Letter Sequence Request |
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MONTHYEARML20065P7791982-10-21021 October 1982 Proposed Change to Tech Spec 4.6.1.2d,requiring That Type C Penetration Tests Be Performed at 24-month Interval, Deviating from 10CFR50,App J Requirement to Perform Test During Each Refueling Shutdown Project stage: Request ML20065P7631982-10-21021 October 1982 Application for Amend to License NPF-9,changing Tech Spec Re Containment Penetration Type C Leak Rate Tests.Amend Requires Exemption from 10CFR50,App J Project stage: Request 1982-10-21
[Table View] |
Proposed Change to Tech Spec 4.6.1.2d,requiring That Type C Penetration Tests Be Performed at 24-month Interval, Deviating from 10CFR50,App J Requirement to Perform Test During Each Refueling ShutdownML20065P779 |
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McGuire ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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10/21/1982 |
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DUKE POWER CO. |
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ML20065P766 |
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References |
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TAC-48982, NUDOCS 8210260336 |
Download: ML20065P779 (4) |
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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20217J6401999-10-0606 October 1999 Revised Pages to McGuire Nuclear Station Selected Licensee Commitments Manual ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20212A2701999-05-28028 May 1999 Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206Q9311999-05-0404 May 1999 Rev 29 to List of Effective Pages for Chapter 16 & Page 16.11-66 to McGuire Selected Licensee Commitment Manual. with ML20206S9401999-04-30030 April 1999 Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. with List of Effective Pages ML20206K3621999-04-30030 April 1999 Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205L2431999-04-0505 April 1999 SFP Soluble Boron Credit Dilution Analysis (Summary of Applicable Portions) ML20205L2531999-04-0505 April 1999 Boraflex Degradation Analysis ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20198A4691998-12-0909 December 1998 Rev 14 to DPC McGuire Nuclear Station Process Control Program ML20196G6891998-11-23023 November 1998 Rev 26 to Selected Licensee Commitments (SLC) Manual ML20196C9211998-11-14014 November 1998 Rev 26 to Selected Licensee Commitments Manual. with Update Instructions ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y2461998-09-15015 September 1998 Proposed Improved Tss,Resolving Items Identified by Util During Review ML20151U3521998-09-0808 September 1998 Proposed Tech Specs & Bases Converting to Improved Tech Specs ML20151Z7751998-09-0808 September 1998 Rev 25 to McGuire Selected Licensee Commitment Manual, Consisting of Revised Pages 16.7-9 & 16.7-10 ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5721998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.3 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A0411998-08-0505 August 1998 Suppl 8 to Improved TS Noting Differences Between Two Units. Proposed Changes Require That Specs & Surveillances Apply to Each Unit Individually,Unless Otherwise Noted,Consistent W/Version of Current TS Prior to Amends 166 & 148 ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236G5301998-06-29029 June 1998 Rev to Bases of TS 3/4.6/3,correcting Editorial Errors ML20249C2081998-06-0909 June 1998 Rev 24 to Selected License Commitments (SLC) Manual & SLC 16.10.1,dtd June 1998 ML20247E3891998-05-0808 May 1998 Proposed Tech Specs,Revising Power Range Neutron Flux High Trip Setpoints in Event of Inoperable MSSVs & Deleting References to 3-loop Operation in Current TS Section 3.7.1.1(b) & Table 3.7-2 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20217E6531998-04-20020 April 1998 Proposed Improved Tech Specs Re Section 1.0,2.0,3.0 & 4.0 ML20217B7871998-03-20020 March 1998 Marked-up Proposed Improved TS 3.6 & 5.5.2 ML20217N9311998-03-0303 March 1998 Proposed Tech Specs 5.5 Re Meteorological Tower Location ML20216B9851998-03-0202 March 1998 Proposed Tech Specs Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Encl ML20203J9391998-02-19019 February 1998 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203E1911997-12-0101 December 1997 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20217H5541997-10-13013 October 1997 Proposed Tech Specs Supporting Replacement of Three Safety Related Narrow Range Refueling Water Storage Tank Level Instruments W/Three Safety Related Wide Range Level Instruments ML20212A2511997-10-0606 October 1997 Proposed Tech Specs Deleting All References to Steam Line Low Pressure Safety Injection Function ML20216A8691997-09-0101 September 1997 Rev 0 to QAM-2.0, Order Entry ML20210K9281997-08-31031 August 1997 Cycle 12 Startup Rept ML20216B8171997-08-25025 August 1997 Rev 0 to PE-9778-1, Test Rept-Grinnell Hydraulic Snubber Freedom of Motion Test Under Duke Powers McGuire Nuclear Station MSLB Accident Temp Condition 1999-09-13
[Table view] |
Text
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DUKE POWER COMPANY MCGUIRE NUCLEAR STATION
) TECitNICAL SPECIFICATION 4.6.1.2d/10CFRSO APPENDIX J EXEMPTION REQUEST
]
McGuire Technical Specification 4.6.1.2d requires that Type C penetration tests "be conducted at intervals no greater than 24 months". This is based on 10 CFR 50, Appendix J, III.c.3, which requires that Type C penetration tesus"be per-formed.during each reactor shutdown for refueling but in no case at ir.tervals greater than 2 years".
McGuire Unit I had previously been scheduled for shutdown in October, 1982 to install the design modification on the Model D Westinghouse steam generators.
Recent delays in delivery of the special tooling required for this modification -
has resulted in a delay of the scheduled shutdown until November, 1982. There-fore, Duke Power Conpany is requesting an exemption from Technical Specifications (and thus 10 CFR 50 Appendix J) to allow penetration number M320 to be leak tested no later than November 30, 1962. This would allow an insignificant exten-sion to the 24 months currently required to a maximum of 25 months. The proposed Technical Specification change is shown in Attachment 1.
Justification Several penetrations require that the unit be in cold shutdown to perform the Type C leakage tests. These penetrations were last tested in 1980 and, there- .
fore, are required to be tested in 1982. Previous shutdowns for steam generator eddy carrent inspections provided an opportunity to test penetrations which were tested mid-year 1980. At the time of the last shutdown in July, 1982, a review was performed of all surveillance rcquiring a unit shutdown to insure the unit
( could operate until the next shutdown, which at that time was scheduled for September, 1982. Penetration M320 was not leak tested during this July outage since it was believed the next shutdown in 1982 would occur no later than the expiration of the interval for this penetration. Other penetrations with earlier test dates were tested during this outage.
As shown on Figure 1 (excerpt f rom FSAR Figure 9.2.4-3 (2 of 2)), penetration M320 is on the component cooling (KC) line from components in the reactor building including the reactor coolant pump motor coolers. Testing of this penetration requires isolating and draining this portion of the line, and thus requires isolation of KC flow to the affected components. Therefore, Unit I would have to be shutdown and cooled down in order to switch to residual heat removal which would allow isolation of KC to reactor coolant pump motor coolers. Current estimate for shutdown, cooldown, penetration testing, and heatup is approximately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. More important is the thermal cycle which would be required only for the purpose of obtaining test results a few days earlier than otherwise available. In addition, the probability of the penetrations failure during the brief delay is extremely remote. Also, the NRC, allows a grace period (generally 125%) for many other types of testing and surveillance, including some valve leak testing pursuant to ASME Boiler and Pressure Vessel Code Section XI, Subsection IWV. The current outage planned to begin in mid-November allows more than sufficient time to complete this penetration test and all other required surveillance for 1982.
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B210260336 821021 .
PDR ADOCK 05000369 i P PDR
i (d Duke Power Company feels the insignificant increase in the surveillance frequency compared to the unnecessary thermal cycle of cooldown and heatup represents responsible and prudent concern for the safety of plant opera-tions.
Safety Evaluation 4
Component cooling system penetration M320 (component cooling water from reactor vessel support coolers and RCP coolers) was tested in May, 1979 and October,
- 1980. The results from these tests were 40 seem and 45 seem respectively. The total allowable leakage for penetrations is specified as 0.07 La or 6343 seem at 14.8 psig. The average maximum allowable leakage for each of the 69 penetra-tions would be 92 sccm. Therefore, pene ration M320 has exhibited leakage rates
, less than half the maximum allowable for individual penetrations. The latest results for leakage rates of all penetrations shows a current total of 2187 seem which is well below the allowable limit of 6343 scem.
The past history shows the leak rate of the penetration has been well within the allowable limit and ther is no justification to assume the penetration will degrade beyond the allowable limit by November 30, 1982. Therefore, Duke believes
, this limited extension in the surveillance period does not involve an unreviewed safety question aad has no effect on the health and safety of the public.
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Revision 37 I
TABLE 3.6-1 SECONDARY CONIAINMENI BYPASS LEAKAGE PATils A PENEIRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE H317 Instrument Air Auxiliary Building Type C H243 Containment Air Release Auxiliary Building Type C H384 Containment Air Addition Auxiliary building Type C H361 Reactor Coolant Pump Hotor Oil Supply Auxiliary Building Type C H353 Fire Protection lleader N Auxiliary Building Type C g H376 Component Cooling Water to Auxiliary Building Type C m Reactor Coolant Drain Tank o 2 lleat Exchanger
[ H355 Component Cooling Water from
' Auxiliary Building Type C Reactor Coolant Drain Tank fleat Exchanger
, H327 Component Cooling Water to Auxiliary Building Type C l Reactor Vessel Support Coolers and RCP Cealers I
j H320 Component Cooling Water from Auxiliary Building Type C**
Reactor Vessel Support Coolers and RCP Coolers Flued llead to Guard Pipe Atmosphere, or ,*
Welds on all llot -
Auxiliary Building, -
Penetrations or Turbine Building
- t Equipment llatch Atmosphere i
Type C l *Fursuant to S'jieHiication 4.6.1.2.e.
- This penetration is exempted from the Type C leak rate test requirementsof specification 4.6.1.2d for the y period November I through November 30, 1982. >
4
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