ML17329A716

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DC Cook Nuclear Plant Units 1 & 2 Summary Rept for Response Time Evaluations Reactor Protection & Control Sys Replacement Project.
ML17329A716
Person / Time
Site: Cook  American Electric Power icon.png
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)
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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.

D.C. Cook Units l 8c 2 Summary Report for Response Time Evaluation Reactor Protection System Replacement Report Number 2985-HEI-Ol Rev. 0 Page of 4 AEP-RTE 92i2i80080 92i2i6 1 PDR ADQCK 050003i5 P, PDR

~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 Summary Report for Response Time Evaluation Reactor Protection System Replacement Report Number 2985-HEI-01 Rev. 0 Page 2 of 4

  • EP-RTE

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 Io 30 9'2-Reviewed By Date Approved By Date D.C. Cook Units l &, 2 Summary Report for Response Time Evaluation Reactor Protection System Replacement Report Number 2985-HEI-01 Rev. 0 Page 3 of 4 AEP-RTE

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

. Better Vendor Documentation Compare of Response Time to Technical Specification's (Acceptable)

Refine Calculated Response Time YES Better Vendor Documentation Compile Data of Response Time and Produce Final Re ort Consider Possible Tech Spec Change END Figure 1 D.C. Cook Units 1 8r,2 Summary Report for Response Time Evaluation l Reactor Protection System Replacement Report Number 2985-HEW)1 Rev. 0 I Page 4 of 4 AEP-RYE

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TABLE 3.3 5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATINC SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

l. Manual Safety In)ection (ECCS) Not Applicable Feedwater Isolation Not hpplicable Reactor Trip (SI) Not Applicable Containment Isolation-Phase h Not hpplicable Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Essential Service Water System Not Applicable
b. Containment Spray Not Applicable Containmcnt Isolation-Phase B" Not Applicable Containment Purge and Exhaust Isolation Not Applicable Containment Air Recirculation Fan Not Applicable
c. Containmcnt Isolation-Phase h" Not Applicable Containment Purge and Exhaust Isolation Not Applicable
d. Stcam Line Isolation Not Applicable
2. Containment Prcssur'c-Hi h Safety Infection (ECCS) Less than or equal to
27. OQQ/27. 0++
b. Reactor Trip (from SI) Less than or equal to 3.0 C. Fecdwatcr Isolation Less than or equal to 8.0
d. Containment Isolation-Phase "A" Less then or equal to 18.09/28.00 c Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwatcr Pumps Not Applicable Essential Service Water System Less than or equal to 13.0g/48.00 COOK NUCLEAR PRATE - UNIT 1 3/4 3-27 AME2G)MENT g j$ ~ 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) Less than or equal to 27 088/27 0++
b. Reactor Trip (from SZ) Less than or equal to 3.0
c. Feedwater Isolation I,ess than or equal to 8.0
d. Containment Isolation-Phase A, Less than or equal to 18.0P
e. Containment Purge and Exhaust Isolation Not Applicable
f. Auxiliary Feedwater Pumps Not Applicable
g. Essential Service Water System Less mohan or equal to 48-0 /13.08
4. Dlfferertial Pressure Between Steam Lines-High
a. Sa ety Injection (ECCS) Less than or equal to 27.088/37.0Ia
b. Reac or Trip (from SZ) Less than or equal to 3.0 C~ Feedwater Isolation Less than or equal to 8.0 d~ Con" ainment Isolation-Phase "A" Less than or equal to 18.0P/28.0SP Q ~ Cortainment Purge and Exhaust Isolation Not Applicable
f. Auxiliary Feedwate 'Pumps Not Applicable ge Essential Service Water System Less than or equal to 13.08/48.0PP
5. Steam Flow 'n Two Steam Lines - Hi h Coincident with Tave--Low-Low
a. Sa ety Injection (ECCS) Less than or equal to 29.09(1/39.08
b. Reactor Trip (from SZ)* Less than or equal to 5.0 C a" Feedwator Isolation Less than or equal to 10.0
d. Containment Isolation-Phase "A" Less than or equal to 1

20.0P/30.OILS

e. Con ainment Purge ar 'xhaust Isolation Not Applica'".'<!
f. Auxiliary Feedwater Pumps Not Applicable go Essential Service Water System Less than or equal to 15.01'/50.0SP
h. Steam Line Isolation Le s s than or equal 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 INITIATING SIGNAL 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) Less than or equal to 27.0QQ/37.0Q
b. Reactor Trip (from SI) Less than or equal to 3.0
c. Feedvater Isolation Less than or equal to 8.0
d. Containment Isolation-Phase "A" Less than or equal to 18.04/28.0m
e. Containment Purge and Exhaust Isolation Not Applicable
f. Auxiliary Feedvater Pumps Not Applicable
g. Essential Service Mater System Less than or equal 'to 14.0~/48.0~
h. Steam Line Isolation Less than or equal to 11.0
7. Containment Pressure--High-Hizh a Containment Spray Less than or equal to 45.0
b. Containment Isolation-Phase "B" Not Applicable C. Steam Line Isolation Less than or equal to 10.0
d. Containment Air Recirculation Fan Less than or equal to 660.0
8. Steam Generator t:ater Level--Hi h-High
a. Turbine Trip Less than or equal to 2.5
b. Feedvater Isolation Less than or equal to 11.0
9. Steam Generator Mater Level--Lov-Lov a.."fotor Driven Auxiliary Feedvater Pumps Less than or equal to 60.0
b. Turbine Driven Auxiliary Feedvater Pumps 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) Not Applicable Feedvater Isolation Not Applicable Reactor Trip (SI) Not Applicable Containment Isolation-Phase 'A" Applicable 'ot Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedvater Pumps . Not Applicable Essential Service Water System Not Applicable
b. Containment Spray Not Applicable Containment Isolation-Phase '3" Not Applicable Containment Purge and Exhaust Isolation Not Applicable Containment hi.r Recirculation Fan Not Applicable
c. Containment Isolation-Phase "A" Not hppli.cable Containment Purge and Exhaust Isolation Not Applicable
d. Steam Line Isolation Not Applicable
2. Containment Pressure-Hi h
a. Safety Infection (ECCS) Less than or equal to
27. OQQ/27. 0++
b. Reactor Trip (from SI) Less than or equal to 3.0 c Feedvater Isolation Less than or equal to 8.0
d. Containment Isolation-Phase "A" Not Appli,cable e ~ Containment Purge and Exhaust Isolation Not Applicable
f. Auxiliary Feedvater Pumps Not hppli.cable Essential Service Water System 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 INITIATING SIGNAL AND FUNCTION KESPONSE TIME IN SECONDS

3. Pressurixcr Pressure-Lov Safety In)ection (ECCS) Less than or equal to 27.0QQ/27.0++
b. Reactor Trip (from SI) Less than or equal to 3.0 C. Fccdvater Isolation Less than or equal to 8.0
d. Containmcnt Isolation - Phase "h" Less than or equal to 18.0¹
e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedvater Pumps Less than or equal to 60.0 Essential Service Vater System Less than or equal to 48.0++/13.0¹
4. Differential Prcssure Betvcen Steam Lines - Hi h
a. Safety In5ection (ECCS) Less than or equal to 27.0/37.0Q
b. Reactor Trip (from SI) Less than or equal to 3.0
c. Feedvater Isolation Less than or equal to 8.0
d. Containment Isolation - Phase "h" Less than or equal to 18.0¹/28.0¹¹ Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedvater Pumps Less than or equal to 60.0 Essential Service Vater System Less than or equal to 13.0¹/48.0¹¹
5. Steam Flov in Tvo Steam Lines - Hi h Coincident vith Tav --Lov-Lov
a. Safety In) ection (ECCS) Not Applicable
b. Reactor Trip (from SI) Not Applicable Ce Feedvater I~" l~-.'on Not Applicable
d. Containment Isolation-Phase "h" Not Applicable Co Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedvater Pumps Not Applicable g~ Essential Service Vater System Not Applicable
h. Stcam Line Isolation 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
a. Safety Injection (ECCS) Less than or equal to 27.0QQ/37.0Q
b. Reactor Trip (from SI) Less than or equal to 3.0
c. Feedwater Isolation Less than or equal to 8.0
d. Containment Isolation-Phase "A" Less than or equal to 18.0¹/28.0¹¹
e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 Essential Service Mater System Less than or equal to 14.0¹/48.0¹¹
h. Steam Line Isolation Less than or equal to 11.0
7. Containment Pressure--Hi h-Hi h
a. Containment Spray Less than or equal to 45.0
b. Containment Isolation-Phase "B" Not Applicable C. Steam Line Isolation Less than or equal to 10.0
d. Containment Air Recirculation Fan Less than or equal to 600.0
8. Steam Generator Mater Level--Hi h-Hi h
a. Turbine Trip Less than or equal to 2.5
b. Feedwater Isolation Less than or equal to 11.0
9. Steam Generator Mater Level--Low-Low
a. Motoz'riven Auxiliary Feedwater Pumps Less than or equal to 60.0
b. Turbine Driven Auxiliary Feedwater Pumps 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 Less than or equal to 60.0
12. Reactor Coolant Pum Bus Undervolta e
a. Turbine Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 134 COOK NUCLEAR PLANT - UNIT 2 3/4 3-28 AMENDMENT NO. gg, gP7, Pgg 142

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

+aPo+ ~~Art- a9'8s-gas-og The FOXbarO COmpany Foxboro, Massachusetts, USA.02035 ~ Tele phone (6t7) 543-6750 FTAEP-020 TO:

American Electric Potter DATE: 8/5/92 Service Corp.

1 Riverside Plaza Columbus, Ohio

REFERENCE:

P.O. C-8741 432]5 S.O. 92F12687, 88 ATTENTION: Mr. William G. Sotos GENTLEMEN: wc ARc cNcLostNO FoR YoUR Usc TNc FoccowtNO DOOUHcNTS tNDtcATco BY (x).

REVIsIDN t)r O

r DESCR I PTI ON C X NUM BE R OR cc X 0 R 0 0 IC O

rc 4.

DATF X < Tl TLE tal rc Il. L. e ~ 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) MARKCD

'Wl TH YOUR APPROVAL AND/OR COHHCNTSi RCTURNCD To US BY 1 tt REMARKS t f

/q g 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 CPS (milliseconds) N-2AI-C2L 20 0071 N-2AI-H2V 37 0030 N-2AI-I2V 37 0030 N-2AI-P2V 2000 0028 N-2AI-T2V 1000 0027 N-2CCA-S 200 1182 N-2CCA-D 200 1182 N-2AO-V2H 80 0029 N-2AO-L2C-R 10 0096 ~ I Notes: Specifications, are based upon Foxboro Corporate Product Specifications (CPS) as listed.

2. 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 RACK ELEC. D/G START TIME Qfogt PARAMETER TRANSMITTER 8$ BKR ESF EQUIPMENT D/G LOAD TIME TOTALTR 5SIPMEH+~geM NCHENT'/S MARGIN

1. CONTAINMENT PRESSURE-HIGH A. SI (ECCS) 0.3715 7.7+6.76 19.63 = <27.0 7.37 B. RX TRIP 0.4366 OA366 $? <3.0 2.56 (FROM SI)

C. FWI 0.2637 4.51 4.87  ?? <8.0 3.13 D. CI-PH A 0.3663/0.3693 5.6/3.9 7.7 5.96/1 1.97 ?? <18.0/28.0 12.04/16.03 E. ESW 0.3637 0.2 7.7+19.65 0.56/27.9 = <13.0/48.0 1 2.44/20.1

2. PRZ PRESSURE LOW A. SI (ECCS) 0.4815 10.5 7.7/7.7+ 6.76 19.74/10.98 ?? <27.0/13.0 7.26/2.02 B. RX TRIP 0.6698 0.6608  ?$ <3.0 2.33 (FROM SI)

C. FWI OA 685 4.51 4.98  ?? <8.0 3.02 D. CI-PH A 0.4815 3.9 7.7 12.08  ?$ <18.0 5.92 E. ESW 0.4685 0.2 7.7+19.65 28.01/0.6885 ?8<48.0/13.0 19.99/1 2.33

3. STEAM UNE D/P -HIGH A. Sl(ECCS) 0.4037 10.5 7.7 10.9/18.6  ?? <13.0/23.0 2.1/4.4 B. RX TRIP 0.4623 0.4623  ?? <3.0 2.54 (FROM SI)

C. FWI 0.3946 4.51 4.9  ?? <8.0 D. CI-PH A 0.3972/0.4004 5.6/3.9 7.7 6/12  ?? <18.0/28.0 12/16 E. ESW 0.3946 0.2 7.7+19.65 0.59/27.94  ?? <13.0/48.0 12.41/20 ESF RESPONSE TIMES UNIT 1 RACK ELECT. D/G START TIME PARAMETER TRANSMITTER 8 BKR ESF EQUIPMENT D/G LOAD TIME TOTAL TR T/8 REQUIREMENT MARGIN

4. Hl STEAM FLOW/

LO-LO TAVE A. SI (ECCS) 1.0874 10.5 7.7 11.58/I 9.29 ~ <15.0/25.0 3.42/5.71 B. RX TRIP 1.1395 1.1395 ~ <5.0 3.86 (FROM SI) C. FWI 1.0718 4.51 5.53 R <10.0 4.47 D. CINCH A 1.077/1.0122 5.6/3.9 7.7 6.68/1 2.68 ~ <20.0/30.0 13.32/17.32 E. ESW 1.0718 0.2 7.7+ 19.65 1.27/28.62 = <15.0/50.0 13.73/31.38 F. SLI 1.0692 5.4 6.47 K <10.0 3.53

5. HI STM FLOW/

LO STEAM PRESSURE A. Sl (ECCS) 0.3206 10.5 7.7 10.82/1 8.521 ~<13 0/23 0 21.8/4.48 B. RX TRIP 0.3206 0.3206 <<3.0 2.6794 (FROM SI) C. FWI 0.3076 4.82 ~ <8.0 3.18 D. CI-PH A 0.31 06/0.31 08 5.6/3.9 7.7 5.91/11.91 M<18.0/28.0 12.09/1 6.09 E. ESW 0.3076 0.2 7.7+19.65 0.51/27.85 ~ <14.0/48.0 13.49/20.15 F. SU 0.3776 5.4 5.71 ~ <8.0 2.29 ESF RESPONSE TIMES UNIT 1 RACK ELECT. D!G START TIME PARAMETER TRANSMITTER & BKR ESF EQUIPMENT D/G LOAD TIME TOTALTR T/S REQUIREMENT MARGIN

6. CTMT PRESS HI.HI A. CTMT SPRAY 0.3731 0.2+ 6A 7.7+30.2 44.87 =<45.0 0.13 B. SU 0.3663 5.4 5.77 = <7.0 1.23 C. CTMT RECIRC 0.3698 598 598.37 c <660 61.63 FAN
7. S/G LEVEL Hl-Hl A. TURBINE 0.4848 0.26 0.75 = <2.5 1.75 TRIP 0.4898 4.5 = <11.0
8. S/G LEVEL LO4.0 A. MDA FWP 0.8452 0.08+2.1 7.7+24.86 35.58 = <60.0 24.42 B. TDA FWP 2.1207 10.14+13.45 25.71 = <60.0 34.29

ESF RESPONSE TIMES UNIT 2 RACK ELECT. D/G START TIME PARAMETER TRANSMITTER 6t BKR ESF EQUIPMENT D/G LOAD TIME TOTAL TR T/S REQUIREMENT MARGIN

1. PRE PRESS-LOW A. SI (ECCS) 0.4967 22/I 1 7.81+16.78 21.29/I 1.5 = <24.0/12.0 2.71/0.5 B. RX TRIP 0.5701 0.5701 ~ <2.0 1.4299 (FROM SI)

C. FWI 0.4916 3.48 ~ <8.0 4.51 D. CI-PH A 0.4967 8.4/9.6 7.81 8.9/17.9 R$ <18.0/28.0 9.1/10.1 E. MDA FWP 0.4967 0.12+4.1 7.81+24.88 37.37  %<60.0 22.63 F. ESW 0.4967 0.16 7.81+19.69 28.16/0.68 ~ <48.0/13.0 19.84/1 2.34

2. STM UNE D/P HIGH A. SI (ECCS) 0.3566 7.81 11.36/19.17 = <12.0/24.0 0.64/4.83 B. RX TRIP 0.4378 0.4378 ~ <2.0 5.622 (FROMSI)

C. ma 0.3514 3.35 <<8.0 D. CI-PH A 0.3566 9.26/8.6 7.81 9.61/I 7.77 = <18.0/28.0 8.39/10.23 E. MDAFWP 0.3903 0.1 +4.1 7.81+24.84 37.24 R <60.0 22.76 F.ESW 0.3903 0.16 7.81+18.59 0.55/28.06 ~ <13.0/42.0 12.45/19.95

3. Hl STM FLOW LO-LO TAVG A. SI ( 0.9254 7.3 = <10.0 2.87 5V-

ESF RESPONSE TIMES UNIT 2 RACK ELECT. D/G START TIME PARAMETER TRANSMITTER 8 BKR ESF EQUIPMENT D/G LOAD TIME TOTAL TR T/S REQUIREMENT MARGIN

4. STM LINE PRESS LOW A. SI (ECCS) 0.3903 7.81 11.39/1 9.2 = <12.0/24.0 61/4.8 B. RX TRIP 0.4741 0.4741 ~ <2.0 1.5251 (FROM SI)

C. FWI 0.3799 3.38 <<8.0 4.62 D. Cl PHA 0.3851 8.9/9.6 7.81 9.29/17.8 = <18.0/28.0 8.71/1 020 E. MDA FWP 0.3903 0.11+4.1 7.81+24.84 37.24 M<60.0 22.76 F. ESW 0.3903 0.16 7.81+19.69 0.55/28.05 ~ < 14.0$ /48 13.45/19.95 G. SLI 0.3799 6.2 6.58 ~ <8.0 1.42

5. CTMT PRESS Hl HI A. CTMT SPRAY 0.3798 1.01+2/49.2 7.81+30.47/7.81 39.87/57.39 = <45.0/60.0 5.13/2.6 I B. SLI 0.3798 6.2 6.58 ~ <7.0 42 C. CTMT RECIR 0.3772 534 534.38 ~<600.0 65.62 FAN
6. S/ LEVEL LO-LO A. MDA FWP 0.339 0.08+4.1 7.81+24.84 37.17 = <60.0 22.83 B.TDA/FWP 0.3259 8.5+14.09 22.92 K <60.0 37.08

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIME UNIT 1 PARAMETER TRANSMITTER RACK ELECTRONICS 8 BKR TOTAL TR T/S REQUIREMENT MARGIN

1. OT/DT 2.5 2.2973%.2448 4.5525 = <6.0 1.45
2. PRZ PRESS.LOW 0.39 0.41454.2448 0.5597 ~ <1.0 0.44
3. PRZ PRESS HIGH 0.39 0.3546%.2448 0.4998 ~ <1.0 0.5
4. PRZ LEVEL-HIGH 0.33 0.4405-0.2448 0.5257 = <2.0 1.47
5. RCS FLOW.LOW 0.4 0.352%.2448 0.5072 = <0.6 0.093
6. S/G LEVEL-LOW.L 0.3 0.8624%.2448 0,9176 = <1.5 0.58 UNIT 2 PARAMETER TRANSMITTER RACK ELECTRONICSSBKR TOTALTR T/S EQUIPMENT MARGIN
1. OT/DT 3.4 1.461 %.1813 4.679 a <6.0 0.32
2. PRZ PRESS-LOW 0.26 0.4964%.1813 0.5751 <<1.0 0.42
3. PRZ PRESS -HIGH 0.35 0.3794%.1813 0.5481 ~ <1.0 0.4519
4. RCS FLOW-LOW 0.42 0.3248%.1813 0.5635 <<0.6 0.04
5. S/G LEVEL-LOW.L 0.3 0.3067%.1813 0.4254 = <1.5 1.07 NOTES: 1. ALLTIMES ARE IN SECONDS
2. WORST CASE LOOP SHOWN 3.ALL DATA IS REPRINTED FROM MATERIALSUPPLIED TO HEI. ORIGINAL MATERIALDATED 04/05/90 (S. MACY)

Attachment 4: 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 oltl Kl LETTER OT OT 12-RPC-02 QT 92F12687 N-2AI-P2V 2000MS DEV FD-2102 SHT 1 &3 N-2CCA-DC 400MS ALARM N-2AD-V2H+P 80MS 2400MS OP QT N-2AI-P2V 2000M S RX TRIP N-2CCA-DC 400MS N-2CCA-DC 400MS N-2 AD-L2C-R 10MS 2810MS OT Q T N-2AI-P2V 2000MS RX TRIP N-2CCA-DC 400MS N-2CCA-DC 400MS N-2AD-L2C-R 10M 2810MS Common for both Units 1&2 Attachment 4: 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 FOXBORO RESPONSE MODULE TIME PER LOOP ID E P /FD NUMBER LETTER Pressurizer 12-RPC-04 .N-2AI-H2V 37MS P re s s u re 92F 12687 N-2CCA-DC 400MS Low- FDP2101 SHTP'1 N-2AD-L2C-R 1 MS 447MS Common for both Units 1 &2 Attachment 4: Reactor Trip System Response Time Evaluation Tables Rp N.:2~7- R*.O Page 3 of 3 Originator $ Kincaid Date: ~10 15/ 2 F 0 XBORO RESPONSE M 0 D U L E TIMEPER ~LQ L ~ER LETTER Pressurizer 12-RPC-04 N-2AI-H2V 37MS Pressure 92F12687 N-2CCA-DC 400MS (High) FD¹2101 SHT¹1 N-2AO-L2C-R 1 MS 447MS Attachment 4: 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 RCS Flow 12-RPC-01 Kl-M 0 D U L E N-2AI-H2V

RESPONSE

TIME PER LET7ER 37MS (Low) 92F 12687 N-2CCA-DC 400MS FD¹2101 SHT 1&3 N-2AO-L2C-R 10M 447MS Common for both Units 1 &2

Attachment 4: Reactor Trip System Response Time Evaluation Tables Rp N.:2~8- p- p R .p Page 5 of 5 Originator S. Kincaid Date: +1~15/32 F OXBORO RESPONSE M 0DULE TIME PER pap E~/ NUMBER LETTER Pressurizer 12-RPC-03 N-2AI-H2V 37MS Level (High) 92F 12687 N-2CCA-DC 400MS FD¹2101 SHT 2 N-2AO-L2C-R 10MS 447MS Common for both Units 1 A2

Attachment 4: Reactor Trip System Response Time Evaluation Tables Rp N.:2~HI!-1R*.I!

Page5of 8 Originator S Ktncaid Date: 10/1~2 FOXBORO RESPONSE MODULE TIME PER Ula c NUMBER LETTER S t e a m 12-RPC-05 N-2AI-H2V 37 MS Generator 92F12687 N-2CCA-DC 400MS Level FD-2101 N-2AO-L2C-R 1 M low-low SHT 5 447MS

Attachment 4: Reactor Trip System Time Response Comparison Page7ot8 Existing Rack New Rack Tech Spec Existing New New Loop Existing Rack New Rack Electronics Electronics Time Response Time Response Time Response Negative Comments/

ID Electronics/Bkr Electronics/Bkr Tot. Resp Time Tot. Resp Time Requirement Margin Margin Margin Resolutions Unit 1 OTDT 2.29732448 2.81 %.2448 2.0525+ 2.5 2.5652+2.5 < = 6.0000 1.4475 0.9348 NONE (2.0525) (2.5652) (4.5525) (5.0652)

OPDT 2.81 %.2448 2.5652+2.5 < = 6.0000 0.9348 (2.5652) (5.0652)

Pressurizer Press 0.4145%.2448 0.447%.2448 0.39+0.1697 0.202+0.39 <%11 0000 OA403 0.408 NONE (LOW) (0.1697) (0.202) (0.5597) (0.592)

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 <R1.5000 0.5824 0.998 NONE Leveldow low (0.6176) (0.202) (0.9176) (0.502)

Attachment 4: Reactor Trip System Time Response Comparison

(<<

Page8of8 Existing Rack New Rack Tech Spec Existing New New Loop Existing Rack New Rack Electronics Electronics Time Response Time Response Time Response Negative Comments/

ID Electronics/Bkr Electronics/Bkr Tot. Resp Time Tot. Resp Time Requirement Margin Margin Margin Resolutions Unit 2 OTDT 1.461%.1813 2.81%.1813 3.4+1.2797 3.4+2.6287 < =6.0000 1.3203 <.0287 Neg. margin (1.2797) (2.6287) (4.6797) (6.0287) using worst response.

Actual times OPDT 2.81-0.1813 3.4+2.6287 < = 6.0000 -0.0287 expected to (2.6287) (6.0287) be much shorter.

Pressurizer Press 0.4964-0.1813 0.447%.1813 0.3151+0.26 0.2666+0.26 < =1.0000 0.4249 0.4734 NONE (LOW) (0.3151) (0.2666) (0.5751) (0.5266)

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 0.447%.1813 0.42+0.1435 0.2666+0.42 <=1.0000 0.4365 0.3134 NONE (0.1435) (0.2666) (0.5635) (0.6866)

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) (0.4254) (0.5666)

I

Attachment 5: Engineered Safety Features Response Time Evaluation Tables Rp N.:2~HEt-1R .G Page 1 of+1 Originator: ~Kincaid Date: +1~1/2 FOXBORO RESPONSE DO ~i MODULE NUMBER TIME PER LET7ER Containment 12-RPC-07 Pressure-High 92F 12687-FD-2103 SHT P4 A. Safety N-2AI-H2V 37MS Inj. N-2CCA-SC 400MS N-2 A0-L2C-R 10MS 447MS B. RX Trip N-2AI-H2V 37MS N-2CCA-SC 400MS N-2AO-L2C-R 10MS 447MS C. FW Isol. N-2AI-H2V 37MS N-2CCA-SC 400MS N-2AO-L2C-R 10M 447MS D. Cont Isol. N-2AI-H2V 37MS N-2CCA-SC 400MS N-2A0-L2C-R 10MS 447MS E. Essential N-2AI-H2V 37MS Service N-2CCA-SC 400MS Water N-2AD-L2L-R 10MS 447MS

Attachment 5: Engineered Safety Features Response Time Evaluation Tables Rl N.:2~H-DIR*.tl Page 2 of +1 Originator: $ Kincaid Date: ~10/IS/ 2 FOXBORO RESPONSE M 0 D U L E TIMEPER Ulo ~cl NUMBER LETTER Pressurizer 12-RPC-04 P re s s u re 92F12687-FD-2101 (Low) SHT 1 FD-2102 SHT 2 A. Safety N-2AI-H2V 37MS Inj. N-2CCA-DC 400MS N-2AO-L2C-R 10MS 447MS B. RX Trip N-2AI-H2V 37MS (From SI) N-2CCA-DC- 400MS N-2AO-L2C-R 10MS 447MS C. FW Isol. N-2AI-H2V 37MS N-2CCA-DC 400MS N-2AO-C2C-R 10MS 447MS D. Cont Isol. N-2AI-H2V 37MS (PHA) N-2CCA-DC 400MS N-2A0-L2C-R 10MS 447MS E. Essential N-2AI-H2V 37MS Service N-2CCA-DC 400MS Water N-2A0-L2C-R 10MS 447MS

Attachment 5: Engineered Safety Features Response Time Evaluation Tables R p N .: 2~HK- I R . 9 Page $ of +1 Originator: ~Kineaid Date: +1~i/2 F 0 X B'0 R 0 RESPONSE MODULE TIME PER nlQ NUMBER LETTER Steam Line 12-RCP-08 Q/P-High 92F12687-FD-2103 SHT 2 A. Safety N-2AI-H2V 37MS Inj. N-2CCA-DC 400MS N-2AO-L2C-R 10MS 447MS B. RX Trip N-AI-H2V 37MS (from SI) N-2CCA-DC 400MS N-2A0-L2C-R 10MS 447MS N-2AI-H2V 37MS Isol. N-2CCA-DC 400MS N-2AO-L2C-R 10M 447MS D. Cont Isol. N-2AI-H2V 37MS (PHA) N-2CCA-DC 400MS N-2AO-L2C-R 10MS 447MS E. Essential N-2AI-H2V 37MS Service N-2CCA-DC 400MS Water N-2AO-L2C-R 10M 447MS

R 2 Pl .: p~l Attachment 5: Engineered Safety Features Response Time Evaluation Tables 2

Page 4 of

+1 2

Originator: pt Kincaid Date: +1~192 FOXBORO RESPONSE npp ~f MODULE MBER TIME PER LETTER High Steam 12-RPC-02 Flow/Lo-Lo 92F 12687 Tavg FD¹2103 SHT 1 FD¹2103 SHT 3 A. Safety FD¹2104 N-2AI-P2V 2000MS Inj. SHT 2864 N-2CCA-DC 400MS N-2A0-L2C-R 10MS 2410MS B. RX Trip N-2AI-P2V 2000MS (From SI) N-2CCA-DC 400MS N-2A0-L2C-R 10MS 2410M S C. Feedwater N-2AI-P2V 2000M S Isol. N-2CCA-DC 400MS N-2A0-L2C-R 10MS 2410MS D. Cont Isol. N-2AI-P2V 2000MS N-2CCA-DC 400MS N-2AO-L2C-R 10M 2410MS E. Essential N-2AI-P2V 2000M S Service N-2CCA-DC 400MS Water N-2AO-L2C-R 10MS 2410MS F. Steam N-2AI-P2V 2000MS Line Isol. N-2CCA-DC 400MS N-2A0-L2C-R 1 MS 2410MS

Attachment 5: Engineered Safety Features Response Time Evaluation Tables RR N.:2RRNRIDIR*.R Page $ of +I Originator: ~Kincai Date: ~10/1 92 FOXBORO RESPONSE

~DID ~l FD¹2103 MODULE

~NR TIME PER LETTER High Steam SHT 1&3 Flow/Low S t e a m FD¹2103 Pressure SHT 2&4 A. Safety N-2AI-H2V 37MS Inj. N-2CCA-DC 400MS N-2A0-L2C-R 10MS 447MS B. RX Trip N-2AI-H2V 37MS N-2CCA-DC 400MS N-2AO-L2C-R 10MS 447MS C. Feedwater N-2AI-H2V 37MS Isol. N-2CCA-DC 400MS N-2A0-L2C-R 10MS 447MS D. Cont Isol. N-2AI-H2V 37MS N-2CCA-DC 400MS N-2AO-L2C-R 10MS 447MS E. Essential N-2AI-H2V 37MS Service N-2CCA-DC 400MS Water N-2 A0-L2C-R 10MS 447MS F. Steam N-2AI-H2V 37MS Line Isol. N-2CCA-DC 400MS N-2AO-L2C-R 10MS 447MS

Attachment 5: Engineered Safety Features Response Time Evaluation Tables ll 2 N .: 20JHH-LIH .2 Page Q of +1 Originator: $ Kincaid Date: +1~1/2 FOXBORO RESPONSE MODULE TIME PER L~l ~HC I D NUMBER LETTER Low Steam 12-RPC-08 N-2AI-H2V -37MS N-2CCA-DC 400MS Pressure 92F12687 FD¹2103 SHT 2&4 N-2AO-L2C-R jill 447MS FD¹2104 SHT 1&3 FOXBORO RESPONSE MODULE TIME PER LOOP ID ECP FD NUMBER LETTER Containment 12-RPC-07 Pressure 92F12687 (Hi Hi) FD¹2103 SHT 4 A. Con t N-2AI-H2V 37MS Sprays N-2CCA-SC 400MS N-2A0-L2C-R 10MS 447MS B. Steam N-2AI-H2V 37MS Line Isol. N-2CCA-SC 400MS N-2AO-L2C-R 10MS 447MS C. Cont N-2AI-H2V 37MS Rescirc Flow N-2CCA-SC 400MS N-2 A0-L2C-R 1 M 447MS

Attachment 5: Engineered Safety Features Response Time Evaluation Tables Rl <<N.:2~HH-1R .0 Page 7 of +I Originator: ~Kine id Date: +1~15/~2 FOXBORO RESPONSE MODULE TIME PER

~CI N MBER LETTER S t e a m 12-RPC-05 G en erato r 92F12687 Level FDP2101 (Hi Hi) SHT 5 A. Turbine N-2AI-H2V 37MS Trip N-2CCA-DC 400MS N-2AO-L2C-R 10MS 447MS B. Feedwater N-2AI-H2V 37MS Isol. N-2CCA-DC 400MS

'-2AO-L2C-R 10MS 447MS

pp Attachment 5: 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 ala N~M LE%i ER S t e a m 12-RPC-05 Generator 92F12687 Level FD¹2101 (Lo Lo) SHT 5 A. Motor N-2AI-H2V 37MS Driven Aux N-2CCA-DC 400MS Feed water N-2A0-L2C-R 10M pump 447MS B. Turbine N-2AI-H2V 37MS Driven Aux N-2CCA-DC 400MS Feedwater N-2AO-L2C-R 10MS pump 447MS

Attachment 5: Engineered Safety Features ime Response Comparison Page 9 of 13 Tech Spec Existing New New Loop Existing Rack New Rack Time Response Time Response Time Response Negative Comments/

ID Electronics/Bkr Electronics/Bkr Requirement Margin Margin Margin Resolutions Unit 1 High Steam Flow/Low Steam Pressure A. SI 0.3206 0.447 < =27.0/37.0 16.18/18.48 16.05/18.35 NONE B. RX trip 0.3206 0.447 < ~3.0 2.6794 2.553 NONE C. FWI 0.3076 0.447 < =8.0 3.18 3.04 NONE D. CI(ph. A) 0.3106/0.318 0.447/0.447 < ~18.0/28.0 12.09/1 6.09 11.95/15.96 NONE E. ESW 0.3076 0.447 <~ 14.0/48.0 13.49/20.15 13.35/20.01 NONE F. SLI 0.3076 0.447 <=11.0 5.29 5.15 NONE Containment Pressure (Hl-Hl)

A. Cont Spray 0.3731 0.447 <=45.0 0.1269 0.053 NONE B. Steam Line Isol 0.3663 0.447 < R10.0 4.42337 4.343 NONE C. Cont Recirc Flow 0.3698 0.447 <=660 61.6302 61.553 NONE Steam Generator Level (Hl-Hi)

A. Turbine Trip 0.4898 0.447 < =2.5 1.7502 1.793 NONE 0.4898 0.447 <=11.0 6.0002 6.043 NONE

Attachment 5: Engineered Safety Features ime Response Comparison Page 10 of 13 Tech Spec Existing New Loop Existing Rack New Rack Time Response Time Response Time Response Negative Comments/

ID Electronics/Bkr Electronics/Bkr Requirement Margin Margin Margin Resolutions Cont Pressure High A. SI 0.3715 0.447 <~27.0 7.37 7.2945 NONE B. RX Trip 0.4366 0.447 < =3.0 2.56 2.549 NONE C. FWI 0.3637 0.447 <=8.0 3.13 3.046 NONE D. CI (Ph. A) 0.3663/0.3693 OA47/OA47 <=18.0/28.0 12.04/16.03 11.959/15.95 NONE E. ESW 0.3637 0.447/0.447 < =13.0/48.0 12.44/20.1 12.356/20.01 NONE Pressurizer Pressure.Low A. SI 0.4815 0.447/0.447 < = 27.0/27.0 7.26/I 6.02 7.2945/16.05 NONE B. RX Trip 0.6698 0.447 < a3.0 2.33 2.5528 NONE C. FWI 0.4685 0.447 <=8.0 3.02 3.0415 NONE D. Cl(Ph. A) 0.4815 0.447 <=18,0 5.92 5.9545 NONE E. ESW 0.4685 0.447/0.447 <~48.0/13.0 19.99/12.33 20.011/12.35 NONE Steam Line D/P High A. Sl 0.4037 0.447 < ~27.0/37.0 1 6.1/I 8.4 16.056/18.35 NONE B. RX Trip OA623 0.447 < R3.0 2.54 2.555 NONE C. FWI 0.3946 OA47 <~8.0 3.1 3.0476 NONE D. Cl(Ph. A) 0.3772/0.4004 0.447/0.447 < ~18.0/28.0 12/16 1 1.9302/15.95 NONE E. ESW 0.3946 0.447 < =13.0/48.0 12.41/20.06 12.3576/20 NONE

Attachment 5: Engineered Safety Features Time Response Comparison Page 11 of 13 Tech Spec Existing New New Loop Existing Rack New Rack Time Response Time Response Time Response  ;; Negative Comments/

ID Electronics/Bkr Electronics/Bkr Requirement Margin Margin Margin Resolutions High Steam Flow/LoLo TAVG A. SI 1.0874 2.41 < ~ 29.0/39.0 17.42/1 9.71 16.0974/18.3874 NONE B. RX Trip 1.1395 2,41 <=5.0 3.8605 2.59 NONE C. FWI 1.0718 2A1 < 5510.0 4.47 3.1318 NONE D. CI (Ph. A) 1.077/1.0122 2.41/2.41 < =20.0/30.0 13.32/17.32 11.987/15.922 NONE E. ESW 1.0718 2.41 < =15.0/50.0 13.73/21.38 12.3918/20.0418 NONE F. SLI 1.0692 2.41 <=13.0 6.53 5.1892 NONE Steam Generator Level (Lo-Lo)

A. MDA FWP 0.8452 OA47 < 5-60.0 35.5852 35.9834 NONE B. TDA FWP 2.1207 0.447 <=60.0 34.2893 35.963 NONE Unit 2 Pressurizer Pressure Lo A. Sl 0.4967 0.447 < 5527.0/27.0 5.7033/15.5033 5.753/15.55 NONE B. RX Trip 0.5701 0.447 < =3.0 2.4299 2.5553 NONE C. FWI 0.4916 0.447 < 5-8.0 4.5084 4.553 NONE D. CI (Ph. A) 0.4967 0.447 < &18.0 9.1033 9.5533 NONE E. MDA FWP 0.4967 0.447 < =60.0 22.6333 22.683 NONE F. ESW 0.4967 0.447 < ~ 48.0/t 3.0 19.8433/1 2.3433 19.893/4 2.39 NONE

'ttachment 5: Engineered Safety Features lme Response Comparison Tech Spec Existing New Loop Existing Rack New Rack Time Response Time Response Time Response Negative Comments/

ID Electronics/Bkr Electronics/Bkr Requirement Margin Margin Margin Resolutions Steam Line D/P High A. SI 0.3566 0.447 < = 27.0/37.0 15.6434/I 7.8334 15.553/1 7.74 NONE B. RX Trip 0.4378 0.447 <<3.0 2.5622 2.553 NONE C. FWI 0.3514 0.447 < ~8.0 4.6486 4.553 NONE D. CI(ph. A) 0.3566 0.447 < =18.0/28.0 8.3834/10.2334 8.293/10.1426 NONE E. MDA FWP 0.3903 0.447 < =60.0 22.7597 22.703 NONE F. ESW 0.3903 0.447 < = 13.0/48.0 12.4497/19.9497 12.393/I 9.88 NONE Hi Steam Flow/

Lo.Lo TAVG A. SU 0.9254 2.41 <=13.0 5.8746 4.39 NONE Steam Line Pressure Lo A. SU 0.3903 0.447 < = 27.0/37.0 15.6097/17.7997 15.553/1 7.733 NONE B. RX Trip 0.4741 OA47 < =3.0 2.5259 2.553 NONE 0.3799 OA47 < ~8.0 4.6201 4.553 NONE D. CI (Ph. A) 0.3851 OA47 <=18.0/28.0 8.7149/10.2049 8.653/10.142 NONE E. MDA FWP 0.3903 0.447 < IR 60.0 22.7597 22.703 NONE F. ESW 0.3903 0.447 < =14.0/48.0 13.4497/1 9.9497 13.393/19.88 NONE G. SU., 0.3799 0.447 <%11.0 4.4201 4.353 NONE

Attachment 5: Engineered Safety Features ime Response Comparison Page 13 of 13 Tech Spec Existing New New Loop Existing Rack New Rack Time Response Time Response Time Response Negative Comments/

ID Electronics/Bkr Electronics/Bkr Requirement Margin Margin Margin Resolutions Containment Pressure Hi-Hi A. Cont Spray 0.3798 0.447 < =45.0 5.1302 5.063 NONE B. SLI 0.3798 0.447 < =10.0 3 4202 3.353 NONE C. Cont Recirc 0.3772 0.447 < =600.0 65.6228 65.553 NONE Flow Steam Generator Level Lo Lo A. MDA FWP 0.339 0.447 <=60.0 22.831 22.723 NONE B. TDA FWP 0.3259 0.447 <=60.0 37.0841 36.963 NONE

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