp Outage,Isi Outage Summary Rept. ML20044C2741993-01-31031 January 1993 Corrected Monthly Operating Rept for Jan 1993 for Susquehanna Steam Electric Station,Unit 2,consisting of Info on Unit Shutdowns & Power Reductions ML17157C3691992-12-31031 December 1992 PP&L Annual Rept 1992. ML20056C3941992-12-31031 December 1992 Allegheny Electric Cooperative,Inc Annual Rept 1992 ML18017A0421992-12-14014 December 1992 Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3 ML18026A2481992-11-27027 November 1992 Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling ML18026A4231992-11-17017 November 1992 LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr ML17157C1421992-10-21021 October 1992 Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020. ML17157C1411992-08-31031 August 1992 Loss of Fuel Pool Cooling Event Evaluation. ML17157C1401992-08-31031 August 1992 Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2. ML20082C4941992-08-14014 August 1992 Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl ML17157C1381992-07-27027 July 1992 Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station. ML17157B9331992-07-24024 July 1992 Sixth Refueling & Insp Outage Inservice Insp Outage Summary Rept, Books 1 & 2 ML20097D4681991-12-31031 December 1991 Pennsylvania Power & Light Company,1991 Annual Rept ML18017A0391991-07-26026 July 1991 LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr 1999-09-30
[Table view] |
Text
REGULA T I-'JFORHA I'IOlTI DISTRIBUT IO'I STE I (RIDS)
ACCESSIO'I NOR'8010070086 DOC ~ DATE'0/09/29 iIOTARIZEO'uO DOCKET ¹ FACIL; Susquehanna Steam Electric Stationp Unit lp Pennsylva 05000387 "38 Susquehanna Steam Electric StationE Jnit 2i Pennsylva 05000388 AUT ~ AUTHOR 4FF ILIATION CURTIS',8 ~ Pennsylvania Power It Light Co. ~P [l RE C I P ~ u 4'4E RECIPIE'JT AFF ILIATIO'J GR IER E B,n. Regi on i Phi adel phi ai Of f i ce of the Director 1 1
SUBJECT:
Final deficiency rept re power generation control complex/
advanced control room cable connector, Inso program nearly complete.A11 Unit 1 cable reoairs will be completed orio,r to fuel loads Unit 2 cables will be installed 5 reoaried.
DISTRIBUTION CODE: B019S COPIES RECEIVED:LTR TITLE: Construction Deficiency Report (10CFR50 ~ 55E) g ENCL g SIZE:M NOTES:Send IEE 3 copies FSAR 4 all amends'5000387 05000388 I
REC IP IETTIT COPIES REC IP IETVT COPIES ID CODE/.'PATE L.rTR ENCL ID CODE/'VANE LTTR ETJCL ACTIOI': A/0 LICEuSNG 04 1 YOUNGBLOODEB 05 1 RUSHBROOKP'DID 06 1, 1 STARKPR ~ 07 1 1 INTERNAL: AD/RC I/IE 17 1 -1 AEOO 18 1 1 ASLBP/J ~ HARD 1 1 D/DIH HUM FAC15 1 1 EDO 4 STAFF 19 1 1 EQUIP QUAL BR11 1 1 IiYD/GEO BR 22 1 1 ICE 09 2 2 LIC QUAL BR 12 1 1 !DIP A 20 1 1
'JRC PDR 02 1 1 OELD 21 1 1 REV 13 1 1 QA BR 14 1 1 EG F I!-E 0 l 1 RUTHERFORDEH ~ IE 1 1 7 ORDS DEV 21 1 1 EXTERiuaL: ACRS 16 16 16 1PDR 03 EIS IC 08 1 1 TOT AL 'IU'LIBEJJ OF COPIES cl EQV IRED: LT TR 40 E VCL 40 I
P"L.
TWO NORTH N1NTM STREEt, ALLENTOWN, PA. 1810) PHONE; (215) 821 5151
~
September 29, 1980
.'!r. Boyce H. Grier Director, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 SUSQUEPANNA STEP~M ELECTRIC STATION FINAL REPORT OF A DEFICIENCY ON PGCC/ACR CABLE CONNECTORS ERs 100450/100508 FILE 840-4/900-10 PLA-545
References:
PLA-437 dated January 8, 1980 PLA-301 dated November 14, 1978
Dear i!r. Grier:
This letter serves to provide the Commission with a final report of a
'deficiency on Power Generation Control Comp1.ex/Advanced Control Room (PGCC/ACR) cable connector deficiencies originally reported in PLA-301.
The information is furnished pursuant to PP&L's obligations under of 10CFR50.55(e). the'rovisions The attachment to this letter describes the deficient condition along with its safety implications and the corrective action being taken to achieve resolution.
He trust the Commission will find the information forwarded by this letter to be satisfactory.
truly yours, 'ery N,. Curtis Vice President-Engineering & Construction-Nuclear Attachment j
FLU'. mk
/ /
I 0XOopn pqg PENNSYLVANlA POWER 8, LIGHT COMPANY
i'fr. Boyce H. Grier September 19, 1980
': ello (15)
D'".=.ctor-~'fiice of Inspection & Enforcement
- uclear Regulatory Commission D C 20555
- . YcDonald, Director Of='.'e of !!anagement information & Program Control L'. S. Nuclear Regulatory Commission 4'asnington, D.C. 20555 Nr. Robert .'f. Gallo U. S. nuclear Regulatory Commission P, Q. Box 52 Sh c!
- .sninny, Pennsylvania 18655
ATTACHbKNT TO PLA 545 Page 1 of 3 PGCC/ACR CABLE PROBLEh/S FINAL REPORT C/ACR Cab'c P:oblems DESCRIPTION In letters from Bechtel Construction dated October 3, 1978, PP5L was informed that during implementation of General Electric's FDDR-KR1-521, Rev. 0 (General Cable Retrofit) rework, it was noted that numerous cases of
-'nsulation damages were found and that one cable was found to have four (4) conductors pulled from their pin connectors. Due to the high percentage of damaged cable, the quality of all terminations was rendered indeterminate.
NCR-3231 was generated to document the problems within the PGCC/ACR complex. t, was agreed to by PP5L, Bechtel and General Electric, that GE
>>ould prepar an FDI which should have details of a complete inspection plan and an approved repair procedure.
In Februarv, 1979, GE issued FDI-NJGO Rev. 0 to perform a 100'o inspection of all GE supplied SITS/FITS cables used in the Susquehanna 1 ACR control room, upper relay room and lower relay room for damaged insulation and suspect pin crimps.
Approved methods of repair for damaged PGCC/ACR cable connectors identified during the inspections performed under FDI-t'fJGO were accomplished in accordance with GE FDDR-KRl-526. This FDDR was originally issued on Sept. 6, 1978 to control the repair of PGCC/ACR panel connectors. The Panel Ccnnector problems were explained in our PLA-506 dated July 8, 1980.
The inspections, repair/rework and tests for the cables under FDI-ÃJGO, FDDR-KR1-526, their revisions and'ddendums are nearly complete. A total of 1762 cables have been inspected. The results of the inspection are as follows:
~Dame e guuant it
- 1. Nicks to conductor insulation 264 Cuts to conductor insulation 346 Damaged or no shrink tubing 265 Pins pulled off during pull test or fell off 58 during depinning
."ot pinned in accordance with wire list or 78 ass ."..bly method V~ F !iled continuity 21
CAUSE
{a} and ", nicks and cuts to conductor insulation; after having inves-
=!~'..";~'.:,"-'arced con"uctor insulation within the T-'.lOD wiring "o a conne." sr,
- .'~;e".."..ired by GE that during reassembly (i.e., pin insertion and ez-trac"icn u ing the standard Amphenol tooling for the termination modules) continual difficulty was experienced. The ferrule edge during extraction and the sharp insertion tool edge during assembly impacted on the densely packed w res at the connector area causing nicks, cuts and abrasions.
(b) It~.. 3, damaged or no shrink tubing, can be broken into two (2) parts: (1) the damaged shrink tubing could have been caused at the factory during asse...bly of the cable or at the construction site during installation; and (2) the lack of shrink tubing was due to an oversight in manufacturing.
(c) Item 4, pins pulled off during pull test or which fell off during depinning; it was determined that a combination of manufacturing personnel error and cr-'mping tool malfunction, due to inadequate QA coverage, was responsible for defective cr mps. This would account for pins failing pull tests or falling off during depinning.
(d) Item 5, not pinned in accordance with wire list or assembly method, is a manufacturing error; i.e., the conductor might be pinned in hole A in a connector but in hole B in the connector on the opposite end of the cable.
(e) Item 6, failed continuity, is a direct resul't of the conductor not pinned in accordance with the wire list or assembly method (Item 5).
ANALYSIS OF SAFETY DPLICATIONS As the various problems are of a random nature and there are a number of Class 1E cables involved, the Safety Analysis is presented on an item by item basis as follows:
(a) In items 1, 2 and 3, nicks and cuts to conductor insulation and damaged or no heat shrink tubing, if bare copper wire is exposed and left uncorrected, permit shorting of wires or introduction of external voltages into i'ould safety related circuits. Any of these conditions could prevent the circuits from performing the designed safety function.
(b) Items 4, 5 and 6, pins pulled off during pull test or fell off during depinning, not pinned in accordance with wire list or assembly method and failed continuity, could affect the designed safety functions. If during a seismic event, the conductor vibrates loosely in the pin so that there is sporadic or no continuity between the pin and conductor, or if the conductor is not pinned correctly such that there is no continuity between the proper connector pins at each end of the table, the operation of the circuit could be adversely affected.
Project Engineering has determined that the above items are reportable under 10CF?5C.55(e).,
-3>>
CORRECTIVE ACTIONS The 100% inspection program for PGCC cable connectors and repair/rework for the problems listed in NCR-3231 is nearly complete.
...."= '.o prevent recur'rences of like p oh's ~ ".:t.~;e i'GCC couche connectors', and which are also applicable to the Susquehanna PGCC/ACR Unit 2 cables, are indicated by GE to be:
t (1) Appropriate training of personnel involved.
(2) 'Revision of fabrication techniques.
(3) Increased/revised inspection activities.
(4) GE has developed a supplemental reinspection instruction (GE Inspection Instruction CA-006) to identify damaged or nonconforming connectors prior to shipment. Satisfactory completion of this cable reinspection on Susquehanna Unit 2 cables was reverified by PPRL audit on Sept. 9-11, 1980 at the GE manufacturing facility in San Jose, CA.
In addition, faulty crimping tools were repaired or replaced and periodic testing of crimping tools was increased.
Construction site personnel have been given further instructions in the handling and installation of cables. The site electricians have been instructed to use a steady pull (not a yank) when making pull tests and the spring testers are calibrated every 30 days or sooner if deemed necessary.
CONCLUSIONS The repair/rework and testing of the Unit 1 PGCC/ACR cables is nearly complete. All Unit 1 PGCC/ACR cables will be completed prior to fuel load.
The Unit 2 PGCC/ACR cables will be installed and repaired or reworked as necessary. Discrepancies will be documented on an NCR.
For Unit 2 PGCC/ACR cables, field inspections of the equipment and additional GE fabrication personnel training, inspection and revised fabrication techniques should preclude recurrence of similar problems.