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{{#Wiki_filter:ACCELERATED
{{#Wiki_filter:ACCELERATED ..                   STBHBUTION DEMON                     TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
..STBHBUTION DEMON TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSXON NBR:9004130056 DOC.DATE: 90/04/06 NOTARIZED:
ACCESSXON       NBR:9004130056           DOC.DATE:   90/04/06   NOTARIZED: NO           DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C. Cook Nuclear Power Plant, 'Unit 2, Indiana 6 05000316 NAME            AUTHOR AFFILIATION                                                  'UTH.
NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C.Cook Nuclear Power Plant,'Unit 2, Indiana 6 05000316'UTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
ALEXICH,M.P.             Indiana Michigan Power Co. (formerly Xndiana 6 Michigan,Ele RECIP.NAME               RECIPIENT AFFXLIATION                                                     R MURLEY,T.E.                 Document Control Branch (Document         Control Desk)
Indiana Michigan Power Co.(formerly Xndiana 6 Michigan,Ele RECIP.NAME RECIPIENT AFFXLIATION R MURLEY,T.E.
Forwards revised figures for loss of load event previously submitted in Attachment 4,App B of VANTAGE 5 reload                                   D transition safety rept supple.ed         by Westinghouse in an 1990.
Document Control Branch (Document Control Desk)DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL TITLE: OR Submittal:
Update is editorial in nature.                                                       .s NOTES'UBJECT:
General Distribution NOTES'UBJECT:
DISTRIBUTION CODE: A001D              COPIES RECEIVED:LTR        ENCL      SIZE:
Forwards revised figures for loss of load event previously submitted in Attachment 4,App B of VANTAGE 5 reload transition safety rept supple.ed by Westinghouse in an 1990.Update is editorial in nature.SIZE: D.s RECIPIENT ID CODE/NAME PD3-1 LA GIXTTER,J.
TITLE:      OR  Submittal: General Distribution RECIPIENT              COPIES            RECIPIENT          COPIES                D ID CODE/NAME            LTTR ENCL      ID  CODE/NAME       LTTR ENCL PD3-1 LA                     1    1    PD3-1 PD                1    1                D GIXTTER,J.                   5    5 INTERNAL'RR/DET/ECMB 9H                     1    1    NRR/DOEA/OTSBll        1    1 NRR/DST         SE2          1     1,   NRR/DST/SELB 8D        1    1 NRR/DST/SICB 7E              1    1'    NRR/DST/SRXB SE         1    1 NUDOCS-ABSTRACT                    1    OC WOMB                 1    0 OGC/HDS 1                    1    0      EG   LE     Ol,     1     1 RES/DS  IR/EIB              1     1 EXTERNAL'PDR                                1     1     NRC PDR                1     1 NSXC                        1     1 D
INTERNAL'RR/DET/ECMB 9H NRR/DST SE2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS 1 RES/DS IR/EI B EXTERNAL'PDR NSXC COPIES LTTR ENCL 1 1 5 5 1 1 1 1, 1 1'1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DOEA/OTSBll NRR/DST/SELB 8D NRR/DST/SRXB SE OC WOMB EG LE Ol, NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 D D D A NOTE TO ALL"RIDS" RECIPIENTS:
A NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE, DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISIRIBUTION LISIS FOR DOCUMERIS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19 S
S PLEASE HELP US TO REDUCE WASTE! CONTACT THE, DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISIS FOR DOCUMERIS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR                   21   ENCL   19
'0'(g I Indiana Mictjga~Power Company PO, Box'663I Columbos.OH-'32'6 INDIANA NICHIGAN POWER AEP:NRC:1071H Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 MODIFICATION TO OUR PREVIOUS SUBMITTAL AEP:NRC:1071E; REVISED FIGURES FOR THE LOSS OF LOAD EVENT U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Hurley April 6, 1990


==Dear Hr.Murley:==
  ' 0' (g
The purpose of this letter is to update our previous submittal AEP:NRC:1071E.
I
The changes provided herein are corrections to the documentation in Appendix B of the VANTAGE 5 Reload Transition Safety Report for Donald C.Cook Nuclear Plant Unit 2, January 1990, supplied by our contractor, Westinghouse.
 
The update is attached to this submittal.
Indiana Mictjga~
The update, which is editorial in nature, consists of revised figures for the loss of load event.Westinghouse has informed us that these revisions have no impact on the conclusions noted in our previous submittal.
Power Company PO, Box '663I Columbos. OH -'32'6 INDIANA NICHIGAN POWER AEP:NRC:1071H Donald C. Cook Nuclear Plant Units        1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 MODIFICATION TO OUR PREVIOUS SUBMITTAL AEP:NRC:1071E; REVISED FIGURES FOR THE LOSS OF LOAD EVENT U.S. Nuclear Regulatory Commission Attn:      Document    Control Desk Washington, D.C. 20555 Attn: T.        E. Hurley April 6,     1990
These figures replace the corresponding figures previously submitted in Attachment 4, Appendix B of our submittal AEP:NRC:1071E.
 
The figures transmitted with AEP:NRC:1071E did not correspond to the bounding case.We apologize for any inconvenience this update may cause you or your staff.This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
==Dear Hr. Murley:==
Sincerely, M.P.Alexich Vice President dfw Attachment goQI>~+3.0 90/-
 
Dr.T.E.Murley-2-AEP:NRC:1071H cc: D.H.Williams, Jr.A.A.Blind-Bridgman R.C.Callen G.Charnoff A.B.Davis-Region III NRC Resident Inspector-Bridgman NFEM Section Chief ATTACHMENT 1 TO AEP:NRC:1071H REVISED FIGURES FOR THE LOSS OF LOAD EVENT PREVIOUSLY SUBMITTED IN ATTACHMENT 4, APPENDIX B OF AEP:NRC:1071E 1.4 z 1.2 X CI z X o QI L LJ O O.OC CL LJ D Z.6.2 0.10 ZO 30 40 50 60 70 80 90 100 2800.2700.2600.2500.g 2400.2300.2200.2100.LJ 2000.1900.1800 0.10.20.30.40.50.60.70.80.90.100.T ILLE (SEC I Figure 8.3-26A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback with Pressurizer Spray and PORVs 8-173 2000.1800.LJ 1600.CI 1400.OC 4J ac 1200.D~A I~QC 1000.800.0.10.20.30.40.50.60.70.80.90.100.3.2 3.Z.8 Z.6 Z.4 5 2-2 2.1.8 1.6 1.4 1.2 0 10 20 30 40 50 60 70 80 90 100 Tjl1E ISECI Figure B.3-27A Loss of Load Pressurizer Water Volume and DNBR Versus Time for Minimum Reactivity with Pressurizer Spray and PORVs B-174 Revision 1  
The purpose        of this letter is to update our previous submittal AEP:NRC:1071E.         The changes provided herein are corrections to the documentation in Appendix B of the VANTAGE 5 Reload Transition Safety Report for Donald C. Cook Nuclear Plant Unit 2, January 1990, supplied by our contractor, Westinghouse.          The update is attached to this submittal.
~!~700 680 660 I 640 CI D 620 o 600 I O P-580 TMOT 0 560 C)C)540 TCOLD 520 500 0 10 20 30 40 50 60 70 80 90 100 700 680.660 640 w 620 600 580 LJ 560 540 520 500 10 20 30 40.50 60 70 80 90 100 TII1E (SEC)Figure 8.3-28A Loss of Load Loop and Core Average Temperatures Versus Time for Minimum Reactivity with Pressurizer Spray and PORVs 8.17S Revf.sion 1 CK Z 1.2 Z o Z Z o I CJ K Qf L Q.'J o Q OC K 4J C3.8.6~4~2 0.10 20 30 40 SO 60 70 80 90 100 2800.2700.2600.V)Q 2SOO.LJ QC 2400.V)LJ 2300.OC LJ 2200'C V)2100'J OC Q 2000.1900 o 1800'0.10.20.30.40'SO~60'0'0'0'00.7111E<SEC1 Figure B.3-29A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Maximum Reactivity Feedback with Pressurizer Spray and PORVs B-176
The update,         which is editorial in nature, consists of revised figures for the loss of load event. Westinghouse has informed us that these revisions have no impact on the conclusions noted in our previous submittal. These figures replace the corresponding figures previously submitted in Attachment 4, Appendix B of our submittal AEP:NRC:1071E. The figures transmitted with AEP:NRC:1071E did not correspond to the bounding case.
.4~CL 1.2 K C)X o I OC 4 OC LJ C)O OC CL LJ D.8.6.2 0.10 20 30 40 50 60 70 80 90 100 2800.2700.2600.O 2500.LJ 2400.2300.OC 4J lV OC C/7 CA LJ OC O 2200.2100.2000.1900.1800.0.10.20.30.40.50.60.70.80.90.100.TIDE'SEC)Figure B.3-32A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback Without Pressurizer Spray and PORVs B.179 Revisian 1 2000.1600.CI LJ lV 1200.D V7<0 DC 1000.800 0.10.20.30.40.50.60.70.80.90.100.3.2 3.2.8 2.6 2.4..2.2 2.1.6 1.4 1.2 0 1O ZO 3O 4O SO 6O 7O 8O eO 1OO TLAT (SEC)Figure B.3-33A Loss of Load Pressurizer Water Volume and DNBR Versus Time for Minimum Reactivity Feedback Without Pressurizer Spray and PORVs B-180 Revision 1 w y 700 680 eeo I w 640 CI o 620 O (J eoo l O F-580 THOT seo 540 TCOLD 520 500 0 10 20 30 40 50 60 70 80 90 100 700 680 660 e4o I 620 CI 600 580 LJ u 560 540 520 500 10 20 3o 40 50 eo 70 80 9o 1oo T1nE (SEC)Figure B.3-34A Loss of Load Loop and Core Average Temperatures Versus Time for Ninimum Reactivity Feedback Without Pressurizer Spray and PORVs 8-181 Revision 1  
We    apologize for any inconvenience this update      may cause  you or your staff.
*I CJ: Z 1~2 K C)X C)I CJ CZ Q'LJ o Q.Ql CZ W CJ D~8.6~4~2 0.0 10 20 0 0.80 60 70 80 90 100 2800.2700.2600.'JJ Q.2500.LJ Q D 2400~CJJ LJ QC 2300.QC LJ 2200.QC CIJ cJJ 2100.LJ QC Q 2000~1900.1800.0.10~20'(~40~SO.60~7 0~80~90.100~T IJ1E (SEr)Figure B.3-35A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Maximum Reactivity Feedback without Pressurizer Spray and PORVs B-182 V AMERICAN ELECTRIC P R SERVICE, CORPORATION ll4/DATE A ril 19 MEMO TO: Attached you will find a corrected copy of the AEP:NRC:1071H letter.We inadvertently mailed the original copies without copying both sides of the attachment.(Please note that Pages B-177 and B-178 were intentionally not copied for the attachment.)
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
We apologize for any inconvenience that our error may have caused,you.
Sincerely, M. P. Alexich Vice President 90/-
dfw Attachment goQI>~+3.0
 
Dr. T. E. Murley                    AEP:NRC:1071H cc:  D. H. Williams, Jr.
A. A. Blind - Bridgman R. C. Callen G. Charnoff A. B. Davis - Region  III NRC  Resident Inspector - Bridgman NFEM Section Chief
 
ATTACHMENT 1 TO AEP:NRC:1071H REVISED FIGURES FOR THE LOSS OF LOAD EVENT PREVIOUSLY SUBMITTED  IN ATTACHMENT 4, APPENDIX B OF AEP:NRC:1071E
 
1.4 z    1.2 X
CI z
oX QI L
            .6 LJ O
O.
OC CL LJ D
Z      .2 0.
10      ZO      30    40        50      60      70      80    90      100 2800.
2700.
2600.
2500.
g 2400.
2300.
2200.
LJ 2100.
2000.
1900.
1800
: 0. 10. 20. 30. 40.       50. 60. 70. 80. 90. 100.
T ILLE      (SEC I Figure 8.3-26A      Loss  of  Load Nuclear Power and Pressurizer          Pressure  Versus Time  for Minimum  Reactivity  Feedback      with Pressurizer Spray      and PORVs 8-173
 
2000.
1800.
LJ 1600.
CI 1400.
OC 4J ac  1200.
D
  ~A I~
QC 1000.
800.
: 0. 10. 20.      30. 40. 50. 60. 70. 80. 90. 100.
3.2 3.
Z.8 Z.6 Z.4 5 2-2 2.
1.8 1.6 1.4 1.2 0 10     20       30 40     50     60   70   80   90     100 Tjl1E    ISECI Figure B.3-27A  Loss of  Load Pressurizer Water Volume and DNBR Versus Time for  Minimum Reactivity with Pressurizer Spray and PORVs B-174 Revision  1
 
~ !
    ~
700 680 660 I
640 CI D    620 o
600                    TMOT I
O P-  580 0   560 C)                          TCOLD C) 540 520 500 0 10    20     30     40       50      60     70     80     90     100 700 680.
660 640 w    620 600 580 LJ 560 540 520 500 10    20    30    40    .50      60      70    80      90    100 TII1E      (SEC)
Figure 8.3-28A  Loss of Load Loop and Core Average Temperatures        Versus Time  for Minimum Reactivity with Pressurizer Spray        and PORVs 8.17S Revf.sion  1
 
CK Z      1.2 Z
o Z
oZ I
CJ
              .8 K
Qf L
Q.'J
              .6 oQ OC      ~ 4 K
4J C3
              ~ 2 0.
10    20      30    40      SO        60      70    80    90    100 2800.
2700.
2600.
V)
Q 2SOO.
LJ QC V) 2400.
LJ 2300.
OC LJ 2200  'C V) 2100  'J OC Q
2000.
1900  o 1800
                '0. 10. 20. 30. 40 'SO 7111E
                                                    ~    60
                                                      <SEC1
                                                            '0 '0 '0 '00.
Figure B.3-29A        Loss  of Load Nuclear Power and Pressurizer        Pressure  Versus Time  for Maximum  Reactivity  Feedback    with Pressurizer Spray    and PORVs B-176
 
            .4  ~
CL 1.2 K
C)
X o
I
            .8 OC 4
OC     .6 LJ C)
O OC CL LJ D
            .2 0.
10     20     30     40       50       60     70     80     90     100 2800.
2700.
2600.
O 2500.
LJ 2400.
2300.
OC 4J lV 2200.
OC C/7 CA LJ 2100.
OC O
2000.
1900.
1800.
: 0. 10. 20. 30. 40.       50. 60. 70. 80. 90. 100.
TIDE        'SEC)
Figure B.3-32A      Loss  of  Load Nuclear Power and Pressurizer          Pressure Versus Time for Minimum  Reactivity  Feedback Without Pressurizer Spray and PORVs B.179 Revisian    1
 
2000.
1600.
CI LJ lV 1200.
D V7
  <0 DC 1000.
800
: 0. 10. 20. 30. 40. 50. 60. 70. 80. 90. 100.
3.2 3.
2.8 2.6 2.4
    .. 2.2 2.
1.6 1.4 1.2 0  1O    ZO      3O    4O      SO    6O    7O    8O    eO      1OO TLAT    (SEC)
Figure B.3-33A    Loss of  Load Pressurizer Water Volume    and DNBR Versus Time for Minimum Reactivity  Feedback Without Pressurizer Spray and PORVs B-180 Revision 1
 
wy 700 680 eeo I
w    640 CI o    620 O
(J eoo l                      THOT O
F-    580 seo TCOLD 540 520 500 0  10     20     30    40      50      60  70  80    90    100 700 680 660 e4o I
CI 620 600 580 LJ u    560 540 520 500 10    20    3o     40     50       eo 70 80   9o     1oo T1nE       (SEC)
Figure B.3-34A   Loss of Load Loop and Core Average Temperatures Versus Time for Ninimum Reactivity Feedback Without Pressurizer Spray and PORVs 8-181 Revision 1
 
                                                                                                            *I CJ:
Z     1 ~   2 K
C)
X C)
I CJ
                ~  8 CZ Q'
                . 6 LJ o
Q.
Ql       ~    4 CZ W
CJ D
                ~   2 0.
0   10       20       0       0 . 80       60       70     80     90       100 2800.
2700.
2600.
'JJ Q.
2500.
LJ Q
D CJJ 2400     ~
LJ QC 2300.
QC LJ 2200.
QC CIJ cJJ LJ 2100.
QC Q
2000     ~
                                      '(
1900.
1800.
: 0. 10 ~   20       ~   40 ~   SO.     60 ~ 7 0 ~   80 ~   90. 100 ~
T IJ1E     (SEr )
Figure B.3-35A               Loss of   Load Nuclear Power and Pressurizer Pressure Versus Time               for Maximum   Reactivity   Feedback   without Pressurizer Spray       and PORVs B-182
 
V AMERICAN ELECTRIC P             R SERVICE,CORPORATION ll4/
DATE   A ril 19 MEMO TO:
Attached you will find a corrected copy of the AEP:NRC:1071H letter. We inadvertently mailed the original copies without copying both sides of the attachment.     (Please note that   Pages B-177 and B-178 were   intentionally not copied for the attachment.)
We apologize for any inconvenience that our error   may have caused,you.
FROM 7155P 83)lAP50 OM 14 (AD 16)
FROM 7155P 83)lAP50 OM 14 (AD 16)
I 0 E h}}
 
I   0 E h}}

Latest revision as of 11:31, 22 October 2019

Forwards Revised Figures for Loss of Load Event Previously Submitted in Attachment 4,App B of Vantage 5 Reload Transition Safety Rept Supplied by Westinghouse in Jan 1990. Update Is Editorial in Nature
ML17334B360
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/06/1990
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1071H, NUDOCS 9004130056
Download: ML17334B360 (15)
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Text

ACCELERATED .. STBHBUTION DEMON TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSXON NBR:9004130056 DOC.DATE: 90/04/06 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C. Cook Nuclear Power Plant, 'Unit 2, Indiana 6 05000316 NAME AUTHOR AFFILIATION 'UTH.

ALEXICH,M.P. Indiana Michigan Power Co. (formerly Xndiana 6 Michigan,Ele RECIP.NAME RECIPIENT AFFXLIATION R MURLEY,T.E. Document Control Branch (Document Control Desk)

Forwards revised figures for loss of load event previously submitted in Attachment 4,App B of VANTAGE 5 reload D transition safety rept supple.ed by Westinghouse in an 1990.

Update is editorial in nature. .s NOTES'UBJECT:

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D GIXTTER,J. 5 5 INTERNAL'RR/DET/ECMB 9H 1 1 NRR/DOEA/OTSBll 1 1 NRR/DST SE2 1 1, NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1' NRR/DST/SRXB SE 1 1 NUDOCS-ABSTRACT 1 OC WOMB 1 0 OGC/HDS 1 1 0 EG LE Ol, 1 1 RES/DS IR/EIB 1 1 EXTERNAL'PDR 1 1 NRC PDR 1 1 NSXC 1 1 D

A NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP US TO REDUCE WASTE! CONTACT THE, DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISIS FOR DOCUMERIS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19

' 0' (g

I

Indiana Mictjga~

Power Company PO, Box '663I Columbos. OH -'32'6 INDIANA NICHIGAN POWER AEP:NRC:1071H Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 MODIFICATION TO OUR PREVIOUS SUBMITTAL AEP:NRC:1071E; REVISED FIGURES FOR THE LOSS OF LOAD EVENT U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Hurley April 6, 1990

Dear Hr. Murley:

The purpose of this letter is to update our previous submittal AEP:NRC:1071E. The changes provided herein are corrections to the documentation in Appendix B of the VANTAGE 5 Reload Transition Safety Report for Donald C. Cook Nuclear Plant Unit 2, January 1990, supplied by our contractor, Westinghouse. The update is attached to this submittal.

The update, which is editorial in nature, consists of revised figures for the loss of load event. Westinghouse has informed us that these revisions have no impact on the conclusions noted in our previous submittal. These figures replace the corresponding figures previously submitted in Attachment 4, Appendix B of our submittal AEP:NRC:1071E. The figures transmitted with AEP:NRC:1071E did not correspond to the bounding case.

We apologize for any inconvenience this update may cause you or your staff.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M. P. Alexich Vice President 90/-

dfw Attachment goQI>~+3.0

Dr. T. E. Murley AEP:NRC:1071H cc: D. H. Williams, Jr.

A. A. Blind - Bridgman R. C. Callen G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman NFEM Section Chief

ATTACHMENT 1 TO AEP:NRC:1071H REVISED FIGURES FOR THE LOSS OF LOAD EVENT PREVIOUSLY SUBMITTED IN ATTACHMENT 4, APPENDIX B OF AEP:NRC:1071E

1.4 z 1.2 X

CI z

oX QI L

.6 LJ O

O.

OC CL LJ D

Z .2 0.

10 ZO 30 40 50 60 70 80 90 100 2800.

2700.

2600.

2500.

g 2400.

2300.

2200.

LJ 2100.

2000.

1900.

1800

0. 10. 20. 30. 40. 50. 60. 70. 80. 90. 100.

T ILLE (SEC I Figure 8.3-26A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback with Pressurizer Spray and PORVs 8-173

2000.

1800.

LJ 1600.

CI 1400.

OC 4J ac 1200.

D

~A I~

QC 1000.

800.

0. 10. 20. 30. 40. 50. 60. 70. 80. 90. 100.

3.2 3.

Z.8 Z.6 Z.4 5 2-2 2.

1.8 1.6 1.4 1.2 0 10 20 30 40 50 60 70 80 90 100 Tjl1E ISECI Figure B.3-27A Loss of Load Pressurizer Water Volume and DNBR Versus Time for Minimum Reactivity with Pressurizer Spray and PORVs B-174 Revision 1

~ !

~

700 680 660 I

640 CI D 620 o

600 TMOT I

O P- 580 0 560 C) TCOLD C) 540 520 500 0 10 20 30 40 50 60 70 80 90 100 700 680.

660 640 w 620 600 580 LJ 560 540 520 500 10 20 30 40 .50 60 70 80 90 100 TII1E (SEC)

Figure 8.3-28A Loss of Load Loop and Core Average Temperatures Versus Time for Minimum Reactivity with Pressurizer Spray and PORVs 8.17S Revf.sion 1

CK Z 1.2 Z

o Z

oZ I

CJ

.8 K

Qf L

Q.'J

.6 oQ OC ~ 4 K

4J C3

~ 2 0.

10 20 30 40 SO 60 70 80 90 100 2800.

2700.

2600.

V)

Q 2SOO.

LJ QC V) 2400.

LJ 2300.

OC LJ 2200 'C V) 2100 'J OC Q

2000.

1900 o 1800

'0. 10. 20. 30. 40 'SO 7111E

~ 60

<SEC1

'0 '0 '0 '00.

Figure B.3-29A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Maximum Reactivity Feedback with Pressurizer Spray and PORVs B-176

.4 ~

CL 1.2 K

C)

X o

I

.8 OC 4

OC .6 LJ C)

O OC CL LJ D

.2 0.

10 20 30 40 50 60 70 80 90 100 2800.

2700.

2600.

O 2500.

LJ 2400.

2300.

OC 4J lV 2200.

OC C/7 CA LJ 2100.

OC O

2000.

1900.

1800.

0. 10. 20. 30. 40. 50. 60. 70. 80. 90. 100.

TIDE 'SEC)

Figure B.3-32A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback Without Pressurizer Spray and PORVs B.179 Revisian 1

2000.

1600.

CI LJ lV 1200.

D V7

<0 DC 1000.

800

0. 10. 20. 30. 40. 50. 60. 70. 80. 90. 100.

3.2 3.

2.8 2.6 2.4

.. 2.2 2.

1.6 1.4 1.2 0 1O ZO 3O 4O SO 6O 7O 8O eO 1OO TLAT (SEC)

Figure B.3-33A Loss of Load Pressurizer Water Volume and DNBR Versus Time for Minimum Reactivity Feedback Without Pressurizer Spray and PORVs B-180 Revision 1

wy 700 680 eeo I

w 640 CI o 620 O

(J eoo l THOT O

F- 580 seo TCOLD 540 520 500 0 10 20 30 40 50 60 70 80 90 100 700 680 660 e4o I

CI 620 600 580 LJ u 560 540 520 500 10 20 3o 40 50 eo 70 80 9o 1oo T1nE (SEC)

Figure B.3-34A Loss of Load Loop and Core Average Temperatures Versus Time for Ninimum Reactivity Feedback Without Pressurizer Spray and PORVs 8-181 Revision 1

  • I CJ:

Z 1 ~ 2 K

C)

X C)

I CJ

~ 8 CZ Q'

. 6 LJ o

Q.

Ql ~ 4 CZ W

CJ D

~ 2 0.

0 10 20 0 0 . 80 60 70 80 90 100 2800.

2700.

2600.

'JJ Q.

2500.

LJ Q

D CJJ 2400 ~

LJ QC 2300.

QC LJ 2200.

QC CIJ cJJ LJ 2100.

QC Q

2000 ~

'(

1900.

1800.

0. 10 ~ 20 ~ 40 ~ SO. 60 ~ 7 0 ~ 80 ~ 90. 100 ~

T IJ1E (SEr )

Figure B.3-35A Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Maximum Reactivity Feedback without Pressurizer Spray and PORVs B-182

V AMERICAN ELECTRIC P R SERVICE,CORPORATION ll4/

DATE A ril 19 MEMO TO:

Attached you will find a corrected copy of the AEP:NRC:1071H letter. We inadvertently mailed the original copies without copying both sides of the attachment. (Please note that Pages B-177 and B-178 were intentionally not copied for the attachment.)

We apologize for any inconvenience that our error may have caused,you.

FROM 7155P 83)lAP50 OM 14 (AD 16)

I 0 E h

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