RS-14-058, Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
ML14184A018 | |
Person / Time | |
---|---|
Site: | Dresden |
Issue date: | 06/30/2014 |
From: | Kaegi G Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
EA-13-109, RS-14-058 | |
Download: ML14184A018 (49) | |
Text
A Exelon Generation.
Order No. EA-13-109 RS-14-058 June 30, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
References:
- 1. NRC Order Number EA-13-109, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013
- 2. NRC Interim Staff Guidance JLD-ISG-2013-02, "Compliance with Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions", Revision 0, dated November 14, 2013
- 3. Exelon Generation Company, LLC's Answer to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated June 26, 2013
- 4. NEI 13-02, "Industry Guidance for Compliance With Order EA-1 3-109, BWR Mark I & II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions", Revision 0, dated November 2013
- 5. NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent, dated September 1, 1989 On June 6, 2013, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an order (Reference 1) to Exelon Generation Company, LLC (EGC). Reference 1 was immediately effective and directs EGC to require their BWRs with Mark I and Mark II containments to take certain actions to ensure that these facilities have a hardened containment vent system (HCVS) to remove decay heat from the containment, and maintain control of containment pressure within acceptable limits following events that result in loss of active containment heat removal capability while maintaining the capability to operate under severe accident (SA) conditions resulting from an Extended Loss of AC Power (ELAP). Specific requirements are outlined in Attachment 2 of Reference 1.
Reference 1 requires submission of an Overall Integrated Plan (OIP) by June 30, 2014 for Phase 1 of the Order. The interim staff guidance (Reference 2) was issued November 14, 2013, which
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-13-109 June 30, 2014 Page 2 provides direction regarding the content of this OIP. Reference 3 provided the EGC initial status report regarding reliable hardened containment vents capable of operation under severe accident conditions. The purpose of this letter is to provide the OIP for Phase 1 of the Order pursuant to Section IV, Condition D.1, of Reference 1. This letter confirms EGC has received Reference 2 and has a Phase 1 0IP complying with the guidance for the purpose of ensuring the functionality of a HCVS to remove decay heat from the containment, and maintain control of containment pressure within acceptable limits following events that result in the loss of active containment heat removal capability while maintaining the capability to operate under SA conditions resulting from an ELAP as described in Attachment 2 of Reference 1.
Reference 4, Section 7.0 contains the specific reporting requirements for the OIP. The information in the Enclosure provides the Dresden Nuclear Power Station, Units 2 and 3 Phase 1 OIP pursuant to Reference 2. The enclosed OIP is based on conceptual design information.
Final design details and associated procedure guidance, as well as any revisions to the information contained in the Enclosure, will be provided in the 6-month OIP updates required by Section IV, Condition D.3, of Reference 1.
For the purposes of compliance with Phase 1 of Order EA-1 3-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, Dresden Nuclear Power Station, Units 2 and 3 plans to install a severe accident capable wetwell vent.
Compliance with the requirements of Reference 1 will supersede any and all actions or commitments associated with Reference 5. Any actions or commitments made relative to Reference 5 are rescinded and not binding by submittal of the Reference 1 Phase 1 OIP via this letter.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 30'h day of June 2014.
Respectfully submitted, Glen T. Kaegi Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Enclosure:
- 1. Dresden Nuclear Power Station, Units 2 and 3, Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-13-109 June 30, 2014 Page 3 cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Project Manager, NRR - Dresden Nuclear Power Station Mr. William D. Reckley, NRR/JLD/PSB, NRC Mr. Rajender Auluck, NRR/JLD/PSB, NRC Illinois Emergency Management Agency - Division of Nuclear Safety
Enclosure 1 Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions (45 pages)
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Table of Contents:
Introduction:
Part 1: General Integrated Plan Elements and Assumptions Part 2: Boundary Conditions for Wet Well Vent Part 3: Boundary Conditions for Dry Well Vent Part 4: Programmatic Controls, Training, Drills and Maintenance Part 5: Milestones Schedule Attachment 1: HCVS Portable Equipment Attachment 2: Sequence of Events Timeline Attachment 3: Conceptual Sketches Attachment 4: Failure Evaluation Table Attachment 5: References Attachment 6: Changes/Updates to this Overall Integrated Implementation Plan Attachment 7: List of Overall Integrated Plan Open Items Page 1 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Introduction In 1989, the NRC issued Generic Letter 89-16, "Installation of a Hardened Wetwell Vent,"
to all licensees of BWRs with Mark I containments to encourage licensees to voluntarily install a hardened wetwell vent. In response, licensees installed a hardened vent pipe from the wetwell to some point outside the secondary containment envelope (usually outside the reactor building). Some licensees also installed a hardened vent branch line from the drywell.
On March 19, 2013, the Nuclear Regulatory Commission (NRC) Commissioners directed the staff per Staff Requirements Memorandum (SRM) for SECY 0157 to require licensees with Mark I and Mark II containments to "upgrade or replace the reliable hardened vents required by Order EA- 12-050 with a containment venting system designed and installed to remain functional during severe accident conditions." In response, the NRC issued Order EA-13-109, Issuance of Order to Modify Licenses with Regard to Reliable HardenedContainment Vents Capable of Operation Under Severe Accidents, June 6, 2013. The Order (EA-13-109) requires that licensees of BWR facilities with Mark I and Mark II containment designs ensure that these facilities have a reliable hardened vent to remove decay heat from the containment, and maintain control of containment pressure within acceptable limits following events that result in the loss of active containment heat removal capability while maintaining the capability to operate under severe accident (SA) conditions resulting from an Extended Loss of AC Power (ELAP).
The Order requirements are applied in a phased approach where:
" "Phase 1 involves upgrading the venting capabilities from the containment wetwell to provide reliable, severe accident capable hardened vents to assist in preventing core damage and, if necessary, to provide venting capability during severe accident conditions." (Completed "no later than startup from the second refueling outage that begins after June 30, 2014, or June 30, 2018, whichever comes first.")
- "Phase 2 involves providing additional protections for severe accident conditions through installation of a reliable, severe accident capable drywell vent system or the development of a reliable containment venting strategy that makes it unlikely that a licensee would need to vent from the containment drywell during severe accident conditions." (Completed "no later than startup from the first refueling outage that begins after June 30, 2017, or June 30, 2019, whichever comes first.")
The NRC provided an acceptable approach for complying with Order EA-13-109 through Interim Staff Guidance (JLD-ISG-2013-02) issued in November 2013. The ISG endorses the compliance approach presented in NEI 13-02 Revision 0, Compliance with Order EA-Page 2 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions13-109, Severe Accident Reliable Hardened Containment Vents, with clarifications.
Except in those cases in which a licensee proposes an acceptable alternative method for complying with Order EA-13-109, the NRC staff will use the methods described in this ISG (NEI 13-02) to evaluate licensee compliance as presented in submittals required in Order EA- 13-109.
The Order also requires submittal of an overall integrated plan which will provide a description of how the requirements of the Order will be achieved. This document provides the Overall Integrated Plan (OIP) for complying with Order EA- 13-109 using the methods described in NEI 13-02 and endorsed by NRC JLD-ISG-2013-02. Six month progress reports will be provided consistent with the requirements of Order EA-13-109.
Dresden venting actions for the EA-13-109 severe accident capable venting scenario can be summarized by the following:
" The HCVS will be initiated via manual action from the Main Control Room (MCR) or Remote Operating Station (ROS) at the appropriate time based on procedural guidance in response to plant conditions from observed or derived symptoms.
" The vent will utilize Containment Parameters of Pressure and Wetwell (WW)
Water Level from the MCR instrumentation to monitor effectiveness of the venting actions.
" The vent operation will be monitored by HCVS valve position, temperature, pressure and effluent radiation levels.
" The HCVS motive force will be monitored and have the capacity to operate for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with installed equipment. Replenishment of the motive force will be by use of portable equipment once the installed motive force is exhausted.
" Venting actions will be capable of being maintained for a sustained period of up to 7 days or a shorter time if justified.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 1: General Inte2rated Plan Elements and Assumptions Extent to which the guidance, JLD-ISG-2013-02 and NEI 13-02, are being followed. Identify any deviations.
Include a descriptionof any alternatives to the guidance. A technicaljustificationand basisfor the alternative needs to be provided. This will likely require a pre-meeting with the NRC to review the alternative.
Ref: JLD-ISG-2013-02 Compliance will be attained for Dresden with no known deviations to the guidelines in JLD-ISG-2013-02 and NEI 13-02 for each phase as follows:
- Unit 3 Phase 1 (wetwell): by the startup from the second refueling outage that begins after June 30, 2014, or June 30, 2018, whichever comes first. Currently scheduled for 4Q2016
" Unit 2 Phase 1 (wetwell): by the startup from the second refueling outage that begins after June 30, 2014, or June 30, 2018, whichever comes first. Currently scheduled for 4Q2017.
- Unit 2 Phase 2 (drywell): by the startup from the first refueling outage that begins after June 30, 2017, or June 30, 2019, whichever comes first. Currently scheduled for 4Q2017
" Unit 3 Phase 2: (drywell): by the startup from the first refueling outage that begins after June 30, 2017, or June 30, 2019, whichever comes first. Currently scheduled for 4Q2018 If deviations are identified at a later date, then the deviations will be communicated in a future 6 month update following identification.
State Applicable Extreme External Hazard from NEI 12-06, Section 4.0-9.0 List resultant determinationof screened in hazardsfrom the EA-12-049 Compliance.
Ref: NEI 13-02 Section 5.2.3 and D.1.2 The following extreme external hazards screen-in for Dresden
- Seismic, External Flooding, Extreme Cold, High Wind, Extreme High Temperature (only list those that screen-in)
The following extreme external hazards screen out for Dresden
Provide key assumptions associatedwith implementation of HCVS Phase ]Actions Ref: NEI 13-02 Section 1 Mark I/II Generic HCVS Related Assumptions:
Anolicable EA-12-049 assumutions:
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 1: General Integrated Plan Elements and Assumptions 049-1. Assumed initial plant conditions are as identified in NEI 12-06 section 3.2.1.2 items 1 and 2 049-2. Assumed initial conditions are as identified in NEI 12-06 section 3.2.1.3 items 1, 2, 4, 5, 6 and 8 049-3. Assumed reactor transient boundary conditions are as identified in NEI 12-06 section 3.2.1.4 items 1, 2, 3 and 4 049-4. No additional events or failures are assumed to occur immediately prior to or during the event, including security events, except for failure of RCIC or HPCI. (Reference NEI 12-06,section 3.2.1.3 item 9) 049-5. At Time=0 the event is initiated and all rods insert and no other event beyond a common site ELAP is occurring at any or all of the units. (NEI 12-06, section 3.2.1.3 item 9 and 3.2.1.4 item 1-4) 049-6. At 60 minutes (time critical at a time greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) an ELAP is declared and actions begin as defined in EA-12-049 compliance 049-7. DC power and distribution can be credited for the duration determined per the EA-12-049 (FLEX) methodology for battery usage, (greater than approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with a calculation limiting value of approximately 6 hrs.) (NEI 12-06, section 3.2.1.3 item 8) 049-8. Deployment resources are assumed to begin arriving at hour 6 and fully staffed by 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 049-9. All activities associated with plant specific EA- 12-049 FLEX strategies that are not specific to implementation of the HCVS, including such items as debris removal, communication, notifications, SFP level and makeup, security response, opening doors for cooling, and initiating conditions for the event, can be credited as previously evaluated for FLEX.
Applicable EA-13-109 generic assumptions:
109-1. Site response activities associated with EA-13-109 actions are considered to have no access limitations associated with radiological impacts while RPV level is above 2/3 core height (core damage is not expected).
109-2. Portable equipment can supplement the installed equipment after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided the portable equipment credited meets the criteria applicable to the HCVS. The portable equipment (e.g., compressor, generator) used to replenish HCVS components must be demonstrated to meet the "SA Capable" criteria that are defined in NEI 13-02 Section 4.2.4.2 and Appendix D Section D.1.3.
109-3. SFP Level is maintained with either on-site or off-site resources such that the SFP does not contribute to the analyzed source term (Reference HCVS-FAQ-07) 109-4. Existing containment components design and testing values are governed by existing plant containment criteria (e.g., Appendix J) and are not subject to the testing criteria from NEI 13-02 (reference HCVS-FAQ-05 and NEI 13-02 section 6.2.2).
109-5. Classical design basis evaluations and assumptions are not required when assessing the operation of the HCVS. The reason this is not required is that the order postulates an unsuccessful mitigation of an event such that an ELAP progresses to a severe accident with ex-vessel core debris which classical design basis evaluations are intended to prevent.
(Reference NEI 13-02 section 2.3.1).
109-6. HCVS manual actions that require minimal operator steps and can be performed in the Page 5 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 1: General Integrated Plan Elements and Assumptions postulated thermal and radiological environment at the location of the step(s)(e.g., load stripping, control switch manipulation, valving-in nitrogen bottles) are acceptable to obtain HCVS venting dedicated functionality. (reference HCVS-FAQ-01) 109-7. HCVS dedicated equipment is defined as vent process elements that are required for the HCVS to function in an ELAP event that progresses to core melt ex-vessel. (reference HCVS-FAQ-02 and White Paper HCVS-WP-01) 109-8. Use of MAAP Version 4 or higher provides adequate assurance of the plant conditions (e.g.,
RPV water level, temperatures, etc.) assumed for Order EA-13-109 BDBEE and SA HCVS operation. (reference FLEX MAAP Endorsement ML13190A201) Additional analysis using RELAP5/MOD 3, GOTHIC, PCFLUD, LOCADOSE and SHIELD are acceptable methods for evaluating environmental conditions in areas of the plant provided the specific version utilized is documented in the analysis.
109-9. Utilization of NRC Published Accident evaluations (e.g., SOARCA, SECY-12-0157, and NUREG 1465) as related to Order EA-13-109 conditions are acceptable as references.
(reference NEI 13-02 section 8) 109-10. Permanent modifications installed per EA-12-049 are assumed implemented and may be credited for use in EA-13-109 Order response.
109-11. This Overall Integrated Plan is based on Emergency Operating Procedure changes consistent with EPG/SAGs Revision 3 as incorporated per the sites EOP/SAMG procedure change process.
109-12. Under the postulated scenarios of order EA-13-109 the Control Room is adequately protected from excessive radiation dose per General Design Criterion (GDC) 19 in 10CFR50 Appendix A and no further evaluation of its use as the preferred HCVS control location is required. (reference HCVS-FAQ-01) In addition, adequate protective clothing and respiratory protection is available if required to address contamination issues.
Plant Specific HCVS Related Assumptions/Characteristics:
Dresden-1 EA- 12-049 (FLEX) actions to restore power are sufficient to ensure continuous operation of non-dedicated containment instrumentation. FLEX DG power is also credited with the back-up capability stipulated in EA-13-109 requirement 1.2.5 for opening the upstream Torus PCIV.
Dresden -2 In case of a severe flood warning, the Dresden units will be shutdown and cooldown prior to the flooding causing an ELAP. The shutdown and cooldown prior to the ELAP will significantly reduce the decay heat that would have to be removed by the Isolation Condenser System (ICS) or, in case of a failure of the ICS, by the HCVS. Dresden will evaluate what actions may be necessary to ensure the WW venting path remains viable following a severe flood.
Open Item 1: Confirm that at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> battery coping time is available.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 1: General Integrated Plan Elements and Assumptions Open Item 2: Determine actions to enable WW venting following flooding around the torus.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Provide a sequence of events and identify any time or environmental constraint required for success including the basis for the constraint.
HCVS Actions that have a time constraintto be successful should be identified with a technical basis and a justificationprovided that the time can reasonably be met (for example, action to open vent valves).
HCVS Actions that have an environmental constraint(e.g. actions in areasof High Thermal stress or High Dose areas)should be evaluated per guidance.
Describe in detail in this section the technical basisfor the constraintsidentified on the sequence of events timeline attachment.
See attachedsequence of events timeline (A ttachment 2)
Ref: EA-13-109 Section 1.1.1, 1.1.2, 1.1.3/NEI 13-02 Section 4.2.5, 4.2.6. 6.1.1 The containment purge exhaust at each Dresden unit consists of a wetwell primary containment isolation valve (PCIV), a DW PCIV, and a common downstream PCIV. The HCVS flow path will utilize portions of this system. The HCVS will connect upstream of the existing downstream PCIV.
Consequently, the HCVS flow path will share the upstream PCIVs with the containment purge system, but it will have a downstream PCIV dedicated to the HCVS flow path. The new HCVS flow path will have a dedicated secondary containment isolation valve. Each unit will have piping that is totally separate from the other unit and with no interconnected systems downstream of the new downstream PCIV. The discharge from each unit is routed separately and discharges above the unit's Reactor Building roof.
Each unit will have dedicated motive power (Pressurized N2) for HCVS valves and dedicated DC power for HCVS components that is not shared with any other function and that does not rely on FLEX, with the clarification that existing containment instrumentation (pressure and wetwell level) are not considered HCVS components and power will be maintained through the actions for EA 049.
The operation of the HCVS will be designed to minimize the reliance on operator actions in response to hazards listed in Part 1. Immediate operator actions will be completed by plant personnel and will include the capability for remote-manual initiation from the HCVS control station. A list of the remote manual actions performed by plant personnel to open the HCVS vent path can be found in the following table (2-1). A HCVS Extended Loss of AC Power (ELAP) Failure Evaluation table, which shows alternate actions that can be performed, is included in Attachment 4.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Table 2-1 HCVS Remote Manual Actions Primary Action Primary Location/ Notes Component
[
[
valves i
- 3. Check shut the DW MCR Precautionary steps; these valves are PCIV 2(3)-1601-23, I normally shut and fail shut.
t the downstream PCIV to the containment purge exhaust 2(3)-
1601-24, and downstream PCIV to the SGTS 2(3)-1601-63
-.4--
- 4. Open Wetwell PCIV Override the containment Back-up capability in the MCR provided by 2(3)-1601-60 isolation signal and open redundant SOV powered by FLEX DG the PCIV in the HVCS Panel
- 5. Open the downstream Key locked hand switch Alternate control via manual valves at the PCIV on the common located in the HVCS ROS HCVS line Panel
- 6. Open HCVS SCIV Key locked hand switch Alternate control via manual valves at the located in the HVCS ROS Panel
- 7. Align FLEX Generator As described in response Prior to depletion of station battery.
to maintain power to to EA- 12-049 Required to maintain power to containment Station Battery instrumentation. Also, credited for satisfying Requirement 1.2.5 of the SACV order.
. .R. . ....-..................
- 8. Align generator to At ROS iPrior to depletion of the HCVS battery HCVS battery charger. supply, actions will be required to recharge the battery.
- 9. Replace N2 motive Replacement Nitrogen Prior to depletion of the pneumatic sources.
power bottles or align bottles and/or compressor actions will be required to connect back-up will be located at the Page 9 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent portable compressor ROS. isources at a time greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Open Item 3: Determine how HCVS DC Power and/or Motive Power will be disabled during normal operation to provide assurancesagainstinadvertent operation,but to also minimize actions to enable operationfollowing an ELAP.
A timeline was developed to identify required operator response times and potential environmental constraints. This timeline is based upon the following three cases:
- 1. Case 1 is based upon the action response times developed for Dresden FLEX in a BDBEE without core damage. Containment venting is not required for Dresden FLEX response since the Isolation Condenser System (ICS) removes all the decay heat from the reactor and the containment does not become pressurized enough to require venting. Dresden does not have a RCIC system but it has a steam driven High Pressure Coolant Injection System (HPCI).
- 2. Case 2 is based on a SECY-12-0157 long term station blackout (LTSBO) (or ELAP) with failure of RCIC after a black start where failure occurs because of subjectively assuming over injection. It is used for Dresden to represent a late failure of the ICS and HPCI. Late failure of the ICS is due to the assumption that FLEX fails to provide make-up water to the ICS.
- 3. Case 3 is based on NUREG-1935 (SOARCA) results for a prolonged SBO (or ELAP) with the loss of RCIC case without black start. For Dresden, this represents that the ICS fails after its initial water volume is expended (i.e., no FLEX make-up to the ICS), and the HPCI fails early at a pool temperature of 140'F.
Discussion of time constraints identified in Attachment 2 for the 3 timeline cases identified above
- With Case 1 (ICS operating), HCVS operation is not required since the only heat input into the containment is from RCS leaks and ambient losses to the environment.
" For Case 3 (limiting case), in approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, initiate use of Hardened Containment Vent System (HCVS) per site procedures to maintain containment parameters below the lower of PCPL or containment design pressure. Reliable operation of HCVS will be met because HCVS meets the seismic requirements identified in NEI 13-02, will be powered by DC power from a dedicated power source, and HCVS valves are supplied with motive force from portable nitrogen bottles. HCVS controls and instrumentation and controls will be DC powered. HCVS valve motive force is from pressurized gas. Valves will be operable from the HCVS control panel in the MCR. DC power and motive air will be available for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from permanent sources. Containment pressure and WW indication will be initially powered from existing IE Station battery and maintained by FLEX generators. Thus, initiation of the HCVS from the MCR or the Remote Operating Station within approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is acceptable because the actions can be performed any time after declaration of an ELAP until the venting is needed at approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for BDBEE venting. This action can also be performed for SA HCVS Page 10 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent operation which occurs at a time further removed from an ELAP declaration as shown in Attachment 2.
" Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the permanently installed nitrogen bottles at the ROS will be replaced, as required, to maintain sustained operation or alternatively a portable compressor will be connect at the ROS. This can be performed at any time prior to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to ensure adequate capacity is maintained; therefore, this time constraint is not limiting.
" Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a portable generator will be installed and connected to recharge the dedicated HCVS power supply to maintain sustained operation. This can be performed any time prior to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; therefore, this time constraint is not limiting.
" Current Dresden battery durations are calculated to last 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. FLEX pre-staged DG will be in service 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after an event (Reference FLEX OIP). Thus, the FLEX DGs will be available to be placed in service at any point after approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> as required to supply power to containment parameters (containment pressure and WW level). A FLEX DG will be maintained and used in on-site FLEX storage buildings. For the flood event, the DG will be transferred and staged via haul routes and staging areas evaluated for impact from external hazards.
Modifications will be implemented to facilitate the connections and operational actions required to supply power within approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> which is acceptable because the actions can be performed any time after declaration of an ELAP until the repowering is needed at greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Discussion of radiological and temperature constraints identified in Attachment 2
" Actions to initiate HCVS operation are taken from the MCR or from the ROS in the Turbine Building. Both locations have significant shielding and/or physical separation from radiological sources. Non-radiological habitability for the MCR is being addressed as part of the Dresden FLEX response. The location in the Turbine Building has no heat generating sources.
" Before the end of the initial 24-hour period, replenishment of the HCVS dedicated DC power and motive power (pressurized gas) will occur at the ROS. The selection of the ROS location will take into account the SA temperature and radiation condition to ensure access to the ROS is maintained. The design will allow replenishment with minimal actions.
Open Item 1: Confirm that at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> battery coping time is available.
Open Item 4: Confirm that the ROS will be in an accessible areafollowing a SA.
Provide Details on the Vent characteristics Vent Size and Basis (EA-13-109 Section 1.2.1 /NEI 13-02 Section 4.1.1)
What is the plants licensed power? Discuss any plansfor possible increases in licensed power (e.g.
Page 11 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent MUR, EPU).
What is the nominal diameter of the vent pipe in inches! Is the basis determined by venting at containment design pressure, Primary Containment Pressure Limit (PCPL), or some other criteria (e.g. anticipatory venting)?
Vent Capacity (EA-13-109 Section 1.2.1 /NEI 13-02 Section 4.1.1)
Indicate any exceptions to the 1% decay heat removal criteria, including reasonsfor the exception.
Provide the heat capacity of the suppressionpool in terms of time versus pressurizationcapacity, assuming suppressionpool is the injection source.
Vent Path and Discharme (EA-13-109 Section 1.1.4. 1.2.2/ NEI 13-02 Section 4.1.3. 4.1.5 and Appendix FIG)
Provides a description of Vent path, releasepath, and impact of vent path on other vent element items.
Power and Pneumatic Supply Sources (EA-13-109 Section 1.2.5 & 1.2.6 / NEI 13-02 Section 4.2.3, 2.5, 4.2.2, 4.2.6, 6.1)
Provide a discussion of electricalpower requirements, including a description of dedicated 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> power supply from permanently installed sources. Include a similar discussionas above for the valve motive force requirements.Indicate the area in the plantfrom where the installed/dedicatedpower and pneumatic supply sources are coming Indicate the areas where portableequipment will be staged after the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, the dose fields in the area, and any shielding that would be necessary in that area.Any shielding that would be provided in those areas Location of Control Panels (EA-13-109 Section 1.1.1. 1.1.2. 1.1.3. 1.1.4, 1.2.4, 1.2.5 / NEI 13-02 Section 4.1.3. 4.2.2. 4.2.3. 4.2.5, 4.2.6. 6.1.1 andAppendix FIG)
Indicate the location of the panels, and the dose fields in the area during severe accidents and any shielding that would be requiredin the area. This can be a qualitativeassessment based on criteria in NEI 13-02.
Hydrogen (EA-13-109 Section 1.2.10, 1.2.11, 1.2.12 /NEI 13-02 Section 2.3,2.4, 4.1.1, 4.1.6, 4.1.7, 5.1, & Appendix H)
State which approach or combination of approachesthe plant will take to address the control of flammable gases, clearly demarcatingthe segments of vent system to which an approach applies Unintended Cross Flow of Vented Fluids (EA-13-109 Section 1.2.3, 1.2.12 / NEI 13-02 Section 4.1.2, 4.1.4. 4.1.6 and Appendix H)
Provide a descriptionto eliminate/minimize unintended crossflow of vented fluids with emphasis on interfacing ventilation systems (e.g. SGTS). What designfeatures are being included to limit leakage through interfacing valves or Appendix J type testingfeatures?
Page 12 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Prevention of InadvertentActuation (EA-13-109 Section 1.2. 7/NEI 13-02 Section 4.2.1)
The HCVS shall include means to prevent inadvertent actuation Component Qualifications(EA-13-109 Section 2.1 /NEI 13-02 Section 5.1, 5.3)
State qualification criteriabased on use of a combination of safety relatedand augmented quality dependent on the location,function and interconnectedsystem requirements Monitoring of HCVS (OrderElements 1.1.4, 1.2.8, 1.2.9/NEI 13-02 4.1.3, 4.2.2, 4.2.4, and Appendix FIG)
Provides a description of instruments used to monitor HCVS operationand effluent. Powerfor an instrument will require the intrinsicallysafe equipment installed as part of the power sourcing Component reliable and rugged Performance (EA-13-109 Section 2.2 / NEI 13-02 Section 5.2, 5.3)
HCVS components including instrumentationshould be designed, as a minimum, to meet the seismic design requirements of the plant.
Components including instrumentationthat are not requiredto be seismically designed by the design basis of the plant should be designedfor reliable and rugged performance that is capable of ensuring HCVSfunctionalityfollowing a seismic event. (reference ISG-JLD-2012-01 and ISG-JLD-2012-03for seismic details.)
The components including instrumentationexternal to a seismic category I (or equivalentbuilding or enclosure should be designed to meet the external hazards that screen-infor the plant as defined in guidance NEI 12-06 as endorsed by JLD-ISG-12-01 for Order EA-12-049.
Use of instruments and supporting components with known operatingprinciples that are supplied by manufacturers with commercial quality assurance programs, such as IS09001. The procurement specifications shall include the seismic requirements and/or instrument design requirements, and specify the need for commercial design standards and testing under seismic loadings consistent with design basis values at the instrument locations.
Demonstration of the seismic reliability of the instrumentation through methods that predict performance by analysis, qualification testing under simulated seismic conditions, a combination of testing and analysis, or the use of experience data. Guidancefor these is based on sections 7, 8, 9, and 10 of IEEE Standard 344-2004, "IEEERecommended Practicefor Seismic Qualificationof Class 1E Equipmentfor Nuclear Power GeneratingStations," or a substantiallysimilar industrialstandard could be used.
Demonstrationthat the instrumentation is substantially similar in design to instrumentation that has been previously tested to seismic loading levels in accordance with the plant design basis at the location where the instrument is to be installed (g-levels andfrequency ranges). Such testing and analysis should be similar to that performedfor the plant licensing basis.
Page 13 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Vent Size and Basis The HCVS wetwell path is designed for venting steam/energy at a nominal capacity of 1% of the currently licensed power, 2957 MWt thermal power at a drywell pressure of 62 psig. This pressure is the lower of the containment design pressure and the PCPL value assuming nominal torus water level.
The nominal diameter of the upstream HCVS piping, which is part of the containment penetration boundary, is 18 inches which provides adequate capacity to meet or exceed the Order criteria. The new downstream piping, which is dedicated to the HCVS venting function, is estimated to be between 12 to 14 inches in diameter.
Open Item 5: Confirm diameteron new common HCVS piping Vent Cavacity The 1% value at Dresden assumes that the suppression pool pressure suppression capacity is sufficient to absorb the decay heat generated during the first 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. The vent would then be able to prevent containment pressure from increasing above the containment design pressure. As part of the detailed design, the duration of suppression pool decay heat absorption capability will be confirmed.
Open Item 6: Confirm suppressionpool heat capacity.
Vent Path and Discharge The HCVS vent path at Dresden will consist of a wetwell vent on each unit. The wetwell vent line has an upstream primary containment isolation valve (PCIV) shared with the normal containment ventilation system, and a dedicated downstream PCIV. The wetwell vent line will be initially routed vertically through the Reactor Building and then horizontally through the Reactor Building wall. The line then will be routed vertically on the outside of the Reactor Building to a point above the top of the Reactor Building. There will be no interconnected systems downstream of the PCIVs and there will be no sharing of any flow path between the two units.
The HCVS discharge path will be routed to a point above any adjacent structure. This discharge point is just above that unit's Reactor Building and will follow the guidance of FAQ- HCVS-04 (Reference
- 16) to the extent reasonably possible such that the release point will vent away from emergency ventilation system intake and exhaust openings, main control room location, location of HCVS portable equipment, access routes required following a ELAP and BDBEE, and emergency response facilities; however, these must be considered in conjunction with other design criteria (e.g., flow capacity) and pipe routing limitations, to the degree practical.
The detailed design will address missile protection to a maximum height of 30 feet from ground elevation, from external events as defined by NEI 12-06 for the outside portions of the selected release pipe. (reference FAQ HCVS-04)
Page 14 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Power and Pneumatic Supply Sources All electrical power required for operation of HCVS components will be from a dedicated HCVS DC battery source with permanently installed capacity for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and design provisions for recharging to maintain sustained operation.
Motive (pneumatic) power to the HCVS valves will be provided by a dedicated bank of N2 gas bottles with permanently installed capacity for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and design provisions for replacing bottles and/or connecting a portable compressor to maintain sustained operation. The initial stored motive air/gas will allow for a minimum of 12 vent cycles for the HCVS valves for the first 24-hours. The 12 vent cycles is defined as initially opening all valves in the wetwell flow path, and then shutting and reopening one of the valves in the flow path 11 times.
- 1. The HCVS flow path valves are air-operated valves (AOV). The existing, upstream PCIV is air-to-open and air-to-shut. The new downstream PCIV and SCIV will be air-to-open and spring-to-shut. Opening the valves from the HCVS control panel located in the MCR requires energizing a DC powered solenoid operated valve (SOV) and providing motive air/gas.
- 2. An assessment of temperature and radiological conditions will be performed to ensure that operating personnel can safely access and operate controls at the Remote Operating Station based on time constraints listed in Attachment 2.
- 3. All permanently installed HCVS equipment, including any connections required to supplement the HCVS operation during an ELAP (i.e., DC power and motive force [pressurized N2/air])
will be located in areas reasonably protected from defined hazards listed in Part I of this report.
4- All valves required to open the flow path will be designed for remote manual operation following an ELAP, such that the primary means of valve manipulation does not rely on use of a handwheel, reach-rod or similar means that requires close proximity to the valve (reference FAQ HCVS-03). The preferred method-is opening from the MCR through the control switch that energizes the AOVs SOV. The back-up method for new valves is from the ROS by repositioning valves on the pneumatic air line; this allows opening and closing of a valve from the ROS without reliance on any electrical power or control circuit. Accessibility to the ROS will be verified during the detailed design. The back-up method for existing valves is from the existing valve solenoids operated from the Control Room using FLEX power.
Open item 4: Confirm the ROS will be accessiblefollowing a SA.
- 5. Any supplemental connections will be pre-engineered to minimize man-power resources and address environmental concerns. Required portable equipment will be reasonably protected from screened in hazards listed in Part 1 of this OIP.
- 6. Access to the locations described above will not require temporary ladders or scaffolding.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Location of Control Panels The HCVS design will allow initiating and then operating and monitoring the HCVS from the Main Control Room (MCR) and in addition, opening valve(s) from the ROS and existing control panels in the control room in case of a DC circuit failure. The tentative location for the ROS is 561 elevation Turbine Building. The MCR location is protected from adverse natural phenomena and it is the normal control point for Plant Emergency Response actions. The ROS will be evaluated to ensure acceptable temperature and dose consequences.
Open item 4: Confirm the ROS will be accessiblefollowing a SA.
Hydrogen As is required by EA-13-109, Section 1.2.11, the HCVS must be designed such that it is able to either provide assurance that oxygen cannot enter and mix with flammable gas in the HCVS (so as to form a combustible gas mixture), or it must be able to accommodate the dynamic loading resulting from a combustible gas detonation. Several configurations are available which will support the former (e.g.,
purge, mechanical isolation from outside air, etc.) or the latter (design of potentially affected portions of the system to withstand a detonation relative to pipe stress and support structures).
Dresden will determine the approach or combination of approaches it will take to address the combustible gas mixture. Dresden intends to follow the guidance in HCVS-WP-03, Hydrogen/CO Control Measures.
Open Item 7: Determine the approachfor combustible gases.
Unintended Cross Flow of Vented Fluids The HCVS will use dedicated PCIVs for containment isolation and a dedicated flow path that has neither any interconnected-systems nor sharing with the opposite unit's HCVS. These containment isolation valves will be AOVs that are air-to-open and spring-to-shut.
Prevention of Inadvertent Actuation EOP/ERG operating procedures provide clear guidance that the HCVS is not to be used to defeat containment integrity during any design basis transients and accident. In addition, the HCVS will be designed to provide features to prevent inadvertent actuation due to a design error, equipment malfunction, or operator error such that any credited containment accident pressure (CAP) that would provide net positive suction head to the emergency core cooling system (ECCS) pumps will be available (inclusive of a design basis loss-of-coolant accident (DBLOCA)). However, the ECCS pumps will not have normal power available because of the starting boundary conditions of an ELAP.
Note that Dresden credits CAP for its DBLOCA. Preventing inadvertent operation is addressed. This is confirmed through UFSAR section 6.3.3.4.3.2.
The features that prevent inadvertent actuation will be two PCIVs in series. These valves will be fail-shut AOVs. They are air to open, spring to shut AOVs that require energizing a SOV to allow the Page 16 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent motive air to open the valve. Each PCIV will be controlled by its own key-locked switch. In addition, the DC power to the SOV and the motive air supplied will normally be disabled to prevent inadvertent operation.
Component Oualifications The HCVS components and components that interface with the HCVS will be routed in seismically qualified structures.
HCVS components that are part of the containment pressure boundary will be safety-related. The containment system limits the leakage or release of radioactive materials to the environment to prevent offsite exposures from exceeding the guidelines of 10CFR100. During normal or design basis operations, this means serving as a pressure boundary to prevent release of radioactive material.
HCVS components downstream of the containment pressure boundary (i.e., downstream of the downstream PCIV) will not be safety-related.
The HCVS components (SOVs and instrumentation) will be powered from a normally de-energized, dedicated power supply that will not be safety-related but will be considered Augmented Quality.
However, if any HCVS electrical or controls component interfaces with Class IE power sources, it will be considered safety related up to and including appropriate isolation devices such as fuses or breakers, as their failure could adversely impact containment isolation and/or a safety-related power source. Newly installed piping and valves will be seismically analyzed to handle the forces associated with the Plant Design Basis Seismic Requirements back to their isolation boundaries. Electrical and controls components will be seismically analyzed and will include the ability to handle harsh environmental conditions (although they will not be considered part of the site Environmental Qualification (EQ) program).
HCVS instrumentation performance (e.g., accuracy and precision) need not exceed that of similar plant installed equipment. Additionally, radiation monitoring instrumentation accuracy and range will be sufficient to confirm flow of radionuclides through the HCVS. The HCVS instruments, including valve position indication, process instrumentation, radiation monitoring, and support system monitoring, will be qualified by using one or more of the three methods described in the ISG, which includes:
- 1. Purchase of instruments and supporting components with known operating principles from manufacturers with commercial quality assurance programs (e.g., IS09001) where the procurement specifications include the applicable seismic requirements, design requirements, and applicable testing.
- 2. Demonstration of seismic reliability via methods that predict performance described in IEEE 344-2004
- 3. Demonstration that instrumentation is substantially similar to the design of instrumentation previously qualified.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Instrument Oualification Method*
HCVS Process Temperature IS09001 / IEEE 344-2004 /
Demonstration HCVS Process Pressure IS09001 / IEEE 344-2004 /
Demonstration HCVS Process Radiation Monitor IS09001 / IEEE 344-2004 /
Demonstration HCVS Process Valve Position IS09001 / IEEE 344-2004 /
Demonstration HCVS Pneumatic Supply Pressure IS09001 / IEEE 344-2004 /
Demonstration HCVS Electrical Power Supply IS09001 / IEEE 344-2004 /
Availability Demonstration
- The specific qualification method used for each required HCVS instrument will be reported in future 6 month status reports.
Monitoring of HCVS The Dresden wetwell HCVS will be capable of being remote-manually operated during sustained operations from a control panel located in the main control room (MCR) and will meet the requirements of Order element 1.2.4. The MCR is a readily accessible location with no further evaluation required (Generic Assumption 109-12). Additionally, to meet the intent for a secondary control location of section 1.2.5 of the Order, a readily accessible Remote Operating Station (ROS) will also be incorporated into the HCVS design as described in NEI 13-02 section 4.2.2.1.2.1. The controls and indications at the ROS location will be accessible and functional under a range of plant conditions, including severe accident conditions with due consideration to source term and dose impact on operator exposure, extended loss of AC power (ELAP), and inadequate containment cooling. An evaluation will be performed to determine accessibility to the location, habitability, staffing sufficiency, and communication capability with Vent-use decision makers.
The wetwell HCVS will include means to monitor the status of the vent system in the MCR and to monitor DC power and N2 pressure at the ROS. The proposed design for the HCVS includes control switches in the MCR with valve position indication. The HCVS controls will meet the environmental and seismic requirements of the Order for the plant severe accident with an ELAP. The ability to open/close these valves multiple times during the event's first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be provided by dedicated motive air and DC power. Beyond the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the ability to maintain these valves open or Page 18 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent closed will be maintained by sustaining the motive air and DC power.
The wetwell HCVS will include indications for vent pipe pressure, temperature, and effluent radiation levels at the MCR. Other important information on the status of supporting systems (i.e., DC power source status and pneumatic supply pressure) will also be included in the design and located to support HCVS operation. Other instrumentation that supports HCVS function will be provided in the MCR. This includes existing containment pressure and wetwell level indication. This instrumentation is not required to validate HCVS function and is therefore not powered from the dedicated HCVS batteries. However, these instruments are expected to be available since the FLEX DG supplies the station battery charger for these instruments and will be installed prior to depletion of the station batteries.
Component reliable and rugged performance Unless otherwise required to be safety-related, Augmented Quality requirements will be applied to the components installed in response to this Order.
The HCVS downstream of the second containment isolation valve, including piping and supports, electrical power supply, valve actuator pneumatic supply, and instrumentation (local and remote) components, will be designed/analyzed to conform to the requirements consistent with the applicable design codes (e.g., Non-safety, Seismic Category 1, B31.1) for the plant and to ensure functionality following a design basis earthquake.
Additional modifications required to meet the Order will provide reliability at the postulated vent pipe conditions (temperature, pressure, and radiation levels). The instrumentation/power supplies/cables/connections (components) will be qualified for temperature, pressure, radiation level, total integrated radiation dose appropriate for that location (e.g., near the effluent vent pipe or at the HCVS ROS location).
Conduit design and/or cable trays will be installed to Seismic Class I criteria.
Both existing and new barriers will be used to provide a level of protection from externally generated missiles when equipment is located outside of seismically qualified structures.
If the instruments are purchased as commercial-grade equipment, they will be qualified to operate under severe accident environment as required by NRC Order EA-13-109 and the guidance of NEI 13-02. The equipment will be qualified seismically (IEEE 344), and environmentally (IEEE 323 These qualifications will be bounding conditions for Dresden per UFSAR 1.18 and 6.2.5.3.2.
For the instruments required after a potential seismic event, the following methods will be used to verify that the design and installation is reliable / rugged and thus capable of ensuring HCVS functionality following a seismic event. Applicable instruments are rated by the manufacturer (or Page 19 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent otherwise tested) for seismic impact at levels commensurate with those of postulated severe accident event conditions in the area of instrument component use using one or more of the following methods:
" demonstration of seismic motion will be consistent with that of existing design basis loads at the installed location;
" substantial history of operational reliability in environments with significant vibration with a design envelope inclusive of the effects of seismic motion imparted to the instruments proposed at the location;
- adequacy of seismic design and installation is demonstrated based on the guidance in Sections 7, 8, 9, and 10 of IEEE Standard 344-2004, IEEE Recommended Practicefor Seismic Qualificationof Class JE Equipmentfor Nuclear Power Generating Stations, (Reference 27) or a substantially similar industrial standard;
" demonstration that proposed devices are substantially similar in design to models that have been previously tested for seismic effects in excess of the plant design basis at the location where the instrument is to be installed (g-levels and frequency ranges); or
" seismic qualification using seismic motion consistent with that of existing design basis loading at the installation location.
Determine venting capability for BDBEE Venting, such as may be used in an ELAP scenario to mitigate core damage.
Ref: EA-13-109 Section 1.1.4/NEI 13-02 Section2.2 First 24 Hour Coping Detail Provide a general description of the venting actionsfor first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using installedequipment including station modifications that are proposed.
Ref: EA-13-109 Section 1.2.6 / NEI 13-02 Section 2.5, 4.2.2 The operation of the HCVS will be designed to minimize the reliance on operator actions for response to a ELAP and BDBEE hazards identified in Part 1 of this OIP. Immediate operator actions can be completed by Operators from the HCVS control station and include remote-manual initiation. The operator actions required to open a vent path are as described in table 2-1.
Remote-manual is defined in this report as a non-automatic power operation of a component that does not require the operator to be at or in close proximity to the component. No other operator actions are required to initiate venting under the guiding procedural protocol.
The HCVS will be designed to allow initiation, control, and monitoring of venting from the Main Control Room (MCR). This location minimizes plant operators' exposure to adverse temperature and radiological conditions and is protected from hazards assumed in Part I of this report.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Permanently installed and dedicated power and motive air/gas capability will be available to support operation and monitoring of the HCVS for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
System control:
- i. Active: The PCIV and the SCIV will be operated in accordance with EOPs/SOPs to control containment pressure. The HCVS will be designed for 12 vent cycles under ELAP conditions over the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an ELAP. Controlled venting will be permitted in the revised EPGs and associated implementing EOPs.
ii. Passive: Inadvertent actuation protection is provided by:
A key locked switch for the dedicated downstream PCIV located in the Main Control Room and controlled by procedures AND Disabling the HCVS DC power to the SOV and disabling the motive power (pressurized N2) for the dedicated PCIV except when required by procedures to initiate containment venting Greater Than 24 Hour Coping Detail Provide a general descriptionof the venting actionsfor greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using portable and installed equipment including station modifications that are proposed.
Ref: EA-13-109 Section 1.2.4, 1.2.8 / NEI 13-02 Section 4.2.2 Before the end of the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> initial phase, available personnel will be able to connect supplemental motive air/gas to the HCVS. Connections for supplementing electrical power and motive air/gas required for HCVS will be located in accessible areas with reasonable protection per NEI 12-06 that minimize personnel exposure to adverse conditions for HCVS initiation and operation. Connections will be pre-engineered quick disconnects to minimize manpower resources.
FLEX is credited solely to sustain power for a BDBEE ELAP to containment instruments used to monitor the containment (e.g., pressure and wetwell level). The response to NRC Order EA-12-049 will demonstrate the capability for FLEX efforts to maintain the power source.
These actions provide long term support for HCVS operation for the period beyond 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 7 days (sustained operation time period) because on-site and off-site personnel and resources will have access to the unit(s) to provide needed action and supplies.
Details:
Provide a brief description of Procedures / Guidelines:
Confirm thatprocedure/guidanceexists or will be developed to support implementation.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Primary Containment Control Flowchart will be provided to direct operations in protection and control of containment integrity, including use of the existing Hardened Containment Vent System.
Open Item 8: Provideproceduresfor HCVS Operation.
Identify modifications:
List modifications and describe how they support the HCVS Actions.
EA- 12-049 Modifications
EA- 13-109 Modifications
" A modification will be required to install the new common piping including the new downstream PCIV. Since this line goes outside of the Reactor Building, it will include a SCIV and provisions to control primary containment leakage during a design basis LOCA. The new valves will include valve position indication and remote-manual control only. There is no sharing of any flow paths with the opposite unit.
" A modification will be required to allow operation of the existing upstream wetwell PCIV.
This includes the capability to override a containment isolation signal. Reopening the valves following a BDBE will be remote-manual.
" A modification will be required to install the dedicated batteries needed to supply power to HCVS for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> including capability for recharging from a portable charger at or before 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The battery will be located at the ROS.
" A modification will be required to install the dedicated motive power (Pressurized N2 gas) needed to open the HCVS valves for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> including capability for replacing N2 bottles or connection a portable compressor after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The N2 bottles will be located at the ROS.
" A modification will be required to add (a) HCVS flow path instrumentation consisting of pressure, temperature, and effluent radiation in the MCR, and (b) Motive power and DC battery indication in the MCR and the ROS.
Key Venting Parameters:
List instrumentationcreditedfor this venting actions. Clearly indicate which of those already exist in the plant and what others will be newly installed (to comply with the vent order)
Page 22 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Initiation, operation and monitoring of the HCVS venting will rely on the following key parameters and indicators which will be added as part of the HCVS modification:
Key Parameter Component Identifier Indication Location HCVS Effluent temperature TBD MCR HCVS Effluent radiation TBD MCR HCVS pressure indication TBD MCR HCVS valve position indication TBD MCR HCVS DC Power Voltage/Conditions TBD MCR/ROS HCVS Pneumatic supply pressure TBD MCR/ROS Initiation, operation and monitoring of the HCVS system will rely on several existing Main Control Room key parameters and indicators which are qualified or evaluated to Regulatory Guide 1.97 per the existing plant design:
Key Parameter Component Identifier Indication Location Drywell pressure 2(3)-1625 MCR wetwell level 2(3)-1626 MCR HCVS indications for HCVS valve position indication, HCVS pneumatic supply pressure, HCVS effluent temperature and radiation, and HCVS system pressure will be installed in the MCR to comply with EA- 13-109.
Notes:
Determine venting capability for Severe Accident Venting, such as may be used in an ELAP scenario to mitigate core damage.
Ref: EA-13-109 Section 1.2.10 /NEI 13-02 Section2.3 First 24 Hour Coping Detail Provide a general description of the venting actionsforfirst 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using installed equipment including station modifications that are proposed.
Ref: EA-13-109 Section 1.2.6 / NEI 13-02 Section 2.5, 4.2.2 The operation of the HCVS will be designed to minimize the reliance on operator actions for response to an ELAP and severe accident events. Severe accident event assumes that specific core cooling actions from the FLEX strategies identified in the response to Order EA- 12-049 were not successfully Page 23 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent initiated. Access to the reactor building will be restricted as determined by the RPV water level and core damage conditions. Immediate actions will be completed by Operators in the Main Control Room (MCR) and will include remote-manual actions. The ROS provides back-up capability to open HCVS valve(s) in case of a valve circuit or SOV failure. The operator actions required to open a vent path were previously listed in the BDBEE Venting Part 2 section of this report (Table 2-1).
Permanently installed power and motive air/gas capability will be available to support operation and monitoring of the HCVS for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Specifics are the same as for BDBEE Venting Part 2.
System control:
- i. Active: Same as for BDBEE Venting Part 2.
ii. Passive: Same as for BDBEE Venting Part 2 Greater Than 24 Hour Coping Detail Provide a general descriptionof the venting actionsfor greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using portableand installed equipment including station modifications that are proposed.
Ref: EA-13-109 Section 1.2.4, 1.2.8 / NEI 13-02 Section 4.2.2 Specifics are the same as for BDBEE Venting Part 2.
These actions provide long term support for HCVS operation for the period beyond 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 7 days (sustained operation time period) because on-site and off-site personnel and resources will have access to the unit(s) to provide needed action and supplies.
Details:
Provide a brief description of Procedures / Guidelines:
Confirm that procedure/guidanceexists or will be developed to support implementation.
The operation of the HCVS will be governed the same for SA conditions as for BDBEE conditions.
Existing guidance in the SAMGs directs the plant staff to consider changing radiological conditions in a severe accident.
Identify modifications:
List modifications and describe how they support the HCVS Actions.
The same as for BDBEE Venting Part 2 Key Venting Parameters:
List instrumentation creditedfor the HCVS Actions. Clearly indicate which of those already exist in the plant and what others will be newly installed (to comply with the vent order)
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent The same as for BDBEE Venting Part 2 Notes:
Determine venting capability support functions needed Ref: EA-13-109 Section 1.2.8, 1.2.9/NEI 13-02 Section2.5, 4.2.4, 6.1.2 BDBEE Venting Provide a general descriptionof the BDBEE Venting actions supportfunctions. Identifh methods and strategy(ies) utilized to achieve venting results.
Ref: EA-13-109 Section 1.2.9 / NEI 13-02 Section 2.5, 4.2.2, 4.2.4, 6.1.2 All containment venting functions will be performed from the MCR or ROS.
Venting to prevent containment overpressurization will be maintained by permanently installed equipment. The HCVS dedicated DC power source and dedicated motive force is adequate for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, but it can be replenished to support sustained operation.
Existing safety related station batteries will provide sufficient electrical power for MCR containment instrumentation for greater than approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Before station batteries are depleted, portable FLEX diesel generators, as detailed in the response to Order EA-12-049, will be credited to charge the station batteries and maintain DC bus voltage after approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Severe Accident Venting Providea general descriptionof the Severe Accident Venting actions supportfunctions. Identify methods and strategy(ies) utilized to achieve venting results.
Ref: EA-13-109 Section 1.2.8, 1.2.9 / NEI 13-02 Section 2.5, 4.2.2, 4.2.4, 6.1.2 The same support functions that are used in the BDBEE scenario would be used for severe accident venting. The ROS (the location of the HCVS DC power source and motive force) location will be evaluated to confirm accessibility under severe accident conditions.
Details:
Provide a brief description of Procedures / Guidelines:
Confirm that procedure/,uidanceexists or will be developed to support implementation.
All the HCVS equipment for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is permanently installed. The key portable HCVS items are the HCVS portable generator, and either a portable compressor or added N2 bottles needed to sustain operation after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Also, the FLEX DGs will be credited to maintain existing containment instrumentation. This portable equipment will be staged in position for the duration of the Page 25 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent event.
Identify modifications:
List modifications and describe how they support the HCVS Actions.
Flex modifications applicable to HCVS operation: No additional FLEX modifications are required to support HCVS.
HCVS modification: Provide a ROS location for the HCVS DC power supply and motive power that will be protected from all applicable screened-in hazards and located such that operator exposure to radiation and occupational hazards will be minimized. The DC power and motive power support systems will include connection points for replenishment for sustained operation.
Key Support Equipment Parameters:
List instrumentationcreditedfor the support equipment utilized in the venting operation. Clearly indicate which of those already exist in the plant and what others will be newly installed (to comply with the vent order)
The HCVS support systems, including its instrumentation, will be new and installed to comply with the order.
The instrumentation will consist of (a) motive gas supply pressure indication in the MCR and local pressure indication at the ROS, and (b) DC voltage in the MCR and local indication at the ROS.
Notes:
Provide a general descriptionof the venting actions using portable equipment including modifications that are proposed to maintain and/or supportsafety functions.
Ref: EA-13-109 Section 3.1 / NEI 13-02 Section 6.1.2, D.1.3.1 Deployment pathways developed for compliance with Order EA-12-049 are acceptable without further evaluation needed except in areas around the Reactor Building or in the vicinity of the HCVS piping.
Before the end of the initial 24-hour period, replenishment of the HCVS dedicated DC power and motive power (pressurized gas) will occur at the ROS. The selection of the ROS location will take into account the SA temperature and radiation condition to ensure access to the ROS is maintained.
The design will allow replenishment with minimal actions.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 2: Boundary Conditions for Wetwell Vent Open Item 4: Confirm that the ROS will be in an accessible areafollowing a SA.
Details:
Provide a brief description of Procedures / Guidelines:
Confirm that procedure/guidanceexists or will be developed to support implementation.
Operation of the portable equipment is the same as for compliance with Order EA- 12-049; thus, they are acceptable without further evaluation.
HCVS Actions Modifications Protection of connections Identify Actions including Identify modifications Identify how the connection is how the equipment will be protected deployed to the point of use.
Per compliance with Order N/A Per compliance with Order EA EA- 12-049 (FLEX) 049 (FLEX)
Notes:
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 3: Boundary Conditions for Drywell Vent Provide a sequence of events and identify any time constraint required for success including the basis for the time constraint.
HCVS Actions that have a time constraintto be successful should be identified with a technical basis and a justificationprovided that the time can reasonably be met (for example, a walk-through of deployment).
Describe in detail in this section the technical basisfor the time constraintidentified on the sequence of events timeline Attachment 2B See attached sequence of events timeline (Attachment 2B).
Ref: EA-13-109 Section X.X.X / NEI 13-02 Section X.X.x This section will be completed with the Phase 2 0P submittal by December 31, 2015.
Severe Accident Venting Determine venting capability for Severe Accident Venting, such as may be used in an ELAP scenario to mitigate core damage.
Ref: EA-13-109 Section X.X.X /NEI 13-02 SectionX.X.x First 24 Hour Coping Detail Provide a general descriptionof the venting actionsforfirst 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using installed equipment including station modifications that are proposed.
Ref: EA-13-109 Section X.X.X / NEI 13-02 Section X.X.x This section will be completed with the Phase 2 0P submittal by December 31, 2015.
Greater Than 24 Hour Coping Detail Providea general descriptionof the venting actionsfor greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using portable and installed equipment including station modifications that are proposed.
Ref: EA-13-109 Section X.X.X / NEI 13-02 Section X.X.x This section will be completed with the Phase 2 0P submittal by December 31, 2015.
Details:
Provide a brief description of Procedures / Guidelines:
Confirm that procedure/guidanceexists or will be developed to support implementation.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 3: Boundary Conditions for Drywell Vent This section will be completed with the Phase 2 0P submittal by December 31, 2015.
Identify modifications:
List modifications and describe how they support the HCVS Actions.
This section will be completed with the Phase 2 0P submittal by December 31, 2015.
Key Venting Parameters:
List instrumentationcreditedfor the venting HCVS Actions.
This section will be completed with the Phase 2 0P submittal by December 31, 2015.
Notes:
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 4: Programmatic Controls. Training, Drills and Maintenance Identify how the programmatic controls will be met.
Provide a description of the programmatic controls equipment protection,storage and deployment and equipment quality addressing the impact of temperature and environment Ref: EA-13-109 Section 3.1, 3.2 / NEI 13-02 Section 6.1.2, 6.1.3, 6.2 Program Controls:
The HCVS venting actions will include:
- Site procedures and programs will be developed in accordance with NEI 13-02 to address use and storage of portable equipment relative to the Severe Accident defined in NRC Order EA-13-109 and the hazards applicable to the site per Part I of this OIP.
- Routes for transporting portable equipment from storage location(s) to deployment areas will be developed as the response details are identified and finalized. The identified paths and deployment areas will be accessible during all modes of operation and during Severe Accidents.
Procedures:
Procedures will be established for system operations when normal and backup power is available, and during ELAP conditions.
The HCVS procedures will be developed and implemented following the plant's process for initiating or revising procedures and contain the following details:
" appropriate conditions and criteria for use of the HCVS
" when and how to place the HCVS in operation,
" the location of system components,
" instrumentation available,
" normal and backup power supplies,
" directions for sustained operation, including the storage location of portable equipment,
" training on operating the portable equipment, and
" testing of portable equipment Dresden relies on CAP for ECCS pump NPSH. The procedures will state that the use of the HCVS vent path would impact NPSH.
Dresden will establish provisions for out-of-service requirements of the HCVS and compensatory measures. The following provisions will be documented in a Site Specific control document:
The provisions for out-of-service requirements for HCVS functionality are applicable in Modes 1, 2 an 3.
- If for up to 90 consecutive days, the primary or alternate means of HCVS operation are non-functional, no compensatory actions are necessary.
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 4: Programmatic Controls, Training, Drills and Maintenance
" If for up to 30 days, the primary and alternate means of HCVS operation are non-functional, no compensatory actions are necessary.
f the out of service times exceed 30 or 90 days as described above, the following actions will If be performed:
o The condition will be entered into the corrective action system, o The HCVS functionality will be restored in a manner consistent with plant procedures, o A cause assessment will be performed to prevent future loss of function for similar causes.
o Initiate action to implement appropriate compensatory actions Describe training plan List trainingplansfor affected organizationsor describe the planfor training development Ref: EA-13-109 Section 3.2 / NEI 13-02 Section 6.1.3 Personnel expected to perform direct execution of the HVCS will receive necessary training in the use of plant procedures for system operations when normal and backup power is available and during ELAP conditions. The training will be refreshed on a periodic basis and as any changes occur to the HCVS. Training content and frequency will be established using the Systematic Approach to Training (SAT) process.
In addition, (reference NEI 12-06) personnel on-site will be available to supplement trained personnel.
Identify how the drills and exercise parameters will be met.
Alignment with NEI 13-06 and 14-Olas codified in NTTF Recommendation 8 and 9 rulemaking The Licensee should demonstrate use of the HCVS system in drills, tabletops, or exercises asfollows:
" Hardenedcontainment vent operationon normal power sources (no ELAP).
- During FLEX demonstrations(as required by EA-12-049: Hardened containment vent operation on backup power andfrom primary or alternate location during conditions of ELAP/loss of UHS with no core damage. System use is for containment heat removal AND containment pressure control.
- HCVS operationon backup power andfrom primary or alternatelocation during conditions of ELAP/loss of UHS with core damage. System use isfor containment heat removalAND containmentpressure control with potentialfor combustible gases (Demonstrationmay be in conjunction with SAG change).
Ref: EA-13-109 Section 3.1 / NEI 13-02 Section 6.1.3 Page 31 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 4: Programmatic Controls, Training, Drills and Maintenance Dresden will utilize the guidance provided in NEI 13-06 and 14-01 for guidance related to drills, tabletops, or exercises for HCVS operation. In addition, Dresden will integrate these requirements with compliance to any rulemaking resulting from the NTTF Recommendations 8 and 9.
Describe maintenance plan:
" The HCVS maintenanceprogram should ensure that the HCVS equipment reliabilityis being achieved in a manner similar to that requiredfor FLEX equipment. Standard industry templates (e.g., EPRI) and associatedbases may be developed to define specific maintenance and testing.
o Periodic testing andfrequency should be determined based on equipment type, expected use and manufacturer'srecommendations (furtherdetails are provided in Section 6 of this document).
o Testing should be done to verify design requirements and/or basis. The basis should be documented and deviationsfrom vendor recommendations and applicable standards should be justified.
o Preventive maintenance should be determined based on equipment type and expected use.
The basis should be documented and deviationsfrom vendor recommendations and applicable standardsshould be justified.
o Existing work controlprocesses may be used to control maintenance and testing.
" HCVS permanent installed equipment should be maintainedin a manner that is consistent with assuring that it performs its function when required.
o HCVS permanently installed equipment should be subject to maintenance and testing guidanceprovided to verifv properfinction.
" HCVS non-installed equipment should be stored and maintainedin a manner that is consistent with assuringthat it does not degrade over long periods of storage and that it is accessiblefor periodic maintenance and testing.
Ref: EA-13-109 Section 1.2.13 / NEI 13-02 Section 5.4, 6.2 Dresden will utilize the standard EPRI industry PM process (similar to the Preventive Maintenance Basis Database) for establishing the maintenance calibration and testing actions for HCVS components. The control program will include maintenance guidance, testing procedures and frequencies established based on type of equipment and considerations made within the EPRI guidelines.
Dresden will implement the following operation, testing and inspection requirements for the HCVS to ensure reliable operation of the system.
Table 4-1: Testing and Inspection Requirements Description Frequency Cycle the HCVS valves and the interfacing Once per operating cycle Page 32 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 4: Programmatic Controls, Training, Drills and Maintenance system valves not used to maintain containment integrity during operations.
Perform visual inspections and a walk Once per operating cycle down of HCVS components Test and calibrate the HCVS radiation Once per operating cycle monitors.
Leak test the HCVS. (1) Prior to first declaring the system functional; (2) Once every three operating cycles thereafter; and (3) After restoration of any breach of system boundary within the buildings Validate the HCVS operating procedures Once per every other operating cycle by conducting an open/close test of the HCVS control logic from its control panel and ensuring that all interfacing system valves move to their proper (intended) positions.
Notes:
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 5: Milestone Schedule Provide a milestone schedule. This schedule should include:
" Modifications timeline
" Procedure guidance development complete o HCVS Actions o Maintenance
" Storage plan (reasonableprotection)
" Staffing analysis completion
" Long term use equipment acquisition timeline
- Training completionfor the HCVS Actions The dates specifically requiredby the orderare obligated or committed dates. Other dates are planned dates subject to change. Updates will be provided in the periodic(six month) status reports.
Ref: EA-13-109 Section D.1, D.3 / NEI 13-02 Section 7.2.1 The following milestone schedule is provided. The dates are planning dates subject to change as design and implementation details are developed. Any changes to the following target dates will be reflected in the subsequent 6 month status reports.
Milestone Target Activity Comments Completion Status [Include date Date changes in this columni Hold preliminary/conceptual design meeting June 2014 Complete Submit Overall Integrated Implementation Plan June 2014 Complete Submit 6 Month Status Report December 2014 Submit 6 Month Status Report June 2015 U3 Initial Design Engineering Modification October 2015 Complete Submit 6 Month Status Report December 2015 Simultaneous with Phase 2 OIP Submit 6 Month Status Report June 2016 U2 Initial Design Engineering Modification October 2016 Complete U3 Implementation Outage October 2016 Operations Procedure Changes Developed November 201.6 Site Specific Maintenance Procedure Developed November 2016 Page 34 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Part 5: Milestone Schedule U3 Training Complete November 2016 U3 Procedure Changes Active November 2016 U3 Walk Through Demonstration/Functional November 2016 Test Submit 6 Month Status Report December 2016 Submit 6 Month Status Report June 2017 U2 Implementation Outage October 2017 U2 Training Complete November 2017 U2 Procedure Changes Active November 2017 U2 Walk Through Demonstration/Functional November 2017 Test Submit 6 Month Status Report December 2017 Submit Completion Report May 2018 Note: Drywell implementation dates will be submitted with the December 2015 OIP Update Page 35 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 1: HCVS Portable Equipment BDBEE Severe Performance Maintenance/ PM requirements List portable equipment Venting Accident Criteria Venting Nitrogen Cylinders X X TBD Check periodically for pressure, replace or replenish as needed Portable compressor X X TBD Test periodically for performance Portable HCVS battery charger X X TBD Test periodically for performance
+
+
t t
+ F F Page 36 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 2: Sequence of Events Timeline Representative BWR Venting Timelines ICS & RPV Injection Established (FLEX) (Dresden 0IP) No containment venting required due to ICS HPCI In-T - 6hrs SBO Spece I
", - Case 1 m FLEX Successful mm v Ref. Dresden FLEX t=O t 2m I - 18 hrs 0lP No Injection iCS ICS restored or core secured and HPCI cooling due to assumed lost shell-side (FLEX) TAF inventory (Dresden dIP) t - 20m t - 2.5 hrs Case 2 Late Injection failure
.. . Ref: SECY-12-0157 t - 23 hrs t - 24 nrs t= ,.34 nrs No Injection Containment Venting or core (based on preventing cooling Containment Venting exceeding PCPL)
(based on preventing
'I not exceeding PCPL)
COMM I Case 3 Early Injection Failure t- 1 hr t- 8 hr Ret SOARCA Legend
References:
-- Adequate core cooling maintained Case 1: Dresden FLEX Overall Integrated Plan Injection Lost Case 2: SECY-12-0157 - ML12344A030
- Increased shine and leakage of radionuclides primarily from Wetwell Case 3: SOARCA-ML13150A053
.. HCVS Post Core Damage Dose Evaluation Required I o scale -
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 3A: Electrical Layout of System (Unit 2, Unit 3 similar)
A, CuV 601-t-ITv
> VALVE 60 60 1601 MCVS vtl MRA PPf',5kA¶ CON4TROL VA0yE Page 38 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 3B: P&ID Layout of HCVS, Unit 2 (Unit 3 similar)
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 3C: Layout and Routing (later)
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Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 4: Failure Evaluation Table Table 4A: Wet Well HCVS Failure Evaluation Table Failure with Alternate Action Functional Failure Impact on Containment Mode Failure Cause Alternate Action Venting?
Failure of Vent to ELAP event (loss of No action needed, DC power and motive No Open on Demand all AC) force is supplied from dedicated HCVS supply Failure of Vent to Valves fail to Recharge HCVS batteries with portable No Open on Demand open/close due to provided generator, considering severe complete loss of accident conditions HCVS batteries (long term)
Failure of Vent to Valves fail to Replace bottles as needed or connect No Open on Demand open/close due to loss portable compressor of pneumatic air supply (long term)
Failure of Vent to Valves fail to Open the affected valve at the ROS which is No Open on Demand open/close due to SOV independent of the electrical circuit.
failure and/or circuit failure Page 41 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 5: References
- 1. Generic Letter 89-16, Installation of a Hardened Wetwell Vent, dated September 1, 1989
- 2. Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events, dated March 12, 2012
- 3. Order EA-12-050, Reliable Hardened Containment Vents, dated March 12, 2012
- 5. Order EA-13-109, Severe Accident Reliable Hardened Containment Vents, dated June 6, 2013
- 6. JLD-ISG-2012-01, Compliance with Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events, dated August 29, 2012
- 7. JLD-ISG-2012-02, Compliance with Order EA-12-050, Reliable Hardened Containment Vents, dated August 29, 2012
- 8. JLD-ISG-2013-02, Compliance with Order EA- 13-109, Severe Accident Reliable Hardened Containment Vents, dated November 14, 2013
- 9. NRC Responses to Public Comments, Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-02:
Compliance with Order EA- 12-050, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents, ADAMS Accession No. ML12229A477, dated August 29, 2012
- 10. NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Revision 1, dated August 2012
- 11. NEI 13-02, Industry Guidance for Compliance with Order EA-13-109,Revision 0, Dated November 2013
- 12. NEI 13-06, Enhancements to Emergency Response Capabilities for Beyond Design Basis Accidents and Events, Revision 0, dated March 2014
- 13. NEI 14-01, Emergency Response Procedures and Guidelines for Extreme Events and Severe Accidents, Revision 0, dated March 2014
- 20. NEI FAQ HCVS-07, Consideration of Release from Spent Fuel Pool Anomalies
- 22. NEI FAQ HCVS-09, Use of Toolbox Actions for Personnel Page 42 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions
- 23. NEI White Paper HCVS-WP-01, HCVS Dedicated Power and Motive Force
- 24. NEI White Paper HCVS-WP-02, HCVS Cyclic Operations Approach
- 25. NEI White Paper HCVS-WP-03, Hydrogen/CO Control Measures
- 26. NEI White Paper HCVS-WP-04, FLEX/HCVS Interactions
- 27. IEEE Standard 344-2004, IEEE Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations,
- 31. Memorandum to R.W. Borchardt, dated May 19, 2013, Subject "Staff Requirements - SECY-12-0157- Consideration of Additional Requirements for Containment Venting systems for Boiling Water Reactors with Mark I and Mark II Containments" Page 43 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 6: Changes/Updates to this Overall Integ-rated Implementation Plan Any significant changes to this plan will be communicated to the NRC staff in the 6 Month Status Reports Page 44 of 45
Dresden Nuclear Power Station, Units 2 and 3 Overall Integrated Plan for Phase 1 Requirements for Reliable Hardened Containment Vent System (HCVS) Capable of Operation Under Severe Accident Conditions Attachment 7: List of Overall Integrated Plan Open Items Open Action Comment Item I Confirm that at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> battery coping time is available. Design effort 2 Determine actions to enable WW venting following a Design Approach flooding around the torus 3 Determine how Motive Power and/or HCVS Battery Power Design approach will be disabled during normal operation 4 Confirm that the ROS will be in an accessible area following Confirmatory action a SA 5 Confirm diameter on new common HCVS Piping Design effort 6 Confirm suppression pool heat capacity Confirmatory action 7 Determine the approach for combustible gases Design approach 8 Provide procedures for HCVS Operation Procedure development 4 +
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