ML18051A175: Difference between revisions

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{{#Wiki_filter:1Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy (XE)Prairie Island Nuclear Generating Plant 02-20-2018 1
{{#Wiki_filter:1 Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy (XE)Prairie Island Nuclear Generating Plant 02-20-2018 1
2Agenda*Background & Schedule  
2 Agenda*Background & Schedule  
*Discuss-Variations from TSTF-425
*Discuss-Variations from TSTF-425
-Site-specific TSSR 3.0.2
-Site-specific TSSR 3.0.2
Line 55: Line 55:
-No affect on TSTF-425
-No affect on TSTF-425
*Model License Amendment Request (LAR) unchanged
*Model License Amendment Request (LAR) unchanged
*Model No Significant Hazards Consideration determination unchanged
*Model No Significant Hazards Consideration determination unchanged*NRC Model Safety Evaluation (SE) unchanged
*NRC Model Safety Evaluation (SE) unchanged
*Not considered a variation to the TSTF 6
*Not considered a variation to the TSTF 6
7PRA Technical Adequacy
7PRA Technical Adequacy
Line 65: Line 64:
-PINGPIPEEEconcluded other exter nal hazards to be negligible contributors to overall plant risk
-PINGPIPEEEconcluded other exter nal hazards to be negligible contributors to overall plant risk
*Shutdown Events
*Shutdown Events
-Shutdown risk management program consistent with NUMARC 91-067 8PRA Technical Adequacy
-Shutdown risk management program consistent with NUMARC 91-06 7 8PRA Technical Adequacy
*Fire -Fire PRA developed for NFPA-805  
*Fire -Fire PRA developed for NFPA-805  
*NFPA-805 LAR approved August 8, 2017
*NFPA-805 LAR approved August 8, 2017
Line 74: Line 73:
9PRA Technical Adequacy
9PRA Technical Adequacy
*Conclusion
*Conclusion
-PINGPPRA models sufficiently robust and suitable for SFCP9 10Questions and Feedback 10?
-PINGPPRA models sufficiently robust and suitable for SFCP 9 10 Questions and Feedback 10?
11Acronyms*CLB-Current Licensing Basis
11 Acronyms*CLB-Current Licensing Basis
*F&O-Finding and Observations
*F&O-Finding and Observations
*FIVE -Fire Induced Vulnerability Evaluation  
*FIVE -Fire Induced Vulnerability Evaluation  
Line 86: Line 85:
*PRA -Probabilistic Risk Assessment
*PRA -Probabilistic Risk Assessment
*RFO-Refueling Outage
*RFO-Refueling Outage
*SE -Safety Evaluation 11 12Acronyms*SFCP-Surveillance Frequency Control Program
*SE -Safety Evaluation 11 12 Acronyms*SFCP-Surveillance Frequency Control Program
*SMA-Seismic Margins Analysis
*SMA-Seismic Margins Analysis
*TS-Technical Specification
*TS-Technical Specification

Revision as of 02:40, 6 July 2018

Prairie Island Nuclear Generating Plant - Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy 2/20/2018
ML18051A175
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 02/20/2018
From:
Northern States Power Co, Xcel Energy
To: Kuntz R F
Plant Licensing Branch III
Kuntz R F
References
Download: ML18051A175 (12)


Text

1 Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy (XE)Prairie Island Nuclear Generating Plant 02-20-2018 1

2 Agenda*Background & Schedule

-Site-specific TSSR 3.0.2

-Probabilistic Risk Assessment (PRA)

  • Fire Model
  • Questions and Feedback 2

3Background & Schedule

  • TSTF-425-Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Initiative 5b)

-Licensee controlled program called the Surveillance Frequency Control Program (SFCP) and is in accordance with NEI04-10

-Planned submittal first quarter 2018

-Requesting approval by April 2019

-Implement prior to Fall 2019 Refueling Outage (RFO) 3 4Variations

  • Variations for the application include
-Revised (clean) TSpages not included

-TSBases insert consistent with the April 14, 2010 NRC letter removing the frequency basis

-Cross-reference list for TSTF-425 (NUREG-1431) markups to PINGPsite specific TSSRs provided

-Administrative changes

  • An expired one-time frequency extension is deleted
  • Two minor formatting changes 4

5PINGP'sTSSR 3.0.2

  • PINGPSR 3.0.2 contains a restriction not in NUREG-1431:

-NUREG-1431 SR 3.0.2 permits a 25% extension of the interval specified in the Frequency

-PINGPSR 3.0.2 also permits a 25% extension of the specified interval, except for Frequencies specified as 24

months*Not a variation to the TSTF

  • Applies to50TSSR
  • One exception -TSSR 3.8.1.8 amended in 2010 to allow the application of the 25% extension to its 24 month surveillance

requirement 5

6PINGP'sTSSR 3.0.2

  • PINGPTSSR 3.0.2 does not affect application of TSTF-425 nor does it affect implementation of the

SFCP-Site specific SR 3.0.2 is applied to the SFCPas described in TSTF-425

  • SFCPAdministrative Controls maintained (TS5.5.17)

-No affect on TSTF-425

  • Model License Amendment Request (LAR) unchanged
  • Model No Significant Hazards Consideration determination unchanged*NRC Model Safety Evaluation (SE) unchanged
  • Not considered a variation to the TSTF 6

7PRA Technical Adequacy

-RG1.200 peer reviewed with Appendix X to NEI05-04 finding closure review complete

  • Seismic-IPEEESeismic Margins Analysis (SMA)
  • Other External Hazards

-PINGPIPEEEconcluded other exter nal hazards to be negligible contributors to overall plant risk

  • Shutdown Events

-Shutdown risk management program consistent with NUMARC 91-06 7 8PRA Technical Adequacy

  • NFPA-805 LAR approved August 8, 2017
  • Fire PRA reflects future state of the as-built/as-operated plant following NFPA-805 modifications

-Unit 1 -Fall 2020 RFO, Unit 2 -Fall 2019 RFO

  • Fire PRA is RG1.200 peer reviewed with an Appendix X closure review*Fire PRA Open F&Osprovided in the Technical Adequacy Section of the SFCPLAR

-During transition, the SFCPevaluations use IPEEEFIVE results supplemented by sensitivities from Fire PRA in accordance with NEI04-10-Following implementation of NFPA-805, evaluations use the Fire PRA in accordance with NEI04-10 8

9PRA Technical Adequacy

  • Conclusion

-PINGPPRA models sufficiently robust and suitable for SFCP 9 10 Questions and Feedback 10?

11 Acronyms*CLB-Current Licensing Basis

  • F&O-Finding and Observations
  • FIVE -Fire Induced Vulnerability Evaluation
  • LAR -License Amendment Request
  • IPEEE-Individual Plant Examination of External Events
  • NEI-Nuclear Energy Institute
  • NSHC-No Significant Hazards Determination
  • PINGP-Prairie Island Nuclear Generating Plant
  • PRA -Probabilistic Risk Assessment
  • RFO-Refueling Outage
  • SE -Safety Evaluation 11 12 Acronyms*SFCP-Surveillance Frequency Control Program
  • SMA-Seismic Margins Analysis
  • TS-Technical Specification
  • TSSR -Technical Specification Surveillance Requirement
  • TSTF-Technical Specification Task Force
  • XE-Xcel Energy 12