Similar Documents at Perry |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20211H6791997-09-18018 September 1997 Safety Evaluation Authorizing Licensees Request for Alternative from Augmented Insp of Reactor Pressure Vessel Circumferential Weld in Plant,Unit 1 ML20211A5881997-09-11011 September 1997 Safety Evaluation Supporting Evaluation of First 10-yr Interval ISI Program Plan Requests for Relief PT-004,PT-005 & PT-006 for Plant,Unit 1 ML20217K9061997-08-12012 August 1997 Safety Evaluation Accepting Plant First 10-yr Interval ISI Program Plan Relief Request PT-007 ML20141L9131997-05-27027 May 1997 Safety Evaluation Accepting Relief Requests for First 10-yr Interval Inservice Insp Program Plan for Plant,Unit 1 ML20147H4211997-04-0101 April 1997 Safety Evaluation Accepting Changes to USAR Sections,Which Continue to Satisfy Criteria of App B of 10CFR50 ML20134D1061997-01-27027 January 1997 Safety Evaluation on Revised EALs for Plant.Proposed EALs Changes Are Consistent W/Guidance in NUMARC/NESP-007,with One Exception,& Meets Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20058M6761993-09-29029 September 1993 Safety Evaluation Accepting Rev 10 to Plant Emergency Plan for NRC Review Under 10CFR50.54(q) ML20246F6481989-08-23023 August 1989 Safety Evaluation Accepting Proposed Turbine Sys Maint Program ML20246Q0291989-07-14014 July 1989 Safety Evaluation Re Updated Safety Analysis Rept Appendix 1B,license Commitment Revs ML20244D6351989-06-0707 June 1989 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance1989-06-0505 June 1989 Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance ML20246Q0771989-05-0909 May 1989 Safety Evaluation Supporting Proposed Mod to Delete K74B & K74D Relays from Electrical Control Circuitry of MSIV to Resolve Spurious Opening of MSIV on Loss of Reactor Protection Sys Bus a or B ML20248G2921989-03-30030 March 1989 Safety Evaluation Accepting Util 840406 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing ML20236E0141989-03-15015 March 1989 Safety Evaluation Supporting Util Implementation of 10CFR50.62 ATWS Rule ML20196D4311988-12-0606 December 1988 Safety Evaluation Documenting NRC Review of Licensee Response to Generic Ltr 83-28.Evaluation Concludes That Licensee Adequately Meets Provisions of Part 1 of Item 2.2 to Generic Ltr 83-28 ML20213A5661987-04-20020 April 1987 Safety Evaluation Supporting Amend 4 to License NPF-58 ML20205Q9771987-04-0101 April 1987 Safety Evaluation Supporting Amend 3 to License NPF-58 ML20203N6951986-10-10010 October 1986 Safety Evaluation Supporting Request for Relief from ASME Code Exam Requirements in Preservice Insp Program ML20203N6981986-10-10010 October 1986 Sser Supporting Util Request for Relief from Preservice Insp Program Requirements ML20202G4321986-07-0808 July 1986 SER Approving Tdi Diesel Generator Owners Group Program to Validate & Upgrade Design & Mfg Quality of Tdi Diesel Generators for Nuclear Emergency Standby Svc ML20198C3951985-11-0505 November 1985 Safety Evaluation Re Reliability of Tdi Standby Emergency Diesel Generators for Application at Domestic Nuclear Plants.Diesel Generators Will Provide Reliable Standby Source of Onsite Power,W/Listed License Conditions ML20138N7461985-10-28028 October 1985 SER Supporting Reliability of Tdi Standby Emergency Diesel Generators.Viewgraphs & Final Draft Tech Specs Encl 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
[Table view] |
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^ t UNITED STATES
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t NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERIC LETTER 92-08 AMPACITY DERATING ISSUES THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT. UNIT NO.1 DOCKET NO. 50-440 BACKGROUND By letters date April 16,1993, February 11,1994, December 15,1994, March 22,1995, June 28,1995, October 2,1996, and January 12,1998, The Cleveland Electric illuminating Company responded to Generic Letter 92-08, "Thermo-Lag 330-1 Fire Barriers," dated December 17,1992, in regard to Thermo-Lag 330-1 fire barriers installed at the Perry Nuclear Power Plant, Unit No.1 (PNPP). In addition, letters dated November 20,1995, June 28,1996, and October 28,1996, addressed Thermo-Lag ampacity derating issues.
I The consideration of ampacity derating factors for Thermo-Lag fire barriers at PNPP is based on a similarity analysis.1 he licensee used the results from the Texas Utilities Electric Company (TUEC) ampacity derating tests in its evaluation of PNPP Thermo-Lag fire barriers. The specific ;
Thermo-Lag ampacity derating value selected and applied to each configuration was determined !
by: (1) Reviewing the ampacity derating testing conducted by TUEC; (2) confirming by similarity analysis that the TUEC tested configurations bound instalbd Thermo-Lag configurations at PNPP; and (3) applying the comments discussed in the NRC " Safety Evaluation of Ampacity issues Related to Thermo-Lag Fire Barriers at Comanche Peak Steam Electric Station, Unit 2,"
dated June 14,1995. ;
- The staffs evaluation of the ampacity derating methodology for PNPP follows.
EVALUATION j 1
After reviewing the licensee's submittals, the staff agrees with the licensee analyses and i conclusions. The ampacity derating analysis questions, the licensee's response, and the staffs evaluation of the responses follow.
9812300070 981222 PDR P
ADOCK 05000440 1 I
PDR ENCLOSURE 1
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) Amoacity Deratino Analysis Review
. Question 1 The licensee should confirm that all fire barrier construction for the subject configuration (s) are representative of the barrier construction used in the Comanche Peak Steam Electric Station (CPSES), Unit 2 ampacity derating tests.
Licensee Response in its submittal dated October 28,1996, the licensee stated that based on the comparison of the Thermo-Lag installations tested by TUEC to obtain the derating factors described in the referenced 1995 NRC Safety Evaluation and those installed at PNPP, the PNPP Thermo-Lag installations are bounded by the TUEC installations. The PNPP configurations are conservative, from an ampacity perspective, because the tested configurations have a slightly greater thickness of Thermo-Lag material than the PNPP configurations. The upgraded assemblies tested by TUEC presented a worst case when compared to the baseline installation applicable to the PNPP assemblies from an ampacity perspective.
Staff Resoonse The information provided by the licensee fully res Slves the staff's concems.
Question 2 The licensee should verify whether the installed Thermo-Lag fire barriers are single (one 1" thick) or double (two %" thick) layer systems. The Thermo-Lag fire barrier system tested at CPSES 2 was a single layer system.
I Licensee Resoonse i
in its submittal of October 28,1996, the licensee stated that at PNFP, the 1" thick preformed conduit sections of Thermo-Lag are single layer systems. These systems are used for 3-hour rated barriers. Only one conduit is protected by a 3-hour fire rated
- barrier at PNPP. However, this conduit contains only control power and position indication circuits for the inboard MSIV main pilot air control valves. The licensee confirmed that control cables are adequately sized at PNPP.
4 39ff Resoonse The information provided by the licensee fully resolves the staff's concerns.
i
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. Question 3 The typical ampacity derating calculation for a conduit (1R33F01038) used an adjustment factor of 0.8 for 6 energized conductors per National Electric Ccie (NEC).
- . _ . - .- . - - . . - - .~.-.- -.- - - . .. . -.-.- _ _- .
i1 ,
t This conduit included 7 cables (at least 30 conductors). The NEC recommends adjustment factor of 0.6 which includes the effects of a load diversity of 50 percent. The licensee needs to provide justification for using 0.8 instead of 0.6. The staff believes that the adjustment factors shall be based on number of conductors in the conduit.
j <
s Licensee Resoonse In its submittal of October 28,1996, the licensee stated that the following information is provided for Conduit 1R33F0103B, which contains seven cables.
l
! Type of Number of B/M Cable Class Circuit
! Cable in this Cables Number Number j Conduit 7
l A 1 EKA-72 3/C#6 1M39F68 l B 1 EKA-75 3/C#12 1E12F8B C 2 EKB-12 2/C#14
- D 2 EKB-16 9/C#14 -
- E 1 EKB-11 STP#16 l
4 A random sampling of cables supplying loads with operating duration less than 120 seconds (Types C and D) was selected for calculation of their ampacity margins. Their positive margins indicated that the cables supplying loads of short operating duration are adequately sized at PNPP, and therefore, were excluded from the calculation. In addition, instrumentation cables (Type E) were excluded from the calculation because they are not sized on the basis of ampacity. They carry low current in the milli-ampere
- range and the Thermo-Lag fire barriers have no impact on the ampacity of these cables.
i Therefore, the only cables included in the derating calculation for this conduit were j- Types A and B. The adjustment factor provided in NEC Table 310-19 Note 8 was applied. Load diversity was not credited in the PNPP Calculation MISC-009.
i From the table above, there is one Type A cable in this conduit, which is a three-l conductor #6 AWG cable. In addition, there is one Type B cable in this conduit which is
{
a three-conductor #12 AWG cable. As stated above, the only cables included in the
! derating calculation for this conduit were Types A and B. Per NEC, the adjustment factor is 0.8 for 6 energized / current carrying conductors in conduit.
Staff Response 1
l The information provided by the licensee fully resolves the staff's concems.
!
- Question 4 For cables installed in exposed or enclosed groups of conduits in air, the grouping l
j factors given in Table IX of ICEA Standard P-46-426 shall be used when the spacing l
t
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} between conduit surfaces is not greater than the conduit diameter or less than 1/4 of the conduit diameter. The sample calculation did not use conduit grouping factor. Provide a ;
discussion about conduit grouping factor at PNPP. :
Licensee Resoonse in its submittal of October 28,1996, the licensee stated that the use of conduit grouping factor described in ICEA Standard P-46-426 applies to cables installed in exposed or i enclosed groups of conduits in air. However, conduits are wrapped individually at PNPP.
Therefore, the use of the conduit grouping factor is not applicable to PNPP.
Staff Resoonse ,
The information provided by the licensee fully resolves the staffs concems.
- . Question 5 j l l Provide conduit size and conduit fill for the sample calculation for conduit Number
! 1R33F0103B. Provide justification of cable ampacity if the conduit fill exceeds the value given in NEC tables.
l Licensee Response !
I !
j in its submittal of October 28,1996, the licensee stated that Conduit Number
- 1R33F01038 is a 2.5" conduit. As stated in Section 3.03 of PNPP Calculation No.
! MISC 5009 conduits, trays, and cables are instal!ed per PNPP Installation Standard i Specification SP-2250, Electrical Work and Equipment. This installation specification l.. administratively controls the maximum conduit fill for conduits at PNPP to be 40%, in 4 accordance with NEC requirements provided in Table 1 of NEC Chapter 9.
p Staff Resoonse j i The information provided by the licensee fully resolves the staffs concems.
I .
! . Question 6 i
The licensee needs to provide specific and complete examples of the ampacity derating
. calcubtions illustrating all aspects of those calculations in detail (baseline ampacity with .
- source, cable characteristics, cable diameter, tray size and type, percent fill, fire barrier rating, etc.) for typical 1-hour tray (480 volt circuit) and typical air drops. ;
l
?:
l Ligpnsee Response .
In its submittal of October 28,1996, the licensee provided a typical ampacity derating
. calculation for a tray in Attachment 2 of the subject submittal.
U i
i y
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I The two cable bundle free air drop configurations tested by TUEC consisted of 12' long cable bundles. At PNPP, there are no air drop configurations similar to this configuration. However, there are raceway configurations where intersecting trays ;
and/or conduits are not continuous (physically joined with fittings). Field walkdowns of ;
Thermo-Lag installations were performed to determine the space between tray / tray and ;
tray / conduit intersections. The space between tray / tray intersections is less than 16", i and the space between tray / conduit intersections is less than 10". The cable (s) routed through these sections of the raceways are wrapped with Flex Blanket Thermo-Lag. The interfaces between raceways protected with Thermo Lag materials are not factors in determining the overall ampacity derating. This type of configuration variation occurs for ;
a short part of the overall run of the Thermo-Lag protected raceways. As stated in the l referenced 1995 NRC Safety Evaluation, the variations in construction for short i t
distances are not expected to impact the overall ampacity derating given the ,
conservatism applied in the derating factors used. Therefore, no ampacity derating calculations were performed for these variations in construction. ;
Additionally, the ampacity of cables with the above configurations were derated based on j their applicable raceways (i.e., tray or conduit) in addition to derating due to the presence l of Thermo-Lag material. The nominal ampacity of a cable routed in a tray was derated ,
based on the depth of cables in the tray and then derated again by 3.5% for the l i
presence of Thermo-Lag material. The nominal ampacity of a cable routed in conduit was adjusted per NEC Table 310-19 Note 8 and further derated by 21% for the presence j of Thermo-Lag material.
~ 'ff Response j The information provided by the licensee fully resolves the staff's concems.
! . Q
_ uestion 7 i I The sample calculation used a load factor of 1.0 for resistive loads and 1.1 for other l loads. This is acceptable provided the loads are not operating at an overload condition i l
or at a service factor. Provide a discussion about the overload or the service factor of
' the load.
l
- Licensee Response l i l
) In its submittal of October 28,1996, the licensee stated that a PNPP long time j overcurrent protection for motors is based on the fullload current rating of the motor. An j
! additional step in assuring the adequacy of motor protection was accomplished during ;
i initial testing. Field measured motor currents in excess of the full load current ratings )
- (overload) noted during testing were reported to engineering personnel in accordance l with procedure gel-0049. The measured values were then evaluated to determine l
acceptability of the motor and motor protection.
f l
I At normal plant operating voltages, heater and motor load ampacities are typically below their nameplate values or have been evaluated by the above mentioned procedure. No overloads have been identified, therefore, the load factors identified are appropriate.
Staff Response The information provided by the licensee fully resolves the staffs concerns.
- Question 8 Certain non-continuous loads (heaters, heat trace circuits) may operate for an extended period when called on to operate (during extreme cold weather, the heaters might i operate at near continuous levels for extended periods). Provide a discussion of these circuits.
Licensee Resoonse in its submittal of October 28,1996, the licensee stated that ampacity derating calculations for heater circuits described in Calculation MISC-009 are based on continuously energized leads. Ampacity margins for the feeder circuits were calculated as continuous loads based on the heater nameplate rating with the exception of two heaters. For these two heaters, the subject calculation utilized the actual field test results. Therefore, the loads cited in this question were considered to be continuously energized, regardless of environmental changes, and have been conservatively derated by the licensee. ,
1 Staff Response The information provided by the licensee fully resolves the staffs concerns.
Acolication of Amoacity Deratino Methodolooy Using the Thermo-Lag ampacity derating factor (ADF) based upon industry tests, the licensee incorporated the applicable test data in PNPP cable ampacity design. The resulting ampacity derating value was then compared to the plant service loads to ensure that the actual operating conditions do not result in exceeding cable ratings. The licensee response to the staffs l questions indicates that all of the PNPP Thermo-lag protected cable installations are applicable l to its corresponding TUEC tested configuration.
CONCLUSIONS On the basis of its review, the staff concludes that no ampacity derating cencems as identified by GL 92-08 rema'in outstanding at the Perry Nuclear Power Plant.
Principal Contributor: Ronaldo Jenkins Date: December 22, 1998
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