ML19347E772
| ML19347E772 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/11/1981 |
| From: | Martin R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105130361 | |
| Download: ML19347E772 (4) | |
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NUCLEAR REGULATORY COMMISSION nsmucrow, o.c.rossa g.
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%; NAf IIAY 111981 Docket No. 50-368 LICENSEE: Arkansas Power & Light Company FACILITY: Arkansas Nuclear One-Unit 2 (ANO-2)
SUBJECT:
SUMMARY
OF MEETING ON ANO-2 CYCLE 2 RELOAD REPORT On M;y 7, 1981 members of'the staff met with representative of the licensee a n t'. Combusti'on Engineering, Inc. in Bethesda Maryland to discuss technical issues requiring resolution to support the operation of ANO-2 during Cycle 2.
A list of attendees is attachad.
The Thermal Hydraulics Section of the Core Performance Branch has recently developed additional requests for information numbered 492.48 through 492.71. These deal with the implementation of the CE-1 DNBR correlation via the CETOP code in the plant's Core Protection Calculator System (CPCS)
Cycle 2 software and with the incorporation of the statistical combination of uncertainties (SCU) in the CPCS Cycle 2 software.
Proposed responses to the questions were discussed. The following schedule for events necessary to support the reload review was developed in the meeting.
May 7:
Discussion of questions 492.48-492.71 May 18: Licensee responds to 492.48-492.71 May 18: Phase II CFCS Test Report in DRAFT formis generated May 27&28: Staff audit of Phase II Test Results in Windsor, Connecticut May 27:
Phase II CPCS Test Report in FINAL form is generated June 5: Projected Cycle 2 Restart Date Several problems were noted with respect to (a) the schedule for providing responses to several of the questions related to the SCU methodology and (b) the schedule required for the staff and its contractor, Battelle Pacific Northwest Labs (PNL), to complete the review of the SCU methodology and implementation relative to the projected startup date for Cycle 2 operation.
The boron dilution transient analysis was also discussed by Reactor Systems Branch representatives. The discussion conicuded with the statement of a tentative staff position that an alarm would be required to alert the operator to a boron-dilution event-in-progress in Modes 5 and 6 with the control rods inoperable. This alarm would be in addition to the source range monitor count rate which is audibly annunciated in the control room and in the containment.
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kooert /Mbin,ProjectManager Operating Reactors Branch #3, DL
Attachment:
As stated cc: See next page 8105130'% l f
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P00R ORIGINAL
I Arkansas Power & Light Company _
cc:
Mr. David C. Trimble Director Criteria and Standards Division Manager, Licensing Office of Radiation Programs ( ANR-460)
Arkansas Power & Lf.ght Company U.S. Environmental Protection Agency P. O. Box 551 Washington, D. C.
20460 Little Rock, Arkantas 72203 U.S. Environmental Protection Agency Mr. James P. O'Hanlon Region VI Office General Manager ATTN:
EIS COORDINATOR Arkansas Nuclear One 1201 Elm Street P. O. Box 608 First International Building Russellville, Arkansas 72801 Dallas, Texas 75270 Mr. Robert P. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420 7735 Old Georgetown Road Director, Bureau of Environmental Bethe:da, Maryland 20014 Heal th. Services 4815 West Markham Street
. Nick Reynolds Little Rock, Arkansas 72201 c/o DeBevoise & Liberman 1200 Seventeenth Street, N.W.
Washington, D. C.
20036 Arkansas Polytechnic College i
Russellville, Arkansas 72801 s
Honorable Ermf1 Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems 4853 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014
NRC/AP&L/C-E MEETING May 7, 1981 NAME COMPANY C. Chiu C-E
T. Mansell AP&L H. Balukjian NRC/CPB Y. G. Hsii NRC/CPB L. Phillips NRC/CPB Z. Karcutas C-E R. E. Martin NRC/DL T. M. Novak NRC/DL L. Rubenstein NRC/DSI B. Sheron NRC/DSI A. Gill NRC/DSI j
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