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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20198L3331997-12-18018 December 1997 Safety Evaluation Supporting Approval of Proposed Merger of Atlantic Energy,Inc,& Delmarva Power & Light Co ML20212G8301997-10-24024 October 1997 Safety Evaluation Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively ML20198S2161997-10-24024 October 1997 Safety Evaluation Accepting Proposed Change to Provisions Identified in Rev 14 of PBAPS QAP Description Re Nuclear Review Board Meeting Frequency ML20217J5631997-10-0909 October 1997 Safety Evaluation Supporting Amend 225 to License DPR-56 ML20217J6161997-10-0707 October 1997 Safety Evaluation Re Alternative to Reactor Pressure Vessel Circumferential Weld Insps for Plant,Unit 3 ML20211L6241997-10-0303 October 1997 Safety Evaluation Authorizing Licensee Proposed Use of Code Case N-516-1 to Weld Modified Suction Strainer in Suppression Chamber at Plant ML20217D8161997-09-30030 September 1997 Safety Evaluation Supporting Amend 224 to License DPR-56 ML20211D6201997-09-17017 September 1997 SER Accepting VT-2 Examiner Qualification Request for PECO Energy Company,Peach Bottom Atomic Power Station,Units 2 & 3 ML20216G5601997-09-0404 September 1997 Safety Evaluation Supporting Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively ML20217M8001997-08-19019 August 1997 Safety Evaluation Supporting Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively ML20149L2841997-07-23023 July 1997 Safety Evaluation Accepting Licensee Relief Request RR-22 for Plant,Units 2 & 3 ISI Program ML20140B0371997-05-30030 May 1997 Safety Evaluation Accepting QAP Description Change ML20135B4111997-02-19019 February 1997 Safety Evaluation Supporting Amends 218 & 221 to Licenses DPR-44 & DPR-56,respectively ML20149L8681996-11-15015 November 1996 SER Accepting Core Spray Piping Insp & Flaw Evaluation for Plant,Unit 2 ML20149L2441996-01-29029 January 1996 Safety Evaluation Accepting Insp & Evaluation Methodology for Operation of Unit 3 Core Shroud for Duration of Current Operating Cycle,Performed in Response to GL 94-03 ML20058F5641993-11-19019 November 1993 SE Accepting Util 930305 Response to NRC Bulletin 90-01, Suppl 1, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20057B6441993-09-16016 September 1993 SER Concluding That Safe Shutdown Capability at Plant, Satisfies Requirements of Section Iii.G & Iii.L of App R to 10CFR50 ML20126H9031992-12-23023 December 1992 Safety Evaluation Granting Relief from Inservice Insp Requirements for Facilities ML20127N4941992-11-17017 November 1992 Safety Evaluation Accepting Util 120-day Response to Suppl 1 to GL 87-02 ML20062C7501990-10-26026 October 1990 Safety Evaluation Re Evaluation of Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20246E0331989-08-21021 August 1989 SER Supporting Util Response to Generic Ltr 83-28,Item 2,1 (Parts 1 & 2).Programs Exist for Identifying safety-related Components Required for Reactor Trip Function & Vendor Interface W/Nmss Vendor for Required Components ML20205A8801988-10-31031 October 1988 Safety Evaluation of Util Plan for Restart of Peach Bottom Atomic Power Station ML20148P3351988-04-0101 April 1988 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Program for All safety-related Components ML20148E6301988-01-15015 January 1988 SER Accepting Util 840116,0927 & 850805 Responses to Generic Ltr 82-33,Item 6 Re Compliance w/post-accident Monitoring Instrumentation Guidelines of Reg Guide 1.97 Concerning Emergency Response Facilities ML20236D0541987-10-22022 October 1987 Safety Evaluation Supporting Util Repts on Computer Program Analyses Methods Intended for Use in Part of Plant Core Reload Analyses ML20235D2431987-09-22022 September 1987 Safety Evaluation Re Proposed Onsite Storage of Liquid Oxygen & Hydrogen for Implementation of Hydrogen Water Chemistry.Permanent Hydrogen Water Installation Acceptable ML20209H0201987-04-24024 April 1987 Safety Evaluation Supporting Util Re Torus Attached Piping Mods - Mark I Program ML20204C1001986-07-24024 July 1986 Safety Evaluation Supporting Listed Util Responses & Actions Reviewed During Insp on 840913-19 Re Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 ML20141F6071986-04-0808 April 1986 Safety Evaluation Granting Util Requests for Relief from Inservice Insp Requirements of ASME Code,Section XI ML20209C3141986-03-20020 March 1986 Safety Evaluation Supporting Shroud Head Connection Replacement at Facility,Per Util 860107 Submittal 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
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' p MEO j UNITED STATES j
2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION j RELATED TO AMENDMENT NOS. 223 AND 227TO FACILITY OPERATING l LICENSE NOS. DPR-44 and DPR-56 PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION. UNIT NOS. 2 AND 3 DOCKET NOS. 50-277 AND 50-278 1.0 .lNTRODUCTION By letter dated May 23,1997, as supplemented by letter dated September 11,1998, the PECO Energy Company (the licensee) submitted a request for changes to the Peach Bottom Atomic Powor Station (PBAPS), Unit Nos. 2 and 3, Technical Specifications (TSs). The requested changes would revise the Technical Specifications (TSs) to exclude the measured Main Steam Line Isolation Valves (MSIVs) leakage from the total Type B and Type C Local Leak Rate Test (LLRT) results. The September 11,1998, letter provided the typed TS pages and did not change the Nuclear Regulatory Commission (NRC) staff's proposed no significant hazards consideration determination.
2.0 EVALUATION The original PBAPS Units 2 and 3 TSs (as approved in Safety Evaluation Report dated August 11,1972) excluded the measured MSIVs leakage from the total Type B and Type C LLRT results. Tnis exclusion was deleted from the TSs ac part of the improved Technical Specifications that were approved in a Safety Evaluation (Amendment Nos. 210 and 214) dated August 30,1995.
On September 12,1995, the NRC approved issuance of a revision to 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,"
which was subsequently published in the Federal Reaister on September 26,1995, and became effective on October 26,1995. Option B,
- Performance-Based Requirements," was added to Appendix J to allow licensees to voluntarily replace the prescriptive testing requirements with testing requirements based on both overall leakage rate performance and the performance of individual components. Regulatory Guide (RG) 1.163, " Performance-Based Containment Leak-Test Program," endorses the Nuclear Energy Institute (NEI) 94-01, Revision 0, " Industry l
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Guideline for implementing Performance-Based Option of 10 CFR Part 50, Appendix J," as guidance for developing a performance-based leakage-testing program. Further, if an exception is to be taken from the methods endorsed in RG 1.163, this exception is to be identified in Section 5.5 of the TS.
l The leakage rate acceptance criterion for total Type B and Type C LLRT results is currently limited to 0.6 L,, where L,is equivalent to a 0.5% mir weight per day primary containment leak rate, as described in TS Section 5.5.12, Primary Containment Leakage Rate Testing Program."
No exceptions to the methods endorsed in the RG are currently identified by the licensee. The MSIV leakage is currently included in the 0.6 L, total, even though the M,SIVs also have a j separate TS Surveillance Requirement (SR) limit of 11.5 standard cubic feet per hour (scfh) per valve.
The primary-to-secondary containment leakage rate analyzed in design basis dose consequence calculations, as described in the Updated Final Safety Analysis Report (UFSAR), is based on j 0.635% primary containment air weight per day, or 1.27 L,. This leakage is filtered by the '
standby gas treatment system (SGTS) and then re' eased through the stack. All of the measured Type B and Type C leakage, except the MSIV leakage, is included in the primary-to-secondary I containment leakage. I In addition to the primary-to-secondary containment leakage rate analyzed in design basis calculations, secondary containment bypass leakage is also analyzed. MSIV leakage is considered to be the sole contribute to secondary containment bypass leakage. The additional secondary containment bypass leakage (through the MSIVs at their TS limit of 11.5 scfh per valve) is identified as a separate 0.145% primary containment air weight per day containment leak rate in the design-basis dose consequence calculations. This leakage has an expected release path through the steam line's and turbine / condenser, in a manner similar to the primary-to-secondary leakage calculation, tae 0.145% primary containment air weight per day bounds the total TS-allowable MSIV leakage rate rather than being equal to it (11.5 scfh per valve, times 4 valves, or 46 scfh which is approximately 0.085% primary containment air weight per day).
Because the MSIVs have a low and separate TS leakage limit of 11.5 scfh per valve and the fact that the dose consequence analysis for MSIV leakage continues to be considered separately from all other containment leakages, it is not considered to be necessary to include the MSIV leakage as part of the primary-to-secondary containment leak rate which has been analyzed as i 1.27 L,. Further, the proposed TS maintains the safety objective of the MSIVs to close automatically to (1) prevent damage to the fuel barrier by limiting the loss of reactor coolant in case of a major leak from the steam piping outside the primary containment, (2) limit release of radioactive materials by closing the nuclear system process barrier in case of gross release of radioactive materials from the reactor fuel to the reactor cooling water and steam, and (3) limit release of radioactive materials by closing the primary containment barri 3r in case of a major leak j from the nuclear system inside the primary containment.
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The dominant contributor to onsite (control room, technical support center, vital areas, and vital area acce.s routes) airt>orne activity-caused doses is the secondary containment bypass leakage. The proposed exclusion would have no impact on these doses. Loadings on the control room and technical support center charcoal intake filters consider both primary-to secondary containment leaisage and secondary containment bypass leakage. Therefore, loadings are not increased by this change.
The combined dose rates from the two release paths, the primary-to-secondary containment leakage, and tha secondary containment bypass leakage are unchanged as a result of the proposed change, art. within the dose guidelines of 10 CFR Part 100, and are in confom:ance with.NUREG-0737 post-accident access requirements.
Current TS 5.5.12, " Primary Containment Leakage Rate Testing Program," requires conformance with the guidelines in RG 1.163, which in tum endorses NEl 94-01. The requirements for maintaining total Type B and Type C leak test results are specified in NEl 94-01. The proposed license change application (LCA) revises Section 5.5.12 of the PBAPS Units 2 and 3 TSs to exclude the measured MSIVs leakage from the total Type B and Type C LLRT results and is identified as an exception to the endorsed methodology in RG 1.163. The benefit of excluding the measured MSIV leakage from 0.6 L, acceptance criterion is to provide an additional operational margin when evaluating the total Type B and Type C LLRT leakage against tb current TS limit. This exclusion is proposed because MSIVs have separate leakage limits (covered under TS 3.6.1.3), and the onsite and offsite post loss-of-coolant-accident (LOCA) doses from MSIVs leakage during a design basis accident have been, and will continue to be, analyzed separately from the primary-to-secondary containment leakage. The proposed change
- does not impact the design-basis dose rate calculational methodology or consequences.
However, Appendix J, Option B, Section Ill.B., sintes, in part:
The tests must demonstrate that the sum of the leakage rates at accident pressure of Type B tests, and.... Type C tests, is less than the performance criterion (L ) with margin, as specified in the Technical Specification.
The phrase "(L.) with margin, as specified in the Technical Specification", in accordance with the current TS and NEl 94-01, means that the limit on the sum of Type B and Type C leakage rates is 0.6 L,; in other words, the margin is 0.4 L,. Further, the summation cannot exclude any measured Type B or Type C leakage rate, not even MSIVs leakage. The summation limit would become:
0.6 L, + (MSIVs leakage) = approximately 0.77 L.
This is greater than the 0.6 L., limit stated in NEl 94-01. However, the LCA takes an exception to NEl 94-01 which implicitly redefines the margin referred to in the Appendix J requirement quoted above. Instead of 0.4 L., the margin will t:e approximately 0.23 L,. In other words, the margin to L , "as specified in the Technical Specification," will be different from the norm. The revised TS 1
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will establish a new margin, smaller than the norm The staff finds this to be acceptable, because, as stated above, the radiological analysis for the plant will not change. Therefore, the revised TS will be in compliance with the requirements of Appendix J, Option B.
Several additional TS Bases changes are also included as a part of the LCA request:
- 1. Bases SR 3.6.1.1.1 is revised to delete a discussion concoming leakage limits. Specific
- leakage limits no longer exist in SR 3.6.1.1.1. Primary containment leakage limits are contained in TS 5.5.12, " Primary Containment Leakage Testing Program."
- 2. llases SR 3.6.1.3.14 is clarified to state that MSIV leakage is secondary containment bypcss I leakage, and is independent of the primary-to-secondary containment leakage.
- 3. Referonce 1 to Bases Section 3.6.1.1 is revised to reflect a new reference to Section 14.9,
" Evaluations Using AEC Method," replacing a former reference to Section 14.6.3,
" Loss-of Coolant Accident," under Section 14.6, Analysis of Design Basis Accidents.
The staff has detennined that the proposed LCA engineering change request (ECR) 96-02324 to
. modify the PBAPS Units 2 and 3 TSs to exclude the measured MSIV leakage from the total Type l B and Type C local leakage rate is acceptable and is consistent with 10 CFR Part 50, j
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Appendix J, Option B. The LCA is consistent with the original design basis for PBAPS Units 2 and 3. The methodology and consequences for design basis accident LOCA evaluations are not changed as a result of the proposed LCA. Based on the above, the proposed changes are acceptable.
t i 3.0 STATE CONSULTATIO_N 4
l In accordance with the Commission's regulations, the Pennsylvania State official was notified of l the proposed issuance of the amendments. The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use on a facility component located within the restricted area as defined in 10 CFR Part 20 and change the surveillance i
requ'irements. The NRC staff has determined that the amendments involve no significant i increase in the amounts, and no significant change in the types, of any effluents that may be d
released offsite, and that there is no significant increase in individual or cumulative occupational
- radiation exposure. The Commission has previously issued a proposed finding that the J
amendments involve no significant hazards consideration, and there has been no public
- comment on such finding (62 FR 35852). Accordingly, the amendments meet the eligibility
- criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no
{ environmentalimpact statement or environmental assessment need be prepared in connection j with the issuance of the amendments.
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5.0 CONCLUSION
i The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the 4
Commission's regulations, and (3) the issuance of the amendments will not be inimical to the
] common defense and security or to the health and safety of the public.
1 Principal Contributors: E. D. Throm
! J. C. Pulsipher i
j Date: October 1, 1998 1
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