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, ev Exelon Generatio-n 200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com April 6, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 1 O CFR 50.71 (e)(4) 10 CFR 54.37(b)
Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRG Docket Nos. 50-277 and 50-278
SUBJECT:
Submittal of the Updated Final Safety Analysis Report (Revision 26),
Fire Protection Program (Revision 21 ), and Reference Drawings In accordance with 1 O CFR 50.71 (e)(4) and 1 O CFR 50.4(b)(6), enclosed is Revision 26 of the Updated Final Safety Analysis Report (UFSAR) and Revision 21 of the Fire Protection Program (FPP) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The enclosed UFSAR and FPP revision copies are being provided to the U.S. Nuclear Regulatory Commission (NRG) iri electronic format on CD-ROM. The electronic versions of the UFSAR and FPP are being submitted in their entirety and are total replacement copies.
1 O CFR 50. 71 ( e )(2) requires that changes made under the provisions of 1 O CFR 50.59 but not previously submitted to the NRG be included in UFSAR updates. Changes to the FPP are to be evaluated in accordance with PBAPS, Units 2 and 3, License Condition 2.C.(4). to this letter identifies UFSAR changes made under the provisions of 1 O CFR 50.59 not previously submitted and included in Revision 26 of the UFSAR. Attachment 1 also identifies those changes to the FPP evaluated in accordance with License Condition 2.C.(4) and included in Revision 21 of the FPP.
10 CFR 50.71 (e)(4) stipulates that revisions to the UFSAR and associated FPP must reflect changes made up to a maximum of six months prior to the submittal. As a result, Revision 26 of the UFSAR and Revision 21 of the FPP for PBAPS, Units 2 and 3, reflect changes at least up to December 31, 2016.
Also enclosed is a CD-ROM containing copies of drawings currently referenced but not included in the PBAPS, Units 2 and 3, UFSAR.
The following enclosures contain the CD-ROMs with the updated files for the UFSAR, FPP, and Reference Drawings in PDF format.
I U.S. Nuclear Regulatory Commission Submittal of PBAPS UFSAR Revision 26 FPP Revision 21 Reference Drawings April 6, 2017 Page2 In addition, pursuant to the requirements of 10 CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision 1, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses, "the UFSAR update required by 1 O CFR 50.71 (e) must include any Structures, Systems, or Components (SSCs) newly identified that would have been subject to an aging management review or evaluation of Time-Limited Aging Analyses (TLAA) in accordance with 1 O CFR 54.21. The UFSAR update must describe how the licensee will manage the effects of aging in order to effectively maintain the intended function(s) of newly-identified SSCs. An evaluation was completed to determine whether any newly-identified SSCs existed in support of submitting UFSAR Revision 26 and FPP Revision 21 for PBAPS, Units 2 and 3. This evaluation involved reviewing pertinent documentation for the period subsequent to the last PBAPS biennial UFSAR I FPP revisions.
As a result of this review, Attachment 2 provides a summary report consistent with the requirements of 10 CFR 54.37(b) on how the effects of aging on a newly-identified Structure, System, or Component (SSCs) will be managed, and summarizes the corresponding changes that are made in Revision 26 of the UFSAR. This report discusses newly identified SSC listed below that were installed in the plant at the time of the license renewal for PBAPS, Units 2 and 3, and were not previously evaluated, and the newly identified TLAA.
- Refueling Water Storage Tank
- Torus Dewatering Tank Dike
- Hoists
- Radwaste Building Demineralizer Hoist
- Dewatering Building Coffing Hoist
- Unit 3 One-Ton Crane (over Repair Area)
- Unit 3 Jet Pump Riser Repair Clamps (TLAA) includes file directory structure information identifying directory path, filename, and size of the individual files on the enclosed CDs.
As required by 1 OCFR50.71 (e)(2)(i), I certify that to the best of my knowledge, Revision 26 of the UFSAR and Revision 21 of the FPP accurately reflect information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above.
If you have any questions or require further information, please contact Richard Gropp at (610) 765-5557.
Respectfully, David P. Helker Manager, Licensing and Regulatory Affairs Exelon Generation Company, LLC
U.S. Nuclear Regulatory Commission Submittal of PBAPS UFSAR Revision 26 FPP Revision 21 Reference Drawings April 6, 2017 Page 3 Attachments: 1. Changes Made Under the Provisions of 10 CFR 50.59 and License Condition 2.C.(4)
- 2. Summary of Newly Identified Items in Accordance with 10 CFR 54.37(b)
- 3. Electronic File Directory Structure
Enclosures:
w/ Attachment and Enclosures Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, PBAPS USNRC Senior Project Manager NRR, PBAPS R.R. Janati, Commonwealth of Pennsylvania S. T. Gray, State of Maryland Page 1 of 4 Changes Made Under the Provisions of 10 CFR 50.59 and License Condition 2.C.(4) 1 O CFR 50.71 (e)(2)(ii) requires that revisions to the Updated Final Safety Analysis Report (UFSAR) include changes made under the provisions of 10 CFR 50.59, but not previously submitted to the NRC. Changes to the Fire Protection Program (FPP) are to be evaluated in accordance with Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, License Condition 2.C.(4). Accordingly, the list below identifies changes included in Revision 26 of the PBAPS, Units 2 and 3, UFSAR or Revision 21 of the PBAPS FPP that were not previously submitted to the NRC. Some exceptions have been noted.
Change Number Revision Description 2012-0016\\ I}
00 Revise various UFSAR sections related to Unit 3 Residual Heat Removal (ECRs 11-00376, 11-00496)
(RHR) loop cross-tie modification work.
2012-022\\l) 00 Revise various UFSAR sections related to Unit 3 RHR loop cross-tie (ECRs 11-00376, 11-00496) modification work.
2012-024 00 Revise various FPP sections related to Unit 3 RHR loop cross-tie modification (ECR 11-00376) work.
2013-022\\ l) 00 Revise various FPP sections related to Unit 3 RHR loop cross-tie modification (ECR 11-00496) work.
2014-004(1)
Revise various UFSAR sections related to Unit 3 replacement of Reactor (ECR 13-00338) 00 Recirculation System Motor Generator (MG) sets with Adjustable Speed Drives (ASDs).
2014-005 Revise UFSAR Appendix C related to Unit 3 replacement of Reactor (ECR 14-00356) 00 Recirculation System Motor Generator (MG) Sets with Adjustable Speed Drives (ASDs).
2014-008 00 Revise UFSAR Table 7.4.1 for Unit 3 related to High Pressure Coolant (ECR 12-00339)
Injection System instrumentation.
2014-013 00 Revise various UFSAR sections for Unit 3 related to implementation of (ECR 13-00049)
Extended Power Uprate (EPU).
2014-022 00 Revise UFSAR Table 11.8.2 for Unit 3 related to replacement of Feedwater (ECR 13-00359)
System heater work.
2014-023 00 Revise various UFSAR sections to include supplemental Global Nuclear Fuels (ECR 12-00045)
(GNF) criticality analysis for Spent Fuel Pool.
2014-024 00 Revise UFSAR Table 11.8.2 for Unit 3 related to replacement of Reactor Feed (ECR 11-00375)
Pump Turbine (RFPT) work.
2014-025 Revise UFSAR Chapter 3 for Unit 3 related to replacement of original Steam (ECR 12-00327) 00 Dryer equipment with new Replacement Steam Dryer designed for EPU conditions.
2014-031 00 Revise UFSAR Chapter 1 for Unit 3 related to the High Pressure (HP) turbine (ECR 14-00087) steam flow path for the new HP rotor designed for EPU conditions.
2014-032 00 Revise various UFSAR and FPP sections related to the listing of safety (ECR 11-00252) valves.
2014-036 00 Revise various UFSAR tables for Unit 3 related to the changes in the (ECRs 14-00082, 14-00083)
Condensate System pump and motor ratings.
2014-037 00 Revise UFSAR Chapter 9 to include a description of the Resin Dewatering Facility.
2014-041 00 Revise various FPP sections to reflect changes in fire hazards materials listed (ECR 15-00002) and fire severity classification of certain fire areas.
2014-043 00 Revise various FPP sections for Unit 3 to include information related to new (ECR 13-00134)
Motor Control Center (MCC) units.
2014-049 00 Revise various UFSAR sections for Unit 3 to include information related to the (ECR 14-00222) addition of two Condensate System filter demineralizers.
2014-050 Revise various FPP sections for Unit 3 to include information related to the 00 addition of four new rooms and two new smoke detectors in the Turbine (ECR 14-00221)
Buildinq.
Revise UFSAR Chapter 9 to include information regarding procedural controls 2015-001 00 related to compliance with 1 O CFR 20 and 40 CFR 190 limits and description of the original Steam Dryer stored outside the Low Level Radioactive Waste
. Storaae Facilitv (LLRWSFl.
Page 2 of 4 Change Number 2015-003 (ECR 14-00322) 2015-004\\l)
(ECRs 11-00496, 11-00378) 2015-005 (ECR 14-00420}
2015-006\\l)
(ECR 11-00496) 2015-007 (ECR 11-00376) 2015-009 (ECR 11-00376) 2015-014 (ECR 11-00051) 2015-015 (ECR 13-00243) 2015-016 (ECR 15-00150) 2015-017 (ECR 15-00091) 2015-018 (ECR 12-00422) 2015-019 (ECRs 10-00478, 13-00243) 2015-020 (ECR 15-00220) 2015-021 (ECR 13-00494) 2015-022 2015-023(1)
(ECR 15-00260) 2015-024 (ECR 15-00191 l 2015-025 (ECR 15-00313) 2015-027 (ECR 13-00040) 2015-028(1)
(ECR 15-00314) 2015-029 (ECR 13-00330) 2015-030 2015-031 (ECR 13-00049}
2015-032 (ECR 15-00430)
Revision Description 00 Revise UFSAR Chapter 7 to update information related to the cask loading area and the cooling period for preselected spent fuel bundles.
00 Revise UFSAR Chapter 8 diesel loading table information for Unit 3 in support of the RHR loop cross-tie modification work.
00 Revise UFSAR Chapter 7 information in support of upgrades for the Unit 2 Pressure Regulator and Turbine-Generator Control Svstem.
00 Revise various FPP sections related to Unit 3 RHR loop cross-tie modification work.
00 Revise various FPP sections for Unit 3 to include information related to new MCC units in support of the RHR loop cross-tie modification work.
Revise various UFSAR sections for Unit 3 to delete the Reactor Protection 00 System () and Primary Containment Isolation System (PCIS) reactor scram and isolation uoon receipt of Main Steam Line hiah radiation trio sianals.
00 Revise UFSAR Chapter 7 to add information regarding the confirmation density algorithm and automatic backup stabilitv protection.
00 Revise various UFSAR sections to support EPU implementation.
00 Revise FPP Section 6 to provide clarifying information related to protection between circuits of concern and Fire Safe Shutdown (FSSD) circuits.
Revise UFSAR Chapter 7 to include information regarding Average Power 00 Range Monitor (APRM) and Operating Power Range Monitor (OPMRM) setpoints and description required to implement Maximum Extended Load Limit Line Analvsis Plus (MELLLA+).
00 Revise various UFSAR sections to reflect information in support of implementation of MELLLA+.
00 Revise UFSAR Appendix H to include information in support of implementation of EPU (Amendment Nos. 293/296).
00 Revise FPP Section 5 to address an administrative discrepancy and clarify information to match with existing plant condition.
Revise various UFSAR sections for Unit 2 to delete the RPS and PCIS 00 reactor scram and isolation upon receipt of Main Steam Line high radiation trip sianals.
00 Revise UFSAR Chapter 2 to update and clarify information on groundwater wells.
Revise UFSAR Chapter 7 for Unit 3 to address the removal of the low 00 condenser vacuum automatic RFPT trip which will be performed by Operator manual action.
00 Revise UFSAR Chapter 7 for Unit 3 to include information related to the replacement of certain pressure transmitters.
Revise UFSAR Chapter 14 to include updated information related to the time 00 limits for secondary containment hatches to be opened following a reactor shutdown and the associated radioloaical dose conseauences.
Revise UFSAR Chapter 8 for Unit 3 to include updated information related to 00 the replacement of the Motor-Generator (MG) set ventilation supply fans and exhaust fans.
Revise UFSAR Chapter 15 to remove information pertaining to 1 O CFR 50, 00 Appendix J testing for a selection of RHR and Core Spray (CS) isolation valves.
Revise various UFSAR sections to reflect information from the Unit 3 Cycle 00 21 reload review and primarily reflects changes as a result of the new Pressure Reaulator and Power Load Unbalance out-of-service analvsis.
Revise FPP Section 5 to inclu.de updated information related to diesel 00 generator bay fire areas resulting from the issuance of Amendment Nos. 255 and 258 for converting the automatic C02 fire suppression system to manual.
00 Revise UFSAR Chapter 7 to reconcile changes between Unit 2 and Unit 3 instruments resulting from EPU implementation.
00 Revise various UFSAR sections to reflect Standby Liquid Control (SLC) system design basis description changes.
Page 3 of 4 Change Number 2016-002 2016-003 lECR 10-00478) 2016-004 (ECR 15-00333) 2016-005 2016-006 2016-007 (ECR 16-00027) 2016-008 (ECR 15-00378) 2016-009 2016-010 (ECR 15-00378) 2016-011 (ECR 16-00005) 2016-012 (ECR 15-00331) 2016-014 (ECR 15-00376) 2016-015 (ECR 15-00451) 2016-016 2016-017 (ECR 15-00140) 2016-018 2016-019 (ECR 07-00010) 2016-020 (ECR 15-00148) 2016-021 2016-022 2016-024 (ECR 16-00248) 2016-025 2016-027 (ECR 16-00346) 2016-031 2016-033 2017-002 (16-00241)
Revision Description 00 Revise various UFSAR sections to include additional information and detail related to the Remote Shutdown Svstem (RSS) desiQn basis 00 Revise various UFSAR sections to reconcile changes between Unit 2 and Unit 3 resulting from EPU implementation.
00 Revise UFSAR Chapter 7 to reflect upgrading Barksdale pressure transmitters tb Rosemount pressure transmitters and trip units.
00 Revise U FSAR Chapter 10 to delete the listed exception for the drywall head strongback load tests.
00 Revise UFSAR Chapter 2 to include information regarding the current RadioloQical Environmental MonitorinQ Promam (REMP).
Revise UFSAR Chapter 7 for Unit 2 to reflect the removal of the low condenser 00 vacuum automatic reactor feed pump turbine trip which will be performed by Operator manual action.
00 Revise various UFSAR sections for Unit 2 to reflect replacement of Recirculation System MG sets with ASDs.
00 Revise UFSAR Table 5.2.2 related to the CS nozzle penetration information listed.
00 Revise various FPP sections for Unit 2 to reflect replacement of Recirculation System MG sets with ASDs.
00 Revise UFSAR Chapter 8 diesel loading table information.
00 Revise UFSAR Chapter 9 to include information regarding fuel channel processing and storage in the Low Level Radwaste (LLRW) facility.
00 Revise various FPP sections for Unit 2 to reflect removal of trash and sprinklers from certain areas on elevation 135'.
00 Revise UFSAR Table 4.2.4 to include updated information related to locations for cycle-based fatigue monitoring.
00 Revise UFSAR Appendix H, Section H.1 to provide clarifying reference information related to the compliance with General Design Criteria (GOG).
00 Revise UFSAR Chapter 10 related to the use of probabilistic analysis for hazardous chemical assessments.
00 Revise UFSAR Table 6.3.1 to change High Pressure Coolant Injection (HPCI) uooer pressure value from 1150 psig to 1170 psig.
Revise UFSAR Chapter 6 to reflect changes related to discontinuing use of a 00 temporary hose connection and install permanent piping for the HPCI stay-full function.
00 Revise UFSAR Chapter 7 to reflect changes in the maximum room temperatures for the Emergency Switchgear and Battery Rooms.
Revise UFSAR Chapter 5 to clarify and describe the basis for the time delay for 00 personnel access to and from the secondary containment (blue light door alarms).
Revise UFSAR Chapter to reflect changes to Severe Accident Management 00 Procedures (SAMP) based on BWROG Emergency Procedure Guideline and Severe Accident Guideline (EPG/SAG), Revision 3 Quidance.
Revise UFSAR Chapter 7 to update the analytical limits for Average Power 00 Range Monitor (APRM) neutron flux-high and neutron flux-high (setdown) scram.
00 Revise UFSAR Appendix Q to address inconsistencies in the methods for environmental fatique calculations.
00 Revise UFSAR Chapter 4 to remove the backseat function description for the Unit 2 "D" Main Steam Isolation Valve (MSIV).
00 Revise UFSAR Table 5.2.2 to include updated information related to various nozzle oenetrations.
00 Revise FPP Section 2 to clarify information related to the design concentration of the Comouter Room C02 svstem.
00 Revise UFSAR Chapter 5 to include updated information to permit the RHR room unit-cooler inoperability during operating Modes 4 and 5.
Page 4 of 4 Change Number 2017-003 2017-004 2017-006 Revision Description 00 Revise UFSAR Appendix Q to include cross-reference information related to license renewal commitment action trackinq items.
00 Revise UFSAR Chapter 8 to reflect Emergency Diesel Generator (EOG) fuel oil transfer manual actions resultinq from issuance of Amendment Nos. 311/315).
00 Revise UFSAR Appendix Q to reflect changes resulting from 10 CFR 54.37(b) review.
,11
- The changes 1dent1f1ed were described m the PBAPS Biennial 10 CFR 50.59 and 10 CFR 72.48 Report submitted by letter dated January 27, 2017.
Page 1 of 2 Summary of Newly Identified Items in Accordance with 1 O CFR 54.37(b)
For holders of a renewed operating license, 1 O CFR 54.37(b) requires that newly identified Structures, Systems, or Components (SSCs) be included in the Final Safety Analysis Report (FSAR) update required by 10 CFR 50.71 (e), describing how the effects of aging will be managed.
Newly identified SSCs are those SSCs that were installed in the plant at the time of license renewal for PBAPS Units 2 and 3, but were not evaluated as part of the License Renewal Application (LRA), as discussed in Regulatory Issue Summary 2007-16, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses." As part of this 10 CFR 50.71 (e) update, four newly identified items are being reported under 10 CFR 54.37(b). Each of these items, and the associated UFSAR impact, is summarized below.
- 1) The Refueling Water Storage Tank (RWST) was not in scope for the first license renewal. The Extended Power Uprate (EPU) project eliminated reliance on Containment Accident Pressure (CAP) in Emergency Core Cooling System pump net positive suction head evaluations. In order to support elimination of reliance on CAP credit, the volume of water in the RWST is required to supplement the water in the in-scope Condensate Storage Tank (CST) for the Appendix Rand ATWS events. The RWST and the SSCs necessary to establish a flowpath to transfer the supplemental volume to the CST are now credited for Appendix Rand ATWS events, and are added to scope for license renewal. Engineering Change Request ECR PB 12-00500 was implemented on Unit 2 changing the plant licensing basis to credit the RWST for the Appendix R and A TWS events.
- a. Impact on the UFSAR:
- i. Section Q.1.4, "Demineralized Water and Condensate Storage Tank Chemistry Activities," is revised to include RWST chemistry activities.
ii. Section Q.2.5, "Outdoor, Buried and Submerged Component Inspection Activities," is revised to include inspections of the RWST and associated Storage and Transfer System piping and valves.
iii. New Section Q.7.1, "Newly Identified Structures, Systems and Components" is added. This section lists the newly identified items, summarizes the aging management review conclusion, and describes affected aging management programs.
- 2) The Torus Dewatering Tank dike was not in scope for the first license renewal. As a result of EPU, the torus dewatering tank dike must provide structural support for piping credited with establishing a flowpath from the RWST to the Unit 3 CST. Since the torus dewatering tank dike is now credited for Appendix Rand ATWS events, it is added to scope for license renewal with an intended function of Structural Support to nonsafety-related components.
- a. Impact on the UFSAR: This item is described in new UFSAR Section Q.7.1, "Newly Identified Structures, Systems and Components," cited above. There is no additional impact on the UFSAR because the description of the Maintenance Rule Structural Monitoring Program in Section Q.1.16 already includes the relevant materials, aging effects and aging management activities to be performed for the torus dewatering tank dike.
Page 2 of 2
- 3) The following hoists were not in scope for the first license renewal:
- Radwaste Building Demineralizer Hoist
- Dewatering Building Gaffing Hoist
- Unit 3 One-Ton Crane (over Repair Area)
As a result of review of the current revision of engineering analysis, M-25-102, Overhead Handling Systems Review Final Report, it was identified that these nonsafety-related hoists are above or nearby to safety-related SSCs, and therefore should be included in scope for license renewal with a 10 CFR54.4(a)(2) structural intended function.
- a. Impact on the UFSAR: This item is described in new UFSAR Section Q.7.1, "Newly Identified Structures, Systems and Components," cited above. There is no additional impact on the UFSAR because the description of the Crane Inspection Activities in Section Q.1.14 already addresses the relevant components, environments and inspection activities to be performed for the three additional cranes/hoists.
- 4) In 1998, prior to the PBAPS Units 2 and 3 license renewal, clamps were installed inside the Unit 3 reactor vessel to structurally replace certain jet pump riser piping welds. Since these clamps use bolts to maintain proper clamping force, loss of bolting preload due to irradiation induced stress relaxation was a design consideration. The analysis for these clamps was associated with. the initial 40-year plant operating period, and should have been identified as a Time Limiting Aging Analysis (TLAA). This analysis has now been reevaluated and confirmed to support continued service of the clamps through the period of extended operation.
- a. Impact on the UFSAR: This item is described in new UFSAR Section Q.7.2, "Newly Identified Time Limited Aging Analyses." In addition to the TLAA description, the TLAA analysis is summarized and the TLAA disposition provided, consistent with the TLAAs that were identified and evaluated within the original LRA, which are shown in UFSAR Section Q.5.
ATTACHMENT 3 Peach Bottom Atomic Power Station Units 2 and 3 Updated Final Safety Analysis Report, Revision 26 Fire Protection Report, Revision 21 File Directory Structure File Directory Structure Page 1of15 Fil~ Slz~ ( Bytes).
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ENCLOSURE 1 Peach Bottom Atomic Power Station Units 2 and 3 Updated Final Safety Analysis Report, Revision 26 Fire Protection Report, Revision 21 Compact Disk (CD)
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ENCLOSURE 2 Peach Bottom Atomic Power Station Units 2 and 3 Updated Final Safety Analysis Report, Revision 26 Fire Protection Report, Revision 21 UFSAR I FPP Reference Drawings Compact Disk (CD)
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