ML20198F095
| ML20198F095 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 12/14/1973 |
| From: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0926, CON-WNP-926 NUDOCS 8605280411 | |
| Download: ML20198F095 (3) | |
Text
_
6b g
1419D pra Docket No. 50-460 V. A. Moore, Assistant Director for Light Water Reactors, Group 2, L REQUEST POR ADDITIONAL REACTOR PHYSICS INPORMATION Plant Name:
Washington Public Power Supply System, Unit 1 Licensing Stage:
CP Docket No.:
50-460 Responsible Branch LUR 2-3 and Project Manager:
T. Cox Requested Completion Date:
December 28, 1973 Applicant's Response Date necessary for Completion of Hext Action Planned:
As Soon As Possible Description of Response:
Answers to Attached Questions and Questions Submitted for Greenwood, Units 2 & 3 Review Status:
Awaiting Information
'Ibe first round reviews of the reactor physics aspects and the control rod ejection accident analysis of the WFPSS PSAR have been completed by the Core Performance Branch. Questions that arose during these reviews are attached. These are considered supplemental to the first round questions submitted for Creenwood, Units 2 & 3, which was the first 17 x 17 B&W design reviewed by the Core Performance Branch. This trans-mittal contains all Core Performance Branch input needed to meet the current Blue Book allestones.
Origina1 Signed d victor Stella Victor Stallo, Jr., Assistant Director for Reactor Safety Directorate of Licensing cc:
S. Hanauer J. Hendrie A. C&&mbusso W. Mcdonald D. F. Ross A. Schwencer i
E. Bailey T. Cox L. Kopp 8605280411 731214 T. Novak 00R ADOCK 0500 0
D. Fieno,
A CPB CPB CPB AD/*RS l'_[ 'c M. chattertom i
ont >
...g,...G rime s.....
....., x-mp.
L.,
.'.4'.2 z.
mmt
.FOPP:bj EBailey DFRoas VSt'ello L
12/ /73 12/@3_ _ _ _
om,,
12/l3/73,_
12h'/73 Form ATC-318 (Rev.9 53) AECM 0240 ese
.es--to-si ess-44s+7s
D f
UNITED STATES f
W/';Mf ATOMIC ENERGY COMMISSION
' b,W wasm NGToN. D.C. 20545 gr 14 T3 Docket No. 50-460 V. A. Moore, Assistant Director for Light Water Reactors, Group 2, L REQUEST FOR ADDITIONAL REACTOR PHYSICS INFORMATION Plant Name:
Washington Public Power Supply System, Unit 1 Licensing Stage:
CP Docket No.:
50-460 Responsible Branch LWR 2-3 and Project Manager:
T. Cox Requested Completion Date:
December 28, 1973 Applicant's Response Date Necessary for Completion of Next Action Planned:
As Soon As Possible Description of Response:
Answers to Attached Questions and Questions Submitted for Greenwood, Units 2 & 3 Revicw Status:
Awaiting Information The first round reviews of the reactor physics aspects and the control rod ejection accident analysis of the WPPSS PSAR have been completed by the Core Performance Branch. Questions that arose during these reviews are attached. These are considered supplemental to the first round questions submitted for Greenwood, Units 2 & 3, which was the first 17 x 17 B&W design reviewed by the Core Performance Branch. This trans-mittal contains all Core Performance Branch input needed to meet the current Blue Book milestones.
.W/;ff.,
,1(
(. c., - t Victor Stello, Jr., Assistant Director
Enclosure:
for Reactor Safety Questions Directorate of Licensing ec:
S. Hanauer J. Hendrie A. Giambusso W. Mcdonald f;
D. F. Ross A. Schwencer E. Bailey l
T. Cox i
L. Kopp i
T. Novak i
D. Fieno M. Chatterton B. Grimos S. Varga i
e REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO REACTOR PHYSICS ASPECTS WPPSS - 1 DOCKET NO. 50-460 NUCLEAR DESIGN 1.
Numerous parameters including reactivity coefficients are identical to those presented in previous SARs for the 15 x 15 design and have apparently not been recalculated for the 17 x 17 core. The Staff wouldliketohavetheparametervaluescorrespondingtothe1[x17 design at. soon as they are available.
2.
The number of control rod guide tubes per fuel assembly has increased from 16 to 24 for the 17 x 17 design signifying more control rods per control rod assembly.
In view of this, explain why the maximum stuck rod worth and the maximum ejected rod worth has decreased.
RCD EJECTION ACCIDENT 1.
Verify that the maximum reactor pressure during any portion of the assumed rod ejection accident will be less than the value that will cause stresses to exceed the " Emergency Condition" stress limits as defined in the AS:1E Nuclear Power Plant Components Code,Section III.
2.
The Staff has previously recommended that the radiological consequences of a rod ejection accident, in terms of the release of fission products from the secondary system, be evaluated with the assumption of a coincident loss of offsite power.
Is this assumption included in the dose results and if not, how does it affect the magnitude of the resulting doses?
. ~ _ - - - - -