ML17329A716
| ML17329A716 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/16/1992 |
| From: | AMERICAN ELECTRIC POWER SERVICE CORP. |
| To: | |
| Shared Package | |
| ML17329A705 | List: |
| References | |
| 2985-HEI-01, 2985-HEI-01-R00, 2985-HEI-1, 2985-HEI-1-R, NUDOCS 9212180080 | |
| Download: ML17329A716 (44) | |
Text
Donald C. Cook Nuclear Plant Units 1 8t: 2 Summary Report for Response Time Evaluations Reactor Protection and Control System Replacement Project Report Number 2985-HEI-01, Rev. 0
~Slib ect:
Evaluation of response times for Foxboro Spec 200 and Spec 200 Micro instrumentation equipment to be utilized in the Reactor Protection System replacement.
References:
1.
Donald C. Cook Nuclear Plant Technical Specifications sections 3/4 and its associated bases.
(reference Attachment ¹1) 2.
Donald C. Cook Station Response Time Procedures IHP 4030 STP.100 A & B for Reactor Protection and Engineered Safeguards Systems Time Response, and EHP 4030 STP.205 A & B.
3.
Functional Diagrams 92F12687-FD-2101 thru 2104 all sheets.
4.
Foxboro letter FTAEP-020 which transmits to AEP module design response times dated 08/05/92.
(reference Attachment ¹2)
Compilation of response time data collected by AEP.
(reference Attachment ¹3)
Isstte:
Compare response time of the Foxboro Spec 200 equipment to that of the existing Foxboro H-Line equipment.
The H-Line equipment is being replaced as part of the Reactor Protection System (RPS) upgrade modification.
AEP-RTE D.C. Cook Units l 8c 2 Reactor Protection System Replacement 92i2i80080 92i2i6 PDR ADQCK 050003i5 P,
PDR Summary Report for Response Time Evaluation Report Number 2985-HEI-Ol Rev. 0 Page 1 of 4
~sco et The scope of this evaluation is to ensure that the Foxboro Spec 200 equipment response times are acceptable with respect to the Donald C. Cook Nuclear Plant licensing basis.
This report shall document the results of the response time evaluation and detail the specific methodology utilized to support the conclusion.
Methodolo The methodology utilized for the response time evaluation is illustrated in the attached Figure
- 1. This methodology has been established to produce two (2) sets of comparison data:
1.
Comparison of Foxboro Spec 200 calculated response times vs. results of actual D. C.
Cook Nuclear Plant surveillance data.
2.
Comparison of Foxboro Spec 200 calculated response times vs. D. C.
Cook Nuclear Plant Technical Specifications.
This process shall document the overall impact of the Foxboro Spec 200 upgrade on the Reactor Protection System response.
Discussion:
This response time evaluation has been produced to provide a level of confidence that the response time characteristics of the Foxboro Spec 200 equipment is acceptable to meet the D.
C. Cook Nuclear Plant licensing basis.
This evaluation was performed in accordance with the above described methodology and documented as follows:
An evaluation of the response times of the new equipment was prepared in accordance with documentation provided by Foxboro to AEP in letter FTAEP-020 dated 08/05/92. Data from this documentation was utilized to determine which modules would be configured to replace the existing H-line equipment and what the worst case response time for that compilation of modules represents.
Next, the calculated response time was compared to the response time test data as documented in the last D. C. Cook surveillance test procedure.
The total loop response time was then compared to the Technical Specification requirements to assure that the loop response was still within the licensing basis.
For those loops where the new response time was less than the current response time, no further action was required.
For those loops where the new response time was greater than the current response time, the specific loop safety function was considered and an evaluation was performed to determine whether or not the new response spectra was acceptable with respect to the Technical Specification requirements.
D.C. Cook Units l &2 Reactor Protection System Replacement
- EP-RTE Summary Report for Response Time Evaluation Report Number 2985-HEI-01 Rev. 0 Page 2 of 4
Conclusions From the documented results of the evaluation of the Reactor Trip System (Attachment ¹4) and the Engineered Safeguards System (Attachment ¹5), it is concluded that the response times for the Spec 200 and Spec 200 Micro instrumentation are superior to that of the old H-line equipment.
The only challenge to the Spec 200 equipment comes in cases where the input module for the system utilizes an RTD or Thermocouple as the primary element (OT/dT and OP/dt). For these protective functions, the worst case Spec 200 module response times utilized for the comparison represent unrealistic values.
The OT/dT and OP/dT comparison data utilizes a 2000 ms response for the R/I converter and 400 ms response for each of the Spec 200 Micro modules.
Actual module response times for the R/I converter and the Micro modules are expected to be significantly less than published data resulting in overall response times being conservative to Technical Specifications.
Therefore, the response times for the new Foxboro Spec 200 modules are found to be acceptable.
Actual response times shall be verified during factory acceptance testing and post installation testing.
~Arovals:
P epared By Date Reviewed By Io 30 9'2-Date Approved By Date D.C. Cook Units l &, 2 Reactor Protection System Replacement AEP-RTE Summary Report for Response Time Evaluation Report Number 2985-HEI-01 Rev. 0 Page 3 of 4
Collect and Review Vendors'iterature, Engineering Design Documentation, and Surveillance Test Data Compare Calculated Response Time to Last Completed Surveillance Data (Acceptable)
Refine Calculated Response Time YES Compare to Technical Specification's (Acceptable)
. Better Vendor Documentation of Response Time Refine Calculated Response Time YES Compile Data and Produce Final Re ort Better Vendor Documentation of Response Time END Consider Possible Tech Spec Change Figure 1
D.C. Cook Units 1 8r,2 l
Reactor Protection System Replacement I
AEP-RYE Summary Report for Response Time Evaluation Report Number 2985-HEW)1 Rev. 0 Page 4 of 4
'a, a
p~~cg~chy ~1 g.
I of s Repa&
gu~beC ZRSS-Hey-~i TABLE 3.3 5
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATINCSIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS
- l. Manual Safety In)ection (ECCS)
Feedwater Isolation Reactor Trip (SI)
Containment Isolation-Phase h
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System Not Applicable Not hpplicable Not Applicable Not hpplicable Not Applicable Not Applicable Not Applicable b.
Containment Spray Containmcnt Isolation-Phase B"
Containment Purge and Exhaust Isolation Containment Air Recirculation Fan c.
Containmcnt Isolation-Phase h"
Containment Purge and Exhaust Isolation d.
Stcam Line Isolation Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable 2.
Containment Prcssur'c-Hi h
b.
C.
d.
c Safety Infection (ECCS)
Reactor Trip (from SI)
Fecdwatcr Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwatcr Pumps Essential Service Water System Less than or equal
- 27. OQQ/27. 0++
Less than or equal Less than or equal Less then or equal 18.09/28.00 Not Applicable Not Applicable Less than or equal 13.0g/48.00 to to 3.0 to 8.0 to to COOK NUCLEAR PRATE - UNIT 1 3/4 3-27 AME2G)MENT gj$ ~ 158
TABLE 3.3-5 Continue ENCZNEERED SAFETY FEATURES RESPONSE TIMES INITIATZNC SIGNAL AND FUNCTION
RESPONSE
TIHE IN SECONDS 3.
Pressurizer Pressure-Low a.
Safety Injection (ECCS) b.
Reactor Trip (from SZ) c.
Feedwater Isolation d.
Containment Isolation-Phase A,
e.
Containment Purge and Exhaust Isolation f.
Auxiliary Feedwater Pumps g.
Essential Service Water System Less than or equal to 27 088/27 0++
Less than or equal to 3.0 I,ess than or equal to 8.0 Less than or equal to 18.0P Not Applicable Not Applicable Less mohan or equal to 48-0
/13.08 4.
Dlfferertial Pressure Between Steam Lines-High a.
b.
C ~
d ~
Q ~f.
ge Sa ety Injection (ECCS)
Reac or Trip (from SZ)
Feedwater Isolation Con" ainment Isolation-Phase "A"
Cortainment Purge and Exhaust Isolation Auxiliary Feedwate
'Pumps Essential Service Water System Less than or equal 27.088/37.0Ia Less than or equal Less than or equal Less than or equal 18.0P/28.0SP Not Applicable Not Applicable Less than or equal 13.08/48.0PP to to 3.0 to 8.0 to to 5.
Steam Flow 'n Two Steam Lines - Hi h Coincident with Tave--Low-Low a.
b.
C a" d.
e.f.
go h.
Sa ety Injection (ECCS)
Reactor Trip (from SZ)*
Feedwator Isolation Containment Isolation-Phase "A"
1 Con ainment Purge ar 'xhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System Steam Line Isolation Less than or equal 29.09(1/39.08 Less than or equal Less than or equal Less than or equal 20.0P/30.OILS Not Applica'".'<!
Not Applicable Less than or equal 15.01'/50.0SP Le s s than or equal to to 5.0 to 10.0 to to to 13.0 COOK NUCLEAR PLANT - UNIT 1 3/4 3-28 AMENDMENT NO.
TABLE 3.3-5 Continued 4I ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATINGSIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 6.
Steam Flow in Two Steam Lines-Hi h Coincident Pith Stcam Linc Prcssure-Lov a.
Safety Infection (ECCS) b.
Reactor Trip (from SI) c.
Feedvater Isolation d.
Containment Isolation-Phase "A"
e.
Containment Purge and Exhaust Isolation f.
Auxiliary Feedvater Pumps g.
Essential Service Mater System h.
Steam Line Isolation 7.
Containment Pressure--High-Hizh Less than or equal 27.0QQ/37.0Q Less than or equal Less than or equal Less than or equal 18.04/28.0m Not Applicable Not Applicable Less than or equal 14.0~/48.0~
Less than or equal to to 3.0 to 8.0 to
'to to 11.0 a
b.
C.
d.
Containment Spray Containment Isolation-Phase "B"
Steam Line Isolation Containment Air Recirculation Fan Less than or equal to 45.0 Not Applicable Less than or equal to 10.0 Less than or equal to 660.0 8.
Steam Generator t:ater Level--Hi h-High a.
Turbine Trip b.
Feedvater Isolation Less than or equal to 2.5 Less than or equal to 11.0 9.
Steam Generator Mater Level--Lov-Lov a.."fotor Driven Auxiliary Feedvater Pumps b.
Turbine Driven Auxiliary Feedvater Pumps Less than or equal to 60.0 Less than or equal to 60.0 10.
4160 volt Emer encv Bus Loss of Voltaire a.
Motor Driven Auxiliary Feedwater r'umps Less than or equal to 60.0 11.
Loss of Main Feedwater Pumps a.
Motor Driven Auxiliary Feedvater Pumps Less than or equal to 60.0
- 12. Reactor Coolant Pum Bus Undervolta c
a.
Turbine Driven Auxiliary Feedvater Pumps Less than or equal to 60.0 COOK NUCLEAR PLANT - UNIT 1 3/4 3-29 AMENDMENT NO. gg XN XA7 158
T~LE 3. 3-5 Continued ThBLE NOTATION I Diesel generator starting and sequence loading delays not included.
Offsite pover available.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
~ Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
++ Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging, SI, and RHR pumps.
Sequential transfer of charging pump suction from the VCT to the RVST (RVST valves
- open, then VCT valves close). is NOT included.
Q Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
Sequential transfer of charging pump suction from the VCT to the RVST (RVST valves open, then VCT valves close) is included.
QQ Diesel generator starting and sequence loading delays NOT included.
Offsite pover available.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging. pumps.
Sequential transfer of charging pump suction from the VCT to the RVST (RWST valves open, then VCT valves close) is included.
COOK NUCLEhR PLhNT - UNIT 1 3/4 3-30 AMENDMENT NO.
graf ~ 158
~~ ~p~ +I Pg.< oP8 AepA nl~kr >9 e5-ba'-ol ThBLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS
- 1. Manual Safety In]ection (ECCS)
Feedvater Isolation Reactor Trip (SI)
Containment Isolation-Phase
'A" Containment Purge and Exhaust Isolation Auxiliary Feedvater Pumps Essential Service Water System b.
Containment Spray Containment Isolation-Phase
'3" Containment Purge and Exhaust Isolation Containment hi.r Recirculation Fan c.
Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Not Applicable Not Applicable Not Applicable
'ot Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not hppli.cable Not Applicable d.
Steam Line Isolation 2.
Containment Pressure-Hi h
Not Applicable a.
b.
c d.
e ~f.
Safety Infection (ECCS)
Reactor Trip (from SI)
Feedvater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedvater Pumps Essential Service Water System Less than or equal to
- 27. OQQ/27. 0++
Less than or equal to 3.0 Less than or equal to 8.0 Not Appli,cable Not Applicable Not hppli.cable Not hppli.cable COOK NUCLEAR PLANT - UNIT 2 3/4 3-26 AMENDMENT No. gag, re 142
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATINGSIGNAL AND FUNCTION 3.
Pressurixcr Pressure-Lov KESPONSE TIME IN SECONDS b.
C.
d.
e.
Safety In)ection (ECCS)
Reactor Trip (from SI)
Fccdvater Isolation Containmcnt Isolation - Phase "h"
Containment Purge and Exhaust Isolation Motor Driven Auxiliary Feedvater Pumps Essential Service Vater System Less than or equal 27.0QQ/27.0++
Less than or equal Less than or equal Less than or equal Not Applicable to to 3.0 to 8.0 to 18.0¹ Less than or equal to 60.0 Less than or equal to 48.0++/13.0¹ 4.
Differential Prcssure Betvcen Steam Lines - Hi h a.
Safety In5ection (ECCS) b.
Reactor Trip (from SI) c.
Feedvater Isolation d.
Containment Isolation - Phase "h"
Containment Purge and Exhaust Isolation Motor Driven Auxiliary Feedvater Pumps Essential Service Vater System Less than or equal 27.0/37.0Q Less than or equal Less than or equal Less than or equal 18.0¹/28.0¹¹ Not Applicable to to 3.0 to 8.0 to Less than or equal to 60.0 Less than or equal to 13.0¹/48.0¹¹ 5.
Steam Flov in Tvo Steam Lines - Hi h Coincident vith Tav --Lov-Lov a.
b.
Ce d.
Co g ~
h.
Safety In)ection (ECCS)
Reactor Trip (from SI)
Feedvater I~"l~-.'on Containment Isolation-Phase "h"
Containment Purge and Exhaust Isolation Auxiliary Feedvater Pumps Essential Service Vater System Stcam Line Isolation Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Less than or equal to"13.0 COOK NUCLEAR PLANT - UNIT 2 3/4 3-27
'AMENDMENT NO. gg, 2PS.
27$
142
TABLE 3. 3-5 Continued ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 6.
Steam Line Pressure--Low e.
Containment Purge and Exhaust Isolation Motor Driven Auxiliary Feedwater Pumps Essential Service Mater System h.
Steam Line Isolation 7.
Containment Pressure--Hi h-Hi h a.
Safety Injection (ECCS) b.
Reactor Trip (from SI) c.
Feedwater Isolation d.
Containment Isolation-Phase "A"
Less than or equal to 27.0QQ/37.0Q Less than or equal to Less than or equal to Less than or equal to 18.0¹/28.0¹¹ Not Applicable Less than or equal to Less than or equal to 14.0¹/48.0¹¹ Less than or equal to 3.0 8.0 60.0 11.0 a.
b.
C.
d.
Containment Spray Containment Isolation-Phase "B"
Steam Line Isolation Containment Air Recirculation Fan Less than or equal to 45.0 Not Applicable Less than or equal to 10.0 Less than or equal to 600.0 8.
Steam Generator Mater Level--Hi h-Hi h a.
Turbine Trip b.
Feedwater Isolation Less than or equal to 2.5 Less than or equal to 11.0 9.
Steam Generator Mater Level--Low-Low a.
b.
Motoz'riven Auxiliary Feedwater Pumps Turbine Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 Less than or equal to 60.0 10.
4160 volt Emer enc Bus Ll.
c I Volta e a.
Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 11.
Loss of Main Feedwater Pumps a.
Motor Driven Auxiliary Feedwater Pumps
- 12. Reactor Coolant Pum Bus Undervolta e
Less than or equal to 60.0 Less than or equal to 60.0 134 AMENDMENT NO. gg, gP7, Pgg 142 3/4 3-28 COOK NUCLEAR PLANT - UNIT 2 a.
Turbine Driven Auxiliary Feedwater Pumps
TABLE 3.3-5 Continued TABLE NOTATION
¹ Diesel generator starting and sequence loading delays not included.
Offsite power available.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging, pumps.
¹¹ Diesel generator starting and sequence loading delays included,
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging
- pumps,
~ Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging, SI, and RHR pumps.
Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves
- open, then VCT valves close) is NOT included.
Q Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves
- open, then VCT valves close) is included.
(~Q Diesel generator starting and sequence loading delays NOT included.
Offsite po~er available.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves
- open, then VCT valves close) is included.
COOK NUCLEAR PLANT <<UNIT 2 3/4 3-29 AMENDMENT NO.
142
The FOXbarO COmpany Foxboro, Massachusetts, USA.02035
~ Tele phone (6t7) 543-6750
+aPo+ ~~Art-a9'8s-gas-og TO:
American Electric Potter Service Corp.
1 Riverside Plaza
- Columbus, Ohio 432]5 DATE:
FTAEP-020 8/5/92
REFERENCE:
P.O.
C-8741 S.O.
- 92F12687, 88 ATTENTION:
Mr. William G. Sotos GENTLEMEN:
wc ARc cNcLostNO FoR YoUR Usc TNc FoccowtNO DOOUHcNTS tNDtcATco BY (x).
NUM BE R REVIsIDN t)r OR DATF rO cc X X <
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tal rc Il.
C 0rc L.
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IC O4.
~z 8/5/92 Module Design Response Time I N ORDCR FOR OUR WORK To PROCCCD Wl THOUT DCLAYi WC MUST KAVC ONC COPY OF t TCH NO ~ (S)
'Wl TH YOUR APPROVAL AND/OR COHHCNTSi RCTURNCD To US BY 1 tt MARKCD REMARKS t f < P ~)~F-YOURS VCRY TRULY, PQQ 1I
~G
~pc (8 CS B
0 COMPANY BY:
Aldo Vianello, D983/C42-2C Utility Engineering FoAM III'05 (5/69 )
AMERICAN ELECTRIC POSER DONALD C COOK NUCLEAR PLANT Module Des~cen Res ones Time
~ s Prepared by: ~~+
~jg>/q g J. T. Kei er Approved by:
A.. Vianello
J%
The purpose of this calculation is to document the module response time for the SPEC 200 and SPEC 200 MICRO modules used in the Reactor Protection Process Instrumentation system at the Donald C.
Cook Nuclear Plant Units 1
& 2.
The response times listed are based on design values published in the Foxboro Corporate Product Specifications (CPS).
The actual response of individual modules is expected to be the same (for digital modules) or better than the maximum response time values published.
Model No
~Ree once time (milliseconds)
CPS N-2AI-C2L N-2AI-H2V N-2AI-I2V N-2AI-P2V N-2AI-T2V N-2CCA-S N-2CCA-D N-2AO-V2H N-2AO-L2C-R 20 37 37 2000 1000 200 200 80 10 0071 0030 0030 0028 0027 1182 1182 0029 0096
~I Notes:
2.
Specifications, are based upon Foxboro Corporate Product Specifications (CPS) as listed.
For analog converter modules the response time is the maximum time required for the output to reach 904 of the final steady state value when excited by an 804 input step (10 to 904 change).
This approximately corresponds to two first order time constants.
3.
The response time for the relay output module, N-2AO-L2C-R, is typical.
4.
The response time listed for the digital modules is the execution time for the processor.
The maximum time to respond to a step change in input based upon worst case timing and loading is 400 milliseconds.
ESF RESPONSE TIMES UNIT 1 PARAMETER
- 1. CONTAINMENT PRESSURE-HIGH TRANSMITTER RACK ELEC.
8$ BKR ESF EQUIPMENT D/G START TIME D/G LOADTIME TOTALTR Qfogt NCHENT'/S 5SIPMEH+~geM MARGIN A. SI (ECCS)
B. RX TRIP (FROM SI)
C. FWI D. CI-PH A E. ESW 0.3715 0.4366 0.2637 0.3663/0.3693 0.3637 4.51 5.6/3.9 0.2 7.7+6.76 7.7 7.7+19.65 19.63 OA366 4.87 5.96/1 1.97 0.56/27.9
= <27.0
$? <3.0
?? <8.0
?? <18.0/28.0
= <13.0/48.0 7.37 2.56 3.13 12.04/16.03 1 2.44/20.1
B. RX TRIP (FROM SI)
C. FWI D. CI-PH A E. ESW 0.4815 0.6698 OA685 0.4815 0.4685 10.5 4.51 3.9 0.2 7.7/7.7+ 6.76 7.7 7.7+19.65 19.74/10.98 0.6608 4.98 12.08 28.01/0.6885
?? <27.0/13.0
?$ <3.0
?? <8.0
?$ <18.0
?8<48.0/13.0 7.26/2.02 2.33 3.02 5.92 19.99/1 2.33
- 3. STEAM UNE D/P -HIGH A. Sl(ECCS)
B. RX TRIP 0.4037 0.4623 10.5 7.7 10.9/18.6 0.4623
?? <13.0/23.0
?? <3.0 2.1/4.4 2.54 (FROM SI)
C. FWI D. CI-PH A E. ESW 0.3946 0.3972/0.4004 0.3946 4.51 5.6/3.9 0.2 7.7 7.7+19.65 4.9 6/12
?? <8.0
?? <18.0/28.0 0.59/27.94
?? <13.0/48.0 12/16 12.41/20
ESF RESPONSE TIMES UNIT 1 PARAMETER TRANSMITTER RACK ELECT.
8 BKR ESF EQUIPMENT D/G START TIME D/G LOADTIME TOTALTR T/8 REQUIREMENT MARGIN
- 4. Hl STEAM FLOW/
B. RX TRIP (FROM SI)
C. FWI D. CINCH A E. ESW F. SLI 1.0874 1.1395 1.0718 1.077/1.0122 1.0718 1.0692 10.5 4.51 5.6/3.9 0.2 5.4 7.7 7.7 7.7+ 19.65 11.58/I 9.29 1.1395 5.53 6.68/1 2.68 1.27/28.62 6.47
~ <15.0/25.0
~ <5.0 R <10.0
~ <20.0/30.0
= <15.0/50.0 K<10.0 3.42/5.71 3.86 4.47 13.32/17.32 13.73/31.38 3.53
- 5. HI STM FLOW/
LO STEAM PRESSURE A. Sl (ECCS)
B. RX TRIP 0.3206 0.3206 10.5 7.7 10.82/1 8.521 0.3206
~<13 0/23 0
<<3.0 21.8/4.48 2.6794 (FROM SI)
C. FWI D. CI-PH A E. ESW F. SU 0.3076 0.31 06/0.31 08 0.3076 0.3776 5.6/3.9 0.2 5.4 7.7 7.7+19.65 0.51/27.85 5.71
~ <14.0/48.0
~ <8.0 4.82
~ <8.0 5.91/11.91 M<18.0/28.0 3.18 12.09/1 6.09 13.49/20.15 2.29
ESF RESPONSE TIMES UNIT 1 PARAMETER
- 6. CTMT PRESS HI.HI A. CTMT SPRAY B. SU C. CTMT RECIRC FAN TRANSMITTER 0.3731 0.3663 0.3698 RACK ELECT.
& BKR ESF EQUIPMENT 0.2+ 6A 5.4 598 D!G START TIME D/G LOADTIME 7.7+30.2 TOTALTR 44.87 5.77 598.37 T/S REQUIREMENT
=<45.0
= <7.0 c <660 MARGIN 0.13 1.23 61.63
- 7. S/G LEVEL Hl-Hl A. TURBINE TRIP 0.4848 0.4898 0.26 4.5 0.75
= <2.5
= <11.0 1.75
- 8. S/G LEVEL LO4.0 A. MDAFWP B. TDAFWP 0.8452 2.1207 0.08+2.1 10.14+13.45 7.7+24.86 35.58 25.71
= <60.0
= <60.0 24.42 34.29
ESF RESPONSE TIMES UNIT2 PARAMETER RACK ELECT.
TRANSMITTER 6t BKR ESF EQUIPMENT D/G START TIME D/G LOAD TIME TOTALTR T/S REQUIREMENT MARGIN
B. RX TRIP (FROM SI) 0.4967 0.5701 22/I 1 7.81+16.78 21.29/I 1.5 0.5701
= <24.0/12.0
~ <2.0 2.71/0.5 1.4299 C. FWI D. CI-PH A E. MDAFWP F. ESW 0.4916 0.4967 0.4967 0.4967 8.4/9.6 0.12+4.1 0.16 7.81 7.81+24.88 7.81+19.69 37.37 28.16/0.68
%<60.0
~ <48.0/13.0 3.48
~ <8.0 8.9/17.9 R$ <18.0/28.0 4.51 9.1/10.1 22.63 19.84/1 2.34
B. RX TRIP 0.3566 0.4378 7.81 11.36/19.17 0.4378
= <12.0/24.0
~ <2.0 0.64/4.83 5.622 (FROMSI)
C. ma D. CI-PH A E. MDAFWP F.ESW 0.3514 0.3566 0.3903 0.3903 9.26/8.6 0.1 +4.1 0.16 7.81 7.81+24.84 7.81+18.59 3.35
<<8.0 9.61/I 7.77
= <18.0/28.0 37.24 R <60.0 0.55/28.06
~ <13.0/42.0 8.39/10.23 22.76 12.45/19.95
(
5V-0.9254 7.3
= <10.0 2.87
ESF RESPONSE TIMES UNIT2 PARAMETER RACK ELECT.
TRANSMITTER 8 BKR ESF EQUIPMENT D/G START TIME D/G LOADTIME TOTALTR T/S REQUIREMENT MARGIN
B. RX TRIP (FROM SI)
C. FWI D. Cl PHA E. MDAFWP F. ESW G. SLI 0.3903 0.4741 0.3799 0.3851 0.3903 0.3903 0.3799 8.9/9.6 0.11+4.1 0.16 6.2 7.81 7.81 7.81+24.84 7.81+19.69 11.39/1 9.2 0.4741 3.38 9.29/17.8 37.24 0.55/28.05 6.58
= <12.0/24.0
~ <2.0
<<8.0
= <18.0/28.0 M<60.0
~ < 14.0$/48
~ <8.0 61/4.8 1.5251 4.62 8.71/1 020 22.76 13.45/19.95 1.42
- 5. CTMT PRESS Hl HI A. CTMT SPRAY B. SLI C. CTMT RECIR FAN 0.3798 0.3798 0.3772 1.01+2/49.2 6.2 534 7.81+30.47/7.81 39.87/57.39 6.58 534.38
= <45.0/60.0
~ <7.0
~<600.0 5.13/2.6 I 42 65.62
- 6. S/
LEVELLO-LO A. MDAFWP B.TDA/FWP 0.339 0.3259 0.08+4.1 8.5+14.09 7.81+24.84 37.17 22.92
= <60.0 K<60.0 22.83 37.08
REACTOR TRIP SYSTEM INSTRUMENTATIONRESPONSE TIME UNIT 1 PARAMETER TRANSMITTER RACK ELECTRONICS 8 BKR TOTALTR T/S REQUIREMENT MARGIN
- 1. OT/DT
- 2. PRZ PRESS.LOW 2.5 0.39
- 4. PRZ LEVEL-HIGH
- 6. S/G LEVEL-LOW.L 0.33 0.4 0.3
- 3. PRZ PRESS HIGH 0.39 2.2973%.2448 0.41454.2448 0.3546%.2448 0.4405-0.2448 0.352%.2448 0.8624%.2448 4.5525 0.5597 0.4998 0.5257 0.5072 0,9176
= <6.0
~ <1.0
~ <1.0
= <2.0
= <0.6
= <1.5 1.45 0.44 0.5 1.47 0.093 0.58 UNIT2 PARAMETER
- 1. OT/DT
- 2. PRZ PRESS-LOW
- 3. PRZ PRESS -HIGH
- 4. RCS FLOW-LOW
- 5. S/G LEVEL-LOW.L 3.4 0.26 0.35 0.42 0.3 1.461 %.1813 0.4964%.1813 0.3794%.1813 0.3248%.1813 0.3067%.1813 4.679 0.5751 0.5481 0.5635 0.4254 TRANSMITTER RACK ELECTRONICSSBKR TOTALTR a <6.0
<<1.0
~ <1.0
<<0.6
= <1.5 0.32 0.42 0.4519 0.04 1.07 T/S EQUIPMENT MARGIN NOTES:
- 1. ALLTIMES ARE IN SECONDS
- 2. WORST CASE LOOP SHOWN 3.ALLDATAIS REPRINTED FROM MATERIALSUPPLIED TO HEI. ORIGINALMATERIALDATED 04/05/90 (S. MACY)
oltl :
Reactor Trip System Response Time Evaluation Tables Rp N.:2~HEt-I R
Page 1 of 8 Originator $ Kincaid Date: +I~I)g2 F 0 X B 0 R 0
RESPONSE
MODULE TIME PER Kl LETTER OT OT 12-RPC-02 92F12687 N-2AI-P2V FD-2102 SHT 1 &3 N-2CCA-DC N-2AD-V2H+P N-2AI-P2V N-2CCA-DC N-2CCA-DC N-2AD-L2C-R N-2AI-P2V N-2CCA-DC N-2CCA-DC N-2AD-L2C-R 2000MS 400MS 80MS 2400MS 2000MS 400MS 400MS 10MS 2810MS 2000MS 400MS 400MS 10M 2810MS QT DEV ALARM OP QT RX TRIP OT Q T RX TRIP Common for both Units 1&2 Reactor Trip System Response Time Evaluation Tables R
1 N.:2~8-DI R*.tl Page 2 of 9 Originator S. Kincaid Date: +1~1/2 LOOP ID E
P /FD FOXBORO
RESPONSE
MODULE TIME PER NUMBER LETTER Pressurizer 12-RPC-04
.N-2AI-H2V P r e s s u r e 92F 12687 N-2CCA-DC Low-FDP2101 SHTP'1 N-2AD-L2C-R 37MS 400MS 1 MS 447MS Common for both Units 1 & 2 Reactor Trip System Response Time Evaluation Tables Rp N.:2~7-R*.O Page 3 of 3 Originator $ Kincaid Date:
~10 15/ 2
~LQ L
F 0 XBORO
RESPONSE
M 0 D U L E TIMEPER
~ER LETTER Pressurizer 12-RPC-04 N-2AI-H2V Pressure 92F12687 N-2CCA-DC (High)
FD¹2101 SHT¹1 N-2AO-L2C-R 37MS 400MS 1 MS 447MS Reactor Trip System Response Time Evaluation Tables Rp N.:2~HI!-I R Page 4 of 8 Originator S. Kincaid Date: ~1~1/2 FOXBORO
RESPONSE
M 0 D U L E TIME PER Kl-LET7ER RCS Flow 12-RPC-01 N-2AI-H2V (Low) 92F 12687 N-2CCA-DC FD¹2101 SHT 1&3 N-2AO-L2C-R 37MS 400MS 10M 447MS Common for both Units 1 & 2 Reactor Trip System Response Time Evaluation Tables Rp N.:2~8-p-p R.p Page 5 of5 Originator S. Kincaid Date: +1~15/32 pap E~/
F OXBORO
RESPONSE
M 0DULE TIME PER NUMBER LETTER Pressurizer 12-RPC-03 Level (High) 92F 12687 FD¹2101 SHT 2 N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10MS 447MS Common for both Units 1 A 2 Reactor Trip System Response Time Evaluation Tables Rp N.:2~HI!-1R*.I!
Page5of 8 Originator S Ktncaid Date: 10/1~2 Ula c
RESPONSE
MODULE TIME PER NUMBER LETTER S
t e
a m
12-RPC-05 Generator 92F12687 Level FD-2101 low-low SHT 5 N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37 MS 400MS 1 M 447MS
- Reactor Trip System Time Response Comparison Existing Rack New Rack Tech Spec Existing New New Page7ot8 Loop ID Existing Rack New Rack Electronics Electronics Time Response Time Response Time Response Margin Margin Electronics/Bkr Electronics/Bkr Tot. Resp Time Tot. Resp Time Requirement Negative Margin Comments/
Resolutions Unit 1 OTDT 2.29732448 (2.0525)
(2.5652)
(4.5525)
(5.0652) 2.81 %.2448 2.0525+ 2.5 2.5652+2.5
< =6.0000 1.4475 0.9348 NONE OPDT 2.81 %.2448 (2.5652) 2.5652+2.5 (5.0652)
<=6.0000 0.9348 Pressurizer Press 0.4145%.2448 0.447%.2448 0.39+0.1697 0.202+0.39 (LOW)
(0.1697)
(0.202)
(0.5597)
(0.592)
<%11 0000 OA403 0.408 NONE Pressurizer Press 0.3546%.2448 0.447%.2448 0.39+0.1098 0.39+0.202
<~1.0000 0.5002 0.408 NONE (HIGH)
(0.1098)
(0.202)
(0.4998)
(0.592)
RCP Flow 0.352%.2448 0.447%.2448 0.4+0.1072 0.4+0.202 1.0000 0.4928 0.398 NONE (LOW)
(0.1072)
(0.202)
(0.5072)
(0.602)
Pressurizer Level 0.4405%.2448 0.447%.2448 0.33+0.1957 0,33+0,202
< =2.0000 1.4743 1.467 NONE (HIGH)
(0.1957)
(0.202)
(0.5257)
(0.532)
S/G 0.8624%.2448 OA47%.2448 0.3+0.6176 0.3+0.202 Leveldow low (0.6176)
(0.202)
(0.9176)
(0.502)
<R1.5000 0.5824 0.998 NONE
(<< : Reactor Trip System Time Response Comparison Existing Rack New Rack Tech Spec Existing New New Page8of8 Loop ID Existing Rack Electronics/Bkr Electronics/Bkr Tot. Resp Time Tot. Resp Time Requirement Margin Margin New Rack Electronics Electronics Time Response Time Response Time Response Negative Margin Comments/
Resolutions Unit 2 OTDT OPDT (1.2797)
(2.6287)
(4.6797)
(6.0287) 2.81-0.1813 (2.6287) 3.4+2.6287 (6.0287) 1.461%.1813 2.81%.1813 3.4+1.2797 3.4+2.6287
< =6.0000 1.3203
< = 6.0000
<.0287
-0.0287 Neg. margin using worst response.
Actual times expected to be much shorter.
Pressurizer Press 0.4964-0.1813 0.447%.1813 0.3151+0.26 0.2666+0.26
< =1.0000 (LOW)
(0.3151)
(0.2666)
(0.5751)
(0.5266) 0.4249 0.4734 NONE Pressurizer Press 0.3794-0.1813 OA47-0.1813 0.1981+0.3S 0.2666+0.3S
< =1.0000 0.4519 0.3834 NONE (HIGH)
(0.1981)
(0.2666)
(0.5481)
(0.6166)
RCS Flow 0.3248%. 1 813 (0.1435)
(0.2666)
(0.5635)
(0.6866) 0.447%.1813 0.42+0.1435 0.2666+0.42
<=1.0000 0.4365 0.3134 NONE QG 0.3067%.1813 0.447%.1813 0.3+0.1254 0.3+0.2666
<=1.5000 1.0746 0.9334 NONE Level4ow low (0.1254)
(0.2666)
I (0.4254)
(0.5666)
Engineered Safety Features Response Time Evaluation Tables Rp N.:2~HEt-1R
.G Page 1 of+1 Originator: ~Kincaid Date: +1~1/2 DO
~i FOXBORO MODULE NUMBER
RESPONSE
TIME PER LET7ER 92F 12687-FD-2103 SHT P4 Containment 12-RPC-07 Pressure-High A.
Safety Inj.
N-2AI-H2V N-2CCA-SC N-2A0-L2C-R 37MS 400MS 10MS 447MS B. RX Trip N-2AI-H2V N-2CCA-SC N-2AO-L2C-R 37MS 400MS 10MS 447MS C. FW Isol.
D. Cont Isol.
N-2AI-H2V N-2CCA-SC N-2AO-L2C-R N-2AI-H2V N-2CCA-SC N-2A0-L2C-R 37MS 400MS 10M 447MS 37MS 400MS 10MS 447MS E. Essential Service Water N-2AI-H2V N-2CCA-SC N-2AD-L2L-R 37MS 400MS 10MS 447MS Engineered Safety Features Response Time Evaluation Tables Rl N.:2~H-DIR*.tl Page 2 of +1 Originator: $ Kincaid Date: ~10/IS/ 2 Ulo
~cl FOXBORO
RESPONSE
M 0 D U L E TIMEPER NUMBER LETTER Pressurizer 12-RPC-04 P r e s s u r e 92F12687-FD-2101 (Low)
SHT 1
FD-2102 SHT 2 A.
Safety Inj.
N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10MS 447MS B. RX Trip (From SI)
N-2AI-H2V N-2CCA-DC-N-2AO-L2C-R 37MS 400MS 10MS 447MS C. FW Isol.
N-2AI-H2V N-2CCA-DC N-2AO-C2C-R 37MS 400MS 10MS 447MS D. Cont Isol.
(PHA)
N-2AI-H2V N-2CCA-DC N-2A0-L2C-R 37MS 400MS 10MS 447MS E.
Essential Service Water N-2AI-H2V N-2CCA-DC N-2A0-L2C-R 37MS 400MS 10MS 447MS
Engineered Safety Features Response Time Evaluation Tables R p N.: 2~HK-I R
. 9 Page $ of +1 Originator: ~Kineaid Date: +1~i/2 nlQ F 0 X B'0 R 0
RESPONSE
MODULE TIME PER NUMBER LETTER Steam Line 12-RCP-08 Q/P-High 92F12687-FD-2103 SHT 2 A.
Safety Inj.
N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10MS 447MS B. RX Trip (from SI)
N-AI-H2V N-2CCA-DC N-2A0-L2C-R 37MS 400MS 10MS 447MS Isol.
N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10M 447MS D. Cont Isol.
(PHA)
N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10MS 447MS E. Essential Service Water N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10M 447MS Engineered Safety Features Response Time Evaluation Tables R 2 Pl.:p~l 2
. 2 Page 4 of +1 Originator:
pt Kincaid Date: +1~192 npp
~f FOXBORO MODULE MBER
RESPONSE
TIME PER LETTER High Steam Flow/Lo-Lo Tavg A.
Safety Inj.
B. RX Trip (From SI) 12-RPC-02 92F 12687 FD¹2103 SHT 1
FD¹2103 SHT 3 FD¹2104 SHT 2864 N-2AI-P2V N-2CCA-DC N-2A0-L2C-R N-2AI-P2V N-2CCA-DC N-2A0-L2C-R 2000MS 400MS 10MS 2410MS 2000MS 400MS 10MS 2410MS C. Feedwater Isol.
N-2AI-P2V N-2CCA-DC N-2A0-L2C-R 2000MS 400MS 10MS 2410MS D. Cont Isol.
E.
Essential Service Water N-2AI-P2V N-2CCA-DC N-2AO-L2C-R N-2AI-P2V N-2CCA-DC N-2AO-L2C-R 2000MS 400MS 10M 2410MS 2000MS 400MS 10MS 2410MS F.
Steam Line Isol.
N-2AI-P2V N-2CCA-DC N-2A0-L2C-R 2000MS 400MS 1 MS 2410MS Engineered Safety Features Response Time Evaluation Tables RR N.:2RRNRIDIR*.R Page $ of +I Originator: ~Kincai Date: ~10/1 92
~DID ~l FD¹2103 High Steam SHT 1&3 Flow/Low S
t e
a m
FD¹2103 Pressure SHT 2&4 FOXBORO MODULE
~NR
RESPONSE
TIMEPER LETTER A.
Safety Inj.
N-2AI-H2V N-2CCA-DC N-2A0-L2C-R 37MS 400MS 10MS 447MS B. RX Trip N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10MS 447MS C. Feedwater Isol.
D. Cont Isol.
N-2AI-H2V N-2CCA-DC N-2A0-L2C-R N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10MS 447MS 37MS 400MS 10MS 447MS E.
Essential Service Water N-2AI-H2V N-2CCA-DC N-2A0-L2C-R 37MS 400MS 10MS 447MS F.
Steam Line Isol.
N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10MS 447MS Engineered Safety Features Response Time Evaluation Tables ll 2 N.: 20JHH-LIH.2 Page Q of +1 Originator: $ Kincaid Date: +1~1/2 L~l
~HC I D Low Steam 12-RPC-08 Pressure 92F12687 FD¹2103 SHT 2&4 FD¹2104 SHT 1&3 FOXBORO MODULE NUMBER N-2AI-H2V N-2CCA-DC N-2AO-L2C-R
RESPONSE
TIMEPER LETTER
-37MS 400MS jill 447MS LOOP ID ECP FD FOXBORO MODULE NUMBER
RESPONSE
TIMEPER LETTER Containment 12-RPC-07 Pressure 92F12687 (Hi Hi)
FD¹2103 SHT 4 A.
Con t Sprays N-2AI-H2V N-2CCA-SC N-2A0-L2C-R 37MS 400MS 10MS 447MS B.
Steam Line Isol.
N-2AI-H2V N-2CCA-SC N-2AO-L2C-R 37MS 400MS 10MS 447MS C.
Cont Rescirc Flow N-2AI-H2V N-2CCA-SC N-2A0-L2C-R 37MS 400MS 1 M 447MS Engineered Safety Features Response Time Evaluation Tables Rl <<N.:2~HH-1R
.0 Page 7 of +I Originator: ~Kine id Date: +1~15/~2
~CI FOXBORO MODULE N MBER
RESPONSE
TIMEPER LETTER S
t e a
m 12-RPC-05 G en erato r 92F12687 Level FDP2101 (Hi Hi)
SHT 5 A.
Turbine Trip B. Feedwater Isol.
N-2AI-H2V N-2CCA-DC N-2AO-L2C-R N-2AI-H2V N-2CCA-DC
'-2AO-L2C-R 37MS 400MS 10MS 447MS 37MS 400MS 10MS 447MS
pp ala :
Engineered Safety Features Response Time Evaluation Tables Rp PN.:2RR
-222M.O Page 8 of +1 Originator: S. Kincaid Date: 10/15/02 F 0 XB OR 0
RESPONSE
MODULE TIME PER N~M LE%iER S t e a
m 12-RPC-05 Generator 92F12687 Level FD¹2101 (Lo Lo)
SHT 5 A. Motor Driven Aux Feed water pump B.
Turbine Driven Aux Feedwater pump N-2AI-H2V N-2CCA-DC N-2A0-L2C-R N-2AI-H2V N-2CCA-DC N-2AO-L2C-R 37MS 400MS 10M 447MS 37MS 400MS 10MS 447MS
- Engineered Safety Features ime Response Comparison Loop ID Existing Rack Electronics/Bkr New Rack Electronics/Bkr Tech Spec Time Response Requirement Existing Time Response Margin New Time Response Margin New Negative Margin Page 9 of 13 Comments/
Resolutions Unit 1 A. SI B. RX trip C. FWI D. CI(ph. A)
E. ESW F. SLI High Steam Flow/Low Steam Pressure 0.3206 0.3206 0.3076 0.3106/0.318 0.3076 0.3076 0.447 0.447 0.447 0.447/0.447 0.447 0.447
< =27.0/37.0
< ~3.0
< =8.0
< ~18.0/28.0
<~ 14.0/48.0
<=11.0 16.18/18.48 2.6794 3.18 12.09/1 6.09 13.49/20.15 5.29 16.05/18.35 2.553 3.04 11.95/15.96 13.35/20.01 5.15 NONE NONE NONE NONE NONE NONE Containment Pressure (Hl-Hl)
A. Cont Spray B. Steam Line Isol C. Cont Recirc Flow 0.3731 0.3663 0.3698 0.447 0.447 0.447
<=45.0
< R10.0
<=660 0.1269 4.42337 61.6302 0.053 4.343 61.553 NONE NONE NONE Steam Generator Level (Hl-Hi)
A. Turbine Trip 0.4898 0.4898 0.447 0.447
< =2.5
<=11.0 1.7502 6.0002 1.793 6.043 NONE NONE
- Engineered Safety Features ime Response Comparison Loop ID Existing Rack Electronics/Bkr New Rack Electronics/Bkr Tech Spec Time Response Requirement Existing Time Response Margin New Time Response Margin Negative Margin Page 10 of 13 Comments/
Resolutions A. SI B. RX Trip C. FWI D. CI (Ph. A)
E. ESW Cont Pressure High 0.3715 0.4366 0.3637 0.3663/0.3693 0.3637 0.447 0.447 0.447 OA47/OA47 0.447/0.447
<~27.0
< =3.0
<=8.0
<=18.0/28.0
< =13.0/48.0 7.37 2.56 3.13 12.04/16.03 12.44/20.1 7.2945 2.549 3.046 11.959/15.95 12.356/20.01 NONE NONE NONE NONE NONE A. SI B. RX Trip C. FWI D. Cl(Ph. A)
E. ESW Pressurizer Pressure.Low 0.4815 0.6698 0.4685 0.4815 0.4685 0.447/0.447 0.447 0.447 0.447 0.447/0.447
< =27.0/27.0
< a3.0
<=8.0
<=18,0
<~48.0/13.0 7.26/I 6.02 2.33 3.02 5.92 19.99/12.33 7.2945/16.05 2.5528 3.0415 5.9545 20.011/12.35 NONE NONE NONE NONE NONE A. Sl Steam Line D/P High B. RX Trip C. FWI D. Cl(Ph. A)
E. ESW 0.4037 OA623 0.3946 0.3772/0.4004 0.3946 0.447 0.447 OA47 0.447/0.447 0.447
<~27.0/37.0
< R3.0
<~8.0
< ~18.0/28.0
< =13.0/48.0 1 6.1/I 8.4 2.54 3.1 12/16 12.41/20.06 16.056/18.35 2.555 3.0476 1 1.9302/15.95 12.3576/20 NONE NONE NONE NONE NONE
- Engineered Safety Features Time Response Comparison Loop ID Existing Rack Electronics/Bkr New Rack Electronics/Bkr Tech Spec Time Response Requirement Existing Time Response Margin New Time Response Margin New
- Negative Margin Page 11 of 13 Comments/
Resolutions High Steam Flow/LoLo TAVG A. SI B. RX Trip C. FWI D. CI (Ph. A)
E. ESW F. SLI 1.0874 1.1395 1.0718 1.077/1.0122 1.0718 1.0692 2.41 2,41 2A1 2.41/2.41 2.41 2.41
< ~29.0/39.0
<=5.0
< 5510.0
< =20.0/30.0
< =15.0/50.0
<=13.0 17.42/1 9.71 3.8605 4.47 13.32/17.32 13.73/21.38 6.53 16.0974/18.3874 2.59 3.1318 11.987/15.922 12.3918/20.0418 5.1892 NONE NONE NONE NONE NONE NONE Steam Generator Level (Lo-Lo)
A. MDAFWP B. TDA FWP 0.8452 2.1207 OA47 0.447
< 5-60.0
<=60.0 35.5852 34.2893 35.9834 35.963 NONE NONE Unit 2 A. Sl Pressurizer Pressure Lo B. RX Trip C. FWI D. CI (Ph. A)
E. MDAFWP F. ESW 0.4967 0.5701 0.4916 0.4967 0.4967 0.4967 0.447 0.447 0.447 0.447 0.447 0.447
< 5527.0/27.0
< =3.0
< 5-8.0
< &18.0
< =60.0
<~48.0/t 3.0 5.7033/15.5033 2.4299 4.5084 9.1033 22.6333 19.8433/1 2.3433 5.753/15.55 2.5553 4.553 9.5533 22.683 19.893/4 2.39 NONE NONE NONE NONE NONE NONE
'ttachment 5: Engineered Safety Features lme Response Comparison Loop ID Existing Rack Electronics/Bkr New Rack Electronics/Bkr Tech Spec Time Response Requirement Existing Time Response Margin Time Response Margin New Negative Margin Comments/
Resolutions A. SI B. RX Trip C. FWI D. CI(ph. A)
E. MDAFWP F. ESW Steam Line D/P High 0.3566 0.4378 0.3514 0.3566 0.3903 0.3903 0.447 0.447 0.447 0.447 0.447 0.447
<= 27.0/37.0
<<3.0
< ~8.0
< =18.0/28.0
< =60.0
< = 13.0/48.0 15.6434/I 7.8334 2.5622 4.6486 8.3834/10.2334 22.7597 12.4497/19.9497 15.553/1 7.74 2.553 4.553 8.293/10.1426 22.703 12.393/I 9.88 NONE NONE NONE NONE NONE NONE Hi Steam Flow/
Lo.Lo TAVG A. SU 0.9254 2.41
<=13.0 5.8746 4.39 NONE A. SU Steam Line Pressure Lo B. RX Trip D. CI (Ph. A)
0.3903 0.4741 0.3799 0.3851 0.3903 0.3903 0.3799 0.447 OA47 OA47 OA47 0.447 0.447 0.447
< =27.0/37.0
< =3.0
< ~8.0
<=18.0/28.0
< IR60.0
< =14.0/48.0
<%11.0 15.6097/17.7997 2.5259 4.6201 8.7149/10.2049 22.7597 13.4497/1 9.9497 4.4201 15.553/1 7.733 2.553 4.553 8.653/10.142 22.703 13.393/19.88 4.353 NONE NONE NONE NONE NONE NONE NONE
- Engineered Safety Features ime Response Comparison Loop ID Existing Rack Electronics/Bkr New Rack Electronics/Bkr Tech Spec Time Response Requirement Existing Time Response Margin New Time Response Margin New Negative Margin Page 13 of 13 Comments/
Resolutions Containment Pressure Hi-Hi A. Cont Spray B. SLI C. Cont Recirc Flow 0.3798 0.3798 0.3772 0.447 0.447 0.447
< =45.0
< =10.0
< =600.0 5.1302 3 4202 65.6228 5.063 3.353 65.553 NONE NONE NONE Steam Generator Level Lo Lo A. MDAFWP B. TDA FWP 0.339 0.3259 0.447 0.447
<=60.0
<=60.0 22.831 37.0841 22.723 36.963 NONE NONE