ML20138E335
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UNITED STATES 4
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WASHINGTON. D.C. 205554 001 March 31, 1994 i
MEMORANDUM FOR: Herbert N. Berkov. Director Project Directorate. PD II-2 Division of Reactor enjats, I/II FROM:
Timothy E. Collins, Acting Chief Reactor Systems Branch
,j Division of Systems Safety and Analysis
SUBJECT:
FLORIDA POWER AND LIGHT: NTH-TR-01, "RETRAN MODEL
_i QUALIFICATION; DECREASE OF HEAT REMOVAL BY THE SECONDARY SYSTEM" (TAC NOS. M75082, M75083, M75084 AND M75085)
By letter dated October 2,1989 Florida Power and Light, the licensee for the Turkey Point Units 3 and 4 and the St. Lucie Units 1 and 2 nuclear power plants, submitted the topical report NTH-TR-01, "RETRAN Model Qualification, Decrease in Heat Removal by the Secondary System" for staff review.
Additional information was submitted on May 2, 1991, May 19, 1992 and September 25, 1993.
The licensee's objective was to obtain NRC approval for their use of RETRAN-02 in licensing actions involving transient events with decreased secondary heat removal.
In Generic Letter (GL) 83-11 the staff took the position that each
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licensee must demonstrate technical competence and to develop its own analytical capability to perform plant transient estimates. The staff review 1
of NTH-TR-01 and related information sought to establish that the licensee met the recommendations in GL 83-11.
NTH-TR-01 has been under NRC review for over four years. Review of the submitted information, including responses to staff requests for additional information, indicated that the licensee has not justified its steam generator nodalization for neither Turkey Point nor St. Lucie. Repeated requests for information to complete the review yielded no new information, therefore, the staff has discontinued this effort. The staff will consider further review when substantive information has been submitted on steam generator nodalization and steam generator water level as described above and in the attached technical evaluation report.
In the review of NTH-TR-01 the staff has been assisted by International Technical Services (ITS) Incorporated, under Job Code Number: L-1318. The staff safety evaluation is in Enclosure 1.
Our SALP evaluation is in
Contact:
L.Lois, SRXB/DSSA 504-3233 19 0h O
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- March 31, 1994.
The ITS technical evaluation report is in Enclosure 3.
This concludes tho SRXB/DSSA review effort for TAC Numbers M75082, M75083, M75084, and M75085.
/s/
Timothy E. Collins, Acting Chief Reactor Systems Branch Division of Systems Safety and Analysis J
Enclosures:
As stated i
cc:
J. Norris R. Croteau PQEB (10-A-19)
M. Virgilio i
DISTRIBUTION Central File JNorris SRXB R/F RCroteau l
MVirgilio MCaruso TCollins LLois i
Llois R/F SRXB:DSSA*
SRXB:DSSA
- DSSA f[rTCOLLINS LLOIS: BAH MCARUS0 3/04/94 3/14/94 3/5f/94 G:\\NTHTR0lR.EV1 1
- See previouse concurrence i
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