ML20141K882
| ML20141K882 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 05/28/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9705300237 | |
| Download: ML20141K882 (3) | |
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UMTED STATES NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.C. 30666 0001 May 28,1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division o
Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230 i
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SUBJECT:
C0lmENT ON THE AP600 TECHNICAL SPECIFICATIONS (TS) RELATED PRESSURE!
ISOLATION VALVES t
Dear Mr. Liparulo:
The U.S. Nuclear Regulatory Commission (NRC) is reviewing the AP600 TSs (08/96-Amendment 0) which were included with Revision 9 to the AP600 standard safety analysis report.
In a letter to Westinghouse dated December 24, 1996, l
the staff questioned why a limiting condition of operation (LCO) on reactor coolant system (RCS) pressure isolation valve (PIV) leakage had been deleted hom the AP600 TS. The staff stated the NUREG-1431 technical specification for DCS PIV leakage (STS LCO 3.4.14) was applicable to the AP600 and should be
. reinstated. Westinghouse responded to the staff's concern in a letter dated Parch 12, 1997 (NSD-NRC-97-5001), and stated that an RCS PIV leakage specifi-L cation is not required for AP600, since the risk basis for having the LCO stated in NUREG-1431 is not met by AP600. The staff does not agree with this t
response.
Although the NUREG-1431 (STS LC0 3.4.14) BASES states that the basis for the i
LCO for the RCS PIV leakage is the 1975 " Reactor Safety Study" that identified potential intersystem LOCAs (ISLOCA) as a significant contributor to the risk of core melt, the BASES also states that RCS PIV leakage satisfies Criterion 2 of the NRC Policy Statement.
The RCS PIVs are those normally closed valves within the reactor coolant pressure boundary (RCPB), which separate the high pressure RCS from attached low pressure systems. Although the staff position on ISLOCA, stated in SECY-90-016, requires (1) PIV leakage testing capability, (2) valve position indication and (3) high pressure alarms for those low-pressure interfacing systems not designed to withstand the RCS operating pre:sure, the PIV leakage test requirement is not limited to these low-pressure interfacing systems.. Because the RCS PIVs are part of RCPB, and the PIV leakage is not considered in the design basis accident anklyses, they are the design features that constitute an initial condition of the design basis accident and transient analyses that challenge the integrity of a fission product barrier.
The PIV leakage LCO provides for monitoring the condition of the RCPB to detect degradation which could lead to accidents, and, therefore, the'PIVs are within the scope of technical specification LCOs per Criterion 2 of 10 CFR 50.36. Consequently, the staff requests that a TS LCO for RCS PIV leakage equivalent to STS LCO 3.4.14 be provided in the AP600 TS.
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goon 9705300237 970528 PDR ADOCK 05200003 A
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.Mr. Nicholas J. Liparulo May 28, 1997 If you have any questions regarding this matter, you may contact me at (301) 415-1141.
Sincerely, original signed by:
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l William'C. Huffman, Project Manager i.
Standardization Project Directorate i.
Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 l
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05/23/97 05/2k/97 U A FFICIAL RECORD COPY l
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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 Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. Cindy L. Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager i
LMR and SBWR Programs L
Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 351 GE Nuclear Energy Rockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.
NE-50 Eckert Seamans Cherin & Mei!ott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 l
Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certificatio-l Lockheed Idaho Technologies Company Electric Power Reser.rch Institute Post Office Box 1625 3412 Hillview Avenae Idaho Falls, ID 83415 Palo Alto, CA 94303 l
Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874 l
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