ML19305A161
| ML19305A161 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/08/1978 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Hannon J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901040289 | |
| Download: ML19305A161 (3) | |
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UNITEO STATES 3h
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December 8,1978 Docket Nos. 50-325 and 50-324 MEMORANDUM FOR: Thomas A. Ippolito, Chief, ORB #3, D0R FROM:
John N. Hannon, Project Manager, ORB #3, DOR
Subject:
MEETING
SUMMARY
A meeting was held with representatives from CP&L, and their consultants on December 6,1978. The purpose of the meeting was to (1) review the data associated with the NDE results from inspections performed on the Brunswick Steam Electric Plant (BSEP) Unit I recirculation pump riser safe-ends, and (2) discuss the alternatives available for follow-up action to assure continued safe operation of the facility. A list of meeting attendees is attached as E,v:losure 1.
After evaluating the data presented by the licensee, the staff was unable to conclude that sufficient evidence had been presented to demonstrate whether or not the UT indications in the BSEP Unit 1 safe-ends were caused by stress corrosion cracking. The general consensus was that the UT indications in the BSEP safe-ends did not reprer.ent an immediate t9reat to the health and safety of the pubic, even as",uming the indi-cations were cracks. The licensee was requested to ',ubmit information documenting the basis for continued plant operation for the duration of the current cycle to January 13, 1979 for Unit 1 (cycle 1) under a working assumption that the indications are cracts.
The staff requested that this submittal include, as a minimum, the following information:
1.
A summary of the UT results including the basis for the licensee's conclusion that the indications do not represent cracks in.the pressure boundary and an estimate of the maximum crack sizes assuming that the indications are pressure boundary cracks.
2.
An analysis of the crevice region for all recirculation inlet safe ends showing the calculation of the General Electric Stress Rule Ir.dex for stress corrosion cracking.
(The analysis should include Nlpa uggon Oulfb) terms in the General Electric Stress Rule as g
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For a representative safe-end for which the ultrasonic examina-tions have shown positive indications, an analysis demonstrating the capability of this safe end to withstand the loads associated with normal operations and accident conditions, including a safe shutdown earthquake assuming the largest crack that could be postulated from the observed indications.
4.
A copy of the code stress analysis for the recirculation pump riser nozzle safe-ends.
In addition, the licensee was requested to submit a program well in advance of the January refueling date which would provide substantially higher con'idence as to whether or not the UT indications represent cracks in ne pressure boundary. The licensee was requested to provide an evaluation of the effectiveness and impact of a number of alternative programs to accomplish this.
Specific alternatives which the staff requested be discussed in the submittal were (1) removal and destructive examination of the safe-end with the most significant indications, (2) additional NDT (both UT and RT) with water removed from the safe-ends, (3) additional NDT with insertion into one or more pipes of a radiography source, and (4) additional frequent NDT with water in the pipes. The staff requested a target date for the first submittal of December 11, 1978 with the second submittal within about 20 days (January 1, 1979).
The licensee indicated plans to reinspect the Unit 1 safe-ends at this refueling outage but indicated that if no changes in the indications were observed, they would likely propose no additional inpsection until the next refueling outage.
B. Grimes indicated that high priority would be given the review of the submittals so that a timely decision could be made on any required actions that may impact the refueling outage.
W John N. Hannon, Project Manager Operating Reactors Bearch #3 Division of Operating Reactors
Enclosure:
Attendees
e ENCLOSURE 1 Attendance List CP&L NRC D. L. Bensinger B. K. Grimes
- S. P. Grant J. M. Hannon E. L Betz R. W. Klecker H. R. Banks W. S. Hazelton E. A. Bishop T. A. Ippolito C. R. Osman J. R. Fair K. R. Wichman R. Johnson NUTECH V. S. Noonan D. H. Danielson P. A. Riccardella T. E. Conlon C. Y. Cheng J. J. Blake IOWA ELECTRIC
.C..C. Williams W..J. Collins P. D. Ward LMT INC.
T. Lambert G.E.
A. R. McIlree H. T. Watawabe K. A. Hill
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Mr. J. A. Jones Executive Vice President Carolina Power & Light Company 336 Fayettevilel Street Raleigh, North Carolina 27602 Richard E. Jones, Esquire Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 George F. Trowbridge, Esquire Shaw, Pittman, Potts & Trowbridge 1800 M Street, NW Washington, D. C.
20036 John J. Burney, Jr., Esquire Burney, Burney, Sperry & Barefoot 110 North Fifth Avenue Wilmington, North Carolina 28401 Southport - Brunswick County Library 109 W. Moore Street Southport, North Carolina 28461 Docket File V. Noonan NRC PDR P. Check Local PDR G. Lainas NRR Rdg
- 8. Grimes OR3#3 Rd; D. Davis E. G. Case Project Manager V. Stello OELD H. Denton 0I&E (3)
D. Eisenhut S. Sheppard A. Schwencer NRC Participants D. Ziemann RS (16)
T. Ippolito E
R. Reid J. R. Buchanan J. Miller i
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