RS-15-216, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049)
| ML15243A088 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/28/2015 |
| From: | Jim Barstow Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-12-049, RS-15-216, TMl-15-083 | |
| Download: ML15243A088 (27) | |
Text
Exelon Generation Order No. EA-12-049 RS-15-216 TMl-15-083 August 28, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
References:
- 1. NRC Order Number EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12, 2012
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," Revision 0, dated August 29, 2012
Revision 0, dated August 2012
- 4. Exelon Generation Company, LLC's Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated October 25, 2012
- 5. Exelon Generation Company, LLC Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated February 28, 2013 (RS-13-026)
- 6. Exelon Generation Company, LLC First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA 049), dated August 28, 2013 (RS-13-131)
- 7. Exelon Generation Company, LLC Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA 049), dated February 28, 2014 (RS-14-016)
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August28,2015 Page 2
- 8. Exelon Generation Company, LLC Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA 049), dated August 28, 2014 (RS-14-214)
- 9. Exelon Generation Company, LLC Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA 049), dated February 27, 2015 (RS-15-025)
- 10. NRC letter to Exelon Generation Company, LLC, Three Mile Island Nuclear Station, Unit 1 - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC No. MF0803), dated December 17, 2013 On March 12, 2012, 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 develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in of Reference 1.
Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-06, Revision O (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the EGC initial status report regarding mitigation strategies. Reference 5 provided the Three Mile Island Nuclear Station, Unit 1 overall integrated plan.
Reference 1 requires submission of a status report at six-month inteNals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports. References 6, 7, 8, and 9 provided the first, second, third, and fourth six-month status reports, respectively, pursuant to Section IV, Condition C.2, of Reference 1 for Three Mile Island Nuclear Station, Unit 1. The purpose of this letter is to provide the fifth six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. The enclosed report provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any. The enclosed report also addresses the NRC Interim Staff Evaluation Open and Confirmatory Items contained in Reference10.
It is noted that open issues were identified by the NRC during the NRC on-site audit review conducted on August 10-13, 2015 that require additional follow-up with the NRC staff and could affect the final strategies.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August28,2015 Page 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 281h day of August 2015.
Respectfully submitted, 0~ ~
James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Enclosure:
- 1. Three Mile Island Nuclear Station, Unit 1 Fifth Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region I NRC Senior Resident Inspector - Three Mile Island Nuclear Station, Unit 1 NRC Project Manager, NRR - Three Mile Island Nuclear Station, Unit 1 Ms. Jessica A. Kratchman, NRR/JLD/PMB, NRC Mr. Jack R. Davis, NRR/DPR/MSD, NRC Mr. Eric E. Bowman, NRR/DPR/MSD, NRC Mr. Jeremy S. Bowen, NRR/DPR/MSD/MSPB, NRC Mr. Robert L. Dennig, NRR/DSS/SCVB, NRC Mr. John D. Hughey, NRR/JLD/JOMB, NRC Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Resources Chairman, Board of County Commissioners of Dauphin County, PA Chairman, Board of Supervisors of Londonderry Township, PA R. R. Janati, Chief, Division of Nuclear Safety, Pennsylvania Department of Environmental Protection, Bureau of Radiation Protection
Enclosure Three Mile Island Nuclear Station, Unit 1 Fifth Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (23 pages)
Three Mile Island Station, Unit 1 Fifth Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 1 Introduction Three Mile Island Nuclear Station, Unit 1 (TMI) developed an Overall Integrated Plan (Reference 1 in Section 8), documenting the diverse and flexible strategies (FLEX), in response to Reference 2. This enclosure provides an update of milestone accomplishments since submittal of the last status report (February 2015), including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
2 Milestone Accomplishments The following milestone(s) have been completed since February 27, 2015 and are current as of August 28, 2015:
- Engineering for o FLEX Electrical Power Supply o FLEX RCS & SFP Makeup o FLEX Feedwater System o FLEX Storage Facility o FLEX fuel oil supply o Spent Fuel Pool Level o On Site Communications modification
- Installation of the FLEX Platform modification is complete 3 Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.
The revised milestone target completion dates do not impact the Order implementation date.
Original Target Activity Status Completion Date Submit 60 Day Status Report Complete Submit Overall Integrated Complete Implementation Plan Contract with SNRC Complete Page 1 of 23
Three Mile Island Nuclear Station, Unit 1 Fifth Six Month Status Report for the Implementation of FLEX, August 28, 2015 Original Target Activity Status Completion Date 6 Month Updates Aug., 2013 Update 1 Complete Feb., 2014 Update 2 Complete Aug., 2014 Update 3 Complete Feb., 2015 Update 4 Complete Aug., 2015 Update 5 Complete with this submittal Modification Development Oct 2014 Phase 1 modifications (1) RCP Seal Upgrade (1) Complete Oct 2014 Phase 2 modifications (1) FLEX Electrical Power Supply (1) Complete (2) FLEX RCS & SFP Makeup (2) Complete (3) FLEX Feedwater System (3) Complete (4) FLEX Storage Facility (4) Complete (5) Turbine Bldg Structure (5) Started (6) Turbine Bldg FLEX platform (6) Complete (7) FLEX fuel oil supply (7) Complete (8) Spent Fuel Pool Level (8) Complete (9) On Site Communications (9) Complete modification (10) Reactor Building Vent (10) Complete (11) Satellite phone storage (11) Complete Oct 2014 Phase 3 modifications None Modification Implementation Nov 2015 Phase 1 modifications (1) RCP Seal Upgrade Not Started Page 2 of 23
Three Mile Island Nuclear Station, Unit 1 Fifth Six Month Status Report for the Implementation of FLEX, August 28, 2015 Original Target Activity Status Completion Date Nov 2015 Phase 2 modifications (1) FLEX Electrical Power Supply Started (2) FLEX RCS & SFP Makeup Started (3) FLEX Feedwater System Started (4) FLEX Storage Facility Started (5) Turbine Bldg. Structural Started (6) Turbine Bldg. FLEX platform Complete (7) FLEX fuel oil supply Started (8) Spent Fuel Pool Level Started (9) On Site Communications Started modification (1 O} Reactor Building Vent Started (11) Satellite phone storage Complete Nov 2015 Phase 3 modifications None Original Target Activity Status Completion Date Procedure development Jun 2015
- Create Site-Specific Procedures Started - to be completed prior to Nov 2015 Jul2015
- Validate Procedures (NEI 12-06, Started - to be completed prior to Sect. 11.4.3) Nov 2015 Jun 2015
- Create Maintenance Procedures Started - to be completed prior to Nov 2015 Jul2015 Staffing analysis Complete Nov 2015 Storage Plan Complete Nov 2015 FLEX equipment acquisition Started Nov 2015 Training Started Jun 2015 Regional Response Center Operational Complete Nov 2015 Unit 1 Implementation date Page 3 of 23
Three Mile Island Nuclear Station, Unit 1 Fifth Six Month Status Report for the Implementation of FLEX, August 28, 2015 4 Changes to Compliance Method The following changes are the most significant changes made to the FLEX implementation strategy since the last update (February 2015):
o Access to CO-V-8 or DW-V-35 could be impeded by internal flooding. Therefore, condensate valve CO-V-13 will be used to isolate the hotwell if the Earthquake adversely affects hotwell integrity and DW-V-30 will be used to control flow from DW-T-2 in the event of a tornado.
5 Need for Relief/Relaxation and Basis for the Relief/Relaxation TMI expects to comply with the Order implementation date and no relief/relaxation is required at this time.
It is noted that open issues were identified by the NRC during the NRC on-site audit review conducted on August 10-13, 2015 that require additional follow-up with the NRC staff and could affect the final strategies.
6 Open Items from Overall Integrated Plan and Interim Staff Evaluation Section Reference Overall Integrated Plan Open Item Status (Refer to OIP Update (Refer to OIP Update from Feb 2014) (As of August 28, 2015) from Aug 2013)
None Page 4 of 23
Interim Staff Evaluation Open Item or Confirmatory Items Item NRC ref Description Status
- no.
AUG 2015 UPDATE 6 3.1.1 .2.A The licensee did not specifically address deployment (1) The potential for earthquake induced liquefaction has been considerations with respect to the deployment of FLEX evaluated. Deployment of TMl1 FLEX equipment will not be adversely impacted. (Reference 5).
equipment through areas subject to liquefaction, routing (2) Evaluation of all actions performed within non-seismic structures only through seismically robust buildings, power required is complete. The strategy was revised to eliminate reliance upon to deploy or move equipment, and protection of the actions within the condenser pit due to the potential for internal means to move equipment. flooding (References 6 and 7)
(3) A vehicle stored in the FLEX storage facility will be used to deploy or move FLEX equipment. No additional power is required.
This response will be completed in the compliance letter.
7 3.1.1.3.A The licensee did not address the determination of A procedure (Reference 8) has been prepared which provides necessary instrument local readings per consideration 1 operators with the direction on how to obtain parameters critical to of NEI 12-06 Section 5.3.2, to support the implementation implementing the FLEX mitigation strategy without reliance on of the mitigating strategies in the event that seismically functional electrical equipment outside the reactor building after a qualified electrical equipment is affected by a BDBEE. seismic event.
[COMPLETE]
8 3.1.1.4.A The licensee did not identify the local assembly area or The local assembly area (Staging area "C") is the Lancaster Airport.
describe the methods to be used to deliver the equipment The site staging area is the south parking lot (staging area "B"). The to the site for all hazards. In the audit process the primary delivery method will be by truck, but airlift capability via licensee stated that the TMI SNRC playbook will be made helicopter will be available to address delivery after any hazard. The available when approved to address this. TMI SNRC playbook has been approved. (Reference 9)
[COMPLETE]
Page 5 of 23
Three Mile Island Nuclear Station, Unit 1 Fifth Six Month Status Report for the Implementation of FLEX, August 28, 2015 Item I NRC ref Description Status
- no.
AUG 2015 UPDATE 22 I 3.2.1.6.A During the ELAP and LUHS [Loss of Ultimate Heat Sink] A SOE timeline for flooding is provided as Attachment 1 B. The beyond-design-basis external event, the licensee has capability to perform the actions within the period identified in identified that times to complete actions in the Events analysis will be validated when the procedures are written, through Timeline are based on operating judgment, the table top, simulator and field simulation exercises.
conceptual designs, and the current supporting analyses.
This response will be completed in the compliance letter.
The TMI mitigation strategy is not based upon the PWROG WCAP-17601-P ELAP mitigation strategy. In the audit process, the licensee stated that the current SOE is for the seismic event only and that another SOE would be developed for the flood event. Based on the information provided by the licensee, it is not possible to determine the validity of the time constraints provided in the preliminary sequence of events timeline for all hazards. The final timelines will be validated once detailed designs are completed and procedures are developed. The results will be provided in a future 6-month update.
39 3.2.4.5.A The licensee provided no information in the Integrated A response plan which coordinates Operations and Security Plan regarding local access to the protected areas under response has been developed (Reference 10), which ensures the ELAP. security staff can support access to the protected area within the time frame required for successful implementation. [COMPLETE]
45 3.3.3.A The specific procedures for training, new or revised, have This response will be completed in the compliance letter.
not yet been completed. The requirements from the analysis will be used to develop and to validate the new and revised procedures. This includes the existing design and licensing basis requirements and the new FLEX requirements. Validation of time response is performed using a composite of field simulation and performance/simulator exercises.
Page 6 of 23
7 Potential Draft Safety Evaluation Impacts No potential impact to the Draft Safety Evaluation was identified.
8 References The following references support the updates to the Overall Integrated Plan described in this 6-month update.
- 1. Three Mile Island Nuclear Station, Unit 1, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA 049), dated February 28, 2013
- 2. NRC Order Number EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, dated March 12, 2012
- 3. NEI 12-06, Rev. 0, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, dated August 2012
- 4. TMI Station's Fourth Six Month Status Report for the Implementation of FLEX, dated February 27, 2015
- 5. 990-2179 "Assessment of earthquake-induced liquefaction potential and associated ground failure hazards for Three Mile Island Unit 1", Geomatrix Consultants
- 6. Technical Evaluation 14-00126, FLEX Impact evaluation -Turbine Building
- 7. Technical Evaluation 15-00142, FLEX Impact evaluation - Non Seismic Eqpt Failures in Class I Buildings
- 8. OP-TM-919-907 "ALTERNATE MONITORING OF ESSENTIAL INSTRUMENTATION
- 10. SY-TM-101-102-1001, "Security system component degradation compensatory measures" Page 7 of 23
Three Mile Island Nuclear Station, Unit 1 Fifth Six Month Status Report for the Implementation of FLEX, August 28, 2015 9 Attachments 1A Sequence of Events Timeline Earthquake or Tornado @ 100% power 1B Sequence of Events Timeline External Flood @ 100% power 1C Sequence of Events Timeline Extreme Cold, Snow and Ice @ 100% power 2A 1E-919-21-001, Rev. 1 draft, FLEX Diesel Generator and Fuel Oil System 28 1E-919-21 -002, Rev. 1 draft, FLEX Electrical Distribution 2C 1E-919-21-003, Rev. 1 draft, FLEX Feedwater System 20 1E-919-21-004, Rev. 1 draft, FLEX RCS & SFP Makeup System 2E 1E-919-21-005, Rev. 1 draft, Long Term water Supply Page 8 of 23
Attachment 1A - Sequence of Events Timeline Earthquake or Tornado@ 100o/o power
- ELAP Action Time Remarks/
Time Constraint Applicability (HR)
Y/N 1 0 Earthquake or tornado Causes LOOP and NA damages unprotected equipment.
All control rods are inserted and the reactor is shutdown.
2 0 Emergency Diesel Generators fail to energize ES NA Failures per NEI 12-06 buses.
3 <.01 EFW actuated: Steam driven pump (EF-P-1) and N Automatic plant response.
EFW Control valves (EF-V-30A & B) supply feedwater. MSSV & ADV control OTSG pressure.
4 <.02 EOP initiated. NA 5 < 0.05 RCS Letdown is automatically isolated on high N Automatic plant response.
temperature (MU-V-3 closes).
6 < 0.08 Control Room operators throttle ADV to stabilize N OTSG pressure and RCS temperature. Adequate core cooling is provided through RCS natural circulation and heat removal through the OTSG.
7 < 0.08 Control Room operators attempt to start and load N SBO Diesel Generator.
8 < 0.10 Control Room operator closes RCP Controlled N Contains RCS losses within Bleed Off Isolation Valve (MU-V-26). the Reactor Bldg.
9 < 0.17 SBO Diesel generator is not functional. N Failure per NEI 12-06.
10 0.25 Operator initiates E-plan. If needed, satellite N phones are used for offsite notifications &
communication .
11 0.25 Operators open main condenser vacuum breaker N This is a pre-condition to (VA-V-8) and valves to vent Main Generator H2 to reduce DC loads.
atmosphere.
12 0.5 Control Room operator secures DC powered FW N DC Load shedding pump turbine lube oil pumps (LO-P-9A & B).
13 0.5 Operator opens doors to inverter and battery y Maintain acceptable rooms. temperature for FLEX equipment.
Page 9 of 23
Attachment 1 A - Sequence of Events Timeline Earthquake or Tornado @ 1OOo/o power
- ELAP Action Time Remarks/
Time Constraint Applicability (HR)
Y/N 14 0.5 Operator de-energizes instrument systems not N DC Load shedding.
required for FLEX.
15 < 0.75 Operator lines up C02 purge for main generator. N Minimize risk of main generator fire.
16a < 0.75 If earthquake occurs, then operator closes N CO-V-13 and CO-V-24.
16b < 0.75 If tornado damages both CO-T-1A and CO-T-1 B, y Maintain EFW and minimize then operator throttles open DW-V-30 to supply loss of condensate EF-P-1 from DW-T-2 until CO-V-1 OB is closed.
17 < 1.0 Operators isolate fire service to IB, CB, AB or N Mitigates the effects of non FHB, if required. (CLOSE FS-V-43, 233 or 51) seismic piping failures in Class I buildings.
18 1.0 Control room operator secures Main Turbine Lube N DC load shedding.
Oil Pump LO-P-6.
19 1.5 Operator lines up FLEX Diesel Generator. y Pre-condition to maintain vital AC power and restore RCS makeup.
20 < 2.0 If battery chargers have not been re-energized, y DC load shedding is then Control room operator secures Main complete.
Generator Seal Oil Pump (GN-P-2).
21 2.0 Actions for passive Intermediate Building N ventilation are completed.
22 2.0 Operator lines up FLEX RCS Makeup Pump from N Pre-condition to maintain BWST or Spent Fuel Pool to RCS. vital AC power and restore RCS makeup.
23 2.0 Operator takes local control of MS-V-6 (EF-P-1 y Bottled air system will last steam supply), EF-V-30A & EF-V-30B (EFW Flow at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and then Control Valves) and MS-V-4A & MS-V-4B local manual control is (Atmospheric Dump Valves). required.
24 2.25 Operator strips loads from 1P & 1S 480V Buses, N Pre-condition to maintain and 1A & 1B ES MCC to prepare to load FLEX vital AC power and restore diesel generator. RCS makeup.
25 2.5 Operator starts FLEX Diesel Generator, energizes N Pre-condition to maintain FLEX MCC and closes breakers to energize 1P- vital AC power and restore 1S 480V cross tie bus. RCS makeup.
Page 10 of 23
Attachment 1 A - Sequence of Events Timeline Earthquake or Tornado @ 1OOo/o power
- ELAP Action Time Remarks/
Time Constraint Applicability (HR)
YIN 26 2.58 Operator closes breakers to energize 1P 480V y Pre-condition to maintain Bus, 1S 480V Bus, 1A ES MCC and 1B ES MCC. vital AC power and restore RCS makeup.
27 2.75 Operator closes breakers for selected loads on 1A y Pre-condition to maintain and 1B ES MCC: vital AC power and restore RCS makeup.
Battery Chargers AC Power to Inverters & Vital Instruments FLEX RCS Makeup Pumps Emergency Lighting 28 3.0 Operator starts FLEX RCS Makeup Pump (A or B) y Restore makeup within 4 to restore RCS inventory and increase RCS boron hours to prevent interruption concentration. of core cooling .
29 3.5 Operator opens service bldg and turbine bldg N machine shop roll up doors and aux boiler roll up door.
30 4.0 Operator connects hose from DF-V-41 to pipe in N Required for continued DGB, connects hose to fuel oil pipe in TB, routes operation of FX-Y-1A or B.
hose to FLEX DG Fuel Oil Tank (FX-T-3), and routes hose from FX-P-7 discharge to FX-T-2.
31 4.0 Operator strips loads on 1A ESV MCC & 1A N Pre-condition to isolate Radwaste MCC and installs jumper between 1A RCP controlled bleed off ESV MCC and 1A Radwaste MCC. flow.
32 4.0 Operator starts DF-P-1 C or DF-P-1 D, as needed, y Required for continued to maintain level in FX-T-3. operation of FX-Y-1A or B.
Pre-staged fuel supply will last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at full load.
33 4.5 Operator energizes1A ESV MCC and 1A N Isolate RCP controlled Radwaste MCC, and Closes CBO Isolation Valves bleed off flow to minimize MU-V-33A, MU-V-338, MU-V-33C and MU-V- RCS loss rate.
330.
34 5.0 When pressurizer level reaches 100 inches, N operator throttles open MS-V-4A & B to initiate a cooldown and controls pressurizer level at 100 inches.
Cooldown rate will be approximately 30 F/HR.
Page 11 of23
Attachment 1A - Sequence of Events Timeline Earthquake or Tornado @ 1OOo/o power
- ELAP Action Time Remarks/
Time Constraint Applicability (HR)
Y/N 35 5.0 Operator initiates temporary ventilation in Control N Bldg, IB and Turbine Bldg.
36 6.0 Operator transfers a pressurizer heater group N Hydraulic control of RCS (RC-HTR-GRP- 8 or 9) to the emergency power pressure can be used if supply and energizes heaters. required.
37 7.0 Operator strips loads on 1C ESV MCC, energizes N Contingency action.
1C ESV MCC, and closes breakers for CF-V-1A and CF-V-1 B.
When a reliable Pressurizer steam bubble is established or If RCS pressure drops below 300 psig, then CLOSE CF-V-1A & CF-V-1 B.
38 8.0 Operator connects hose from FX-P-2A & B pump N This is a pre-condition to discharge to FLEX feedwater header, connects use backup feedwater power cable to FX-P-2A or B starter, opens FX-V- capability.
203, FX-V-205, EF-V-67A and EF-V-67B.
39 8 to 11 Transfer portable diesel-driven pump (FX-P-3A or y Minimum condensate FX-P-3B) from FLEX storage facility (FSF) to road supply would last greater next to the river, route suction hose into river, and than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
route discharge hose to CO-T-1 B or hotwell.
40 < 10.0 OTSG Pressure is now less than 200 psig. N Design objective is to be Backup feedwater capability is enabled. If backup able to establish a backup feedwater is required, operator starts FX-P-2A or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Band throttles opens FX-V-206A and FX-V-206B to control OTSG level (all action TB 322 north).
41 10.0 RCS cooldown is complete. N
- lncore temperature 400F
- OTSG A & B Pressure 150 psig
- RCS Pressure 400 psig Operator begins raising pressurizer level to > 300 inches 42 12.0 Operator opens SF-V-88, connects hose from N Spent fuel pool boiling FLEX feedwater header to the FLEX primary low occurs after 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.
pressure header, monitors SF pool level and throttles FX-V-101 open as needed to maintain SFP level.
Page 12 of 23
Attachment 1A - Sequence of Events Timeline Earthquake or Tornado@ 100% power
- ELAP Action Time Remarks/
Time Constraint Applicability (HR)
Y/N 43 15.0 Operator props open doors from Unit 2 fuel pool N Spent fuel pool boiling area to the roof to provide a U 1 spent fuel pool occurs after 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.
vent path.
44 24.0 NSRC resources begin arriving on site. N If BWST is damaged by tornado, then a borated NSRC Equipment will be used to provide a quality water supply will be condensate supply and to address longer term required.
needs for fuel oil or borated water.
On site fuel supply is sufficient for greater than 2 weeks.
Page 13 of 23
Attachment 1 B - Sequence of Events Timeline External Flood @ 1OOo/o power
- ELAP Action Time Remarks I Time (only selected actions in AOP-002 listed) Constraint Applicability (HR)
Y/N 1 -36 River level exceeds 284.2 or flow exceeds 200,000 cfs. NA Plant @ 100% power.
Emergency procedure OP-TM-AOP-002 "Flood" is initiated.
2 -35 to Operators maximize condensate tank Note 1 (CO-T-1A & CO-T-1 B) and demineralized water tank
-12 (DW-T-2) inventory.
3 -30 Operators install drain plugs, close drain valves and Note 1 inflate seals for AB & FHB Missile shield doors.
4 - 30 to - Operator connects hose from DF-V-41 to pipe in DGB, Note 1 DF-P-1 C can fill FX-T-2 in 16 connects hose to fuel oil pipe in TB, and routes hose to approx. 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
FLEX DG Fuel Oil Tank (FX-T-2).
Operator starts DF-P-1 C and initiates fill of FX-T-2.
5 - 30 to - Maintenance installs flood barriers and stages, Note 1 12 consumables within the flood protected area.
6 - 22 to - Maintenance installs U2 flood barriers and stages, Note 1 2 consumables within the flood protected area.
7 - 20 Plant shutdown and cool-down initiated. y 8 - 19 to Vent the main generator hydrogen and purge with C02. N
- 12 9 -18 Reactor is shutdown. y 10 -16 RC-P-1 C and RC-P-1 D shutdown and cooldown initiated N 11 -13 RCS cooldown terminated N
- RCS temperature at 375F
- RCS pressure 400 psig
- Pressurizer level 200 to 220 inches
- CF-V-1A & B closed
- MU-V-33C & D closed
- OTSG pressure A & B at 165 psig
- OTSG Level A & B at 97 to 99 % op ranqe 12 -10 RCS boron concentration exceeds cold shutdown boron N concentration requirement.
13 -9 to -8 Operator transfers a pressurizer heater group Note 1 (RC-HTR-GRP- 8 or 9) to the ES power supply.
-6 FLEX truck, FX-P-3A or B, FX-P-4 and FX-Y-4 are Note 1 relocated to the training center.
14 Page 14 of 23
Attachment 1 B - Sequence of Events Timeline External Flood @ 1OOo/o power
- ELAP Action Time Remarks I Time (only selected actions in AOP-002 listed) Constraint Applicability (HR)
Y/N 15 -6 Operator connects hose from FX-P-2A & B pump Note 1 discharge to FLEX feedwater header, connects power cable to FX-P-2A or B starter, opens FX-V-203, FX-V-205, EF-V-67A and EF-V-678.
16 -4 Operator lines up FX-P-1 A & B path from BWST to RCS. Note 1 Operator connects hose from FLEX feedwater header to the FLEX primary low pressure header, and lines up FLEX makeup to the SF pool.
17 -3 Operator connects power cable to FX-P-5A or B, hose Note 1 from FX-P-5A & B discharge to FX-T-3 and FX-P-7 discharge to FX-T-2.
18 -2 Operator opens breakers for BWST tunnel sump pumps Note 1 and closes WDL-V-612 19 -1 Operator strips unprotected DC circuits from DC system Note 1 Prevents loss of battery (OP-TM-734-903 & 904). capacity.
20 0 River level exceeds the height of the dike. NA Failures per NEI 12-06.
LOOP occurs and Emergency Diesel Generators fail to energize ES buses.
21 0 EFW actuated: Steam driven pump (EF-P-1) starts and NA Automatic plant response.
EFW Control valves (EF-V-30A & B) are available to supply feedwater. RCS hot leg and cold leg temperatures diverge. OTSG pressure is dropping slowly.
22 <.02 EOP initiated. NA 23 < 0.05 Letdown isolates (MU-V-3) automatically on high NA Automatic plant response.
temperature.
24 < 0.08 Control Room operators throttle ADV to reduce OTSG N pressure, maintain OTSG level with EFW control valves, and stabilize RCS temperature. Adequate core cooling is provided through RCS natural circulation and heat removal through the OTSG. RCS conditions follow:
- RCS temperature at 400F
- RCS pressure 425 psig
- Pressurizer level 200 to 220 inches
- OTSG pressure A & B at 150 psig
- OTSG Level A & B is maintained 75 to 85 %
operatinq ranqe.
Page 15 of 23
Attachment 1 B - Sequence of Events Timeline External Flood @ 100°/o power
- ELAP Action Time Remarks/
Time (only selected actions in AOP-002 listed) Constraint Applicability (HR)
Y/N 25 < 0.08 Control Room operators attempt to start and load SBO N Diesel Generator.
26 < 0.10 Control Room operator closes RCP Controlled Bleed Off N Contain RCS losses Isolation Valve (MU-V-26). within Reactor Bldg.
27 < 0.17 Control room operators recognize SBO Diesel generator N Failure per NEI 12-06.
is not functional.
28 0.25 Operator performs E-plan offsite notifications & N communication using satellite phones.
29 < 0.25 Operator close FS-V-256 & FS-V-257 to terminate N IA-P-1 A & B cooling water flow into IB sump.
30 < 0.5 Operator lines up FLEX Diesel Generator. y Pre-condition to maintain vital AC power and restore RCS makeup.
31 0.5 Operator opens doors to inverter and battery rooms for y Maintain acceptable FLEX ventilation. equipment cooling.
32 .75 Operator strips loads from 1P & 1S 480V Buses, and 1A N Pre-condition to maintain
& 1B ES MCC to prepare to load FLEX diesel generator. vital AC power and restore RCS makeup.
33 < 1.0 Operator starts FLEX Diesel Generator, energizes FLEX N Pre-condition to maintain Distribution Panel and closes breakers to energize 1P- vital AC power and 1S 480V cross tie bus. restore RCS makeup.
34 1.0 Operator closes breakers to energize 1P 480V Bus, 1S y Pre-condition to maintain 480V Bus, 1A ES MCC and 1B ES MCC. vital AC power and restore RCS makeup.
35 1.25 Operator closes breakers for selected loads on A and B y Pre-condition to maintain 480V ES Bus: vital AC power and
- Battery Chargers restore RCS makeup.
- AC Power to Inverters & Vital Instruments
- Pressurizer heater Qroup 36 1.5 Operator starts FLEX RCS Makeup Pump (A or B) and N slowly raises pressurizer level above 300 inches.
37 2.0 If backup feedwater is required, then operator starts N FX-P-2A or Band throttles open FX-V-206A and FX-V-206B to control OTSG level.
Page 16 of 23
Attachment 1B - Sequence of Events Timeline External Flood @ 1OOo/o power
- ELAP Action Time Remarks I Time (only selected actions in AOP-002 listed) Constraint Applicability (HR)
Y/N 38 2.0 Operator takes local control of MS-V-6 (EF-P-1 steam y Bottled air system will last supply), EF-V-30A & EF-V-30B (EFW Flow Control at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and then Valves) and MS-V-4A & MS-V-4B (Atmospheric Dump manual control is Valves). required.
39 2.5 Operator strips loads on 1A ESV MCC and installs N jumper between 1A ESV MCC and 1A Radwaste MCC.
40 3.0 Operator energizes1A ESV MCC and 1A Radwaste N MCC, and Closes CBO Isolation Valves MU-V-33A and MU-V-33B.
41 3.5 Operator use FX-V-8 to gravity drain fuel oil from FX-T-2 y Required for continued to maintain level in FX-T-3. operation of FX-Y-1 A or B. Pre-staged fuel supply will last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at full load.
42 4.0 Operator sets up and starts temporary ventilation in CB, N IB and TB.
43 15.0 Operator lines up spent fuel pool vent path N Spent fuel pool boiling occurs after 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.
(opening doors through U2 fuel pool to atmosphere).
44 24.0 NSRC resources are available. No equipment is required N until after water level recedes from the site.
45 > 24 Operator throttles open FX-V-101 as needed to maintain N Spent fuel pool boiling SFP level. occurs after 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.
46 > 96 Transfer portable diesel-driven pump (FX-P-3A or FX-P- N Minimum condensate 3B) from temporary offsite storage to road next to the supply would last greater river, route suction hose into river, and route discharge than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after water hose to CO-T-1 B. recedes.
NOTE 1: In the event of a flood, additional resources are applied to ensure the proactive actions can be completed within the described timeline.
f '
Page 17of23
Attachment 1C - Sequence of Events Timeline Extreme Cold, Snow and Ice @ 1OOo/o power
- ELAP Action Time Remarks/
Time Constraint Applicability (HR)
V/N
-8 Weather predicts extreme cold conditions. NA Staff augmentation is initiated.
-4 Staff augmentation is complete. NA 1 0 Extreme cold, snow or ice causes LOOP. NA All control rods are inserted and the reactor is shutdown.
See Attachment 1A items 2 through 41.
42 12.0 Operator connects a hose from main steam drain N line to piping connected to condensate tank 8 and initiates tank heating.
43 12.0 8WST immersion heater 1A is energized from 1A N ESF MCC.
44/ See Attachment 1A items 42 and 43.
45 46 48 Establish condensate resupply using (1) Portable N Minimum condensate diesel-driven pump (FX-P-3A or FX-P-38) placed supply would last greater on ramp with suction hose into river, and route than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
discharge hose to CO-T-1 B or (2) Portable submersible (FX-P-6A & 8) dropped into ISPH pump bay and discharge routed to CO-T-1 8.
Page 18 of 23
Attachment 2A 1 E-919-21-001, draft, FLEX Diesel Generator and Fuel Oil System REVISIONS REY ZONE DESCRIPTION 1D NEW DRAWING PER ECR 1+-00032 REV. 1 FUEL OIL CONTAINER FX-HOSE-Y OUTSIDE lURBINE (PHASE 3) VENT BUILDING CONTROL BUILDING ROOF VENT VENT VENT FX-V10 EXHAUST 3 SECT. OF SILENCER
/ FX-HOSE-Y s* FX-Y-2 I
I FX-V15 I
I I
I I
I I GENERATOR I I DIESEL GENERATOR COMPRESSED I FX-Y-1A
/ AIR F1TTING I
FX-Fl-1003 I FX-V2
- r--@-rc I 3 SECT. OF FX-HOSE-Y ........._
~ .... FX- V19 I FX-HOSE-Y-X1 FX-HOSE-Y-X3 I FX-V11B I
HOSE COUPLING FX-V1 FX-V10 FX-HOSE-Y-X1
- i--L-c FX-HOSE-Y-X2 FX-HOSE-Y-X4 1*
l:rr-c / FX-Pl -1004 HOSE TEE I "' FX-P-SA
.-----*-FX-V13B FX-T3-FILL I FX-V2 T
FX-HOSE-Y-X4 I 1*
FX-VSB I FX-P-58 lURBINE BUILDING
,---+ -----------------r- EL 322'-0" I : 1 I :
FX-HOSE-Y I
SI Slf I 1* I DF~~-2B'7-L"-i:.-:J---~* ,._+-,+-.....--'--+-lmf-l-~~~......L-l 1 ...
DF-V40 I DF-V41 "' FX-V1 1 FX-HOSE-Y-X1
~ FO-V81 FUEL 'oil-------, I TRANSFER PUMPS l I r---.!lE.-_V!~ I I RElURN
- AUX BOILER ~
TO ':r- __lil;JlJB!Lelft;_ __ ~ FO-V11A OR B I ,Jl--~J I FO-T-1 TAILPIPE DRAIN r---J-C.....J DF-vad, I
! DF-P-1C ! I lURBINE BUILDING I ,... ___ !!f'.=.Yf!!-l!Jt I I EL 305'-0" I I I : I DRAFT I I ,Jl--~J I S~Y ..,.J.----J-C.....J DF-V8D I I FLEX OVERVIEW DIESEL GENERATOR & FUEL OIL DF-T-1 DF-P-10 I IN1ERMEDIATE I DIESEL I BUILDING I ""'*
GEN. BLOG.
.... .... .... mu:
Page 19 of 23
Attachment 28 1E-919-21-002, draft, FLEX Electrical Distribution REVISIONS REV ZONE De.SCRIPTION 1D NEW DRAWING PER ECR 14-00032 REV. 1 RELAY TEMPORARY
'TEST LOAD BANK PHASE 3 FX-Y-18 a<:!)).-...---:FX~~B-BK=-=,,.,....~--'rr DIESEL GENERATOR FX-CABLE-0 FX-cABLE-0 FX-CAEll.£-02 (22 REQ'D) (11 REQ'D)
FX-Ql\BLE-B (8 REQ'O)
Tiii DWG.NO.
1E-91~1-00Z
"" 1D Page 20of23
Attachment 2C 1 E-919-21-003, draft, FLEX Feedwater System REVISI ONS REV ZONE DESCRIPTION 1D NEW DRAWING PER ECR 14-00032 REV.
FX-HOSE-X r------------------------~i::-~~~-1.:~~~-=-~~=~~-===~!::c~~~~==~=~~-~------------------------1 ~~~JI.-~E~iP~~TH
!10*
I I.------E~=!.=!..~-------. I
,_.:r___E~=!.=!..E! _____....,
I I
.-------~-=--...!.:-3______ ....,
I I
!I .------_!!~--------.
I I I 216,000 GALLONS ,I I 216,000 GALLONS I I 232.000 GALLONS I 1 I 31.BOO GALLONS I
- CO-V14A C0-V10A: AVAILABLE ABOVE I : AVAl~LE ABOVE : I AVAILABLE ABOVE I I : AVAILABLE ABOVE 303'-6"1 1 Ci),. Ci) 1 305' ELEV. 0 1 Ci) 1 305 El.EV. 0 1 1 315' ELEV. 0 MIN. 1 I Ci) I 0 MIN LEVEL 8 FT 1 L_~!._2_:,.-r-t>l<J---l II I II I I I
sm s1 a*:I ! ._ _________________ __.
I MIN. LEVEL OF 16' ..---t:::.&.:J---l II co-v10e ._
MIN. LEVEL OF 1 s*
I _________________; I LEVEL OF 21 *
._ ________ T _ _ _ _ _ _ _ _ __.I L--..i.---...l co-v12 Sif"-slil I ____ f ____ l ___ __.I
- ! L____i*----~-----~-----J
~co-v1 6A co-v111A co-v111B I =
~tt-;
.y~v1038 co-vs~
L 10
. N.o,$ow-V2a 1 10*
N c.
~-----=-~----~
?I 12* I I I
T : Vi~
- I .. ~~ V 6" ~ II TO or.;c
~
~
1 EF-V1A
~
I I 12*
~ CO-V103A~* I 1
1 I
Vi CO-V24
- I 1
DW-V32""""
N.0. ~
Nc L-----i
- N.C. 1 DW-V30
" -~ Siii Slf IN.0.
- 10 1
CO-V8
- I
- 6" "'?
Slf Siii 1-----(><J---------Dic:r----'
INTERMED.
BUILDING REACTOR BUILDING
---c;---, I a* M a* : ~ I ho* I -------t..--4----'----r-..t------~ CO-V108 CO-V7
\._~_-:,r---'---------EF-V1B------~~6-;.----., C¥JI !10" ! ! Ci) DW-V34 OW-V35 ! 12" "T"' _ 6 - EF-V52D EF-V12A!
EF-P-1 t_ ___ -t>l<j-___ l __ J_,.-.!.~------1--t:::.&.:J-------------------------.._I FROM EF-P-1 --~-----l><J-- --N--.J-- 01SG A CO-V<"8 ~ CO-V'3 ~FX-HOSE-X TO FX-V-H3 <F-Y300 3" 1-:::.,,
~ ~*
l----~~~IDWG.1E,919-21-00:.
(4 REQ'D) EF-V67A 40 ,------
- I ~---=-----------------r,-/~2~-----
I 3* I FX-V207A j I
. I 'f I ""? 6
- EF-V52B FROM EF-P-1 ------{:MLCJ-- --e-<:r------+- 01SG e 4* 3~ I 3"
~l-}-P{;;l-><1::J00-11 <(B>
EF-V30B EF-V67B :=-*
- T
. _ _ _. . .. _ _ . . . . __ _.L-_ _ _ _ _ 3*_ _ _ _ _ _ _ _ _ _ _ _ _ _ -r:-1~/~2-=-'
FX-V207B FLEX FEEDWATER HEADER INTERMEDIATE BUILDING TURBINE BUILDING EL 322'-0" EL 29!5'-0" 'f NOTE: "'INDICATES A CHANGE IN NORMAL VALVE POSmON.
THIS 1$ A COMPuTI!*
GeNrllAT1!0 DltAWIHG DO NOT lteYISI! IT MANUAU.T DRAFT FLEX OVERVIEW FEEDWATER SUPPLY TANK/PUMP SKID . v.
TURBINE BLDG. 292" ...... DW<O.NO.
1E-91 9-21~3 SH.
NA 1D
.... WA. NO.
Page 21of23
Attachment 20 1 E-919-21-004, draft, FLEX RCS and SFP Makeup System REVISIONS REV ZONE DESCRIPTION 1D NEW DRAWING PER ECR 14-00032 REV*
.--111----Ckr-~
....-~~~~..___~~~
WDL-V22* I WDL-T-1C I~*
lYPICALLY MORE I THAN 50,000 rt..S7woL-V37 GALLONS ABOVE " Lf"-
2200 PPMB I o-tI WDL-V31
~-I
,..~_:'~
I t..!5.: ~
t:::;t-.-.i _1L
- v2-WOL-P-6C~1 WDL-V34 WOL-V38
¢
- $:WDL-V421 T_~-
FROM MOBILE BORATION SKID SEE DWG 1E-919-21-005
~V304f\
2* PIPE CAP/.*~/
2* P IPE I J FX-V111 2* PIPE CAP rs-it1:~~)z AUX BLDG 305 WEST WALL CONTROL TURBINE VENTILATION EQUIP ROOM CA-V220 11/.
FX-V102B FX-Pl-1002 BLDG. BLDG.
FX-V112BI 'IHIS ts ACOM~
RECLAIMED WATER GENERATED 0"'-WING DO DRAFT NOT REVtSI! IT MANUAU.Y FLEX OVERVIEW I REACTOR COOLANT !It SPENT RJa MAKEUP RCS/SFP MU PUMPS DW'G. NO. SH.
CONTROL BLDG. PATIO TMI 1 1:-91 9-21-004 NA 1D EL. 322"-o* SCALE : N LI!
285" WA.NO.
Page 22 of 23
Attachment 2E 1 E-919-21-005, draft, Long Term water supply REVISIONS REV ZONE DESa11P110N 1D NEW DRAWING PER ECR 14-00032 REV. I OUTSIDE PROT. AREA INSIDE PROT. AREA 14 SECT. OF FX-HOSE-X DIKE WEST MAIN STEAM OF NOB (306 ELEV.) i'3/4" FX-HOSE-F-X5 5 SECT. OF FX-HOSE-X *MS-V78
\ ...L.
~-HOSE-G
'--~~~~~--'~*.AirJlilrn'JU;p ,......-FX-HOSE-F-X3 l I EF-V17
,T--------, . 1*
I t-1--iXJ-.L-- ~EFW PUMP IN I C0-T-1B I C0-V176 RECIRC.
I I (ijl 12*
I I- ~ ~SEE OWG. IE-919-21-00J WATER TREATMENT SKID L_ - - - - - - - ...JCO-VIOB (PHASE 3) - - - 13 SECT. OF FX-HOSE-X
~ Ex:f-=1 ~
MOBILE I NOTE I I BORATlON I SKID I I (PHASE 3) E:)-1 f-FX-HOSE-X TO AB WEST WAU. TB 322 25 SECT. OF FX-HOSE-X------
FX-P-4 SEE IMC IE-919-21-004 L - -
0-K J EX-V9 e*
r--0--
._j s*
UNIT 1 ISPH FX-HOSE-X/
t_r---------;
1 I HOTWELL I
~----,
I I N.C.
FX-P-6A-BK I '?1 ~ '?12*
MAIN STEAM~ ....,._s:__-t><r- - _ _ _ _ _ _ _ _ - -f"L.J--'- ~SEE I
I MS-V3A MS-V12A I j co-w OWG. lE-919-21-00J EL 308 I FX-CABLE-G1 I I ~I---=--- I U TB 292 I I I FX-HTR-1 ~
I FX-HOSE-F I I
I L-<>- ~ ~ - - :1 480V IFX-Y-3 I
I FX-Y-3-BK EL 305 DIESEL GEN.
&'1189- DRAFT NOTES: FLEX OVERVIEW MIN. WATER "'--"--"--"'-"'--".V-.-"-"--""_,._,.'-"'.._,,.'---"'--""-"'-"'.._,,..._1/'.../'....-"'--'
LEVEL 272' 1. REMOVE 6" HAND HOLE COVER TO Pl.ACE HOSE IN TANK. LONG TERM WATER SUPPLY DWG. NO. SH. REV.
T'MI 1E-919-21-oo5 MA tD SCALE:
... ND.
Page 23 of 23