ML19276E038
| ML19276E038 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/09/1979 |
| From: | Boyd R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7903020170 | |
| Download: ML19276E038 (4) | |
Text
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jE NUCLEAR REGULATORY COMMISslON I I
- I WASHINGTON, D. C. 20555 E
FE5 9 1979 Docket Nos. 50-369 and 50-370 Mr. William 0. Parker, Jr.
Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
SUBJECT:
AUGMENTED INSERVICE IflSPECTION FOR PIPE RUPTURE PROTECTION (McGuire Nuclear Station, Units 1 & 2)
On January 18, 1979, we met with representatives of your organization to discuss your proposed use of augmented inservice inspection, supplemented by enhanced local leak detection, to satisfy the requirements of General Design Criterion 4 (GDC-4) for a very limited number of locations in the McGuire piping systems. This meeting resulted in the following specific requirements:
1.
The applicant will doctment its meeting presentation, including a discussion of:
(a) postulated break locations evaluated for the dynamic effects of pipe whip and jet impingement (about 200-300 locations); (b) utilization of conventional methods of meeting GDC-4; (c) the reasons why conventional methods are not feasible for six locations; and (d) the proposed use of augmented ISI utilizing improved examination techniques in combination with enhanced leak detection for these six locations.
2.
The applicant shall further demonstrate that the McGuire piping system design meets General Design Criterion 4 (see Item 1) by providing analyses that show, for the 10 inch acctmulator line break; that:
a.
the impinged 16" feedwater line falls within the faulted stress limit (jet force, pressure, temperature, and dead weight loads) b.
f ailure of the 2" steam generator blovdown line (along with the 10" acctmulator line) does not result in exceeding the containment design pressure.
790302 0/7o
i r. William O. Parker, Jr. FEB 9 M79 NOTE:
This can be accomplished with a complete computer analysis. However, if a comparison of mass and energy release rates shows that'the combination of the two-inch and 10-inch breaks are less severe than the design basis break, we would consider this to be satisfactory.
c.
the consequences of the failure of the impinged 6" hot leg injection line (along with the 10" accunulator line) are acceptable under 10 CFR Part 50, Appendix K, using qualitative reasoning in light of other LOCA evaluations for this plant.
3.
The applicant will provide an acoustic emission leak detection capability for each of the six postulated break locations noted in Item 1 above. We require that final design of the system, including a description of the proposed acceptance standards and plant corrective action, be submitted for our approval three months prior to initial fuel loading and that the leak detection system be fully operational prior to exceeding 17. power.
The staff agreed that based upon acceptable responses to the above items, a normal ASME Secti;n XI inservice inspection frequency for the code weld areas, for each of the six postulated break locations, would be satisfactory pursuant to the baseline data and specific procedures for future examination.
In order that we may complete our review of this matter in a timely manner, we request that you provide a full and satisfactory response by March 12,1979.
If you have any questions regarding this matter, please contact us.
Sincerely, f.
Roger S. boyd, Di rec Division of Project Management Office of Nuclear Reactor Regulation ccs: See next pages
Mr. William 0. Parker, Jr.
FEB 9 G79 Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 cc: Mr. W. L. Porter Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Mr. R. S. Howard Power Systems Division Westinghouse Electri.. Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith EDS Nuclear Incorporated 220 Montgomery Street San Francisco, California 94104 Mr. J. E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President The Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.
Debevoise & Liberman 700 Shoreham Building 806 15th Street, N. W.
Washington, D. C.
20005 Shelley Blum, Esq.
418 Law Building 730 East Trade Street Charlotte, North Carolina 28202
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- r. William 0. Parker, Jr.
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cc: Robert M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Emmeth A. Luebke Atomic Safety ar.d Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. 0. Box 247 Bodega Bay, California 94923 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 U. S. Environmental Protection Agency ATTN: EIS Coordinator Region IV Office 345 Courtland Street, N. E.
Atlanta, Georgia 30308
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