ML20032E443
| ML20032E443 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 11/13/1981 |
| From: | Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GO1-81-377, NUDOCS 8111200564 | |
| Download: ML20032E443 (2) | |
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Washington Public Power Supply System P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 November 13, 1981 8
4 G01-81-377 p
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Docket Nos.: 50-460 & 50-513 q
Mr. Harold A. Denton, Director
' 2Y NOV2 01981* Te' Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission m ga g 7 R Washington, D.C. 20555
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Dear Mr. Denton:
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Subject:
Supply System Nuclear Projects No. 1 & 4 (WNP-1/4)
Response to October 23, 1981 Meeting on Verification Testing for SB LOCA Methods This letter expresses our understanding of the agreements reached in the meeting of October 23, 1981 with you and members of your Staff.
In sumary, the Staff agreed to participate in an in depth review of the current B&W SB LOCA Methods Program including the verification testing base. This review is to begin as soon as practical and will include the review of results achieved with the improved models and methods now being developed. This review is to be completed one month before the completion of the SB LOCA Methods Program or June 1,1982, which-ever is earlier.
In addition, the Staff requested commitments to install RCS~ vents and wate:r level measurement.
Based on the above understanding, we are comitted to the following:
1.
We will participate in a joint effort with the Staff to assure that our current SB LOCA methods and AT0G efforts are fully understood.
This program will include the following:
t Code parameters, nodel, assumptions, etc., which are important in controiling dynamics of interest will be identified and available experimental data substantiating their validity will be reviewed. This would be done using results of the improved evaluation model in order that the most accurate dynamic response characteristics are reviewed.
Additional experimental data, from separate effects or integral tests, will be defined which address specific technical gaps, if any. Our position is not one of opposition to additional testing.
Instead, we want to assure that questions which must be answered are answered in the most appropriate technical and cost-effective manner.
Identify where and how additional experimental data may be obtained, if any is required.
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4 Docket Nos.: 50-460 & 50-513 November 13, 1981 Mr. Harold A. Denton G01-81-377 l
Page 2 With your cooperation, we commit to complete this program within one month of completion of the SB LOCA program or June 1,1982, l
whichever is earlier.
1 Consistent with this effort it is expected the Staff will continue review and approval of AT0G by April 1982.
2.
We are providing directly to R.W. Hernan, Project Manager, Licensing Branch No. 4, a summary of Dr. Roy's presentation on the philosophy underlying AT0G and the report titled, " Abnormal Transient Operating Procedures for Nuclear Power Plants" by J. J. Kelly and D. H. Williams, I
which includes the total scope of the AT0G approach as well as the philosophy presented by Dr. Roy.
3.
With regard to RCS vents and water level measurement:
l We will install RCS vents on the pressurizer and the hot legs.
These vents will be installed before fcel load.
On July 29, 1981 we met with the Staff to present the WNP-1/4 plan for implementation of NUREG-0737, Item II.F.2.
This included the proposed plan for measurement of the reactor coolant system water i
level.
In this meeting, and in the NRC meeting notes, the Staff responded that, with proper design, the level measurement concept proposed would probably be acceptable to the Staff.
l Further details on these two issues will be discussed in SubsecQon 1.10.1 of the WNP-1/4 FSAR when it is submitted in December,1981.
4.
In response to Dr. Mattson's question, we will provide information cn the formation of steam during normal operating transients includ-i ing rapid cooldown. A schedule for the submittal of the information i
i will be developed separately.
We believe this letter reflects the major conclusions and agreements reached in the October 23 meeting.
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The B&W Owners Group is prepared to begin the review of our SB LOCA Methods Program with the Staff and request that the assigned Staff reviewer contact Mr. Lou Lanese of GPUNC to establish the details fnr carrying out this review.
It is our intent to implement this review without impacting the current schedule for the completion of the 3B LOCA Methods Program.
I Very truly yours, i
ek G. D. Bouchey, ty Director l
Safety & Security GDB:pp cc: RW Hernan, NRC A Toth, NRC l
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