ML20072R736
| ML20072R736 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/01/1983 |
| From: | Jeffrey Riley CAROLINA ENVIRONMENTAL STUDY GROUP |
| To: | DUKE POWER CO., NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| References | |
| NUDOCS 8304060293 | |
| Download: ML20072R736 (4) | |
Text
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April 1, 1983 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION T@D '
I!EFORE THE ATOMIC SAFETY AND LICENSI BOARD Ahl~5 pio;;9 in the Matter of
)
)
)
Docket'Nos. 50.-413
)
"50-414 (Catawba Nuclear Station,
)
Units 1 and 2)
)
CESG8S DISCOVERY AND DOCUMENT PRUDUCTION REQUESTS TO NRC STAFF AND TO APPLICANT RE CESG CONTENTION 18 AND RE DES CONTENTION 17 CESG submits herewith discovery questions and document pro-duction requests to Staff and Applicant on the subject contentions.
CESG Corttention 16 1.
Cracks have reportedly been found in used reactor welds by ultrasonic testing, including an Uconee reactor.
These reactors have presumably not been submitted to stress under other than mechanism do you account for the formation of craEkI.
By what ductile conditions, i.e. at temperatures above RT under these conditions?
2.
Under what conditions would you expect these cracks to grow?
Specifically, relate crack growth to stress at temperatuges of 100 F; of nogmally encountered both above and below a RTIf you are not in a position to a 50 F.
explain why it is not of concern.
3 What is the effect of stress fatigue, whether isothermal tensile, temperature gradient-induced in the absence of applied Please quantitate your response for a) routinely encou M r?
stress, or a combination of applied and thermal, on RT ed gradients and stress levels in a reactor and b) under the rapid rate of cooldown encountered in a large break LOCA.
h.
The values of RT required under 100FR Part 50 Appendix G Ill A and B and Appe b Ix H,II and III are performed on coupons.
What plates, welds, welding materials, etc. are exposed?
How many samples are there of estch type of. material?
"E E n..5 Pursuant to 4, foregoing, Is the neutron fluence of the coupons identical?
How does it relate to the neutron fluence hg@
of the reactor?
n 6.
Pursuant to 4., foregoing, For the core to be employed at Catawba, diagram relative neutron fluences around the beltline.
8<
7 How many heating and cooling cycles are anticipated for the lifetime of the Catawba reactors?
g a.o 8.
Does RT change with the fatigue history of reactor materials?
D NDT
a
, 9.
If the answer to 8 is affirmative, provide quantitative estimates of the differences between reactor materials and corresponding coupons at 25, 50, 75 and 100% of estimated reactor operating life.
10.
Why are Charpy speciments V notched?
11.
Will a notched specimen fail unde'r tensile stress levels that an unnotched specimen of the same material and minimum cross-sectional area will withstand?
12.
Will a notch result in failure of a specimen in a ductile state at a lower level of stress than an unnotched specimen of the same effective minimum cross-sectional area?
Is the same true of a crack?
13 What is your underetanding of the mechanism of crack growth?
14 What is your understanding of mechanisms of crack propagation to failure?
DES Contention 17 I
1.
Please provide the Sandia study comparing the specific rates of injury and/or mortality for serious accidents at the McGuire and Catawba plant sites.
This study was apparently the basis for an article originally published in the Washington Fost, Nov. 1, 1902.
Tne weather conditions assumed are the matter of interest.
(Addressed to NRC staff only.)
l 2.
Provide the specific values used in the accident consideration l
of DES 5 9 4 5. (Staff only.)
3 Provide the specific weather parameters used in considering serious accidents, p. 5-37 of the DES.
(Staff only.)
4 Provide a definition of the plume assumed in both DBA's and serious accidents showing the elevation of maximum intensity as a function of distance from the source and the corresponding level of radiation at ground level.
(Staff only.)
5 Was precipitation assumed in the several dosage models?
If not, what would the effect be of a) mist, b) light rainfall, c) moderate rainfall, d) heavy rainfall with r.aspective depositions or u.05,.25, 75, and 2 inches?
(Staff only.-).
6.
Noting the information in Table 5 10 in the DES, what composition What total mass?
'and size distribution was assumed for particulates?
(Staff only.)
7 What people-sheltering and evacuation assumptions were made for both DBA and serious accident estimates?
(Staff only.)
6.
What time of year would correspond to the conditions used?
What time of day did the release occur?
(Staff only.)
l l
l
. 9 Please provide, as they become available, the upper bound calculations referred to on DES p. 5-35, providing source term and assumptions entering the calculations.
(Staff only.)
10.
Prior to the event, what were the estimated probabilities by Stafrand/or consultants of 1) the TM1-2 accident scenario, including multiple failures (if several estimates were made, provide dates for each), 2) the Browns Ferry fire, etc., 3) the Fermi-1 partial meltdown, 4; the uinna steam generator release accident.
(Staff only.)
11.
Please provide the detailed analys'is and sets of assumptions employed in the severe accident calculations described in DES pp.
5-37 to 36. (staff only.)
has ectfully submitted, l bhui Jesse L. Miley for CESG m
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l
r-s UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION C:' ;.
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
~
'83 Apg -5 gg t9
' In the Matter of
)
bb
^
, DUKE POWER COMPANY, et al.,
)
Docket No.
)
50-414 (Catawba Nuclear Station,
)
Units 1.and 2)
)
AFFIRMATION OF SERVICE i hereuy afrirm that copies of CESu'S DISCOVERY AND DOCUMENT PRODUC-TION REQUESYS TO NRC STAFF AND TO APPLICANT RE CESG CONTENTION 16 AND RE. DES CONTENTION 17 in the above captioned matter have been served s
on the parties 'as listed in the U.S. mail this lat day of April,1983 James L. Kelley, Chairman Michael McGarry, III, Esq.
Atomic Safety & Licensing Board Debevoise and Liberman (M
U.S. Nuclear Regulatory Commission 1200 17th Street, N.W.
li Washington, D.C.
20555 Washington, D.C.
20036 i.
Dr. Dixon Callihan William L. Porter, Esq.
Union Carbide' Corporation
- Albert V. Carr, Esq.
t Duke Power Company P.O. Box Y' Oak Ridge, Tennessee P.O. Box 33189 Charlotte, NC 282h2 l
b.
o 6
- George E. Johnson, Esq.
l Sunriver, Oregon 97701 Counsel for NRC Staff U.S. Nuclear Regulatory Commission Atomic Safety & Licensing : Appeal Panel Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Washington, D.C.
20555.
. Robert Guild. Esq.
Attorney for the Palmetto Allianc'e P. O. Box 12097 Atomic Safety & Licensing Board Panel
' Charleston, South Carolina 29412
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U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Palmetto Alliance 2135% Devine Street.
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Docketing and Service Sectio 6 Columbia, SC 29205-U.S. Nuclear Regulatory Commission Washi'ngton, D.C.
20555 -
Henry Presler, Chairman Charlotte Meck. Eny't'l. Coalition Richard P. Wilson, Esq.
942 Henley Place Assistant Attorney General Charlotte, NC 28207 2600 Bull Street Col'umbia, SC 29201
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u-J Q. /
.m Jes'se L. Riley for SG
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