ML092440164
| ML092440164 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/14/2009 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | |
| Singal, Balwant, 415-3016, NRR/DORL/LPL4 | |
| References | |
| TAC ME1739, TAC ME1740 | |
| Download: ML092440164 (27) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 14, 2009 LICENSEE:
Luminant Generation Company LLC FACILITY:
Comanche Peak Steam Electric Station, Units 1 and 2
SUBJECT:
SUMMARY
OF AUGUST 25,2009, CATEGORY 1 MEETING WITH LUIVIINANT GENERATION COMPANY LLC - PRE-APPLICATION MEETING TO DISCUSS FUTURE REQUEST FOR ONE-TIME LICENSE AMENDMENT TO TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES-OPERATING" (TAC NOS. ME1739 AND ME1740)
On August 25, 2009, a public meeting was held between the U.S. Nuclear Regulatory Commission (NRC), and representatives of Luminant Generation Company LLC (Luminant, the licensee), at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, MD.
Luminant intends to submit in the future a request for a one-time license amendment request to revise Technical Specification 3.8.1, "AC Sources - Operating" for Comanche Peak Steam Electric Station, Units 1 and 2. The change is needed in order to facilitate the installation of a planned plant modification, which would provide the capability to connect a spare offsite source transformer to the onsite Class 1E busses within the existing limiting condition for operation required completion time.
The purpose of the meeting was to provide NRC staff with an overview of the proposed modification and receive an early NRC staff feedback.
A list of meeting attendees is provided in Enclosure A.
Results of Discussion The licensee provided an overview of the proposed modification during the meeting, including the insight into the risk assessment for the proposed one-time amendment request. The proposed one-time amendment request will extend the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time to 14 days for Required Action A.3 for TS 3.8.1 to facilitate a modification that will improve the reliability and availability of 345 KV offsite source. A copy of the slides for the presentation is provided as Enclosure B.
The NRC staff suggested that the licensee should include the following additional information in the formal submittal:
- The proposed one-time amendment request should describe how the proposed modification complies with the of General Design Criteria 17
- The proposed amendment request should include a detailed timeline for implementing the proposed modification.
- 2 No member of the public was present during the meeting. Also, no Public Meeting Feedback Forms were received for this meeting.
Please direct any inquiries to me at (301) 415-3016, or Balwant.Singal@nrc.gov.
Sincerely,
~l w e-.+ LZ, "'-'c::--.2 Balwant K. Singal, Senior Proje'lt-Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
A. List of Attendees B. Copy of the Presentation Slides cc w/encl: Distribution via Listserv
ENCLOSURE A LIST OF MEETING ATTENDEES AUGUST 25. 2009, PUBLIC MEETING WITH LUMINANT GENERATION COMPANY LLC
LIST OF ATTENDEES FOR AUGUST 25, 2009 PUBLIC MEETING WITH LUMINANT GENERATION COMPANY LLC NAME ORGANIZATION Balwant K. SinQal NRR/DORLlLPL4 Sheila Ray NRR/DE/EEEB G. Singh Matharu NRR/DE/EEEB Ken Miller NRR/DE/EEEB Michael Markley NRR/DORLlLPL4 Gerry Waig (by Phone)
NRR/DIRS/ITSB Donnie Harrison NRR/DRAIAPLA Margaret Stambaugh NRRIDRAIAPLA Tim Hope Luminant, ManaQer Nuclear Licensing Daniel Tirson Luminant Thomas Brown Luminant Robert SlouQh Luminant Ijaz Ahmed Luminant Steven D. Karpyak Luminant Tamera Ervin-Walker Luminant Rod S. Sorrecc Luminant
ENCLOSURE B COpy OF THE PRESENTATION BY LUMINANT GENERATION COMPANY LLC
Proposed License Amendment Request Allowance Of A One-Time, 14-Day TS Completion Time Extension For Required Action A.3 From 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> t014 Days To Facilitate A Modification That Will Improve The Reliability/Availability of 345KV Offsite Source
Luminant Pre-Application Meeting Agenda Tim Hope, Manager, Nuclear Licensing
Introductions
Rod Sorrell, System Engr.
Current Plant Design Tom Brown, Mod. Engineering Mgr.
Plant Modification Overview Tamera Ervin-Walker, Licensing Engr.
TS 3.8.1 and Extended CT Dan Tirsun, Risk Assessment &
Risk Assessment Application NRC Staff Questions/Feedback Tim Hope, Mgr., Nuclear Licensing Closing remarks/summary
I Park,r Venu~
I Comanche Switch I I
Wolf Hollqw
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CPNPP Offsite AC Power Sources
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Plant Modification Overview XST2 XST2A I
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r IF Alternate offsite Preferred offsite source - Unit 2 source - Unit 1
Technical Specification 3.8.1 CONDITION REOUIRED ACTION COMPLETION TIME A. Olle required offsite eircuit inoperable.
I A.l P&rfOffil SR 3.8.'.1 fa required OPERABLE ofuite circuit.
.A,ND
NC>TE-----------
In MODES 1.2 ard 3. :he IDAFW pu mp i;: oone.idered s required redLndafit fearure.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 8 rOLrs thereafter 4.2 l\\ND A.3 Declare requirad tedture{s} \\\\lith no offsite FKlwer av~i lable inoperable when its redl.mdant required feature{s; is inoperabie.
Rf!:!'IOrf! rAqui rAd ()ff~itR ciruu t to OrEI1ABLE status 24 hcurs rr-orn disco.... e-y::>f no affsite power to one train concurrent v~ith inoper~bility uf ree undant req uired fealure{s)
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Technical Specification 3.8.1 CONDITION A.. One required offsite circuit inoperatle.
REOUIRED ACTION I "\\.)
P9rfOffi'l SR 3.8.'.1 fCf" required OPERABLE offsite ci rcuit
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In MODES 1.2 ard 3, :he TDAFW pump is considered s required redLndant feature.
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,A,ND A.3 Declare requi f"'!ld feature(sj \\~th no offsite p<:Jwef dv~ilable inoperabl~ wh~n its redundant required feature{s; IS inoperable.
Rf;slor~ rP.oflui md offsitA cimu t to orEHABLE statI I!'>
COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ANQ Once~r B t"oLrs thereafter 24 hcurs from disco....e-y ::>f no affSlte power to one train concurrent \\....ith inQper~bility :Jf r~cundant required feature{s)
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- For XST2 only, the Completion Time for Required Action A.3 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" up to 14 days for a one-time outage to complete terminations as part of the plant modification to facilitate connection of either XST2 or XST2A to the 1E buses, to be completed by March 1, 2011.
Risk Analysis
- Objectives for this section
- Summarize PRA Model Scope and Quality
- Describe the Risk Assessment
- Discuss the Sensitivity Analyses
- Discuss the Configuration Risk Management Program and Risk Reduction Measures
- Summarize the Results
- Overall Conclusions I Risk Insights
PRA Model Scope and Quality
- High Confidence that the PRA Model Scope and Quality are adequate to address the risk aspects of the LAR WOG peer review, focused self assessments, focused peer reviews and MSPI review with no outstanding findings and observations of significance.
Self assessment of CPNPP PRA model to RG 1.200 including NRC memorandum - clarifications to revision 1.
- Model generally meets at least Capability Category II for most of the supporting elements.
- Most of these Gaps could be eliminated by more detailed documentation or programmatic guidance.
- Gaps in modeling detail or capability were generally confined to the Internal Flooding and Large Early Release Frequency elements. The modeling gaps are generally due to the age and associated conservatism of the model, or that some elements of the Standard were beyond the scope of the original analysis.
Evaluation of gaps identified in the RG 1.200 self assessment shows there none that adversely impact this LAR.
PRA Model Scope and Quality
- Adequately addresses as-built, as-operated plant
- Plant specific data and plant specific best estimate T-H to address success criteria
- Loss of Offsite Power modeling is robust
- Electric power systems modeling is robust
- Convolution method used for LOOP recovery analyses
Description of Risk Assessment
- Applicable Guidance and Criteria
- Quantitative Analyses for Internal Events and Flood, Level 1 and 2
- Quantitative and Qualitative Analyses /
Evaluations for External Events
- Fire and Tornado PRA
- based on IPEEE methods
- LAR impacts evaluated using current model
- Seismic margins
- Supported by detailed walk-down of plant
Discussion of Sensitivity Analyses
- Sensitivity studies are used to address uncertainties. These studies include:
Reliability of components important to the risk contributions of the CT extension LOOP recovery values Recovery of important components LOOP Weather and Plant Centered frequencies Tornado F1 and F2 non-recovery probability Deferred maintenance
- Results of these studies show that there are no uncertainties that significantly affect the conclusions of this risk evaluation.
Configuration Risk Management Program
- CPNPP has a Configuration Risk Management Program Incorporates the characteristics of the model Configuration Risk Management Program described in RG 1.177 CRMP description has been incorporated into plant Technical Specifications - 5.5.18 Previously approved for risk informed Technical Specifications change for Centrifugal Charging Pumps - B 3.5.2 Required Action A.1
- CRMP is a requirement of the Maintenance Rule Program. CPNPP endorses the guidance in NUMARC 93-01, "Industry Guideline For Monitoring the Effectiveness Of Maintenance At Nuclear Power Plants."
Configuration Risk Management Program - Risk Mitigation Actions
[Implemented during the extended CT]
- 1.
Restricted Access to and Suspension of Maintenance in the Switchyard.
- 2.
Testing of Diesel Generators and Turbine Driven Auxiliary Feedwater Pumps within Two (2) Weeks Prior to the Start of the XST2 14 CT.
- 3.
Rescheduling of Testing and Maintenance on the DGs, TDAFWPs, XST1, and SSWPs to occur out side the extended CT window.
- 4.
Temporary Diesel Generators Sets Will Be Onsite For Each Unit for Defense-In-Depth For Shutdown Cooling.
- 5.
Suspension of Hot Work Activities Near XST1 Power and Control Cabling.
- 6.
Roving Hourly Fire Watch Along Paths of XST1 Power and Control Cabling.
- 7.
Selection of Time of Year Due to Weather Considerations..
- 8.
Seismic Walkdown for the DGs and TDAFWPs.
- 9.
Operations preparations and grid monitoring during the CT.
Summary of Results
- The resulting cumulative risk metrics in the following table show the addition of the risk metrics from each of the event analyses and how they meet the acceptance guidelines.
As seen in Table 1, for Unit 2 the fire ICCDP is slightly above 5E-07. Also, the cumulative 6CDF and ICCDP are slightly above 1E-06/yr and 5E-07, respectively.
To address this specific issue, risk reduction measures were identified for each of the fire events.
Given these risk reduction measures, Unit 2 fire events and cumulative 6CDF and ICCDP would fall below the guideline values if they were quantitatively addressed.
Table 1: Comparison of Risk Assessment Total Results to Acceptance Guidelines Below Acceptance Acceptance Unit OutDut Pa ra meters Value Freauencv Guideline Guideline Internal Events CDF NEWxST2 1.02E-05 Per Year
< 1.00E-04/yr Yes Unit 1 oClCDF xsT2 2.75E-07 Per Year
< 1.00E-06/yr Yes ICCDPxsT2 2.75E-07 Dim ens ion less
< 5.00E-07/yr Yes CDF NEWxST2 9.93E-06 Per Year
< 1.00E-04/yr Yes Unit 2 oClCDFxsT2 254E-07 Per Year
< 1.00E-06/yr Yes ICCDPxST2 2.54E-07 Dim ens ion less
< 5.00E-07/yr Yes Fire Events Fire CDF New 2.11 E-05 Per Year
< 1.0E-04/yr Yes Unit 1 Fire oClCDF 2.17E-07 Per Year
< 1.00E-06/V r Yes Fire ICCDP 2.17E-07 Dim ens ion less
< 5.00E-07/vr Yes Fire CDF New 2.17E-05 Per Year
<100 E-04/yr Yes Unit 2 Fire oClCDF 7.BBE-07 Per Year
< 1.00E-06/vr Yes Fire ICCDP 7.BBE-07 Dim ens ion less
< 5.00E-07/vr No Flood EventslUnits1 and2l Both Flood CDF 6.91 E-OB Hiqh Wind ITornado Events (Units 1 and ii' Per Year
< 1.0E-04/vr Yes Both High Wind I Torn CDF 3.70E-06 Per Year
< 1.0E-04/yr Yes Seismic Events IUnits 1 and 2l Both Seismic CDF 7.61 E-09 Per Year
< 1.0E-04/vr Yes Total Values IInternal Events and Fire Eventsl CD FN8IIJ Total 1.40E-05 Per Year
< 1.00E-04/y r Yes Unit 1 oCl CD FTotal 4.92E-07 Per Year
< 1.00E-06/y r Yes ICCDPTotal 4.92E-07 Dim ens ion less
< 5.00E-07/yr Yes CD FN8IIJ Total 2.49E-05 Per Year
< 1.00E-04/yr Yes Unit 2 oClCDFTotal 104E-06 Per Year
< 1.00E-06/yr No ICCDPTotal 104E-06 Dim ens ion less
< 500E-07/yr No
Overall Conclusions of Risk Assessment
- Based upon the comprehensive risk assessment, the one time extension of the XST2 CT from 3 to 14 days will have minimal impact on plant risk.
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ML092440164 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlEEEB/BC NRRlLPL4/BC NRRlLPL4/PM NAME BSingal JBurkhardt GWilson MMarkley BSingal DATE 9/8/09 9/4/09 9/9/09 9/14/09 9/14/09