ML20134P913
| ML20134P913 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 11/26/1996 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9611290371 | |
| Download: ML20134P913 (3) | |
Text
_
F2 -co 3 tt:oqk UNITED STATES E
NUCLEAR REGULATORY COMMISSION 5
f WASHINGTON, D.C. 20066-0001
.....[
November 26, 1996 Mr. Nicholas J. Liparulo, Manager i
Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230
SUBJECT:
COMMENTS ON THE AP600 DETECTION OF REACTOR COOLANT PRES LEAKAGE
Dear Mr. Liparulo:
The Nuclear Regulatory Commission (NRC) staff has recently been attempting to close out the review of various AP600 standard safety analysis report (SSAR) chapters which have relatively few remaining open items identified in the open item tracking system. During the review of AP600 SSAR Chapter 5, the staff has been concentrating its effort on leak detection instrumentation to ensure that the design is capable of detecting reactor coolant pressure boundary leakage of 0.5 gpm which is used as a criteria for leak-before-break piping analyses.
In a telephone conversation with your staff on November 22, 1996, t
it was noted that the reactor coolant system (RCS) leak detection capability of containment atmosphere radioactivity monitor (gaseous N13/F18) instrumenta-tion is only effective above 20 percent power. Therefore, use of this instrument for leak detection does not appear to be appropriate for modes 2, 3, or 4, as well as mode 1 below 20 percent. The staff also notes th:t the use of a gaseous N13/F18 monitor is inconsistent with technical specification requirements which states that the containment atmosphere radioactivity monitor shall be operable in modes 1, 2, 3, and 4.
Upon further consideration, the staff has some additional concerns about the design capabilities of AP600 leak detection system.
Besides the containment atmosphere radiation monitor, the other required RCS leak detection instrument (per technical specifications) is the containment sump level monitor.
Condensate from the containment fan coolers, floor drains, and the containment shell gutter drains is normally directed to the containment sump. The containment sump level instrumentation is capable of detecting level changes 1
equivalent to 0.5 gpm leak rate increase within one hour. However, this capability would be circumvented should the containment shell gutter system be redirected to the in-containment refueling water storage tank, such as would occur with the actuation of the passive residual heat removal system (PRHR).
Since the PRHR system can be operational in modes 2, 3, or 4, the use of toe containment sump level monitor to detect unidentified reactor coolant pressure boundary leakage can not be assured under all anticipated operational condi-
@1 tions.
Because of the importance of the leak detection system for assuring the validity of the leak-before-break applications used in the AP600 RCS piping design, it is the staff's opinion that Westinghouse should give these concerns i
a high priority.
9611290371 9
^ "
61126'"#88 NRC FRE CENTER CO
Mr. Nicholas J. Liparulo November 26, 1996 During the November 22,199o, telephone conference on this subject, the staff also noted several editerial errors in the SSAR section on leak detection.
The definition of identified leakage provided in Section 5.2.5-is inconsistent with technical specification and is incorrect.
In addition, the referenced applicable technical specifications in Section 5.2.5.7 are incorrect.
If you have any questions regarding this matter, you can contact me at (301).415-1141.
Sincerely, original signed by:
William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 cc: 'See next page DISTRIBUTION:
Docket File PDST R/F TMartin PUBLIC DMatthews TQuay TKenyon BHuffman JSebrosky DJackson JMoore, 0-15 B18 WDean, 0-17 G21 ACRS (11)
GHolahan, 0-8 E2 TMarsh, 0-8 DI.
TCollins, 0-8 E23 JLyons, 0-8 D1 RYoung, 0-8 D1 GBagchi, 0-7 HIS Glainas, 0-7 D26 DOCUMENT NAME: A: LEAK-DET.CMT Ta seceive a copy of this document, Indicate in the ben: "C" = Copy wJthout attachment / enclosure
'E" = Copy with ettachment/ enclosure "N* = No copy 0FFICE PM:PDST:DRPM SC:SPLB:RSfA BC:ECGB:DE.
IE D:PDST:DRPM [S NAME WCHuffma h'JLyons v' '
GBagchi'#/6//v TRQua n a)
DATE 11Q996 11/Z6/96 11/ft,/96 11/26/96/fdfP OFFICIAL RECORD COPY d
.w
i Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 Eye Street, N.W.
P.O. Box 355 Suite 300 3
f Pittsburgh, PA 15230 Washington, DC 20006-3706 Mr. John C. Butler Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates l
Westinghouse Electric Corporation Post Office Box 34 l
Energy Systems Business Unit Cabin John, MD 20818 Box 355 i
Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager l
LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 e
Westinghouse Electric Corporation San Jose, CA 95125 One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz l
Suite 350 GE Nuclear Energy j
Rockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks 4
U.S. Department of Energy Barton Z. Cowan, Esq.
i NE-50 Eckert Seamans Cherin & Mellott i
19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 l
Mr. S. M. Modro Mr. Ed Rodwell, Manager l
Nuclear Systems Analysis Technologies PWR Design Certification i
Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer i
U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 4
19901 Germantown Road 19901 Germantown Road j
Germantown, MD 20874 Germantown, MD 20874 l
-