ML20125A506: Difference between revisions

From kanterella
Jump to navigation Jump to search
VisualWikitext
StriderTol Bot insert
 
StriderTol Bot change
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:_y.._                      _ , _ . _ _ _ . _ . _                                                    _ . _ _ _ . . _ _ . _ _                      _ _ _ . _ . _                _ _ _ _ . _ _                _ _ _ _ _ _
{{#Wiki_filter:_y.._
4
4 i
                                                                                                                          ..                                                                                                      i l,
l 1
1 AUG 19 U75 i                                                                                                                                                                                                     .
AUG 19 U75 i
Earl R. Goller, Assistant Director
Earl R. Goller, Assistant Director for Operating Baaetore Division of Raastor u aanaing
                    ";                                                    for Operating Baaetore                                                 '
(
(
Division of Raastor u aanaing                                                                                                                                ,
MONTICEL1h NUCLEAR GENERATING 1"LANT - RE REQUEST - REVIEW PROPOSED CHANGE IN NONT i
i                        '
ICAL ASSISTANCE LIMITATIONS FOR OPERATION.- (TAR-1760) i URE-TEMPERAltTRE i
MONTICEL1h NUCLEAR GENERATING                                                                                                         1"LANT - RE i                                         REQUEST LIMITATIONS FOR OPERATION.- (TAR-1760)               -      REVIEW      PROPOSED                              CHANGE ICAL ASSISTANCE URE-TEMPERAltTRE IN NONT i
Plant Name Monticello l
Plant Name                               Monticello l                                         Docket Number: 50-263 j                                          Responsible Branch and Project Manager:
Docket Number: 50-263 Responsible Branch and Project Manager:
Raquested Completion Date:                                                       ORB-2; B. Buckley i
j Raquested Completion Date:
August 20, 1975 Technical Baview Description                         of Raquest:            Branch Involved:
ORB-2; B. Buckley August 20, 1975 i
Naterials Engineering Branch Review Proposed Change in Monticello's Review Status: Complete Pressure-Temperature Limitation for Operation
Technical Baview Branch Involved:
!                )
Description of Raquest:
{                                          Section of the Meterials Engineering                                                                   , the HaterialeBranch      PerformancehaIn re and core operation proposed by Northern Amendment Request dated July 1, 1975.
Naterials Engineering Branch Review Proposed Change in Monticello's Pressure-Temperature Limitation for Operation Review Status: Complete
                                                                                                                                                                            , heatup, cooldown              States Ppre ower Company in License l
)
i The current pressure-temperature limitations f                             .
Section of the Meterials Engineering Branch haIn re
are based on HDT temperature plus 60*F and do notor operation of Montice requirements Raquirements."                                        of Appendia G,10 CFR Part                             comply 50, "_with Fracture    all the T
, the Hateriale Performance
              !                                                                                                                                                              oughness l                                            based on the requirements of Appendix GThe proposed                                                                                           are  pressure-t ASME Code Section III.
{
reference temperature, RTIn                                            calculations'to'determina these limits the. 10 j
and core operation proposed by Northern States Ppre
this vessel was designed and 1966 Addenda).                                                                                            mente manufactured of the Code to which (1965
, heatup, cooldown Amendment Request dated July 1, 1975.
      'j reference temperature used was' the MDT                                                                                         n, the temperatureWh NDT-temperature was not known, the reference't                                                               .- Where-the dropweight.-
ower Company in License l
temperature at which 30 ft-lb of energy wa emperature used was-the
The current pressure-temperature limitations f i
        !                                              of reported Charpy V notch test data.                                                   s expected to occur on the basis j                                              the vessel purchase specification                                                     vessel emperature permitted by for anyfrom the co l                                              material certified test                  is +40'F     results.-      and this value is used for the'RTPressure boundary
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."
                                                                                                                                                                      # in lieu of
based on the requirements of Appendix GThe proposed pressure-t oughness l
    -j                                             Predicted are         given inchanges-in         Figure 3.6.1.MDT temperature as a fu nction of neutron flancos.
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).
This curve is based en 35 data points from n                       i
reference temperature used was' the MDT temperatureWh j
                                                                                                                                                                \
' j NDT-temperature was not known, the reference't n, the
(                                                             ,
.- Where-the dropweight.-
9212000372 750819                                                                                                                                                                 '
temperature at which 30 ft-lb of energy wa emperature used was-the of reported Charpy V notch test data.
PDR               ADOCK 05000263.
s expected to occur on the basis the vessel purchase specification for anyfrom the co j
                                            .p                                                           PDR
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
\\
(
9212000372 750819 PDR ADOCK 05000263.
.p PDR


  ~*O
~*O c
  !                                                                              c Karl R. Coller                               .         [
Karl R. Coller
k
. [
:                                                                                D tests on SA 302B and SA 533B steel. Itag$eeswithourpredictionfor
k D
:                  SA 5335 steel with 0.15% copper. The percent of copper in the Monticello i                  reactor vessel plate material from the beltline region has not been
tests on SA 302B and SA 533B steel. Itag$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.
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.
I i'
  !                  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.
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.
i
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
    !                  We conclude that the proposed temperature-pressure limits for operation
service life.
:                  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 Ph osphorus and copper content of vessel plate and weld material in the-vessel core region be determined at that time, and the results included in the report. We also conclude that the proposed changes in surveil-                                               ,
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
lance requirements, specifications 4.5.A and B, are acceptable.
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.
Details of our evaluation including calculations for operating limits are available in MTEB Branch files.
,                                                                                    pgghialdruediF Lp.m. usum             .
pgghialdruediF Lp.m. usum R. R. Maccary, Assistant Director for Engineering Division of Technical Review l
R. R. Maccary, Assistant Director for Engineering
Office of Nuclear Reactor Regulation ec:
    ,                                                                  Division of Technical Review
R. E. Heineman, TR DISTRIBUTION:
,    l                                                                  Office of Nuclear Reactor Regulation ec:     R. E. Heineman, TR                       DISTRIBUTION:
R. S. Boyd, RL Docket File (50-263)
R. S. Boyd, RL                           Docket File (50-263)
W. G. Mcdonald, MIPC
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
-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:   F       TR MT.             TR:MTEB                   :
-W. S. Baselton, TR K. G. Hoge, TR Materials Performance Section, TR o,, e >
                  .w...,        K      a            2    on      ,
TR: F TR MT.
SSPa                      la        ry onre >    8/18/75        87/d. f./,/75       8/a/75
TR:MTEB K
                                                                . .,1/
a 2
8/te/75
on SSPa la ry
                                                                                        . _ z,. 9..
.w...,
Forum ABC.318 (Rev. 9 5)) AECM 0240               W u. s. soVERNMENT PRINTING OFFIC E31974 326-104
87/d. f./,/75 8/a/75 8/te/75 8/18/75 onre >
                                                                                                                                          ,}}
..,1/
. _ z,. 9..
Forum ABC.318 (Rev. 9 5)) AECM 0240 W u. s. soVERNMENT PRINTING OFFIC E31974 326-104
,}}

Latest revision as of 21:06, 12 December 2024

Responds to Technical Assistance Request for Review of Proposed Change in Plant pressure-temp Limitations for Operation
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)
v • d • e


Text

_y.._

4 i

l 1

AUG 19 U75 i

Earl R. Goller, Assistant Director for Operating Baaetore Division of Raastor u aanaing

(

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

\\

(

9212000372 750819 PDR ADOCK 05000263.

.p PDR

~*O c

Karl R. Coller

. [

k D

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: F TR MT.

TR:MTEB K

a 2

on SSPa la ry

.w...,

87/d. f./,/75 8/a/75 8/te/75 8/18/75 onre >

..,1/

. _ z,. 9..

Forum ABC.318 (Rev. 9 5)) AECM 0240 W u. s. soVERNMENT PRINTING OFFIC E31974 326-104

,

Retrieved from "https://kanterella.com/w/index.php?title=ML20125A506&oldid=4281092"