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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems ML20095L0231995-12-22022 December 1995 Proposed Improved TS & Bases,Allowing Flexibility to Install Main Stack Rms (Mod 5386) W/O Need for Addl Licensing Actions & Addressing Annotations to Reflect pre- & post-mod Scenarios,Respectively ML20095J1321995-12-21021 December 1995 Proposed Tech Specs,Consisting of Change Request 95-08, Eliminating Outdated Matl from FOLs & Making FOL for Unit 2, Consistent W/Fol for Unit 3 ML20095J7011995-12-19019 December 1995 Proposed Tech Specs Re Administrative Change to Ventilation Filter Testing Program ML20095A1731995-11-30030 November 1995 Proposed Tech Specs,Changing Minimum Allowable Control Rod Scram Accumulator Pressure & Charging Water Header Pressure from Value of 955 Psig to Value of 940 Psig ML20094R2971995-11-22022 November 1995 Revised,Proposed TS Pages 147,157 & 158 Re Early Implementation of Improved TS Section 3.4.3 ML20094Q6801995-11-21021 November 1995 Proposed Tech Specs Re SR for High Pressure Test of HPCI & B 3.5-14 & B 3.5-28.Administrative Change Proposed to Eliminate Ref to Section Previously Eliminated ML20092A2141995-09-0101 September 1995 Proposed Tech Specs,Consisting of Change Request 95-07, Deleting License Condition 2.C ML20092A2841995-08-30030 August 1995 Proposed Tech Specs,Requesting Enforcement Discretion from Portion of FOL Condition 2.C ML20092B9871995-08-28028 August 1995 Proposed Improved Tech Specs ML20087E8881995-08-0404 August 1995 Proposed Tech Specs Re Implementation of New SR Associated W/Conversion to TS 1999-09-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
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ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 Docket No. 50-277 Ucense No. DPR-44 TECHNICAL SPECIFICATION CHANGE REQUEST No. 94-05 Ust of Attached Pages Unit 2 167 l
l 9405250228 940513 PDR ADOCK 05000277 PDR P
F T
Unit 2 PBAPS
. LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment (Cont'd. ) 4.7.A Primary Containment (Cont'd.)
L ,= measured ILR at 25 g
psig (P g)
L, = measured ILR at 49.1 p s i g ( P ,) , and L**
$ 0.7, otherwise La L, = La (P,/P,) V2 where !
La = 0.5 percent of the primary containment volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49.1 psig P, = peak accident pressure (psig)
P, = appropriately measured test pressures (psig)-
- c. The ILRT's shall be performed at the following minimum frequency:
- 1. Prior to initial unit operation.
- 2. After the preoperational leakage rate tests, a set of three Type A tests shall be performed at approximately equal intervals during each 10 year service period.*
These intervals may be extended up to eight months if necessary to coincide with re-fueling outage.
- d. The allowable leakage rates, L,,and L,, shall be less than 0. 75 L, and 0.75. L, for the reduced. pressure tests and peak pressure tests, respectively.
- Except for PBAPS Unit 2, refueling outage'10.
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ATTACHMENT 3 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 Docket No. 50-277 Ucense No. DPR-44 EXEMPTION REQUEST Supporting Information: 5 Pages I
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Docket No. 50-277 Ucense No. DPR-44 l Exemption Reauest An exemption from 10 CFR 50, Appendix J, section Ill.D.1.(a) is necessary due to a difference between the PBAPS, Unit 2 second Appendix J 10-year service period and the second 10-year plant inservice inspection interval.
10 CFR 50.54(o) requires that the primary reactor containments for water cooled power reactors shall be subject to the requirements set forth in 10 CFR 50, Appendix J. Section ,
Ill.D.1.(a) of 10 CFR 50, Appendix J states, "After the preoperational leakage rate tests, a set of three Type A tests shall be performed, at approximately equal intervals during each 10-year service period. The third test of each set shall be conducted when the plant is shutdown for the 10-year plant inservice inspections."
The difference between the 10-year plant inservice inspection interval and the 10 CFR 50, Appendix J 10-year service period is the result of a revision to the length of the second 10- i year plant inservice inspection interval dates which was discussed in a letter from G. J.
Beck (PECO Energy Company) to USNRC, dated February 25,1991. Our February 25, 1991 letter established the revised second 10-year plant inservice inspection interval dates as September 19,1986 to November 4,1997. Therefore, we are proposing to re-align the 1 Type A test service period with the 10-year inservice inspection interval by requesting an exemption to 10 CFR 50, Appendix J to extend the interval between the second and third Type A test by 24 months (i.e., the interval would be 66 months) and to extend the Appendix J 10-year service period.
The 10 CFR 50, Appendix J, requirement that the Type A tests be performed at approximately equalintervals would require the performance of a Type A test during the upcoming PBAPS, Unit 2 refueling outage 10 scheduled to begin September, 1994. 10 l CFR 50, Appendix J, also requires that the third Type A test during the 10-year service period be conducted when the plant is shutdown for the 10-year plant inservice inspections. This would require the performance of another Type A test during the PBAPS, Unit 2 refueling outage 11 that is scheduled to begin in September,1996, since this refueling outage 11 comes at the end of the 10-year inservice inspection interval. In order to avoid performing two consecutive Type A tests, PECO Energy Company is requesting a schedular exemption that would extend the PBAPS, Unit 2 Type A test interval such that the interval is not "approximately equal" to the first two Type A test intervals. This schedular exemption includes extending the Appendix J 10-year service period.
Performing the Type A test during two consecutive refueling outages to comply with 10 I CFR 50, Appendix J would result in an unnecessary increase in personnel radiation exposure and increased cost by unnecessarily increasing the length of one of the affected refueling outages. 5 1
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Docket No. 50-277 Ucense No. DPR-44 Justification for the Exemptl0D We are requesting a one-time (i.e., temporary) schedular exemption from 10 CFR 50, Appendix J, section Ill.D.1.(a) which establishes the periodic test schedule for Type A tests (i.e., Containment Integrated Leakage Rate Test (CILRT)), specifically, the 10 CFR 50, Appendix J requirement that three Type A tests be performed at approximately equal intervals during the 10-year service period.
The purpose of this requirement is to determine that the total leakage from primary containment does not exceed the maximum allowable leakage rate, La, as specified in the PBAPS, Units 2 and 3 Facility Operating Ucense. This primary containment maximum allowable leakage rate provides an input assumption to the calculation required to ensure that the maximum potential offsite dose during a design basis accident does not result in a dose in excess of that specified in 10 CFR 100.
A review of activity-based failure mechanisms has determined that the potential from degradation due to activity based mechanisms is minimal.
Regarding the potential for primary containment degradation due to a time-based mechanism, we have concluded that the PBAPS Local Leak Rate Test (LLRT) program would identify most types of penetration leakage. The LLRT program involves measurement of leakage from Type B and Type C primary containment penetrations as defined in 10 CFR 50, Appendix J.
The 10 CFR 50, Appendix J, Type B tests are intended to detect local leaks and to measure leakage across pressure containing or leakage-limiting boundaries other than valves, such as containment penetrations incorporating resilient seals, gaskets, expansion bellows, flexible seal assemblies, door operating mechanism penetrations that are part of the containment system, doors, and hatches.10 CFR 50, Appendix J, Type C testing is intended to measure reactor system primary conta'nment isolation valve leakage rates.
The frequency of the Type B and Type C testing is not being alter 6tf by the proposed TS change. The acceptance criterion for Type B and Type C leakage is 0.6 La (i.e.,0.3 %
wt/ day) which, when compared to the Type A test acceptance criterion of 0.75 La (i.e.,
0.375 % wt/ day), is a significant portion of the Type A test allowable leakage.
Finally, a review of previous PBAPS, Unit 2 CILRT results concluded that the only failure mechanism which has been detected during the past CILRTs is activity-based and that there is no indication of time based failures that would not be identified during the performance of Type B and Type C tests. Therefore, we have concluded that the proposed extended test interval would not result in a non-detectable PBAPS, Unit 2 l primary containment leakage rate in exce i of the allowable value (i.e.,0.5% wt/ day) l established by the TS and 10CFR50, App. dix J. '
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Docket No. 50-277
_, cense No. DPR-44 Based on the above technical justification, we request a one-time exemption of the requirements of 10 CFR 50, Appendix J, section Ill.D.1.(a), in accordance with two of the criteria of 10 CFR 50.12.
The NRC may, upon application, grant exemptions from the requirements of 10 CFR 50, where special circumstances are present.10 CFR 50.12(a)(2)(ii) defines such a circumstance where, " Application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule..." The underlying purpose of 10 CFR 50, Appendix J, section Ill.D.1.(a) is to establish and maintain a level of confidence that any primary containment leakage, during a hypothetical design basis accident, will remain less than or equal to the maximum allowable value, La, established by 10 CFR 50, Appendix J, by performing periodic Type A testing. Compliance with 10 CFR 50, Appendix J would require PECO Energy Company to perform a Type A test during two consecutive refueling outages at PBAPS, Unit 2. This is not necessary to achieve the underlying purpose of the rule, as explained in the above technical justification. The technical justification supports the conclusion that the requested schedular exemption to extend the PBAPS, Unit 2 third Type A test by 24 months will maintain the same level of confidence that any PBAPS, Unit 2 primary containment leakage will remain less than or equal to the maximum allowable leakage rate value, La, during the proposed one-time extension.
10 CFR 50.12(a)(2)(iii) states the NRC may grant exemptions from requirements of 10 CFR 50 where, " Compliance would result in undue hardship or other costs that are significantly in excess of those contemplated when the regulation was adopted, or that are significantly in excess of those incurred by others similarly situated..." The current PBAPS, Unit 2 Type A test schedule established by 10 CFR 50, Appendix J, section Ill.D.1.(a) will require that the Type A test be performed during two consecutive PBAPS, Unit 2 refueling outages.
This current test schedule will result in unnecessary additional personnel radiation exposure in order to perform the test and unnecessary costs assoc:ated with an increase in the refueling outage length of two days.
Information Supporting an Environmental Assessmept With respect to the requested exemption for PBAPS, Unit 2, the following information is provided to support an Environmental Assessment.
Identification of Proposed Action The proposed action is to grant an exemption from 10 CFR 50, Appendix J, section Ill.D.1.(a) which requires a set of three Type A tests (i.e., Containment Integrated Leakage Rate Test (CILRT)) to be performed at approximately equal intervals during each 10-year service period and specifies that the third test of each set shall be conducted when the plant is shutdown for the performance of the 10-year plant inservice inspection. This one-
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Docket No. 50-277 Ucense No. DPR-44 time exemption would allow the third, PBAPS, Unit 2 Type A test to be performed during PBAPS, Unit 2 refueling outage 11 scheduled to begin in September,1996, approximately 66 months after the last PBAPS, Unit 2 CILRT test, thereby coinciding with the 10-year plant inservice inspection refueling outage. Furthermore, this one-time exemption would i result in the third Type A tcst not being peiformed at an interval approximately equal to previous intervals during the 10-year service period, and the Appendix J 10-year service period would be extended. Without the exemption, the PBAPS, Unit 2 third Type A test would be required to be performed during the PBAPS, Unit 2 refueling outage 10 scheduled to start September,1994, and during the PBAPS, Unit 2 refueling outage 11, scheduled to begin in September,1996, to coincide with the 10-yr inservice inspection l refueling outage.
The Need for the Proposed Action The requested exemption is needed because the requirements of 10 CFR 50, Appendix J, and the current PBAPS, Unit 2 refueling outage schedule would require that the 10 CFR 50, Appendix J, Type A test be performed during two consecutive refueling outages.
There is a difference between the 10 CFR 50, Appendix J 10-year service period and the 10-year plant inservice inspection interval for PBAPS, Unit 2. Without this exemption, the 10 CFR 50, Appendix J, Type A test would be required to be performed during the PBAPS, Unit 2 refueling outage 10 scheduled to begin in September,1994, at an interval approximately equal to the previous PBAPS, Unit 2 Type A test intervals and during the PBAPS, Unit 2 refueling outage 11 scheduled to begin September,1996, in order to coincide with the second 10-year inservice inspection refueling outage.
Environmental Impacts of the Proposed Action The requested exemption would not significantly increase the probability of exceeding the maximum allowable value of expected primary containment leakage (i.e., La, established by 10 CFR 50, Appendix J), during a hypothetical design basis accident, therefore, the primary containment integrity would be maintained. Although the requirements in 10 CFR 50, Appendix J, section Ill.D.1.(a) state that three Type A tests shall be performed in each 10-year service period and at approximately equal intervals during that service period, we have concluded that performing the third Type A test of the 10-year service period approximately 66 months after the second Type A test would meet the underlying purpose of the rule and that any primary containment leakage during a hypothetical design basis accident will remain less than the maximum allowable leakage rate value, La, established by 10 CFR 50, Appendix J.
Alternative to the Proposed Action Since we have concluded that there is no significant environmental impacts associated with the requested exemption, any alternatives would have either no or greater environmental impact.
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Docket No. 50-277 Ucense No. DPR-44 Alternative Use of Resources This proposed exemption does not involve the use of any resources not previously considered.
Information Supporting a Finding of No Significant impact We have concluded, based on the preceding environmental assessment, that the proposed action will not have a significant effect on the quality of the human environment, therefore, an environmental impact statement for the requested exemption would not be required.
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