ML20198R199
| ML20198R199 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 01/14/1998 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9801230244 | |
| Download: ML20198R199 (4) | |
Text
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January 14, 1998 Mr. Nicholas J. Liparuto, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
OPEN ITEMS ASSOCIATED WITH PRESSURE ISOLATION VALVE (PlV) LEAK TESTING
Dear Mr. Liparulo:
In a letter dated October 16,1997, the U.S. Nuclear Regulatory Commission (NRC) identifie6 final safety evaluation report (FSER) open items associated with the need for Westinghouse to include certain AP600 valves into the technical specification for PlV integrity (Technical Specifi-cation (TS) 3.4.16) and conduct leak testing of these valves in accordance with ASME Section XI guidance for Category A valves.
Westinghouse letter NSD-NRC 97 5452 dated m 'mber 21,1997, responded to the NRC FSER open items concerning PlV testing and the associated TS 3.4.16. Westinghouse agreed to inaude the normal residual heat removal syctem PlVs into TS 3.4.16 but did not agree to include any of the chemical and volume control system PlVs. Westinghouse modified TS 3.4.16 to leak test the valves on a refueling outag) basis and permits use of attemate PlVs to comply with the TS LCO if necessary. In addition, Westinghouse proposed a change to increase the maximum allowable leakage from 5 gpm to 10 gpm in TS 3.4.16 which is not in accordance with ASME Section XI leak testing for Category A valves.
The staff has evaluated the November 21,1997, Westinghouse submittal on the PlVs and has additional open items. The open items are designated as FSER open ite.ns and are provided in the enclosure to this letter.
If you have any questions regarding this matter, you may contact me at (301) 4151141.
Sincerely, original signed by:
William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management I
' Office of Nuclear Reactor Regulation o
(fh 1 i Docket No.52-003 DISTRI.3'JTION. See next page
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Enclosure:
As stated cc w/ encl: See next page
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OFFICE PM PDST:DRPM BC:14:16E BC:SRXB:DSSA
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, DATE 01(1/98 '
9901230244 980114 PDR ADOCK 05200003 E
.s Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc:
Mr. B A. McIntyre Mr. Russ Bell Advanced Plant Safety & Licensing Senior Project Manager, Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 i Street, NW 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 Dr. Craig D. Sawyer, Manager Advanced Ruactor Programs Mr. Sterling Franks CE Nuclear Energy U.S. Department cf Energy 175 Curtner Avenue, MC-754 NE 50 San Jose, CA 95125 1E901 Germantown Road Germantown, MD 20874 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC-781 U.S. Department of Energy, NE-42 San Jose, CA 95125 Office of LWR Safety and Technology 19901 Germantown Road Barton Z. Cowan, Esq.
Germantown, MD 2087/.
Eckert Searnans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE 50 Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenuo Mr. Rnbert Maiers, P.E.
Palo Alto, CA 94303 Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box B469 Harrisburg, PA 17105-8469
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l OPEN ITEMS ASSOCIATED WITH AP600 PRESSURE ISOLATION VALVES 250.35F FSER open item 230.147F, related to the CVS classification issue, requested that Westing-house perform ASME Section XI leak testing on the isolation valves between the RCS and the CVS piping. Although these valves do not strictly meet the definition of PlVs (two normally closed valves between high pressure and low pressure systems), the staff believes that the function of these valves is equivalent to PlVs for isolating the RCS from the non-ASME code class CVS piping. The potential for full RCS differential pressure across the valves from a g
failure of the downstream CVS piping dictates that ieak tightness be assured so that failure of the CVS piping will not result in a LOCA for the AP600. Westinghouse should include valves CVS-PL V001, V002, V003, V080, V081, V082, V084, and V085 as PlVs under proposed SSAR Table 3.918 and subject them to the RCS PlV Integrity technical specification, TS 3.4.16 Limiting Conditions of Operation. In addition, these valves should be included in IST Table 3.916 as Category A valves requiring a leak test.
250.36F Westinghouse has proposed that the TS 3.4.16 leakage limit be less than or equal to to gpm for any PlV. The NRC does not agree with this leakage limit and requests that the ASME Section XI limit for Category A valves be specified. That is, the leak testing and acceptance criteria should be as currently required by ASTM Section XI (OM-10) which allows 0.5D gpm or 5 gpm (whichever is less), where D is the nominai valve diameter expressed in inches.
250.37F The BASES background discussion of TS 3.4.16 should be revised to explain that the normal!y open RCS to CVS interface valves will be treated as PlVs for the AP600 design because of the potential of these valves to perform a PlV functions if the CVS piping were to experience a failure. Westinghouse should develop appropriate wording for a PlV inclusion criterion explaining that the NRC rationale for designating the RCS to CVS interface valves as PlVs is based on the capability of these valves to establish and maintain the leak tight integrity of ASME Section lil reactor coolant pressure boundary piping under high pressure RCS operation.
Westinghouse should review the entire TS 3.4.16 BASES discussion and make it consistent with inclusion of the RCS to CVS interface valves.
Enclosure i
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