ML13070A213

3/5/13 Summary of Preapplication Meeting Via Conference Call with STP Nuclear Operating Company to Discuss License Amendment Request for Fire Protection Program to Credit Additional Operator Actions for South Texas, Units 1 and 2 (TAC MF057

ML13070A213
Person / Time
Site:	South Texas
Issue date:	03/29/2013
From:	Singal B K Plant Licensing Branch IV
To:	Office of Nuclear Reactor Regulation
Singal B K
References
TAC MF0578, TAC MF0579
Download: ML13070A213 (7)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 March 29, 2013 STP Nuclear Operating Company South Texas Project, Units 1 and 2 SUMMARY OF MARCH 5, 2013, PRE-LICENSING CONFERENCE CALL PUBLIC MEETING WITH STP NUCLEAR OPERATING COMPANY TO DISCUSS THE PROPOSED LICENSE AMENDMENT REQUEST FOR APPROVAL OF THE REVISED FIRE PROTECTION PROGRAM RELATED TO THE ALTERNATE SHUTDOWN CAPABILITY DOCUMENTED IN THE FIRE HAZARDS ANALYSIS (TAC NOS, MF0578 AND MF0579) On March 5,2013, a conference call public meeting was held between the U,S, Nuclear Regulatory Commission (NRC), and representatives of STP Nuclear Operating Company (STPNOC, the licensee) at NRC Headquarters, Rockville, Maryland. The meeting notice and agenda, dated February 22, 2013, is located in the Agencywide Documents Access and Management System (ADAMS) at Accession No, ML 13046A065. The purpose of the meeting was to discuss the proposed license amendment request (LAR) for approval of the revised fire protection program related to the alternate shutdown capability documented in the fire hazards analYSis for South Texas Project (STP), Units 1 and 2. A list of meeting attendees is provided as an Enclosure 1 to this meeting summary, Discussion Topics The discussion included an overview of the proposed LAR for STP, Units 1 and 2, as follows: Purpose Proposed licensing Action and Operator Actions Impacted Regulatory Requirements Impact of the Proposed Request on Operating licenses for STP, Units 1 and 2 Technical and Analytical Basis for the Proposed Licensing Action Summary of the Results for limiting Case Analysis Performed in Support of the Proposed Action, including Fire Modeling of the Main Control Room Submittal Schedule Summary and Conclusions A copy of the meeting materials/handouts dated February 20, 2013, is located at ADAMS Accession No. ML 13051A855. The licensee provided an additional slide for Control Room Control Panel Switcb Orientation on the day of the meeting. A copy of this slide is provided in Enclosure 2,

-Results of Discussions The licensee clarified that the proposed application will be based on a deterministic approach. The licensee made a reference to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.48(e) on slide 8 of the presentation. The NRC staff stated that 10 CFR 50.48(e) has been deleted and should not be referenced as a regulatory requirement in the proposed submittal. On slide 15, the licensee stated "Operator will be pre-alerted because actions are not initiated until a fire occurs and the decision is made to trip the reactor. II The NRC staff was concerned that if the fire causes a plant trip, there may not be sufficient time to alert the operators for performing the operator actions from the control room. The licensee stated that there are detection systems installed that will pre-alert the operator about the control room fire. The licensee stated that these systems will be discussed in the proposed submittal. On slide 17, titled, "Design features," the licensee mentioned robust safety train circuit separation. The NRC staff requested the licensee to provide more details about routing of the cables in the proposed submittal to ensure safety train separation. The NRC staff questioned if loss-of-offsite power event was considered in conjunction with the most limiting fire scenario. The licensee stated that based on its analysis, the worst-case scenario is offsite power available in conjunction with the most limiting fire scenario. The licensee agreed to clearly discuss it in its proposed submittal. The NRC staff suggested that the licensee should address the adequacy of use of RETRAN-3D (computer code used to perform transient thermal-hydraulic analysis of light water reactors) to show that the natural circulation (based on single and two-phase flow) and reflux boiling can be maintained following a loss-of-offsite power event. It should include a discussion of the data used for the RETRAN model comparison, the treatment of the measurement uncertainties of the data associated with the initial conditions and instrumentation data, and the results of the RETRAN code bench marked with the applicable test data related to the two-phase flow natural circulation cooldown and reflux boiling phenomenon. As an example, comparisons could be made to NRC approved methodology that relies on RETRAN and any differences could be identified and discussed. On slide 22, the licensee discussed the scenario when no credit is taken for any of the proposed operator actions. The licensee stated that the most limiting case will be a stuck open pressurizer power-operated relief valve (PORV). The licensee made an assumption that the operator can terminate the event by securing the pressurizer PORV in 10 minutes from the alternate control station. The licensee was requested to explain the scenario in detail, including the circuit protection scheme in the proposed submittal. The licensee was also requested to confirm if the PORV would pass liquid water during the postulated event.

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• For the scenario when no credit is taken for the proposed operator actions, the licensee confirmed that no credit has been taken for any additional operator action from the control room. It was suggested that the licensee state it clearly in the proposed submittal.

• On slide 35, the licensee stated that it intends to use Consolidated Fire Growth and Smoke Transport Model (CFAST) for modeling the control room fire. The NRC staff suggested that the proposed submittal should include verification and validation for the use of CFAST model and was advised to refer to NUREG-1824, Volume 5, "Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications," (ADAMS Accession No. ML071730527) for details.

• The NRC staff was concerned that licensee has not discussed the impact of hot shorts inside the control room as a result of the fire in the control room (Reference: Information Notice 92-18, "Potential for Loss of Remote Shutdown Capability During a Control Room Fire," February 28, 1992 (ADAMS Accession No. ML031200481) and requested the licensee to address the impact of hot shorts in the proposed submittal.

-4 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, D __v--T1t:.2J, v0 Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 Enclosures: 1. List of Attendees 2. Copy of Additional Slide cc w/encl: Distribution via Listserv LIST OF MARCH 5, 2013, CONFERENCE CALL PUBLIC WITH STP NUCLEAR OPERATING REGARDING PROPOSED LICENSE AMENDMENT FOR APPROVAL OF REVISED FIRE PROTECTION PROGRAM TO THE ALTERNATE SHUTDOWN SOUTH TEXAS PROJECT, UNITS 1 AND DOCKET NOS. 50-498 AND NAME Ken T applett* Roland Dunn* Frank Cox* Charles Albury* Michael Murray* Donald Rohan* Mike Berg* *Richard Kersey* Jason Trbovich* Mark Coughlin*

• Coley Chappel* Duane Gore* Balwant K. Singal Harry Barrett Daniel Frumkin Carmen Franklin Ben Parks* *Undine Shoop* Summer B. Sun TITLE ORGANIZATION Licensing Engineer !STP Nuclear Operating Company (STPNOC) Manager, Nuclear Fuel and Analysis STPNOC Safe Shutdown Supervising 'STPNOC . Engineer Thermal Hydraulic Analysis STPNOC Supervisor Manager, Regulatory Affairs STPNOC Operations Procedures STPNOC -STPNOC -STPNOC -STPNOC -STPNOC -STPNOC -STPNOC Senior Project Manager U.S. Nuclear Regulatory Commission (NRC) Senior Fire Protection Engineer NRC Team Leader, Fire Protection NRC Branch Human Factor Engineer NRC Reactor Systems Engineer NRC Chief, Health Physics and Human ,NRC Performance Branch I Senior Reactor Engineer NRC I i I i I I I I

• Participated via phone Enclosure 1 Control Room Control Switch ZCP_ ZCP_ ZCP.... E! §I EI §ICONTROL ROOM U;Gl:1C) 1. REJOCTtIR TRIP 5111 TCW 2. MAIN STUM ISOLATION SWITCW 3. _SQlRIZfiR P()RV a.OCK Y.liLVE S1fITO*$ (TWOI ". RCP TRIP S1fITO*$ (FOUR. 5. FUOWATER ISOLATION S1fITCW (FOUR' O. STMTUP FEEOWATER _ PU.L-TCH.OCK S1fITCW 7. LET_ ISOLATION SIIITCHES (TWO) I!. CHMGIMC _ PU.L-TO-LOCK SWITCHES (TWO' .IiLL S1fITCWES _ ON fElICHBOMO PART OF PANEL I!X(%PT S1fITCW[S 3

• 7 WHICH _ ON YVlTlCiIL SECT ION OF PANEL. SOUTH TEXAS PROJECT ccoo__ccoo___UNITS 1.. 2 _ ,TCH OIlIOtTAT ION REvISION

• Back Up Slide 1 -South Texas Project Enclosure 2

-No Public Meeting Feedback Forms were received for this Please direct any inquiries to me at (301) 415-3016, or Docket Nos. 50-498 and 50-499 Enclosures: 1. List of Attendees 2. Copy of Additional Slide cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV rtf RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrDraAfpb Resource RidsNrrDraAhpb Resource RidsNrrDssSrxb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMSouthTexas Resource Sincerely, IRAJ Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor licensing Office of Nuclear Reactor Regulation RidsOgcRp Resource RidsRgn4MailCenter Resource TWertz, NRR JCassidy, EDO RIV HBarrett, NRR/DRAJAFPB DFrumkin, NRRIDRAJAFPB CFranklin, NRRlDRAJAHPB BParks, NRRlDSS/SRXB SAlferink, RIV N f SummalY ML 13070A213 ADAMS A ccesslon N0.: Mee mg f o Ice ML13046A065, M f INRR/LPL4/LA . NRR/DRAJAHPB/BC NRR/DSS/SRXB/BCNRR/LPL4/PMOFFICE JBurkhardt UShoop CJackson IBSingalI NAME !DATE ! 3/15/13 3/13/13 3/20/13 3/26/13 I NRR/LPL4/BC NRR/LPL4/PMNRR/DRAJAFPB/BCOFFICE MMarkley (JPolickoski BSingalAKlein ! for)NAME 3/29/13DATE 3/19/13 ! 3/29/13 OFFICIAL RECORD