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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARPY-CEI-NRR-2427, Application for Amend to License NPF-58,deleting License Condition 2.C.10 Re Controls Over Containment Air Locks During Plant Outages & Clarifying License Condition 2.F Re Reporting Requirements of TS & EPP Violations1999-09-14014 September 1999 Application for Amend to License NPF-58,deleting License Condition 2.C.10 Re Controls Over Containment Air Locks During Plant Outages & Clarifying License Condition 2.F Re Reporting Requirements of TS & EPP Violations PY-CEI-NRR-2406, Application for Amend to License NPF-58,eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula.Summary & Description of Change Is Encl1999-09-0909 September 1999 Application for Amend to License NPF-58,eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula.Summary & Description of Change Is Encl PY-CEI-NRR-2430, Application for Amend to License NPF-58,revising Allowables Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons1999-09-0909 September 1999 Application for Amend to License NPF-58,revising Allowables Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons PY-CEI-NRR-2420, Application for Amend to License NPF-58,increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal.Proprietary SAR Encl. Proprietary SAR Withheld,Per 10CFR2.790(a)(4)1999-09-0909 September 1999 Application for Amend to License NPF-58,increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal.Proprietary SAR Encl. Proprietary SAR Withheld,Per 10CFR2.790(a)(4) PY-CEI-NRR-2418, Application for Amend to License NPF-58,incorporating Addl Option Into TS 3.9.1 Required Actions When Refueling Interlocks Are Inoperable1999-08-0404 August 1999 Application for Amend to License NPF-58,incorporating Addl Option Into TS 3.9.1 Required Actions When Refueling Interlocks Are Inoperable PY-CEI-NRR-2398, Application for Amend to License NPF-58,changing SRs as Identified to Support Implementation of 24-month Operating Cycle at Pnpp1999-06-17017 June 1999 Application for Amend to License NPF-58,changing SRs as Identified to Support Implementation of 24-month Operating Cycle at Pnpp ML20206F5971999-05-0505 May 1999 Application for Amend to License NPF-58,authorizing CEI to Possess Dl 13.74% Undivided Ownership Interest in Pnpp PY-CEI-NRR-2362, Application for Amend to License NPF-58,proposing Change in Plant USAR by Incorporating leak-off Line in RHR Sys, Which Will Significantly Reduce Collective Dose to Plant Operations Personnel.Annotated USAR Pages,Encl1999-03-17017 March 1999 Application for Amend to License NPF-58,proposing Change in Plant USAR by Incorporating leak-off Line in RHR Sys, Which Will Significantly Reduce Collective Dose to Plant Operations Personnel.Annotated USAR Pages,Encl PY-CEI-NRR-2373, Application for Amend to License NPF-58,correcting Typos Found in TS Table 3.3.6.1-11999-03-15015 March 1999 Application for Amend to License NPF-58,correcting Typos Found in TS Table 3.3.6.1-1 PY-CEI-NRR-2359, Suppl Application for Amend to License NPF-58,involving Rev of Main Steam Line Leakage Requirements & Elimination of Main Steam Isolation Valve Leakage Control Sys.Proprietary Calculations Encl.Proprietary Encls Withheld1999-01-18018 January 1999 Suppl Application for Amend to License NPF-58,involving Rev of Main Steam Line Leakage Requirements & Elimination of Main Steam Isolation Valve Leakage Control Sys.Proprietary Calculations Encl.Proprietary Encls Withheld PY-CEI-NRR-2352, Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs1999-01-0606 January 1999 Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs PY-CEI-NRR-2325, Application for Amend to License NPF-58,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by Ge.Proprietary Addl Info Re 1.09 Cycle Specific Slmcpr,Encl.Proprietary Info Withheld1998-10-27027 October 1998 Application for Amend to License NPF-58,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by Ge.Proprietary Addl Info Re 1.09 Cycle Specific Slmcpr,Encl.Proprietary Info Withheld PY-CEI-NRR-2322, Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program1998-09-0909 September 1998 Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program PY-CEI-NRR-2319, Application for Amend to License NPF-58,permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allow Performance of EDG 24-hour TS SR Test in Modes 1 & 21998-09-0303 September 1998 Application for Amend to License NPF-58,permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allow Performance of EDG 24-hour TS SR Test in Modes 1 & 2 PY-CEI-NRR-2298, Application for Amend to License NPF-58,increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Vol Due to Vortex Formation at Eductor Suction Nozzles Located in Fuel Oil Storag1998-09-0303 September 1998 Application for Amend to License NPF-58,increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Vol Due to Vortex Formation at Eductor Suction Nozzles Located in Fuel Oil Storage Tank PY-CEI-NRR-2300, Application for Amend to License NPF-58,allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable1998-08-31031 August 1998 Application for Amend to License NPF-58,allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable PY-CEI-NRR-2299, Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld1998-07-22022 July 1998 Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld ML20151P1891998-07-13013 July 1998 Application for Amend to License NPF-58,revising Safety Setpoint Requirements for Srv.Proprietary Info & Affidavit Are Contained in Attachment 5.Proprietary Info Withheld PY-CEI-NRR-2295, Application for Amend to License NPF-58,revising TS 3.1.7, Standby Liquid Control Sys to Increase Boron Concentration in Standby Liquid Control Sys for Cycle 8 Fuel Design & to Provide Margin for Future Cycles as Required1998-06-30030 June 1998 Application for Amend to License NPF-58,revising TS 3.1.7, Standby Liquid Control Sys to Increase Boron Concentration in Standby Liquid Control Sys for Cycle 8 Fuel Design & to Provide Margin for Future Cycles as Required ML20236H6931998-06-30030 June 1998 Application for Amend to License NPF-58,transferring Operating Authority for Pnpp from Ceic & Centerior Svc Co to New Operating Company Named Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments,Included PY-CEI-NRR-2245, Application for Amend to License NPF-58,revising TS 3.8.1, AC Sources - Operating, to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs1997-12-23023 December 1997 Application for Amend to License NPF-58,revising TS 3.8.1, AC Sources - Operating, to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs PY-CEI-NRR-2230, Application for Amend to License NPF-58,incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchangers1997-10-22022 October 1997 Application for Amend to License NPF-58,incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchangers PY-CEI-NRR-2207, Application for Amend to License NPF-58,revising TS 5.2.2.e, Organization-Unit Staff, by Removing Ref to NRC Policy Statement on Working Hours1997-09-0808 September 1997 Application for Amend to License NPF-58,revising TS 5.2.2.e, Organization-Unit Staff, by Removing Ref to NRC Policy Statement on Working Hours PY-CEI-NRR-2206, Application for Amend to License NPF-58,revising Pressure- Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.901997-08-28028 August 1997 Application for Amend to License NPF-58,revising Pressure- Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90 ML20217F5751997-07-28028 July 1997 Application for Amends to Licenses DPR-66,NPF-73 & NPF-58, Authorizing Holders to Possess Beaver Valley Power Station, Unit 1 & Authorizes Duquesne Light to Use & Operate Beaver Valley Unit 1 in Accordance W/Procedures PY-CEI-NRR-2164, Application for Amend to License NPF-58,revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys1997-05-0202 May 1997 Application for Amend to License NPF-58,revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys PY-CEI-NRR-2165, Application for Amend to License NPF-58,revising Tech Specs Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria1997-05-0202 May 1997 Application for Amend to License NPF-58,revising Tech Specs Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria PY-CEI-NRR-2155, Application for Amend to License NPF-58,revising TS Surveillance Requirements 3.9.1.1 & 3.9.2.2,extending SR Frequency on Refueling Equipment & one-rod-out Interlocks1997-04-0909 April 1997 Application for Amend to License NPF-58,revising TS Surveillance Requirements 3.9.1.1 & 3.9.2.2,extending SR Frequency on Refueling Equipment & one-rod-out Interlocks PY-CEI-NRR-2133, Application for Amend to License NPF-58,requesting Implementation of App J,Option B,Performance-based Primary Containment Leakage Rate Testing Program for Type A,B & C Leak Rate Tests1997-01-31031 January 1997 Application for Amend to License NPF-58,requesting Implementation of App J,Option B,Performance-based Primary Containment Leakage Rate Testing Program for Type A,B & C Leak Rate Tests ML20132C7601996-12-13013 December 1996 Application for Amend to License NPF-58,authorizing Transfers of Control PY-CEI-NRR-2104, Application for Amend to License NPF-58,modifying MCPR Reactor Core Safety Limit Contained in TS 2.1.1.21996-10-24024 October 1996 Application for Amend to License NPF-58,modifying MCPR Reactor Core Safety Limit Contained in TS 2.1.1.2 ML20117E7821996-08-27027 August 1996 Application for Amend to License NPF-58,revising MSL Leakage Requirements & Eliminating MSIV Leakage Control Sys. Attachment 7 Provides Proprietary Dose Calculations. Attachment 7 Withheld PY-CEI-NRR-1999, Application for Amend to License NPF-58,revising Improved Tech Specs.Changes Either Administrative in Nature or Reflect Minor Technical Errors Discovered During Implementation Process1996-04-26026 April 1996 Application for Amend to License NPF-58,revising Improved Tech Specs.Changes Either Administrative in Nature or Reflect Minor Technical Errors Discovered During Implementation Process PY-CEI-NRR-2030, Application for Amend to License NPF-58 Re Drywell Personnel Air Lock Shield Door Analyses1996-02-27027 February 1996 Application for Amend to License NPF-58 Re Drywell Personnel Air Lock Shield Door Analyses PY-CEI-NRR-2027, Application for Amend to License NPF-58,changing TS to Reflect Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 61996-02-17017 February 1996 Application for Amend to License NPF-58,changing TS to Reflect Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6 PY-CEI-NRR-2007, Application for Amend to License NPF-58,revising TS Requirements for Drywell Leak Rate Testing1996-01-16016 January 1996 Application for Amend to License NPF-58,revising TS Requirements for Drywell Leak Rate Testing PY-CEI-NRR-2013, Application for Amend to License NPF-58,requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 9601271996-01-10010 January 1996 Application for Amend to License NPF-58,requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127 ML20095L2181995-12-28028 December 1995 Suppl Application for License Transfer of 12.58% Ownership Interest in Addition to 17.42% Approved on 951220 PY-CEI-NRR-2004, Application for Amend to License NPF-58,revising License to Reflect License Transfer for Part of Oh Edison Co Ownership Interest in Pnpp Unit 1 to Wholly Owned Subsidiary,Oes Nuclear,Inc1995-11-22022 November 1995 Application for Amend to License NPF-58,revising License to Reflect License Transfer for Part of Oh Edison Co Ownership Interest in Pnpp Unit 1 to Wholly Owned Subsidiary,Oes Nuclear,Inc PY-CEI-NRR-1978, Application for Amend to License NPF-58,requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operating1995-11-0202 November 1995 Application for Amend to License NPF-58,requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operating PY-CEI-NRR-1995, Application for Amend to License NPF-58,revising TS Requirements for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Certain Specs Related to Performing Core Alterations1995-11-0202 November 1995 Application for Amend to License NPF-58,revising TS Requirements for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Certain Specs Related to Performing Core Alterations PY-CEI-NRR-1997, Application for Amend to License NPF-58,providing Suppl Info That Revises License to Reflect Proposed Merger of Operating Companies1995-11-0101 November 1995 Application for Amend to License NPF-58,providing Suppl Info That Revises License to Reflect Proposed Merger of Operating Companies PY-CEI-NRR-1969, Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)1995-08-29029 August 1995 Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L) PY-CEI-NRR-1961, Application for Amends to Licenses NPF-58,reflecting One Time Extension of Performance Intervals for Certain TS Surveillance Requirements1995-06-30030 June 1995 Application for Amends to Licenses NPF-58,reflecting One Time Extension of Performance Intervals for Certain TS Surveillance Requirements PY-CEI-NRR-1954, Application for Amend to License NPF-58.Amend Would Allow one-time Extension of Performance Intervals for Certain Srs. Application Supplements Original Request1995-06-0909 June 1995 Application for Amend to License NPF-58.Amend Would Allow one-time Extension of Performance Intervals for Certain Srs. Application Supplements Original Request PY-CEI-NRR-1956, Application for Amend to License NPF-58,proposing Early Implementation of Control Rod Drive Scram Time Testing Consistent W/Requirements in Pnpp Improved TS LAR1995-06-0101 June 1995 Application for Amend to License NPF-58,proposing Early Implementation of Control Rod Drive Scram Time Testing Consistent W/Requirements in Pnpp Improved TS LAR PY-CEI-NRR-1944, Suppl Application for Amend to License NPF-58,App a Tss. Suppl Addresses Minor Discrepancies & Items Needing Clarification1995-05-0505 May 1995 Suppl Application for Amend to License NPF-58,App a Tss. Suppl Addresses Minor Discrepancies & Items Needing Clarification PY-CEI-NRR-1932, Application for Amend to License NPF-58.Amend Would Incorporate Results of Work Performed by BWROG Re Elimination of Selected Response Time Testing Requirements1995-05-0101 May 1995 Application for Amend to License NPF-58.Amend Would Incorporate Results of Work Performed by BWROG Re Elimination of Selected Response Time Testing Requirements PY-CEI-NRR-1934, Application for Amend to License NPF-58,proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS1995-04-28028 April 1995 Application for Amend to License NPF-58,proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS PY-CEI-NRR-1927, Application for Amend to License NPF-58 Re Removal of License Conditions for Tdi EDGs Specified by Paragraph 2.c & Defined in Attachment 2 to Operating License1995-04-28028 April 1995 Application for Amend to License NPF-58 Re Removal of License Conditions for Tdi EDGs Specified by Paragraph 2.c & Defined in Attachment 2 to Operating License 1999-09-09
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARPY-CEI-NRR-2427, Application for Amend to License NPF-58,deleting License Condition 2.C.10 Re Controls Over Containment Air Locks During Plant Outages & Clarifying License Condition 2.F Re Reporting Requirements of TS & EPP Violations1999-09-14014 September 1999 Application for Amend to License NPF-58,deleting License Condition 2.C.10 Re Controls Over Containment Air Locks During Plant Outages & Clarifying License Condition 2.F Re Reporting Requirements of TS & EPP Violations PY-CEI-NRR-2430, Application for Amend to License NPF-58,revising Allowables Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons1999-09-0909 September 1999 Application for Amend to License NPF-58,revising Allowables Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons PY-CEI-NRR-2406, Application for Amend to License NPF-58,eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula.Summary & Description of Change Is Encl1999-09-0909 September 1999 Application for Amend to License NPF-58,eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula.Summary & Description of Change Is Encl PY-CEI-NRR-2420, Application for Amend to License NPF-58,increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal.Proprietary SAR Encl. Proprietary SAR Withheld,Per 10CFR2.790(a)(4)1999-09-0909 September 1999 Application for Amend to License NPF-58,increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal.Proprietary SAR Encl. Proprietary SAR Withheld,Per 10CFR2.790(a)(4) PY-CEI-NRR-2418, Application for Amend to License NPF-58,incorporating Addl Option Into TS 3.9.1 Required Actions When Refueling Interlocks Are Inoperable1999-08-0404 August 1999 Application for Amend to License NPF-58,incorporating Addl Option Into TS 3.9.1 Required Actions When Refueling Interlocks Are Inoperable PY-CEI-NRR-2398, Application for Amend to License NPF-58,changing SRs as Identified to Support Implementation of 24-month Operating Cycle at Pnpp1999-06-17017 June 1999 Application for Amend to License NPF-58,changing SRs as Identified to Support Implementation of 24-month Operating Cycle at Pnpp ML20206F5971999-05-0505 May 1999 Application for Amend to License NPF-58,authorizing CEI to Possess Dl 13.74% Undivided Ownership Interest in Pnpp PY-CEI-NRR-2362, Application for Amend to License NPF-58,proposing Change in Plant USAR by Incorporating leak-off Line in RHR Sys, Which Will Significantly Reduce Collective Dose to Plant Operations Personnel.Annotated USAR Pages,Encl1999-03-17017 March 1999 Application for Amend to License NPF-58,proposing Change in Plant USAR by Incorporating leak-off Line in RHR Sys, Which Will Significantly Reduce Collective Dose to Plant Operations Personnel.Annotated USAR Pages,Encl PY-CEI-NRR-2373, Application for Amend to License NPF-58,correcting Typos Found in TS Table 3.3.6.1-11999-03-15015 March 1999 Application for Amend to License NPF-58,correcting Typos Found in TS Table 3.3.6.1-1 PY-CEI-NRR-2359, Suppl Application for Amend to License NPF-58,involving Rev of Main Steam Line Leakage Requirements & Elimination of Main Steam Isolation Valve Leakage Control Sys.Proprietary Calculations Encl.Proprietary Encls Withheld1999-01-18018 January 1999 Suppl Application for Amend to License NPF-58,involving Rev of Main Steam Line Leakage Requirements & Elimination of Main Steam Isolation Valve Leakage Control Sys.Proprietary Calculations Encl.Proprietary Encls Withheld PY-CEI-NRR-2352, Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs1999-01-0606 January 1999 Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs PY-CEI-NRR-2325, Application for Amend to License NPF-58,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by Ge.Proprietary Addl Info Re 1.09 Cycle Specific Slmcpr,Encl.Proprietary Info Withheld1998-10-27027 October 1998 Application for Amend to License NPF-58,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by Ge.Proprietary Addl Info Re 1.09 Cycle Specific Slmcpr,Encl.Proprietary Info Withheld PY-CEI-NRR-2322, Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program1998-09-0909 September 1998 Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program PY-CEI-NRR-2298, Application for Amend to License NPF-58,increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Vol Due to Vortex Formation at Eductor Suction Nozzles Located in Fuel Oil Storag1998-09-0303 September 1998 Application for Amend to License NPF-58,increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Vol Due to Vortex Formation at Eductor Suction Nozzles Located in Fuel Oil Storage Tank PY-CEI-NRR-2319, Application for Amend to License NPF-58,permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allow Performance of EDG 24-hour TS SR Test in Modes 1 & 21998-09-0303 September 1998 Application for Amend to License NPF-58,permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allow Performance of EDG 24-hour TS SR Test in Modes 1 & 2 PY-CEI-NRR-2300, Application for Amend to License NPF-58,allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable1998-08-31031 August 1998 Application for Amend to License NPF-58,allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable PY-CEI-NRR-2299, Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld1998-07-22022 July 1998 Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld ML20151P1891998-07-13013 July 1998 Application for Amend to License NPF-58,revising Safety Setpoint Requirements for Srv.Proprietary Info & Affidavit Are Contained in Attachment 5.Proprietary Info Withheld PY-CEI-NRR-2295, Application for Amend to License NPF-58,revising TS 3.1.7, Standby Liquid Control Sys to Increase Boron Concentration in Standby Liquid Control Sys for Cycle 8 Fuel Design & to Provide Margin for Future Cycles as Required1998-06-30030 June 1998 Application for Amend to License NPF-58,revising TS 3.1.7, Standby Liquid Control Sys to Increase Boron Concentration in Standby Liquid Control Sys for Cycle 8 Fuel Design & to Provide Margin for Future Cycles as Required ML20236H6931998-06-30030 June 1998 Application for Amend to License NPF-58,transferring Operating Authority for Pnpp from Ceic & Centerior Svc Co to New Operating Company Named Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments,Included PY-CEI-NRR-2245, Application for Amend to License NPF-58,revising TS 3.8.1, AC Sources - Operating, to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs1997-12-23023 December 1997 Application for Amend to License NPF-58,revising TS 3.8.1, AC Sources - Operating, to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs PY-CEI-NRR-2230, Application for Amend to License NPF-58,incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchangers1997-10-22022 October 1997 Application for Amend to License NPF-58,incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchangers PY-CEI-NRR-2207, Application for Amend to License NPF-58,revising TS 5.2.2.e, Organization-Unit Staff, by Removing Ref to NRC Policy Statement on Working Hours1997-09-0808 September 1997 Application for Amend to License NPF-58,revising TS 5.2.2.e, Organization-Unit Staff, by Removing Ref to NRC Policy Statement on Working Hours PY-CEI-NRR-2206, Application for Amend to License NPF-58,revising Pressure- Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.901997-08-28028 August 1997 Application for Amend to License NPF-58,revising Pressure- Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90 ML20217F5751997-07-28028 July 1997 Application for Amends to Licenses DPR-66,NPF-73 & NPF-58, Authorizing Holders to Possess Beaver Valley Power Station, Unit 1 & Authorizes Duquesne Light to Use & Operate Beaver Valley Unit 1 in Accordance W/Procedures PY-CEI-NRR-2164, Application for Amend to License NPF-58,revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys1997-05-0202 May 1997 Application for Amend to License NPF-58,revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys PY-CEI-NRR-2165, Application for Amend to License NPF-58,revising Tech Specs Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria1997-05-0202 May 1997 Application for Amend to License NPF-58,revising Tech Specs Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria PY-CEI-NRR-2155, Application for Amend to License NPF-58,revising TS Surveillance Requirements 3.9.1.1 & 3.9.2.2,extending SR Frequency on Refueling Equipment & one-rod-out Interlocks1997-04-0909 April 1997 Application for Amend to License NPF-58,revising TS Surveillance Requirements 3.9.1.1 & 3.9.2.2,extending SR Frequency on Refueling Equipment & one-rod-out Interlocks PY-CEI-NRR-2133, Application for Amend to License NPF-58,requesting Implementation of App J,Option B,Performance-based Primary Containment Leakage Rate Testing Program for Type A,B & C Leak Rate Tests1997-01-31031 January 1997 Application for Amend to License NPF-58,requesting Implementation of App J,Option B,Performance-based Primary Containment Leakage Rate Testing Program for Type A,B & C Leak Rate Tests ML20132C7601996-12-13013 December 1996 Application for Amend to License NPF-58,authorizing Transfers of Control PY-CEI-NRR-2104, Application for Amend to License NPF-58,modifying MCPR Reactor Core Safety Limit Contained in TS 2.1.1.21996-10-24024 October 1996 Application for Amend to License NPF-58,modifying MCPR Reactor Core Safety Limit Contained in TS 2.1.1.2 ML20117E7821996-08-27027 August 1996 Application for Amend to License NPF-58,revising MSL Leakage Requirements & Eliminating MSIV Leakage Control Sys. Attachment 7 Provides Proprietary Dose Calculations. Attachment 7 Withheld PY-CEI-NRR-1999, Application for Amend to License NPF-58,revising Improved Tech Specs.Changes Either Administrative in Nature or Reflect Minor Technical Errors Discovered During Implementation Process1996-04-26026 April 1996 Application for Amend to License NPF-58,revising Improved Tech Specs.Changes Either Administrative in Nature or Reflect Minor Technical Errors Discovered During Implementation Process PY-CEI-NRR-2030, Application for Amend to License NPF-58 Re Drywell Personnel Air Lock Shield Door Analyses1996-02-27027 February 1996 Application for Amend to License NPF-58 Re Drywell Personnel Air Lock Shield Door Analyses PY-CEI-NRR-2027, Application for Amend to License NPF-58,changing TS to Reflect Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 61996-02-17017 February 1996 Application for Amend to License NPF-58,changing TS to Reflect Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6 PY-CEI-NRR-2007, Application for Amend to License NPF-58,revising TS Requirements for Drywell Leak Rate Testing1996-01-16016 January 1996 Application for Amend to License NPF-58,revising TS Requirements for Drywell Leak Rate Testing PY-CEI-NRR-2013, Application for Amend to License NPF-58,requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 9601271996-01-10010 January 1996 Application for Amend to License NPF-58,requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127 ML20095L2181995-12-28028 December 1995 Suppl Application for License Transfer of 12.58% Ownership Interest in Addition to 17.42% Approved on 951220 PY-CEI-NRR-2004, Application for Amend to License NPF-58,revising License to Reflect License Transfer for Part of Oh Edison Co Ownership Interest in Pnpp Unit 1 to Wholly Owned Subsidiary,Oes Nuclear,Inc1995-11-22022 November 1995 Application for Amend to License NPF-58,revising License to Reflect License Transfer for Part of Oh Edison Co Ownership Interest in Pnpp Unit 1 to Wholly Owned Subsidiary,Oes Nuclear,Inc PY-CEI-NRR-1978, Application for Amend to License NPF-58,requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operating1995-11-0202 November 1995 Application for Amend to License NPF-58,requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operating PY-CEI-NRR-1995, Application for Amend to License NPF-58,revising TS Requirements for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Certain Specs Related to Performing Core Alterations1995-11-0202 November 1995 Application for Amend to License NPF-58,revising TS Requirements for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Certain Specs Related to Performing Core Alterations PY-CEI-NRR-1997, Application for Amend to License NPF-58,providing Suppl Info That Revises License to Reflect Proposed Merger of Operating Companies1995-11-0101 November 1995 Application for Amend to License NPF-58,providing Suppl Info That Revises License to Reflect Proposed Merger of Operating Companies PY-CEI-NRR-1969, Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)1995-08-29029 August 1995 Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L) PY-CEI-NRR-1961, Application for Amends to Licenses NPF-58,reflecting One Time Extension of Performance Intervals for Certain TS Surveillance Requirements1995-06-30030 June 1995 Application for Amends to Licenses NPF-58,reflecting One Time Extension of Performance Intervals for Certain TS Surveillance Requirements PY-CEI-NRR-1954, Application for Amend to License NPF-58.Amend Would Allow one-time Extension of Performance Intervals for Certain Srs. Application Supplements Original Request1995-06-0909 June 1995 Application for Amend to License NPF-58.Amend Would Allow one-time Extension of Performance Intervals for Certain Srs. Application Supplements Original Request PY-CEI-NRR-1956, Application for Amend to License NPF-58,proposing Early Implementation of Control Rod Drive Scram Time Testing Consistent W/Requirements in Pnpp Improved TS LAR1995-06-0101 June 1995 Application for Amend to License NPF-58,proposing Early Implementation of Control Rod Drive Scram Time Testing Consistent W/Requirements in Pnpp Improved TS LAR PY-CEI-NRR-1944, Suppl Application for Amend to License NPF-58,App a Tss. Suppl Addresses Minor Discrepancies & Items Needing Clarification1995-05-0505 May 1995 Suppl Application for Amend to License NPF-58,App a Tss. Suppl Addresses Minor Discrepancies & Items Needing Clarification PY-CEI-NRR-1932, Application for Amend to License NPF-58.Amend Would Incorporate Results of Work Performed by BWROG Re Elimination of Selected Response Time Testing Requirements1995-05-0101 May 1995 Application for Amend to License NPF-58.Amend Would Incorporate Results of Work Performed by BWROG Re Elimination of Selected Response Time Testing Requirements PY-CEI-NRR-1934, Application for Amend to License NPF-58,proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS1995-04-28028 April 1995 Application for Amend to License NPF-58,proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS PY-CEI-NRR-1927, Application for Amend to License NPF-58 Re Removal of License Conditions for Tdi EDGs Specified by Paragraph 2.c & Defined in Attachment 2 to Operating License1995-04-28028 April 1995 Application for Amend to License NPF-58 Re Removal of License Conditions for Tdi EDGs Specified by Paragraph 2.c & Defined in Attachment 2 to Operating License 1999-09-09
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GNR PERRY NUCLEAR POWER PLANT Mad Ac$ess:
c 10 CENTER ROAD P.O. BOX 97 Michael D. Lyster PERRY. OHIO 44081 PERRY. OHIO 44D81 Vece President Woear (216)259 3737 September 19, 1990 PV-CEI/NRR-1217 L U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Technical Specification Amendment Request - Containment Airlocks Gentlemen Enclosed is a request for amendment to the Perry Nuclear Power Plant, Unit 1 Facility Operating License, NPF-58. In accordance with the requirements of 10CFR50.91(b)(1), a copy of this request for amendment has be u sent to the State of Ohio as indicated below.
This amendment requests revision of Technical Specification 3.6.1.3 Actions.
Currently, the Perry Technical Specificetions do not contain a specific Action to address an inoperable containment airlock interlock mechanism. This change request proposes to add a new Action 50 address this occurrence, and to require appropriate compensatory actions to be taken, which vill permit containment entries to be made after the compensatory measures have been accomplished. Additionally, the Action for one inoperable air lock door currently permits continued but limited access for repair of an inoperable inner airlock door, but does not allov limited access for repair of an outer door, or for other required or necessary containment entries. This change request revises the footnote to provide for these other necessary airlock entries.
If you have any questions, please feel free to call.
Sincer ly 9010020205 900919 _
POR ADOCK 05000440: #[ ., O P PNU:"
Michael D. Lys r .
MDL BSFinjc cci NRR Project Manager Sr. Resident Inspector USNRC Region III State of Ohio
,1 v , d
- Operati ng units-Clevelano Elec' ec illumsnating j [/ /
i Toledo Edisor
///
Attachment 1 !
PY-CEI/NRR-1217 L r Page 1 of 5 l
Summary The primary containment design at Perry provides two personnel airlocks, each '
consisting of two doors interlocked such that only one door may be opened at a time. The personnel access airlocks are briefly described in the Updated Safety Analysis Report (USAR) Section 3.8.2.1.4. As stated in the Technical l Specification Bases Section 3/4.6.1.3 only one closed door in each airlock is !
required to maintain the integrity of the containment. This design allows entry and exit during normal operation to perform required surveillances, maintenance, inspections, and to perform routine operational activities such ,
as chemistry sampling, reactor water cleanup system operations, and operator rounds. Vithout the ability to perform these activities the plant vould be required to shutdown. Therefore, access to the primary containment is required for continued safe plant operation. q The first of the prop; . e changes deals with adding an Action Statement for an ,
inoperable airlock into ock mechanism. Since the only purpose of the i interlock is to assure '.nat both airlock doors are not open at the same time, a broken interlock doer not directly affect the safety function of the airlock. This proposed change request is requesting a modification to Technical Specification 3/4.6.1.3. The change proposee an additional ACTION statement to describe actions required when an access airlock mechanical interlock becomes inoperable. Presently, due to the lack of an Action for an inoperable interlock, the plant is conservatively enterir.g Action b.,
declaring the airlock inoperable, and requiring the plant to be shutdown if the interlock cannot be fixed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This unnecessarily requires plant shutdown, even though the safety function of the airlock can be ,
adequately maintained. ,
This ci:ange proposes the compensatory measures to be taken if an interlock is -6 inoperable to assure at least one OPERABLE airlock door is maintained shut at all times while the interlock remains inoperable. To maintain a. level of assurance equivalent to the mechanical interlock, the proposed change requires that one operable door remains shut and locked at all times, or that an -
individual is dedicated to assuring that both airlock doors are not opened simultaneously. ;
The second portion of the proposed change deals with modifying the
As presently written this footnote permits entry through an OPERABLE outer airlock door to repair an inoperable inner airlock door. A time restriction of I hour per year was included in this footnote to limit the total time an airlock could have a door opened while its corresponding door is inoperable. i The proposed change vill maintain the one hour time restriction, but modify the footnote to also perait opening an operable inner door if an outer door is incperable, and also to permit this action for cases other than repair activities. As stated above, periodic, but important entries are required to be made through the containment airlocks. Also, Perry has already experienced two occasions when technicians vere inside the containment and were delayed i exiting due to both personnel airlocks being inoperable. In both cases, the current wording of the footnote prevented the technician frot opening the i inner airlock door for his exit due to the outer docr in the airlock being .
l considered " inoperable." These two occasions are documented in LER 88-032, l
e-.
4 Attachment 1 PY-CEI/NRR-1217 L Page 2 of 5 and LER 90-007. To address situations such as these, the footnote has been .
changed to permit opening of either airlock door when the associated airlock !
door is inoperable and to identify those types of activities for which the !
limited access through an airlock with an inoperable airlock door is
- permitted. The one hour per year time limit vill remain.
Finally, the Bases are being revised to discuss use of the airlocks when an airlock door or an interlock mechanism is inoperable. ,
Safety Analysis ;
There are two personnel airlocks providing access into the primary containment at Perty. Each of the airlocks employs a dual door design, which permits personnel access through the airlock, while always maintaining containment
- integrity by having one of the two doors closed. As stated above, only one of :
the two doors is required to be closed to maintain containment integrity. t During normal airlock operation a mechanical interlock operates to physically i prevent both doors from being opened at the same time. As long as compensatory actions are taken to assure that both doors are not opened '
simultaneously, the interlock could be inoperable without any decrease in safety. The proposed Action statements provide this assurance. Proposed i Action b.1 assures that at least one OPERABLE airlock door is maintained closed. This gives the operators assurance that the airlock is OPERABLE and i ' least one of the airlock doors is closed.
Actions b.1 and b.2 provide added assurance that at least one OPERABLE door will remain closed by either locking closed one of the OPERABLE airlock doors, or, as provided by the footnote ** by stationing an individual dedicated to ;
assuring that only one airlock door is open at any time. This option of stationing an individual is necessary to the design of the Perry Nuclear Power Plant. Frequent entries into Primary Containment are necessary during normal t plant operation. As briefly discussed in the summary, there are numerous activities such as surveillances, maintenance, inspections, operator rounds, sampling, and operational system manipulations that are required to be ;
performed inside the primary containment. Without these activities being ,
performed, the facility would be required to be shutdown, resulting in unnecessary cycling of plant systems. Although personnel access could be performed while maintaining one of the airlock doors locked at all times, the safety of the personnel involved would at times be compromised by the locked doors, such that they may not be able to exit Primary containment during an accident, or other personnel may not be able to enter Primary Containment to aid injured workers, depending on which side of the door the lock vas placed <
on. For this reason the option of stationing a dedicated individual at the airlock to assure that one airlock door is closed at all times (without the need to place a lock on a door at the same time that the individual is stationed) is required. ,
As stated in the Techr.ical Specification Bases Section 3/4.6.1.3 only one door is required to be closed in each airlock to maintain primary containment integrity. The proposed compensatory actions for an inoperable interlock mechanism gives assurance that the containment integrity vill be maintained,
Attachment 1 PY-CEI/NRR-1217 L ,
Page 3 of 5 and thus there is no decrease in safety due to this proposal. By establishing a separate Action for an inoperable interlock mechanism the facility vill no longer be required to declare the entire airlock inoperable due to e ,
inoperable interlock mechanism. Presently, the plant conservatively declares ;
the airlock inoperable any time an interlock mechanism is inoperable. By the present Action b. a plant shutdown is required if the interlock niechanism cannot be made OPERABLE vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. It is felt that this action is a l detriment to plant safety, since it puts the plant and its systems through a shutdown cycle even though the safety function of the airlock can be ,
adequately assured. The Bases have been revised to add a brief discussion of l the use of the airlock during the period when an interlock mechanism is inoperable.
The second portion of this change involves modification of the current * ,
footnote. The revision to the
- footnote vill increase plant safety. The footnote as written permits entry through an OPERABLE outer airlock door to repair an inoperable inner airlock door. The footnote establishes a cumulative time limit of I hour per year for this condition to exist. As '
written, this footnote is overly restrictive and hampers personnel and plant safety, and also may prevent repairs to an inoperable outer door. 5 First, personnel safety may be hampered by the existing footnote. As discussed in the summary above, twice plant personnel have been inside containment performing required evolutions when the out6r airlock door became inoperable, preventing their exit from containment without violating the Technical Specifications (in both cases the other airlock was also inoperable, ;
' leaving no exit pathway from the containment due to the vording of the footnote). This delayed the personnel exits, and under emergency situations could result in personnel injury, or delaying emergency response personnel in aiding an injured person inside containment.
Secondly, the footnote as written could also prevent personnel from responding
- to an alarm or-condition inside containment which has the potential to affect plant safety. For example, the control-rod drive scram accumulators are located inside containment and are monitored by a control room annunciator for ,
pressure, and for water leakage on the nitrogen side of the accumulator. If this control room alarm is received an operator is sent into containment to ,
recharge or drain the alarming accumulator as appropriate. Without access to ,
the containment this operation could not be completed and the accumulator in question may degrade to the point where it may have an adverse effect on the control rods scram time. Therefore, entry into containment under this condition is considered the appropriate action.
Third, the outer door may malfunction in such a way that the only way to repair the outer door is to gain accere through the inner door to the inside of the airlock. For instance the outer door linkage may be jammed on the inside such that it vill not open. Repair parsonnel vould then be required to gain access to containment through the other airlock, then gain access to the airlock with the jammed outer door by using the OPERABLE inner door. As currently written, the footnot- vould not permit this operation.
s
k Attachment 1 i PY-CEI/NRR-1217 L '
Page 4 of 5 t
The revised footnote vill permit access to and from the containment and to an ;
inoperable outer airlock door without changing the time restrictions of the present footnote. The present footnote permits use of an VPERABLE door on an '
airlock with the corresponding door inoperable for a cumulative period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per year. The proposed footnote maintains this restriction. The only '
change is to permit the OPERABLE door to be either the inner or outer door. '
As noted within the proposed footnote and the Bases, access through an operable airlock door is limited to certain types of activities repair of the i inoperable door; personnel safety and required operational / maintenance /sur-veillance activities necessary to ensure safe plant operations.
Significant Hazards Analysis The standards used to arrive at a determination that a request for amendment requires no significant hazards consideration are included in the Commission's .
Regulations, 10 CFR 50.92, which state that the operation of the facility in I accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previousif evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. CEI has reviewed the proposed change with respect to these three factors.
This change doe = act involve a significant increase in the probability or consequences or an accident previously evaluated.
The probability of occurrence of a previously evaluated accident is not increased because the containment airlocks do not affect the initiation of any accident. Therefore this change to add action requirements for an inoperable airlock interlock mechanism and to revise the wording of the footnote addressing use of the operable airlock door can not increase the probability of an accident previously evaluated. ;
The consequences of an accident remain bounded by conditions which exist prior to this change, s uce operation under the provisions of the proposed changes to the airlock Actions does not produce potential containment leakage paths beyond the currently approved Technical Specifications. For the inoperable airlock interlock mechanism, at least one OPERABLE airlock door vill be maintained closed at all times thus meeting the requirements for the airlock doors. In the case of having one airlock door inoperable, the OPERABLE door on that airlock cannot be used for more than I hour per year which is the same restriction in place under the existing Technical Specification. In approving the current restriction, the NRC previously evaluated the potential for an event :
requiring primary containment integrity occurring during the limited time when an airlock door is inoperable and its associated operable door is open, and determined that it is suf ficiently remote to justify limited av:ess when required. This change maintains the same cumulative time limit for these entries but revises the restrictions on the circumstances required to exist to allow entry. Therefore, the changes addressing the interlock mechanism and the current footnote cannot increase the consequences of any accident previously evaluated by the NRC.
. i
\
i; Attachment 1 PY-CEI/NRR-1217 L l Page 5 of 5 ;
This proposed change does not create the possibility of a new or different !
kind of accident from any previously evaluated.
Containment airlocks are designed and assumed to be used for entry and ,
exit. Their operation does not interface with the reactor coolant pressure boundary or any other machanical or electrical controls which '
could impact the operations of the reactor or its direct support systems.
Therefore a new or different accident cannot be created. As discussed above the integrity of the containment is maintained as long as at least one OPERABLE airlock door is closed. The proposed change to the airlock '
door interlock mechanism does not change the requirement to have at least one OPERABLE door closed at all times. Instead it assures that this is in fact still occurring by locking one door closed, or by stationing an individual dedicated to assuring that one OPERABLE door is always closed.
As such this proposed change does not create the possibility of a new or !
different type of accident. Likevise, the proposed change to the
- 1 footnote does not create the possibility of a new or different kind of accident, since the conditions of the containment and its airlock.
remains unchanged and the actual operating mode and procedures for the airlock are unsfiected by these Technical Specification changes. ;
The proposed change does not involve a significant reduction in the margin of safety.
The applicable margin of safety consists of maintaining the primary containment leak rates within the assumptions of the design' basis accident analysis. Vith regard to the containment airlocks, these leak rates are maintained provided at least one operable airlock door remains closed during the event. The period of time that an airlock could have no operable door closed was previously limited to "a cumulative time not i to exceed I hour per year." This time remains unchanged, therefore the margin of safety is not reduced.
Vith an inoperable interlock, the proposed action vill still maintain at least one operable airlock door closed at all times. Therefore, the assumed margin of safety is not reduced.
Environmental Consideration The Cleveland Electric Illuminating Company has reviewed the proposed Technical Specification change against the criteria of 10 CFR 51.22 for environmental considerations. As shown above, the proposed change does not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, CEI concludes that the proposed Technical Specification change meets the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion l from the requirement for an Environmental Impact Statement.
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