ML19312C743
| ML19312C743 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/26/1967 |
| From: | Grimes B US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7912190954 | |
| Download: ML19312C743 (4) | |
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SUPPLEMENTAL' UNITED STATES GOVERNMENT fl(( CQpy ILemorandum TO Roger S. Boyd, Assistant Director DATE:)UU 2 0 lbO7 for Reactor Projects, DRL
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TERU: Charles G. Long, Chief,' RP3 #3, DRL
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- 3. Grimes, Reactor Project 3 ranch No. 3 # '/
/-- N Division of Reactor Licensing s*cJECT: STAFF MEETING APRIL 27, 1967, AND ACRS SUBCOMMITTEE MEETING, MAY 2, 1967, ON OCONEE NUCLEAR STATION (DUKE POWER COMPANY) DOCKET NOS. 50469/270/287 A.
Staff Meetin2 N
Cn April 27 and 23, 1967, a =eeting was held in the 3etheTda offices to discuss the Duke Power application for construction permits for reactors at its Oconee Nuclear Station, Ocence County, South Carolina.
Attendance at the =eeting included the following (a number of other tech-nical staff ne bers representing the applicant were also present):
DUKE 3&W W. S. Lee D. W. Montgomery L. C. Dail G. E. Kulynych E. C. Fiss R. E. Wascher W. H. Owen J. H. Taylor T. E. Wyke M. E. Sankovich W. H. Grigg T. Helm f
H. E. Flora Z. M. Schuler BECHTEL USAEC
?. R. Cassidy C. G. Long J. J. Tkacik
- 3. Grimes H. W. Wahl D. Sullivan F. Schauer i
R. Waterfield S. Pawlick4 M. Taylor j
R. Maccary i
Subjects discussed and salient points of information are su=marized below:
1 1.
Rod Drives - 25W =ade a precentation on the rack.and pinion
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drives now proposed to replace the nutating actuator drives, l
The nutating drives are being withdrawn, at least for these reactors, because 3&W has had trouble during the hot prototype 3
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Roger S. 3oyd tests with magnetic properties of.the materials at high te=peratures. Rod housings will be 304 stainless designed to ASME Section 3.
36W esti=ated that wear on the seal shaft would be small and could be detected by an inspection progra=.
2.
Instrumentation - D. Sullivan discussed the power /ficw'=oni-toriag circuits, instrument channel testing and containment isolition system.
The review in this area is not completed but there appear to be no =ajor areas which are unsatisfactory.
3.
Seis=ic Analysis - As a result of our discussions with Drs.
Newmark and Coulter we indicated to the applicant that the earthquake response spectrus chosen was not satisfactory (this was revised by A=endment 4).
A su==ary of the foun-dation investigation conducted for the dams was also re-quested.
It was stated that the intake canal dike would be of the same =aterials as the major dams but that the design was more conservative since the dam slopes were determined by the ability to mow the grass on them.
It was also indi-cated that the hydro equipnent and buildings were founded on the rock and would be Class I structures.
14.
Turbine Missile Analysis - The results of a revised analysis at 180% overspeed were presented.
The draft of the analysis has been reviewed at our request by J. Proctor of the Naval Ordnance Laboratory and'is satisfactory to him.
f 5.
Leakage Considerations - R. Maccary discussed the containment leakage proposal submitted by the applicant - it is acceptable
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to us.
The design of the penetrations were discussed and the applicant indicated that the penetration area would be strengthened to make it the strongest part of the piping and that pipe anchors would be installed on high energy (type 1) lines.
6.
Pri=ary and Secondary Systems - The applicant justified the Class C classification of the letdown cooler on the grounds that it was non-regenerative and therefore did not experience many ther=al transients (Westinghouse uses regenerative and specifies Class A) and they could be isolated if necessary.
The type of valve to be used on the secondary system which would serve as both a safety valve and as 25% bypass control.
was discussed (the applicant has since-decided to have.100%
safety valve capacity independent of the bypass valves).
O
Roger S. Boyd Inspectability of the primary vessel during its service life was discussed and the applicant indicated that a 42 inch space had been provided around the exterior of the vessel in case it should ever be necessary to conduct an inspection of the outer surface.
S. Pawlicki discussed neutron flux monitoring and calculations with the applicant.
This subject =ay be purpused on future applications but the design appears adequate by co=parison with other designs and because of the large safety factor applied in B&W's model.
Pawlicki also pointed out that recent woek =ay indicate that neutron irradiation =igh: affecr the low cycle fatigue life and gave them the reference.
7.
E=ergency Power and Water - The ability to handle an accident during hydro plant outages was generally discussed as was the ability to shut dcwn af ter a postulated da= failure. During infor ation discussions Mr. Lee and Mr. Owen of Duke Power pro-posed the installation of a 100 kv line which could be sepa-rated frc= the external grid and a turbine unit 30 =iles from the site which could run at a no-load conditiond during hydro outage.
This would also serve as a power source after da:
failure.
A detailed discussion of qualification of the hydro plants as redundant power sources was deferred to a special =eeting with D. Sullivan and R. Ferguson (May 3, 1967).
S.
Meteorology - R. Waterfield indicated our differences with the app'icant's accident =cteorology. We also indicated that the tornado design wind speed of 225 was not acceptable and that at least 300 =ph should be used.
9.
Engineered Safeguards - Core flooding tanks were discussed and a si:ua: ion in which a water leg could remain behind in the stea generator, : rap a steam bubble and prevent core - flooding was post-ula:ed. h*hether or no: :he stop valves _ on the core flooding tanks would be closed during operation was discussed.
The applicant indicated that they would not be closed if both flooding tanks were required to meet the design basis.
Pu=p seal failure during recirculation af ter an accident was discussed with respect to enviren= ental consequences.
Results of a study of filter heatup indicate that if a filter is isolated at peak heat load and no convection or radiation heat transfer is assu=ed, the ignition te=perature 'would not be reached for about S hours (for 4000 cf= fans). All heat could probably be trans-ferred by radiation and convection.
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