Letter Sequence Other |
---|
|
|
MONTHYEARML20132F6811985-09-24024 September 1985 Forwards Request for Exemption from 10CFR50,App J Requirement to Leak Test Mechanical Penetrations,For Ice Condenser Refrigeration Sys,Using Air or N as Test Medium Across Valve Sealing Surface.Fee Paid Project stage: Request ML20137K8881986-01-21021 January 1986 Proposed Tech Specs Permitting Utilization of Exemptions to 10CFR50,App J Re Type Band C Tests Project stage: Other ML20137K8791986-01-21021 January 1986 Application for Amend to Licenses NPF-9 & NPF-17,authorizing Use of Exemptions Re Type Band C Tests.Proposed Changes to Tech Specs,Justification,Safety Analyses & 850924 Request for Exemption Encl.Fee Paid Project stage: Request ML20140D2431986-03-17017 March 1986 Proposed Tech Specs,Incorporating Alternate Means to Perform Specific Containment Penetration Leakage Test Project stage: Other ML20140D2341986-03-17017 March 1986 Supplemental Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs to Incorporate Alternate Means to Perform Specific Containment Penetration Leakage Test Project stage: Supplement ML20203P0171986-04-14014 April 1986 Clarifies Position Re IE Info Notice 85-071, Containment Integrated Leak Rate Tests, in Response to . Notice Will Be Used as Insp Guidance Representing Headquarters Interpretations of Leak Rate Test Requirements Project stage: Approval 1986-01-21
[Table View] |
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels 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 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 ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements 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 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 ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P 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 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 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 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 ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements 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 ML20133M5541997-01-13013 January 1997 Proposed Tech Specs Implementing performance-based Containment Leak Rate Testing Requirements of 10CFR50, App J,Option B ML20133D3991997-01-0606 January 1997 Proposed Tech Specs 3/4.6 Re Containment Systems ML20132F0001996-12-17017 December 1996 Proposed Tech Specs,Supplementing Amend Request to Change Surveillance 4.8.2.1.2.e Which Will Achieve Alignment W/ Improved STS SR 3.8.4.8 ML20135B0381996-11-26026 November 1996 Proposed Tech Specs 3.8.2 Re DC Sources ML20134M1541996-11-0101 November 1996 Proposed Tech Specs 3.8.2 Allowing Use of Low Specific Gravity Cells in Vital 125 Volt Dc Sys When Desired ML20129F7591996-10-22022 October 1996 Proposed Tech Specs 3.6.1.5 Re Containment Systems & Air Temp ML20117K1011996-08-29029 August 1996 Proposed Tech Specs,Replacing 960516 Response to Concerns Re Proposed Changes for Diesel Starting Air Sys Surveillance Testing ML20113C7201996-06-21021 June 1996 Proposed Tech Specs 3.9.6,revising Term Lifting Loads to Lifting Force Used in Manipulator Crane TS 3.9.6b.2 & Redefining Auxiliary Hoist Min Capacities ML20112A7571996-05-16016 May 1996 Proposed Tech Specs 3/4.8 Re Surveillance Requirements ML20101H6101996-03-15015 March 1996 Proposed Tech Specs Re Replacement of SGs ML20101C8281996-03-0808 March 1996 Proposed Tech Specs Reflecting Separate Vols for Unit 1 & Unit 2 ML20100R4601996-03-0404 March 1996 Proposed Tech Specs,Deleting Flow Monitoring Sys from TS 3.4.6.1 & Associated SRs ML20097G3911996-02-13013 February 1996 Proposed Tech Specs Re Listing of Core Operating Limit Methodologies for Editorial Correction ML20095E9571995-12-14014 December 1995 Proposed Tech Specs Action Statements & SRs for Dgs, Incorporating Guidance & Recommendations in NUREG-1366,GL 93-05,GL 94-01 & NUREG-1431 ML20095E8081995-12-12012 December 1995 Proposed Tech Specs,Making McGuire Afd Limit Equations Identical to Previously Approved by NRC for Catawba Nuclear Station ML20095B6221995-12-0505 December 1995 Proposed TS SR 4.8.2.1.2.e Re 60-month Battery Testing ML20093L2861995-10-17017 October 1995 Proposed Tech Specs Listings of Core Operating Limit Methodologies ML20098A4631995-09-18018 September 1995 Proposed Tech Specs,Providing Revised Record Pages for LTOP Protection in TS Amend ML20092K4481995-09-18018 September 1995 Proposed Tech Spec Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints ML20092B1571995-09-0101 September 1995 Proposed Tech Specs,Revising TS 3/4.6.5 to Reduce Required Ice Weight in Containment Ice Condenser of Each Unit from 2,099,790 Lbs to 1,516,800 Lbs 1999-09-13
[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
ATTAClutENT 1 PROPOSED TECHNICAL SPECIFICATION CHANCES l
l l 8601240264 G60121 1 PDR ADCCK 05000369 l P PDR
l CONTAINMENT SYSTEMS l
SURVEILLANCE REQUIREMENTS (Continued)
- a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40
- 10 month intervals during shutdown at 14.8 psig, or at P , 7.4 psig, during each 10 year eitherPle,riod.
service The third tekt of each set shall be conducted during the shutdown for the 10 year plant inservice inspection;
- b. If any periodic Type A test fails to meet either 0.75 L or 0.75 L the test schedule for subsequent Type A tests shall be $eviewed anb, approved by the Commission. If two consecutive Type A tests fail to meet either 0.75 L or 0. 75 L a Type A test shall be performed at least every 18 monfhs until tb, consecutive Type A tests meet either 0.75 L resume 8;or0.75Lg at which time the above test schedule may be
- c. The accuracy of each Type A test shall be verifled by a supplemental test which:
- 1) Confirms the accuracy of the Type A test by verifying that the, difference between supplemental and Type A test data is within 0.25 L,, or 0.25 L t
- 2) Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test; and
- 3) Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25% of the total measured leakage at P ,
14.8 psig, or Pg , 7.4 psig. a d.
Type 8 and C tests shall be conducted with gas at P , 14.8 psig, at intervals no greater than 24 months except for testl involving:
- 1) Air locks,
- 2) Oual-ply bellows assemblies on containment penetrations between the containment building and the annulus, and
- 3) Purge supply and exhaust isolation valves with resilient material seals
- e. Purge supply"an*d hh[s N oiaN onN al M w r silient material seals shall be tested and demonstrated OPERA 8LE by the requirements of Specification 4.6.1.9.3 or 4.6.1.9.4, as applicable; i f.
The combined bypass leakage rate shall be determined to be less than by applicable Type 8 and C tests at least once per 24 months e-0.07 L,for penetrations which are not individually testable; pene 4 l except tions not individually testable shall be determined to have no detect-
) <
able leakage when tested with soap bubbles while the containment is pressurized to P,, 14.8 psig, or Pt. 7.4 psig, during each Type A test; McGUIRE - UNITS 1 and 2 Amendment No. V'(Unit 2) 3/4 6-3 Amendment No. 29 (Unit 1)
:: x l
l l
ATTACRMENT 2 JUSTIFICATION AND SAFETY ANALYSES i
JUSTIFICATION AND SAFETY ANALYSIS i
The proposed change to the McGuire Technical Specifications is an administrative change to allow the NRC to approve exemptions from 10CFR50 Appendix J (relative to Type B and C leakage tests). In some cases, it may be appropriate to pres-surize with a different medium instead of gas. These cases would be submitted and justified to the NRC Staff on an individual basis. This change would allow such an exemption to be granted and utilized, i
Specifically. Attachment 4 contains an exemption request submitted September 24 1985 to allow initial leak testing of two containment penetrations using glycol as discussed in the request; in this case, the acceptance criteria is zero lenk-age. If this is not met, the penetration would be drained and tested according to Appendix J. Such exemptions would be justified individually to assure that containment integrity is not compromised.
4 ATTACHMENT 3 ANALYSES OF SIGNIFICANT HAZARDS CONSIDERATION k
ANALYSES OF SIGNIFICANT HAZARDS CONSIDERATIONS Pursuant to the requirements of 10CFR50.91, this analysis provides a determina-tion that the proposed amendment of the Technical Specification does not involve any significant hazards consideration, as defined by 10CFR50.92.
The proposed amendment would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The change is administrative to allow exemptions to Containment penetration testing requirements and would assure, through the NRC approval process, that Containment Integrity is not compromised thus r.ot affecting the pro-bability or consequences of an accident previously evaluated, i.e., con-tainment failure.
- 2) Create the possibility of a new or dif ferent kind of accident f rom any accident previously evaluated.
No hardware changes would be made as a result of this change so no accident mechanisms are affected or created.
- 3) Involve a significant reduction in a margin of safety.
Containment integrity is maintained with no reduction in margin.
Based upon the preceding analysis, Duke Power Company concludes that the proposed amendments do not involve a significant hazards consideration.
1 ATTACHMENT 4 EXEMPTION REQUEST OF SEPTEMBER 24 1985 4
I l
4 1
I I
l t
DmCE POWER COMPANY p.o. mox 30:se H.U., 5. M'CKER enAntorrz w.c. ass 4a nem enemme=
= = = - TW u r.co g September 24, 1985 t
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensaa. Chief Licensing Branch No. 4
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 i Request for Exemption from 10 CFR 50 Appendix J Requirement i -
Dear Mr. Denton:
{
Attached is a Request for Exemption from the 10 CFR 50 Appendix ent J Requi
! to leak rate test mechanical penet:ations using air or nitrogen asethtest medium across the valve sealing surface.
1 to two penetrations for the Ice Condenser Refrigeration System e it is wherThis Re j
of the procedure is included in the request.otherwise An outline necessary i
be used as the pressurization medium.The proposal would allow an altern is not met, I
I Appendix J. th~e penetration will be fully drained and tested in accord 4
j Review test cycle. and approval is requested by February 1. 1966 to support the current
' Pursuant to 10 CFR 170.21. a check for $150.00 is enclosed.
Please feel free to contact us At you require any additional information .
Very truly yours.
y Hal B. Tucker 4
JBD/hrp Attachment ec:
Dr. J. Nelson Grace. Regional Administrator
! U. S. Nuclear Regulatory Commission Mr. W. T. Orders Region II NRC Resident Inspector 101 Marietta Street. NW. Suits 2900 McGuire Nuclear Station Atlanta, Georgia 30323 i
3 (f ). } i 7 E'L 4 T J ! y f
l l
t Raouest for Eveantion from 10CFRLu Annandir J Raouirement i
10CFR50 Appendix J III C 2(a) requires mechanical penetrations to be leak rate tested using air or nitrogen as the test mediua across the valve sealing surface. An exemption is requested froa j
this requirement for penetration numbers M-372 and M-373.
i local The 4
from the leakage test will be performed without draining the glycol seats of the diaphram valves in these penetrations.
Attachment A depicts the arrangement of these penetrations.
McGuire utilizes an ice condenser to surpress the peak accident i
pressure is in the reactor containment building. The ice condenser
! glycolrefrigerated by recirculating a 505 - 505 mixture of ethylene
- and water through a series of air handling unita located inside the containment building and chillers the auxiliary building. units located in Typically, draining, testing and refilling the system requires 24 to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of downtime for the ice condenser refrigeration system.
potentially diminishes the amount of This extended downtime ice in the baskets.
3 j
Draining the glycol consumes a significant number of manhours and creates toxic waste which has to be disposed.
! As an alternative i
to draining the 200 gallons of glycol i necessary following to perform this test in accordance with Appendix J, the i Penetration procedure for testing these penetrations is proposed, M-373 would be drained through NF-1173 and i NF-960.
j NF-229 both (a duo NF-228A sides. check valve) wouldwould be local leak tested with air on pressurization then be tested with air as the medium and glycol on its seats. The systen high
- point vent, NF-1150, would serve as the vent valve for NF-228A.
Similarly, i
glycol. NF-233B M-372 would be tested without completely draining the would utilizing NF-236 as the test vent. be tested by pressurizing through NF-957 j NF-234A would be pressurized i
through NF-957 utilizing NF-1150 as the test vent.
{ NF-228A, NF-233B and NF-234A are diaphraga valves which have excellent history of leak an
- tightness. This characteristic is primarily due to the resiliency of the rubber diaphragm. If
! a rupture leakage around of the diaphrage were to occur, it would be evident via the valve stem due to the static pressure I
maintained on the glycol system.
A
{
rate bench test was performed at McGuire to corrolate the leakage
! of air and the Glycol / Water mixture.
! fabricated using a metering valve to achieve A test stand was leakage area. a repeatable The upstream side was pressurized to 15 pais, the i'
downstream constant side at 75 discharged degrees F. The to atmosphere and temperature was held following results were obtained:
l i
AIR LEAK WATER / GLYCOL RATE (SCCM) LEAK RATE (SCCM) !
500 15 1000 28 1500 47 These results infer a 1 to 31 glycol to air leakage ratio a .994 corrolation coefficient. This ratio will be differentwith at different temperatures due to changes in kinematic viscosity.
The leakage rate acceptance criteria that would be these diaphragm valves would be zero imposed on indicated leakage (not including instrument error).
If the leak rate is greater than zero, the. penetration will be fully drained and Appendix the valves leak tested in accordance with J. Performing the local leakage rate test on these penetrations without fully draining them will not compromlse containment integrity.
4 e
O 4
u l
. , - - . - . . . . - - - - - - ~ - - - - . . - - -_ -_ . . .- - . .-.,- - . -- -., .- . . . . . - . ~ . - - ,.- . - - - --_- -
Attachmsnt A G ,,e
==n w @ -
'.., m N'N ',m +-0-il'*=7
-as- , ,!{ 4[ **um
-u.mu 2 i :,;,
cig a1,,mat t'ra I I a: '=
cv - - - - , . , _ . . .
~--
,en
. ggar "v\ ' .EIci ji I I f ' 'l w . . .. . . ,-/
,3 l l El m o v a >.- .mion ,
ev - a. - = Go + +-o-][g, m i I ! 1E
{-'*]" 8 . [ .. . m GI col #l'* " " + 7 Re urn ate Em <. rem er h ' *"* L" arna' O ,....-
m
,e= or
, , , (m,q
,rua
- P i oigsgo, , " h....J ---4 d[' *"'
< , - - 2 04 %'2%es**"""
bd
/* e-*
\ e..m... e
<.. - TEJ n
-4 .* j MC-1558-4.0 ..
+ CIED
, ...m Q b
(For infortnation Only) .5Ti g een as
',7.',
-W,3*='- a rzEn
. ,, , e* ' @
g , , , ,
, _7. .
_72 C'
= i
-l- -l-cv cv en tt M o ..,,, _
swas m
-4 ** I
're T s
'~
fw'3
<.- >-- .t. [ ,
swee EE
- jd=
Glycol Supply a y l
l
.