ML20197K016
| ML20197K016 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 12/17/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9801050178 | |
| Download: ML20197K016 (3) | |
Text
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Decembcr 17, 1997 L
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 SAFETY EVALU/. TION REPORT (CER) ON AP600 TECHNICAL SF'ECIFICATIONS (TSs)
Dear Mr. Liparulo:
The U.S. Nucinar Regulatory Commission Standardization Project Directorate has received a partial SER submittal from the Containment Systems and Severe Accident Branch on the AP600 pH adjustment and passive autocatalytic recombiner TSs. The input has open items which have -
been extracted and designated as final safety evaluation report open items 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. Huffmaa, Projec Manager Standardization Project Directorate Division of Reactor Program Management -
Office of Nuclear Reactor Regulction Docket No.52-003 gg g gtg $[3y
Enclosures:
As stated ec w/ encl: See next page ll ll llll!lll ll ll DISTRIBUTION:
, Docket File PDST R/F JRoe PUBLIC DMatthews TQuay TKenyon WHuffman JSebrosky JNWilson DScaletti JMoore,0-15 B18 WDean,0-5 E6 ACRS (11)
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DOCUMENT NAME: A:TS-3-OI.SER To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment /enclosare "N" = No copy OFFICE PM:PDST:DRPM BC:TSB:ADPR D:PDST:DRPM NAME WCHuffmanWa WBeckner
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12/17/97 OFFICIAL RECORD CCPY 9801050178 971217 PDR ADOCK 05200003 E
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Mr. Nicholas J. Lloarulo 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 Adynneed Reactor Programs Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energ r 175 Curtner Avenue, MC-754 NE 50 San Jose, CA 95125 19901 Germantown Road Germantown, MD 20874 Mr. Robert H. B :hholz 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 Gerrnantown Road Barton Z. Cowan, Esq.
Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE 50 for. Ed Rodwell, Manager 19901 Germantown Road PWR Design Cectification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Mr. Robert Malers, P.E.
Palo Alto, CA 94303 Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-84S9 1
- s SER OPEN ITEMS ASSOCIATED WITH AP600 TECHNICAL SPECIFICATION 3.6.9 4BO.1115F LCO 3.6.9 pH Adjustment Because the Westinghouse Standard Technical Specifications (STS), NUREG-1431, do not have an equivalent LCO for comparison to the AP600 LCO 3.6.9, *,H Adjustment," SCSB compared AP600 LCO 3.6.9 to LCO 3.5.5," Trisodium Phosphate," of toe Combustion Engineering Standard Technical Specifications. AP600 LCO 3.6.9 is not esistent with the corresponding Combustion Engineering standard (STS) nor is the LCO consistent with its own BASES. The following are open items for this technical specification:
(a) TM LCO 3.6.9 is not consistent with the LCO BASES description nor is it consistent with CE STS 3.5.5. The LCO simply states that the pH adjustment shall be operable. The LCO BASES and the CE STS discuss the minimum acceptable volume of TSP in the actual LCO.
This is an open item.
(b) ACTION B: The REQUIRED ACTION B.2.2 is not consistent with the CE STS. Action B.2.2 states that if 70 percent of the TSP is verified to be available, then the plant can remain in Mode 3 until the basket is restored to 100 percent of the limit specified in SR 3.6.9.1. The BASES states that this altemative is acceptable because the required volume is based on severe accident conditions and that no MODE 3 DBAs are predicted to result in a signif;mnt fission product release. The staff does not consider this attemative acceptable because the DBA source term would not significantly change if one changed the initial conditions from MODE 1 to MODE 3. This is an open item.
(c) The LCO 3.6.9 BASES BACKGROUND ctates that natural circulation of water inside the containment, following a LOCA, is driven by the core decay heat and provides mixing to achieve a uniform pH. Sections 6.3.2.1.4 and 6.3.2.2.4 of the SSAR, which are referenced at the bottom of the paragraph containing this statement, fail to support this assumption.
This is en ov n item.
e (d) The LCO 3.6.9 BASES discussion on the APPLICABLE SAFETY ANALYSES fails to mention that the LOCA radiological consequences analysis takes credit for iodine retention in the sump solution based on the sump solution pH being greater than or equal to 7.0. This is a deviation from the CE STS and is an open item.
(e) The LCO BASES discussion on the SURVEILLANCE REQUIREMENTS fails to discuss the bases of the surveillance period. This is an open itern.
(f)
The testing described in BASES SURVEILLANCE REQUIREMENT 3.6.9.2 is not consistent with the CE STS. This is an open item.
Enclosure
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