RS-13-123, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
| ML13240A266 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/28/2013 |
| From: | Jim Barstow Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| EA-12-049, RS-13-123 | |
| Download: ML13240A266 (16) | |
Text
{{#Wiki_filter:1 Exelon Generation ~ Order No. EA-12-049 RS-13-123 August28, 2013 u.s. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353
Subject:
First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
References:
- 1. NRC Order Number EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12, 2012
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," Revision 0, dated August 29, 2012
- 3. NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,"
Revision 0, dated August 2012
- 4. Exelon Generation Company, LLC's Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated October 25, 2012
- 5. Exelon Generation Company, LLC Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated February 28, 2013 (RS-13-022)
- 6. NRC Order Number EA-12-050, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents," dated March 12,2012
- 7. NRC Order Number EA-13-1 09, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013 On March 12,2012, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an order (Reference 1) to Exelon Generation Company, LLC (EGG). Reference 1 was immediately
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 2 effective and directs EGC to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in Attachment 2 of Reference 1. Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the EGC initial status report regarding mitigation strategies. Reference S provided the Limerick Generating Station, Units 1 and 2 overall integrated plan. Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports. The purpose of this letter is to provide the first six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. The enclosed report provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any. As described in Reference S, full implementation of NRC Order EA-12-049 required mitigation strategies is dependent upon implementation of reliable hardened containment venting capability established in accordance with NRC Order EA-12-0S0 (Reference 6). NRC Order EA-13-109 (Reference 7) issued by the NRC on June 6,2013, rescinded the requirements of Order EA-12-0S0 and established revised schedule timelines and implementation dates for reliable hardened containment vents capable of operation under severe accident conditions. The revised schedule and implementation time line contained in Order EA-13-1 09 delays the ability to achieve full implementation of the mitigation strategy requirements of Order EA 049. This need for relaxation from the implementation requirements of Order EA-12-049 is described in Section S of the enclosed update report. The request for relaxation of the full implementation schedule requirements of Order EA-12-049 will be submitted separately. This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-76S-SS2S. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 28th day of August 2013. Respectfully submitted, Je=ffiO~ Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
u.s. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 3
Enclosure:
- 1. Limerick Generating Station, Units 1 and 2 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region I NRC Senior Resident Inspector - Limerick Generating Station, Units 1 and 2 NRC Project Manager, NRR - Limerick Generating Station, Units 1 and 2 Ms. Jessica A. Kratchman, NRR/JLD/PMB, NRC Mr. Robert J. Fretz, Jr, NRR/JLD/PMB, NRC Mr. Robert L. Dennig, NRR/DSS/SCVB, NRC Mr. Eric E. Bowman, NRRlDPR/PGCB, NRC Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Resources R. R. Janati, Commonwealth of Pennsylvania
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 4 bcc: Site Vice President - Limerick Generating Station, Units 1 and 2 Vice President Operations Support Plant Manager, Limerick Generating Station, Units 1 and 2 Site Engineering Director - Limerick Generating Station, Units 1 and 2 Regulatory Affairs Manager Regulatory Assurance Manager - Limerick Generating Station, Units 1 and 2 Severe Accident Management Director Site Operations Director - Limerick Generating Station, Units 1 and 2 Corporate Licensing Manager - East Corporate Licensing Director - East Exelon Records Management Vinod Aggarwal Steven Pierson David Schupp Craig Markle PA DEP BRP Inspector - LGS
Enclosure Limerick Generating Station, Units 1 and 2 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (11 pages)
Enclosure Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of Order EA-12-049, Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 1 Introduction Limerick Generating Station, Units 1 and 2 developed an Overall Integrated Plan (Reference 1 in Section 8), documenting the diverse and flexible strategies (FLEX), in response to NRC Order EA-12-049 (Reference 2). This enclosure provides an update of milestone accomplishments since submittal of the Overall Integrated Plan, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any. 2 Milestone Accomplishments None. 3 Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan (Reference 1). It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed. The revised target completion dates impact the order implementation date. An explanation of the impact of these changes is provided in Section 5 of this enclosure. Milestone Schedule Site: Limerick Generating Station Target Revised Target Activity Completion Activity Status Completion Date Date Submit 60 Day Status Report October 2012 Complete Submit Overall Integrated Plan February 2013 Complete Contract with RRC October 2012 Complete Submit 6 Month Updates: Complete with Update 1 August 2013 this submittal Update 2 February 2014 Not Started Update 3 August 2014 Not Started Update 4 February 2015 Not Started Update 5 August 2015 Not Started Update 6 February 2016 Not Started Page 1 of 11
Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Target Revised Target Activity Completion Activity Status Completion Date Date Update 7 August 2016 Not Started Submit Completion Report April 2016 Not Started April 2018 Modification Development & Implementation: Unit 1 Modification Development (All February 2015 Started FLEX Phases) Unit 1 Modification Implementation (All April 2016 Not Started FLEX Phases) Unit 2 Modification Development (All March 2014 Started FLEX Phases) Unit 2 Modification Implementation (All April 2015 Not Started FLEX Phases) Procedures: Create Site-Specific Procedures April 2015 Not Started Validate Procedures (NEI 12-06, Sect. February 2015 Not Started 11.4.3) Create Maintenance Procedures April 2015 Not Started Perform Staffing Analysis Nov 2014 Not Started Storage Plan and Construction April 2015 Started FLEX Equipment Acquisition April 2015 Started Training Completion April 2015 Not Started Regional Response Center Operational Dec 2014 Started Started See Section 5 of Unit 1 FLEX Implementation April 2016 this enclosure. Started See Section 5 of Unit 2 FLEX Implementation April 2015 this enclosure. Started See Section 5 of Full Site FLEX Implementation April 2016 this enclosure. Page 2 of 11
Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 4 Changes to Compliance Method Attachment 3 of Reference 1 contained conceptual sketches of the water supply and electrical power supply strategies. On the mechanical sketch, a FLEX pump is shown supplying water to the RHR to Fire Water Connection (B.5.b). This was not described in the body of the integrated plan since this was an initial conceptual design that was evaluated and determined to not be the optimal alternate strategy. In addition, a FLEX pump is shown bypassing the existing Suppression Pool Cleanup pump. This was also not described in the body of the integrated plan since this was an initial conceptual design that was evaluated and determined to not be an optimal strategy. These changes are shown in Attachment 1a (Unit
- 1) and Attachment 1b (Unit 2).
On the electrical sketch, a power supply from the FLEX Generators was shown to the suppression pool cleanup pumps. This was not described in the body of the integrated plan since this was an initial conceptual design that was evaluated and determined to not be an optimal strategy. These changes are shown in Attachment 1c. No other changes to the FLEX strategies have been identified at this time. S Need for RelieflRelaxation and Basis for the RelieflRelaxation This section provides a summary of needed relief/relaxation only. The specific details will be submitted in a separate document. NRC Order EA-12-049 requires implementation of Mitigation Strategies to include procedures, guidance, training, and acquisition, staging, or installing of equipment needed for the strategies. The Overall Integrated Plan (Reference I) provided the Limerick Generating Station response to NRC Order EA 049. The cover letter identifies that delays in implementing the Hardened Containment Vent System as required by NRC Order EA-13-1 09 will also affect implementation of the Mitigation Strategies Order EA-12-049 actions. The Overall Integrated Plan (Reference 1) enclosure describes the Limerick Generating Station Mitigation Strategies that are based on venting the containment using the Hardened Containment Vent System. It also describes that a modification to install a Hardened Containment Vent System (HCVS) is required. Thus, the Limerick Generating Station NRC Order EA-12-049 response provided in Reference 1 was premised on installation and use of a Hardened Containment Vent System as required by NRC Order EA-12-050. Upon issuance of NRC Order EA-13-109, the NRC staff changed technical and schedule requirements applicable to the Hardened Containment Vent System and rescinded the requirements of NRC Order EA-12-050. As a result, full compliance to the Mitigation Strategies required by NRC Order EA-12-049 and described in Reference 1 for Limerick Generating Station Units 1 and 2 will not be achieved until compliance to NRC Order EA-13-109 is achieved. Relief/relaxation from the NRC Order EA-12-049 IV.A.2 requirements is required. Limerick Generating Station will be in compliance with the aspects of the Reference I, Unit 1 and Unit 2 Mitigation Strategies that do not rely upon a Hardened Containment Vent System unless otherwise described. Page 3 of 11
Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28,2013 6 Open Items from Overall Integrated Plan and Draft Safety Evaluation The following tables provide a summary of the open items documented in the Overall Integrated Plan or the Draft Safety Evaluation (SE) and the status of each item. Section Reference Overall Integrated Plan Open Item Status Sequence of Events (p. 8) The times to complete actions in the Events Not Started Timeline are based on operating judgment, conceptual designs, and current supporting analyses. The final timeline will be time validated once detailed designs are completed and procedures developed. Sequence of Events (p. 7) Initial evaluations were used to determine Not Started Installed Phase I Equipment the fuel pool timelines. Formal calculations (p.37) will be performed to validate this information during development of the spent fuel pool cooling strategy detailed design. Sequence of Events (p. 7) Analysis of deviations between Exelon's Completed. Attachment engineering analyses and the analyses 2 included with this six contained in BWROG Document NEDC- month update. 33771 P, "GEH Evaluation of FLEX Implementation Guidelines" and documentation of results was not completed and submitted with the Overall Integrated Plan (Reference 1). Identify how strategies will Transportation routes will be developed Not Started be deployed in all modes from the equipment storage area to the (p. 11) FLEX staging areas. An administrative program will be developed to ensure pathways remain clear or compensatory actions will be implemented to ensure all strategies can be deployed during all modes of operation. Identification of storage areas and creation of the administrative program are open items. Page 4 of 11
Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Section Reference Overall Integrated Plan Open Item Status Identify how the An administrative program for FLEX to Not Started programmatic controls will establish responsibilities, and testing & be met (p. 12) maintenance requirements will be implemented. Sequence of Events (p. 9) Additional work will be performed during Not Started detailed design development to ensure Suppression Pool temperature will support RCIC operation, in accordance with approved BWROG analysis, throughout the event. Portable Equip Phase 2 Complete an evaluation of the spent fuel Not Started (p.50) pool area for steam and condensation. Installed Equip Phase 1 Evaluate the habitability conditions for the Not Started (pA7) Main Control Room and develop a strategy Portable Equip Phase 2 to maintain habitability. (p.49) Installed Equip Phase 1 Develop a procedure to prop open battery Not Started (pA7) room doors upon energizing the battery Portable Equip Phase 2 chargers to prevent a buildup of hydrogen in (p.50) the battery rooms. Draft Safety Evaluation Open Item Status N/A N/A 7 Potential Draft Safety Evaluation Impacts There are no potential impacts to the Draft Safety Evaluation identified at this time. S References The following references support the updates to the Overall Integrated Plan described in this enclosure.
- 1. Limerick Generating Station Units 1 and 2, "Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)," dated February 28, 2013 (RS-13-022).
- 2. NRC Order Number EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12,2012.
Page 5 of 11
Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28,2013
- 3. NRC Order EA-I3-1 09, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013.
- 4. LG-MISC-O 12, MAAP Analysis to Support FLEX Initial Strategy. Revision 1.
- 5. NEDC-33771P, GEH Evaluation of FLEX Implementation Guidelines, Revision 1, January 2013.
- 6. NRC Order EA-I2-0S0, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents," dated March 12,2012.
- 7. LGS UFSAR, Revision 16.
9 Attachments Ia - Simplified FLEX Design Mitigation Strategies, Unit 1, Mechanical Schematic Ib - Simplified FLEX Design Mitigation Strategies, Unit 2, Mechanical Schematic Ic - Simplified FLEX Design Mitigation Strategies, Units 1 and 2, Electrical Schematic 2 - NSSS Significant Reference Analysis Deviation Table Page 6 of 11
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Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Attachment 2 NSSS Significant Reference Analysis Deviation Table NEDC-NEDC-33771P 33771P Plant AppUed Value Item Parameter of Interest Rev 1 Value Page (Reference 4, Case 2) NEDC-3377I P Rev 1 Section 4.5.1.4 and 4.5.2.6 define the inputs and results that are closest to the LGS MAAP inputs and results (WW Venting, Suction from Suppression Pool). The LGS model assumed a 10" wetwell vent. The results will be listed from the GEH report for the 8" and 12" wetwell vent. Differences between the GEH SHEX case and the MAAP analysis of the Limerick FLEX strategy (Reference 4, Case 2) are listed below. Input Parameter Values 1 Core thermal power Note 1 18 3515 MWT 2 Primary System Leakage Note 1 18 36gpm I 3 RPV Depressurization Rate Note 1 18 250°F/hr 4 Drywell Free Volume Note 1 18 243,580 fe 5 Initial Drywell Temperature Note 1 18 135°F 6 Initial Drywell Pressure Note 1 18 15.45 psia 7 Initial Drywell Humidity Note 1 18 20% 8 Wetwell Free Volume Note 1 18 158,253 fe 9 Initial Wetwell Pressure Note 1 18 15.45 psia 10 Suppression Pool Volume Note 1 18 123,407 fe 11 Initial Suppression Pool Temperature Note 1 18 95°F 12 RCIC Suction Source Suppression Pool 18 Suppression Pool 13 Time ofWW Venting Note 1 18 5.8 hours Page 10 of 11
Limerick Generating Station, Units 1 and 2 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Attachment 2 NSSS
- - -- -- -- Shmificant Refl
--- - - - --- -- Analvsis Deviation Tabl NEDC-33771P Rev 1 Section 4.5.1.4 and 4.5.2.6 define the inputs and results that are closest to the LGS MAAP inputs and results (WW Venting, Suction from Suppression Pool). The LGS model assumed a 10" wetwell vent. The results will be listed from the GEH report for the 8" and 12" wetwell vent. Differences between the GEH SHEX case and the MAAP analysis of the Limerick FLEX strategy are listed below.
Results SHEX MAAP 8" Vent 12" Vent Page 10" Vent 1 Maximum Suppression Pool Temperature Note 1 Note 1 23,24 234 of at 19 hours 2 Maximum Wetwell Temperature Note 1 Note 1 23,24 Not Available 3 Maximum Wetwell Pressure Note 1 Note 1 23,24 Not Available 4 Maximum Drywell Temperature Note 1 Note 1 23,24 233°F at 3.4 hours, 247°F at 72 hours 5 Maximum Drywell Pressure Note 1 Note 1 23,24 27 psia at 5.8 hours Note 1: The values are GEH proprietary values and have been excluded from this report. The values can be found in NEDC-33771P. Page 11 of 11}}