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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-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 PY-CEI-NRR-1655, Application for Amend to License NPF-58,adding New Programmatic Requirements Governing Radiological Effluents Into Administrative Controls Section of TS & Relocating Procedural Details of RETS to ODCM or Pcp,Per GL 89-011995-04-0303 April 1995 Application for Amend to License NPF-58,adding New Programmatic Requirements Governing Radiological Effluents Into Administrative Controls Section of TS & Relocating Procedural Details of RETS to ODCM or Pcp,Per GL 89-01 PY-CEI-NRR-1890, Application for Amend to License NPF-58 Re one-time Extension of Performance Intervals for Certain TS Surveillance Requirements1995-03-24024 March 1995 Application for Amend to License NPF-58 Re one-time Extension of Performance Intervals for Certain TS Surveillance Requirements 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-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 PY-CEI-NRR-1655, Application for Amend to License NPF-58,adding New Programmatic Requirements Governing Radiological Effluents Into Administrative Controls Section of TS & Relocating Procedural Details of RETS to ODCM or Pcp,Per GL 89-011995-04-0303 April 1995 Application for Amend to License NPF-58,adding New Programmatic Requirements Governing Radiological Effluents Into Administrative Controls Section of TS & Relocating Procedural Details of RETS to ODCM or Pcp,Per GL 89-01 PY-CEI-NRR-1890, Application for Amend to License NPF-58 Re one-time Extension of Performance Intervals for Certain TS Surveillance Requirements1995-03-24024 March 1995 Application for Amend to License NPF-58 Re one-time Extension of Performance Intervals for Certain TS Surveillance Requirements 1999-09-09
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THE-CLEVELAND ELECTRIC ILLUMINATING COMPANY P.O. BOX 97 5 PERRY, OHIO 44001 5 TELEPHONE (216) 259-3737 5 ADDRESS-10 CENTER FDAD FROM CLEVELAND; 479 1260 5 TELEX: 241599 ANSWERsACK: CEIPRYO At Kaplan Serving The Best Location in the Nation PERRY NUCLEAR POWER PLANT Q,$'[,, March 16, 1990 PY-CEI/NRR-1140 L U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Technical Specification Change Request-Performance of Containment Isolation Valve Testing With Primary Containment Integrity-Shutdown Centlemen:
Tne Cleveland Electric Illuminating Company (CEI) hereby requests 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 been sent to the State of Ohio as indicated below.
This application is filed to revise the Primary Containment Integrity-Shutdown Technical Specification (LCO 3.6.1.1.2) to provide limited flexibility during the performance of 10CFR50 Appendix J Type C leak rate testing of containment
. isolation valves. Attachment 1 to this letter provides the Summary, Safety Analysis, Significant Hazards and Environmental Impact Considerations.
Attachment 2 provides the proposed changes to the Technical Specifications.
In order to permit potential critical path LLRT's to be performed during periods requiring containment integrity during the upcoming second refueling outage, it is requested that this amendment be processed prior to the start of the outage, presently scheduled for, September 7, 1990.
Should you have any questions, please feel free to call.
Very tru y oure G J, 9003210283 900316 Al kap 1 an PDR ADOCK 05000440 P PDC Vice President Nuclear Group AK:njc Attachments cc: T. Colburn P. Hiland USNRC Region III i J. Harris (State of Ohio) ;
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- . Attcchr nt 1 PY-CEI/NRR-1140 L Page 1 of 8 Summary on March 31, 1989 the NRC issued Amendment No. 19 to Facility Operating License No. SPF-58 for the Perry Nuclear Power Plant. The approved amendment revised the Technical Specification for Primary Containment Integrity-Shutdown. ,It allowed the perfotmance of containment isolation valve Type C local leak rate tests with 3/4 inch vent and drain lines open on certain penetrations that vould otherwise not be testable when the specification is applicable (such as during refueling activities). This amendment was approved for the first refueling outage only. The Safety Evaluation accompanying the approved amendment indicated that final acceptance of a permanent change to the Technical Specifications was contingent upon a favorable review by the staff of the original analysis without reliance on a 15 day decay period used by the staff in the interim approval. CEI has performed analyses which demonstrate that as many penetrations as desired could remain open provided there is a seven day delay betvoen plant shutdown and starting the local leak rate tests. This seven day period provides for significant decay of the source term contained in the fuel. Based on this analysis, CEI is requesting that the Technical Specification be changed to permit the performance of Type C local leak rate tests with as many as six (6) open vent / drain line pathways as long as the facility has been suberitical for 7 days or more. The analyses in this submittal supercede the previously submitted analyses in the December 29, 196d letter.
Safety Analysis i The Type C local leak rate tescs specified in 10CFR50 Appendix J require that >
l the containment isolation valves be tested by pressurization with air or nitrogen at the calculated peak containment' internal pressure resulting from ,
the design basis accident (11.31 psig). In the original Technical l
Specification for Primary Containment Integrity-Shutdown, many of the local leak rate testa could not be conducted during refueling activities since ,
primary containment integrity would not be maintained during depressurizing/
draining of the test volume in prepL ation for testing, and during system restoration. In our letter dated December. 29, 1988 ve included a typical simplified piping arrangement and a description of the sequence of events for the testing of tne containment isolation valves. The December 29, 1988 letter assumed only 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of decay time, and requested that the Technical Specifications be revised to permit opening of up to two vent and/or drain line pathways (3/4 inch diameter each) while Primary Containment Integrity-Shutdovn was required. Based on our analysis at that time we also stipulated that primary to' secondary containment differential pressure had to be verified
- within the limits of Technical Specification 3.6.1.6 whenever 1 or 2 vent / drain line pathways were open.
y . Attach =nt 1 PY-CEI/NRR-1140 L Page 2 of 8 The NRC staff reviewed our request and performed an independent calculation based on our submittal and concluded that it was acceptable to change the Technical Specifications as requested with the following stipulations: :,
- 1. The' staff assumed a decay period of 15 days versus the 1 day assumed in our submittal since the plant had already been shutdown for 15 days at that point in the staff review. :
- 2. The Amendment was only approved for the first refueling outage. The NRC staff indicated in the Safety Evaluation Report which accompanied the Amendment that they would have to review the issue ,
in more detail to revise the specification permanently.
Based on the above, CEI has completed further analyses in order to support ,
this request to make the change permanent. The new analyses used the following assumptions:
- 1. A decay period of 7 days (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) suberiticality was assumed.
This decay period was selected since it provides for significant decay of the source term contained in the fuel. Realistic scheduling'shows that at least six days would be cequired after entering Mode 3 before primary containment integrity would be needed
- to support fuel handling activites, and the seventh day was added to ensure that offsite dose consequences from a postulated fuel handling accident vould remain vithin the NRC SRP acceptance critera. This seven day time period is considered acceptable by CEI for support of outage LLRT activities.
- 2. All the airborne activity existing inside of the containment after-the accident is assumed to be immediately discharged'to the environment. This highly conservative analysis assumes that there 7
is no containment barrier, no dilution prior to the release and no l' filtering done.by any ventilation system.
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- 3. The radiological analysis utilized the PNPP short term (accident) dilution factors (X/0) provided in USAR Table 2.3-24 for the ,
Exclusion Area Boundary (EAB) and the Lov Population Zone (LPZ) l based on seven site years. 1
- 4. All other assumptions and input parameters are provided in Table 1 to this letter. These other assumptions are consistent with those l used in USAR Section 15.7.6. This USAR analysis had previously been ;
reviewed by the NRC staff in the Perry Safety Evaluation Report !
(NUREG-0887) dated May 1982 and found consistent with the l requirements of Regulatory Guide 1.25 and the procedures.specified in the SRP Section 15.7.4. This was restated in the Safety
- Evaluation which accompanied the Amendment 19 approval letter dated March 31, 1989. Table 2 to this letter provides the values of (
radiological activity released into the containment and then !
directly to the environment.
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- - Attachmsnt 1 PY-CEI/NRR-1140 L Page 3 of 8 Using the above-assumptions, the dose was calculated for both the Exclusion Area Boundary and the Low Population Zone. Table 3 shows the results of these calcul ations, for both the Design Basis case and the Realistic case values.
As shown by the Table, this conservative analysis indicates that the calculated values are all within the guidelines of the SRP Section 15.7.4.
The SRP states that the calculated values should be no more than 25 percent of the 10 CFR 100 limits of 300 rem to the thyroid and 25 rem whole body at the EAB and LPZ. This then limits the doses to 75 rem to the thyroid and 6 rem to the whole body. Table 3 shows that all calculated values are within these SRP acceptance criteria even with the highly conservative assumptions made in the calculation.
The above analysis is conservative for several reasons. First the analysis assumes no containment. The analysis demonstrates that it vould be acceptable to.have no containment integrity for the fuel handling accident after being shutdown for 7 days. _However, in the proposed Technical Specification CEI has limited the number of open vent and drain pathways to the six. 'This was done in response to known NRC concerns over administrative controls on the closing of these vent / drain pathways in the event of an accident, and to ensure that the calculated doses vould not be exceeded. When utilizing the proposed change, at no time during the testing process are the containment isolation valves disabled, and therefore, the containment isolation function provided by the valves vould remain available if called upon to close. Additionally, administrative controls vill be established in order to ensure that the number of 3/4 inch vent and drain pathways opened at any one time vill be limited to
- 6. These controls vill include assuring that the control room operators are aware of how many pathways may be opened by the LLRT teams at any one time, and vill stipulate that the test engineers make reasonable attempts to isolate vent / drain lines prior to-evacuating if evacuation is announced over the PA system. Thus,--the containment system vill remain intact.
The analysis also does not assume any credit for ventilation filters and no decay of the isotopes following the accident. As described in our December 29, 1988 submittal, the Containment Vessel and Dryvell Purge System would typically isolate on high radiation following the accident. In the original submittal, it was conservatively estimated that this vould occur 20 seconds after the accident. However, using the new analysis assumptions that all the airborne activity is immediately discharged to the environment, no credit is taken for this isolation or for the charcoal and HEPA filters which this system contains.
The new analysis takes no credit for mixing. This analysis assumed that the air directly over the pool is immediately exhausted to the atmosphere. In reality, substantial mixing would take place with the containment atmosphere which would dilute the discharge to the environment, and greatly reduce the EAB doses.
I
., . - Attachm:nt 1 PY-CEI/NRR-1140 L Page 4 of 8-Based on the above, the analysis is conservative and within the limits described by the SRP and 10 CFR 100 guidelines, and the additional restrictions placed on the number of open vent and drain pathways is conservative.
Significant Hazards Consideration In accordance with the requirements of 10 CFR 50.92, the following discussion ;
is provided in support of the determination that no significant hazards are involved with the changes proposed in this amendment request.
- 1. No significant increase in the probability or consequences of an accident previously evaluated results from the proposed changes because Having up to 6 vent and drain pathways does not increase the probability of any accident previously evaluated. As discussed above, the accident of concern is the fuel handling accident inside containment. Having vent and drain valves open does not increase the probability of this accident occurring. -The proposed change also does not increase the consequences of this accident since as described above, the new analysis performed shows that the doses at both the EAB and LPZ are within the guidelines of SRP 15.7.4 and well within the requirements of 10 CFR 100. Therefore the consequences of the accident are not increased and the proposed i
action vould result in no significant radiological environmental impact.
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- 2. The proposed change vill not create the possibility of a new or different kind of accident than previously evaluated because:
The initiating event and event sequence remain unchanged. The initiating event is the dropping of a channeled fuel assembly onto the core as a result of the failure of the fuel assembly lifting i mechanism. The number of fuel rods damaged as a result of this event (124) were conservatively calculated using the methodology
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provided in USAR Sections 15.7.4 and 15.7.6, and are unchanged by the proposed amendment. The only change.resulting from the proposed amendment is the evaluation of the consequences of the postulated l
event inside primary containment. Additionally, the proposed change I does not alter the plant design or functional capability and does not introduce any new operating modes, only new potential pathways.
l As a result, the proposed amendment does not create the possibility of a new or different kind of accident than previously evaluated.
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- 3. The proposed change does not involve a significant reduction in the margin of safety because:
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. . Attachm2nt 1 PY-CEI/NRR-1140 L Page 5 of 8 The margin of safety is provided by maintaining the offsite dose consequences of a postulated fuel handling accident well within the exposure guidelines of 10 CFR 100. As stated above the Standard Review Plan (SRP) Section 15.7.4 provides additional guidance by defining "vell within" as 25 percent or less of the 10 CFR 100 guidelines.
Application of this recommer.dation vould result in a limit of 75 rem.
for the' thyroid and 6 rem for the whole body at the Exclusion Area Boundary (EAB). The margin of safety is provided by the difference between the exposure guidelines in the SRP Section 15.7.4 and the 10 CFR 100 limits of 300 rem to the thyroid and.25 rem to the whole body at the EAB. As shown in Table 3, the calculated doses based on the new analyses is 45.6 rem for the thyroid and 0.114 rem for the-whole body at the EAB. Doses for the Low Population Zone (LPZ) were also calculated and determined to be 5.09 rem thyroid and 0.0127 rem whole body. Since these offsite doses are below the exposure guideline values provided in SRP 15.7.4 and 10 CFR 100, the existing margin of safety has been maintained.
Based on the above considerations, the proposed change does not significantly increase the probability or the consequences of a previously evaluated accident, does not create the possibility of-a new or different kind of accident from any previously evaluated, and does not involve a significant reduction in the margin of safety. Therefore, the Cleveland Electric Illuminating Company proposes that no significant hazards are involved.
Environmental Impact Consideration 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 changed does not involve a significant hazards consideration, nor significantly increase the types and amounts of effluents 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 from the requirement for an Environmental Impact Statement. The NRC staff arrived at the same conclusion regarding an environmental impact statement for the interim approval given in Amendment 19.
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Attachtsnt 1 PY-CEI/NRR-1140 L ,
Page 6 of 8 TABLE 1 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT PARAMETERS TABULATED FOR POSTULATED ACCIDENT ANALYSIS Design Basis Realistic Assumptions Assumptions I. Data and assumptions used to estimate radioactive sources from postulated accident.
A. Power level 3758 MVt Same B. Burnup 1,000 days Same C. Radial peaking factor 1.5 Same D. Fuel damage 124 rods Same E. Release of activity by nuclide 10% iodine 0.32% iodine 30% Kr-85 1.80% Kr-85 10% other 1.80% other noble gases noble gases F. Radionuclide decay time 168 hrs. Same (7 days)
G. Iodine gap activity species ,
- 1. Organic 0.25% Same
- 2. Inorganic 99.75% Same H. Minimum vater coverage above 23 ft. Same damaged fuel rods I. Pool decontamination factors:
- 1. Organic iodine 1 Same
- 2. Inorganic iodine 133 Same
- 3. Noble gases 1 Same J. Activity Airborne in Containment Table 2 Table 2 II. Data and assumptions used to estimate activity released A. Release pathway Instantaneous Same unfiltered exhaust direct to the environment B. All other pertinent data and Reg. Guide Same assumptions 1.25 III. Dispersion Data (USAR Table 2.3-24)
A. Exclusion Area Boundary 4.3xig-4 Same (863 meters) sec/m B. Lov Population Zone 4.8x1g-5 Same (4002 meters) sec/m IV. Dose Data A. Method of dose calculation Reg. Guide Same 1.25 B. Dose conversion assumptions Reg. Guide Same 1.25 C. Doses Table 3 Table 3
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PY-CEI/NRR-1140 L Page 7 of 8 ,
TABLE 2.
FUEL HANDLING ACCIDENT INSIDE CONTAINMENT ACTIVITY AIRBORNE IN THE CONTAINNElff BUILDING AND. '
RELEASED TO THE ENVIRONMENT (CURIES)
, . Isotope Activity Design Realistic I-131 2.05E+2 1.68E+1 132 *
134 *
! Kr-83M *
- 85M 7.54E-8 4.16E-9 85 8.95E+2 6.00E+2
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87 *
- i l: Xe-131M 1.82E+2 4.67E+1 L
133M 1.35E+3 1.35E+2 133 2.52E+4 4.20E+3 135H' *
- 135- 2.69E-1 .5.59E-2 137 *
- Indicates isotope activity is less than E-10 curies. (i.e. dose contribution is insignificant when compared to the other isotopes).
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.,- - Attcchnsnt 1 PY-CEI/NRR-1140 L Page 8 of 8 TABLE 3 FUEL HANDLINC ACCIDENT INSIDE CONTAINMENT
~ RADIOLOGICAL EFFECTS Design Basis Values- Realistic Values Whole Body Inhalation Whole Body Inhalation Dose (rem) Dose (rem) Dose (rem) Dose (rem)*
Exclusion Area 1.14E-1 4.56 E+1 1.81E-2 3.73E+0 (863 meters)
Lov Population Zone 1~.27E-2 5.09E+0 2.03E-3 4.16E-1 !
(4,002 meters) l l
- These values are'over-estimated by a factor of from 10 to 106since an iodine partitignfactgrof100wasutilizedforconservatismratherthanavalueof from 10 to 10 as have been experimentally determined.
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