ML20125A506
| ML20125A506 | |
| Person / Time | |
|---|---|
| Site: | Monticello |
| Issue date: | 08/19/1975 |
| From: | Maccary R Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9212080372 | |
| Download: ML20125A506 (2) | |
Text
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AUG 19 U75 i
Earl R. Goller, Assistant Director for Operating Baaetore Division of Raastor u aanaing
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MONTICEL1h NUCLEAR GENERATING 1"LANT - RE REQUEST - REVIEW PROPOSED CHANGE IN NONT i
ICAL ASSISTANCE LIMITATIONS FOR OPERATION.- (TAR-1760) i URE-TEMPERAltTRE i
Plant Name Monticello l
Docket Number: 50-263 Responsible Branch and Project Manager:
j Raquested Completion Date:
ORB-2; B. Buckley August 20, 1975 i
Technical Baview Branch Involved:
Description of Raquest:
Naterials Engineering Branch Review Proposed Change in Monticello's Pressure-Temperature Limitation for Operation Review Status: Complete
)
Section of the Meterials Engineering Branch haIn re
, the Hateriale Performance
{
and core operation proposed by Northern States Ppre
, heatup, cooldown Amendment Request dated July 1, 1975.
ower Company in License l
The current pressure-temperature limitations f i
are based on HDT temperature plus 60*F and do notor operation of Montice requirements of Appendia G,10 CFR Part 50, " Fracture T comply _with all the Raquirements."
based on the requirements of Appendix GThe proposed pressure-t oughness l
ASME Code Section III. In calculations'to'determina these limits the. 10 are reference temperature, RT this vessel was designed and manufactured (1965 mente of the Code to which 1966 Addenda).
reference temperature used was' the MDT temperatureWh j
' j NDT-temperature was not known, the reference't n, the
.- Where-the dropweight.-
temperature at which 30 ft-lb of energy wa emperature used was-the of reported Charpy V notch test data.
s expected to occur on the basis the vessel purchase specification for anyfrom the co j
emperature permitted by material is +40'F and this value is used for the'RTPressure boundary vessel l
certified test results.-
in lieu of Predicted changes-in MDT temperature as a fu
-j are given in Figure 3.6.1.
nction of neutron flancos.
This curve is based en 35 data points from i
n
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9212000372 750819 PDR ADOCK 05000263.
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Karl R. Coller
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tests on SA 302B and SA 533B steel. Itag$eeswithourpredictionfor SA 5335 steel with 0.15% copper. The percent of copper in the Monticello reactor vessel plate material from the beltline region has not been i
j determined.
I i'
Calculations indicate that the maximum neutron fluence on the vessel wall is presently about 2 x 1017 n/cm2 and will be approximately 2.2 x 10 d n/cm2 at and of life.
The material surveillance program for Monticello consists of three sets of specimens representing the vessel base, weld and HAZ material and conforms to ASTM E 185-66. Northern States Power Company proposes to change the withdrawal schedule to withdraw samples at 1/4 and 3/4 of i
service life.
i We conclude that the proposed temperature-pressure limits for operation of Monticello comply with the requirements of Appendix G, 10 CFR Part 50 l
and are acceptable until data from the first material surveillance-capsule are obtained and reported to the NRC. We recommend that the P osphorus and copper content of vessel plate and weld material in the-h vessel core region be determined at that time, and the results included in the report. We also conclude that the proposed changes in surveil-lance requirements, specifications 4.5.A and B, are acceptable.
Details of our evaluation including calculations for operating limits are available in MTEB Branch files.
pgghialdruediF Lp.m. usum R. R. Maccary, Assistant Director for Engineering Division of Technical Review l
Office of Nuclear Reactor Regulation ec:
R. E. Heineman, TR DISTRIBUTION:
R. S. Boyd, RL Docket File (50-263)
W. G. Mcdonald, MIPC
-NRR Reading File D. L. Zimmann, RL MTEB Reading File B. Buckley, RL RE 1.1-1 S. S. Pawlicki, TR R. M. Gustafson, TR U. Potapovs, TR
-W. S. Baselton, TR K. G. Hoge, TR Materials Performance Section, TR o,, e >
TR:MTEB K
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87/d. f./,/75 8/a/75 8/te/75 8/18/75 onre >
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Forum ABC.318 (Rev. 9 5)) AECM 0240 W u. s. soVERNMENT PRINTING OFFIC E31974 326-104
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