ML20059F896

Requests for Addl Info to Support Review Activities Re Sbwr Design Certification

ML20059F896
Person / Time
Site:	05200004
Issue date:	09/28/1993
From:	Malloy M Office of Nuclear Reactor Regulation
To:	Marriott P GENERAL ELECTRIC CO.
References
NUDOCS 9311050148
Download: ML20059F896 (6)

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001

• September 28, 1993

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Docket No.52-004 .

4 Mr. Patrick W. Harriott, Manager 't Licensing.& Consulting Services GE Nuclear Energy 1 175 Curtner Avenue 1 San Jose, California 95125 *

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 review activities related to the SBWR design certification. .A portion of the '

staff review has focused on the SBWR test program as it' pertains to ensuring.

the structural integrity of the units under normal, design basis accident, and severe accident conditions for the 60-year life of the plant. Some additional ,

information on the isolation condenser (Q900.48-Q900.54) and passive contain- 1 ment cooling condenser (Q900.55-Q900.61) systems as described in GE Nuclear Energy's (GE's) test specification 23A6999, " Isolation Condense  :

Containment Condenser Test Requirements," Revision 1 is needed.r Please& Passive- 1 provide a written response to the enclosed questions within 60 days of the ;

date of this letter.

You have previously requested that portions of the information' submitted in- a the August 1992, application for design certification of the SBWR plant, as .

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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 2.790; 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 1 portions of the information for which you are seeking exemption. However, the staff _ will withhold this letter from public disclosure for 30 calendar days i from the date of this letter to allow GE,the opportunity to verify-the staff's conclusions. If, after that time, you' do not request that all or. portions of- l 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- -

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• The numbers in parentheses designate the tracking numbers assigned toithe i questions. :l 010022 , 1 i

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'Mr. Patrick W. Marriott September 28, 1993 This RAI affects nine or fewer respondents, and therefore, is not subject to

. review by the Office of Management and Budget under P.L.96-511.

If you have 'any questions regarding this matter, please contact me at (301) 504-1178.

Sincerely, (Original signed by)

Melinda Malloy, Project. Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation.

Enclosure:

RAI on the SBWR Design cc w/ enclosure:

See next page Distribution (w/ enclosure):

• PDR -*Central File PDST R/F MMalloy SNinh DMcPherson, 8E2 RElliott, 8H2 Alevin, 8E21- RCaruso,_8E1 TLee, NLN353 JHan, NLN353 YChen, NLN353 CTinkler, NLN344 ANotafrancesco, NLN344 : ' MFinkel stein, - 15B18 ,

ATGody, Jr., 17G21 JKudrick, 807 - MSnodderly, BH7 JMonninger, 801 Shou, 7H15 SAliSyed, 7H15--

Slee, 7H15 NMarkisohn FHasselberg DTerao, 7H15 Distribution (w/o enclosure):

DCrutchfield/WTravers RBorchardt JNWilson . .

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PShea TMurley/FMiraglia,12G18 WRussell,12G18 AThadani/MVirgilio, 8E2 RBarrett, 8H2 RJones,_BE21 s BSheron/TKing, NLS007 FEltawila, NLN344 -JMoore, 15B18-ACRS (11) GBagchi, 7H15 LShotkin, NLN353

• To be held _for 30 days 0FC LA:PDST b PM:PDST P,M:PDST _ PM: PDST hC:hdS[-

NAME PShea Y $$M k hil:tz'# Malioy SNMh'- JNWilson DATE '09h3' 09d/93 09/M93 09[/93 09M/93 DOCUMENT NAME: SBWR9321.NM

Hr. Patrick W. Harriott Docket No.52-004 General Electric Company cc: Mr. Laurence S. Gifford GE Nuclear Energy 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. John E. Leatherman SBWR Licensing Manager GE Nuclear Energy 175 Curtner Avenue, M/C 781 San Jose, California 95125 Mr. Frank A. Ross Program Manager, ALWR Office of LWR Safety & Technology U.S. Department of Energy NE-42 19901 Germantown Road Germantown, Maryland 20874

t REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE SIMPLIFIED BOILING WATER REACTOR (SBWR) DESIGN The General Electric test specification 23A6999, " Isolation Condenser &

Passive Containment Condenser-Test Requirements," Revision 1, specifies the requirements for tests of full-scale prototypes of the isolation condenser (IC) and passive containment cooling condenser (PCC) designed for.use in the SBWR. The tests objectives for the PCC is to confirm that the Ansaldo-designed PCC meets the thermal hydraulic performance requirements for use in the SBWR and that the mechanical design of the Ansaldo PCC is adequate to assure the structural integrity of the unit for the expected SBWR lifetime process service conditions. Also, the document provides general strategy and description of tests, schedule requirements, test plan and procedures, quality assurance requirements, and data transmittal and reporting requirements.

The staff has reviewed the test specification and has tne following comments and questions on the IC and the PCC Test:

Isolation Condenser:

900.48 Discuss the ASME Code classification of the IC-related piping and tubing and its relevance to the stress levels to be confirmed by the tests. Discuss how the test results will be used with other_ piping loads (e.g., seismic) to verify that the stress allowable limit of 1.5 5 will be met for the steam supply line. In addition, discuss how tee thermal gradient effects though the pipe wall and the number of cycles are considered in the design and verified in the test for the portion of piping and tubing submerged in the~IC pool. If any of this submerged piping is not ASME Code Class 1, discuss how the test results will be used for establishing its design.

900.49 Are the IC connecting pipes (i.e.,' steam supply line and drain line) and valves representative of the actual piping and valves to be installed in the SBWR plant? If they are not entirely similar, explain the applicability of the test results to the actual piping and valves to be installed in the SBWR plant.

900.50 Are the tests always conducted with saturated dry steam with a quality greater than 99.8 percent? Discuss,how a constant steam quality can be maintained throughout the tests since the test '

pressure varies from 70 to 1375 psig.

900.51 Detailed drawings that identify sensor locations are not provided.  ;

Explain the criteria used to select the type and _ location of these sensors and show their locations in drawings.

900.52 Will modal survey tests be conducted on the IC assemblies prior to the planned flow tests? (Such information will be helpful for investigating the behavior response under vibratory loadings.)

Enclosure

4 900.53 What are the acceptance criteria for the measurements received from the sensors when monitoring the test responses? For instance, how will it be verified that flow-induced vibrations (FIVs) are not a problem? Will spectral analyses of monitored data be conducted to examine the vibratory behavior of responses especially if severe FIV or water hammer loadings occur?

900.54 What level of sensitivity or accuracy is expected for the proposed leak detection method? Discuss the objective of the leak test and any follow-up actions that might need to be taken when defined limits or acceptance criteria are exceeded.

Passive Containment Cooling Condenser:

900.55 Section 1 of the test' specification states that the purpose of the  :

tests is to confirm the structural adequacy of the Ansaldo-designed hardware for use in the SBWR. The test specification includes the facility requirements, test procedures, and structural data to be collected but does not provide the structural acceptance criteria.

Provide the structural acceptance criteria and the methodology for '

satisfying the criteria in order to confirm the structural adequacy of the PCC system.

900.56 Section 4.1.1 of the test specification states that'a full-size PCC unit will be provided to be mounted inside the tank simulating the PCC pool in SBWR. Provide the details for mounting the PCC unit inside the PCC tank. ,

900.57 Section 4.1.4.3 of the test specification states that Module B is instrumented in only a few positions for comparison with Module A and for confirmation of symmetrical performance. However, the measurements specified for Module B are thermal hydraulic (See also Table 4-2) only and do not include any structural response measure-ments. Provide the structural response measurements that will be included for Module B for comparison with Module A and for confirma- ,

tion of symmetrical structural response. '

900.58 Section 4.1.4.3 of the test specification states that acceleration '

measurements will be made for the purpose of evaluating the vibra-tion characteristics and detection of possible condensation / water hammer loads. Specify the time interval at which.the structural responses, such as accelerations and displacement measurements, will be taken. ,

900.59 Table 4-2 of the test specification shows that the location for the measurement of permanent strain at the upper header / tube junction-for Module A is position number 5. However, Figure 4-4 indicates that the location of upper header / tube junction for Module A is position number 4. Clarify the location for the permanent strain measurement at the upper header / tube junction for Module A.

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900.60 Table 4-2 of the test specification gives 'the required structural measurements for.the PCC test. In some cases, multiple measurement locations will be utilized, but these positions are not clearly specified in Table 4-2. For' example, Table 4-2 does not specify the five positions for the measurement of acceleration at mid-length of tube. Provide the position location for measurements to be taken at-a multiple number of positions.

900.61 The PCC test description (Section 3.4.2), of the test specification states, "The tests will include sufficient pressure / temperature cycles (five times the number of cycles used for design)-to confirm the structural integrity." Discuss the adequacy of five times the number of design cycles for the severe accident condition. Al so ,

discuss how the number of cycles used for design was established.

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