ML19220C137
| ML19220C137 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/03/1968 |
| From: | Racquel Powell US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904280285 | |
| Download: ML19220C137 (5) | |
Text
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UNITED STATES
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ATOMIC ENERGY COMMISSION
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Rcger S. Soyd, Assistant Director for Reacter Projects, DRL THRC-Rcbert L. Tedesco, Chief, RP3-2, DRL
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MINUTES CF TECHNICAL MEETING - OYSTER CREEK CNIT 2
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DOCKET No. 50-320 A techn:.ai caeting was held en August 27, 1968 with representatives of the Jersey Central Power and Lign: Ccepany (JC?LL), General Public Utilities (GP'J), the architect and engineer, Burns and Roe (3&R), the nuclear steam supplier, Babcock & %'Licox (35'll, Pickard and Lcwe Associates, Schupack Associates, consultants. Technical details were discussed conterning the containment structures, structural analysis and instru=entation. Those attending the =eeting are listed in Attach =ent I.
I.
Grouted Tendens Areas of concern regarding the use of pre-stressed ; routed tendens were. discussed. The applicant was asked to respend to four questions which RT feels =ust be answered in order that they can evaluate the acceptability of grouted tendons. These questions, 2.10 thru 2.13, are being processed for DRL concurrence and should be for= ally submitted to JC?&L by September 6,1968.
The applicant was requested to take a ec=parison, listing all the advantages and disadvantages of the grouted and greased tendcas.
RT will review the requested information when it is received fren JCP&L.
II. Liner Design The linar anchcrag design was discussed with respect to anchorage failure propagation. 3&R indicated its design analysis would consider protection against this code of failure.
The protection of the bottom of the liner from corrosion by ground water reaching the liner thru the concrete slab was discussed.
3&R described the water-proof design which would be used to protect the bottes of the concrete slab against water penetration.
It was indi-cated by 3&R that as a result of horings and geophysical studies at the site locaticn the concreta slac thickness has been increased free a 12 fcot thickness to 19 feat.
This change and the bases for the change would be included in the next amendment to the applicarica.
RT will review this design change information and the additicnal information requested concerning the liner design.
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Roger 3. Boyd September 3, 1968 III.
Large Centainment Penetrations B&R indicated the code SAMAS would be used in analyzing the large penetraticas. RT requested a description of the code and its capabilities. 3&R was requested to indicate what design te=petarures were to be used in determining the temperature gradient in the concrete adj acent to the penetraticus.
RT questions were informally given to the applicant.
RT will review the infor ation requested when received.
IV.
Ecuierent Sucoor*; (inside containment)
The RT questions concerning these =atters were discussed with the applicant.
RT will review information when received.
V.
Tornado Design The PSAR criteria for tornado design requiraments were reviewed.
RT questions were discussed with the applicant and DRL guidelines (RTM) were discussed.
Clarification of the design intent will b2 requested of the applicant concerning buildings other than the containment building.
71.
Seismic RT indicated to JC?L that the translation notion ef fects on masses was not included in PSAR analysis. 3&R indicated they would be doing the analysis and would include this addition notion ef fect.
RT questions concerning those matters were discussed with the applicant.
RT will review the requested information when received.
7II.
Iodine Dese Follcwing Maximun Hvoothetical Accidea_t_
The applicant was informed that preliminary cniculation using the present DRL =cdel to evaluate the containment building iodine rencval syste folicwing the XHA indicates the part 100 limit for the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose at the 14C0 fact exclusion radius is exceeded by a factor of approximately 1.6.
The results of the c.; calculations vould be discussed with the applican*
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- 'ere is a probles.
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Roger S. 3cyd September 3, 1969 VIII. Miscellaneous RT informally indicated to the applicant that additional information is requi d in'the following areas. A written request for this information should be subsitted to RP before September 13, 3 9C8.
1.
Environment Monitoring program 2.
Fish & Wildlife letter 3.
Dose calculations for steam line break with leakage from the pri=ary eystem 4
Tritius analy, sis. hcndling and discharge 5.
Isotopic content of plant effluent 6.
Liquid waste storage tank 7.
Waste gas tank rupture 8.
X/Q =cdel 9.
Rain-out Cold Shutdown with Less of Offsite Power The applicant indicated that the plant can be taken to a cold shutdown condition usitg enly emergency diesel pcwer. A request will be =ade to obtain a tabulation of the equipment load requirement.
Site Geochvsical Report JCP&L indicated this report is being reviewed and will be submitted in the next a=end=ent.
The applicant was requested to address the liquifaction phenecena and include any conclusions in this report.
Contain=ent and Coolinz Fan and Coils 3&R indicated that they did not intend to do any tests to determine the cooling capacity of the cooling coils with accident s team air =i> ;ure conditions. They felt that they could calculate the heat transfer coefficients with sufficient accuracy so that no test is required.
JCP&L indicated the only test they knew was being performed was a test to determine that the fan notor seals would not permit the accident steam water sixture to reach the fan motor.
RP will submit request for back-up data of bare cocling coils heat re: wal capability.
Fuel Shiocing 'ag The applicant was asked if they had considered an accident casulting from the spent fuel shipping cask falling into the spent fuel storage pool.
3&R indicated that if the cask were to fall into the storage pool it wculd go through the bottom of the pool.
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Roger S. Soyd Sept 2 ber 2, 1968 RP will check previous applications and request applicant to analyre consequences of this accident.
IX.
Instrumentatien A separate meeting was held with B&W and 3&R to discuss instrumenta-
- ion.
Areas of concern to DRL and the ACRS were reviewed as they affect this facility.
RT is requested to submit any request for additional information ccncerning instrumentatien =atters by September 13, 1963.
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- n. Powell Reactor Project 3 ranch 2 Division of Reactor Licensing Distribution: y d Suppl.
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DRL Reading RP3-2 Reading P. A. Morris F. Schroeder S. Levine D. Skovholt Branch Chiefs, DRL D.
Sullivan A. Gluck= ann G. Arndt C. J. Hale M. A. McCoy J. M Mcccugh W. Nischan R. Powell CO (2) m7 7 ', il b/
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ATTACHMENT #1 AITINDANCE OC-II AUC'J ST 2 7, 1968 TECE'iICAL EETING
.4EC - DRL General Public Utilici_es D.
F. Sullivan R. W.
Heward, Jr.
R. Powell A. Gluckiann Burns & Roe G. Arndt C. J. Hale J. C. Archer M. A. McCoy G. A. Harstead J. M. McGough R. J. Dobbs R. Tedesco P. P. DeRienzo JC?&L mm,+
ock 5 Wilcox 3i G. H. Ritter G. Ward W. A. Cobb Pickard & Lowe Assoc.
Schupack & Assoc.
K. Woodard M. Schupack e
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