ML20209D942
| ML20209D942 | |
| Person / Time | |
|---|---|
| Issue date: | 07/07/1999 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | Liberatori L WESTINGHOUSE OPERATING PLANTS OWNERS GROUP |
| Shared Package | |
| ML20209D945 | List: |
| References | |
| PROJECT-694 NUDOCS 9907140092 | |
| Download: ML20209D942 (3) | |
Text
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NUCLEAR REGULMORY COMMISSION i WASHINGTON, D.C. 20666 4001
+9 * * * * * ,o July 7, 1999 i
Mr. Lou Liberatori, Chairman Westinghouse Owners Gmup Steering Committee Indian Point Unit 2 Broadway & Bleakley Ave.
Buchanan, NY 10511 '
SUBJECT:
SAFETY EVALUATION OF TOPICAL REPORT WCAP-14750, "RCS FLOW VERIFICATION USING ELBOW TAPS AT WESTINGHOUSE 3-LOOP PWR.s"
Dear Mr. Liberatori:
l The NRC staff has completed its review of the subject topical report which was submitted by Southern Nuclear Operating Company (SNC), the licensee for the operation of Joseph M.
Farley Nuclear Plant Units 1 and 2, by letter dated November 26,1996. SNC submitted the topical report on behalf of the Westinghouse Owners Group (WOG) and requested the staff l review the report for generic approval for application to other Westinghouse 3-loop plants. The staff has found that this report is acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the report and in the associated NRC safety evaluation. The safety evaluation defines the basis for acceptance of the report, which is enclosed.
WCAP-14760 describes a methodology for using reactor coolant systom (RCS) cold-leg elbow taps to measure RCS flow as an altemative to using precision heat balance measurements for this purpose. The need to use this attemate method for the RCS flow surveillance verification arises from an inherent limitation of the calorimetric flow measurement because of the occurrence of a hot-leg temperature streaming phenomenon, due to the use of low leakage core loading patterns (LLLP). This alternate method correlates the cold-leg elbow tap differential measurements to the calorimetric flow measurements of pre-LLLP fuel cycles when [/
core radial power distributions had minimalimpact on the hot leg temperature streaming biases. /
The use of this alternate RCS flow surveillance verification method is consistent with those f approved for other pressurized-water reactors such as McGuire Nuclear Station, Catawba Nuclear Station, and South Texas Project Electric Generating Station. ,p The staff will not repeat its review of the matters described in the subject report, when the report appears as a reference in license applications, except to ensure that the materia!
presented applies to the specific plant involved. In accordance with procedures established in NUREG-0390, the NRC requests that WOG publish accepted versions of the submittal, proprietary (-P) and non-proprietary (-NP), within 3 months of receipt of this letter. The accepted versions shall incorporate (1) this letter and the enclosed safety evaluation between the title page and the abstract and (2) an "-A" (designating " accepted") following the report identificat:an symbol. If the NRC's criteria or regulations change so that its conclusion that the submntalis acceptable are invalidated, WOG and/or the applicant referencing the report will be expected to revise and resubmit its respective documentation, or submit justification for the continued applicability of the report without revision of the respective documentation.
9907140092 990707 PDR TOPRP EMWEST f0
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e o-Mr. Lou Liberatori . 2 July 7,1999 Should you have any questions or wish further clarification, please call me at (301) 415-1282 or ,
- Y. Gene Hsii at (301) 415-2877. !
Sincerely, r
04 Cynt A. Carpenter, Chief Genenc issues, Environmental, Financial and Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation Project No.' 694
Enclosure:
Safety Evalua'.lon
)
cc w/ enc: See next page i
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Mr. Lou Liberatori 2 July 7,1999 Should you have any questions or wish further clarification, please call me at (301) 415-1282 or Y. Gene Hsil at (301) 415-2877.
I Sincerely,- 1 Original Signed By: I Cynthia A. Carpenter, Chief Generic issues, Environmental, Financial and Rulemsking Branch Division of Regulatory improvement Programs Office of N Jclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enc: See next page 4 4
DISTRIBUTION:
! roject P File PUBLIC RGEB r/f SRXB r/f OGC ACRS DMatthews/SNewberry GHolahan/TCollins JWermiel EWeiss YHHsii J Donohew DOCUMENT NAME: G:\RGEB\PXW\elbowtap.wpd /
OFFICE PM:RGEB BCtSRXB SC:RGhh7b BC:RGEB NAME PWen:awM JW FAkstulewicz CCarpenterk
, DATE 7 / [ /99 7/ f /99 7/ h /99 7/ 9 /99 Y
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