ML20140G454
| ML20140G454 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 06/12/1997 |
| From: | Joseph Sebrosky NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9706160252 | |
| Download: ML20140G454 (7) | |
Text
l June 12, 1997 APPLICANT: Westinghouse Electric Corporation FACILITY:
AP600
)
l
SUBJECT:
SUMMARY
OF MAY 20,.1997, MEETING WITH WESTINGHOUSE TO DISCUSS THE AP600 CONTAINMENT HYDR 0 GEN CONTROL SYSTEM i
The subject meeting was held on May 20, 1997, in the Monroeville, Pennsylva-nia, office of the Westinghouse Electric Corporation between representatives of Westinghouse and the Nuclear Regulatory Commission staff. Attachment 1 is a list of meeting attendees.
The purpose of the meeting was to discuss issues associated with the Hydrogen l
Control System found in Chapter 6.2.4 of the AP600 Standard Safety Analysis Report (SSAR).
The discussion revolved around the passive autocatalytic recombiners and the hydrogen igniter systems. The intent of the meeting was to identify the issues that needed resolution in order for the final safety l
evaluation report to be written. Attachment 2 contains the action items tnat were identified during the meeting. The staff requests that the Westinghouse action items identified in attachment 2 be entered into the Open Item Tracking l
System. A draft of this meeting summary was provided to Westinghouse to allow l
them the opportunity to ensure that the representations of their comments and l
discussions were correct.
t original signed by:
Joseph M. Sebrosky, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 l'
Attachments: As stated 1
cc w/ attachment: See next page g(
DISTRIBUTION w/ attachments:
Docket File PDST R/F TKenyon 9[03 l
PUBLIC BHuffman DTJackson h
l JSebrosky MSnodderly, 0-8 H7 JKudrick, 0-8 H7 1
DISTRIBUTION w/o attachment:
SCollins/FMiraglia, 0-12 G18 TMartin, 0-12 G18 RZimmerman, 0-12 G18 l
MSlosson SWeiss TQuay i
I WDean, 0-5 E23 ACRS (11)
JMoore, 0-15 B18 l
4 DOCUMENT NAME: A:FP MTG. SUM l
To roccivs a copy of this document,Tndcate in the boa; "C" =, Copy without attachment / enclosure
- E' = Copy with attachment /enclosse
- N' = No copy l
0FFICE PM:PDST:DRPM SC9Q:01 D:PDST:DRPM l
NAME.
JMSebrosky:sg 4 CJKudbhtfMrs 1RQuay if*
DATE 06/(j/97 V
06AA197VT \\ 06/tt/97 9706160252 970612 PDR ADOCK 05200003 A
l Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road i
P.O. Box 355 Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Ronald Simard, Director Mr. B. A. McIntyre Advanced Reactor Program Advanced Plant Safety & Licensing Nuclear Energy Institute Westinghouse Electric Corporation 1776 Eye Street, N.W.
Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs l
GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz 11921 Rockville Pike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.
U.S. Department of Energy Eckert Seamans Cherin & Mellott NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. S. M. Modro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, ID 83415 Mr. Charles Thompson, Nuclear Engineer AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874 l
WESTINGHOUSE AP600 CONTAINMENT HYDROGEN CONTROL MAY 20, 1997 MEETING PARTICIPANTS HAME ORGANIZATION DON LINDGREN WESTINGHOUSE DAN MCDERM0TT WESTINGHOUSE
- SUSAN FANT0 WESTINGHOUSE
- BRIAN MCINTYRE WESTINGHOUSE
- JIM GRESHAM WESTINGHOUSE
- JIM SCOBEL WESTINGHOUSE
- CINDY HAAG WESTINGHOUSE
- JIM SEJVAR WESTINGHOUSE
- MIKE CORRELLETTI WESTINGHOUSE
- GENE PIPLICA WESTINGHOUSE JACK KUDRICK NRC/DSSA/SCSB MIKE SN0DDERLY NRC/DSSA/SCSB J0E SEBROSKY NRC/DRPM/PDST l
- PART TIME
May 20, 1997 AP600 HYDROGEN MEETING ACTION ITEMS 1
~ OUTLINE OF ITEMS 11 WESTINGH0VSE ACTION ITEMS ASSOCIATED WITH THE PASSIVE AUT0 CATALYTIC RECOMBINERS (PARS) (additional information provided below for these items)
A)
Concern about a well mixed environment B)
Mixing above the 135 foot elevation C)
Mixing below the 135 foot elevation D)
Environmental Qualification E)
Technical Specifications F)
References to testing done at Battelle Frankfurt G)
Compliance with regulations H)
Debris Clogging of PARS i
I)
Location of PARS relative to pipe breaks etc...
111 WESTINGHOUSE ACTION ITEMS ASSOCIATED WITH THE HYDR 0 GEN IGNITERS (additional information orovided below for these items)
A)
Location of igniters in the upper dome of containment B)
Location of igniters in the Reactor Cavity C)
Location of igniters in the CVCS room D)
Compliance with regulations E) location of ignit'ers relative to pipe breaks, etc...
Jill NRC ACTION ITE!$
A)
Set up a telecon to better understand the decay heat model used to determine the hydrogen production from radioalysis.
B)
Pass on draft responses to containment initial test program comments and schedule a telecon to discuss the draft re-1 sponses.
C)
Provide feedback to Westinghouse on the hydrogen monitoring system for the AP600.
DETAILS OF WESTINGHOUSE ACTION ITEMS I)
PARS A)
Concern about a well mixed environment
- 1) Westinghouse will document in the SSAR sensi'civity cases to address adverse distributions of hydrogel and the ability of the design to cope with these dist.ributions.
l (For example, Westinghouse will evaluate the performance l
of the PARS at less than bulk average conditions.)
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l j
I.A.2)
Westinghouse will incorporate the substance of the February 7, 1997, letter (NSD-NRC-97-4978) on aerosol mixing into SSAR Section 6.2.4.
The discussion will be supplemented for treatment of downward flow, condensa-tion in the dome, and the scope will be changed to discuss hydrogen and aerosol mixing in the long term.
B)
Mixing above the 135 foot elevation
- 1) The staff is concerned about the effectiveness of the PARS for the area above the 135' elevation.
In past designs containments sprays could be relied on to demon-strate a well-mixed environment. Westinghouse will reconsider the merits of using more than two PARS 1
because of the staff's concern.
C)
Mixing below the 135 foot elevation
- 1) The SSAR does not currently discuss mixing below the 135 foot elevation and the staff is concerned about hydrogen control in the accumulator and Chemical and Volume Control System areas. Westinghouse will address why PAR coverage in these areas is not needed either through a discussion of mixing in these areas or an explanation as to why hydrogen will not accumulate in these areas. Another solution is to add safety related PARS in these areas to address the staff's concern.
- 2) Westinghouse will make the PAR unit in the vent of the In-containment Refueling Water Storage Tank safety-grade or provide justification for it not being safety-grade.
D)
Environmental Qualification
- 1) Westinghouse will submit the EPRI report concerning fission product poisons or the applicable portions of the report.
- 2) Westinghouse will add a Combined License (COL) item that requires the applicant to determine the performance of l
the selected PARS unit including the effects of contaminants.
- 3) Westinghouse will change the first paragraph on page 6.2-42 of the SSAR which concerns fission product l
poisons to be consistent with the staff position letter sent to Westinghouse in an April 1,1997, letter.
Westinghouse will cross-reference the revised paragraph to SSAR Section 3.11.
1
(
- E)
Technical Specifications
- 1) The staff is concerned that the technical specifications need to address the following areas for surveillance testing of the PARS:
- 1) temperature requirement,
- 2) time it takes to get to temperature, 3) where the temperature is measured, 4) the input mixture of hydro-gen and oxygen used in the surveillance test, and 5) a verification of uniform thickness of the wafer during the visual surveillance of the unit. The staff also believes that the test objectives need to be clearly identified.
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- 2) Westinghouse will address how the above information (i.e., I.E.1) is conveyed to the COL applicant. An example of how this could be done is a COL action item.
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- 3) Westinghouse will consider beefing up SSAR Table 3.9-17 note 9 to discuss the above.
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- 4) Westinghouse will clearly address in the technical specification basis how the single failure criteria applies to the PARS.
F)
References to testing done at Battelle Frankfurt
- 1) Westinghouse will fix the reference in SSAR Sec-tion 6.2.4 to the Battelle Frankfurt test. The staff disagrees that the PAR testing conducted under the NIS quality assurance program is appropriate for design certification.
G)
Compliance with regulations
- 1) Westinghouse will add to SSAR Section 6.2.4.1.5 a state-ment that the PARS design complies with 10 CFR 50.44, GDC 41, GDC 42, GDC 43, and Regulatory Guide 1.7
- 2) Concerning Regulatory Guide 1.7, Westinghouse will revise Chapter IA of the SSAR. Specifically, Westing-house will change the wording associated with Item C.3, C.4, and C.5 to identify that an exception is not needed for these items.
- 3) Westinghouse will identify the component (s) that will be used to comply with Regulatory Guide 1.7 Item C.4.
H)
Debris Clogging of PARS
- 1) Westinghouse will evaluate Regulatory Guide 1.82 revi-sion 2 to demonstrate that debris clogging of the PARS I
is not a problem.
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w
O.
1)
Location of FARs relative to pipe breaks etc...
- 1) Westinghouse will add a discussion in the SSAR for how the PARS are protected against missiles, jet impinge-ment. and pipe ruptures.
II)
Hydrogen Igniters A) location of igniters in the upper dome of containment
- 1) Westinghouse will provide justification for not having igniters in the upper containment dome (the staff is skeptical of the success of this approach). As an alternative Westinghouse will consider placing igniters in the upper dome area.
T Location of igniters in the Reactor Cavity
- 1) Westinghouse will provide justification in the SSAR for why igniters are not needed in the reactor cavity.
This discussion will include a reference to the three vent paths which are: the reactor vessel seal ring, the steam generator compartments, and the vertical access compart-ment.
C)
Location of igniters in the CVCS room
- 1) Westinghouse will enhance the discussion of the justifi-cation for the location of the igniters located in the CVCS room.
D)
Compliance with regulations
- 1) Westinghouse will add to SSAR Section 6.2.4.1.6 a state-ment that the hydrogen igniters comply with 50.34(f)(2)(ix), 50.34(f)(1)(xii), and SECY 93-037.
(Westinghouse will evaluate if SECY 93-087 and 50.34(f)(2)(ix) contain the same requirements relative to igniters.)
E)
Location of igniters relative to pipe breaks, etc...
- 1) Westinghouse will add a disce:.' ion in the SSAR for how the igniters are protected against missilet, jet impingement, and pipe ruptures.
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