ML12115A205
| ML12115A205 | |
| Person / Time | |
|---|---|
| Site: | 05000021 |
| Issue date: | 05/01/2012 |
| From: | Ngola Otto NRC/NRO/DNRL/LB2 |
| To: | Mitsubishi Heavy Industries, Ltd |
| Otto, Ngola NRO/DNRL/LB2, 415-6695 | |
| References | |
| Download: ML12115A205 (8) | |
Text
May 1, 2012 AUDIT PLAN FOR REVIEWING THE TURBINE DRIVEN EMERGENCY FEED WATER PUMP ROOM TRANSIENT HEAT-UP CALCULATIONS May 9, 2012 US-APWR DESIGN CERTIFICATION Mitsubishi Heavy Industries, Ltd.
Docket No.52-021 Location:
Mitsubishi Nuclear Energy Systems, Inc.
1001 19th Street North, 7th Floor Arlington, VA
Background:
On September 22, 2011, the Advisory Committee on Reactor Safeguards (ACRS) issued a letter (ML11256A206) based on its review the United States - Advanced Pressurized Water Reactor (US-APWR) Safety Evaluations for Chapters 2, 5, 8, 10, 11, 12, 13, and 16. In the letter related to Chapter 10, Steam and Power Conversion System, ACRS indicated that the staff should request that the applicant, Mitsubishi Heavy Industries, Ltd. (MHI) provide room heat-up analyses and documentation of the turbine control systems environmental qualifications that justify why the turbine driven emergency feedwater (TDEFW) pumps will continue to operate stably for at least one hour after loss of all room cooling. Subsequent to the letter, the staff issued Request for Additional Information (RAI) 875-6211 (ML113410187), dated December 5, 2011, under Standard Review Plan Section 8.4, requesting that MHI provide the heat-up calculations for the emergency feedwater (EFW) pump rooms for a station blackout (SBO) induced loss of ventilation event in which the turbine-driven EFW pumps begin to operate at the onset of the SBO and the EFW pump room cooling is not available during the first hour after the onset of the SBO. On January 27, 2012, MHI submitted its response dated January 27, 2012, to RAI 875-6211 (ML12031A243). Based on a review of the RAI response, the staff determined that an audit of the transient heat-up analysis of the TDEFW pump room was needed to validate the heat-up analysis provided in the response, and understand the underlying assumptions.
Regulatory Audit Bases:
General Design Criterion 17, Electric power systems.
Title 10 of the Code of Federal Regulations (10 CFR) 50.63, Loss of all alternating current power.
10 CFR 52.47(b)(1), ITAAC proposed for a DC Application.
Regulatory Audit Scope:
The audit team will review documents, drawings, analysis, specifications and other relevant design information associated with the US-APWR TDEFW pump room transient heat-up analysis. The main focus of the audit would be to validate the technical information and understand the assumptions inherent in the US-APWR TDEFW pump room transient heat-up analysis for the SBO-induced loss of ventilation event in which the TDEFW pumps begin to operate at the onset of the SBO and the TDEFW pump room cooling is just lost due to the SBO.
The staff would make sure that the analysis and the assumptions are conservative.
Information and Other Material Necessary for the Regulatory Audit The staff requires access to knowledgeable personnel regarding the US-APWR TDEFW pump room transient heat-up analysis for the SBO-induced loss of ventilation event; and the following information/documentation should be available to the audit team:
TDEFW pump room construction/drawings:
o Room layout and dimensions. Drawing will be needed.
o Wall, floor, and ceiling dimensions and thicknesses. Drawing may be needed.
o Density, thermal conductivity, and specific heat of the concrete, steel, etc. used in the construction of the wall, floor, and ceiling. For composite materials, any mean effective values used should be provided.
Heat loads and room temperature/moisture design limits:
o Total heat load and its equipment-wise break-up; information regarding any time dependence involved.
o Equipment Qualification limits for the safety-related equipment/instrumentation inside the TDEFW pump room.
o Information regarding any moisture accumulation related issue.
Major assumptions and justifications regarding:
o Any outdoor in-leakage rate.
o Indoor and outdoor temperature/humidity conditions assumed for the design basis analysis. Specify any diurnal temperature swings credited in the calculations.
o Thermal conditions and heat loads in the adjacent rooms on all sides, including below the floor and above the ceiling. How was the soil, if any, handled?
Drawing may be needed.
o Heat transfer coefficients used inside/outside the room.
o Air temperature stratification inside the room.
o The heating, ventilation and air conditioning (HVAC) system being out of service due to routine maintenance or a limiting condition of operation condition. This would allow the staff to understand the TDEFW pump rooms thermal response due to the SBO when its HVAC system has already been down and the room temperature and humidity have been creeping up.
o Initial TDEFW pump room air temperature.
o Any other significant initial and boundary conditions.
o Coping analysis with a SBO of the specified duration Simulations & Results:
o Transient room air temperature results over the SBO coping period.
o Simulation results from any sensitivity studies of the heat-up analyses conducted.
o Any built-in design margins to withstand and recover from the SBO.
o How were the calculations performed? Which software package was used? Any deck information, relevant calculations details, equations, etc.
Information regarding the related inspection, testing, analysis, and acceptance criteria.
Other documents, which the applicant deems as necessary to support the NRC staffs audit.
Team Assignments:
Syed Haider, Containment and Ventilation Branch, NRO (Audit Team Lead)
Ngola Otto, Project Manager, NRO Logistics:
The audit will be conducted at the Mitsubishi Nuclear Energy Systems, Inc. location identified earlier. The audit is scheduled to begin at 9:00 a.m. Participating individuals will meet at the audit location.
Special Requests Appropriate handling and protection of proprietary information shall be acknowledged and observed throughout the audit.
The NRC staff may request an ad-hoc extension of the audit if findings during the ongoing audit reveal the need for additional time. Such an extension will be requested before the audit is adjourned on May 9, 2012, by the NRC staff responsible for the audit.
Deliverables:
The audit team will issue a regulatory audit summary within 90 days after completing the audit.
The audit outcome will be used to identify any additional information to be submitted for making regulatory decisions. The audit will assist the NRC staff in the preparation and issuance of further RAIs for the licensing review of the US-APWR Design Certification Application.
References:
- 1.
10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants.
- 2.
NRC NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, (ADAMS Accession No. ML090580432).
- 3.
US-APWR Design Control Document, Revision 3.
Docket No.52-021 cc: See next page
- 3.
US-APWR Design Control Document, Revision 3.
Docket No.52-021 cc: See next page DISTRIBUTION:
PUBLIC RidsAcrsAcnwMailCenter RidsOpaMailCenter NMIP R/F RidsOgcMailCenter RidsNroLACSmith D081 RidsNroDnrlNmip NOtto, NRO JCiocco, NRO ADAMS Accession No.: ML12115A205 NRC-001 OFFICE DNRL/LB2 :PM DNRL/LB2 :LA DNRL/LB2: PM DNRL/LB2: BC DSRA/SCVB: BC NAME NOtto CMurphy JCiocco HHamzehee JMcKirgan DATE 05/1/12 04/30/12 05/1 /12 05/1 /12 05/1/12
DC Mitsubishi - US APWR Mailing List (Revised 03/15/2012) cc:
Ms. Michele Boyd Legislative Director Energy Program Public Citizens Critical Mass Energy and Environmental Program 215 Pennsylvania Avenue, SE Washington, DC 20003 Atsushi Kumaki Mitsubishi Heavy Industries, Ltd.
APWR Promoting Department Wadasaki-cho-1-1-1, Hyogo-ku Kobe 652-8585 JAPAN Dr. Masanori Onozuka Mitsubishi Nuclear Energy Systems, Inc.
1001 19th Street North, Suite 710 Arlington, VA 22201-5426 Dr. C. Keith Paulson Mitsubishi Nuclear Energy Systems, Inc.
300 Oxford Drive, Suite 301 Monroeville, PA 15146 Mr. Tony Robinson AREVA NP, Inc.
3315 Old Forest Road Lynchburg, VA 24501 Mr. Robert E. Sweeney IBEX ESI 4641 Montgomery Avenue Suite 350 Bethesda, MD 20814 Mr. Gary Wright, Director Division of Nuclear Facility Safety Illinois Emergency Management Agency 1035 Outer Park Drive Springfield, IL 62704 Page 1 of 3
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