Letter Sequence Other |
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MONTHYEARML20211K7841985-04-25025 April 1985 Forwards Affidavit for Withholding Proprietary McGuire Units 1 & 2 Tubesheet Region Plugging Criterion (Ref 10CFR2.790).Nonproprietary Version Encl.Proprietary Version Withheld Project stage: Other ML20127P5321985-05-0909 May 1985 Summary of 850502 Meeting W/Util & Westinghouse in Bethesda,Md Re Steam Generator Tube Plugging for Indications within Tubesheet Region.List of Attendees & Viewgraphs Encl Project stage: Meeting ML20195C3711985-10-0909 October 1985 Change 0 to B&W Spent Fuel Receipt,Storage & Shipping W/Nli Cask. Summary of TN-8L Cask Procedure Encl Project stage: Other ML20140F8021986-03-20020 March 1986 Application for Amend to Licenses NPF-9 & NPF-17,authorizing Use of TN-8 & TN-8L Casks for Receipt of Irradiated Fuel. Justification Encl.Fee Paid Project stage: Request ML20195C3861986-05-0909 May 1986 TN-8L Draft Unloading Procedure for McGuire Station Project stage: Draft Other ML20195C3521986-05-23023 May 1986 Responds to 860512 & 15 Requests for Addl Info Re 860320 Application for Amends to Licenses NPF-9 & NPF-17,permitting Use of multi-element Spent Fuel Casks.Summary of Procedure OP/O/A/6550/13 Encl.W/Two Oversize Drawings Project stage: Request ML20195E2821986-05-28028 May 1986 Proposed Tech Spec 3/4.6.2.3,deleting Drywell Air Lock Seal Pressure Instrumentation 31-day Channel Functional Test from Surveillance Requirement 4.6.2.3.d.1 Project stage: Other ML20211K7791986-06-24024 June 1986 Proposed Tech Specs,Changing Steam Generator Tube Plugging Criteria to Allow Evaluations of Degraded Tubes to Be Performed within Tubesheet Project stage: Other ML20211K7711986-06-24024 June 1986 Application for Amends to Licenses NPF-9 & NPF-17,modifying Steam Generator Tube Plugging Criteria to Allow Evaluations of Degraded Tubes to Be Performed within Tubesheet.Fee Paid Project stage: Request ML20206U0001986-07-0101 July 1986 Forwards Revised Marked Up Proposed Tech Specs,Re Criterion for Plugging Steam Generator Tubes,Reflecting Change in Wording of Proposal.Changes Not Functionally Different from Changes in 860624 Submittal Project stage: Other ML20203A5051986-07-10010 July 1986 Informs of Present Schedule for Ongoing Refueling Outage,Per Proposed Changes to Tech Specs Submitted in 860624 & 0701 Ltrs.Approval of Change Required Prior to Entry Into Mode 4, Presently Scheduled for 860822 Project stage: Request ML20202J7721986-07-10010 July 1986 Forwards Addl Info to Support 860320 Application for Amends to Licenses NPF-9 & NPF-17,authorizing Use of Multielement Spent Fuel Casks TN-8 & TN-81 for Receipt of Irradiated Oconee Fuel.Timely Approval Requested Project stage: Request ML20207B1531986-07-11011 July 1986 Notice of Consideration of Issuance of Amends to Licenses NPF-9 & NPF-17 & Opportunity for Prior Hearing Re Elimination of Requirements for Plugging Steam Generator If Defect 2 Inches Below Top of Tube Sheet Project stage: Other ML20207B1381986-07-11011 July 1986 Disagrees That Proposed Amends to Licenses NPF-9 & NPF-17, Eliminating Need to Plug Steam Generator Tubes,Would Not Involve Significant Hazards Consideration.Notice of Opportunity for Prior Hearing Re Amends Encl Project stage: Other ML20211P2621986-07-16016 July 1986 Notification of 860725 Meeting W/Util & Westinghouse in Bethesda,Md to Discuss Proposed Tech Spec Change Re Plugging of Steam Generator Tubes W/Defects in Tubesheet Region Project stage: Meeting ML20212B8841986-07-31031 July 1986 Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators Project stage: Other ML20212B8741986-08-0101 August 1986 Requests That WCAP-11224 Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl Project stage: Other ML20212D0061986-08-0505 August 1986 Suppls 860320 Application for Amends to Licenses NPF-9 & NPF-17,permitting Use of multi-element TN-8 & TN-8L Spent Fuel Casks for Receipt of Irradiated Fuel.Info Re Environ Impacts Per 10CFR51.52 Encl Project stage: Request ML20212B8661986-08-0505 August 1986 Proposed Tech Specs,Incorporating Revised Steam Generator Plugging Criteria Project stage: Other ML20206M3031986-08-13013 August 1986 Proposed Tech Specs Re RCS Surveillance Requirements for Steam Generator Tube Plugging Project stage: Other ML20206M2951986-08-13013 August 1986 Supplemental Application for Amends to Licenses NPF-9 & NPF-17,revising Tech Specs Re RCS Surveillance Requirements for Steam Generator Tube Plugging.Tubes Will Be Inspected During Each Inservice Insp Project stage: Supplement ML20206M2821986-08-18018 August 1986 Forwards Revised marked-up Pages to Proposed Tech Specs Re Criterion for Plugging Steam Generator Tubes Reflecting Change in Wording of Proposal.Changes Not Functionally Different from Changes in 860813 Submittal Project stage: Other ML20206P8861986-08-25025 August 1986 Approves Withholding WCAP-10949, Tubesheet Region Plugging Criterion for Full Depth Hardroll Expanded Tubes, Per Util 860723 Application & Recipient 860722 Affidavit (Ref 10CFR2.790) Project stage: Other ML20210S5421986-09-22022 September 1986 Submits Addl Info Re Radiochemistry Program for Primary to Secondary Leakage Detection & Quantification,Per 860812 Telcon Request Project stage: Other ML20203N6881986-10-15015 October 1986 Agrees to Withhold Proprietary Version of McGuire Units 1 & 2 Tubesheet Region Plugging Criterion, (Ref 10CFR2.790) Per 860801 Request Project stage: Other AECM-86-0351, Forwards Application for Amend to License NPF-29,correcting Reactor Pressure Vessel pressure-temp Graph,Figure 3.4.6.1-1,clarifying Drywell Airlock & Changing Portion of Surveillance Requirement 4.6.2.3.Fee Paid1986-11-11011 November 1986 Forwards Application for Amend to License NPF-29,correcting Reactor Pressure Vessel pressure-temp Graph,Figure 3.4.6.1-1,clarifying Drywell Airlock & Changing Portion of Surveillance Requirement 4.6.2.3.Fee Paid Project stage: Request ML20213G7591986-11-11011 November 1986 Application for Amend to License NPF-29,correcting Reactor Pressure Vessel pressure-temp Graph (Figure 3.4.6.1-1), Clarifying Drywell Airlock & Changing Portion of Surveillance Requirement 4.6.2.3 Re Airlock Seal Sys Project stage: Request ML20213G7631986-11-11011 November 1986 Proposed Changes to Tech Spec Figure 3.4.6.1-1 Re Min Reactor Pressure Vessel Metal Temp Vs Reactor Vessel Pressure & Spec 3.6.2.3 Re Drywell Airlocks Project stage: Request ML20212J3341987-01-20020 January 1987 Supplemental Application for Amend to License NPF-29, Revising Tech Spec 3/4 4.6 Re Reactor Pressure Vessel pressure-temp Curve to Delete Ref to NEDO-21778-A Project stage: Supplement ML20212J3471987-01-20020 January 1987 Proposed Tech Spec 3/4 4.6 Re Reactor Pressure Vessel pressure-temp Curve,Deleting Ref to NEDO-21778-A Project stage: Other AECM-87-0037, Revises 861111 Application for Amend to License NPF-29, Changing Tech Spec 4.6.2.3.d.1 Re Drywell Airlock Seal Pressure Instrumentation Channel Functional Test Submitted on 860528,per Discussion W/Nrc.Proposed Tech Spec Page Encl1987-02-13013 February 1987 Revises 861111 Application for Amend to License NPF-29, Changing Tech Spec 4.6.2.3.d.1 Re Drywell Airlock Seal Pressure Instrumentation Channel Functional Test Submitted on 860528,per Discussion W/Nrc.Proposed Tech Spec Page Encl Project stage: Request ML20211D6221987-02-13013 February 1987 Proposed Tech Spec 4.6.2.3 Re Surveillance Requirements for Containment Sys Concerning Drywell Air Lock Project stage: Other 1986-07-10
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests ML20059B0351993-10-15015 October 1993 Proposed Tech Specs Converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20057C7281993-09-23023 September 1993 Proposed Tech Specs Removing Surveillance Requirement 4.4.1.2.2 Due to Problems Encountered W/Jet Pump Differential Pressure Instrumentation Measurements ML20056E4511993-08-12012 August 1993 Proposed Tech Specs 3/4 6-3,6-4,6-4a,6-6,6-12 Re Exemption to 10CFR50,App J, Primary Reactor Containment..., for Local Leak Rate ML20056D5621993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.5 Reflecting Relocation of Certain Accident Monitoring Instrumentation to Administrative Control ML20046D2081993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.10, Loose Part Detection Sys, Relocating Loose Part Detection Instrumentation from TS to Administrative Control ML20046D1961993-08-11011 August 1993 Proposed Tech Specs Supporting Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7141993-07-15015 July 1993 Proposed Tech Specs Removing Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve 1999-08-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20210F6651997-12-22022 December 1997 Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations ML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6101994-01-14014 January 1994 Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20029D6451993-11-30030 November 1993 Reactor Containment Bldg 1993 Integrated Leakage Rate Test. ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests 1999-08-20
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Text
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PS-85/07
SUBJECT:
Technical Specification Surveillance Requirement 4.6.2.3.d.1.a; page 3/4 6-16 DISCUSSION: The proposed change will delete the drywell air lock seal pressure instrumentation 31 day channel functional test from the subject technical specification. This surveillance requirement cannot be performed without entering and staying in a high radiation area. The existing 18 month channel calibration which includes a channel functional test and the 6 month overall air lock leakage test remain in the technical specifications.
JUSTIFICATION: The purpose of the inflatable seal pressure instrumentation is to provide a signal to indicating lights which then in turn provide personnel entering one door of the air lock with an indication that the other door is properly sealed. The drywell air lock inflatable seal pressure instrumentation actuates no control room status lights or alarms.
During operation above 5% power, drywell entry is not allowed.
The 31 day channel functional test is presently performed on the outer door of the drywell air lock but is not performed on the inner door with the reactor above 5% power. The. inner door is declared inoperable when the test cannot be performed with the plant at power. The provisions of Action a of Technical Specification 3/4.6.2.3 allows for continued operation of the plant until performance of the next required overall air lock leakage test provided that the operable air lock door is verified to be locked closed at least once per 31 days.
I The only feasible method for performing the 31 day channel functional test on the inner door, while maintaining drywell integrity, would require entry into the drywell air lock, closure r,f the outer door, and deflation of the inner door seals without opening the inner door. At power operation, the area inside the drywell air lock is usually classified a high radiation area (approximately 225 mrem /hr neutron, 400 mR/hr gamma at 67% power), thus requiring according to 10CFR 20.203 that personnel not be prevented from leaving the area. With the outer drywell air lock door closed during performance of the 31 day channel functional test on the inner door, exit from the air lock is impeded and with failure of the outer door mechanism, a person could be trapped in a high radiation area. This
( possibility prevents the performance of the 31 day channel functional test when the reactor is at power.
When the inner drywell air lock door is declared inoperable because the 31 day channel functional test has not been performed, this action potentially impacts the successful performance of Surveillance Requirement 4.6.2.3.b for the overall air lock leakage test. With the inner air lock door 8606050316 86052s J10 MISC 86052701A - 1 PDR ADOCK 05000416 P PDR
a .
2:'
. /
l
, s .
' declared inoperable, Action a of Technical Specification
? 3/4.6.2.3 is entered and the operable outer drywell air lock door is locked closed. To perform Surveillance Requirement
"^ 4.6.2.3.b,.the outer air lock door must be opened thus s requiring entry into Action b. If the plant has been operating
.' - ' in Action a for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed in Action b to restore the air lock to operable status has been
~
used and the plant must be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if
_ the overall air lock feakage test is not successfully completed.
' Since this test can take more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to perform, successful completion of the overall air lock leakage test is not assured and plant shutdown is a strong possibility.
,. Deletion of the 31 day channels functional test on the seal y pressure instrumentation will remove the requirement to declare l the innekdoor of the drywell air lock inoperable and thus J- p'rovide an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (as allowed in Action b) to
- - perform the overall air lock leakage test per Surveillance 7 Re,quirement 4.6.2.3.b.
The drywell air lock inflatable seal pressure instrumentation actuates no control room status lights or alarms, and thus
, serves no function in warning of drywell integrity violation.
r However, the performance of other technical specification surveillance requirements such as verifying seal air flask l 4- pressure an'd seal leakage tests help to ensure seal integrity.
- .< Under the present technical specifications, the air lock is demonstrated operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each closing. The overall air lock and seal pneumatic system are leak tested on 4
-an appropriate surveillance interval to ensure air lock and
, , tseal integrity. In addition, the seal air flask pressure is I ,
verified to be greater than or equal to 90 psig at least once L
per 7 days.
, . .f .
; :Since drywell entry is not allowed during operation above 5%
~
l -
power, cycling the air lock seals every 31 days serves no I ,
- useful function and could contribute to seal failure through wear and excessive testing. MP&L believes that the deletion of Technical' Specification Surveillance Requirement 4.6.2.3.d.1.a is justified:
~s ,
1). Due to the radiological threat to personnel performing the
., required surveillance; e
2)I Because the drywell air lock is not used for entry during i
' operation above 5% power; y ,
' Because the overall air lock leakage test is impacted when 3)
" the inner door is declared inoperable and when the test must be run with the reactor at power.
- 4) Due to the rel.ative inconsequential function served by the
- drywell air . lock inflatable seal pressure instrumentation; 4
J10 MISC 86'050701A - 2
}:
j SIGNIFICANT HAZARDS CONSIDERATIONS:
L The proposed technical specification change would delete the required drywell~ seal pressure instrumentation 31 day channel
, functional test (Survefilance Requirement 4.6.2.3.d.1.a). The proposed change does not involve a significant hazards consideration because operation of Grand Gulf Unit 1 in accordance with this change would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated. The only purpose of the inflatable seal pressure instrumentation is to provide a signal to indicating lights which provide personnel entering one door of the I air lock with an indication that the other door is j sealed. An interlock exists which prevents the opening of both doors simultaneously. In addition, the drywell air l i
lock inflatable seal pressure instrumentation actuates no control room status lights or alarms, and thus, serves no function in warning of drywell integrity violation. Other technical specification surveillance requirements verify seal air flask pressure and seal leak tests thus helping to ensure seal integrity. Therefore, this change does not increase the probability or consequences of an accident.
(2) create the possibility of a new or different kind of accident from any previously analyzed. The reduction in testing the seal pressure instrumentation does not create the possibility of a new or different kind of accident since this instrumentation serves no function in the warning or maintaining of drywell integrity. The only function is to provide personnel entering one door indication that the other door is sealed.
r (3) involve a significant reduction in a margin of safety.
! The seal pressure instrumentation serves no safety related l function nor does it actuate any control room status lights / alarms or perform any automatic action. The instrumentation simply provides personnel with an indication of the drywell air lock door status.
. Therefore, deletion of Technical Specification
! 4.6.2.3.d.1.a will not reduce the margin of safety as J provided by the Technical Specifications. '
J10 MISC 86052701A - 3
- a. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> # after each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> #, by verifying seal leakage rate less than or equal to 2 scf per hour when the gap between'the door seals is pressurized to Pa , 11.5 psig.
- b. By conducting an overall air lock leakage test at Pa , 11.5 psig and verifying that the overall air lock leakage rate is within its limit:
- 1. At least once per 6 months # ,
- 2. Prior to establishing DRYWELL INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability,
- c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
- d. By verifying each airlock door inflatable seal system OPERABLE by:
- 1. Demonstrating each of the two inflatable seal pressure instrumentation channels per airlock door OPERABLE by performance of a:
a) C"^""EL FU"CTIO"^L TEST at le :t once per 21 day , and DELETED b) CHANNEL CALIBRATION at least once per 18 months, with a low pressure setpoint of > 60 psig.
- 2. At least once per 7 days verifying seal air flask pressure to be greater than or equal to 90 psig.
- 3. At least once per 18 months, conducting a seal pneumatic system leak test and verifying that system pressure does not decay more than 2 psig from 90 psig within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
The provisions of Specification 4.0.2 are not applicable.
GRAND GULF-UNIT 1 3/4 6-16 A N E Wd M M F $/0.
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