NLS2014082, Third Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
| ML14246A188 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/26/2014 |
| From: | Limpias O Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-12-049, NLS2014082 | |
| Download: ML14246A188 (14) | |
Text
Nebraska Public Power District Always there when you need us NLS2014082 August 26, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Nebraska Public Power District's Third Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA- 12-049)
Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
- 1. 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
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, "Compliance with Order EA- 12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," Revision 0, dated August 29, 2012
- 3. NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide," Revision 0, dated August 2012
- 4. NPPD Letter, "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 29, 2012
- 5. NPPD Letter "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
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued an Order (Reference 1) to Nebraska Public Power District (NPPD). Reference 1 was immediately effective and directs NPPD to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in Attachment 2 of Reference 1.
COOPER NUCLEAR STATIONAK P.C. Box 98 / Browniville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.vnppd.com
NLS2014082 Page 2 of 3 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 Nuclear Energy Institute 12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided NPPD's initial status report for Cooper Nuclear Station (CNS) regarding mitigation strategies. Reference 5 provided CNS' Overall Integrated Plan for diverse and flexible coping strategies (FLEX).
Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports. The purpose of this letter is to provide the third 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. Attachment 1 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. provides revised pages in CNS' Overall Integrated Plan for FLEX.
This letter contains no new regulatory commitments.
Should you have any questions regarding this report, please contact David Van Der Kamp, Licensing Manager, at (402) 825-2904.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: O________
Vice President - Nuclear and Chief Nuclear Officer
/bk Attachments: 1. Nebraska Public Power District's Third 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
- 2. Cooper Nuclear Station - Overall Integrated Plan for Diverse and Flexible Coping Strategies (FLEX), Revised Pages
NLS2014082 Page 3 of 3 cc: Regional Administrator, w/attachments USNRC - Region IV Director, w/attachments USNRC - Office of Nuclear Reactor Regulation Senior Resident Inspector, w/attachments USNRC - CNS Cooper Project Manager, w/attachments USNRC - NRR Project Directorate IV- 1 NPG Distribution, w/attachments CNS Records, w/attachments
NLS2014082 Attachment I Page 1 of 6 Attachment 1 Nebraska Public Power District's Third 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 Introduction Nebraska Public Power District (NPPD) developed an overall integrated plan for Cooper Nuclear Station (CNS) (Reference 1), documenting the diverse and flexible coping strategies (FLEX), in response to Reference 2. This attachment provides an update of milestone accomplishments since submittal of the second status report to the overall integrated plan (Reference 3), including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
Milestone Accomplishments The following milestone(s) have been completed since the submittal of the second status report for the overall integrated plan, and are current as of August 15, 2014:
0 Develop Storage Plan Milestone Schedule Status The following table 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.
Target Revised Target Milestone Completion Status Completion Date Date 60-day Status Update October 2012 Complete Submit Overall Integrated Plan February 2013 Complete 6-month Status Update August 2013 Complete 6-month Status Update February 2014 Complete Regional Response Center TBD Started September 2014 Operations Develop Storage Plan May 2014 Complete Purchase FLEX Equipment June 2014 Started December 2014
NLS2014082 Page 2 of 6 Target Revised Target Milestone Completion Status Completion Date Date Refine Strategies June 2014 Started December 2014 (post-NRC review)
Issue Maintenance Procedures August 2014 Not Started December 2014 (for FLEX equipment) 6-month Status Update August 2014 Complete Develop Strategies / Contract with Regional Response Center August 2014 Not Started April 2015 Develop Training Plan October 2014 Not Started December 2014 Implementation Outage I Fall 2014 Not Started Develop Online Mods and December 2014 Started Implementing Procedures 6-month Status Update February 2015 Not Started Walk-throughs or April 2015 Not Started Demonstrations Implement Training May 2015 Not Started 6-month Status Update August 2015 Not Started Develop Outage Mods and October 2015 Not Started Implementing Procedures Implement Online Mods and December 2015 Not Started Procedures 6-month Status Update February 2016 Not Started Perform Staffing Assessment May 2016 Not Started 6-month Status Update August 2016 Not Started Implementation Outage 2 Fall 2016 Not Started Implement Outage Mods and Fall 2016 Not Started Procedures Implement Training Updates Fall 2016 Not Started Submit Completion Report Fall 2016 Not Started
NLS2014082 Attachment I Page 3 of 6 Changes to Compliance Method There are no changes to the compliance method at this time.
During review of the overall integrated plan, it was discovered that instruments CM-LI-1681 B (ECST Level) and PC-LI- 110 (Torus Level) had the wrong ranges listed. The affected pages have been corrected. This error has no effect on the overall strategy, compliance method, or implementation of the overall integrated plan. to this letter provides the revised pages of the overall integrated plan with the correction discussed above. Revision 2 of CNS' Overall Integrated Plan for FLEX has been posted to the ePortal system.
Need for Relief/Relaxation and Basis for the Relief/Relaxation NPPD expects to comply with the Order implementation date and no relief/relaxation is required at this time.
Open and Confirmatory Items in the Interim Staff Evaluation In Reference 4, the Nuclear Regulatory Commission (NRC) issued the Interim Staff Evaluation (ISE) for CNS relating to the overall integrated plan. The following table provides a summary of the confirmatory items documented in the ISE and the status of each item. There were no open items identified in the ISE.
ISE Confirmatory Items Item Number Description Status 3.1.1.2.A Confirm that the required debris removal Open equipment remains functional and deployable to clear obstructions from pathways between the FLEX storage locations and deployment locations, after the FLEX storage building locations are finalized.
3.1.1.4.A Confirm the location(s) of the staging area(s) for Open equipment from the RRC, and the licensee's plans for transportation from the RRC, staging, and on-site deployment is in accordance with the guidance in NEI 12-06, Sections 5.3.4, 6.3.4, 7.3.4, and 8.3.4, or provide an acceptable alternative to that guidance.
3.1.3.1 .A Confirm that when the FLEX equipment storage Open building locations are finalized, separation distance and axis of separation is reviewed to confirm that the building locations are consistent
NLS2014082 Attachment I Page 4 of 6 ISE Confirmatory Items Item Number Description Status with the recommendations in NEI 12-06, Section 7.3.1.
3.1.4.2.A Confirm that obtaining makeup water from the Open Missouri River during an ELAP event adequately addresses NEI 12-06, Section 8.3.2, consideration 3.
3.2.1.1 .A Benchmarks must be identified and discussed Open which demonstrate that Modular Accident Analysis Program (MAAP) is an appropriate code for the simulation of an ELAP event at CNS, consistent with the NRC endorsement (ADAMS Accession No. ML13275A318) of the industry position paper on MAAP.
3.2.1.1.B The licensee should demonstrate that the collapsed Open reactor pressure vessel level remains above Top of Active Fuel and the reactor coolant system cool down rate is within technical specifications limits.
3.2.1.1 .C The licensee should demonstrate that MAAP is Open used in accordance with Sections 4.1, 4.2, 4.3, 4.4, and 4.5 of the June 2013 position paper (ADAMS Accession No. ML13190A201).
3.2.1.1.D The licensee must identify, in using MAAP, the Open subset of key modeling parameters cited from Tables 4-1 through 4-6 of the "MAAP Application Guidance, Desktop Reference for Using MAAP Software, Revision 2" (Electric Power Research Institute Report 1020236, available at www.epri.com). This should include response at a plant-specific level regarding specific modeling options and parameter choices for key models that would be expected to substantially affect the ELAP analysis performed for CNS.
3.2.1.2.A Confirm that the analysis for a long-duration Open ELAP event shows that the reactor recirculation pump seal leakage value does not exceed the value used in analysis of a 4-hour station blackout event.
3.2.1.3.A Confirm that the method for transferring water Open from the hotwells to the ECSTs, including flow path, valves, pumps, and related equipment, when developed, is reliable.
3.2.1.3.B Confirm that the RCIC room heatup evaluation Open and RCIC room flooding time evaluation are
NLS2014082 Page 5 of 6 ISE Confirmatory Items Item Number Description Status completed with acceptable results.
3.2.1.3.C Confirm that the licensee's staffing assessment is Open completed and it shows that proposed actions from the FLEX strategies can be completed within the specified time constraints.
3.2.1.4.A Confirm that the Phase 2 FLEX equipment Open performance criterion, when developed, supports the licensee's mitigation strategies.
3.2.2.1 .A Confirm that modifications to the reactor building Open roof hatch provide the ability to maintain adequate SFP area ventilation.
3.2.3.A Confirm that CNS's containment venting strategy Open is finalized and that the strategy supports both containment pressure protection and proposed RCIC and Phase 2 FLEX pump operation.
3.2.3.B With regard to maintaining containment, the Open implementation of BWROG Emergency Procedure Guideline/Severe Accident Guideline, Revision 3, including any associated plant-specific evaluations, must be completed in accordance with the provisions of NRC letter dated January 9, 2014 (ADAMS Accession No. ML13358A206).
3.2.4.2.A Confirm that fan sizing evaluations support Open adequate ventilation in the main control room, in the RCIC room, and in other applicable plant areas.
3.2.4.6.A Confirm that analyses addressing heat up in areas Open that might have personnel habitability considerations conform to the guidance in NEI 12-06, Section 3.2.2, Guideline 11, or provide an acceptable alternative to that guidance.
3.2.4.7.A Confirm that the design provisions, as well as Open operational and protection requirements for the new on-site well/water treatment equipment used for Phase 2 water sources adequately support CNS's proposed ELAP strategies.
3.2.4.8.A Confirm that adequate electrical interaction and Open isolation considerations are adequately addressed.
3.2.4.8.B Confirm that the sizing of the portable FLEX Open diesel generators adequately supports CNS's ELAP mitigation strategy.
3.2.4.8.C Provide single-line diagrams showing the proposed Open
NLS2014082 Page 6 of 6 ISE Confirmatory Items Item Number Description Status connections of Phase 2 and Phase 3 electrical equipment and showing protection information (e.g., breaker, relay, or fuse) and rating for the equipment used when available.
3.2.4.1 O.A Confirm that the minimum dc voltage and dc load Open profile for the ELAP have been determined, the minimum dc bus voltage and the associated load profile supports CNS's proposed ELAP mitigation strategy.
References The following references support the status update to the overall integrated plan described in this attachment:
- 1. NPPD Letter, "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
- 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. NPPD Letter, "Cooper Nuclear Station's 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 26, 2014
- 4. NRC Letter, "Cooper Nuclear Station - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA- 12-049 (Mitigation Strategies) (TAC No.
MF0972)," dated February 11, 2014
NLS2014082 Page 1 of 5 Attachment 2 Cooper Nuclear Station -
Overall Integrated Plan for Diverse and Flexible Coping Strategies (FLEX)
Revised Pages Cover page (new)
Page 14 Page 21 Page 24
CNS Overall Integrated Plan for Diverse and Flexible Coping Strategies (FLEX) - Revision 2 Revision Date Description of Change 0 2/28/2013 Initial submittal 1 2/15/2014 Corrected timeline and updated milestones 2 7/30/2014 Corrected instrument ranges for CM-LI-1681B and PC-LI- 110 Page 1 of 53
CNS Overall Integrated Plan for Diverse and Flexible Coping Strategies (FLEX) -
Revision 2 Key Reactor List instrumentationcreditedfor this coping evaluation.
Parameters Parameter Instrument Indicator Location RPV Level Narrow Range RFC-LI-94A, B and C (0 to 60") Control Room RPV Level Narrow Range NBI-LIS 83A and B (0 to 60") Local rack NBI-LIS-101A, B, C and D (0 to 60") Local rack RPV Level Wide Range NBI-LI-185B (-155" to + 60") Local ASDR RPV Level Wide Range NBI-LIS-57A and B (-150" to +60") Local rack NBI-LIS-58A and B (-150" to +60") Local rack NBI-LIS-72A, B, C and D (-150" to Local rack
+60")
RPV Level Fuel Zone NBI-LI-191B (-320" to +60") Local ASDR RPV Level Fuel Zone NBI-LITS-73A and B -260" to +40") Local rack RPV Pressure RFC-PI-90A, B and C (0 to 1200 psig) Control Room RPV Pressure NBI-PIS-60A and B (0 to 1500 psig) Local rack NBI-PIS-52B and D (0 to 500 psig) Local rack NBI-PI-61 (0 to 1500 psig) Local rack Drywell Pressure PC-PI-513 (0 to 2 psig), PC-PI-2104AG Local rack (0 to 100 psig)
Torus Pressure PC-PI-20 (0 to 2 psig), PC-PI-2104BG Local rack (0 to 100 psig)
Drywell Temperature PC-TI-505A, B, C, D and E (50 to Control Room 600F)
Drywell Temperature PC-TE-505A,B, C, D and E, with use of Control Room M&TE (50 to 600F)
Torus Temperature PC-TE-1A thru H and PC-TE-2A thru H Local, Cable with use of M&TE (0 to 250F) Spreading Room Torus Temperature PC-TI-2A, C, E and G (0 to 250F) Local ASDR Torus Level PC-LI-1 10 (-6' to +6' H20) Local ASDR I ECST Level CM-LI-1681B (2' to 16' H20) Local ASDR ECST Level HPCI-PI-1 17A, convert pressure to Local rack level Spent Fuel Pool Level TBD, NRC Order EA-12-051 Spent Fuel Pool Level Visual Local at SFP Spent Fuel Pool Temperature M&TE Local at SFP ASDR - Aux Shutdown Room TAF = -158" Notes: None.
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CNS Overall Integrated Plan for Diverse and Flexible Coping Strategies (FLEX) -
Revision 2 NPPD will evaluate the following potential modifications to address this phase:
- Modification for connection of 4160 VAC RRC DG to the F or G 4160 VAC bus is made by modifying a spare breaker in the warehouse to be able to accept the cable connections from the RRC DG such that in Phase 3 that breaker can be inserted into a spare slot or non-required breaker to connect the DG to the bus. (Primary Strategy)
- Modification to allow re-powering the Reactor Building Aux Condensate Pump.
Key Reactor List instrumentationcredited or recoveredfor this coping evaluation.
Parameters Parameter Instrument Indicator Location RPV Level Narrow Range RFC-LI-94A, B and C (0 to 60") Control Room RPV Level Narrow Range NBI-LIS 83A and B (0 to 60") Local rack NBI-LIS-101A, B, C and D (0 to 60") Local rack RPV Level Wide Range NBI-LI-185B (-155" to + 60") Local ASDR RPV Level Wide Range NBI-LIS-57A and B (-150" to +60") Local rack NBI-LIS-58A and B (-150" to +60") Local rack NBI-LIS-72A, B, C and D (-150" to Local rack
+60")
RPV Level Fuel Zone NBI-LI-191B (-320" to +60") Local ASDR RPV Level Fuel Zone NBI-LITS-73A and B -260" to +40") Local rack RPV Pressure RFC-PI-90A, B and C (0 to 1200 psig) Control Room RPV Pressure NBI-PIS-60A and B (0 to 1500 psig) Local rack NBI-PIS-52B and D (0 to 500 psig) Local rack NBI-PI-61 (0 to 1500 psig) Local rack Drywell Pressure PC-PI-513 (0 to 2 psig), PC-PI-2104AG Local rack (0 to 100 psig)
Torus Pressure PC-PI-20 (0 to 2 psig), PC-PI-2104BG Local rack (0 to 100 psig)
Drywell Temperature PC-TI-505A, B, C, D and E (50 to Control Room 600F)
Drywell Temperature PC-TE-505A,B, C, D and E, with use of Control Room M&TE (50 to 600F)
Torus Temperature PC-TE-1A thru H and PC-TE-2A thru H Local, Cable with use of M&TE (0 to 250F) Spreading Room Torus Temperature PC-TI-2A, C, E and G (0 to 250F) Local ASDR Torus Level PC-LI-1 10 (-6' to +6' H20) Local ASDR ECST Level CM-LI-1681B (2' to 16' H20) Local ASDR ECST Level HPCI-PI-1 17A, convert pressure to Local rack level Spent Fuel Pool Level TBD, NRC Order EA-12-051 Spent Fuel Pool Level Visual Local at SFP Spent Fuel Pool Temperature M&TE Local at SFP ASDR - Aux Shutdown Room TAF = -158" Page 21 of 53
CNS Overall Integrated Plan for Diverse and Flexible Coping Strategies (FLEX) -
I Revision 2 Details:
Provide a brief Confirm that procedure/guidanceexists or will be developed to description of support implementation.
Procedures /
Strategies /
Guidelines.
CNS will utilize the industry developed guidance from the Owners Groups, EPRI, and NEI Task team to develop site specific procedures or guidelines to address the criteria in NEI 12-
- 06. These procedures and/or guidelines will support the existing symptom based command and control strategies in the current EOPs.
Identify modifications List modifications.
Hardened Containment Vent System (i.e., Reliable Hardened Vent) is currently installed but will be enhanced in accordance with NRC Order EA-12-050, Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents.
Key Containment List instrumentationcreditedfor this coping evaluation.
Parameters Parameter Instrument Indicator Location Drywell Pressure PC-PI-513 (0 to 2 psig), PC-PI- Local rack 2104AG (0 to 100 psig)
Torus Pressure PC-PI-20 (0 to 2 psig), PC-PI- Local rack 2104BG (0 to 100 psig)
Drywell Temperature PC-TI-505A, B, C, D and E (50 to Control Room 600F)
Drywell Temperature PC-TE-505A,B, C, D and E, with use Control Room of M&TE (50 to 600F)
Torus Temperature PC-TE-1A thru H and PC-TE-2A Local, Cable thru H with use of M&TE (0 to 250F) Spreading Room Torus Temperature PC-TI-2A, C, E and G (0 to 250F) Local ASDR Torus Level PC-LI- 110 (-6' to +6' H20) Local ASDR Hard Pipe Vent Open Indication PC-RIL-SPV32 Control Room Hard Pipe Vent Closed PC-GIL-SPV32 Control Room Indication PC 233MV Open Indication PC-RIL-MV233 Control Room PC 233 MV Closed Indication PC-GIL-MV233 Control Room PC 237AV Open Indication PC-RIL-SPV237 Control Room PC 237AV Closed Indication PC-RIL-SPV237 Control Room ASDR - Aux Shutdown Room Notes: None.
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