ML20057E205
| ML20057E205 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 08/20/1993 |
| From: | Malloy M Office of Nuclear Reactor Regulation |
| To: | Marriott P GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9310080109 | |
| Download: ML20057E205 (8) | |
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UNITED STATES
.[.'",j, NUCLEAR REGULATORY COMMISSION 8
WASHINGTON, D.C. 20555 0001 o%.N <.. /
August 20, 1993
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Docket No.52-004 Mr. Patrick W. Marriott, Manager Licensing & Consulting Services GE Nuclear Energy 175 Curtner Avenue San Jose, California 95125
Dear Mr. Marriott:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE SIMPLIFIED BOILING' WATER REACTOR (SBWR) DESIGN The staff has determined that it needs additional information to support its independent assessment program activities related to the SBWR design certifi-cation review. Some additional information is needed on the SBWR plant, the GIRAFFE testing program, and the PANTHERS facility (Q950.1-Q950.26).
Please respond to the enclosed questions within 60 days of the date of this letter.
You have previously requested that portions of the information submitted in the August 1992, application for design certification of the SD R plant, as supplemented in February 1993, be exempt from mandatory public disclosure.
The staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.DO, therefore, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that this RAI does not contain those
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portions of the information for which you are seeking exemption. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow GE Nuclear Energy the opportunity to verify the staff's conclusions.
If, after that time, you do not request that all or portions of the information in the enclosure be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the NRC's Public Document Room.
This request for additional information affects nine or fewer respondents, and therefore, is not subject to review by the Office of Management and Budget under P.L.96-511.
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- The numbers in parentheses designate the tracking numbers assigned to the go 3 questions.
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t Mr. Patrick W. Marriott August 20, 1993 If you have any questions regarding this matter, please contact me at (301) 504-1178 or Mr. Son Ninh at (301) 925-1125.
Sincerely, Ong!nelS.'gne g.y Melinda Malloy, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation l
Enclosure:
l RAI on the SBWR Design cc w/ enclosure:
See next page Distribution (w/ enclosure):
- Central ' File PDST R/F MMalloy PShea l
- PDR SNinh DMcPherson, 8E2 RElliott, 8H2 Alevin, 8E21 TLee, NLN353.
Y-Schen, NLN344 MFinkelstein, 15B18 AGody, Jr.,17G21 Djstribution (w/o enclosure):
DCrutchfield/WTravers RBorchardt JNWilson TMurley/FMiraglia,12G18 WRussell,12G18 ACRS (11)
AThadani/MVirgilio, BE2 RJones, 8E21 RBarrett, 8H2 BSheron/TKing, NLS007 LShotkin, NLN353 FEltawila, NLN344 JMoore, 15B18 GSuh (2), 12E4 l
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- To be held for 30 days A
l OFC LA:PDST PN:PDST PM:PDST SCSB [
SC:P,6$TI NAME PShea G t b' IIY1Iy:'tz S$4M RB[rkt/
JNdt[ son t
DATE 08/Nd3 08Ah/93 08//d /93 08h/93 08/9 93
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l DOCUMENT NAME: SBWR9315.MM l
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Mr. Patrich W. Marriott Docket No.52-004
't General Electric Company i
1 cc:
Mr. Laurence S. Gifford GE. Nuclear Energy 4
12300 Twinbrook Parkway Suite 315 Rockville, Maryland 20852 Director, Criteria & Standards Division Office of Radiation Programs U.S. Environmental Protection Agency 401 M Street, S.W.
^
Washington, D.C.
20460 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington; D.C.
20585 Mr. Jeffrey C. Baechler GE Nuclear Energy i
175 Curtner Avenue, MC-782 San Jose, California 95125 Mr. Frank A. Ross Program Manager, ALWR Office of LWR Safety & Technology i
U.S. Department of Energy NE-42 i
19901 Germantown Road i
Germantown, Maryland 20874 a
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._..,s.
REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE SIMPLIFIED BOILING WATER REACTOR (SBWR) DESIGN SBWR Plant Additional information is needed in the following areas to assist in building the RELAPS input deck:
950.1 What are the system set points that activate (all) the squib valves?
950.2 What is the delay time associated with activation of the squib valves?
950.3 What are the pressure losses and the area associated with the squib valves?
950.4 Provide the decay heat curves associated with SBWR fuel at several state points in the fuel cycle, if different from the standard ANS
- curves, 950.5 For the TRACG input deck that was used in the Chapter 15 analysis of the SBWR standard safety analysis report (SSAR), provide a noding diagram, input deck of TRACG, and an input description to decipher the information.
950.6 Provide the point kinetics parameters for the equilibrium fuel cycle of the SBWR at several state points.
950.7 What is the flow area for the fully opened check valve in the condensate return line of the isolation condenser? What are the flow characteristics of this check valve, i.e., pressure losses, area function of gate, and activation set points?
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950.8 Provide a drawing showing the total pipe length and elevation difference between the isolation condenser exit and entrance to the reactor pressure vessel for the condensate return line and the noncondensable vent line.
950.9 What is the density (in kg/m3) of the sodium pentaborate solution inside the accumulator of the standby liquid control system?
950.10 Provide the exact radial and axial locations of the injection ports of boron from the spargers into the core.
950.11 What is the design pressure for the condensate return to the reactor pressure vessel?
950.12 Provide activation criteria of the vent for noncondensable gas removal from the system isolation condenser to the suppression pool.
Enclosurc
RAI ON THE SEWR DESIGN 950.13 Provide the flow-dependent loss coefficients for single-phase flow entrance to the core, two-phase flow across the fuel bundle spacers, and two-phase flow exit losses from the core and riser.
950.14 Provide the following data on the feedwater pump:
a.
pump head and torque characteristic curves b.
feedwater pump head and condensate booster pump head c.
moment of inertia of both pumps d.
feedwater pump speed at rated conditions e.
controllers connected to the electric pumps and their effect on i
the pump 950.15 Describe the feedwater runback feature of the SBWR, i.e., the related controllers and flow conditions.
950.16 Provide plots of the TRACG predictions for the steam and condensate flow rate from the isolation condensers during the main steam
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isolation valve closure anticipated transient without scram with fine motion control rod drive (reference SBWR SSAR Figures 15.8-2 and 15.8-3.
GIRAFFE TESTING PROGRAM The document, " GIRAFFE Passive Heat Removal Testing Program," NEDC-322215P Rev. 0 (June 1993) contains a large amount of information essential for constructing a RELAP5 model for analyzing the GIRAFFE tests, however, the following additional information is needed:
950.17 Provide a complete piping diagram with valve locations, pipe inner and outer diameters, and flow orifice locations and flow orifice loss coefficients, along with a detailed description of the reactor pressure vessel.
[For example, Figure 2.3-7 details the main loss-of-coolant accident (LOCA) and passive containment cooling gas vent lines.
There should be information on the dimensions of the LOCA vent line and the location of the 3 holes in the vent line.]
950.18 Provide more complete instrumentation documentation and description.
(For example, while Figure 2.3-4 shows the approximate locations of the passive containment cooling unit thermocouple and pressure transducers, the exact locations are needed to properly position the nodes in the RELAP5 simulations.) -
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RAI ON THE SBWR DESIGN i
i 950.19 Provide a clearer description of the Phase 1 tests.
(The actual l
paths and the hardware used is not precise. A more comprehensible i
l test matrix description and piping diagrams would alleviate confu-l sion. The use of the drywell in Phase 1, Test 1 is unclear.)
l 950.20 The presentation of the data in the report needs clarification.
(The graphs often had several thermocouple temperatures plotted against time on a single set of axes.
Fcr example, the test results l
shown in Figures 5.1-3 and 5.5-3 are not distinguishable. The data should be replotted with better resolution of the data and legends
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connecting curves with appropriate sensors.)
950.21 To facilit V 4 the comparison between the GIRAFFE test data the l
RELAPS pridb (dons, provide a digital tape of the GIRAFFE data so l
that the osia.an be plotted one-to-one against the RELAPS l
predictions.
950.22 Provide a description of the May-Witt decay heat curves.
l PANTHERS Facility 950.23 Provide the test plan and the final hardware configuration for the PANTHERS facility.
950.24 Provide a description of PANTHERS that contains information to facilitate review of the test plan and to develop a RELAP5 input deck, including:
a.
geometrical design data b.
valve characteristic data c.
instrumentation and calibration data d.
control system data e.
test documentation 950.25 To facilitate the transfer of information on the PANTHERS facility, provide the TRACG input deck, noding diagram, and input description.
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RAI ON THE SBWR DESIGN 950.26 Provide the following documents:*
a.
Isolation Condenser System Piping and Instrumentation Diagram, Drawing No. 107E5154.
b.
Isolation Condenser System Design Specification, Document No.
25A5013.
c.
Isolation Condenser System Interlock Block Diagram, Drawing No.
137C9292.
d.
Isolation Condenser System Process Flow Diagram, Drawing No.
107E6073.
e.
Passive Containment Cooling System Piping and Instrumentation Diagram, Drawing No. 107E5160.
f.
Passive Containment Cooling System Design Specification, Docu-ment No. 25A5020.
g.
Passive Containment Cooling System Process Flow Diagram, Drawing No. 107E6072.
h.
SBWR Composite Design Specification, Document No. 23A6723.
- i. Containment Configuration Data Book, Document No. 25A5044.
J.
IC H.X. Equipment Requirements Specification, Document No. SBW 5280 TNIXN014000, k.
PCC Equipment Requirements Specification, Document No. SBW 5280 TNIXN015000.
(continued on the next page) e Documents listed in this question were referenced in the following:
" Confirmatory Tests of Full-Sce's Condensors for the SBWR isolation Condenser System and the Passive e.
Containment Cooling System." S. Botti, G. Fitzsimmons, and P. Masoni, undated.
b.
- PANTHERS Test Program,* Presentation to the ACRS by P. F. Bilhg, June 2,1992.
c.
- isolation Condenser & Passive Containment Condenser Test Requirements,' GE MPL ltem FB32 3030/T15-3030. November 12.1992.
d.
- PCC Test Plan & Procedure," SIET 0o096 ED 91 Rev. A, undsted.
e.
"Technico! Specificet;on for PCC Instrumentation installation,* SIET 001S7ST92 Rev. A, undated. -
RAI ON THE SBWR DESIGN l
950.26, continued 1.
Passive Containment Cooling and Isolation Condenser Prototype Structural Instrumentation, Document No. SBW 5280-TNIX-1115000.
m.
IC Pool Compartment Arrangement, Drawing No. SBW5280DMNX1103.
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