ML24045A041

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Proposed RO Admin JPMs
ML24045A041
Person / Time
Site: Davis Besse 
Issue date: 12/14/2023
From:
NRC/RGN-III/DORS/OB
To:
Energy Harbor Nuclear Corp
Greg Roach
Shared Package
ML22251A143 List:
References
Download: ML24045A041 (1)
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Text

Davis-Besse Initial License Exam 2024 Admin JPM RO-A1.1

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.1 Page 1 of 5 Examinee:

Date:

Examiner:

Facility: Davis-Besse JPM No: OPS-JPM-316 Task

Title:

Calculate Steam Generator Tube Leak Rate Task No: 000-044-05-0100 System:

K/A

Reference:

2.1.19 (3.9) R3 Safety Function:

Time Critical Task: No Alternate Path:

Validation Time:

15 minutes Method of testing:

Simulated Performance ___

Actual Performance _X_

Classroom _X_

Simulator ___

Plant ___

Task Standard:

Determine SG Tube leak rate Required Materials:

DB-OP-02531 Attachment 1, RCS Leak Rate Calculation Pictures of RE 1003A and RE 1003B Chemistry Data Sheet Calculator General

References:

None Notes:

None Initiating Cue:

The Initiating Cues are specified in the Examiner/Student Copy Performance Measure pages.

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.1 Page 2 of 5 EXAMINER COPY INITIAL CONDITIONS:

The unit is at 100% power SG 1 has a tube leak Pressurizer level is 220 inches and steady The Computer Calculation for RCS Leakage is NOT available EO reports Steam Jet Air Ejector flow is 15 scfm INITIATING CUE:

The Shift Manager directs you to manually calculate the leak rate.

REFER TO DB-OP-02531 R24, STEAM GENERATOR TUBE LEAK

  • , RCS LEAK RATE CALCULATION Section 4, Leak Rate Estimation Using RE 1003A, OR RE 1003B Provide the examinee a copy of DB-OP-02531 Attachment 1, RCS Leak Rate Calculation Pictures of RE 1003A and RE 1003B Chemistry Data Sheet

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.1 Page 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:

The unit is at 100% power SG 1 has a tube leak Pressurizer level is 220 inches and steady The Computer Calculation for RCS Leakage is NOT available EO reports Steam Jet Air Ejector flow is 15 scfm INITIATING CUE:

The Shift Manager directs you to manually calculate the leak rate.

REFER TO DB-OP-02531 R24, STEAM GENERATOR TUBE LEAK

  • , RCS LEAK RATE CALCULATION Section 4, Leak Rate Estimation Using RE 1003A, OR RE 1003B

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.1 Page 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the "Comments".

START TIME:

1.

PERFORMANCE STEP: Record Date and time STANDARD: Correct date and time used CUE: None SAT UNSAT

2.

PERFORMANCE STEP: Record Steam Jet Air Ejector radiation levels

........C........

STANDARD: Correctly read RE 1003A (1.02E4 cpm) and RE 1003B (3.97E3 cpm)

CUE: None SAT UNSAT

3.

PERFORMANCE STEP: Convert RE readings (cpm) to Ci/cc

........C........

STANDARD: Correctly multiply SJAE reading by conversion factor:

RE 1003A = 6.63E-05 Ci/cc RE 1003B = 1.27E-04 Ci/cc COMMENT: Acceptable Range RE 1003A = 6.6E-05 to 6.7E-05Ci/cc RE 1003B = 1.2E-04 to 1.3E-04Ci/cc CUE: None SAT UNSAT

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.1 Page 5 of 5

4.

PERFORMANCE STEP: Record Steam Jet Air Ejector (SJAE) flow from FI1002

........C........

STANDARD: Correctly record 15 scfm, as given in the initial cue by an EO CUE: None SAT UNSAT

5.

PERFORMANCE STEP: Record the latest RCS Xe-133 activity from Chemistry

........C........

STANDARD: Refers to the Chemistry Data Sheet, correctly record RCS Xe-133 activity (6.66E-03 Ci/cc)

CUE: None SAT UNSAT

6.

PERFORMANCE STEP: Calculate primary-to-secondary tube leak using RE 1003B

........C........

STANDARD: Correctly calculate tube leak using RE 1003B (2.14 gpm)

COMMENT: Acceptable Range 2 to 3 gpm CUE: None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by the examinee)

END TIME_________

16 DB-OP-02531 Revision 25 ATTACHMENT 1: RCS LEAK RATE CALCULATION Page 1 of 3 NOTE 1 This attachment provides four methods to quickly estimate Reactor Coolant System to Steam Generator leak rate using readily available Control Room indications. This attachment is used if the Computer Calculation for RCS Leakage is not available.

Section 1, Leak Rate Estimation Using RE1003A, OR 1003B Readings and Chemistry Data.

Section 2, Leak Rate Estimation Using RCS Inventory Parameters.

This method assumes PZR level is relatively constant and Tave is not changing.

Section 3, Leak Rate Estimation Using Pressurizer and Makeup Tank Level Change - This method will allow leak rate determination when Pressurizer Level is NOT constant.

Section 4, Leak Rate Estimation Using RE 1003A, OR RE 1003B To simplify the calculations, errors associated with density corrections, known existing leakage, and other variables are not considered. A more accurate leak rate can be obtained by performing DB-SP-03357, RCS Water Inventory Balance.

_____ 1.

Leak Rate Estimation Using RE1003A or RE1003B Readings and Chemistry Data Compare current RE1003A or RE1003B reading to the Chemistry Data provided table of SG Tube Leakage Rates. Estimate the leak rate based on the readings.

Method 4 expands the range of using RE 1003A/B beyond the pre-calculated values provided in the Chemistry Data.

_____ 2.

Leak Rate Estimation Using RCS Inventory Parameters (MU Flow + Seal Injection Flow) - (Letdown Flow + Seal Return Flow) = SGTL Rate

(________ gpm + ________ gpm) - (_______ gpm + _______ gpm) = _______gpm

17 DB-OP-02531 Revision 25 ATTACHMENT 1: RCS LEAK RATE CALCULATION Page 2 of 3 NOTE 3 This leakrate calculation assumes an addition to the Makeup Tank is NOT in progress during the calculation.

_____ 3.

Leak Rate Estimation Using Pressurizer and Makeup Tank Level Change Initial RCS Inventory Conditions Time = ___________ hr: min Pressurizer Level = ___________ in Makeup Tank Level = ___________ in Final RCS Inventory Conditions Time = ___________ hr: min Pressurizer Level = ___________ in Makeup Tank Level = ___________ in Initial RCS Inventory (30 x Initial MU Tank Level) + (24 x Initial Pressurizer Level) = Initial RCS Inventory (30 x _______________ in) + (24 x _________________ in) = ___________ gal Final RCS Inventory (30 x Final MU Tank Level) + (24 x Final Pressurizer Level) = Final RCS Inventory (30 x _______________ in) + (24 x _________________ in) = ___________ gal SG Tube Leak Rate Rate SGTL Period Time Inventory RCS Final Inventory RCS Initial gal/min min gal gal

18 DB-OP-02531 Revision 25 ATTACHMENT 1: RCS LEAK RATE CALCULATION Page 3 of 3

_____ 4.0 Leak Rate Estimation Using RE 1003A or RE 1003B (a.)

Record the date and time. Date Time (b.)

Record Xe-133 activity RE1003A reading CPM from the Steam Jet Air RE1003B reading CPM Ejector (SJAE) monitors (c.)

SJAE activity - convert CPM to µCi/cc Xe-133; (RE1003A, from (b.)

CPM) (6.5 E-9)=

µCi/cc (RE1003B, from (b.)

CPM) (3.2 E-8)=

µCi/cc (d.)

Record SJAE flow from FI1002 (must be greater than 0)

FT³/MIN (e.)

Record the latest Xe-133 concentration in the Reactor Coolant System from Chemistry.

µCi/cc (f.)

Using the highest value from (c.), calculate the primary to secondary tube leak as follows:

.)

e ep St

(

d.)

c.)(Step (Step FT GAL 48

.7 3

R L

7 48

(

)

GAL FT

(

)(

)

3

= ____GPM

CHEMISTRY ANALYSES STATUS Page 1 of 2 Li 7

3 D

A V

I S

B E

S S

E N

U C

L E

A R

P O

W E

R S

T A

T I

O N

C H

E M

I S

T R

Y PRIMARY (RCS)

SECONDARY (FEEDWATER)

Date: Today Date:

Today Specification Value Specification Value 5

O2 <2 ppb 5

O2

<2 ppb 50 Cl- 0.73 ppb 20 N2H4 74 ppb 50 F- 0.94 ppb 10 SiO2

<5 ppb 50 SO4-2 0.19 ppb 1

Na+

0.06 ppb DBRM-CHEM-0001 Li 1.27 ppm 3

Cl-0.28 ppb 25 - 50 H2 37.3 cc/kg 1

SO4-2

<0.064 ppb 10 Zinc 4.84 ppb 5

Total Iron 0.37 ppb 1.0 DEI-131 1.23E-4 µCi/gm 2

ETA 2.53 ppm

  • 2x steady state value I-131 3.42E-5 µCi/gm 6

MPA 7.28 ppm

  • Increase of 0.01 Xe-133 6.66E-03 µCi/gm

<100 Condensate Dissolved O2 8.1 ppb

  • <1.0 Xe-133/Xe-135 Ratio 0.85 CEI-R (Month): 0.04 CEI-R (Rolling): 0.23 Issues/Challenges: None.

100/

Specific Act.

0.15

µCi/gm 100/ Maximum Limit 913

µCi/gm Makeup Tank Pressure Band: 30-40 psig BORON (PPM)

Primary-To-Secondary Leakage Vessel Measured Effective

    • Acceptable Range Time Date Based on RI-1003: <1.98 gal per day RCS 291 0800 10/11/19 Based on DB-CH-03031: <5 gal per day PZR 345 1640 10/4/19 Details for RE1003A/B Equivalent cpm for OTSG leakage are on page 2 of 2 BWST 2748 2711 2626 - 2772 0955 10/8/19 BAAT 1 11372 11297 7954 - 12994 0130 10/5/19 NOTES
  • IF any Fuel Integrity Action Level is reached, THEN make notifications in accordance with NOP-NF-1102, Fuel Integrity Monitoring and Assessment.

BAAT 2 12165 12153 7954 - 12994 0123 9/28/19 CWRT 1 2691 2684 2626-2772 0920 8/27/19 CWRT 2 1149 1730 8/23/18 CFT 1 2916 2903 2626 - 3465 1048 9/19/19

    • Acceptable Range is for Effective boron results and accounts for 1%

analysis uncertainty. Effective boron results are corrected for Boron-10 depletion.

CFT 2 2880 2880 2626 - 3465 1425 9/19/19 SFP 2608 2576 630 0820 10/8/19 Refuel Canal N/A Per COLR N/A N/A

CHEMISTRY ANALYSES STATUS Page 2 of 2 Li 7

3 D

A V

I S

B E

S S

E N

U C

L E

A R

P O

W E

R S

T A

T I

O N

C H

E M

I S

T R

Y Comments:

RE 1003A/B Equivalent cpm for OTSG Leakage Date determined Today Based on RCS Xe-133 6.66E-03 µCi/cc Based on FI 1002 15 cfm RE 1003A RE 1003B Efficiency used for calculation 6.5E-9

µCi/cc/cpm 3.2E-8

µCi/cc/cpm 5 GPD 1.2E2 cpm 1.5E2 cpm 30 GPD 1.5E2 cpm 1.5E2 cpm 75 GPD 2.0E2 cpm 1.6E2 cpm 150 GPD 2.9E2 cpm 1.8E2 cpm Increase of 30 GPD 3.5E1 cpm 7.1E0 cpm Comment:

Completed by Date/Time

/

Verified by Date/Time

/

Reviewed by Date/Time

/

Shift Manager

Davis-Besse Initial License Exam 2024 Admin JPM RO-A1.2

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.2 Page 1 of 5 Examinee:

Date:

Examiner:

Facility: Davis-Besse JPM No: OPS-JPM-276 Task

Title:

Perform 1/M Plot Task No:

115-033-01-0100 System:

K/A

Reference:

2.1.43 (4.1)

Safety Function:

Time Critical Task: No Alternate Path:

Validation Time: 15 minutes Method of testing:

Simulated Performance ___

Actual Performance X Classroom X Simulator ___

Plant ___

Task Standard:

Perform the calculations and 1/M Plot and recommend no further rod withdrawal.

Also, acceptable to recommend inserting Control Rod Groups 2-7 Required Materials:

DB-OP-06912 R22, Approach to Criticality Straight edge Calculator General

References:

None Notes:

None Initial Conditions:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Initiating Cue:

The Initiating Cues are specified in the Examiner/Student Copy Performance Measure pages.

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.2 Page 2 of 5 EXAMINER COPY INITIAL CONDITIONS:

The Plant is in Mode 2.

A reactor startup is in progress.

Group 1-4 rods are withdrawn Regulating Rods are pulled to 100 Rod Index INITIATION CUE:

The Shift Manager directs you to perform a peer check of the Reactor Engineer performing the 1/M Plot by performing a separate 1/M Plot using the Source Range count rate data provided on of DB-OP-06912, Approach to Criticality.

Compare the 1/M data with the predicted ECP data Make a recommendation for further rod withdrawal.

Document recommendation below.

(Hand Candidate a copy of DB-OP-06912, Approach to Criticality, Calculator, and a Straight Edge)

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.2 Page 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:

The Plant is in Mode 2.

A reactor startup is in progress.

Group 1-4 rods are withdrawn Regulating Rods are pulled to 100 Rod Index INITIATION CUE:

The Shift Manager directs you to perform a peer check of the Reactor Engineer performing the 1/M Plot by performing a separate 1/M Plot using the Source Range count rate data provided on of DB-OP-06912, Approach to Criticality.

Compare the 1/M data with the predicted ECP data Make a recommendation for further rod withdrawal Document recommendation below.

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.2 Page 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".

START TIME: ___________

1.

PERFORMANCE STEP:

Refer to data on Attachment 1 STANDARD:

Refer to data on Attachment 1 for count rate data CUE:

None SAT UNSAT

2.

PERFORMANCE STEP:

........C........

Plots data SR data on 1/M Plot STANDARD: Evaluates count rate data on attachment 1 and plots this data on the 1/M Plot for 25, 50, 75, and 100 Rod Index COMMENTS: Calculated 1/M values are critical 25:.92 50:.76 75:.52 100:.16 Predicted Critical Positions on Answer Key are not critical CUE:

None SAT UNSAT

3.

PERFORMANCE STEP:

........C........

Evaluate 1/M Plot data STANDARD:

  • Plot the 1/M by connecting the last two data points on the graph and extending the line down to meet the horizontal (Rod index) axis.
  • Determines that the 1/M Plot predicts criticality before reaching the Lower Rod Index limit of the ECP listed as 125 (- 0.5%k/k)

CUE:

None SAT UNSAT

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A1.2 Page 5 of 5

4. PERFORMANCE STEP:

........C........

Notify SRO that the 1/M Plot predicts criticality before reaching the Lower Rod Index limit of the ECP and recommend no further rod withdrawal.

STANDARD:

Notify SRO that the 1/M Plot predicts criticality before reaching the Lower Rod Index limit of the ECP and recommend no further rod withdrawal.

May also recommend inserting Control Rod Groups 2-7.

CUE:

None - Verify that the candidate makes the recommendation for no further rod withdrawal or ask a follow-up question.

SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by examinee).

END TIME: ____________

Davis-Besse Initial License Exam 2024 Admin JPM RO-A2

Job Performance Measure Form 3.2-3 Worksheet Simulator JPM A2 Page 1 of 5 Examinee:

Date:

Examiner:

Facility: Davis-Besse JPM No: OPS-JPM-NEW (335)

Task

Title:

Perform a Leak Isolation Task No: 119-035-0100 System: 008 Component Cooling Water System K/A

Reference:

G2.2.15 (3.9) R3 Safety Function:

Time Critical Task: No Alternate Path: No Validation Time: 25 minutes Method of testing / Location:

Simulated Performance ___

Actual Performance X Classroom _X__

Simulator Plant ___

Task Standard:

Identify valves / pumps to isolate a CCW break using mechanical prints Required Materials:

OS21 Sheet 1 - Operational Schematic Component Cooling Water System (Rev. 39)

OS21 Sheet 3 - Operational Schematic Component Cooling Water System (Rev. 12)

General

References:

OS Drawings Book Magnifying Glass Notes:

This Admin JPM is a 2-part JPM and will require two classrooms to facilitate it.

Initial Conditions:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Initiating Cue:

The Initiating Cues are specified in the Examiner/Student Copy Performance Measure pages.

Job Performance Measure Form 3.2-3 Worksheet Simulator JPM A2 Page 2 of 5 EXAMINER COPY INITIAL CONDITIONS:

All plant systems are in a normal alignment.

Component Cooling Water (CCW) Pump 1 is in STBY.

Component Cooling Water (CCW) Pump 2 is running.

CCW Pump 3 is lined-up Spare as Pump 2 INITIATING CUES:

The Control Room receives a call reporting a leak from the Component Cooling Water system coming from the inlet weld to the Component Cooling Heat Exchanger 1-1.

The crew has opened DW2643, CCW Surge Tank Demin Water Makeup Valve to maintain normal CCW Surge Tank level.

The Unit Supervisor directs you to identify the valves needed to isolate the leak.

(Provide examinee with a set of Operational Schematics or access to filenet)

Job Performance Measure Form 3.2-3 Worksheet Simulator JPM A2 Page 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:

All plant systems are in a normal alignment.

Component Cooling Water (CCW) Pump 1 is in STBY.

Component Cooling Water (CCW) Pump 2 is running.

CCW Pump 3 is lined-up Spare as Pump 2 INITIATING CUES:

The Control Room receives a call reporting a leak from the Component Cooling Water system coming from the inlet weld to the Component Cooling Heat Exchanger 1-1.

The crew has opened DW2643, CCW Surge Tank Demin Water Makeup Valve to maintain normal CCW Surge Tank level.

The Unit Supervisor directs you to identify the valves needed to isolate the leak and list affected components.

Job Performance Measure Form 3.2-3 Worksheet Simulator JPM A2 Page 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".

START TIME: ________

1.

PERFORMANCE STEP: Identify prints needed.

........C........

STANDARD: Identifies correct print for where the CCW System leak is located:

OS-021 SH 1.

CUE: Once candidate identifies print(s), provide a copy of Component Cooling Water System Schematics (OS-021 SH 1-3)

SAT UNSAT

2.

PERFORMANCE STEP: Identify components to isolate CCW leak

........C........

STANDARD: Uses identified prints to isolate CCW leak.

CC32, CCW Heat Exchanger 1 Outlet Butterfly CLOSED CC1, CCW Pump 1 Suction Butterfly Valve CLOSED

  • P43-1, CCW Pump 1 OOS. (Place CCW Pump 3 as 1 in STBY, is also acceptable)

NOTE: Other components may be identified for equipment protection such as HPI and LPI Pumps, or EDG 1, these are to be treated as NON-CRITICAL.

CUE: Once the candidate identifies the equipment that must be manipulated, role play as the Unit Supervisor as required.

IF the isolation plan includes CC1, The operator in the field is unable to close CC1 and the CCW leak continues. Identify additional components which MUST be manipulated to isolate the CCW leak.

IF the candidate has already expanded the isolation points, evaluate the boundary to ensure the leak has been isolated (JPM Step 3), and mark this JPM Step N/A.

SAT UNSAT

Job Performance Measure Form 3.2-3 Worksheet Simulator JPM A2 Page 5 of 5

3.

PERFORMANCE STEP: Identify valves to isolate CCW leak

........C........

STANDARD: Uses identified prints to isolate CCW leak.

Normally CLOSED valves are NOT listed.

CCW Pump 3 as 1 is also not listed since it was initially lined up as spare.

The following identify the MINIMUM valves to be closed to isolate the leak based on CC1 failing to close.

CC123, CCW Surge Tank Isolation (from Sheet 3)

CC172, CCW From Decay Heat Cooler 1 Outlet Iso CC661, CCW From HPI & DH Pump 1 Normal Source Outlet CC162, CCW From EDG 1 Outlet Iso CC243, CTMT Gas Analyzer 1 Normal Source Outlet The following identify the MINIMUM valves to be closed to isolate the leak if CC32 was NOT used as an isolation.

CC653, CCW to HPI & DH Pump 1 Normal Source CC165, CCW to EDG 1 Inlet Iso CC156, CCW to Decay Heat Cooler 1 Inlet Iso CC239, Containment Gas Analyzer 1 Normal Source Inlet NOTE: Other components may be identified, if that is the case, these are to be treated as NON-CRITICAL portions of this step.

CUE: None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by the examinee)

END TIME:

C JP OPERATIONAL SCHEMATIC O

JOR JOR 03-20-91 OS-021 SH.3 124 123 119 120 118 (V) 3601B 3601 PI 3601 3601A DW3 DW69 DW2643 S

FO FC SV2643 OPEN OPEN CLSD CLOSE CCW SURGE TANK DEMIN WTR MAKEUP DW2643 HIS2643 AOV O S-045,F-4 FROM DEMINERALIZED WATER STORAGE TK DW6 SS106 SS105 O S-051,B-40 TO SAMPLING SYSTEM S-036-1,2 WM29 WM30 PW2 WM31 DRAIN (V) 219 221 (V) 222 T13 117 (V)

CHEM POT FEEDER 1-1 PI 2644 2644 2644B 2644A ZONE A-7 116 O S-045,G-4 FROM DEMINERALIZED WATER STORAGE TK 1403C LT 1403 LI 1403 1403D 1403E 1403F 1403G 1403H 1403B LSLL 3758A LSLL 3758B LSL 1404 LSLL 3758C LSH 1404 55 IN 11-4-A LSLL 3757A LSLL 3757B LSL 1400 LSLL 3757C LSH 1400 55 IN 11-4-A 5VM LT 1402 LI 1402 5VM 3758E 3758F 3758L 3758M 3758C 3758D 3758J 3758K L067 1404C 1404D 1404G 1404H 3758A 3758B 3758G 3758H 1404B 1404A 1404E 1404F L067 L068 1400B 1400R 1400A 1400D 1403A 1400G 1400H 1400J 1400N 3757G 3757H 3757J 3757K 1400K 1400L 1400P 3757E 3757D 3757F 3757L 3757B 3757A 3757C 3757M NN153 NN151 PSIG 2

O S-049,D-13 FROM NITROGEN SUPPLY SYSTEM NN150 NN1892 NN152 S

FO 5

PSIG FC FO 1412

  • CL-5*

SV1412 1643 TO ATM 5

PSIG X

609 3602 LO O S-029,F-1 TO MISC WASTE DRAIN TANK (D) 548 39 (D) 122 121 ZONE B-2 ZONE B-2 ZONE A-2 COMPONENT COOLING WATER SYSTEM LEGEND GREEN DENOTES DEVICES LOCATED IN THE CONTROL ROOM BLUE DENOTES COMPONENT COOLING WATER LINE 1 FLOWPATH ORANGE DENOTES COMPONENT COOLING WATER LINE 2 FLOWPATH ISSUED FOR DCR 91-0030

  • CL-3*
  • CL-9*
  • CL-7*
  • CL-9*
  • CL-7*
  • CL-4*
  • CL-7*
  • CL-9*

I II 115 DW5 114

  • CL-7*
  • CL-9*

1400S 1400M 1400C ZONE A-2 OS-045,B-14 302 49 IN 11-3-A L066 37.1 IN 11-2-A L068 49.5 IN 11-3-A L066 36.25 IN 11-2-A 1403J 1400T 1400E 1400F G:\OPSCH\OS21S3.DGN JAD JBG JET PKG JPH 9

SBW JOR GLB SBW LO LO SBW 301 COMPONENT COOLING SURGE TANK T12 2350 GALLONS (NOTE 21) 6 GAL NOTE 21 FOR CONTROL LOGICS, NOTES AND REFERENCES SEE OS-021 SH 1 AND SH 2 CONTROL LOGICS (CONTD)

  • CL-12* THE STANDBY COMPONENT COOLING WATER PUMP WILL START WHEN LOW FLOW

(<1000 GPM) IS SENSED BY THE LOW FLOW SWITCH ACCORDING TO THE FOLLOWING TABLE:

1-1 (ZONE K-3) 1-2 (ZONE D-3) FIS1422D (ZONE J-5) 1-1 (ZONE K-3) 1-3 (ZONE G-3) FIS1422D (ZONE J-5) 1-2 (ZONE D-3) 1-1 (ZONE K-3) FIS1432C (ZONE C-5) 1-2 (ZONE D-3) 1-3 (ZONE G-3) FIS1432C (ZONE C-5) 1-3 (ZONE G-3) 1-1 (ZONE K-3) FIS1427C (ZONE F-5) 1-3 (ZONE G-3) 1-2 (ZONE D-3) FIS1427D (ZONE G-5)

  • CL-14* CRDC BOOSTER PUMP 1-1 WILL AUTOMATICALLY TRIP IF ANY OF THE FOLLOWING CONDITIONS EXIST:

- PUMP SUCTION VALVE 1328 (ZONE B-34) IS NOT FULLY OPEN

- MOTOR OVERLOAD CONDITION EXISTS RUNNING COMPONENT STANDBY COMPONENT LOW FLOW SWITCH COOLING WATER PUMP COOLING WATER PUMP <1000 GPM INC. DCN OS-21-108 PER DDR 00-2062 12 DB 07-02-07 SBW 7

29 91 9

11 00 3

17 06 3

30 06 7

13 07 10 JDK PWJ LOOP ONLY:

IF COMPONENT COOLING WATER (CCW) PUMP 1-1 IS RUNNING IT WILL RESTART WHEN EDG 1-1 STARTS AND ITS OUTPUT BREAKER CLOSES.

IF CCW 1-1 IS THE STANDBY PUMP IT WILL START 10 SECONDS AFTER EDG 1-1 OUTPUT BREAKER CLOSES.

SFAS WITH LOOP:

IF COMPONENT COOLING WATER (CCW) PUMP 1-1 IS RUNNING IT WILL RESTART WHEN EDG 1-1 STARTS AND ITS OUTPUT BREAKER CLOSES. IF CCW 1-1 IS THE STANDBY PUMP IT WILL START WHEN EDG 1-1 OUTPUT BREAKER CLOSES.

IF COMPONENT COOLING WATER (CCW) PUMP 1-3 IS RUNNING AS CCW PUMP 1-1, IT WILL RESTART UPON ITS ASSOCIATED EDG START AND BREAKER CLOSURE.

IF CCW 1-3 IS IN STANDBY FOR CCW PUMPS 1-1 IT WILL START WHEN ITS ASSOCIATED EDG OUTPUT BREAKER CLOSES.

  • CL-13*

INC. DCN OS-21-123 PER ECR 05-0095-00 (CR 03-00949, CA 08)

SFAS ONLY:

IF COMPONENT COOLING WATER (CCW) PUMP 1-1 (ZONE K-3) IS RUNNING IT WILL STAY RUNNING UPON SFAS. IF CCW 1-1 IS THE STAND BY PUMP IT WILL START UPON RECEIVING A SFAS SIGNAL.

11 MJM JDK LOGIC FOR COMPONENT COOLING WATER PUMP 1-2, P43-2 (ZONE D-3) IS SIMILAR IF COMPONENT COOLING WATER (CCW) PUMP 1-3 (ZONE G-3) IS RUNNING AS CCW PUMP 1-1, IT WILL STAY RUNNING IF CCW 1-3 IS IN STANDBY FOR CCW PUMPS 1-1 IT WILL START UPON RECEIVING A SFAS SIGNAL.

IF COMPONENT COOLING WATER (CCW) PUMP 1-3 IS RUNNING AS CCW PUMP 1-1, IT WILL RESTART UPON ITS ASSOCIATED EDG START AND BREAKER CLOSURE.

IF CCW 1-3 IS IN STANDBY FOR CCW PUMPS 1-1 IT WILL START 10 SECONDS AFTER ITS ASSOCIATED EDG OUTPUT BREAKER CLOSES.

LOGIC FOR CRDC BOOSTER PUMP 1-2 (ZONE C-33) IS SIMILAR EXCEPT PUMP SUCTION VALVE IS 1338 (ZONE C-34)

INC. DCN OS-21-124 PER ECR 05-0095-00 (CR 03-00949, CA 08) & GEN.

UPDATE CORRECT SPELLING IN *CL-14*,LOGIC AND SIMILAR SAS SJO 12 INC. DCN OS-21-81 PER MOD 95-0050-00 12 FROM DEMIN. WATER STORAGE TANK REV DAVIS-BESSE NUCLEAR POWER STATION UNIT NO 1 DRAWING NO SCALE DESIGNED DATE DRAWN DATE NO NONE J

H E

D C

B A

G F

K J

H E

D C

B A

G F

K REVISIONS BY CHK ENGR ENGR SUPV ENGR ENGR 35 36 37 38 39 40 41 42 43 44 45 46 47 48 50 51 49 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 DES SYS OPS MGR

248 613 3

10 PI 1439 TE 1684D T089 TE 1684E T085 667(V)

M TE 1684C T087 TE 1684A T088 TE 1684B T086 4.16KV BUS D1 CLOSE G

W R

LEVEL 2 BLOCK PI 1419 16 TI 1431 TE 1490 TT 1490 TI 1490 T069 PI 1433 PI 1438 TE 1686D TO97 TE 1686E T093 TE 1686C T095 TE 1686A T096 TE 1686B TO94 PI 1417 TI 1426 TE 3765 TT 3765 TO83 PI 1428 NOTE 4 TE 1657D T081 TE 1657E T077 TE 1657C T079 TE 1657A T080 TE 1657B T078 G

W R

LEVEL 2 BLOCK PI 1415 FIS 1422 F070 FIS 1422D TE 1489 TT 1489 TI 1489 T068 PI 1423 TSH 1483A 115 11-1-B F

T072 TIC 1424 NOTE 4 RE 1412 RI 1412 RSH 1412 R104 RE 1413 RI 1413 RSH 1413 HI RAD 11-1-A R103 4

5 6

7 PUMP 1-2 COOLING COMPONENT 2

9 668(V) 15 LEVEL 2 BLOCK 33 1

8 666(V) 14 4.16KV BUS C1 CC PMP 2 17 32 TSH 1484 T074 115 11-3-B F

38 37 36 35 PT 1455 P068 532 5095 M

ZONE D-30 ZONE B-34 OPEN OPEN CLSD CLOSE OPEN OPEN CLSD CLOSE Z126 LEVEL 3 BLOCK 1460 125 FC OPEN OPEN CLSD CLOSE Z105 LEVEL 3 BLOCK FC 1495 41 42 LC 43 ZONE K-18 TE 1649 T104 TE 1648 T103 OPEN OPEN CLSD CLOSE 2645 531 530 OPEN OPEN CLSD CLOSE 5098 549 OPEN OPEN CLSD CLOSE 2649 91 OPEN OPEN CLSD CLOSE LEVEL 3 BLOCK Z107 (D) 170 168 LO 166 159 160 1474 LO LO TI 1475 PDSH 3982 FIS 1476 800 GPM 1-3-J F065 1-2 HEAT EXCHANGER JACKET C.W.

GENERATOR DIESEL EMERGENCY E10-2 TI 1470 OPEN OPEN CLSD CLOSE LEVEL 3 BLOCK Z106 LO LO LO TI 1472 PDSH 3981 FIS 1473 800 GPM 1-3-B F063 LO TI 1468 156 165 162 1471 161 237 238 239 240 241 242 1-1 1-2 243 244 LO LO 254 253 P42-2 150 149 LO LO 654 652 LO LO 148 147 LO LO 252 251 LO 661 659 LO 662 660 PT 1456 P069 533 OPERATIONAL SCHEMATIC C

COMPONENT COOLING WATER SYSTEM HRB CML JLL ATR RSM VMW PUMP 1-1 COOLING COMPONENT P43-1 P43-2 P43-3 PUMP 1-3 COOLING COMPONENT G

W R

LEVEL 2 BLOCK 4.16KV BUS D1 4.16KV BUS C1

  • CL-1*
  • CL-1*
  • CL-1*
  • CL-1*

18 19 ARRANGEMENT PIPING TEST COUPON CORROSION

  • CL-7*

23 24 G

W R

225 247 175 67

  • CL-1*
  • CL-1*
  • CL-7*
  • CL-3*
  • CL-1*

134 133 154 153 137 138 LO LO LO 1-2 BRG OIL COOLER HP INJ PUMP 1-2 HOUSING CLNG PUMP BRG DECAY HEAT 1-1 BRG OIL COOLER HP INJ PUMP 1-1 HOUSING CLNG PUMP BRG DECAY HEAT P42-1 653 655 131 LO 132 151 152 136 135 LO LO SYSTEM HEAT EXCHANGERS CONTAINMENT GAS ANALYZER 173 1469 174 LO LO BYPASS 171 1467 172 LO LO FO

  • CL-7*
  • CL-7*
  • CL-7*

LEGEND CONTROL LOGICS FOLLOWING ACTIONS WILL OCCUR IN THE EVENT OF A SAFETY LEVEL 2 SIGNAL LEVEL 3 SIGNAL

- PHASE A OR C TIME DELAY OVERCURRENT SENSED BY RELAY CO (SEE NOTE 5) AND PHASE A OR C INSTANTANEOUS OVERCURRENT SENSED

- INSTANTANEOUS GROUND OVERCURRENT SENSED BY 50GS RELAY WATER HEADER INTAKE LINE 1 RETURN ISOLATION VALVE 5097 ISOLATION VALVE 5096 (ZONE C-8) AND COMPONENT COOLING WATER

1. ALL VALVES ARE PREFIXED WITH "CC" UNLESS OTHERWISE NOTED.

ANNUNCIATOR ANNUNCIATOR ENGRAVING BY RELAY ITT

- PHASE A OR C INSTANTANEOUS OVERCURRENT SENSED BY RELAY IIT AUTOMATICALLY CLOSE IF IT IS 20% OPEN AND COMPONENT COOLING LOGIC FOR COMPONENT COOLING WATER HEADER DISCHARGE LINE 1 INLET ISOLATION VALVE 5095 (ZONE D-8) AND COMPONENT COOLING NOTES

  • CL-1* WITH REGARD TO THE COMPONENT COOLING WATER SYSTEM, THE
  • CL-3*

(ZONE B-9) WILL AUTOMATICALLY CLOSE IF COMPONENT COOLING WATER

  • CL-4*

GREEN DENOTES DEVICES LOCATED IN THE CONTROL ROOM

  • CL-1*
  • CL-1*
  • CL-1*
  • CL-1*

ZONE A-23 ZONE C-30 NOTE 5 NOTE 5 NOTE 5 7860 GPM AT 7860 GPM AT 7860 GPM AT 25 3.

FEATURES ACTUATION SYSTEM (SFAS) SIGNAL:

  • CL-2* COMPONENT COOLING PUMP 1-1 (ZONE K-3) WILL TRIP IF ANY OF THE COMPONENT COOLING WATER AUXILIARY EQUIPMENT INLET VALVE 1495
  • CL-5* COMPONENT COOLING WATER SURGE TANK ATMOSPHERIC VENT VALVE 1412 O

IL4801 HS4801 MCC F11A TO STOP A COMPONENT COOLING WATER PUMP OR TO CHANGE POSITION OF A COMPONENT COOLING WATER VALVE DURING AN SFAS, EACH COMPONENT'S "BLOCK" PUSHBUTTON MUST BE DEPRESSED FIRST.

RO3980 BREAKER BF1119 MCC E11D BREAKER BE1161 MCC F11D BREAKER BF1161 SV1474 FE1476 SV1467 SV1471 FE1473 RO3979 FE1422 HIS1414A S-036-5 S-036-4 FE1432 FE1427 HIS1416D HIS1416C HIS1418A HI RAD 11-1-A SV1495 SV1460 5096 OPEN OPEN CLSD CLOSE

  • CL-7*

BREAKER BE1226 MCC E12A M

M S-021 SH 1 0

EWT SW232 SW233 BLUE DENOTES COMPONENT COOLING WATER LINE 1 FLOWPATH ORANGE DENOTES COMPONENT COOLING WATER LINE 2 FLOWPATH RED DENOTES COMPONENT COOLING WATER SYSTEM COMMON SUPPLY FLOWPATH PURPLE DENOTES COMPONENT COOLING WATER SYSTEM COMMON RETURN FLOWPATH 1-2 REMOVAL COOLER DECAY HEAT E27-2 S

FO S

FO S

FO M

M M

O S-020,E-11 M

S FO MCC F11A BREAKER BF1106 TRIP BREAKER AD113 PULL TO LOCK BREAKER AD108 CLOSE TRIP PULL TO LOCK CLOSE TRIP PULL TO LOCK BREAKER AC108 CLOSE TRIP PULL TO LOCK BREAKER AC113 O S-051,B-40 ZONE F-27 HEADER INTAKE LINE 2 RETURN ISOLATION VALVE 5098 (ZONE J-12)

LO 155 501 (V) 158 (V) 179 SYSTEM ANALYZER GAS CONTAINMENT TO/FROM SYSTEM ANALYZER GAS CONTAINMENT TO/FROM (D) 1-1 REMOVAL COOLER DECAY HEAT E27-1 169 167 SYSTEM REMOVAL HEAT DECAY TO/FROM SYSTEM REMOVAL HEAT DECAY TO/FROM 504 (V) 1-1 HEAT EXCHANGER JACKET C.W.

GENERATOR DIESEL EMERGENCY E10-1 S

FO TI 1421 TIC 1429 2.

  • CL-7* COMPONENT COOLING WATER LINE 1 VALVE 2645 (ZONE K-11) WILL JACKET DIESEL GENERATOR TO/FROM NOTE 12 ZONE B-31 ZONE A-31 JACKET DIESEL GENERATOR TO/FROM NOTE 12 O S-051,B-40 NOTE 5 RT 1412 RT 1413 O S-020,G-6 O S-051,B-40 WATER SYSTEM SERVICE FROM FOR GENERAL NOTES, PIPING SYMBOLS, INSTRUMENTATION SYMBOLS 4.

11-4-88 WATER SYSTEM SERVICE FROM O

O WATER SYSTEM SERVICE TO 1-1 HEAT EXCHANGER COMPONENT COOLING E22-1 1-3 HEAT EXCHANGER COMPONENT COOLING E22-3 WATER SYSTEM SERVICE FROM O

O WATER SYSTEM SERVICE TO O

O 1-2 HEAT EXCHANGER COMPONENT COOLING E22-2 TSH 1435A 115 11-2-B F

T073 TIC 1434 NOTE 4 34 WATER SYSTEM SERVICE TO LT LT TANK IF HIGH RADIATION IS SENSED BY RSH1412 OR RSH1413 NOTE 14 NOTE 14 NOTE 14 LOGIC FOR COMPONENT COOLING WATER LINE 2 VALVE 2649 (ZONE HB JAN MP HIS1418 AD113 II 1418 HIS5096 BF1106-A CC5096 SUPPLY LINE 2 NON-ESSENTIAL CCW ISOLATION VALVE HIS1460A AOV HIS1460 CC1460 CLRS CCW TO MU PUMP HIS5095 BE1226-A CC5095 SUPPLY LINE 1 NON-ESSENTIAL CCW ISOLATION VALVE HIS1467A AOV HIS1467 CC1467 HIS5098 BF1119-A CC5098 RETURN CTMT BLDG LINE 2 NON-ESSENTIAL CCW ISOLATION VALVE CC PMP 3 1

CH II 1416A II 1416B ACD3 AD108 2

CH CC PMP 3 HIS1416A HIS1416B HIS1414 AC113 CCW PMP 1 II 1414 HIS1469A AOV HIS1469 CC1469 ANNUNCIATOR TABLE NOTE 6 NORM CCW HIS1495A AOV HIS1495 CC1495 NON-ESSENTIAL HEADER CCW TO AUX BLDG ACD2 AC108 HIS2645 BE1161-D CC2645 RETURN AUX BLDG LINE 1 NON-ESSENTIAL CCW ISOLATION VALVE HIS2649 BF1161-D CC2649 RETURN AUX BLDG LINE 2 NON-ESSENTIAL CCW ISOLATION VALVE LEVEL 4 SIGNAL NOTE 18

  • CL-5*

NOTE 18

  • CL-5*

E198-2 E198-1 PUMP 1-1 SA231A K-3 STARTS BLOCK PUSHBUTTON VALVE 1495 SA321A B-9 CLOSES BLOCK PUSHBUTTON VALVE 1338 SA422D C-34 CLOSES BLOCK PUSHBUTTON VALVE 1407A SA421B C-27 CLOSES BLOCK PUSHBUTTON IF VALVE >20% OPEN.

IF VALVE >20% OPEN.

VALVE 1407B SA422B C-29 CLOSES BLOCK PUSHBUTTON VALVE 1411A SA421A D-27 CLOSES BLOCK PUSHBUTTON VALVE 1411B SA422A D-29 CLOSES BLOCK PUSHBUTTON VALVE 1567A SA421C B-29 CLOSES BLOCK PUSHBUTTON IF VALVE >20% OPEN.

VALVE 1567B SA422C B-30 CLOSES BLOCK PUSHBUTTON IF VALVE >20% OPEN.

COMPONENT SIGNAL ZONE ACTION REMARKS III. COMPONENT COOLING WATER FLOW 1000 GPM AS SENSED BY V. COMPONENT COOLING WATER FLOW 1000 GPM AS SENSED BY 6.

5. WHITE INDICATING LIGHT ON HANDSWITCHES HIS1414, HIS1416A, INATES WHEN TIME DELAYED OVERCURRENT ALARM RELAY HAS OPERATED.

"NOT OPER" AS INDICATED BY THE "BYPASS" LIGHT (ZONE H-16).

WHENEVER THE COMPONENT COOLING WATER SYSTEM IS INOPERABLE, THE OPERATOR IS TO PLACE HANDSWITCH HS4801 (ZONE H-16) IN 65 PSID 65 PSID 65 PSID SAMPLING SYSTEM TO SAMPLING SYSTEM TO S-036-3 SAMPLING SYSTEM TO WATER SYSTEM SERVICE FROM TE 4678 WATER SYSTEM SERVICE FROM VALVE 1460 SA322A C-10 CLOSES BLOCK PUSHBUTTON K-12), COMPONENT COOLING WATER HEADER DISCHARGE LINE 2 INLET 634 (V) 40 (V)

(V) 177 NOTE 20 (V) 64 96 (V)

(D) 163 164 (D)

(V) 534 (V) 535 (V)

(V) 305 306 SURGE TANK LEVEL SIDE 1 47 IN AS SENSED BY LSLL3757A WATER SURGE TANK LEVEL SIDE 1 IS 37.125 IN AS SENSED BY (V) 493 13 600 (V)

( S-020,D-14)

(V) 31 22 28 (D)

(D)

( S-020,D-14) 157 (V)

( S-020,D-11)

( S-020,D-9)

(V)

(D)

(D) 30 21 27 (V)

(D)

(D) 29 20 26

( S-020,D-9)

(D)

(D) 602 (V) 603 (V) 606 304 (V)

( S-020,D-11)

(V) 11 605 604 113 (V)

(D)

(D) 507 505 506 (V) 508 (V) 648 (D) 647 (D)

(V) 651 502 (D) 503 (V)

(V) 109 500 (V)

(D) 105 (D) 509 CONDITIONS I, II, III AND (IV OR V) EXIST:

(ZONE J-11) IS SIMILAR.

I. VALVE 20% OPEN.

LSLL3757B AND LSLL3757C.

II. SURGE TANK LEVEL SIDE 1 37.125 IN AS SENSED BY IS SIMILAR EXCEPT SURGE TANK LEVEL SIDE 2 IS <36.25 IN AS AND OPERATIONAL SCHEMATIC INDEX, SEE INDEX SHEET DWG OS-000.

INFORMATION ONLY (D)

LC LC LC LC EDG 1 CCW FLOW LO EDG 2 CCW FLOW LO 1-3-B 11-1-A CCW RETURN RAD HI 11-1-B CCW HX 1 OUTLET TEMP HI 11-2-A CCW SURGE TK LVL LO-LO 11-2-B CCW HX 2 OUTLET TEMP HI 11-3-A CCW SURGE TK LVL LO 11-3-B CCW HX 3 OUTLET TEMP HI 11-4-A CCW SURGE TK LVL HI 11-4-B CCW PMP 1 FLOW LO 11-5-B CCW PMP 2 FLOW LO 11-6-B CCW PMP 3 FLOW LO VALVE 1328 SA421D B-34 CLOSES BLOCK PUSHBUTTON 1-3-J LC LC LC LC ZONE D-24 ZONE D-27 ZONE F-26 ZONE F-24 125 PSIG 11047 125 PSIG 11048 TT 4678 1437 1437B 1422A 1422B 5VM 1423 1423A 1423B 1428 1428A 1428B 5VM FIS 1427D

  • CL-7*

FIS 1427 F074 5VM FIS 1427C

  • CL-7*

5VM 1427A 1427B 1415A 1415 1415B 1417 1417A 1417B 1438 1438A 1438B FIS 1432 F072 FIS 1432C 5VM 1419 1419B 1419A 1439 1439A 1439B

  • CL-7*

1432A 1432B 1433 1433A 1433B 2VM 1456 1456A 2VM 1455 1455A 5VM 1473A 1473B 1473C 1473D 5VM 3981A 3981B 3981C 3981D 5VM 1476A 1476B 1476C 1476D 5VM 3982A 3982C 3982B 3982D ZONE H-41 ZONE G-39 ZONE C-36 ZONE C-36 ZONE A-38 FOR THE OPERATION OF TIC1424, TIC1429 AND TIC1434 (ZONES K-7, G-7 AND D-7) SEE SERVICE WATER SYSTEM DWG OS-020, *CL-7*.

PUMP 1-2 SA232A D-3 STARTS BLOCK PUSHBUTTON PUMP 1-3 SA231B,SA232B G-3 STARTS BLOCK PUSHBUTTON (ZONE A-43) WILL AUTOMATICALLY SHIFT TO THE MISC WASTE DRAIN (ZONES J-1 AND C-1).

LSLL3757B (ZONE E-38) AND 37.25 IN AS SENSED BY LSLL3757C (ZONE D-38) OR THE BREAKERS FOR PUMPS 1-1 AND 1-3 ARE BOTH OPEN.

SENSED BY LSLL3758B (ZONE E-44) AND <36.75 IN AS SENSED BY HIS1416B AND HIS1418 (ZONES J-3, F-2, F-4 AND C-3) ONLY ILLUM-VALVE 1467 SA311C H-10 OPENS BLOCK PUSHBUTTON VALVE 1469 SA312C H-13 OPENS BLOCK PUSHBUTTON LEVEL SIDE 2 35 IN AS SENSED BY LSLL3758A (ZONE F-44).

AUTOMATICALLY CLOSE IF COMPONENT COOLING WATER SURGE TANK COMPONENT COOLING WATER VALVE 1460 (ZONE C-10) WILL (ZONE F-38).

FIS1432C (ZONE C-5).

NOTES CONT'D ON SH. 2 (D) 3000 GPM 11-5-B 3000 GPM 11-6-B 3000 GPM 11-4-B 5VM 1422C 1422D 1427C 1427D 5VM 1432C 1432D 1000 TEST CONN.

1002 TEST CONN.*CL-7*

5097 M

BREAKER BE1227 MCC E12A OPEN OPEN CLSD CLOSE HIS5097 BE1227-A CC5097 RETURN CTMT BLDG LINE 1 NON-ESSENTIAL CCW ISOLATION VALVE 1003 (D)

LO LO LO LO LO LO DFN= /OPSCH/OS21S1.DGN SBW A

B SEAL WATER PUMP VALVE "A" VALVE "B" P43-1 P43-2 P43-3 5099A 5100A 5101A 5099B 5100B 5101B PUMP DETAIL COMPONENT COOLING (B-3)

SEE DETAIL 1437A PI 1437 FO SV1469 S

FO NC NC NC NC SBW FOLLOWING CONDITIONS EXIST:

SBW LOGIC FOR PUMPS 1-2 AND 1-3 (ZONES D-3 AND G-3) ARE SIMILIAR.

VALVE 2645 WILL AUTOMATICALLY OPEN IF

  • CL-13*
  • CL-12*
  • CL-2*
  • CL-1*

12 (D)

(B-3)

SEE DETAIL

  • CL-13*
  • CL-12*
  • CL-2*
  • CL-1*

(D)

(B-3)

SEE DETAIL

  • CL-13*
  • CL-12*
  • CL-2*
  • CL-1*

IN PLACE ABANDONED IN PLACE ABANDONED 4

11 88 3

20 14 6 1 15 4 4 16

  • CL-6* DELETED IN PLACE ABANDONED IN PLACE ABANDONED 39 DB 04-04-16

-005 REV.00 INC. DUN 11-0614-001 37 SAC SSK RACKED OUT POSITION.

IV. BREAKER FOR PUMP 1-1 IS IN THE TEST OR FIS1427C (ZONE F-5).

LSLL3758C (ZONE D-44), COMPONENT COOLING WATER FLOW IS SENSED COMPONENT COOLING WATER PUMP IS 1-2.

BY FIS1422D AND FIS1427D (ZONES J-5 AND F-5) AND 38 SEE OS-021 SH 2 AND SH 3 FOR CONTROL LOGICS, NOTES AND REFERENCES SAP BTR SAP 39

  • CL-4*
  • CL-1*

(V) 203 DELETED 202 (V) 201 (V)

OPER NOT CDA

-002 REV.00 INC. DUN 15-0293-001 LO LO 005 BOTH REV.0

-005 & 15-0041-001-INC. DUN 15-0040-001 39 39 14 13 12 10 9

8 7

6 5

4 3

2 14 13 10 9

8 7

6 5

4 3

2 15 16 17 15 16 17 REV DAVIS-BESSE NUCLEAR POWER STATION UNIT NO 1 DRAWING NO SCALE DESIGNED DATE DRAWN DATE NO NONE J

H E

D C

B A

G F

K J

H E

D C

B A

G F

K REVISIONS BY CH'K ENGR ENGR SUPV ENGR SYS ENGR OPS ENGR DES MGR 11 1

1 12 11 Leak Location CC1 Fails to close

Davis-Besse Initial License Exam 2024 Admin JPM RO-A3

FOR TRAINING USE ONLY VSDS Standard Map Survey Report Survey DB-M-2018-TRG

FOR TRAINING USE ONLY VSDS Standard Map Survey Report Survey DB-M-2018-TRG Cooler 1-2 DH HPI Cooler 1-1 CS Sump ALARA RA Catwalk CA DR 2 15 DR 1 12 CA DR 10 50 DR 9 22 DR 3 20 DR 4 60 DR 5 70 DR 7 10 DR 6 20 DR 8 10 DR 12 5

4 1

2 3

5 7

6 8

DR 11 HS* 540 11

FOR TRAINING USE ONLY VSDS Standard Map Survey Report Survey DB-M-2018-TRG Type Inst.

Value Units Position Notes 1

DR N/A 12 mrem/hr 2

DR N/A 15 mrem/hr 3

DR N/A 20 mrem/hr 4

DR N/A 60 mrem/hr 5

DR N/A 70 mrem/hr 6

DR N/A 20 mrem/hr 7

DR N/A 10 mrem/hr 8

DR N/A 10 mrem/hr 9

DR N/A 22 mrem/hr 10 DR N/A 50 mrem/hr 11 DR HS N/A HS

  • 540 mrem/hr Hot Spot # 1 Elbow, placard reads *540 /11/@ 30 CM N/A

+11 mrem/hr 12 DR N/A 5

mrem/hr Type Inst.

Value Units Position Notes 1

Smear N/A

/ 22 DPM/100 cm2 floor N/A

< MDA DPM/100 cm2 2

Smear N/A

/ 47 DPM/100 cm2 floor N/A

< MDA DPM/100 cm2 3

Smear N/A

/ 62 DPM/100 cm2 floor N/A

< MDA DPM/100 cm2 4

Smear N/A

/ <MDA DPM/100 cm2 floor N/A

< MDA DPM/100 cm2 5

Smear N/A

/ 38 DPM/100 cm2 floor N/A

< MDA DPM/100 cm2 6

Smear N/A

/ 38 DPM/100 cm2 floor N/A

< MDA DPM/100 cm2 7

Smear N/A

/ 587 DPM/100 cm2 floor N/A

< MDA DPM/100 cm2 8

Smear N/A

/ MDA DPM/100 cm2 floor N/A

< MDA DPM/100 cm2

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A3 Page 1 of 5 Examinee:

Date:

Examiner:

Facility: Davis-Besse JPM No: OPS-JPM-305 Task

Title:

Stay Time Calculation Task No: 115-035-01-0100 System:

K/A

Reference:

2.3.12 (3.2)

Safety Function:

Time Critical Task: No Alternate Path:

Validation Time: 20 minutes Method of testing:

Simulated Performance ___

Actual Performance X Classroom X Simulator ___

Plant ___

Task Standard:

Determine the total dose received and the time required to receive an EAD Dose Alarm.

Required Materials:

Survey Map DB-M-2018-TRG Calculator General

References:

None Notes:

None Initial Conditions:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Initiating Cue:

The Initiating Cues are specified in the Examiner/Student Copy Performance Measure pages.

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A3 Page 2 of 5 EXAMINER COPY INITIAL CONDITIONS:

The plant is in procedure DB-OP-02527 Loss of Decay Heat Removal Refer to the Decay Heat Pump area Rad Pro Survey Map.

You are to stage yourself inside the radiologically controlled area while awaiting directions.

You are to remain in the area identified on the survey map with the lowest possible dose during the wait time.

Your task will be to vent Decay Heat Pump 2 using vent valve DH56, DH PUMP 2 CASING VENT when directed.

Your RWP has the following limits:

- Dose Rate Alarm = 75 mrem/hr

- Dose Alarm = 40 mrem Aux Building 545 ECCS Room 2 is posted as a Radiation Area Time line:

0800 - You enter ECCS Room 2 room and wait in the area identified on the survey map with the lowest possible dose 0830 - Wait time is complete, you start venting Decay Heat Pump 2 0855 - Venting is complete, you immediately exit the room and report back to the CTRM INITIATING CUE:

Based upon the above timeline, the information from your RWP and the Aux Building 545 ECCS Room 2 survey map:

1.

Determine the total amount of dose that was received from room entry to exit. Use the highest potential dose rate in the area of the pump in determining your dose for the actual venting portion of the entry.

2.

Assuming no dose was received until you entered ECCS Room 2, determine the MAXIMUM time (including the wait time) you could take to vent the Decay Heat Pump 2 until you would receive an EAD Dose Alarm.

You do not have to include any dose received while transiting from the waiting area through the room to and from the pump.

(Provide examinee a copy of Survey Map DB-M-2018-TRG)

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A3 Page 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:

The plant is in procedure DB-OP-02527 Loss of Decay Heat Removal Refer to the Decay Heat Pump area Rad Pro Survey Map.

You are to stage yourself inside the radiologically controlled area while awaiting directions.

You are to remain in the area identified on the survey map with the lowest possible dose during the wait time.

Your task will be to vent Decay Heat Pump 2 using vent valve DH56, DH PUMP 2 CASING VENT when directed.

Your RWP has the following limits:

- Dose Rate Alarm = 75 mrem/hr

- Dose Alarm = 40 mrem Aux Building 545 ECCS Room 2 is posted as a Radiation Area Time line:

0800 - You enter ECCS Room 2 room and wait in the area identified on the survey map with the lowest possible dose 0830 - Wait time is complete, you start venting Decay Heat Pump 2 0855 - Venting is complete, you immediately exit the room and report back to the CTRM INITIATING CUE:

Based upon the above timeline, the information from your RWP and the Aux Building 545 ECCS Room 2 survey map:

1.

Determine the total amount of dose that was received from room entry to exit. Use the highest potential dose rate in the area of the pump in determining your dose for the actual venting portion of the entry.

2.

Assuming no dose was received until you entered ECCS Room 2, determine the MAXIMUM time (including the wait time) you could take to vent the Decay Heat Pump 2 until you would receive an EAD Dose Alarm.

You do not have to include any dose received while transiting from the waiting area through the room to and from the pump.

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A3 Page 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".

START TIME:

1.

PERFORMANCE STEP: Determine the dose that will be received while waiting in the

........C........

lowest dose waiting area in the radiologically controlled area.

STANDARD:

Calculates the dose received for the duration of the time in the low dose area Map location DR12.

Based on a 30-minute wait at the area with a dose rate of 5 mrem/hr:

Low Dose Wait Area Dose: 5 mrem/hr X 0.5 hr = 2.5 mrem COMMENT: Acceptable range is 2.5 to 3.0 mrem CUE:

None SAT UNSAT

2.

PERFORMANCE STEP: Determine the dose that will be received while venting the pump.

........C........

STANDARD:

Calculates the dose received for the duration of the time venting the pump. Per the Survey Map location DR10 has the highest dose at 50 mrem/hr.

Based on a 25 minute task duration at the pump with a dose rate of 50 mrem/hr:

Pump Venting Dose: 50 mrem/hr X (25/60) hr = 20.83 mrem COMMENT: Acceptable range is 20.8 to 21 mrem.

CUE: None SAT UNSAT

Job Performance Measure Form 3.2-3 Worksheet Admin JPM RO-A3 Page 5 of 5

3. PERFORMANCE STEP: Determine the Total dose that will be received while in the area

........C........ performing the task.

STANDARD:

Calculate the dose received for the duration of the task.

TOTAL Dose: 2.5 mrem + 20.83 mrem = 23.33 mrem COMMENT: Acceptable range is 23.3 to 24.0 mrem CUE: None SAT UNSAT

4.

PERFORMANCE STEP: Determine the maximum time to complete the task before

........C........

reaching the EAD Dose Alarm setpoint.

STANDARD:

Calculates the maximum time until Dose Alarm.

The RWP Dose Alarm setpoint is 40 mrem.

Subtract the low dose waiting area dose from the total allowed:

40 mrem - 2.5 mrem = 37.5 mrem Vent Time Dose Rate is 50 mrem / hr:

37.5 mrem/ 50 mrem / hr = 0.75 hrs or 45 minutes TOTAL Time is 45 minutes COMMENT: Acceptable range is 44 to 45 minutes.

CUE: None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by examinee)

END TIME: __________

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