RNP-RA/14-0083, Third 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)

Third 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)

ML14253A161
Person / Time
Site:	Robinson
Issue date:	08/26/2014
From:	William Gideon Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EA-12-049, RNP-RA/14-0083
Download: ML14253A161 (20)

Text

W. R. Gideon H. B. Robinson Steam DUKE Electric Plant Unit 2 SRGYVice President ENERGY, Duke Energy Progress 3581 West Entrance Road Hartsville. SC 29550 0: 843 857 1701 F: 843 857 1319 Randy. Gideona duke-energM con 10 CFR 50.4 Serial: RNP-RA/14-0083 August 26, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23

Subject:

Third 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. Nuclear Regulatory Commission (NRC) Order Number EA-1 2-049, Order Modifying Licensees With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, Revision 0, Dated March 12, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12054A735)

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 (ADAMS Accession No. ML12229A174)

3. NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Revision 0-A, Dated August 2012

4. Duke Energy Letter, CarolinaPower and Light Company and FloridaPower Corporation'sInitial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategiesfor Beyond-Design-BasisExternal Events (Order Number EA-12-049), Dated October 29, 2012, (ADAMS Accession No. ML12307A021)

5. Duke Energy Letter, CarolinaPowerAnd Light Company's Overall IntegratedPlan in Response to March 12, 2012, Commission OrderModifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis ExternalEvents (Order Number EA-12-049), Dated February 26, 2013 (ADAMS Accession No. ML13071A415)

6. Duke Energy Letter, First Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategiesfor Beyond-Design-Basis ExternalEvents (OrderNumber EA-12-049), Dated August 28, 2013 (ADAMS Accession No. ML13252A243)

7. Duke Energy Letter, Second Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-BasisExternal Events(OrderNumber EA-12-049), Dated February 24, 2014 (ADAMS Accession No. ML14063A283)

U. S. Nuclear Regulatory Commission Serial: RNP-RA/14-0083 Page 2 of 2 Ladies and Gentlemen, On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Order EA-12-049 (Reference

1) to Duke Energy. Reference 1 was immediately effective and directs Duke Energy 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, as issued by the NRC, required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an Overall Integrated Plan (OIP) pursuant to Section IV, Condition C. Reference 2, as issued by the NRC, endorses industry guidance document NEI 12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided Duke Energy's initial status report regarding mitigation strategies at the Brunswick, Robinson and Shearon Harris Nuclear Power Plants. Reference 5 provided Duke Energy's OIP for the H. B. Robinson Steam Electric Plant, Unit No. 2.

Reference 1 requires submission of a status report at six-month intervals following submittal of the OIP. Reference 3 provides direction regarding the content of the status reports. References 6 and 7 provided Duke Energy's first and second six-month status report respectively for the H. B. Robinson Steam Electric Plant, Unit No. 2.

The purpose of this letter is to provide the third six-month status report pursuant to Section IV, Condition C.2, of Reference 1. The attached 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.

This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments.

Should you have any questions regarding this submittal, please contact Mr. Richard Hightower, Manager, Nuclear Regulatory Affairs at (843) 857-1329.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on _____ _"_'

Sincerely, dt. Gideon Site Vice President WRG/shc

Enclosure:

Third 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) cc: Ms. M. C. Barillas, NRC Project Manager, NRR Mr. K. M. Ellis, NRC Sr. Resident Inspector Mr. V. M. McCree, NRC Region II Administrator

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

ENCLOSURE H. B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 Renewed License No. DPR-23 Third 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)

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/1 4-0083 18 Pages (including cover sheet)

1. Introduction RNP developed an Overall Integrated Plan (Reference 1), documenting the diverse and flexible strategies (FLEX), in response to NRC Order EA-12-049 (Reference 4). The Overall Integrated Plan was submitted to the NRC on February 26, 2013. The first six-month update was provided to the NRC on August 28, 2013 (Reference 2). The second six-month update was provided to the NRC on February 24, 2014 (Reference 3). This enclosure provides an update of milestone accomplishments including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any, that occurred during the period January 28, 2014 through July 28, 2014 (hereafter referred to as "the update period"). This update is based on an approved formal Engineering Change-Evaluation (88926R3) (Reference 5) that is discipline reviewed and design verified.

2. Milestone Accomplishments The following milestone(s) have been completed since the development of the Overall Intelrated Plan (Reference 1), and are current as of July 28. 2014.

• Complete Strategy Development

• Submit Integrated Plan

• Complete Modification Identification

• Submit First 6-month Status Update

• Submit Second 6-month Status Update

3. Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change when design and implementation details are developed.

The revised milestone target completion dates do not impact the order implementation date.

Target Revised Milestone Completion Activity Target Status Completion Date Date Complete Strategy Development February Complete Date Not 2013 Revised Submit Integrated Plan February Complete Date Not 2013 Revised August 2013 Complete Revised February Complete Date Not 2014 Revised Submit 6-month Status Update August 2014Reid Started Date Not Revised February Not Started Date Not 2015 Revised Complete Modification Identification March 2013 Complete Date Not Revised

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

Revised Target Activity Target Milestone Completion Status Completion Date Date Complete Modification Development February Started Date Not 2015 Revised Complete Equipment Procurement February Started Date Not 2015 Revised Complete Equipment PM Development February Not Started Date Not 2015 Revised Date is July 2014 Started Revis Complete FSG Development Revised June 2015 Not Started Date is Issue FSGs Revised Date ReviseNot Complete Training Development May 2014 Started Revised Date ReviseNot Initiate Training Implementation May 2014 Started Revised Date ReviseNot Complete Training May 2015 Not Started Revised November Started Date Not Complete Staffing Assessment 2014 Revised Date Not Issue Regional Response Center Playbook for RNP May 2015 Not Started Revise Revised Complete Communications Integrated Plan November Started Date Not 2014 Revised Not Started Date Not Complete Online Modification Implementation May 2015 Revise Revised Complete Outage Modification Implementation June 2015 Not Started Date Not (R229) Revised Date Not RNP FLEX Implementation Complete June 2015 Not Started Revise Revised

4. Changes to Compliance Method The following summarizes the changes to the strategies as documented in the Overall Integrated Plan (Reference 1) that were made during the update period. These changes do not impact RNP compliance with NEI 12-06.

1) Change:

The RNP OIP (Reference 1) Sequence of Events (page 6 of 74) states:

2-12 hours - Align portablenitrogen tanks to operate SG PORV's (contingency for installed, robust nitrogen accumulator). The nitrogen is needed to operate the SG PORVs and the SGs are being subjected to an early depressurization.

The RNP OIP (Reference 1) PWR Installed Equipment Phase 1 (page 12 of 74) also states in part:

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

RNP has elected to follow the WCAP-17601-P guidance. RNP's depressurizationcapability includes the SG Pressure OperatedRelief Valves (PORVs) which are normally operated using the Instrument Air System or with the backup Nitrogen System. However, neither the primary Instrument Air nor the backup Nitrogen System are robust and are not qualified to all applicablehazards.A seismically qualified pressuresource (accumulator)capable of supplying 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of SG PORV operation will be installed, (Open Item 16).

Update:

The proposal to install a new robust pressure source for the SG PORVs is cancelled (Open Item 16). EC88926, Rev.3, FLEX Strategies and Implementation Plan (Reference 5), has revised the strategy as follows:

Strategies currently exist to align portable nitrogen tanks to the S/G PORV header using RNP procedure EDMG-004, Steam Generators,Attachment 1, Connecting Emergency PressureSource to Operate SG PORVs, or Attachment 2, SG Manual Depressurization (Reference 11). Open Item 23 tracks the protectedstorage of necessarynitrogen tanks.

In addition to the SG PORV capabilitiesrecommended in PA-PSC-0965, RNP also has an existing strategy to cooldown the RCS using the main steam line isolation valve (MSIV) bypass lines. The strategyis detailed in calculation RNP-M/MECH-1712, Appendix R MechanicalBasis Calculation, section 3.27, Cooldown Using MSIV Bypass Lines (Reference 12). This capabilityresults in a cooldown rate of 83°/hr, which bounds the recommended Westinghouse cooldown rate of 70W/hr. EC90627is initiated to harden the Turbine Building Class 1 Bay through calculation, analysis, or modification to support the local strategies.

Justification:

The Instrument Air System and Backup Nitrogen System are not robust against RNP hazards.

In place of a major modification to provide SG PORV capability for RCS cooldown, RNP has an Extreme Damage Mitigation strategy to install temporary nitrogen tanks to the SG PORVs directly using existing, approved plant procedures developed for a postulated B.5.b event. The necessary equipment will be stored in the protected Permanent FLEX Storage Facility.

RNP also has an existing strategy to bypass the MSIVs and vent steam from the main steam vents and drain lines. This capability is an approved RNP procedure that results in cooldown rates bounded by PA-PSC-0965, (Reference 16) as shown in calculation RNP-M/MECH-1712, Appendix R Mechanical Basis Calculation, section 3.27, Cooldown Using MSIV Bypass Lines (Reference 12).

Documentation:

• EC EVAL 88926 Rev. 3, FLEX Strategies and Implementation Plan (Reference 5)

• EDMG-004, Steam Generators (Reference 11)

• RNP-M/MECH-1712, Appendix R Mechanical Basis Calculation, section 3.27, Cooldown Using MSIV Bypass Lines (Reference 12)

• PA-PSC-0965, PWROG PSC - ELAP CORE TEAM Core Cooling Management Interim Position Paper, Revision 0 (Reference 16)

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

2) Change:

The OIP and the Second Six-Month Update planned to install an AFW FLEX connection downstream of valve AFW-54 in the motor driven AFW piping. This was also shown on drawing Z09R2 M-3 G-1 90197 SH0004, Connections to C AFW Pump, MDAFWP discharge FLEX Conn.

Update:

The stated AFW FLEX connection will be installed upstream of AFW-54. Drawing Z09R2 M-3 G-190197 SH0004, Connections to C AFW Pump, MDAFWP discharge FLEX Conn, is revised and renamed Z09R3 M-3 G-190197-SH00004 Connections to C AFW Pump, MDAFWP Discharge, SDAFWP Suction FLEX Conn. Revision 3.

Justification:

EC 90623 is approved and includes the following:

A.6 Solution Statement In support of the Diverse and Flexible Coping Strategies (FLEX) requirements imposed by NEI 12-06 (Reference B.2.9. 1) and EngineeringChange (EC) 88926 (Reference B.2.8. 1),

this EC will install one new standardmechanical connection inside the AFW Pump Room, upstream of valve AFW-54. EC95266 installs the second AFW FLEX connection point.

The new AFW FLEX connection installedby this EC will include a new branch pipe and isolation valve.

The location of the FLEX connection point will ensure that all three steam generatorscan be provided with makeup water using a portable pump and portablehoses to support RCS cooldown.

Documentation:

• EC EVAL 88926 Rev. 3, FLEX Strategies and Implementation Plan (Reference 5)

• EC 90623, New Pipe Tee and Standard Connection for NTTF 4.2 (FLEX) (Reference 14)

3) Change:

The Second Six-Month Update planned to install an AFW FLEX connection upstream of valve AFW-4 in the SDAFWP suction piping. This was also shown on drawing Z09R2 M-3 G-1 90197 SH0004, Connections to C AFW Pump, MDAFWP discharge FLEX Conn.

Update:

The stated AFW FLEX connection will be installed downstream of AFW-4. Drawing Z09R2 M-3 G-1 90197 SH0004, Connections to C AFW Pump, MDAFWP discharge FLEX Conn, is revised and renamed Z09R3 M-3 G-1 90197-SH00004 Connections to C AFW Pump, MDAFWP Discharge, SDAFWP Suction FLEX Conn. Revision 3.

Justification:

EC 94741 is in development and includes the following:

A.6 Solution Statement EC 94741 will utilize the Circulating Water System (CWS) intake block inventory to supply makeup water to the suction of the SDAFW pump via a portable Diesel FLEX pump and hose system. The CW intake block is fed by the lake and will maintain a usable inventory volume

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet) as long as lake level is above a minimum Tech Spec limit of 218' (normal average level is 220.7ft).

To facilitate tie-ins of the FLEX equipment into both systems (AFW and CW), EC 94741 will install the following FLEX connections:

" Connection at CWS Intake Block: The eastern most manhole cover at this location will be replaced with a modified cover that is fitted with a stand pipe (dip-tube and isolation valve). This mechanical connection will facilitate attachment of the FLEX pump suction hose. This is an outdoor connection and may require missile protection.

" Connection at the SDAFWP Suction: A piping connection with an isolation valve will be fitted onto the suction pipe of the SDAFWP downstream of AFW-4. This mechanical connection will provide the means for attaching the FLEX pump discharge hose. This connection is inside the protection of the Turbine Building.

The FLEX Pump and Hoses procuredby this EC will be stored in a protected area (near Turbine PedestalStructure) within the Turbine Building and will be deployed as needed in a staging location that facilitates all operable connections.

Documentation:

• EC EVAL 88926 Rev. 3, FLEX Strategies and Implementation Plan (Reference 5)

• EC 94741, Circulating Water Supply to Steam Driven Aux Feedwater Pump Suction During ELAP and/or LUHS (Reference 15)

5. Need for Relief/Relaxation and Basis for the Relief/Relaxation RNP expects to comply with the order implementation date and no relief/relaxation is required at this time.

6. Generic Open Items RNP Duke Energy confirms that the FLEX strategy station battery run-time was calculated in accordance with the IEEE-485 methodology using manufacturer discharge test data applicable to the licensee's FLEX strategy as outlined in the NEI white paper on Extended Battery Duty Cycles (Reference 7). This Generic Open Item is complete and was included in the RNP Second Six-Month Status Report (Reference 3).

The Electric Power Research Institute (EPRI) Report 3002000623 entitled "Nuclear Maintenance Applications Center: Preventive Maintenance Basis for FLEX Equipment," (Reference 8) continues to be evaluated by RNP Duke Energy. This is Open Item 93 in Section 6.a of this report.

RNP Duke Energy will incorporate the guidance provided in the Westinghouse position paper entitled "Westinghouse Response to NRC Generic Request for Additional information (RAI) on Boron Mixing in support of the Pressurizer Water Reactor Owners Group (PWROG)" (ADAMS Accession Number ML13235A135) (Reference 9) with clarifications. This was identified as Open Item 3.2.11.8.B in the ISE. The Open Item has been dispositioned and the RNP response is uploaded to the Robinson ePortal.

RNP Duke Energy will incorporate the supplemental guidance provided in the NEI position paper entitled "Shutdown/Refueling Modes" to enhance the shutdown risk process and procedures (Reference 10). This is Open Item 143 in Section 6.b of this report.

The MAAP4 and CENTS computer code Generic Open items do not apply to RNP.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

The following tables provide a summary status of the Open Items. The table under Section 6.a.

provides the open items that were previously identified in the original OIP submitted on February 28, 2013 and in the first and second six-month status reports submitted by (References 1, 2 and 3).

The table under Section 6.b. provides a list of open items that were added after January 28, 2014.

a. Open Items Documented in Overall Integrated Plan and in First and Second Six-Month update.

Item # Open Item Description Status

1. A Regional Response Centers (RRC) playbook will be developed to support Started RNP during beyond design basis events.

2. Figure(s) (site plot plan) showing FLEX equipment storage locations and Complete deployment routes will be provided.

3. Deployment strategies will be incorporated into an administrative program. Not Started

4. RNP will implement the programmatic controls in accordance with NEI 12-06. Not Started

5. Equipment associated with these strategies will be procured as commercial Started equipment with design, storage, maintenance, testing, and configuration control in accordance with NEI 12-06, Section 11.1.

6. The unavailability of equipment and applicable connections that directly perform Started a FLEX mitigation strategy will be managed using plant equipment control guidelines developed in accordance with NEI 12-06, Section 11.5.

7. Programs and processes will be established to ensure personnel proficiency in Started the mitigation of beyond-design-basis events as developed and maintained in accordance with NEI 12-06, Section 11.6.

8. The FLEX strategies and basis will be maintained in overall FLEX basis Started documents.

9. Existing plant configuration control procedures will be modified to ensure that Not Started changes to the plant design, physical plant layout, roads, buildings, and miscellaneous structures will not adversely impact the approved FLEX strategies in accordance with NEI 12-06, Section 11.8.

10. Applicable training initiated through the Systematic Approach to Training (SAT) Started process will be completed prior to the implementation of FLEX.

16. A seismically qualified pressure source capable of supplying SG PORV Strategy operation will be installed. Deleted

17. Site-specific procedures and/or FSGs will be developed using industry guidance Started to address the criteria in NEI 12-06, Section 11.4.

18. A portable pump will be procured and pre-staged near the condensate pump Pre-staging area. Strategy Deleted

20. Valve C-66 to be modified to include FLEX connections. Started

22. A tee-connection will be added to the C AFW Pump discharge. Complete

23. Sufficient nitrogen tanks (for SG PORV) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coping duration will be Started relocated to a protected location.

24. The existing connection point for the portable nitrogen tank will be modified to Strategy include quick-connects. Deleted

25. The SI accumulator isolation valves will be re-powered via switchgear El or E2 Started with portable diesel generators.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

Item # Open Item Description Status

26. Modify the current 480V switchgear El or E2 and existing diesel generator s to Started include portable diesel generator connection points capable of switching between the existing diesel generator power feeds and portable FLEX generator power feeds.

28. To provide primary and alternate connections for portable pumps, an alternate Started mechanical tee-connection will be provided.

29. Mechanical connections will be available for the south and north SW headers to Started allow connection of a portable pump.

30. N+1 portable pumps will be procured and stored in a robust structure in a Pre-staging protected location near the intake structure in support of Item 29 above. Strategy Deleted

31. During Modes 5 and 6, a portable pump will be used to take suction from the Started RWST or portable tanker and discharge to the SI header.

32. Primary and alternate mechanical FLEX connections will be added to the SI Started header.

33. Drain valve (SI-837) at the base of the RWST will be modified to align it to the Started standardized connection type.

34. Structures to provide protection of the FLEX equipment will be built prior to the Started FLEX implementation date.

35. The RNP procedures and programs must be developed to address storage Not Started structure requirements, deployment path requirements, and FLEX equipment requirements relative to the hazards applicable to RNP.

36. Necessary modifications will be made to existing SSC connections to facilitate Started FLEX equipment deployment.

37. Necessary modifications will be made to existing onsite fences, structures or Not Started security parameters to facilitate flex equipment deployment.

38. The equipment connection points will be designed to withstand the applicable Started external hazards.

39. The means for connecting the Phase 3 generator will be identified based on the Started selected onsite location of the generator.

40. Low leakage Reactor Coolant Pump (RCP) seals will be installed. Started

42. Actual size of generator to be determined at a later time. Complete

44. The resolution of method for SFP level determination is being addressed by the Started actions taken in response to Order 12-051.

45. To maintain SFP inventory, a portable pump equipped with suction and Started discharge lines and compatible hose connections will be available.

46. The alternate strategy for SFP cooling is to provide makeup via installed SFP Started piping which will require modifications. One of two Emergency Cooling Connections (ECCs) can be used for external filling to robust piping. These connections will be used with portable pumps to draw water from diverse locations directly into the pool. This change was reported in the Second Six-Month Update.

47. Alternate methods for powering the 480V MCC 5 and 6 require either bus Strategy modification to accommodate the diesel generator connector, or the addition of Deleted a new diesel generator connection integrated into vertical panel design.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/1 4-0083 18 Pages (including cover sheet)

Item # Open Item Description Status

50. Applicable areas of the Turbine Building will be analyzed or hardened to provide Started an adequate level of assurance of critical instrumentation availability.

51. Calculations will be performed for extending the time before HVAC is needed to Started beyond eight hours.

53. Additional portable lighting will be procured to facilitate implementation of the Started FLEX strategies.

54. Strategies to mitigate the loss of communications systems will be developed per Started NEI 12-06 Section 3.2.2(8).

55. Staffing studies will be performed in accordance with NRC RFI and NEI 12-01 to Started ensure adequate staffing is available to support, install, and operate FLEX equipment in the time necessary.

56. Phase 2 battery coping will require portable diesel generators to power the Started battery chargers and the Battery Room exhaust fans in order to remove hydrogen gas accumulation during charging.

57. Manual disconnect switches, compatible for quick portable diesel generator Started connection, will be installed to directly power the battery chargers.

58. Permanent cable and raceway will be installed to make cable deployment Strategy directly to the battery chargers feasible. Deleted

60. Manual transfer switches with the ability to quick-connect to portable 5kW diesel Strategy generators will be installed to provide ventilation to the Battery Rooms. Deleted

61. An analysis of HVAC requirements for operating equipment will be performed Started based on area heat-up times without cooling available for indefinite coping.

62. Portable fan blowers/generators will be procured and used to provide forced Started convection.

63. RNP will acquire a fuel pumping vehicle/trailer that can be used to extract and Complete deliver fuel oil.

64. An analysis to determine the fuel consumption rate of all portable Started generators/equipment will be performed.

65. Provisions will be made for an offsite fuel delivery to RNP before all onsite fuel is Not Started depleted.

66. Results of the PWROG task will be used in determining the minimum flow rate Complete and pumping capacity required for borated water makeup.

67. Portable equipment maintenance will be performed in accordance with the Not Started requirements of NEI 12-06, Section 11.5.

68. An analysis will be performed to determine the radiation protection equipment Complete requirements.

69. An analysis will be performed to determine the commodities requirements. Not Started

70. Transportation equipment will be provided to move large skid/trailer mounted Started equipment provided from off-site.

71. Additional or revised conceptual sketches will be provided in future updates as Started engineering packages mature from conceptual design to final design.

72. Develop procedures, references, and tables to determine key parameters using Started a portable DVM in the instrument racks.

74. Implement the RNP integrated plan for Order EA-12-049 as stated in the Started

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

Item # Open Item Description Status submittal. If plans change, ensure that the changes are reflected in future six month status reports that are required to be submitted per the Order. Ensure Open Items listed in RNP-RA/13-0022 (i.e., 588978), are addressed.

79. Revise SAMG and other RNP Emergency procedures to include FLEX response Started and related setpoints.

Note: This activity / scope does not include revision of other site procedures as they will be revised as part of the mods that impact them. Mod estimates include budget for associated procedure revisions.

80. FI-6416 installed per EC83801 is a safety related instrument and is currently Started used in DSP-002, "Hot Shutdown Using the Dedicated/Alternate Shutdown System" Attachment 6. Ensure use of this instrument is accounted for in the new FSGs.

81. Ensure no credited SBO circuits are removed from operation when determining Complete which additional loads can be shed for a deep load shedding strategy. Refer to 8S1 9-P-1 01, Station Blackout Coping Analysis Report, Table 1 for credited SBO equipment.

82. When new load shedding strategies are developed, perform manual action Not Started walk-throughs and validation (simulated) to demonstrate the proposed operator actions are feasible and achievable.

86. Re-evaluate SI Accumulator Isolation Valve closure as a phase 2 strategy Complete (determine how to get power to the valves by possibly using the battery charger diesel generators.

87. Loss of heat tracing on significant required instrumentation sensing lines has Started been identified. The heat tracing is not safety related and it is not robust.

Develop strategies to address the loss of heat tracing on instrument sensing lines.

89. Develop an ELAP boration strategy that includes rates, times, and SDM Complete calculations for all times in core life.

90. Develop a one-line electrical sketch of the RNP battery bus power scheme Started showing connections for the FLEX portable equipment to be used in an ELAP event.

91. Describe how electrical isolation will be maintained such that (a) Class 1E Started equipment is protected from faults in portable/FLEX equipment and (b) multiple sources do not attempt to power electrical buses.

92. Develop a formal strategy for refueling of all FLEX portable equipment during an Started ELAP event. Explain how fuel quality will be assured if it stored for extended periods of time. See Open Item 64 also. Include the strategy in FSG-005.

93. Provide details in the OIP of how RNP will incorporate the EPRI industry Not Started program for maintenance and testing of FLEX electrical equipment such as batteries, cables, and diesel generators.

94. Discuss the reliability of the SDAFWP with respect to the following: Not Started

" The steam traps are all ganged into one line to the condenser that has the Potential to be pinched or crimped in an event and render the SDAFWP inoperable.

"The SDAFWP minimum flow recirculation line has the same exposure to being pinched or crimped in an event and render the SDAFWP inoperable.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

Item # Open Item Description Status

95. Evaluate the SG PORVs for an Uncontrolled Cooldown scenario as follows: Not Started (a) Clarify whether the ADV or upstream associated piping is a safety-related system, protected from external events such as tornadoes. If not, address the following questions:

(b) Clarify whether damage to an ADV or upstream associated piping could occur during an ELAP that would result in an uncontrolled cooldown of the reactor coolant system and provide a basis for the response.

(c) Clarify whether postulated damage would be limited to a single ADV and/or associated piping, or whether failures could be postulated resulting in an uncontrolled cooldown affecting both steam generators, and provide a basis for the response.

(d) If ELAP scenarios involving the uncontrolled cooldown of one or more steam generators may be postulated, describe key operator actions that would be taken to mitigate these events.

(e) If ELAP scenarios involving the uncontrolled cooldown of one or more steam generators may be postulated, provide analysis demonstrating that the intended mitigating actions would lead to satisfaction of the requirements of Order EA-1 2-049 for these cases.

(f) As applicable, ifthe operator actions to mitigate an ELAP event involving an uncontrolled cooldown results in an asymmetric cooldown of the reactor coolant system, address the consequences of the asymmetric cooldown on the mixing of boric acid that is added to the reactor coolant system to ensure sub-criticality.

96. The issue of how to control critical equipment without control power must be Started assessed as part of the response to load shedding.

97. Purchase portable gas or propane heaters to replace the 480 VAC heaters used Not Started for freeze protection in cold weather operations. The portable heaters will be stored in the FLEX storage facility.

98. Provide documentation of high wind and missile protection for the components Not Started associated with EC94741.

99. Procure a diesel driven sump pump to dewater the Intake SW Strainer Pit Not Started following a rain event.

100. Evaluate the Rad Waste building to determine if it is robust against the high Not Started wind and missile hazard.

101. Develop a formal calculation to determine the time to boil off the SFP inventory Complete to 10' above the fuel racks and to the top of the fuel racks assuming:

1/3 Core Offload 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after refueling

• Mode 6 Full Core Offload 102. Evaluate the Lake Robinson dam to determine ifit is robust against the high Not Started wind and missile hazard.

103. Determine if it is required to store HazMat equipment in the FLEX storage Complete facility to cope with an acid or caustic tank rupture/spill.

104. Perform walkdowns and simulations to verify and validate that time critical Not Started actions required for mitigating strategies for core cooling are feasible.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

Item # Open Item Description Status 105. Perform walkdowns and simulations to verify and validate that time critical Not Started actions required for mitigating strategies for RCS boration and inventory are feasible.

106. Perform walkdowns and simulations to verify and validate that time critical Complete actions required for mitigating strategies for SFP cooling are feasible.

107. Revise drawing Z25R2 to specify all 'A'staging areas, deployment routes from Complete storage to staging, equipment to be staged in each area, and distance to the related FLEX connection points.

108. Add a section to the FLEX/Fukushima Program document to list all SSCs Not Started affected by FLEX implementation. See EC 88926, Rev. 2, Design Verification Comment #81.

109. Determine which of the following instruments located in the Turbine Class 1 Bay Complete are critical to FLEX response strategies for core cooling.

1. Secondary Control Panel on the mezzanine LI-607A-2 LI-607B-2 LI-607C-2 LI-607D-2 PI-607E-2 Ll-1454C TI-410B TI-413B

2. Instruments, LI-477A, 487A and 497A on the mezzanine

3. Instrument FI-6416 on the mezzanine

4. Main Steam Line Pressure transmitters Cabinet on the mezzanine PT-474 PT-475 PT-484 PT-485 PT-495 PT-496 Ensure critical instruments are included in EC 90627 before the 30% Design Review.

b. Open Items added after January 28, 2014. This table includes Open and Confirmatory Items that were identified in the NRC Interim Staff Evaluation and Audit Report (Reference 6). Items with a status of Complete are posted on the H. B. Robinson ePortal.

Item # New Open, ISE Open, and Confirmatory Items Status 110. Open Item 3.2.1.8.B Complete Core Sub-Criticality - Verify that RNP will apply the generic resolution for boron mixing under natural circulation conditions potentially involving two-phase flow, in accordance with the PWROG position paper, dated August 15, 2013, subject to the additional conditions provided in the NRC endorsement letter dated January 8, 2014; or alternatively, justify the boric acid mixing assumptions that will ensure adequate shutdown margin exists through all 3 phases of an ELAP event.

111. Open Item 3.2.4.8.A Complete The strategy to use a pre-staged portable diesel generator to supply ac power directly to the vital battery chargers is an alternative approach for satisfying the Mitigating Strategies Order, which relies primarily on portable equipment. Verify that this strategy provides the equivalent level of flexibility for responding to an undefined event as would be achieved through conformance with the endorsed guidance of NEI 12-06.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/1 4-0083 18 Pages (including cover sheet)

Item # New Open, ISE Open, and Confirmatory Items Status 112. Confirmatory Item 3.1.1.1 .A Started Confirm that the final design of the FLEX equipment storage building and location ensures that FLEX equipment such as pumps and power supplies will be secured, and that stored equipment and structures will be protected from seismic interactions, high wind events, and extreme temperature conditions.

113. Confirmatory Item 3.1.1.2.A Started Confirm that the vehicles and equipment provided for debris removal will be protected from seismic events.

114. Confirmatory Item 3.1.1.2.B.1 Started Confirm that all site travel paths and deployment routes for FLEX equipment have been analyzed to ensure survivability following a seismic event.

115. Confirmatory Item 3.1.1.2.B.2 Started Confirm that the deployment strategies for FLEX equipment ensure that connection points are protected and that key areas are accessible through seismically robust structures following a seismic event.

116. Confirmatory Item 3.1.1.3.A Started Confirm that guidance will be made available to operators on critical actions to perform while establishing alternate indication for key instruments and on how to control critical equipment without control power.

117. Confirmatory Item 3.1.1.4.A Complete Off-Site Resources - Confirm the identification of the local staging area, the evaluation of access routes, and the method of transportation to the site for the RRC provided equipment.

118. Confirmatory Item 3.1.5.2.A Complete Confirm that potential problems with door access, such as sheet metal expansion or swollen door seals due to high temperature conditions, will be mitigated.

119. Confirmatory Item 3.2.1 .A Complete Confirm that the generic ELAP analyses in WCAP-1 7601 -P, "Reactor Coolant System Response to the Extended Loss of AC Power Event for Westinghouse, Combustion Engineering and Babcock & Wilcox NSSS Designs," (ADAMS Accession Nos. ML13042A011 and ML13042A013, non-public), are applicable to RNP, and specifically, that the important parameters and assumptions used are representative and appropriate for simulating the ELAP transient.

120. Confirmatory Item 3.2.1 .B Complete Confirm that the RNP FLEX mitigation strategies address each of the 7 PWROG recommendations listed in Section 3.2 of WCAP-17601-P.

This information should include the rationale for whether each issue is applicable to the plant, how the applicable recommendations have been considered in the ELAP coping analysis, and how they will be implemented in the RNP mitigating strategies.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

Item # New Open, ISE Open, and Confirmatory Items Status 121. Confirmatory Item 3.2.1.C Complete Confirm that the SG PORVs will be provided with motive force and adequately protected from hazards so that they can function as required for the RNP mitigating strategies.

122. Confirmatory Item 3.2.1.E Not Confirm that the configurations of the SDAFW pump steam traps and Started mini-flow recirculation line are such that the pump will not be rendered inoperable if the lines are damaged.

123. Confirmatory Item 3.2.1.1 .A Started Confirm that the application of the NOTRUMP code for the ELAP analysis for RNP is limited to the flow conditions prior to reflux condensation initiation. This includes specifying an acceptable definition for reflux condensation cooling.

124. Confirmatory Item 3.2.1.2.A Complete Confirm that the impacts of the Westinghouse 10 CFR Part 21 report, "Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21," dated July 26, 2013 (ADAMS Accession No. ML13211A168) on the use of the low seal leakage rate have been addressed in the ELAP analysis for RNP. (Note: The TER, on page 27 of 60, listed an incorrect ADAMS accession number for the August 16, 2013, PWROG position paper on RCP seal leakage; it should be ML13235A151 ).

125. Confirmatory Item 3.2.1.2.B Complete If the RCP seals are changed to the newly designed Generation 3 SHIELD seals or non-Westinghouse seals, confirm that acceptable justification is provided for the seal leakage rates used in the revised ELAP analysis for RNP.

126. Confirmatory Item 3.2.1.3.A Not Started used in the Confirm that appropriate methods and assumptions are decay heat calculations for RNP for an ELAP event. This should include justification for the model and the values used for the key parameters.

127. Confirmatory Item 3.2.1.6.A Complete Confirm that the revised analyses for makeup rates, boration strategies, and core cooling times based on the use of low leakage RCP seals are adequately justified and appropriately reflected in the sequence of events timeline.

128. Confirmatory Item 3.2.1.6.8 Complete Confirm that the revised safety injection accumulator isolation strategy will ensure timely isolation to prevent nitrogen injection into the RCS.

129. Confirmatory Item 3.2.1.8.A Complete Confirm that the revised boration strategies ensure that acceptable shutdown margin will be maintained throughout all phases of an ELAP event.

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

Item # New Open, ISE Open, and Confirmatory Items Status 130. Confirmatory Item 3.2.1.9.A Started Confirm that the design requirements and supporting analyses for the portable FLEX pumps show that they are capable of performing their respective functions as credited in the mitigating strategies.

131. Confirmatory Item 3.2.3.A Started Confirm that the RNP strategies for maintaining containment are consistent with the containment pressure and temperature analysis for all 3 phases of an ELAP event.

132. Confirmatory Item 3.2.4.1.A Complete Confirm that cooling water will be supplied, as needed, to plant equipment credited to perform a mitigation strategies function under ELAP conditions.

133. Confirmatory Item 3.2.4.2.A Started Confirm that actions necessary to ensure equipment functionality and personnel habitability during an ELAP event are appropriately incorporated into the FLEX strategies, based on the analyses of the impact of high temperatures on various areas/compartments {main control room, battery room, SDAFW pump room).

134. Confirmatory Item 3.2.4.2.B Started Confirm that adequate ventilation is provided to the battery rooms to prevent unacceptable levels of hydrogen accumulation.

135. Confirmatory Item 3.2.4.2.B Started Confirm that appropriate actions are implemented to address the loss of heat tracing on instrument lines under ELAP conditions.

136. Confirmatory Item 3.2.4.4.A Started The NRC staff has reviewed the licensee communications assessment (ADAMS Accession Nos. ML12311A299 and ML13058A045) and has determined that the assessment is reasonable (ADAMS Accession No. ML13105A413). Confirm that upgrades to the site's communications systems have been completed.

137. Confirmatory Item 3.2.4.7.A Complete Confirm that alternate sources of cooling water, such as Lake Robinson or the discharge canal, have been evaluated for the potential impacts of reduced water quality, and that actions to address water quality have been developed, as needed to ensure the successful implementation of the RNP mitigating strategies.

138. Confirmatory Item 3.2.4.9.A Started Confirm that the methods and sources for refueling the FLEX equipment are consistent with the analyzed fuel consumption rates of all portable generators and pumping equipment.

139. Confirmatory Item 3.2.4.10.A Started Confirm the sizing calculations for the FLEX DGs to show that they can

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/1 4-0083 18 Pages (including cover sheet)

Item # New Open, ISE Open, and Confirmatory Items Status supply the loads assumed in Phases 2 and 3.

140. Confirmatory Item 3.2.4.10.B Complete Confirm that the ELAP load shed analysis has adequately accounted for the loss of functions and has addressed any impacts on defense in depth and redundancy.

141. Confirmatory Item 3.3.1.A Not Started Confirm that the licensee's implementation of maintenance and testing guidance for FLEX equipment conforms to the generic approach endorsed by the staff, or constitutes an acceptable alternate approach.

The generic approach is.provided in the EPRI technical report on preventive maintenance of FLEX equipment, submitted by NEI by letter dated October 3, 2013 (ADAMS Accession No. ML13276A573). The NRC staff's endorsement letter is dated October 7, 2013 (ADAMS Accession No. ML13276A224).

142. Confirmatory Item 3.4.A Complete Confirm that NEI 12-06, Section 12.2, guidelines 2 through 10, regarding minimum capabilities for offsite resources, have been adequately addressed.

143. Duke Energy will incorporate the supplemental guidance provided in the Not NEI position paper entitled "Shutdown/Refueling Modes" to enhance the Started shutdown risk process and procedures.

144. Incorporate the SG cooldown MSIV bypass strategy (EPP-1, Attachment Not

4) into the new ECA-0.0 (ELAP) or an FSG. Started

7. References The following references support the updates to the Overall Integrated Plan described in this attachment.

1. Duke Energy Letter, Carolina Power and Light Company's 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 26, 2013 (ADAMS Accession No. ML13071A415).

2. Duke Energy Letter, H. B. Robinson Steam Electric Plant, Unit No. 2, 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), dated August 28, 2013 (ADAMS Accession No. ML13252A243).

3. Duke Energy Letter, H. B. Robinson Steam Electric Plant, Unit No. 2, Second 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), dated February 24, 2014 (ADAMS Accession No. ML14063A283)

4. NRC Order Number EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12, 2012 (ADAMS Accession No. ML12054A735).

U. S. Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0083 18 Pages (including cover sheet)

5. EC EVAL 88926 Rev. 3, FLEX Strategies and Implementation Plan

6. H.B. Robinson Steam Electric Plant, Unit 2 -Interim Staff Evaluation Regarding Overall Integrated Plan In Response To Order EA-12-049 (Mitigation Strategies) (TAC NO. MF0720),

dated 2/19/14 (ADAMS Accession No. ML13365A291).

7. NRC letter from Jack R. Davis, Director Mitigating Strategies Directorate Office of Nuclear Reactor Regulation, to Nuclear Energy Institute, Mr. Joseph E. Pollock, Vice President Nuclear Operations, dated September 16, 2013, (ADAMS Accession No. ML1 3241 Al 88)

8. NRC letter from Jack R. Davis, Director Mitigating Strategies Directorate Office of Nuclear Reactor Regulation, to Nuclear Energy Institute, Mr. Joseph E. Pollock, Vice President Nuclear Operations, dated October 7, 2013, (ADAMS Accession No. ML13276A224

9. NRC letter from Jack R. Davis, Director Mitigating Strategies Directorate Office of Nuclear Reactor Regulation, to Jack Stringfellow, PWROG PWR Owners Group, Program Management Office Westinghouse Electric Company LLC, dated January 8, 2014, (ADAMS Accession No. ML13276A183)

10. NRC letter from Jack R. Davis, Director Mitigating Strategies Directorate Office of Nuclear Reactor Regulation, to Nuclear Energy Institute, Mr. Joseph E. Pollock, Vice President Nuclear Operations, dated September 30, 2013, (ADAMS Accession No. ML13267A382)

11. EDMG-004, Steam Generators

12. RNP-M/MECH-1712, Appendix R Mechanical Basis Calculation, section 3.27, Cooldown Using MSIV Bypass Lines

13. WCAP-1 7601 -P, "Reactor Coolant System Response To The Extended Loss Of AC Power Event For Westinghouse, Combustion Engineering And Babcock & Wilcox NSSS Designs"

14. EC 90623, New Pipe Tee and Standard Connection for NTTF 4.2 (FLEX)

15. EC 94741, Circulating Water Supply to Steam Driven Aux Feedwater Pump Suction During ELAP and/or LUHS

16. PA-PSC-0965, PWROG PSC - ELAP CORE TEAM Core Cooling Management Interim Position Paper, Revision 0