ML18019A351
| ML18019A351 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/29/1985 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-43, REF-GTECI-ES, RTR-REGGD-01.082, RTR-REGGD-1.082, TASK-A-43, TASK-OR NLS-85-317, NUDOCS 8509040210 | |
| Download: ML18019A351 (6) | |
Text
r RS LA'IIY INFORMATION DISTR IS%KIDSYSTEM (RIDS)
A ACCESSION NBR: 8509040210 OOC ~ DATE: 85/08/29 NOTARI'ZED: - NO FACIL:50-400 Shearon Harris Nuclear Power Planti Unit 1F Carolina.
AUTH,NAME AUTHOR AF F ILIATION CUTTER,A,BE Carolina Power L Light Co.
RECIP ~ NAME RECIPIENT AFFILIATION DENTON~H,RE Office of Nuclear Reactor Regulationi Director SUBJECT; For wards evaluation outline re proposed resolution to Generic Safety Issue A
Q3 to demonstrate that containment'ecirculation sump meets Reg Guide 1.82 provisions,Mee,ting w/NRC on 850911 requested to discuss analytical
- methods, DISTRIBUTION CODE:
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TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8, Related Correspondenc NOTES:
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Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 - DOCKET NO.50-000 CONTAINMENTRECIRCULATIONSUMP SERIAL: NLS-85-317
Dear Mr. Denton:
In order to demonstrate that the existing design is a technically sound resolution to the Harris Containment Recirculation Sump Issue NRC IDI Item D.2.3-1 Carolina Power k Light Company (CPRL) will perform a
study using the guidance of the proposed resolution to Generic Safety Issue A-03. Such a study was requested by the NRC Staff in a meeting of August 19, 1985 between the NRC and CPRL.
Carolina Power R Light Company proposes to follow the enclosed evaluation outline derived from the guidance of A-03 to demonstrate the adequacy of the containment sump.
We request a meeting with your Staff on September ll, 1985 to discuss the analytical methods being used to resolve this issue.
Although we have agreed to the above study in the interest of resolving an open issue, CPRL believes the current sump design meets all of the provisions of Regulatory Guide 1.82.
We believe the NRC Staff has changed its interpretation of what constitutes compliance with this guide based on the Staff's acceptance of our Regulatory Guide 1.82 compliance in the Harris SER dated November 1983.
The SER is based upon NRC review of design information presented in Chapter 6 of the Harris FSAR and in responses to Safety Review Question Responses 080.27 and 080.28 dated August 31, 1982 and August 2, 1982, respectively.
If you have any questions, please call.
Your very t ABC/DCM/mf (1885DCM)
Enclosure A. B. Cutter Vice resident Nuclear Engineering R Licensing Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
Mr. 3. L. Kelley (ASLB)
Mr. B. K. Grimes (NRC)
(NRC)
CC:
8509040210'850829 PDR
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SHEARON HARRIS NUCLEAR POWER PLANT CONTAINMENTRECIRCULATIONSUMP EVALUATION I.
Debris Assessment A.
Assess areas and volumes of insulation removed by pipe whip, pipe impact, and jet impingement.
B.
Define limiting case for fibrous insulation volume and subsequent transport to sump.
C.
Determine for the limiting case the volume of fibrous insulation transported to the sump screen.
II.
Sum Performance A.
Determine available NPSH.
B.
Compare to required NPSH and identify margin.
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