ML19220B767
| ML19220B767 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/23/1968 |
| From: | Racquel Powell US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904270308 | |
| Download: ML19220B767 (8) | |
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..a Eoger C. Eoyd, Assistant Directer for Reactor Projects Division cf Reactor Licenaine THRU:
R. L. Ie d e s co, Chic f, RP 3-2, OE'.
MI iU ES OF G~2iERAL I:iFDP.".ATIO:i MEETI:iG - CYSTE2 C?.~~? L".i1T 2 -
Doc nT :i0. 50-320 A neeting was held with representatives of the Jersey Central Nuer and Light Conpany (JC?&L), General Public Utilitien (C'"J), 3urna &
Roe (3&R), architect and engineer, Babcock & Wilcox (3&*;*), T R Associates, and Pickard & Love Associates, consultants, en Auzust 16, 1963, to discuss general areas of the PSAR. Those attending tne neeting are listed in Attacncent A.
The following are the areas which were discussed:
1.
Quality Control & Assurance The applicant was expected to give a presentatien of its quality control and assurance progra:s in greater detail than was discussed in the PSAR. Eevever, due to a misunders tanding, it did not have a presentation prepared.
JCP&L indicated it would rely upon Burns & Roe to supply addi-tienal nanpower and expertise to supplenent its evn staff to inplenent the quality contcol and assurance progran. Review of all B&W and sc=e 3&R specifications and drawings vill be peric=ed by MPR Associates. JC75L will reviev and approve 35R drawings and specifications.
It was indicated by B&W that electro-slag velding sould be used in febrication of scue of the pressure vessels. B&W will be requested to submit a list of all pressure vessels fabricated using the electro-slag veld technique.
DRL questions vill be subnitted to request additional information conceming the organization plan to be used in the quality centrol and assurance progra=.
2.
Centrol Red Drives 7 9 0 4 ~')7 0 30 <T The control rod drive R&D and life testint. ku keen c-leted.
1 A topical report en the results of these tests vil.1 be subnitted.
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Tests performed at temperature and pressure with 150" of worst acc::ulative tolerances as misalignment resulted in no chance in ts: rod drop ti=e.
The life test was made trith 100~ wors t accu =ulative tolerance as nisaliga:.ent.
'"he drive pac'me la cacable of applyin;; a force of 800 lbs, to insert a stuc'.s rod.
All drive pace.a;es are autcratically driven in en a scran condition.
Attachmenta 3 and C show the control red guide assembly and control rod asse:bly. 3&W indicated they aad no plans to do tests si:ulating blowdevn forces en their full size control rod =ock-up.
Report will be reviewed when received.
3.
R&D Status 3&W reviewed the R&D progra=s and gave the folleving status and estimated repcrt dates.
a.
Centrol Rod Drive - cc=oleted, report to be submitted (August 1968) b.
Steam Generator Test (blevdown) - completed, report to be submitted (early 1969) c.
Thermal & Eydraulic Design Vent valve test to be co=pleted by Dece=ber 1968.
Sundle test vill not be ccupleted for this appli-cation. (late 1969)
The W-3 correlatien vill be relied uoon.
d.
31ovdevn Force en Core internals Analysis is continuing to develop correli.cion with I.o f t tes ts.
(July 1909) e.
In-core Detectors Life testing continuing at Big Rock Point and B&W reactor.
f.
Cladding Test (late 1969)
Potential mechanisms of failure - effort is centinuine.
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Che=ical Spray - continuing (earl r 1969) h.
Xenon oscillation (late 1969) j
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Roger S. 3cvd AUC 2 0 I333 cesigners have assuned they would have oscillations and indicated how they would control the oscillations. 3&W atated that if they do have xenon oscillations, they would use partial length rods to control the oscillations and the partial length rods would be subst1*.uted for standard rods since their design tas excess centrol mar-gins. Questions vill be developed to get ce=nitment from applicant of design intent.
1.
Fuel Burn-up (March 1969)
M J intends to support the 55000 %d/T barn-up ca: ability using analytical technicue only (no in-core test).
J.
Grouted Tendon (3&R)
(Cctober 1963)
The Phase III of the grouted tendon test program is to start the week of Septenber 1,1968.
Dr.L was invited to obsem the stressing and grouting operations.
4.
Site lhe results of the latest cite flooding analvsis are cceplete end a report will be subnitted in several weeks. This latest analysis indicates no sienificant chanee in the =axinun flood height other than reported in the PSAR.
Soil borin ;s at the site location and a geophysical report vill be cempleted for subninston in Septenher 1968.
Effect on Cnit 2 of missiles generated by Unit 1 vill be cor -
sidered by JC?&L. This would include Unit 1 generator =issile a: d Unit 1 ats -k missile.
JCP&L indicated it has ccusidered the effect of Unit 2 construc-tion on Unit 1 and fences, locked doors plus additicoal radiation nonitors vill be a= ployed as safeguards durine this period.
Evacuation plans vill include consideration of the Unit 2 con-struction force. No blasting is anticipated.
5.
Shared racilities JCP&L indicated that Unit 2 vill have its own fire protection system.
JC?&L is still studying whether Unit 2 vill share the Unit 1
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Fuel Storare Pool JCP&L indicated the fuel storage pool cover described in the PSAR would not be used.
It indicated the ec,ver had been designed to reduce the ventilation requirenent for the storate pool roon.
'Je vill review this aspect further.
7.
Tornado Desi n D.e applicant's design criteria for tornado crotection of :.11 critical structures and components =ust be clarified. The present criteria are pri=arily directed at containment only.
8.
S=ergency 7an Coolers The applicant does not intend to test the cooline capabilit" of the escrgency fa. coolers under simulated accident cenditiens.
Its position see=a to be that the performance is well known and analytical methods, rather than testinr, is only reautred.
We vill continue our review of this area in detail.
9.
Cool-devn Cacability The applicant stated that the plant can be tooled down with onsite power although the electrical lead analysis does not include this capability.
i.'e vill request such a load analvsis.
We vill also request an analysis sheving that sufficient condensate storage capacity is provided to allo i an crderl-cooldown of the plant follevine a loss of offsite oever.
10.
Automatic Dissatch Syst s There was some question as to whether the plant vill be cperated by an automatic dispatch system. The applicant vill clarify this matter.
11.
Miscellaneous Several of the design criteria were discussed for clarification of the design intent. A technical Meting vill be scheduled to permit Reactor Technology to discuss details of desien which are of current concern for review of this facility.
3&W indicated they would review all reactor building isolatten valve require =ents with regard to the specification of clesine time. De criteria were not discussed in the PSA?..
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2 3 IE53 Roger S. 3cyd The 3&W design criteria for the ICCS will limit the maxinun fuel clad temperat tre to less than 2300*r for an r size break in the primarv syster. Tne codes and assunatiens rresentiv used by SL' to analyze reactor and fuel raranctcra durine bicwdown are not able to ana.17:e effects of break size belo" 0.4 ft2 withcut changing the blowdoen model presently used.
The Unit 2 design is described in the PSAR as bein: capable of going fro = 100; to 15 power level on loss of lead. JC?5L indicated this transient would not be tested since no credit has been taken for this transient capability with regard to analysis of the loss of offsite electrical rewer accident.
This transient will be reviewed only as a source of radioactive release and its effect on public safety.
Ravacnd R. Pcwell Reactor Project Branch 2 Division of Reactor Licensine Attachnents:
As stated above (3) cc:
P. A. Morris F. Schroeder S. Levine 3 ranch Chiefs, PJ Attendees CO (2)
Dis trib ution:
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