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| document type = GENERAL EXTERNAL TECHNICAL REPORTS, TEXT-SAFETY REPORT
| document type = GENERAL EXTERNAL TECHNICAL REPORTS, TEXT-SAFETY REPORT
| page count = 3
| page count = 3
| project =
| stage = Request
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=Text=
=Text=
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{{#Wiki_filter:r1 l
c    .
l            a. Moderator Temperature Coefficient (ag)
Calculations of as are performed using the methods described in Section 2.      Cycle specific calculations for this accident are made at unrodded full power.
: b. Doppler Temperature Coefficient (a o)
Calculations of no are performed in accordance with the procedure described in Section 2.
l
: c. Boron Concentration Reactivity Coefficient (a s)
Calculations      of as  are  performed        using        methods described in Section 2.      Cycle specific calculations for this accident are made at unrodded full power.
: d.      Shutdown Margin (SDM)
The shutdown margin will be calculated and compared with the limiting assumptions used in the safety analysis using the methods described in Section 2.0.
: e. Nuclear Enthalpy Rise Hot Channel Factor (Fan)
The maximum core Fan is assumed to remain within the current    limits  as  defined    in        the        Technical Specifications for allowable combinations of axial offset and power level.        For Prairie Island,                  the continuous surveillance of the power distribution is accomplished with the excore detectors using the Exxon PDC-iia
* scheme.
3.5.5 Reload Safety Evaluations All the cycle specific parameters discussed above are adjusted to include model reliability factors, RF i, and biases, B. 1  These results are then compared to the bounding
;            values assumed in the safety analysis.          The cycle specific parameters are acceptable if the following inequalities are met:
(
l 9906290199 990623 PDR  ADOCK 05 P
Page 71 of 298 Copyright o 1999 by Northem States Power
 
c      ,.
CYCLE SPECIFIC PARAMETERS        SAFETY ANALYSIS PARAMETERS i
: a. ax + RFu + Bn              5 cts (least negative bounding value)
: b. n o* (1 - RFo)              s ao (least negative bounding value)
: c. a *s (1 + RFa) * (1 + Bs)  2 as (most negative bounding value)
: d. Shutdown Margin            2 Shutdown Margin (bounding)
: e.  ( Faa+RFraa+ Bran) * (1+T) s Fan (Technical Specifications) l l
l l
Page 72 of 298 Copyright c 1999 by Northern States Power
 
F .. . . . .
l            .o    o l
l                                                                                                        l i                                                                                                      i l                                                                                                      )
l      APPENDIX H 1
H.1  Changes Made In Revision 7 To This Report The  format  of  this  document  has  changed        slightly        between Revisions 6 and 7.        Most of this was due to the use of a                            i different word processor which reformatted the entire document.                          l For reference, alterations made in Revision 7 are summarized                            I below.
Rev. 6 Page    Rev. 7 Page  Description of Change Number (s)    Number (s) 1              1*            Revision number and date were updated.
2,3            2*,3*        Margins were adjusted.
4-12          4-12*        Provided additional sections in Table of                            l Contents, adjusted titles of various figures (but not the actual figures).                                  j 13-14          13-14        Text was added to describe the addition of Appendix G.                                                      J 47            49            Changed text to show VIPRE is used rather than COBRA.
{
l l      50            52            The    equation    for    Moderator          Temperature        j Coefficient    was    corrected.              An    error      j introduced in Rev. 6 in the inequality for                      )
excore tilt was also corrected.                                  j 66, 67        69, 70*      Corrected the character for delta in the                          )
text.'    Text was    added to describe the l
addition of Appendix G.
68            71, 72        Clarification of shutdown margin.                                ,
84, 97,        88, 101,      Provided    additional    information            for      the  l 133, 145      138, 150      Doppler Coefficient.
131            136          Corrected number of pumps assumed to trip in each figure.
133, 145      138, 150      Added Shutdown Margin-to the Cycle Specific Parameters list and text describing it.
155            160          Correct typo on pressure at which steamline l
break occurs.
157            163          Pressure under (e) is corrected.
188            194          The    equati.ns    for    pere    and      Aputer were l                                                                                                    l corrected.
I      200            206          The    equation      for      Boron          Reactivity Coefficient was corrected.
257            264*          Corrected the units in two columns.
263            270*          Changed f(A) and A to f(AI)and AT.                              [
n/a            293-298      Added Appendices G and H.
various        various*      Corrected spelling and grammar, added spaces to separate words, corrected subject / verb                      l agreement, etc.
* No revision bars are provided for spelling and grammar corrections or text format changes.                                                            ,
i Page 298 of 298  a Copyright 81999 by Northem States Power 1
[}}

Latest revision as of 05:44, 9 December 2021

Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units
ML20196F408
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/23/1999
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20196F394 List:
References
NSPNAD-8102, NSPNAD-8102-R07, NSPNAD-8102-R7, NUDOCS 9906290199
Download: ML20196F408 (3)
v • d • e


Text

r1 l

c .

l a. Moderator Temperature Coefficient (ag)

Calculations of as are performed using the methods described in Section 2. Cycle specific calculations for this accident are made at unrodded full power.

b. Doppler Temperature Coefficient (a o)

Calculations of no are performed in accordance with the procedure described in Section 2.

l

c. Boron Concentration Reactivity Coefficient (a s)

Calculations of as are performed using methods described in Section 2. Cycle specific calculations for this accident are made at unrodded full power.

d. Shutdown Margin (SDM)

The shutdown margin will be calculated and compared with the limiting assumptions used in the safety analysis using the methods described in Section 2.0.

e. Nuclear Enthalpy Rise Hot Channel Factor (Fan)

The maximum core Fan is assumed to remain within the current limits as defined in the Technical Specifications for allowable combinations of axial offset and power level. For Prairie Island, the continuous surveillance of the power distribution is accomplished with the excore detectors using the Exxon PDC-iia

  • scheme.

3.5.5 Reload Safety Evaluations All the cycle specific parameters discussed above are adjusted to include model reliability factors, RF i, and biases, B. 1 These results are then compared to the bounding

values assumed in the safety analysis. The cycle specific parameters are acceptable if the following inequalities are met

(

l 9906290199 990623 PDR ADOCK 05 P

Page 71 of 298 Copyright o 1999 by Northem States Power

c ,.

CYCLE SPECIFIC PARAMETERS SAFETY ANALYSIS PARAMETERS i

a. ax + RFu + Bn 5 cts (least negative bounding value)
b. n o* (1 - RFo) s ao (least negative bounding value)
c. a *s (1 + RFa) * (1 + Bs) 2 as (most negative bounding value)
d. Shutdown Margin 2 Shutdown Margin (bounding)
e. ( Faa+RFraa+ Bran) * (1+T) s Fan (Technical Specifications) l l

l l

Page 72 of 298 Copyright c 1999 by Northern States Power

F .. . . . .

l .o o l

l l i i l )

l APPENDIX H 1

H.1 Changes Made In Revision 7 To This Report The format of this document has changed slightly between Revisions 6 and 7. Most of this was due to the use of a i different word processor which reformatted the entire document. l For reference, alterations made in Revision 7 are summarized I below.

Rev. 6 Page Rev. 7 Page Description of Change Number (s) Number (s) 1 1* Revision number and date were updated.

2,3 2*,3* Margins were adjusted.

4-12 4-12* Provided additional sections in Table of l Contents, adjusted titles of various figures (but not the actual figures). j 13-14 13-14 Text was added to describe the addition of Appendix G. J 47 49 Changed text to show VIPRE is used rather than COBRA.

{

l l 50 52 The equation for Moderator Temperature j Coefficient was corrected. An error j introduced in Rev. 6 in the inequality for )

excore tilt was also corrected. j 66, 67 69, 70* Corrected the character for delta in the )

text.' Text was added to describe the l

addition of Appendix G.

68 71, 72 Clarification of shutdown margin. ,

84, 97, 88, 101, Provided additional information for the l 133, 145 138, 150 Doppler Coefficient.

131 136 Corrected number of pumps assumed to trip in each figure.

133, 145 138, 150 Added Shutdown Margin-to the Cycle Specific Parameters list and text describing it.

155 160 Correct typo on pressure at which steamline l

break occurs.

157 163 Pressure under (e) is corrected.

188 194 The equati.ns for pere and Aputer were l l corrected.

I 200 206 The equation for Boron Reactivity Coefficient was corrected.

257 264* Corrected the units in two columns.

263 270* Changed f(A) and A to f(AI)and AT. [

n/a 293-298 Added Appendices G and H.

various various* Corrected spelling and grammar, added spaces to separate words, corrected subject / verb l agreement, etc.

  • No revision bars are provided for spelling and grammar corrections or text format changes. ,

i Page 298 of 298 a Copyright 81999 by Northem States Power 1

[

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