ML101650151
| ML101650151 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/28/2010 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| 50-250/07-301, 50-251/07-301, ES-301, ES-301-1 50-250/07-301, 50-251/07-301 | |
| Download: ML101650151 (712) | |
Text
{{#Wiki_filter:ES-301 Administrative Topics Outline ES-3O-Form ES-301-1 Facility: Turkey Point Units 33 &
&4 04/2007 Date of Examination: 0412007 Exam Level: SRO (I) 2007-30 1 Operating Test Number: 2007-301 Administrative Topic Type Code Describe Activity to be performed (See Note) (See Note)
A. l.a A.l.a Verify Adequate Shutdown Margin CR D CR,D Conduct of Operations (G2.1 .7 - 3.7/4.4 & 001 A4.11 (G2.l.7 - A4. 11 - 3.5/4.1) Initiate a Containment Purge and Respond to Termination A I b A.l.b. S,M Criteria Conduct of Operations 2.5/3.4, 029 Al.02 (G2.3.9 - 2.5/3.4,029
- A1.02 - 3.4/3.4 &
- & 073 A2.0.2 - 2.7/3.2)
Write Equipment Clearance Order to remove equipment from A2 A.2
. CR,P service (Charging Pump)
Equipment Control (G2.2.13 - 3.6/3.8) A.3 Read a Survey Map and Apply RWP requirements CR M CR,M Radiation Control (G2.3.10 - 2.9/3.3) A.4 - SRO Review NRCOC Notification Form CR N CR,N Emergency Plan (G2.4.43 - 2.8/3.5) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 55 are required.
- Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank (:::3
( 3 for ROs, :::4 4 for SROs) (N)ew or (M)odified from bank (~l) (1) (P)revious 2 Exams (:::1 (1 Randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Units Facility: Units 3 &&4 Date of Examination: 04/2007 Date 04/2007 Exam Level: RO Operating Test Number: 2007-301 Administrative Topic Type Code Describe Activity to be performed (See Note) (See Note) A.1.a A.l.a Conduct a 11M l/M Plot Plot CRD CR,D Conduct of Operations (G2.2.34 - 2.8/3.2, 001 K5.75 - 2.9/3.5 &
- - & 015 K5.05 - 4.114.4)
- 4.1/4.4)
A I b Initiate a Containment Purge and Respond to Termination A.l.b
. S,M Criteria Conduct of Operations (G2.3.9 - 2.5/3.4, 029 Al.02 - 3.4/3.4 &
- - & 073 A2.0.2 - 2.7/3.2)
A2 Write Equipment Clearance Order to remove equipment from A.2.
. CR,P service (Charging Pump)
Equipment Control (G2.2.13 - 3.6/3.8) A.3 Radiation Control - - A.4 A.4-RO - RO Make Emergency Notifications as Communicator C,M M Emergency Plan (G2.4.43 - 2.8/3.5) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 55 are required.
- Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank (( 3::;3 for ROs, ::;4 S4 for SROs)
(N)ew or (M)odified from bank (1) (2: 1) (P)revious 22 Exams (1(::;1 Randomly selected)
ES-301 Roomlln-Plant Systems Outline Control Room/In-Plant Form ES-301-2 Facility: Turkey Point Date of Examination: 04/2007 Exam Level (circle one): RO / SRO-ISRO-l Operating Test No.: 2007-301 Systems@ (8 for RO; 7 for SRO-I; Control Room Systems@ SRO-l; 2 or 3 for SRO-U) System /I JPM Title Code* Type Code* Safety Function
- a. Respond to Pressurizer Pressure Control Malfunction (01041013102) MAS 3 (010 A2.02 - 3.9/3.9)
- b. Respond to Loss of RHR Inventory (01050003302) DSL 4P (002 A2.01 - 4.3/4.4)
- c. Adjust Rod Position for Tavg Control (01028025301) MAS 1 1
(001 A2.1 A2.111 - 4.4/4.7 &
- & 001 A2.14 3.7/3.9)
- d. Test the Source Range NIS Channel (Shutdown) (01059017200) DSL 7 (015 A4.02 - 3.9/3.9 &
- & 015 A4.03 - 3.8/3.9)
- e. Respond to Component Cooling Water System Malfunctions (01030008303) DASL 8 (008 A2.01 - 3.3/3.6 &
- & 062 A2.04 - 3.1/3.4)
- f. Emergency Borate the RCS (01046008303) DASL 2 (004 A2.06 - 4.2/4.3 &
- & 004 A2.14 - 3.8/3.9)
- g. Respond to Loss of 3C Transformer (01005021300) MS 6 (062 A2.05 - 2.9/3.3)
- h. Reduce PRT Liquid Temperature (01041012100) DS 5 (010 A1.03 - 2.9/3.2)
Systems@ (3 for RO; 3 for SRO-I; In-Plant Systems@ SRO-l; 3 or 2 for SRO-U)
- i. EnterContainmentvia Enter Containment via Emergency Access Hatch (01051009100) DRE 5 (103 A2.05 - 2.9/3.9)
- j. Perform Gaseous Radwaste Release (0-OP-061.14 sect 7.1 - SNPO) - NR 9 (071 A4.26 - 3.1/3.9)
- k. Recover from a Unit 4 EDG Auto Start Failure (04023030500) DAE 6 (064 A4.01 - 4.0/4.3)
@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes SRO-l / SRO-U Criteria for RO / SRO-I (A)lternate path 4-6 / 4-6 / 2-3 4-6/4-6/2-3 (C)ontrol room (D)irectfrombank (D)irect from bank 918/4
- 0;9/:0;8/:0;4 (E)mergency or abnormal in-plant 1 I 1 / 1
;::1/;::1/;::1 (L)ow-Power 1/ 1 /1
;::1/;::1/;::1 (M)oditied from bank including 1(A)
(N)ew or (M)odified ;::2/;::2/;::1 2I 2/ 1 (P)revious 2 exams 3 / 3/:0;
- 0; 3/:0; 3 I 2 (randomly selected)
(R)CA ;::1/;::1/;::1 (S)imulator
ES-301 ES-301 Control Room/In-Plant Control Room/In-PlantSystems Systems OutlineOutline Form Form ES-301-2 ES-301-2 Facility: Facility: Turkey Point Turke~ Point Date of Date ofExamination: Examination: 04/2007 04/2007 Exam Exam Level Level (circle (circle one): one): RO RO1/SRO-I SRO-l Operating Test Operating Test No.: No.: 2007-301 2007-30 1 Control Room Control Systems@ (8 Room Systems@ (8 for forRO; RO; 77 for forSRO-I; SRO-l; 22 or or33 for forSRO-U) SRO-U) System1/ JPM System JPM Title Title Type Code* Type Code* Safety Safety Function Function
- a. Respond to
- a. Respond to Pressurizer Pressurizer Pressure Pressure Control Control Malfunction Malfunction (01041013102)
(01041013102) MAS MAS 33 (010 A2.02 (010 A2.02 - 3.9/3.9)
- 3.9/3.9)
- b. Respond
- b. Respond to to Loss Loss of of RHR RHR Inventory Inventory (01050003302)
(01050003302) DSL DSL 4P 4P (002 A2.01 - 4.3/4.4) (002 A2.01 - 4.3/4.4) c.c. Adjust Adjust RodRod Position Position for for Tavg Tavg Control Control (01028025301) (01028025301) MAS MAS 11 (001 A2.11 (001 A2.1 1 - 4.4/4.7
- 4.4/4.7 & & 001 001 A2.14 A2.14 3.7/3.9) 3.7/3.9)
- d. Test the
- d. Test the Source Source Range Range NIS NIS Channel Channel (Shutdown)
(Shutdown) (01059017200) (01059017200) DSL DSL 77 (015 A4.02 - 3.9/3.9 (015 M.02 - 3.9/3.9 & 015 A4.03
& 015 A4.03 - 3.8/3.9)
- 3.8/3.9) e.e. Respond Respond to to Component Component Cooling Cooling Water System System Malfunctions (01030008303)
(01030008303) DASL 88 (008 A2.01 (008 A2.01 - 3.3/3.6
- 3.3/3.6 & & 062 A2.04 - 3.1/3.4) 062 A2.04 -
f.f. Emergency Borate Emergency Borate the the RCS RCS (01046008303) (01046008303) DASL 2 (004 A2.06 (004 A2.06 - 4.2/4.3
- 4.2/4.3 & & 004 004 A2.14 A2.14 - 3.8/3.9)
- 3.8/39) g.
- g. Respond to Respond to LossLoss of of 3C 3C Transformer Transformer (01005021300)
(01 005021 300) MS 6 (062 A2.05 (062 A2.05 - 2.9/3.3)
- 2.9/3.3)
- h. Reduce PRT
- h. Reduce PRT Liquid Liquid Temperature Temperature (0104101210 (01041012100) 0) DS 5 (010 (010 A1.03 A 1.03 - 2.9/3.2) 2.9/3.2)
In-Plant Systems@ In-Plant Systems@ (3 (3 for for RO; RO; 33 for SRO-l; SRO-I; 33 or 22 for SRO-U) i.i. Enter Enter Containment Containment via via Emergency Emergency Access Hatch Hatch (0105100910 (01051009100) 0) DRE DRE 55 (103 (103 A2.05 A2.05 - 2.9/3.9) 2.9/3.9) j.j. Perform Perform Gaseous Gaseous Radwaste Radwaste Release Release (0-OP-061.1 (O-OP-061.14 4 sect sect 7.1 7.1 - SNPO)
- SNPO) NR NR 99 (071 (071 A4.26 M.26 - 3.1/3.9) 3.1/3.9) k.k. Recover Recover from from aa Unit Unit 44 EDG EDG Auto Auto Start Start Failure Failure (0402303050 (04023030500) 0) DAE DAE 66 (064 (064 A4.01 M.01 - 4.0/4.3) 4.0/4.3) @@ All All control control room room (and(and in-plant) in-plant) systems systems must must bebe different different and and serve serve different different safety safety functions; functions; in-plant in-plant systems systems and and functions functions may may overlap overlap those those tested tested inin the the control control room.
room.
- Type Type Codes Codes Criteria Criteria for RO /1SRO-l for RO SRO-I /1SRO-U SRO-U (A)lternate (A)lternate path path 4-6 /14-6 4-6 4-6 /12-3 2-3 (C)ontrol (C)ontrol room room (D)irectfrom (D)irect from bank bank ~9/~8/~4 918/4 (E)mergency (E)mergency or orabnormal abnormal in-plant in-plant ;::1/;::1/;::1 1 / 1 / 1 (L)ow-Powe (L)ow-Power r ;::1/~1/;::1 1 I 1 / 1 (N)ew (N)ewor or(M)odified (M)odified from from bankbank including including 1(A) 1(A) ;::2/~2/~1 2/ 2/ 1 (P)revious (P)revious22exams exams ~ 3/ 1 ~33/1 ~22 (randomly (randomlyselected) selected)
(R)CA (R)CA ~1/~1/~1 (S)imulator (S )imulator
1%t%lI ( ( ( \ I
Appendix C Appendix C Job Performance Job Performance Measure Measure Form Form ES-C-1 ES-C-I Worksheet Worksheet Facility: Facility: Turkey Point Turkey Point No: Task No: Task Respond to Respond to Pressurizer Pressurizer Job Performance Job Performance Task
Title:
Task
Title:
Pressure Control Pressure Control Malfunction Malfunction Measure No: Measure No: Systems Systems - aa KIA
Reference:
K/A
Reference:
010 A2.02 {3.9/3.9} (3.9/3.9) Examinee: Examinee: NRC Examiner: NRC Examiner: Facility Evaluator: Facility Evaluator: Date: Date: Method of testing: Simulator Simulated Performance Actual Performance Yes
-------------------- ----------~~---------
Classroom Simulator Yes
-----~~-----
Plant Plant _________ Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Unit 3 is in Mode 11 at 75% power with all systems in service Task Standards:
- 1. PCV-3-455C or MOV-3-536 manually closed PCV-3-455B manually closed
- 2. PCV-3-4558
~
- 3. Reactor is manually tripped before pressurizer pressure drops below 1835 psig or OT 11T reactor trip OTI2kT setpoint
- 4. Stops 3C RCP before pressurizer pressure drops below 1730 psig auto safety injection setpoint Required Materials:
- 1. 3-ONOP-041.5 3-0NOP-041.5
- 2. 3-EOP-E-0 General
References:
1.
- 1. 3-ONOP-041 3-0NOP-041.5 .5
- 2. 3-EOP-E-0 Initiating Cue:
Respond to plant conditions as Unit 33 Reactor Operator Time Critical Task: Yes/No Validation Time: 15 15 minutes
Appendix C Page 2 of 9 ES-C-I Form ES-C-1 INSTRUCTIONS TO TO OPERA OPERATOR TOR READ TO TO OPERA OPERATOR: TOR: TELL YOU TO BEGIN, WHEN II TELL BEGIN, YOU ARE TO PERFORMPERFORM THE ACTIONS AS DIRECTED DIRECTED ININ THE INITIATING INITIATING DESCRIBE THE GENERAL CONDITIONS UNDER CUES. II WILL DESCRIBE UNDER WHICH THIS TASK IS IS TO BE BE PERFORMED PERFORMED AND PROVIDE AND PROVIDE THE NECESSARY NECESSARY TOOLS WITH WHICH TO PERFORM PERFORM THIS TASK. BEFORE BEFORE STARTING, STARTING, II WILL EXPLAIN THE INITIAL INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB INITIATING PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS: CONDITIONS. Unit 3 is in Mode 11 at 75% power with all systems in service. INITIATING INITIA CUE. TlNG CUE: Respond to plant conditions as Unit 3 Reactor Operator. TERMINATION TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. NOTES TO EVALUAEVALUATOR TOR AND IIF I/F OPERA OPERATOR. TOR:
- 1. Reset simulator to IC-16 IC-i 6 or IC-137.
IC-i 37. If IC-137 IC-i 37 used, skip ahead to step 8.
- 2. Unit 3 is in Mode 1 1 at 75% power with all systems in service.
- 3. Place simulator in run.
- 4. Take PCV-3-455A controller to Manual and set demand at 5%.
- 5. Fail PCV-3-455A as is as follows: Click on Schema ~ REACTOR COOLANT SYSTEM ~ >
PRESSURIZER ~ > PCV-455A ~ > TVHV55AF - PCV455A FAIL AS IS ~ -÷ TRUE then INSERT ~ TVHV455A - PCV-455A VALVE LEAKAGE ~
- enter selected value =
= 0.4 & condition =
= V80A18 then INSERT.
- 6. Verify PORV block valves MOV-3-535 & 536 are open.
- 7. Return PCV-3-455A to AUTO.
- 8. Store temporary IC if needed for repeat runs of this JPM
- 9. Verify QSPDS is working and selected to page 2i 2111 on both channels.
- 10. Open & execute lesson file NRC SRO XXIII JPM a.
ii. When task performance begins, place simulator in run and insert failure as follows: 11.
- 1) Click on Schema ~
- REACTOR COOLANT SYSTEM ~
- PRESSURIZER ~
- P-444 *~ PT-444 >~
TFH1TU44 - PT-444 TRANSMITTER FAIL HIGH * ~ TRUE then INSERT or
- 2) Trigger lesson step PT-3-444 PT-.3-444 FAIL HIGH
- 12. May reduce PCV-3-455A leakage (TVHV455A) to 0.3 to prolong time to 2000 psia as follows:
- 1) Click on Schema *
- 1) ~ REACTOR COOLANT SYSTEM * ~ PRESSURIZER * ~ PCV-455A -* ~
TVHV455A - PCV-455A VALVE LEAKAGE >
- ~ enter selected value ==0.3 (or at value as needed) then INSERT or
- 2) Trigger lesson step PCV-3-455A LEAK ==0.3
- 3. If 3-ONOP-041 i13. 3-0NOP-041.5 .5 step 19 reached and reactor not yet tripped, increase PZR spray valve leakage to drive PZR pressure << 2000 psig as follows:
i)
- 1) Click on Schema - ~ REACTOR COOLANT SYSTEM * ~ PRESSURIZER * ~ PCV-455A > ~
TVHV455A - PCV-455A VALVE LEAKAGE >
- ~ enter selected value ==0.5 (or at value as needed) then INSERT or
- 2) Trigger lesson step PCV-3-455A LEAK ==0.5
I Appendix Appendix C C Page 33 of Page of 99 Form ES-C-1 Form ES-C-I I Denote critical Denote critical steps steps with with aa check check mark mark Start Time Start Time Performed immediate Performed immediate operator operator actions actions of of 3-0NOP-041.5 3-ONOP-041 .5 STEP STEP 1I : SAT
- - SAT UNSAT STANDARDS:
J
..J 11.. Closed PCV-3-455C and/or Closed MOV-3-536
..J1 2. PC3-444J in manual and drove Controller Output toward Placed PC-3-444J ZERO to energize PZR heaters
- 3. Determined PZR pressure decreasing 4..
..Jq 4 Placed PCV-3-455A & PCV-3-455B in manual and drove both closed
- 5. not failed Determined PT-3-445 notfailed
- 6. Determined PORVs PCV-3-455C & PCV-3-456 closed.
- 7. Determined PZR pressure less than normal
- 8. Checked PZR spray valves closed (ERDADS) and determined PCV-3-455A in mid position CUE*
CUE: If operator requests permission to close PORV block valves, as SM, grant permission. of 3-ONOP-041 .5 and verifies immediate operator STEP 2 : Obtains copy 3-0NOP-041.5 actions - - SAT UNSAT 1.
- 1. Obtained control room copy of 3-ONOP-041 3-0NOP-041.5 .5 STANDARDS:
- 2. Reviewed steps 11 thru 3 and foldout page Checked PZR safety valves closed STEP 3 :
- - SAT
- - UNSAT UNSAT Determined PZR safety valves closed STANDARDS: 1. PZR safety acoustic monitor LEDs not
- 1. not lit lit 2.
- 2. PZR PZR safety line line temperature at or nearnear normal
Appendix C of 9 Page 4 of9 ES-C-I Form ES-C-1 STEP 4 : Checked PZR pressure stable or increasing - - SAT UNSAT UNSAT Determined PZR pressure decreasing STANDARD: Checked PZR pressure above normal value STEP 5 : SAT
- - UNSAT Determined PZR pressure below normal value STANDARD:
Checked PZR pressure low or decreasing STEP 6 :
- - SAT UNSAT Determined PZR pressure low and decreasing STANDARD:
STEP Checked & Maintained PZR pressure> 2000 psig 7
- - SAT UNSAT STANDARDS: 1. Continued attempts to restore PZR pressure>
pressure > 2000 psig
- 2. Determined that PZR pressure still > 2000 psig but decreasing still>
- 3. When it is determined that PZR pressure can not be maintained>
J~ 2000 psig, then tripped reactor & turbine and performed immediate actions of 3-EOP-E-0 3-EOP-E-O If reactor tripped because PZR pressure can not be maintained << 2000 psig, allow candidate to perform immediate operator actions CUE: of 3-EOP-E-0 1-4) then inform candidate that another 3-EOP-E-O (steps 1-4) operator will take over performance of EOP network while candidate continues performance of 3-ONOP-041.5. 3-0NOP-041.S.
II Appendix CC Page 55 of Page of 99 Form ES-C-1 Form ES-C-I I Checked PZR heaters operable STEP 88 : Checked PZR heaters operable SAT SAT UNSAT UNSAT 1.
- 1. Checked all PZR heaters on STANDARDS:
- 2. Determined PZR heaters not capable of maintaining pressure I/F operator responds as NSO if directed to perform Att. 11 to evaluate PZR heater output.
CUEs: I/F operator responds as Electrical Dept. if notified that PZR heaters ifF not maintaining PZR pressure Checked if a PORV was leaking STEP 9 : SAT
- - UNSAT Determined that there was no PORV leakage
- 1. PZR relief line temperature returning to normal STANDARDS:
- 2. PRT level/temperature/pressure stable or decreasing
- 3. PZR PORV acoustic monitor LEDs not lit Determined if a leaking PZR safety was causing pressure to decrease STEP 10 - - SAT UNSAT Determined that there was no PZR safety leakage
- 1. PZR safety line temperature stable or decreasing STANDARDS:
- 2. PRT level/temperature/pressure stable or decreasing
- 3. PZR safety acoustic monitor LEDs not lit Once operator reads step requiring determination if RCS leakage is is CUE: causing pressure to decrease, decrease, state that the STA STA will perform perform 3-OSP-3-0SP-041.1 and report results when they become become available.
Appendix C Appendix C Page 66 of Page of 99 Form Form ES-C-1 ES-C-I Checked if pressurizer pressure decreasing STEP STEP 11 11 : Checked if pressurizer pressure decreasing - - SAT SAT
- - UNSAT UNSAT STANDARD:
STANDARD: Determined that pressurizer Determined pressurizer pressure still decreasing decreasing Determined ifif PZR Determined PZR spray valve leakage leakage or failure failure to to close was STEP* 12 STEP 12 - - SAT preventing RCS pressure stabilization
- - UNSAT STANDARD:
Determined that PCV-3-455A not fully closed was preventing RCS pressure stabilization 3-ONOP-041 .5 step 19 reached and reactor not yet tripped, If 3-0NOP-041.5 I/F increase PZR spray valve leakage to drive PZR pressure < < 2000 IfF psig as follows: Click on Schema ~ REACTOR COOLANT OPERATOR CUE CUE: SYSTEM ~ PRESSURIZER ~
> PCV-455A ~
- TVHV455A - PCV- - PCV 455A VALVE LEAKAGE ~ =
- enter selected value = 0.5 (or at value as needed) then INSERT.
Referred to foldout page item #2 and once determined that PZR STEP 13
- pressure can not be maintained >2000 psig then: - - SAT
- 1. Continued efforts to restore PZR pressure - - UNSAT
- 2. Tripped reactor and turbine and performed immediate operator actions of 3-EOP-E-0 3-EOP-E-O STANDARDS:
I~ 1.
- 1. Determined that PZR pressure can not be maintained maintained> > 2000 psig and tripped reactor & turbine before reaching low PZR pressure auto reactor trip setpoint at 1835 1835 psig 2.
- 2. Performed immediate operator actions of immediate operator of 3-EOP-E-0
- a. Verified reactor tripped
- 1) Determined rod bottom
- 1) bottom lights on
- 2) Determined reactor trip
- 2) & bypass trip & bypass breakers breakers open open
- 3) Determined
- 3) Determined rod position position indicators indicators atat zero zero
- 4) Determined
- 4) Determined neutron neutron flux decreasing decreasing b.
- b. Verified Verified turbine turbine tripped tripped
- 1) Determined
- 1) Determined allall turbine stop valves turbine stop valves closed closed j~ 2) Closed
- 2) Closed MSR MSR main steam stop main steam stop MOVs MOVs
- 3) Determined
- 3) Determined MidMid and East GCBs and East GCBs openopen (after (after 30 sec delay) 30 sec delay)
I Appendix Appendix C C Page 77 of Page of 99 ES-C-I I Form ES-C-1 Form c.
- c. Verified power power toto emergency emergency 4kV4kV buses buses
- 1) Determined
- 1) Determined both both 3A 3A or or 3B 3B 4kV buses buses energized energized
- 2) Determined Determined 3D3D 4kV bus bus aligned aligned toto energized energized 3B 3B 4kV 4kV bus bus d.
- d. Checked ifif SI Checked SI actuated
- 1) Determined no SI annunciators on & no safeguards equipment auto started
- 2) Determined SI not required NOTE: SI should not be required at this point unless operator 51 response too slow to trip RCPs before reaching low PZR pressure 51SI setpoint.
Once 3-EOP-E-O IOAs lOAs complete, state that other crew members CUE: will continue in the EOP network while the candidate returns to 3-ONOP-041 .5 step in effect to restore PZR pressure control. ONOP-041.S 3-ONOP-041.5 step in effect Returned to 3-0NOP-041.5 STEP 14 :
- - SAT UNSAT 3-ONOP-041 .5 procedure step in effect Returned to 3-0NOP-041.5 STANDARD:
Reduced PZR spray flow to stop RCS pressure decrease STEP : 15
- - SAT
- 1. Verified PZR spray valves closed UNSAT
- 2. Checked reactor shutdown
- 3. Stopped 3C RCP per 3-OP-041 3-0P-041 .1
- 4. Checked PZR pressure stable or increasing STANDARDS: 1.
- 1. Determined PCV-3-455B & CV-3-31 CV-3-3111 closed while PCV-3-455A indicating mid-position (ERDADS)
- 2. Determined reactor shutdown q..J 3.
- 3. Stopped 303C RCP per 3-OP-041 3-0P-041.1.1 before reaching SI low pressure setpoint (1730 (1730 psig)
- 4. Determined PZR pressure stable or increasing increasing Terminating Terminating 3C RCP stopped 3C stopped and and PZR PZR pressure determined determined stable or increasing increasing STOP Cue:
Cue: Stop Stop Time - - - -
Appendix C Page 8 of 9 ES-C-I Form ES-C-1 Verification of Completion Job Performance Measure No. _S.Lys_t'-.e_m Systems a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
......s_-........c..a Examinees Name:
Examinee's Examiners Name: Examiner's Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiners signature and date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Examiner's
JPM BRIEFING SHEET
- C-) 0 Cl)
INITIAL CONDITIONS: C -- a 01 Unit 3 is in Mode 1 at 75% power with all systems in service. CD t3 0 CD 1 CD 3Cl) CD C, INITIA TlNG CUE: Respond to plant conditions as Unit 3 Reactor Operator. CD Cj, - -D C) - Cl) D C) - - 0 - - cz m
-<0 Co 00 C
rm -I> m0 C TI mr II cn I ZZ IC HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT I I -I I I _-o -1> YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 ci.
.c) 3-0NOP-041.S c)
C-
Title:
Pressurizer Pressure Control Malfunction Safety Related Procedure Responsible Department: Operations Revision Approval Date: 10/7/01 RTSs 92-1254P, 92-1142P, 92-2143P, 93-1420P, 96-0981P, 96-1011P, 96-bliP, 98-0918P, 01-0622P 98-0918P,01-0622P PC/Ms 87-011,90-528, PCIMs 87-011, 90-528, 92-031 0408-9 7 OTSC: 0408-97 W97:TNM/dUsw/bc W97:TNM/dt/sw/bc
Procedure No.: Procedure
Title:
Procedure
Title:
Page: 2 Approval Date: 3-ONOP-041 .5 3-0NOP-041.5 Pressurizer Pressure Control Malfunction 10/7/01 LIST OF EFFECTIVE PAGES Revision gç Page Date 11 10/07/01 2 10/07101 10/07/01 3 10/07/01 10107/01 4 10/07/01 5 10/07/01 6 10/07101 10/07/01 7 10/07/01 10107/01 8 10107/01 10/07/01 99 10/07/01 10 10107/01 10/07/01 11 10107/01 10/07/01 12 10/07/01 10107/01 13 10107/01 10/07/01 14 10/07/01 15 10/07/01 10107/01 16 10107101 10/07/01 17 10107/01 10/07/01 Foldout Page 10107/01 10/07/0 1 W97:TNM/dt/sw/bc W97:TNM/dtlsw/bc
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Procedure Page: Page: 33 Approval Approval Date: Date: 3-ONOP-041.5 3-0NOP-041.5 Pressurizer Pressure Pressurizer Pressure Control Control Malfunction Malfunction 10/7/01 10/7/01 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 This procedure provides This procedure operator response provides operator response guidelines guidelines for for pressure pressure control control in in the the event event either nonnal pressurizer either nonnal pressurizer pressure pressure control control malfunctions malfunctions or or aa PZR PZR PORV PORV fails fails when when aligned aligned for nonnal for control. normal pressure control. 2.0 2.0 SYMPTOMS SYMPTOMS 2.1 Annunciators 2.1.1 Annunciator A 9/2, PZR CONTROL HVLO HIILO PRESS 2.1.2 Annunciator A 9/5, PRZ PRESSURE CONTROLLER HI OUTPUT 2.1.3 Annunciator A 4/1, PORV/SAFETY OPEN 2.1.4 Annunciator A 711, 7/1, PRT HVLO HI/LO LEVEL HI PRESS/TEMP 2.1.5 Annunciator A 7/2, PZRPORVPZR PORV HI TEMP 2.1.6 Annunciator A 7/3, PZR SAFETY VALVE AlB/C AIB/C HI TEMP 2.2 Indications 2.2.1 PZR relief line temperature, TI-3-463, INCREASING 2.2.2 PZR relief tank level, LI-3-470, INCREASING 2.2.3 PZR relief tank temperature, TI-3-471, INCREASING 2.2.4 PZR relief tank pressure, P1-3-472, PI-3-472, INCREASING 2.2.5 PZR PORV/Safety Acoustic Monitor, LEDs LIT 2.2.6 PZR PORV indicating lights indicate OPEN OR INTERMEDIATE 2.2.7 PZR PORV Block Valve indicating lights indicate INTERMEDIATE 2.2.8 Pressurizer spray valves, heaters and/or PORVs operation not compatible with plant conditions. W97:TNM/dtlsw/bc W97:TNM/dtlsw/bc
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Page: 4 Approval Date: 3-0NOP-041.5 Pressurizer Pressure Control Malfunction 10/7/01 2.2.9 P1-3-444 or PI-3-445 Pressure indicator PI-3-444 P1-3-445 not compatible with other RCS pressure indications. 2.2.10 PZR safety line temperature, TI-3-465, INCREASING INCREASiNG or at saturation temperature associated with the PZR relief tank pressure per Attachment 2. 2.2.11 PZR safety line temperature, TI-3-467, INCREASING or at saturation temperature associated with the PZR relief tank pressure according to Attachment 2. 2.2.12 PZR safety line temperature, TI-3-469, INCREASING iNCREASING or at saturation temperature associated with the PZR relief tank pressure according to Attachment 2. W97:TNM/dtlsw/bc W97:TNM/dt/sw/bc
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Page: 5 Approval Date: 3-0NOP-041.5 Pressurizer Pressure Control Malfunction 10/7/01
3.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REOUIRED/COMMITMENT DOCUMENTS 3.1 References 3.1.1 Technical Specifications
- 1. 3/4.4.3, Pressurizer
- 2. 3/4.4.4, Relief Valves
- 3. 3.4.9.3, Overpressure Mitigating System 3.1.2 Final Safety Analysis Report
- 1. Section 4, Reactor Coolant System
- 2. Figure 4.2-1, Reactor Coolant System 3.1.3 FPL Drawings
- 1. 5610-T-D-16B, Pressurizer Pressure Control 3.1.4 Procedures
- 1. 3-OP-041.2, Pressurizer Operation 3-0P-041.2,
- 2. 3-OSP-041.1, RCS Leak Rate Calculation 3-0SP-041.1,
- 3. MI-41-011, Pressurizer Pressure Control Loop 3.1.5 PC/M, Correspondence)
Miscellaneous Documents (i.e., PCIM, Conespondence)
- 1. Analysis/PORVs PNSC Minutes 78-62, Safety AnalysislPORVs
- 2. PC/M 87-011, Control Group KW Meter
- 3. PC/M PCIM 90-528, Pressurizer Pressure Transmitter Replacement
- 4. PC/M 92-03 1, PT-3-1606X - 1608X Installation 92-031, -
- 5. PTN-OPS-88-084, R. Mende to V. Wager, 4/13/88, Procedure Concerns
- 6. CR 96-754, Appendix R (Postulated) Fire in Containment (Fire Zones 59 and
- 60) could result in spurious actuation of CV-3/4-3 CV-3/4-311 11 W97:TNM/dtlsw/bc W97:TNM/dt/sw/bc
Procedure No. ProcedureTitle:
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Procedure No.: Procedure Page: Page: 66 Approval ApprovalDate: Date: 3-ONOP-041.5 3-0NOP-041.S PressurizerPressure Pressurizer PressureControl ControlMalfunction Malfunction 10/7/01 10/7/01 3.2 Records 3.2 RecordsRequired Required 3.2.1 3.2.1 None None 3.3 Commitment 3.3 CommitmentDocuments Documents 3.3.1 CTRAC 88-706, 88-706, ERT ERT 87-005; 87-005; 12/25/87, Action 3,3, Loss Loss of 3.3.1 CTRAC 12/25/87, Corrective Corrective Action of RCS RCS Pressure Control, IncorporateMonitoring Pressure Control, Incorporate Monitoring RCS RCS Leakage Leakage W97:TNM/d tlsw/bc W97:TNM/dt/sw/bc
Procedure No.: Procedure No.: Procedure
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Procedure
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Page: 7 Approval Date: 3-ONOP-041.5 3-0NOP-041.S Pressurizer Pressure Pressurizer Pressure Control Control Malfunction Malfunction 10/7/01 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED NOTES NOTES I ** Steps 1I through Steps through 33 are are IMMEDIA IMMEDIATE ACTION steps. TE ACTION steps. III *
- Foldout page is required to be monitored throughout this procedure.
------------------------- I CAUTION CA UTION The Master Controller should be operated carefully (Normal controller output for 2235 psig is 42.5 percent demand; 92 percent demand will open PCV-3-455C). If the following conditions are met, an excessive increase in controller output could cause Power Operated Relief Valve Valve PCV-3-455C to open:
- 1. PCV-3-455C hand switch in AUTO.
- 2. Pressurizer pressure is greater than or equal to 2000 psig, p51g. or OMS switch in LO Press Ops.
1I Check PZR Pressure Control Instrument Loop Not Failed
- a. Check PT-3-444 - NOT FAILED by
- a. Perform the following:
comparison with adjacent pressure channels and known plant parameters (1) Verify PCV-3-455C OR MOV-3-536 CLOSED. (2) Take manual control of PC-3-444J, PZR PRESS CONTROL. (3) IF manual control of PC-3-444J is NOT effective, THEN perform the NOT following:
- Take manual control of PZR control of spray valves.
Take manual control of of PZR heaters. heaters.
- b. Check PT-3-445 - NOT
- b. - NOT FAILED byby b.
- b. following:
Perform the following: comparison comparison with adjacent adjacent pressure pressure (1) Verify (1) Verify PCV-3-456 PCV-3-456 Q, OR MOV-3-535 MOV-3-535 channels channels and known plant parameters and known CLOSED. CLOSED. W97:TNM/dtlsw/bc W97:TNM/dUsw/bc
Procedure No.: Procedure
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Page: 8 Approval Date: 3-0NOP-041.5 Pressurizer Pressure Control Malfunction 10/7/01 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED 2 Check PORVs Check Closed PORVs Closed Perform the Perform the following: following:
** PCV-3-455C - CLOSED PCV-3-455C - CLOSED ** IF PZR IF PZR pressure pressure is is less less than than 2335, 2335, THEN THEN manually manually close close PORVs.
PORVs. IF IF any any
** PCV-3-456 - CLOSED PCV-3-456 - CLOSED PZR PORV PZR PORV can NOT be can NOT be closed, closed, THEN THEN manually close its manually its block block valve.
CAUTION CA Ur/ON A fire in containment or the 38 3B 4KV Switchgear Room may cause spurious actuation of and give false valve position indication for Auxiliary Spray Valve, CV-3-311. 3 Check PZR Spray Valves Closed IF PZR pressure less than normal, THEN perform the following:
- PZR pressure normal
- a. Verify PZR Spray valves closed.
- Place PZR Spray Loop C, PCV-3-455A in MANUAL and CLOSE.
- Place PZR Spray Loop B, PCV-3-455B in MANUAL and CLOSE.
- Verify Aux Spray Valve CV-3-31CV-3-3111 CLOSED.
4 Check PZR Safety Valves Closed
- a. PZR PORV/Safety acoustic monitor LEOs - NOT LEDs - NOT LIT
- b. PZR safety line temperatures at or near normal
- PZR safety line line temperature, temperature, Tl-3-465 TI-3-465
- PZR safety line temperature, safety line Tl-3-467 TI-3-467
- PZR safety line PZR safety line temperature, temperature, Tl-3-469 TI-3-469 55 Check PZR Pressure Check PZR Pressure Stable Or Increasing Stable Or Increasing Perform Perform the the following:
following:
** efforts to Continue efforts to restore restore PZR PZR pressure control.
pressure control. W97:TNMldtIswJbc W97:TNM/dtlsw/bc
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Procedure Page: 9 Approval Date: 3-ONOP-041.5 3-0NOP-041.S Pressurizer Pressure Control Malfunction 10/7/01 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED I I RESPONSE NOT OBTAINED I 6 Check Pressurizer Pressure Above Normal Go to Step 10. Value 7 Restore Pressurizer Pressure Using Manual Pressure Control
* ----------------------- NOTES I *. If Pressurizer Pressure Malfunction is a result of a failure of the 3-459CX or 3-460CX 3-46 OCX I I relays (as indicated by a loss of Letdown flow with a loss of Pressurizer Heaters with I no concurrent failure of Level Transmitters 3-459A, 3-460, 3-461), use 3-0NOP-003.6, 3-ONOP-003.6, I 3-ONOP-003.9, Attachment 4 for 3-459CX Attachment 4 for 3-460CX failure, OR 3-0NOP-003.9, I failure as guidance for establishing Letdown flow and Pressurizer Heaters. I I *. If the buttons on relays 3-459CX or 3-460CX are used to restore Letdown flow and I I Pressurizer Heaters, comply with Tech Spec Action Statement 3.4.3 Action b. I I *. If the manual control of Heaters from the Electrical penetration room is used, comply I II L _
with_ _Spec Tech __ __ Action _ _3.4.3 Statement __ Action __ a. _ _ _ _ _ _ _ _ _ ~ I L_ 8 Check If Automatic Pressure Control Can Be Established
- a. PZR pressure controls - OPERABLE
- a. Perform the following:
(1) Notify the Instrument and Controls Department. (2) Continue efforts to restore Automatic pressure control. (3) Return to Step 7.
- b. RCS Pressure - STABLE
- b. Continue efforts to restore RCS pressure fQ AND return to Step 7.
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Page: Page: 10 10 Approval Approval Date: Date: 3-ONOP-041.5 3-0NOP-041.5 Pressurizer Pressure Pressurizer Pressure Control Control Malfunction Malfunction 10/7/01 10/7/01 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED I 9 Establish Automatic Establish Automatic Pressurizer Pressurizer Pressure Pressure Control Control
- a. Place Pressurizer
- a. Place Pressurizer Pressure Pressure Controls Controls in in AUTOMATIC using AUTOMATIC 3-OP-041 .2, using 3-0P-041.2, PRESSURIZER OPERATION PRESSURIZER OPERATION
- b. PZR pressure
- b. Verify PZR pressure controls controls operating in in -- b.
- b. Perform Perform the following:
following: AUTOMATIC MODE AUTOMATIC (1) Re-establish (1) Re-establish manual manual pressure pressure control. control. (2) Re-establish normal pressurizer pressure. (3) Notify the Instrument Instrument and Controls Department. (4) Return to Step 7.
- c. Go to appropriate Plant Procedure as determined by the Nuclear Plant Supervisor Go to Step 20.
GotoStep20. Io 10 . Check Pressurizer Pressure Low Or Decreasing Maintain PZR Pressure Greater Than 2000 a. Restore pressure to greater than 2000 11 PSIG psig.
- Check PZR pressure greater than 2000 b. IF pressure can NOT be maintained psig greater than 2000 psig, THEN perform the following:
- Maintain PZR pressure greater than 2000 ** Continue efforts to restore pressure psig and
- Trip the Reactor and turbine and go to 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1. 1.
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Procedure
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Page: Page: 11 Approval Approval Date: Date: 3-ONOP-041.5 3-0NOP-041.S Pressure Control Pressurizer Pressure Pressurizer Control Malfunction Malfunction 10/7/01 10/7/01 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT OBTAINED NOT OBTAINED I 12 12 Check PZR Check Heaters Operable PZR Heaters Operable Perform the Perform the following: following:
- a. Check PZR
- a. Check PZR Heaters Heaters ON ON a.
- a. Perform Perform the the following:
following: PZR Control Verify PZR Control Group Group Heater Heater Distribution Distribution Panel Panel B-11 B-i i Breakers, Breakers, Electrical Penetration West Electrical Penetration Room, Room, CLOSED. CLOSED.
** PZR Backup Verify PZR Backup Group Group A Heater Heater Distribution Distribution Panel Panel B-12 B-i2 Breakers, Breakers, West Electrical Penetration Room, CLOSED.
** Verify PZR Backup Group B Heater Distribution Panel B-13 Breakers, West Electrical Penetration Room, CLOSED.
- b. Check PZR Htrs capable of maintaining b. Dispatch an operator to perform pressure Attachment 1, Pressurizer Heater Output Worksheet, to determine heater output.
- c. Notify the Electrical Department.
13 13 Check If A PORV Is Leaking Go to Step 15.
- Tl-3-463 -
PZR relief line temperature, TI-3-463 - INCREASING or at the saturation temperature associated with the PZR relief tank pressure according to Attachment 2
- PZR relief tank level, LI-3-470 Ll-3-470 --
INCREASING
- PZR relief tank temperature, TI-3-47i TI-3-471 - -
INCREASING OR above ambient temperature for containment conditions
- PZR relief tank pressure P1-3-472 PI-3-472 -
INCREASING
- PZR PORV/Safety PORV/Safety Acoustic Monitor Monitor - LEDs LIT LIT W97:TNM/dtlsw/bc W97:TNM/dtlsw/bc
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Page: 12 Approval Date: 3-0NOP-041.S Pressurizer Pressure Control Malfunction 10/7/01 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED II 14 Isolate The Isolate The Leaking Leaking PORVPORV Perform the Perform the following: following:
- a. Isolate the
- a. Isolate the leaking leaking PORV PORV a.
- a. IF the IF block valve the block valve can can NOTNOT bebe closed, closed, THEN THEN perform perform the the following:
following:
- Close either MOV-3-535 Close MOV-3-535 OR ** IF IF MOV MDV block block indicating indicating lights lights are are Close MOV-3-536 LIT AND LIT AND thethe MOV MDV willwill NOT NOT operate
- Close from from thethe console, console, THEN THEN notify notify the the Electrical Department.
Electrical Department. MDV block valve indicating lights IF MOV are NOT lit, with the NPS permission, reclose the breaker and operate the MOV from the switch on the console.
- b. Check the following to see if the leaking b. IF the leaking PORV has NOT been PORV has been isolated: isolated, reopen the applicable PORV BLOCK valve, THEN repeat Step 14a
** PZR relief line temperature and Step 14b for the opposite PORV.
DECREASING
- PZR relief tank level - STABLE
- PZR relief tank temperature - STABLE or DECREASING
- PZR relief tank pressure - STABLE
- PZR PORV/Safety Acoustic Monitor LEDs - NOT LIT LEOs -
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Procedure
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Page: Page: 13 13 Approval Approval Date: Date: 3-ONOP-041.5 3-0NOP-041.S Pressurizer Pressure Pressurizer Pressure Control Control Malfunction Malfunction 10/7/01 10/7/01 I STEP STEP I ILACTIONIEXPECTED RESPONSE I I RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED I 15 15 Determine IfIf A Determine A Leaking Leaking PZR PZR Safety Safety Is Is Pressure To Causing Pressure Causing To Decrease Decrease
- a. Check ifif aa PZR
- a. Check PZR Safety Safety isis leaking leaking a.
- a. Go to Go to Step Step 16.
16.
- PZR safety line PZR line temperature, temperature, TI-3-465 - -
INCREASING or INCREASING or at at saturation saturation associated with the PZR temperature associated PZR relief pressure per relief tank pressure per Attachment 2
- PZR safety line temperature, TI-3-467 Tl-3-467 - -
INCREASING or at saturation temperature associated with the PZR relief tank pressure per Attachment 2
- PZR safety line temperature, TI-3-469 - -
INCREASING or at saturation temperature associated with the PZR relief tank pressure per Attachment 2
- PZR relief tank level, LI-3-470 - -
INCREASING
- PZR relief tank temperature, TI-3-471 Tl-3-471 - -
INCREASING
- PZR relief tank pressure, PI-3-472 P1-3-472 -
INCREASING
- PZR PORV/Safety Acoustic Monitor- Monitor -
LEDs LIT LEOs
- b. Refer to Technical Specifications for a leaking PZR SAFETY 16 16 Determine If RCS Leakage Is Causing Pressure To Decrease
** Monitor Monitor RCS Leakage using 3-OSP-041 3-0SP-041.1,.1, RCS LEAK RATE CALCULATION 117 7 Check Pressurizer Pressure Decreasing Go Go to Step 20.
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Page: 14 Approval Date: 3-0NOP-041.S Pressurizer Pressure Control Malfunction 10/7/01 I STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I I II 18 Determine If PZR Spray Valve Leakage Or Go to Step 20. Failure To Close Is Preventing RCS Pressure Stabilization 19 Reduce PZR Spray Flow As Follows
- a. Verify PZR Spray valves closed
- Place PZR Spray Loop C, PCV-3-455A in MANUAL and CLOSE
- Place PZR Spray Loop B, PCV-3-455B in MANUAL and CLOSE
- CV-3-31 1 Verify Aux Spray Valve, CV-3-311 CLOSED
- b. Check Reactor Shutdown b. WHEN the Reactor is shutdown, THEN continue with Step 19c.
- c. Stop RCPs to reduce PZR Spray flow as follows:
- Stop either the 3B or the 3C RCP using 3-OP-041.1, REACTOR COOLANT 3-0P-041.1, PUMP
- d. Check pressure stable or increasing d. IF pressure continues to decrease, THEN repeat Step 19c and 19d for the other RCP.
20 Check RCS Pressure Stable Return to Step 5. 21 Check If Automatic Pressure Control Can Be Perform the following: Established
- Pressurizer Pressure Control Channel 1. Notify the Instrument and Controls Operable Department.
- 2. Continue efforts to establish Automatic Pressure Control.
- 3. Return to Step 20.
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Page: 15 Approval Date: 3-0NOP-041.5 Pressurizer Pressure Control Malfunction 10/7/01 I STEP STEP I I ACTION/EXPECTED RESPONSE I I RESPONSE II ACTIONIEXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED 22 Establish Automatic Establish Controls Automatic Pressurizer Pressurizer Pressure Pressure Perform the Perform following: the following: Controls
- a. Place Pressurizer
- a. Place Pressure Controls Pressurizer Pressure Controls in in ** Re-establish manual Re-establish manual pressure pressure AUTOMATIC using AUTOMATIC 3-OP-041 .2, using 3-0P-041.2, control.
control. PRESSURIZER OPERATION PRESSURIZER OPERATION PZR pressure
- b. Verify PZR controls operating in pressure controls in
- Re-establish normal Re-establish normal PZR PZR pressure.
pressure. automatic mode automatic mode
** Notify I&C Notify l&C Department.
Department.
** ReturntoStep2O.
Return to Step 20. 23 Check PORV NOT Leaking 14. Go to Step 14.
- PZR Relief Line PZR Line Temp - STABLE or DECREASING
- PZR Relief Tank Level - STABLE PZR Relief Tank Temperature - STABLE or DECREASING
- PZR Relief Tank Pressure - STABLE
- PZR PORV/Safety Acoustic Monitor LEDs - -
NOT LIT. 24 Request Nuclear Plant Supervisor Review Plant Technical Specifications For Failed Equipment 25 Go To Appropriate Procedure As Determined By The Nuclear Plant Supervisor END OF TEXT W97:TNM/dtlsw/bc W97:TNM/dtlsw/bc
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Page: 16 Approval Date: 3-0NOP-041.S Pressurizer Pressure Control Malfunction 10/7/01 ATTACHMENT 11 ATTACHMENT (Page 11 of (Page of 1) 1) PRESSURIZER HEATER PRESSURIZER HEATER OUTPUT OUTPUT WORKSHEET WORKSHEET Pressurizer Heater Pressurizer Control Group Heater Control Group Power Power ____ kw at 3C kw at 3C Load Load Center Center 3A 480 Volt Load Center Voltage Calculation Backup Heater Group 3A Amperage Calculation (Ref. Step 5.4.4) (Ref. AB _ _ _~Volts A._ _ _ _ Amps BC Volts B
B Amps CA Volts C
C Amps Total _ _ Volts +÷ 3 = Avg __ Volts Total _ _ Amps +÷ 3 =
= Avg __ Amps Average _ _ Volts x Average _ _ Amps x 0.00173 = kw*
3D 480 Volt Load Center Voltage Calculation Backup Heater Group 3B Amperage Calculation (Ref. Step 5.4.4) AB Volts A ctA_ _ _ _ Amps BC ---~Volts B
B Amps CA Volts C C Amps Total __ Volts +÷ 33 = = Avg __ Volts Total __ Amps +÷ 33 =
= Avg __ Amps Average _ _ Volts x Average _ _ Amps x 0.00173 0.00 173 = kw*
TOTAL POWER KW
- Pressurizer Backup Heater Groups 3A 3A and 3B 3B SHALL have greater than 125KW125KW capacity capacity each (refer to Technical Technical Specifications 3/4.4.3).
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Procedure
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Page: Page: 17 17 Approval Approval Date: Date: 3-ONOP-041.5 3-0NOP-041.S Pressurizer Pressure Pressurizer Pressure Control Control Malfunction Malfunction 10/7/01 10/7/01 ATTACHMENT 22 ATTACHMENT (Page 11 of (Page of 1) 1) PRESSURIZER PORV PRESSURIZER PORV DOWNSTREAM DOWNSTREAM TEMP TEMP VERSUS VERSUS PRT PRT PRESSURE PRESSURE P1-3-472 PI-3-472 TI-3-463 INDICATED PRESSURE APPROXIMATE (PSIG) (PSIG) TEMPERATURE TEMPERATURE (OF)(°F) 0 212 5 230 10 10 240 15 250 20 260 25 270 30 275 35 280 40 285 45 290 50 295 FINAL PAGE W97:TNM/dt/sw/bc W97:TNM/dt/sw/bc
Procedure No.: Procedure No.:
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Procedure
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Page: Page: Foldout Approval Date: Approval .... 3-ONOP-041.5 3-0NOP-041.5 Pressurizer Pressure Control Malfunction 10/7/01 10/7/01 FOLDOUT FOR PROCEDURE 3-0NOP-041.5 3-ONOP-041.5
- 1. FAILED INSTRUMENT ISOLATION
- a. IF any Pressurizer Pressure control Instrument Loop fails, THEN place applicable control switches to a position that isolates the failed instrument.
- 2. IFffl PZR pressure cannot be maintained greater than 2000 psig, THEN perform the following:
- a. Continue efforts to restore PZR pressure and
- b. Trip the reactor and turbine and go to 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION.
- 3. PORV ISOLATION/LEAKING PORV IDENTIFICATION
- a. if any PORV is OPEN OR Leaking AND pressure is less than 2235 psig, THEN CLOSE the applicable IF PORV and/or Block valve.
- b. The following are indications of leakage from a PZR PORV and should be used to identify and isolate a leaking PORV:
- 1) PZR relief line temperature, TI-3-463, INCREASING.
- 2) PZR relief tank level, LI-3-470, INCREASING.
- 3) PZR relief tank temperature, TI-3-471, INCREASING.
- 4) P1-3-472, INCREASING.
PZR relief tank pressure, PI-3-472,
- 5) PZR PORV/SAFETY ACOUSTIC MONITOR, LEDs LIT.
- 4. OPEN/LEAKING PZR SAFETY VALVE IDENTIFICATION
- a. The following are indications that a PZR safety is open or leaking:
- 1) PZR Safety line temperature, TI-3-465, INCREASING or at saturation temperature associated with the PZR relief tank pressure per Attachment 2.
- 2) PZR Safety line temperature, TI-3-467, INCREASING or at saturation temperature associated with the PZR relief tank pressure per Attachment 2.
- 3) PZR Safety line temperature, TI-3-469, INCREASING or at saturation temperature associated with the PZR relief tank pressure per Attachment 2.
- 4) Ll-3-470, INCREASING.
PZR relief tank level, LI-3-470,
- 5) PZR relief tank temperature, TI-3-471, INCREASING.
- 6) PZR relief tank pressure, P1-3-472, PI-3-472, INCREASING.
- 7) PZR PORV/Safety Acoustic Monitor,Monitor, LEDs LIT.
- 5. SPURIOUS ACTUATION OF OF CV-3-311 AUXILIARY SPRAY VALVE due to fire in Containment or 3B 4KV Switchgear Room
- a. IF pressurizer pressure is decreasing and Auxiliary Spray Valve, CV-3-311, is suspect, THEN reduce charging to one charging pump pump on slow speed AND close charging to RCS Control Valve HCV-3-121.
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..i. nvcncory
/
Appendix C Job Performance Measure ES-C-I Form ES-C-1 Worksheet Worksheet Facility: Facility: Turkey Point Turkei: No: Task No: Respond to Loss Respond RHR Loss of RHR Performance Job Performance Task
Title:
Inventory Inventory Measure No: Measure Systems - bb Si:stems K/A
Reference:
KIA 002 A2.01 {4.3/4.41 (4.3/4.4) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulator Simulated Performance Actual Performance Yes Classroom Simulator ---------"--=-=------- Yes Plant -------------- Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Unit 3 is in Mode 5 (RCS temperature == 180°F and RCS pressure == 340 psig before event initiation)
- 2. RHR was in service before event initiation
- 3. Increased RCS makeup required
- 4. Annunciators G-9/5 & 1-4/6 for containment sump high level are alarming 3-ONOP-041 .8, step 16 is in progress
- 5. Performance of 3-0NOP-041.8,
- 6. The Primary Operator (SNPO) discovered the source of the leakage while evacuating containment.
Leak location is on the RHR system just downstream of MOV-3-744A. Task Standards: RHRJRCS inventory terminated.
- 1. Loss of RHRlRCS
- 2. Core cooling is maintained/restored.
Required Materials: 3-ONOP-041.8
- 1. 3-0NOP-041.8 General
References:
- 1. 3-ONOP-041.8 3-0NOP-041.8 Initiating Cue:
The Unit Supervisor directs you to perform Attachment 1 3-ONOP-041 .8 to restore RHR cooling. 1 of 3-0NOP-041.8 Time Critical Task: Yes/No Validation Time: 15 minutes 15
Appendix C Appendix C Page 22 of Page of 88 Form ES-C-1 Form ES-C-I INSTRUCTIONS TO TO OPERA OPERATOR TOR READ TO READ TO OPERA OPERATOR: TOR: WHEN II TELL WHEN TELL YOU YOU TO TO BEGIN, BEGIN, YOU ARE ARE TO TO PERFORM PERFORM THE THE ACTIONS ACTIONS AS DIRECTED DIRECTED IN IN THE THE INITIATING INITIATING CUES. II WILL CUES. WILL DESCRIBE DESCRIBE THE THE GENERAL GENERAL CONDITIONS CONDITIONS UNDER UNDER WHICH WHICH THIS THIS TASK TASK ISIS TO TO BE BE PERFORMED PERFORMED AND PROVIDE AND PROVIDE THE THE NECESSARY NECESSARY TOOLS TOOLS WITH WITH WHICHWHICH TOTO PERFORM PERFORM THIS THIS TASK. TASK. BEFORE BEFORE STARTING, STARTING, II EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE WILL EXPLAIN INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR INITIATING FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS:
- 1. Unit 3 is in Mode 5 (RCS temperature::::
temperature 180°F and RCS pressure:::: pressure 340 psig before event initiation)
- 2. RHR was in service before event initiation
- 3. Increased RCS makeup required 1-416 for containment sump high level are alarming G-915 & 1-4/6
- 4. Annunciators G-9/5 3-ONOP-041 .8, step 16 is in progress
- 5. Performance of 3-0NOP-041.8,
- 6. The Primary Operator (SNPO) discovered the source of the leakage while evacuating containment.
Leak location is on the RHR system just downstream of MOV-3-744A. INITIATING !NITIA TlNG CUE: The Unit Supervisor directs you to perform Attachment 11 of 3-0NOP-041.8 3-ONOP-041 .8 to restore RHR cooling. TERMINATION TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. NOTES TO EVALUATOR AND IIF I/F OPERA OPERATOR:TOR: 10-28 or IC-138.
- 1. Reset simulator to IC-28 10-138. If IC-138 IC-i 38 used, skip ahead to step 7.
- 2. Unit 3 is in Mode 5 (RCS temperature pressure 340 psig before event initiation).
temperature:::: 180°F and RCS pressure::::
- 3. Initiate LOCA as follows: Click on Schema > ~ REACTOR COOLANT SYSTEM > ~ MAIN RCS HYDRAULICS ~ RCS HYD * > ~ TVHHCLA - COLD LEG LOOP A LEAKAGE >
- ~ enter selected value ==0.002 then INSERT.
- 4. Restore power to MOV-3-869, MOV-3-866AMOV-3-866A & MOV-3-866B as follows: Click on Schema * ~ SAFETY SYSTEM * ~ SAFETY INJECTION PROC ÷ ~ MOV-869 ~ TCM2DO7M TCM2D07M - MOV 869 30737 BKR MECH CONT CLOSE * ~ TRUE then INSERT > ~ MOV-866A * ~ TCM2DO5M TCM2D05M - MOV 866A 30732 BKR MECH CONT CO NT CLOSE ~ TRUE then INSERT > ~ MOV-866B ~ TCM2DO6M TCM2D06M - MOV 866B 30621 BKR MECH CONT CO NT CLOSE * ~ TRUE then INSERT INSERT
- 5. Place simulator in run and perform 3-ONOP-041 3-0NOP-041.3 .3 & 3-ONOP-041 3-0NOP-041.8 .8 until step 16 16 is reached and PZR cold cal level :::: 10%.
10%.
- 6. Freeze simulator and store
- 6. store temporary temporary IC IC ifif needed needed for repeat runs of this JPM.
JPM. 7.
- 7. Open & execute lesson lesson file NRC SRO NRC SRO XXIII JPM b.
JPM b.
- 8. Hang valve placards
- 8. Hang placards onon vertical panel control switches as appropriate appropriate for mode mode 55 cold shutdown shutdown conditions.
I Appendix Appendix C C Page 33 of Page of 88 Form ES-C-1 Form ES-C-I I Denote critical Denote critical steps steps with with a check check mark mark Start Time Start Time Obtained copy of 3-0NOP-041.8 3-ONOP-041 .8 Attachment Attachment 11 STEP STEP 11 : SAT
- - SAT
-- U NSAT UNSAT STANDARD: Obtained copy of 3-0NOP-041.8 3-ONOP-041 .8 Attachment 11
. Checked RHR System components between RCS (MOV-3-750 /
STEP 2 MOV-3-751 and 3-752A /I 3-752B) and 3A13B RHR pump Inlet - - SAT Isolation Valves - Not Leaking UNSAT STANDARD: Determined leak not between RCS and 3A13B RHR pump Inlet Isolation Valves STEP
. Checked RHR System components bounded by 3-752A, 3-759A & 3- 3 3
757D - Not Leaking - - SAT
- - UNSAT STANDARD: Determined leak not between 3-752A, 3-759A & 3-757D Checked RHR System components bounded by 3-752B, 3-759B 3759B & 3-STEP 4 --
SAT 757C - Not Leaking
- - UNSAT STANDARD: Determined leak not between 3-752B, 3-759B & 3-757C Checked RHR System components between RCS and RHR Dischg to STEP 5 SAT Cold Leg Isol Valves - Not Leaking
- - UNSAT STANDARDS: 1.
- 1. Determined leak between MOV-3-744A MOV-3-744A and RCS J..j 2.
- 2. Stopped the running RHR pump J..j 3. Closed MOV-3-744A && MOV-3-744B When MOV-3-744A MOV-3-744A & B B closed, remove leak on RCS cold leg leak on leg as hF IIF follows: Click on on Schema * ~ REACTOR COOLANT SYSTEM * ~
OPERATOR MAIN MAIN RCS HYDRAULICS HYDRAULICS * ~ RCS HYD
- TVHHCLA-HYD ~ TVHHCLA - COLD
- COLD CUE: LEG LOOP A LEAKAGE * ~ enter selected value = =0.0 0.0 then INSERT or Trigger lesson step ISOLATE Q!: ISOLATE RCS LEAK.LEAK.
Appendix C of 8 Page 4 of Form ES-C-1 ES-C-I locally STEP 6 : Directed Primary Operator (SNPO) to locally close 3-887 -- SAT
- - UNSAT STANDARD:
.yq Directed Primary Operator (SNPO) to locally close 3-887 lIE Respond as SNPO when directed to locally close valve 3-887. Click on IIF OPERATOR Schema ~ + SAFETY SYSTEM ~ > RHR PROCESS ~ -* 887 ~
TAMR1V39 - VALVE PORT AREA ~ enter selected value == 0.0 then CUE: - INSERT or Trigger lesson step CLOSE 3-887. Report when complete. Directed Primary Operator (SNPO) to locally check both RHR pump STEP 7 discharge pressures < < 210 psig - - SAT
- - UNSAT STANDARD: Directed Primary Operator (SNPO) to locally check both RHR pump discharge pressures < < 210 psig Respond as Primary Operator when directed to check RHR pump 1fF IIF discharge pressure. RHR pump discharge pressure may be read OPERATOR directly from RHR Process system mimic as follows: Click on Schema CUE: ~ SAFETY SYSTEM >
* ~ RHR PROCESS * ~ P-600 & P-601 (upper left corner). Report indicated value.
pressure > 210 psig: If RHR pump discharge pressure> STEP 8 : -- SAT
- 1. Verified MOV-3-862A & MOV-3-862B closed UNSAT
- 2. Directed Primary Operator (SNPO) to locally open MOV-3-863A and MOV-3-863B STANDARDS: If RHR pump discharge pressure pressure>> 210 psig:
- 1. Determined MOV-3-862A & MOV-3-862B closed
.yq 2. Directed Primary Operator (SNPO) to locally open MOV-3-863A and MOV-3-863B Respond as Primary Operator if directed to open MOV-3-863A and MOV-3-863B. To open MOVs, click on Schema ~ SAFETY SYSTEM I/F IIF OPERATOR ~ RHR PROCESS
> ~ MOV-863A -* ~ TFMUV1110 TFMUV1 0 - MOV 863A FAIL CUE CUE: OPEN > ~ TRUE then INSERT - ~ MOV-863B
- TFMUV120 - MOV
~ TFMUV12O -
863B FAIL OPEN ~ TRUE then INSERT or Trigger lesson step OPEN MOV-3-863AB. Report when complete.
I Appendix C Page 5 of 8 ES-C-I I Form ES-C-1 If RHR pump discharge pressure < 210 psig: STEP 9 : - - SAT
- 1. Directed Primary Operator (SNPO) close breaker 30726 for MOV-MDV-3-863A & Secondary Operator (NPO) close breaker 30626 for - - UNSAT MOV-3-863B closed
- 2. Opened MOV-3-863A or MOV-3-863B STANDARDS: If RHR pump discharge pressure < 210 psig:
q~ 1. Directed Primary Operator (SNPO) close breaker 30726 for MOV-MDV 3-863A & Secondary Operator (NPO) close breaker 30626 for MOV-3-863B closed J~ 2. Opened MOV-3-863A or MOV-3-863B Respond as Primary Operator if directed to close breaker 30726 for MOV-3-863A and Secondary Operator if directed to close breaker 30626 for MOV-3-863B. To close MOVMDV breakers, click on Schema ~ lIE IfF OPERATOR SAFETY SYSTEM ~
- RHR PROCESS ~ > MOV-863A ~ TCM1 D11Dli M M- -
CUE CUE: MOV 863A 30726 BKR MECH CONT CLOSE ~ TRUE then INSERT
. ~
- MOV-863B ~ TCMID12M TCM1 MDV 863B 30626 BKR MECH CONT D12M - MOV CLOSE > ~ TRUE then INSERT .Q[ or Trigger lesson step CLOSE MOV 863AB BREAKERS. Report when complete.
Opened MOV-3-872 STEP 10 : -- SAT UNSAT STANDARD: J~ Opened MOV-3-872 FLOOR level > 50%, secure the running When either RHR restored or PZR level> OPERATOR HHSIP. CUE: (Ll-3-462) Checked RCS level greater than 10% PZR cold cal level (LI-3-462) STEP 11 : -- SAT
- - UNSAT STANDARD: (Ll-3-462)
Determined RCS level greater than 10% PZR cold cal level (LI-3-462)
Appendix C Appendix C Page 66 of Page of 88 Form ES-C-1 Form ES-C-I Started one RHR RHR pump pump STEP STEP 12 12 : Started one SAT SAT UNSAT
- - UNSAT STANDARD:
..j Started the RHR pump in the same train as the open MOV-3-863 I/F Respond as PO P0 when directed to determine running RHR pump Llp, i2p, IIF OPERATOR click on Schema ~ > SAFETY SYSTEM ~
- RHR PROCESS and report CUE: difference between suction & discharge pressures of running RHR pump to the crew (should be between 105 and 115 psid).
Maintained running RHR pump Llp ip 105-115 1 05-1 15 psid STEP 13 1.
- - SAT Directed Primary Operator (PO) (P0) to report running RHR pump Llp ip UNSAT
- 2. If running RHR pump Llp Lip outside 105-115 psid range, directed POP0 3-754A/B discharge valve as needed to locally throttle 3-754A1B STANDARDS: 1. Directed Primary Operator (PO) (P0) to report difference between PI P1 1595A/B 1595A1B and P1-3-601/600 PI-3-601/600 for the running RHR pump
- 2. Determined running RHR pump Llp Lip 105-115 105-1 15 psid and no adjustment of RHR pump discharge valves required Respond as PO P0 when directed to locally adjust MOV-3-749A(B) hF IfF position to control RCS temperature. Click on Schema > ~ COMMON OPERATOR SERVICES > ~ COMPONENT COOLING ~ *,CCW CCW TO SI PUMP CUE: CLRS AND RHR HEAT EXCH ~ 748A(B) * ~ TAKA748A(B) -- 748A(B)
RHR HX A(B) OUTLET * ~ enter selected value then INSERT. Controlled RCS cooldown rate locally by throttling CCW from STEP 14 14 SAT operating RHR heat exchanger -- UNSAT STANDARDS: 1.
- 1. Determined RCS cooldown rate
- 2. Directed Primary Operator (P0)(PO) to locally throttle MOV-3-749A(B) as necessary to control RCS cooldown rate NOTE:
NOTE: Since RCS temp already << 200°F, 200°F, cooldown cooldown rate following restoration of RHR should should be minimal minimal Terminating Terminating RHR flow restored and action taken to stabilize RCS temperaturetemperature STOP Cue: Stop Stop Time ----
I Appendix C Page 7 of 8 ES-C-I I Form ES-C-1 Verification of Completion Job Performance Measure No. _S~ys:...:tc.::..ec..:.mc...:s_---=-b Systems b _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Examinee's Examinees Name: Examiners Name: Examiner's Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Examiners signature and date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
JPM BRIEFING JPM BRIEFING SHEET SHEET N INITIAL CONDITIONS: CONDITIONS: INITIAL
- 1. Unit
- 1. Unit 33 isis inin Mode Mode 55 (ReS (RCS temperature temperature == 180°F 180°F and and ReS RCS pressure pressure == 340 340 psig psig before before event event initiation) initiation)
- 2. RHR was
- 2. RHR was in in service service before before event event initiation initiation
- 3. Increased ReS
- 3. Increased RCS makeup makeup required required
- 4. Annunciators
- 4. Annunciators G-9/5 1-4/6 for G-915 && 1-4/6 for containment containment sump high level sump high level are are alarming alarming
- 5. Performance
- 5. Performance of of 3-0NOP-041.8, 3-ONOP-041 .8, stepstep 1616 isis in progress in progress
- 6. The
- 6. The Primary Primary OperatorOperator (SNPO)
(SNPO) discovered discovered the the source source of of the leakage while the leakage while evacuating evacuating containment. containment. Leak location Leak location is is on on the the RHR RHR system system just downstream downstream of MOV-3-744A. of MOV-3-744A. INITIATING INITIA TlNG CUE: CUE: The Unit The Unit Supervisor Supervisor directs directs you you to perform perform Attachment 11 of of 3-0NOP-041.8 3-ONOP-041 .8 to restore restore RHR RHR cooling. cooling. HAND THIS PAPER BACK TO YOUR EVALUATOR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY SATISFACTORILY COMPLETED COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 Shutdown LOCA [Mode (Mode 5 or 6] 61 Safety Related Procedure Responsible Department: Operations Revision Approval Date: 3/29/04 RTSs 93-1422p.,. 94-1 102P, 95-0904P, 96-0984P, 96-1409P, 93-14221P.. 94-0349P, 94-1102P, OO-0485P, 02-0016P, 04-0185P 00-0485P, W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 22 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA [Mode jMode 55 or or 6] 6j 3/29/04 3/29/04 LIST OF EFFECTIVE PAGES Revision Revision Page Date Date 11 03129/04 03/29/04 2 03129/04 03/29/04 3 02122/02 02/22/02 4 02122/02 02/22/02 5 02/22/02 6 02/22/02 7 03129104 03/29/04 8 02122/02 02/22/02 9 02122/02 02/22/02 10 02/22/02 11 02/22/02 12 02122102 02/22/02 13 02/22/02 14 02/22/02 15 02/22/02 16 02122102 02/22/02 17 02/22/02 18 02/22/02 19 02/22/02 20 02/22/02 21 02/22/02 22 02122102 02/22/02 23 02/22/02 24 02/22/02 25 02/22/02 26 02/22/02 27 02/22102 02/22/02 28 02/22/02 29 02122/02 02/22/02 30 30 02122/02 02/22/02 31 31 02/22/02 32 32 02/22/02 33 33 02/22/02 34 34 02122102 02/22/02 35 35 02/22/02 02/22/02 W97:DH/bvclmra W97:DH/bvc/mr
Procedure No.: Procedure
Title:
Page: 3 Approval Date: 3-0NOP-041.S Shutdown LOCA [Mode 5 or 6] 2/22/02 1.0 1.0 PURPOSE 1.1 This procedure provides actions necessary for maintaining core cooling and protecting the reactor core in the event that RHR cooling is lost during Mode S5 OR 6 EXCEPT WHEN the Refueling Cavity is Flooded. 2.0 SYMPTOMS OR ENTRY CONDITIONS 2.1 Annunciators 2.1.1 H 6/2, RHR HX HIILO HI/LO FLOW 2.1.2 H6/4,RHRPPAJBTRIP H 6/4, RHR PP AlB TRIP 2.1.3 I 7/6, RHR SUMP PUMP ROOM A HI LEVEL 17/6, 2.1.4 I 8/6, RHR SUMP SUIvIP PUMP ROOM B HI LEVEL 2.1.5 2.1.S I 3/6, RHR SUMP HX ROOM HI LEVEL 2.1.6 I 7/3, RX VESSEL DRAINDOWN LO-LO-LEVEL 2.1.7 A 711, HJJLO LEVEL HI PRESS/TEMP 7/1, PRT HIILO 2.2 Indications 2.2.1 Neither RHR pump is operating when required for decay heat removal. 2.2.2 FI-3-605. Low flow indicated on FI-3-60S. 2.2.3 Air Binding of the RHR pumps as evidenced by the following:
*** Motor current oscillations
** Erratic flow oscillations
- Excessive pump noise
** Pump Cavitation 2.3 Procedures 2.3.1 3-ONOP-041 3-0NOP-041.3, .3, Excessive Reactor Coolant System Leakage 2.3.2 3-ONOP-050, Loss ofRHR 3-0NOP-OSO, of RHR W97DH/hvr./mrü W97:DH/bvc/mr
Procedure No.: Procedure
Title:
Page: 4 Approval Date: 3-0NOP-041.S Shutdown LOCA [Mode 5 or 6] 2/22/02
3.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT DOCUMENTS REFERENCESIRECORDS 3.1 References 3.1.1 Technical Specifications for Turkey Point Unit 3 and Unit 4 3.1.2 Turkey Point Unit 3 and Unit 4 Final Safety Analysis Report 3.1.3 Operating Diagrams
- 1. 5613-M-3050, RESIDUAL HEAT REMOVAL SYSTEM
- 2. 5613-M-3062, SAFETY INJECTION SYSTEM 3.1.4 Plant Procedures
- 1. 3-ONOP-033 .2, Refueling Cavity Seal Failure 3-0NOP-033.2,
- 2. 3-ONOP-041 .3, Excessive Reactor Coolant System Leakage 3-0NOP-041.3,
- 3. 3-ONOP-.050, Loss ofRHR 3-0NOP-050, of RHR
- 4. 3-OP-041.1, Reactor Coolant Pump 3-0P-041.1,
- 5. 3-OP-050, Residual Heat Removal System 3-0P-050, 3.1.5 Plant Change/Modifications
- 1. PC/NIl 89-333, Generic Letter 88-17, Loss of Decay Heat Removal PC/M Programmed Enhancement-RCS Redundant Level Monitors.
3.1.6 Miscellaneous Documents
- 1. JPN-PTN-SEMJ-89-094, Engineering Evaluation for the Adequacy of Core of GL-88-17, Loss of Decay Heat Removal)
Cooling (Support ofGL-88-17,
- 2. JPN-PTN-SENP-95-026, Safety Evaluation for CCW Flow Balance and Post-Accident Alignment Requirements to Support Thermal Up-Rate 3.2 Records Required 3.2.1 None W97DH/hvc/mra W97:DH/bvc/mr
Procedure No.: Procedure
Title:
Page: 5 Approval Approval Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA [Mode 5 or 6]61 2/22/02 3.3 Commitment Documents 3.3.1 NRC IBINWIN No. 86-101, Loss of Decay Heat Removal Due to Loss of Fluid Levels inRCS. in RCS. 3.3.2 INPO SER 17-86, Loss of Shutdown Cooling Flow CTRAC No.87-0823) 3.3.3 0E1744, RHR Gas Binding Due to Erroneous Half-Loop Indication INPO OE1744, (CTRAC No. 85-1178-34) 3.3.4 LER 250/95-006, Analysis Shows CCW Heat Exchangers Incapable of Handling Full Accident CCW Flow. W97:DH/bvc/mra W97:DH/bvc/mr
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 3-0NOP-041.8 Shutdown LOCA rMode 5 or 61 2/22/02 1J I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I CAUTIONS
** Changes in RCS pressure may result in inaccuracies in RCS level readings.
Changes
** 3-ONOP-033.2, REFUELING If the refueling Cavity is flooded, then go to 3-0NOP-033.2, CAWTY CA VITY SEAL FAILURE.
** from 3-0NOP-050, If entering this procedure from 3-ONOP-050, Loss Of RHR, then go to step 21. 21.
1I Check If RHR Pumps Should Be Stopped
- a. pumps-ANY RHR pumps - ANY RUNNING a. GotoSTEP2 Go to STEP 2
- b. RCS LEVEL - ADEQUATE FOR PLANT
- b. Perform the following:
CONDITIONS
- 1) Stop both RHR pumps and place
** Drain Down Level them in standby.
- 1) LI-3-6421 - GREATER THAN 23%
GotoSTEP2.
- 2) Go to STEP 2.
- 2) LI-3-6423 - GREATER THAN 23%
OR
** Pressurizer Level, LI-3-462 Ll-3-462 - GREATER THAN 10%
- c. Check RCS Level - STABLE OR
- c. Perform the following:
INCREASING
- 1) Maintain RCS inventory using the following methods while continuing with this procedure:
a) Charging flow (Step 13). b) RWST Gravity Feed (Step 14). c) VCT Overpressure Feed (Step 15).
- d. RHR flow - LESS THAN 3000 GPM
- d. Reduce RHR flow to 3000 gpm
- e. RHR pumps - CAVITATING
- e. Perform the following:
- 1) IF level stable or increasing, THEN go to appropriate plant procedure as determined by the Nuclear Plant Supervisor.
- 2) IF level decreasing, THEN go to Step if.
1f.
- f. Stop both RHR pumps and place them in standby.
W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Page: 7 Approval Date: 3-0NOP-041.S Shutdown LOCA fMode 5 or 61 3/29/04 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 2 Isolate Letdown Isolate Letdown And And Known Drain Paths Known Drain Paths
- a. Excess letdown
- a. Excess letdown isolation isolation valves - CLOSED CLOSED
- 1) HCV-3-137, Excess
- 1) HCV-3-137, Excess Letdown Letdown Flow Flow 1)
- 1) Close Close HCV-3-137 HCV-3-137 Controller
- 2) CV-3-387,
- 2) CV-3-387, Excess Letdown Isolation 2)
- 2) WHEN HCV-3-137 has has been been Valve From Cold Leg From Cold Excess Leg To Excess closed for 12 closed hours, THEN close 12 hours, close Letdown Heat Letdown Heat Exchanger Exchanger CV-3-387.
CV-3-387.
- b. Normal Letdown isolation valves - CLOSED- b. Manually close valves.
- CV-3-200A, LLTDN TDN Orifice Stop Valve -
45 gpm
- CV-3-200B, LLTDN TDN Orifice Stop Valve -
60 gpm
- CV-3-200C, LLTDN TDN Orifice Stop Valve -
60 gpm
- LCV-3-460, High Pressure Letdown Isolation From Loop B Cold Leg
- c. RHR letdown Isolation Valves - CLOSED
- c. Manually close valve.
- HCV-3-142, RHR LTDN to CVCS 3 Check RCS Operating In A Drain Down OR Reduced Inventory Configuration Prior To Go to step 55 The Event W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0NOP-041.8 Shutdown LOCA [Mode 5 or 6] 2/22/02 I ACTION/EXPECTED ACTION/EXPECTED RESPONSE RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 4 Determine The Determine Time To The Time Saturation Based To Saturation Based OnOn Existing Conditions Existing Conditions
- a. Determine Time
- a. Determine Time to to Saturation Saturation from from Figure Figure 11
- b. Time to reach RCS saturation (boiling)
(boiling) -
- b.
- b. OBSERVE THE CAUTION CAUTION PRIOR PRIOR TO LESS THAN REQUIRED LESS REQUIRED TIME FOR STEP 10, AND GO TO STEP 10.
10, AND 10. CONTAINMENT CLOSURE FROM FROM TABLE BELOW BELOW
. . Containment Plant Configuration Closure Time Configuration 1:
- 1. RCS cold legs, RCPs, or intermediate legs have openings totaling one square inch or greater AND 25 minutes
- 2. Rx Vessel upper plenum and RCS hot legs .QI NOT vented with a minimum of 72 square inch opening Configuration 2:
- 1. RCS cold legs, RCPs, or intermediate legs have openings totaling one square inch or greater AND 115 minutes
- 2. Rx Vessel upper plenum or RCS hot legs vented with a minimum of 72 square inch opening None of the above configurations 120 120 minutes
- c. Go to Step 6 W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Page: 9 Approval Date: 3-0NOP-041.8 Shutdown LOCAIMode 5 or 6] 2/22/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 5 Determine Time Determine Time To To Saturation Saturation By By Plotting ReS Plotting RCS Heatup Heatup RateRate
- a. Plot RCS
- a. Plot heatup rate RCS heatup rate
- 1) Plot core exit TCs every minute
- 1) minute for five minutes
- 2) Calculate
- 2) Calculate RCSRCS heatup heatup rate rate
- 3) Determine time required to reach saturation in in RCS
- 4) Report results to Unit RCO and NPS
- 5) Repeat this step every 15 minutes until RHR cooling is restored
- b. Time to reach RCS saturation b. OBSERVE THE CAUTION PRIOR TO (boiling) - LESS THAN REQUIRED
- STEP 11, AND fl GO TO STEP 11.
TIME FOR CONTAINMENT CLOSURE FROM TABLE BELOW
. Containment Plant Configuration Closure Time Configuration 1:
- 1. RCS cold legs, RCPs, or intermediate legs have openings totaling one square inch or greater ojD AND 25 minutes
- 2. Rx Vessel upper plenum and RCS hot legs QI NOT vented with a minimum of 72 square inch opening Configuration 2:
1.
- 1. RCS cold legs, legs, RCP5, RCPs, or intermediate intermediate legs have openings totaling one square inch inch or greater prn AND 115 minutes 115
- 2. Rx Vessel upper plenum or RCS hot legs vented 2.
with aa minimum minimum of of 72 72 square inch inch opening None of None of the the above above configurations 120 minutes 120 minutes W97:DH/bvc/mrg W9?: DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 10 10 Approval Approval Date: Date: 3-ONOP-041.8 2/22/02 2/22/02 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA rMode or 61 [Mode 55 or 6] I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I II RESPONSE I RESPONSE NOT NOT OBTAINED OBTAINED I 6 Initiate Actions Initiate Actions To Protect Personnel To Protect Personnel Working In In UNIT UNIT 33 Containment Containment
- a. Evacuate Non-essential
- a. Evacuate Non-essential Personnel Personnel InIn Containment Containment
- 1) Announce over the plant PA system:
- 1) 1)
- 1) Request NPSNPS pass supervisory supervisory announcement announcement over over MTX-900 radio
- Attention all "Attention personnel inside all personnel inside Unit Unit to order personnel personnel out out of Containment Evacuate 3 Containment Evacuate Unit Unit 3 containment.
containment. Containment Containment"
- 2) Sound the containment evacuation 2) Notify Health Physics Shift alarm Supervisor OR Operations Department personnel inside containment to order all personnel to evacuate the containment building.
- 3) Announce over the plant PA system: 3) Request NPS pass supervisory announcement over MTX-900 radio
- Attention all personnel inside Unit "Attention to order personnel out of 3 Containment Evacuate Unit 3 containment.
Containment Containment"
- b. Protect personnel inside containment as follows:
- 1) Direct H.P Shift Supervisor to determine 1)
Containment radiological entry requirements based on current plant conditions
- 2) Direct personnel teams inside containment to abide by updated H.P.
requirements OR exit containment
- c. Periodically monitor monitor R-3-11 AND R-3-12 to determine containment radiation conditions W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: ProcedureNo.: Procedure
Title:
Procedure
Title:
Page: Page: 11 11 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.S Shutdown LOCA Shutdown LOCA [Mode [Mode 55 or or 6J 61 2/22/02 2/22/02 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED II 7 Initiate Actions Initiate Actions To Establish Containment To Establish Containment Closure: Closure:
- a. Direct personnel
- a. Direct personnel to close any to close open any open containment penetrations containment penetrations
** Equipment Hatch Equipment Hatch
** Personnel Hatch Personnel Hatch
** Emergency Escape Hatch Emergency Hatch
** Any other known Any other known RCSRCS openings openings
- b. Actuate Containment Isolation Phase A:
- 1) Manually actuate Containment isolation 1) phase A
- 2) Verify Containment isolation phase A IF any containment isolation phase
- 2) j.
valve white lights on VPB - ALL - A valve is NOT closed, THEN BRIGHT manually close valve. IF valve(s) can NOT be manually closed, THEN manually or locally isolate affected containment penetration. W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No. Procedure
Title:
Procedure
Title:
Page: Page: 12 12 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.S Shutdown LOCA Shutdown LOCA [ModejMode 55 oror 6] 6] 2/22/02 2/22/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I CAUTION CAUTION If only If two CCW only two CCW Heat Exchangers are Heat Exchangers are in in service service AND AND MOV-3-749A MOV-3-749A and and MOV-3-7498 MOV-3-749B are OPEN, then are OPEN, two CCW then two CCW Pumps Pumps shall shall be be maintained maintained in in Pull-To-Lock. Pull-To-Lock. 8 Check CCWCCW System Status Status
- a. Verify Proper
- a. Verify Proper CCW CCW System System Operation Operation for for containment cooling:
containment cooling:
- 1) CCW Heat Exchangers - THREE IN
- 1) Perform the following:
SERVICE a) Start or stop CCW COW pumps to establish ONLY ONE RUNNING CCW PUMP. b) IF W MOV-3-749A AND MOV-3-749B are open, THEN stop and place in Pull-To-Lock all except one CCW COW pump. c) Go to Step 8b. GotoStep8b. COW pumps - ONLY TWO RUNNING
- 2) CCW - 2) Start or stop CCW COW pumps to establish ONLY TWO RUNNING CCW COW PUMPS.
- b. Check Normal Containment Coolers - - b. Go to Step 9 ALIGNED TO THE CHILLED WATER SYSTEM
- c. Stop any running ROPs RCPs W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Procedure Page: 13 Approval Date: 3-ONOP-04L8 3-0NOP-041.8 Shutdown LOCA rMode[Mode 5 or 61 2/22/02 2122/02 I STEP I I ACTION/EXPECTED RESPONSE II II RESPONSE NOT OBTAINED II 9 Establish Containment Cooling:
- a. Reset containment isolation phase A a. Stop any running RCPs AND fQ go to STEP ge.
9e.
- b. Open CCW to Normal Containment Cooler b. Stop any running RCPs AND go to valves Step ge.
9e.
- MOV-3-1417
- MOV-3-1418
- c. Check CCW Pumps - ALIGNED TO
- c. Direct an operator to restart the Chilled NORMAL CONTAINMENT COOLERS Water System
- d. Reset and start normal containment coolers
- e. Start emergency containment cooling equipment as follows:
- 1) Emergency containment filter fans - AT LEAST TWO RUNNING
- 2) Emergency containment coolers - -
ONLY TWO RUNNING W97:DH/bvc/mrg W97: DH/bvc/mrg
Procedure No.: Procedure No.: TiUe Procedure
Title:
Procedure I Page: Page: I 14 14 I Approval Approval Date: Date: 2/22/02 2/22/02 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA [Mode [Mode 55 oror 61 6j STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I CAUTIONS CAUTIONS
** Personnel working Personnel working in in containment containment should should be be warned prior to refilling warned prior refilling the the RCS RCS to avoid to inadvertent contamination avoid inadvertent contamination of of personnel personnel working working nearnear RCS RCS openings.
openings.
** The NPS SHALL evaluate the The necessity of evacuating non-essential personnel the necessity inside containment.
*a Only borated Only borated water water should be be added added to the RCS to maintain the RCS maintain adequate adequate shutdown margin.
10 Check RCS Level:
- a. RCS level a. Perform the following:
- Drain Down Level 1) Maintain RCS inventory using the following method(s) while continuing
- Ll-3-6421 - LESS THAN OR EQUAL LI-3-6421 - with this procedure:
TO 23% a) Charging flow (Step 13). OR b) RWST Gravity Feed (Step 14).
- Ll-3-6423 - LESS THAN OR EQUAL LI-3-6423 -
TO 23% c) VCT Overpressure Feed (Step 15). OR Go to Step 16.
- 2) GotoStepl6.
- Pressurizer Level, Ll-3-462-LI-3-462- LESS THAN OR EQUAL TO 50%
- b. RCS level b. Go to STEP 13 GotoSTEP13
- Drain Down Level
- LI-3-6421 LESS THAN OR EQUAL TO Ll-3-6421 14%
14% OR
- LI-3-6423 LESS Ll-3-6423 LESS THAN OR OR EQUAL TO TO 14%
14% OR
- Pressurizer Level, Ll-3-462-Pressurizer Level, LI-3-462- LESS LESS THAN THAN OR EQUAL TO OR EQUAL TO 10%
10% W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 15 15 Approval Approval Date: Date: 3-ONOP-041.8 Shutdown LOCA LOCA rMode 2/22/02 2/22/02 3-0NOP-041.8 Shutdown IMode 55 or or 6J 6] I STEP STEP I I ACTION/EXPECTED RESPONSE I I RESPONSE II ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED NOT OBTAINED 11 Refill The Refill The ReS RCS As As Follows: Follows:
- a. Align
- a. Align at least one High-head at least High-head SISI pump pump for hot for hot leg injection as leg injection follows:
as follows:
- 1) Align at least one train of safety 1) injection as follows:
- Verify the following A train SI SI equipment aligned for injection injection a) SI To Hot Leg, MOV-3-869,
- OPEN b) Loop A Hot Leg Safety MOV-3-866A Injection, MOV-3-866A- -
OPEN
** Verify the following B train SI equipment aligned for injection a) SI To Hot Leg, MOV-3-869,
- OPEN b) Loop B B Hot Leg Safety Injection, MOV-3-866B - -
OPEN
- b. Start at least one HI-Head SI pump
- c. Refill RCS with HHSI until either of the following conditions satisfied:
- RHR cooling - RESTORED OR
- LI-3-462, PZR Level Cold Cal Cal--
GREATER THAN 50%. 50%. 12 GoToStepl6 Go To Step 16 W97:DH/bvc/mrg W97:DH/bvc/mrg
f Procedure No.: Procedure Procedure
Title:
Procedure
Title:
Page: Page: 16 16 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.S Shutdown LOCA rMode 6] 2/22/02 IMode 5 or 61 I STEP I II ACTION/EXPECTED RESPONSE RESPONSE I I RESPONSE II I I RESPONSE NOT OBTAINED Using Charging Inventory Using Maintain RCS Inventory 13 Flow Flow
- a. Verify VCT makeup available:
** Makeup set for greater than or equal to RCS boron concentration
** Makeup set for automatic control Makeup
- b. Open Charging Flow To REGEN Heat Exchanger, HCV-3-121
- c. Open Loop A Charging Isolation, c. Open Loop C Charging Isolation, CV-3-31 OA CV-3-310A CV-3-31 OB.
CV-3-310B.
- d. Start at least one charging pump d. IF one charging pump can NOT be started, THEN perform the following:
- 1) Close Charging Flow To REGEN Heat Exchanger, HCV-3-121.
- 2) Close Loop A Charging Isolation, CV-3-31 OA.
CV-3-310A.
- 3) Verify Loop C Charging Isolation, CV-3-310B - CLOSED
- 4) Verify Auxiliary Spray Valve CV-3-31 1 - CLOSED CV-3-311 -
- 5) OBSERVE NOTE PRIOR TO STEP 14 AND GO TO STEP 14.
- e. Verify the makeup system maintains VCT e. Verify charging pump suction auto level transfer to RWST:
- 1) Place RCS MAKEUP control switch to STOP.
- 2) RWST to Charging Pump Suction, LCV-3-1 15B - OPEN.
LCV-3-115B -
- 3) VCT Outlet Isolation Valve, LCV-3-115C LCV-3-1 1 5C - CLOSED W97:DH/bvc/mrg
Procedure No.: Procedure Procedure
Title:
Procedure
Title:
Page: Page: 17 Approval Date: Approval Date: 3-ONOP-041.8 3-0NOP-041.8 [Mode 5 or 6J Shutdown LOCA [Mode 6] 2/22/02 2/22/02 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE I I RESPONSE NOT I I NOT OBTAINED II
- f. RCS Level Verify ReS f. Perform the following:
Perform
** LI-3-6421/6423 - GREATER THAN
- 1)
- 1) Increase charging pump speed.
23%
- 2) Start additional charging pumps as OR necessary to raise ReS RCS level.
- LI-3-462 - GREATER THAN 10%
RCS Level
- g. Maintain ReS
- LI-3-642116423 - GREATER THAN LI-3-6421/6423 23%
OR
** LI-3-462 - GREATER THAN 10%
- h. GoGotoSTEPI6.
to STEP 16. W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure Procedure
Title:
Procedure Page: 18 Approval Approval Date: 3-ONOP-041.8 3-0NOP-041.8 [Mode 5 or 61 Shutdown LOCA rMode 2/22/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED I I RESPONSE NOT OBTAINED I I1 NOTE -----------------------~ NOTE I II Cycling MOV-3-872, Alternate Low Head Safety Injection Valve, full open and then closed II I will add about 500 gallons of RWST water to the RCS. I L _______________________ ~ L 14 14 Maintain ReS RCS Level Using RWST Gravity Feed:
- a. Place RCS MAKEUP control switch to STOP.
- b. Cycle Alternate Low Head Safety Injection, b. Go to STEP 15 MOV-3-872, Open and THEN Close
- c. Verify RCS Level c. Perform the following:
- Ll-3-642116423 - GREATER THAN LI-3-6421/6423 - ** IF Reactor Coolant level has 23% increased, THEN return to STEP 14a.
1 4a. OR OR
- Ll-3-462 - GREATER THAN 10%
LI-3-462 -
** IF Reactor Coolant level has NOT increased, THEN continue efforts to raise RCS level and go to STEP 15.
GotoStepl6
- d. Go to Step 16 W97:DHlbvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 19 19 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA fMode [Mode 55 or or 6J6] 2/22/02 2/22/02 STEP I I ACTION/EXPECTED I STEP RESPONSE I I RESPONSE II ACTION/EXPECTED RESPONSE I I RESPONSE NOT NOTOBTAINED OBTAINED 15 15 Maintain RCS Maintain Level Using RCS Level Using VCTVCT Overpressure Feed Overpressure Feed
- a. Verify VCT
- a. Verify VCT makeup makeup available:
available:
- Makeup set for greater than or equal to Makeup RCS boron concentration concentration
** Makeup set set for automatic automatic control control
** LCV-3-115C-OPEN LCV-3-115C - OPEN
** VCT Pressure Pressure - GREATER
- GREATER THAN 25 psig
- b. Open Charging Flow To REGEN Heat Exchanger, HCV-3-121
- c. Open Loop A Charging Isolation, c. Open Loop C Charging Isolation, CV-3-31 OA CV-3-310A CV-3-310B.
CV-3-31 OB.
- d. Verify RCS Level d. Perform the following:
- LI-3-6421/6423 - GREATER THAN U-3-6421/6423 - ** IF Reactor Coolant level has 23% increased, THEN return to STEP 15a 1 5a OR OR
- Ll-3-462 - GREATER THAN 10%
U-3-462 -
** IF Reactor Coolant level has NOT increased, THEN continue efforts to raise RCS level and go to STEP 16.
16. W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 20 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA [Mode [Mode 55 or or 6] 6] 2122/02 2/22/02 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED 16 16 Identify And Identify And Isolate Isolate Any Any ReS RCS leakage leakage
- a. Dispatch operators
- a. Dispatch operators to identify the to identify the source source of of the leak the leak as as follows:
follows:
** Search for Search for the source of the source of the leak the leak
** Check known Check known drain drain rigs rigs for RCS RCS leakage leakage
- b. WHEN the
- b. WHEN the source source of the leak of the leak isis identified, identified, THEN isolate the leak as follows:
- 1) IF the leak is is from the RHR system, perform ATTACHMENT 11 while THEN perform procedure continuing with this procedure
- 2) IF the leak is from the RCS, THEN isolate the leak using any available boundaries r-----------~~----------,
NOTE I To maintain ReSRCS pressure low enough for gravity feed, at least 2 SGs must be refilled and I L I L___ _______________________ utilized for heat sink. ________1 ~ I 17 17 Determine If a Secondary Heat Sink Should Be Established:
- a. SGs - REQUIRED
- a. OBSERVE NOTES PRIOR TO STEP 20 AND GO TO STEP 20
- Reactor Core in vessel
- NO LARGE RCS VENT PATHS
- b. SGs - ANY AVAILABLE
- b. Perform the following:
- 1) Try to restore SGs
- 1) SGs to service.
- 2) WHEN SGs SGs are returned to service, THEN perform STEPS 18 18 and 19.19.
- 3) OBSERVE
- 3) OBSERVE NOTES NOTES PRIOR PRIOR TO TO STEP 20, STEP 20, and and GO GO TO STEPSTEP 20 20 W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 21 21 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA rMode jMode 55 or or 61 6] 2/22/02 2/22/02 STEP I I ACTION/EXPECTED I STEP RESPONSE I I RESPONSE I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED 18 18 Maintain S/G Maintain SIG Levels: Levels:
- a. Narrow range
- a. Narrow range level level - GREATER
- GREATER THAN THAN 6%6% a.
- a. Maintain Maintain total total feed feed flow flow greater greater than than 390 390 gpm gpm until until narrow narrow range range level level greater than than 6%6% inin at least least one one S/G.
SIG.
- b. Control feed flow to maintain
- b. maintain narrow narrow range range between 15%
level between 15% and and 50% 50%
- c. Narrow range
- c. Narrow range level level - LESS
- LESS THAN 50%50% c.
- c. Stop Stop feed feed flow to anyany S/G SIG with narrow narrow range level greater than 50%.
19 19 SIG steam dump to atmosphere Open S/G valves W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 22 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA [Mode 2/22/02 2/22/02 IMode 55 or or 6] 6j STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I1 JE NOTES I I . . The time The time to to saturation saturation in in the the ReS RCS should should be taken into be taken into consideration consideration when when determining determining I I how much how much time time should should be spent venting be spent venting the RHR system the RHR system prior prior to to taking taking additional additional I actions for actions for alternate alternate cooling cooling sources. sources. I I I
- If adequate time to completely vent out of thethe RHR RHR lines lines by vent the filling the by filling the RHR the ReS RHR system RCS toto 29%
system is not available, air can 29% and running running an can be swept RHR pump at aa flow an RHR swept flow I Ii I greater than rate greater rate than 3000 3000 gpm.gpm. II I 20 Vent RHR System As Necessary:
- a. Determine IF RHR RHR venting requiredrequired a. Go to Step 21.
- RHR pump cavitation required stopping RHR pump(s).
- RCS Level LI-3-6421/L1-3-6423 ReS Ll-3-6421/LI-3-6423 - LESS THAN 14% DURING THE PERFORMANCE OF THIS PROCEDURE
- b. Request assistance from HP shift supervisor and mechanical maintenance to perform venting
- c. Maintain RCS level while venting the RHR system
- d. Vent the RHR system from the following valves:
- 3-939A, RHR Pump A Seal Water HX Vent
- 3-939B, RHR Pump BB Seal Water HX Vent
- 3-761E, 3-761 E, RHR DISCH Hdr Vent W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No. Procedure
Title:
Procedure
Title:
Page: Page: 23 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA rMode 2/22/02 2/22/02 IMode 55 oror 61 6] I STEP STEP I I ACTION/EXPECTED ACTION/EXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED I 21 Establish Conditions Establish Conditions To To Start Start RHR RHR Pump: Pump: Verify RCS
- a. Verify
- a. RCS Level Level a.
- a. Perform Perform thethe Following:
Following:
** Ll-3-642116423 - GREATER LI-3-6421/6423 - GREATER THAN THAN OR OR 1)
- 1) Monitor Monitor RCS RCS heatup heatup rate rate EQUAL TO 23%
EQUAL
- 2) Feed Feed and Bleed Bleed cooling using using ATTACHMENT 22
- Pressurizer Level, Pressurizer Level, LI-3-462, LI-3-462, GREATER GREATER 3)
- 3) Return Return to to Step Step 6.
6. THAN OR EQUAL TO 10% 10%
- b. RHR pump - AVAILABLE
- b. Perform the Following:
1)
- 1) Monitor RCS RCS heatup rate rate
- 2) Feed and Bleed cooling using ATTACHMENT 2
- 3) Return to Step 6.
- c. Verify RHR System Valves In Proper c. Manually align valves to establish at Alignment As Follows: least one train of RHR flow.
** MOV-3-750 - OPEN -
** MOV-3-751 - OPEN -
** MOV-3-744A - OPEN -
** MOV-3-744B - OPEN -
** MOV-3-749A - OPEN -
** MOV-3-749B - OPEN -
** MOV-3-862A - CLOSED-
** MOV-3-862B - CLOSED-
** MOV-3-863A - CLOSED-
** MOV-3-863B - CLOSED-
- d. Verify CCW cooling to RHR System - IN - d.
ci. Restore CCW cooling to the RHR heat SERVICE exchangers using Step 8a of this procedure.
- e. Check Check core exit TCs - LESS THAN 200°F
- 200°F e. Initiate makeup to the RCS using One Initiate High-head SI pump.
High-head W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 24 24 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.S Shutdown LOCA Shutdown LOCA rMode [Mode 55 oror 61 6j 2/22/02 2/22/02 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I CAUTION CAUTION Starting an Starting an RHR RHR pump may may result result in in an an ReS RCS level level decrease decrease duedue to shrink shrink or or void void collapse. collapse. II NOTES I I* .* The RCS level necessary to The RCS to operate operate RHR RHR pumps is aa function of RHR RHR flow. flow. Figure Figure 2 I I should be referred to in order order to to determine thethe required level necessary. II II .* Methods for maintaining RCS level are; Charging Flow, Step 13; RWST Gravity Feed, I LI _Step __ 14; _ __ or VCT _ _ _ Feed Overpressure __ _15 Step ___________ ~ I 22 Restore RHR Flow:
- a. Close HCV-3-758, RHR Heat Exchanger Outlet Flow
- b. Close FCV-3-605, RHR Heat Exchanger Bypass Flow
- c. Start one RHR pump
- d. Maintain RCS level within the acceptable regions of Figure 2
- e. Establish 3100 gpm RHR flow as follows:
- Slowly open HCV-3-758, RHR Heat Exchanger Outlet Flow
- f. RHR flow - RESTORED
- f. Perform the Following:
- 1) Monitor
- 1) Monitor RCS heatup heatup rate
- 2) Continue
- 2) Continue efforts to cool the RCS using secondary using secondary heatheat sink.
sink.
- 3) Consult the NPS to determine IF
- 3) IF Feed and Bleed Cooling using Feed ATTACHMENT 22 should be ATTACHMENT be performed.
performed.
- 4) Return
- 4) Return to to Step Step 6.
6.
- g. Established desired
- g. Established RCS cooldown desired RCS cool down rate:
rate: 1)
- 1) Adjust FCV-3-605 fjQ Adjust FCV-3-605 AND HCV-3-758 HCV-3-758 to to obtain desired cooldown obtain desired rate while cooldown rate while maintaining maintaining RHR RHR flow flow W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Page: 25 Approval Date: 3-0NOP-041.8 Shutdown LOCA rMode 5 or 61 2/22/02 STEP I I ACTION/EXPECTED I STEP RESPONSE I I RESPONSE II ACTIONIEXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED 23 Check IfIf RCS Check RCS Makeup Should Be Makeup Should Be Reduced: Reduced: a.
- a. Perform Perform the the following:
following:
- a. RCS
- a. RCS temperature temperature - LESS
- LESS THAN THAN 200°F 200°F 1)
- 1) Continue Continue efforts efforts to to cooldown using using RHR.
RHR. 2)
- 2) Return Return to to STEP 22d.22d.
- b. RCS
- b. level STABLE RCS level- - STABLE OROR INCREASING INCREASING b.
- b. Perform Perform the the following:
- 1) Continue efforts to cooldown using RHR.
- 2) Return Return to STEP 22d.
- c. Stop any running High-head SI pumps and place them in standby.
- d. Control charging flow to maintain RCS level within the acceptable region of FIGURE 2 24 Check RCS Temperature - LESS THAN
- Perform the following:
140°F
- a. Continue cooldown using RHR.
- b. Return to STEP 22d.
25 Go To Appropriate Plant Procedure As Determined By The Nuclear Plant Supervisor END OF TEXT W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Page: 26 Approval Date: 3-0NOP-041.8 Shutdown LOCA [Mode 5 or 6] 2122/02 Li!..J I ACTION/EXPECTED ACTION/EXPECTED RESPONSE RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I FIGURE 11 FIGURE (Page 11 of (Page of 1) 1) LOSS OF RHR COOLING AT MID-LOOP MIDLOOP OPERATIONS OPERATIONS T1)E TO TIME SATURATION TO SATURATION 26 26 24 24 22 22 20 Ii) U) wLi I 18
~ 18
- >z z
S 16 16 zz 00 14 14 I
~
0:
- > 12 12
~
U) VI 10 10 0 0 I-
~
w Li 8B
- l' I-j::.
66 44 INITIAL ReS TEMP 200 *t~ 22 0 0 40 80 120 120 160 160 200 240 240 TIME AFTER RX SHUTDOWN AfTER RX SHUTDOWN (HOURS) (HOURS) W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No. Procedure No.: Procedure
Title:
Procedure
Title:
I Page: Page: 27 Approval Approval Date:Date: 3-0NOP-041.8 3-ONOP-041.8 Shutdown LOCA [Mode rMode 55 or 6] 61 2/22/02 STEP ACTIONIEXPECTED ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I FIGURE 22 (Page 11 of 1) 1) REQUIRED RCS ReS LEVEL VS RRR RHR FLOW
~
ACCEPTABLE ~ REGION ~ 8.0
~.8.0
~
CO? eq
~
23%
~
co CD
~ 7.0 '0 C)
~
eq
~ ..c
~ C.)
Co) co CD
~
- A1VtD UNACCEPT ABLJ= I- 6.0 -
.-C-.
c REGIO? REGION o0
....:l 22% oC
...J row
> 5.0 I-5.0 _Q 2
~
....:l :e
- Z o0
~ E-til 0
Q
~.4.0 4.0 >
.. e:<
-eo:-<
Z 21%
- I-*.°
..J Col Q
Ul U 3.0
~
ex:
- .-2.o . 2.0 20%
-* 1.0 (MID-LOOP)
(MID-L.OOP) . I- 0.0 19% 19%
.0.5
-0.5
'000 1000 . 1500 2000 2500 3000 3500 4000 RHR FLOW GPH W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
I Page: Page: I 28 28 I Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA rMode[Mode 55 or or 616j 2/22/02 2/22/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I ATTACHMENT 1I ATTACHMENT (Page 11 of (Page of 5) 5) RHR LEAK RHR LEAK ISOLATION ISOLATION CAUTION If High If High Temperature Temperature or High High Velocity Velocity break break hampers hampers leak leak identification, identification, stopstop the running RHR running RHR pumps to minimize minimize break break flow flow 1 Check RHR system components Perform the following: between RCS (MOV-3-750 / MOV-3-751 AND 3-752A / 3-752B) 3-752B) a. Stop Stop both RHR pumps. 3A3B RHR and 3A13B RHR pump Inlet pump Inlet b. Shut the following valves: Isolation Valves- NOT LEAKING Isolation LEAKING
- MOV-3-750, LOOP 3C RHR Pump Suction Stop Vlv
- MOV-3-751, LOOP 3C RHR Pump Suction Stop Vlv
- 3-752A, 3A RHR Pump Inlet Isol Iso!
- 3-752B, 3B RHR Pump Inlet Isol
- MOV-3-862A, RHR Pump Recirc to RWST
- MOV-3-862B, RHR Pump Recirc to RWST
- 3-741A, RHR Cross Conn Vlv for Hot & Cold Leg
- c. Go to procedure step in effect.
2 Check RHR System components Perform the following: bounded by the following RHR valves - NOT LEAKING:
- a. Verify RHR pumps STOPPED.
- b. Close the following valves:
- 3-752A, 3A RHR Pump Inlet
- 3-752A, 3A RHR Pump Inlet Isolation Isolation.
Isolation.
- 3-759A, RHR HX A Outlet
- 3-757D, RHR HX A Bypass HDR Valve ISOL.
ISOL.
- 3-757D, RHR HX A Bypass
- 3-759A, RHR HX A Outlet Valve.
Hdr Hdr Isol.
- c. Go to STEP 99 of this ATTACHMENT.
Go ATTACH MENT. 33 Check RHR System components components Perform the following: bounded by by the following RHR valves - NOT - LEAKING: LEAKING: a.
- a. Verify RHRRHR pumps STOPPED.
b.
- b. Close the Close the following valves:
- 3-752B, 3-752B, 3B 3B RHR Pump Pump Inlet Inlet
- 3-752B, 3-752B, 3B3B RHR PumpPump Inlet Inlet Isolation.
Isolation. Isolation. Isolation.
- 3-759B, 3-759B, RHRRHR HX HX BB Outlet Outlet
- 3-757C, 3-757C, RHRRHR HXHX BB Bypass Bypass Hdr Hdr Isol.
Isol.
** 3-757C, 3-757C, RHRRHR HX HX BB Bypass Bypass HdrHdr Isol.
Isol. ** 3-759B, 3-759B, RHRRHR HXHX BB Outlet. Outlet.
- c. Go
- c. Go toto STEP STEP 99 ofof this this ATTACHMENT.
ATTACHMENT. W97:DH/bvc/mrg W97: DH/bvclmrg
Procedure No.: Procedure
Title:
Page: 29 Approval Date: 3-0NOP-041.8 Shutdown LOCA fMode 5 or 61 2/22/02 STEP I I ACTION/EXPECTED I STEP RESPONSE I I RESPONSE II ACTION/EXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED ATTACHMENT 1I ATTACHMENT (Page 22 of (Page of 5) 5) RHR LEAK RHR ISOLATION LEAK ISOLATION 4 Check RHR system Check RHR system components components Perform the Perform the following: between RCS between RCS andand RHRRHR DISCH DISCH To To Cold Leg Cold Leg Isol Isol Valves- NOT NOT LEAKING LEAKING a. Stop Stop both both RHR RHR pumps. pumps.
- b. Shut
- b. Shut the following valves:
** MOV-3-744A RHR RHR DISCH DISCH To Cold ** MOV-3-744A MOV-3-744A Isol Valve Leg Isol Leg ** MOV-3-744B
** MOV-3-744B RHR DISCH To Cold c. Go to STEP 7 of this ATTACHMENT.
Leg Isol Valve 5 Check RHR System components Perform the following: bounded by the following RHR valves - NOT LEAKING:
- a. Stop both RHR pumps.
- b. Close RHR Disch To Cold Leg Isol
** 3-757D, RHR HX A Bypass valves:
Hdr Isol IsoI ** MOV-3-744A
** 3-759A, RHR HX A Outlet Vlv. ** MOV-3-744B
** 3-759B, RHR HX B Outlet Vlv. c. Close RHR HX AlB C. A/B Outlet Vlvs:
** 3-757C, RHR HX B Bypass Hdr ** 3-759A Isol. ** 3-759B
** MOV-3-744A RHR DISCH To Cold d. Close RHR HX AlB A/B Bypass HDR Isol Leg Isol Valve Valves:
** MOV-3-744B RHR DISCH TO Cold ** 3-757D Leg Isol Valve ** 3-757C
- e. Go to STEP 7 of this ATTACHMENT 6 Return to procedural step in effect.
W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 30 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA [Mode [Mode 55 or or 61 2/22/02 2/22/02 6] STEP I I ACTION/EXPECTED I STEP RESPONSE I I RESPONSE II ACTION/EXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED ATTACHMENT 1I ATTACHMENT (Page 33 of (Page of 5) 5) RHR LEAK ISOLATION RHR LEAK ISOLATION 7 RHR System For Align RHR For Alternate Cooldown Cool down Lineup
- a. Close 3-887,
- a. Close 3-887, RHRRHR To To RWST RWST Supply Hdr Hdr IsoIsolI VLV.
- b. Check both RHR pump discharge b. Perform the following:
pressures - LESS THAN 210 PSIG
- 1) Verify RHR Suction From RWST
- P1-3-600 PI-3-600 valve - CLOSED
- P1-3-601 PI-3-601 ** MOV-3-862A
- MOV-3-862B
- 2) Open MOV-3-863A and MOV-3-863B LOCALLY.
- 3) Go to STEP 7e of this ATTACHMENT
- c. Close the following breakers:
- 30726 for MOV-3-863A
- 30626 for MOV-3-863B
- d. Open an RHR Alternate Disch Isol VLV
- MOV-3-863A
- MOV-3-863B MOV-3-863B
- e. Open MOV-3-872, Alternate Low HEAD HEAD SI
- f. Check RCS Level f. Perform the following:
- Ll-3-6421 GREATER THAN LI-3-6421 GREATER THAN 23%
23% 1) WHEN reactor vessel
- 1) vessel level level GREATER THAN 23%, OR OR
- LI-3-6423 GREATER Ll-3-6423 GREATER THAN 23% 23% Pressurizer Level Level greater greater than 10%,
10%, STEP 88 of this THEN return to STEP OR ATTACHMENT. ATTACHMENT.
** LI-3-462 GREATER Ll-3-462 GREATER THAN THAN 10%
10% 2) Continue
- 2) Continue with with procedure procedure STEP in STEP in effect.
effect. W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 31 31 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA Shutdown LOCA [Mode[Mode 55 or or 6J6] 2122/02 2/22/02 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED II ATTACHMENT 1I ATTACHMENT (Page 44 of (Page of 5) 5) RHR LEAK ISOLATION RHR LEAK ISOLATION 88 Establish RHR Establish RHR Cooling Cooling Start One
- a. Start One RHR RHR pump:pump:
- 3A RHR pump 3A RHR with MOV-3-863A-pump with MOV-3-863A -
OPEN OPEN
- 3B RHR pump with MOV-3-863B -
OPEN
- b. Maintain running RHR pump b. Throttle RHR Pump AlB A/B Isol Isol valve to differential pressure running RHR pump to obtain proper
- BETWEEN 105 AND 115 PSIG differential pressure:
- P1-3-601 Difference between PI-3-601 ** 3-754A for 3A RHR pump Pl-3-1595A for 3A RHR and PI-3-1595A ** 3-754B for 3B RHR pump pump
- P1-3-600 Difference between PI-3-600 and PI-3-1595B for 3B RHR pump
- c. Control RCS cooldown rate locally by throttling CCW from operating RHR heat exchanger:
- MOV-3-749A for 3A HX
- MOV-3-749B for 3B HX
- d. Go to plant procedure as determined by NPS W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No. Procedure
Title:
Procedure
Title:
Page: Page: 32 32 Approval Approval Date: Date: 3-ONOP-041.8 Shutdown LOCA LOCA rMode 2/22/02 2/22/02 3-0NOP-041.8 Shutdown IMode 55 or or 61 6j I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOTOBTAINED OBTAINED II ATTACHMENT 1I ATTACHMENT (Page 55 of (Page of 5) 5) RHR LEAK RHR LEAK ISOLATION ISOLATION 9 Start Unisolated Unisolated RHR Pump RHR Pump
- a. Check RCS Level a. Perform Perform the following:
following:
- Ll-3-6421 GREATER LI-3-6421 GREATER THAN THAN 23%
23% 1) WHEN
- 1) WHEN reactor reactor vessel vessel level level greater greater than 23%
23% OROR pressurizer level level
- Ll-3-6423 GREATER THAN 23%
LI-3-6423 GREATER THAN 10%, THEN return to STEP 9b of this ATTACHMENT.
** Ll-3-462 - GREATER THAN 10%
LI-3-462 - 10% 2) Continue with procedural STEP in in effect.
- b. Start unisolated RHR pump:
** 3A 3ARHRpump RHR pump
** 3B 3BRHRpump RHR pump
- c. Return FCV-3-605, RHR Heat Exchanger Bypass Flow, to automatic at desired flow.
- d. Open HCV-3-758, RHR Heat Exchanger Outlet Flow, as necessary to maintain desired RCS temperature.
- e. Return to procedural Step in effect.
W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 33 Approval Approval Date: Date: 3-ONOP-041.8 3-0NOP-041.8 Shutdown LOCA [Mode Shutdown [Mode 55 or or 6] 2/22/02 2/22/02 61 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I II RESPONSE I RESPONSE NOT NOT OBTAINED OBTAINED II ATTACHMENT 22 ATTACHMENT (Page 11 of (Page of 3) 3) FEED AND BLEED FEED BLEED COOLING COOLING 1I Check Secondary Check Secondary Heat Heat Sink Sink Return STEP in Return to STEP effect. in effect. NOT AVAILABLE NOT 2 Verify RCS RCS FEED FEED Path:Path: Manually Manually Start pumps and align valves to establish one train
- a. One train of SI valves of safety injection equipment injection, aligned for injection. for an RCS Feed Path. IF E aRCS a RCS feed path can NOT be established,
- b. High-head SI pumps -AT AT THEN return to STEP in effect.
LEAST ONE RUNNING 3 Verify Containment Isolation IF any containment isolation IE Phase A White Lights On VPB - phase A valve is NOT closed, ALL BRIGHT THEN manually close valve. IF valve(s) can NOT be manually closed, THEN manually OR locally isolate affected penetration. 4 Establish RCS Bleed Path:
- a. Verify power to PZR PORV Block a. Restore power to block valves.
valves - AVAILABLE
- b. Open both PZR block valves
- c. Open both PZR PORVs W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Page: 34 Approval Date: 3-0NOP-041.S Shutdown LOCA rMode 5 or 61 2/22/02 IISTEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED II ATTACHMENT 22 ATTACHMENT (Page 22 of (Page of 3) 3) FEED AND FEED BLEED COOLING AND BLEED COOLING 55 Verify Adequate RCS Verify Bleed Path: RCS Bleed Path: Perform the Perform the following: following:
** PZR PORVs - BOTH PZR PORVs - BOTH OPEN OPEN a.
- a. Continue attempts Continue attempts to open open allall PZR PZR PORVs and PZR PORVs PZR PORV PORV blockblock valves.
** PZR PORV block PZR PORV valves - BOTH block valves - BOTH OPEN OPEN b.
- b. Direct operator Direct operator to to install install fuses fuses forfor RCS RCS vent valves:
- 31013101 for SV-3-6318A SV-3-6318A
** 3102 for SV-3-6318B SV-3-6318B
** 3103 for SV-3-6319A
- 3104 for SV-3-6319B
- 3105 for SV-3-6612
- 3106 for SV-3-6611 SV-3-661 1
- c. WHEN power is restored to RCS vent valves, THEN open all RCS vents:
- SV-3-6318A
- SV-3-6318B
- SV-3-6319A
- SV-3-6319B
- SV-3-6612
- SV-3-6611 6 Maintain RCS Heat Removal:
- Maintain SI flow
- Maintain PZR PORV - BOTH OPEN
- Maintain PZR PORV block valves - BOTH -
OPEN 7 Check For Adequate Heat Sink: Return to Step 11 of the procedure.
- RHR cooling flow - RESTORED OR
- Secondary Heat sink -AVAILABLE
-AVAILABLE W97:DH/bvc/mrg W97:DH/bvc/mrg
Procedure No.: Procedure
Title:
Page: 35 Approval Date: 3-0NOP-041.8 Shutdown LOCA rMode 5 or 61 2/22/02 I STEP I II ACTION/EXPECTED RESPONSE I I RESPONSE II ACTIONIEXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED ATTACHMENT 22 ATTACHMENT (Page 33 of (Page of 3) 3) FEED AND FEED BLEED COOLING AND BLEED COOLING 88 Check RCS Check Vent Valves RCS Vent Valves - ALL
- ALL CLOSED:
CLOSED: Perform Perlorm the the following: following:
** SV-3-6318A SV-3-6318A a.
- a. Close Close all all RCS RCS vent vent valves.
valves.
** SV-3-6318B SV-3-6318B
** SV-3-631 9A SV-3-6319A b.
- b. Direct Direct operator operator toto remove remove fuses fuses for for all all
** SV-3-631 9B SV-3-6319B RCS RCS vent vent valves:
valves:
** SV-3-6612 SV-3-6612
** SV-3-6611 SV-3-6611 ** 3101 for SV-3-6318A 3101 SV-3-6318A
- 3102 3102 for for SV-3-6318B SV-3-6318B
- 3103 for SV-3-6319A
- 3104 for SV-3-6319B
- 3105 for SV-3-6612 SV3-6612
** 3106 for SV-3-6611 SV-3-661 1 9 Close Both PZR PORVs IF any PZR PORV can NOT be closed, THEN manually close its block valve 10 Stop all High-head SI pumps feeding the RCS 11 Consult Plant Management For additional Containment Cleanup Requirement Based On Existing Plant Conditions 12 12 Go To Step In Effect FINAL FINAL PAGE PAGE W97:DH/bvc/mrg W97:DH/bvc/mrg
o you
-J icn
( ~
Appendix C Appendix C Job Performance Measure Job Performance Measure Form Form ES-C-1 ES-C-I Worksheet Worksheet Facility: Facility: Turkey Point Turkel:: Point Task No: Task No: Adjust Rod Adjust Position for Rod Position for Tavg Tavg Performance Job Performance Job Task
Title:
Task
Title:
Control Control Measure No: Measure No: Systems - cc Sl::stems 001 A2.11 001 A2.11 (4.4/4.7) (4.4/4.7) K/A
Reference:
KIA
Reference:
001 A2.14 001 A2.14 {3.7/3.9} (3.7/3.9) Examinee: Examinee: NRC Examiner: NRC Examiner: Facility Evaluator: Facility Evaluator: Date: Date: Method of testing: Method Simulator Simulator Simulated Performance Simulated Actual Performance Yes Classroom Simulator Simulator - - -Yes ---- Plant - - - - - - - Plant Classroom Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Unit 3 is has been at 50% power for the past 40 hours following repairs to the 38 3B SGFP
- 2. 3-GOP-301, Hot Standby to Power Operation is available to support return to 100% power beginning at step 5.88
- 3. A rod control malfunction resulted in Tavg approximately approximately 2°F below tref
- 4. The rod control malfunction has been repaired Task Standards:
- 1. Rod control is placed in manual and control bank D rods withdrawn.
- 2. The rod control urgent failure is recognized and reset
- 3. Uncontrolled control rod withdrawal is recognized and the reactor manually tripped Required Materials:
3-ONOP-028
- 1. 3-0NOP-028 3-ARP-097.CR (annunciator panel B)
- 2. 3-ARP-097.CR 8)
General
References:
- 1. 3-ONOP-028 3-0NOP-028
- 2. 3-ARP-097.C 3-ARP-097.CR R
- 3. 3-GOP-301 Initiating Cue:
The Unit Supervisor directs you to withdraw control rods in 33 step increments to match Tavg with Tref. Time Critical Task: Yes/No Validation Time: 15 15 minutes
Appendix C Page 2 of 8 ES-C-I Form ES-C-1 INSTRUCTIONS TO OPERA OPERATOR TOR READ TO TO OPERA OPERA TOR: TOR: WHEN II TELL YOU TO BEGIN, BEGIN, YOU ARE TO PERFORM PERFORM THE ACTIONS AS DIRECTED DIRECTED IN IN THE INITIATING INITIATING CUES. II WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS IS TO BE BE PERFORMED PERFORMED PROVIDE THE NECESSARY AND PROVIDE NECESSARY TOOLS WITH WHICH TO PERFORM PERFORM THIS TASK. BEFORE STARTING, II WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS:
- 1. Unit 3 is has been at 50% power for the past 40 hours following repairs to the 3B SGFP
- 2. 3-GOP-301, Hot Standby to Power Operation is available to support return to 100% power beginning at step 5.88
- 3. A rod control malfunction resulted in Tavg approximately 2°F below tref
- 4. The rod control malfunction has been repaired INITIATING INITIA TlNG CUE:
The Unit Supervisor directs you to withdraw control rods in 3 step increments to match Tavg with Tref. TERMINATION TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. NO TES TO EVALUATOR AND IIF NOTES I/F OPERA TOR: IC-i 39. If IC-139
- 1. Reset simulator to IC-2 or IC-139. IC-i 39 used, setup is complete.
- 2. Click on Schema -+ REACTOR -+ > ROD CONTROL ROD POSITION -+ ROD SPEED TO LOGIC CABINET. -+ > LOGIC CABINET -+ TFL11UAL TFL UAL - LOG_CAB INSTRUC URGENT ALARM -+
- > FALSE IML1ALRP then enter condition = IML 1ALRP then INSERT
- 3. Place simulator in run and insert rods 12 steps to lower Tavg := 2.2°F below Tref. Return rods to AUTO. Allow Tavg & power to stabilize.
- 4. Freeze simulator and store temporary IC if needed for repeat runs of this JPM.
- 5. Open & execute lesson file NRC SRO XXIII JPM c.
I Appendix C Page 3 of 8 I ES-C-I I Form ES-C-1 Denote critical steps with a check mark Start Time Placed the rod control selector switch to MANUAL Placed MANUAL STEP 11 :
- - SAT UNSAT STANDARD:
..Jq Placed the rod control selctor switch to MANUAL STEP 2 Withdrew control rods to match Tavg with Tref
- - SAT
- - UNSAT STANDARDS:
1
..J 11.. In-Hold-Out switch moved to the OUT position J
..J 2. First rod withdrawal stopped when rods are withdrawn no more than 3 steps
- 3. Plant allowed to stabilize as necessary
- 4. In-Hold-Out switch moved to the OUT position I/F IIF nd 2
After initiation of the 2 rod withdrawal, click on Schema ~* OPERATOR REACTOR * ~ ROD CONTROL ROD POSITION ~
- ROD SPEED TO CUE: LOGIC CABINET *. * ~ LOGIC CABINET * ~ TFL TFLIUAL 1UAL - LOG_CAB INSTRUC URGENT ALARM ~ ÷ TRUE then INSERT OR Trigger lesson step ROD CONTROL URGENT FAILURE.
STEP Recognized/reported rod control urgent failure 3 : -- SAT
- - UNSAT
- 1. Recognized/reported annunciator B-8148-8/4 alarming STANDARDS:
- 2. Released In-Hold-Out switch Referred to 3-ARP-097.CR for annunciator B-8148-8/4 STEP 4 : -- SAT UNSAT
- 1. Obtained 3-ARP-097.CR STANDARDS:
- 2. Referred to annunciator response for B-8/4 8-8/4
Appendix C Appendix C Page 44 of Page of 88 Form Form ES-C-1 ES-C-I Determined status Determined status of of trouble trouble indicating indicating lamps lamps on on rod rod control control logic logic and and STEP 55 STEP power cabinets power cabinets - - SAT SAT UNSAT UNSAT STANDARDS: STANDARDS:
..JJ 1.
- 1. Directed Turbine Directed Turbine Operator Operator (TO)
(TO) proceed proceed to to 3B 3B MCC room and MCC room and unit 3 rod check status of unit rod control logic and power cabinets
- 2. Received report from TO TO that that no trouble lamps are lit on unit 3 rod control logic control logic or or power power cabinets cabinets hF IIF When asked as TO to check status of unit 3 rod control logic and OPERATOR power cabinet trouble lamps, report back that none are lit.
CUE: STEP 6 : Verified rod control selector switch in MANUAL - - SAT
- - UNSAT STANDARD: Determined rod control selector switch in MANUAL As Unit Supervisor (US), direct RO not to dilute or increase load to CUE: match Tavg & Tref at this time Inform RO that US will address 3-0NOP-028 3-ONOP-028 Ensured I&C notified of rod control urgent failure and indications at rod STEP 7
- control logic and power cabinets - - SAT
- - UNSAT Notified or requested US notify l&C I&C that:
STANDARDS: 1. Rod control urgent failure annunciator B-814
- 1. B-8/4 alarming
- 2. No trouble indicating lamps lit on unit 33 rod control logic or power cabinets
. 3-ARP-097.CR directs the RO to reset the rod control urgent urgent failure CUE:
CUE: alarm and return rods to AUTO. IfIf askedasked as US, US, direct RO to follow the procedure and that l&C I&C concurs with this course of action
II Appendix Appendix C C Page 55 of Page of 88 Form ES-C-1 Form ES-C-I I Reset rod control urgent failure failure alarm alarm STEP STEP 88 : Reset rod control urgent SAT SAT
- - UNSAT UNSAT STANDARDS:
STANDARDS:
..JJ 1.
- 1. Pressed rod Pressed rod control control alarm alarm reset reset pushbutton pushbutton
- 2. Recognized/reported that rod control urgent failure alarm reset (annunciator 8-8/4 B-8/4 extinguished)
CUE* CUE: US, direct RO As US, RO to match match Tavg == Tref by resumption of previously by resumption previously ordered rod withdrawal STEP 9 : Withdrew control rods to match Tavg with Tref SAT
- - UNSAT STANDARDS:
J
..J 11.. In-Hold-Out switch moved to the OUT position J
..J 2. Second rod withdrawal stopped when rods are withdrawn no more than 3 steps
- 3. Plant allowed to stabilize as necessary
- 4. In-Hold-Out switch moved to the OUT position After initiation of the 3rd rod withdrawal, click on Schema * ~
I/F IIF REACTOR f ~ ROD CONTROL ROD POSITION * ~ ROD MOTION OPERATOR FAILURE AND CONTROLS (SC408) * ~ TFLIO3 TFL 103 - SC408 CONTI CUE: ROD WITHDRAWAL MAN/INDIV * ~ TRUE then INSERT OR Trigger lesson step CONTINUOUS ROD WITHDRAWAL. I Recognized uncontrolled continuous rod withdrawal and manually STEP 10 10 SAT tripped reactor per 3-ONOP-028 3-0NOP-028 -- UNSAT UNSAT STANDARDS: 1.
- 1. Determined rods withdrawing continuously in an uncontrolled manner manner 2.
2 . Detemined that rod control selector switch switch already in MANUAL already in MANUAL 1..J 3. Manually
- 3. Manually tripped tripped reactor reactor per per 3-ONOP-028 3-0NOP-028 step step 4.4.2 4.4.2
Appendix C Appendix C Page 66 of Page of 88 Form Form ES-C-1 ES-C-I Terminating Reactor manually tripped STOP Cue: Stop Stop Time Time - - - -
I* Appendix CC Page 7 of 8 I ES-C-I I Form ES-C-1 Verification of Completion Job Performance Measure No. Systems - c
~~~=-~-------------------------------------------
Examinees Name: Examinee's Examiner's Examiners Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Examiners signature and date: __________________________________
JPM BRIEFING SHEET INITIAL CONDITIONS: 3B SGFP
- 1. Unit 3 is has been at 50% power for the past 40 hours following repairs to the 38
- 2. 3-GOP-301, Hot Standby to Power Operation is available to support return to 100% power beginning at step 5.88
- 3. A rod control malfunction resulted in Tavg approximately 2°F below tref
- 4. The rod control malfunction has been repaired INITIATING
!NITIA TlNG CUE: The Unit Supervisor directs you to withdraw control rods in 3 step increments to match Tavg with Tref. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 3-0NOP-028 CAUTION Performance of this procedure may affect core reactivity_
Title:
Reactor Control System Malfunction Safety Related Procedure Responsible Department: Operations Revision Approval Date: 5/31/05 RTSs 88-0535P, 88-0729, 88-0906P, 88-2135P, 89-2683, 91-0380T, 91-1074, 92-0359P, 92-1245P, 93-0619, 93-1215P, 95-0378P, 95-0778P, 02-01 80P, 03-0533P, 96-0732P, 00-0229P, 01-0059P, 02-0180P, 04-0497P, 05-0354P PC/Ms 92-031, PCIMs 92-03 1, 03-048 W97:/JWB/dtlbvc/ev W97:/JWB/dUbvc/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 2 Approval Date: Date: 3-ONOP-028 3-0NOP-02S Reactor Control System Malfunction 5/31/05 LIST OF EFFECTIVE PAGES Revision Revision Page Date Page Date 11 05/31/05 12 11111104 11/11/04 2 05/31/05 05/31105 13 11111104 11/11/04 3 04/30/0 1 04/30101 14 04/12/02 4 05/31/05 05/31105 15 05/31/05 05/31105 55 05/24/00 OS/24/00 16 05/31/05 05/31105 6 05/24/00 17 05/31/05 7 05/24/00 18 05/31/05 05/31105 88 11111104 11/11/04 19 05/31/05 05/31105 9 11/11/04 11111104 20 05/31/05 05/31105 10 11/11/04 11111104 21 05/31/05 05/31105 11 11/11/04 11111/04 W97:/JWB/dtlbvc/ev W97:/JWB/dtJbvc/ev
Procedure No.: Procedure No. Procedure
Title:
Procedure
Title:
Page: Page: 3 Approval Date: Approval Date: 3-ONOP-028 3-0NOP-028 Reactor Control System Malfunction 4/30/01 TABLE OF CONTENTS Section 1.0 PURPOSE .................................................................................................................... . 5 2.0 SYMPTOMS 2.1 Immovable RCC '" ............................................................................................ . 6 2.2 Failure of an RCC Control Bank to Insert with Reactor Control in Automatic ...................................................................................................... . 6 2.3 Continuous Insertion of an RCC Control Bank ................................................ . 6 2.4 Continuous Withdrawal of an RCC Control Bank ........................................... . 7 2.5 Control Bank D Demanded Past 230 Steps ...................................................... . 7 3.0 AUTOMATIC ACTIONS 3.1 Immovable RCC ............................................................................................... . 8 3.2 Failure of an RCC Control Bank to Insert with Reactor Control in Automatic ...................................................................................................... . 8 8 3.3 Continuous Insertion of an RCC Control Bank ................................................ . 8 3.4 Continuous Withdrawal of an RCC Control Bank ........................................... . 8 3.5 Control Bank D Demanded Past 230 Steps ...................................................... . 8 8 4.0 IMMEDIATE ACTIONS 4.1 Immovable RCC ............................................................................................... . 9 9 4.2 Failure of an RCC Control Bank to Insert with Reactor Control in Automatic ...................................................................................................... . 9 4.3 Continuous Insertion of an RCC Control Bank ................................................ . 9 9 4.4 Continuous Withdrawal of an RCC Control Bank ........................................... . 9 9 4.5 Control Bank D Demanded Past 230 Steps ...................................................... . 9 W97:/JWB/dt/evIcv W97:/JWB/dtJev/ev
Procedure No.: Procedure
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Page: 4 Approval Date: 3-0NOP-028 Reactor Control System Malfunction 5/31105 TABLE OF CONTENTS (Cont'd) TABLE (Contd) Section Section fg 5.0 5.0 SUBSEOUENT ACTIONS SUBSEQUENT ACTIONS 5.1 ImmovableRCC Immovable RCC ................................................................................................ 10 10 5.2 5.2 Failure of an RCC Control Bank to Insert with Reactor Control Automatic in Automatic....................................................................................................... 15 15 5.3 Continuous Insertion of an RCC Control Bank ................................................. 15 15 5.4 Continuous Withdrawal of an RCC Control Bank ............................................ 17 17 5.5 Control Bank D Demanded Past 230 Steps ........ ............. ...... ... .......... ......... ...... 17 17
6.0 REFERENCES
/RECORDS REQUIRED/ REOUIRED/ DOCUMENTS COMMITMENT DOCUMENTS............................................................................... 19 ENCLOSURE Enclosure 11 Accident Analyses Requiring Re-evaluation in the Event of RCC an Inoperable RCC............................................................................................. 21 hIQ7I W97:/JWB/dtlev/ev
Procedure No.: Procedure No.; Procedure
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Procedure
Title:
Page: Page: 55 Approval Date: Approval Date: 3ONOP-028 3-0NOP-028 Control System Reactor Control System Malfunction Malfunction 5/24/00 5/24/00 1.0 1.0 PURPOSE 1.1 This procedure provides instructions to be followed because of a Reactor Control System Malfunction due to: 1.1.1 Failure of an RCC to move due to being untrippable, CRDM failure, or rod control power supply failure 1.1.2 Failure of an RCC control bank to insert following a change in Turbine load or in boron concentration with reactor control in automatic 1.1.3 Continuous insertion of an RCC control bank 1.1.4 Continuous withdrawal of an RCC control bank 1.2 This procedure provides instructions to be followed when Control Bank D step demands greater than 230 steps while the Rod Motion Control Selector is positioned in MAN. WQ7I. lWR/Hi/ivIv W97:/JWB/dt/ev/ev
Procedure No.: Procedure No.: Procedure
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Procedure
Title:
Page: Page: 66 Approval Approval Date: Date: 3-ONOP-028 3-0NOP-028 Reactor Control Reactor Control System System Malfunction Malfunction 5/24/00 5/24/00 2.0 2.0 SYMPTOMS SYMPTOMS 2.1 2.1 Immovable RCC Immovable RCC 2.1.1 2.1.1 The RCC The RCC is determined to is detennined to bebe immovable immovable during during routine routine operation operation oror perfonnance performance of 3-0SP-02S.6, of 3-OSP-028.6, RCCA RCCA PERIODIC PERIODIC EXERCISE. EXERCISE. 2.2 Failure of an RCC Control Bank Bank to Insert with Reactor Control inin Automatic 2.2.1 Failure of the control banks to insert when Tavg exceeds Tref by greater than 1.5 degrees F 1.5 2.2.2 Annunciators
- 1. B 4/4, TAVG/TAVG - TREF DEVIATION
- 2. B 4/5, RCS HIILO HIJLO TAVG
- 3. B 9/4, ROD CONTROL URGENT FAILURE 2.3 Continuous Insertion of an RCC Control Bank 2.3.1 Tref matched, or Tavg less than Tref RCCs stepping in with Tavg and Trefmatched, 2.3.2 Tavg decreases more than 1.5 degrees F below Tref 2.3.3 Decreasing reactor power 2.3.4 of PT-3-446 (if selected)
Failure ofPT-3-446 2.3.5 Failure of PT-3-447 (if selected) ofPT-3-447 2.3.6 Failure of Power Range Channel 4 2.3.7 Failure of TM-408, Medium Signal Selector ofTM-40S, 2.3.8 2.3.S Annunciators
- 1. B B 4/4, TAVG/TAVG - TREF DEVIATION
- 2. B SI1, ROD BANK B 8/1, A/B/C/D LO LIMIT BANKAIB/C/D
- 3. B S/2, ROD BANK B 8/2, A/B/C/D EXTRA LO LIMIT BANKAIB/C/D W97:/JWB/dt/ev/ev W97:/JWB/dUev/ev
Procedure No.: Procedure No.: Procedure
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Procedure
Title:
Page: Page: 77 Approval Approval Date: Date: 3-ONOP-028 3-0NOP-028 Reactor Control Reactor Control System System Malfunction Malfunction 5/24/00 5/24/00 2.4 2.4 Continuous Withdrawal Continuous Withdrawal of of an an RCC RCC Control Control Bank Bank 2.4.1 2.4.1 RCCs stepping RCCs stepping outout as as indicated indicated onon the the RPls RPIs or or group group demand demand step step counters, counters, and and not manually not manually initiated initiated by the operator. by the operator. 2.4.2 2.4.2 Tavg increases Tavg increases more more than than 1.5 degrees FF above 1.5 degrees above Tref Tref 2.4.3 Annunciators AilllUnciators 1.
- 1. B 4/4, TAVG/TAVG - TREF DEVIATION
- 2. B 4/5, RCS HIILOHI/LO TAVG
- 3. B 6/3, POWER RANGE OVERPOWER ROD STOP 2.5 Control Bank D Demanded Past 230 Steps Steys 2.5.1 Control Bank D group demand step counters indicate greater than 230 steps.
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Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0NOP-028 Reactor Control System Malfunction 11/11/04 3.0 AUTOMATIC ACTIONS 3.1 Immovable RCC 3.1.1 None 3.2 Failure of an RCC Control Bank to Insert with Reactor Control in Automatic 3.2.1 Charging pump flow decrease in response to increasing pressurizer level. 3.3 Continuous Insertion of an RCC Control Bank 3.3.1 Charging pump flow increase 3.3.2 Actuation of the pressurizer heaters 3.3.3 Pressurizer low pressure reactor trip 3.4 Continuous Withdrawal of an RCC Control Bank 3.4.1 OPAT OP~T reactor trip 3.4.2 OTAT OT~T reactor trip 3.4.3 Power range high flux level reactor trip 3.4.4 Charging pump flow decrease 3.4.5 Pressurizer spray valves open on increasing pressurizer pressure. 3.5 Control Bank D Demanded Past 230 Steps 3.5.1 None W97:/JWB/dtlev/ev W97:/JWB/dtJev/ev
Procedure No.:
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Page: Page: 9 Approval Date: 3-ONOP-028 3-0NOP-028 Reactor Control System Malfunction 11111104 11/11/04 CAUTIONS
** If the Rod Control System is inoperable due to Urgent Failure or other cause, the Shift Manager shall be notified immediately.
** If a transient occurs and the Reactor cannot be stabilized by borationldilution boration/dilution or changes in turbine load, the Reactor shall be tripped and a transition made to 3-EOP-E-O, REACTOR TRIP OR SAFETY INJECTION INJECTION..
NOTES a II . . Boration/dilution or changes in turbine load will effect shutdown margin and axial Borationldilution I offset. If plant conditions permit, the Shift Manager shall be consulted for methods used to achieve and maintain stable plant conditions. I
- Failure of RCC(s) to move when demanded, (e.g., ROD CONTROL URGENT i I
- inoperabiity of the associated RCC(s). The requirements of FAILURE), constitutes inoperability I T.S. 3.1.3.1 apply.
I I 4.0 IMMEDIATE ACTIONS 4.1 Immovable RCC hnmovable 4.1.1 IF the Rod Motion Control Selector is in Auto, THEN place in the MAN position. 4.1.2 DO NOT withdraw any control banks until the RCC(s) have been aligned. 4.2 Failure of an RCC Control Bank to Insert with Reactor Control in Automatic 4.2.1 Place the Rod Motion Control Selector switch to the MAN position. 4.3 Continuous Insertion of an RCC Control Bank 4.3.1 Place the Rod Motion Control Selector switch to the MAN position. 4.3.2 IF RCC control cannot be maintained manually, THEN trip the Reactor and Turbine and go to 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION. 4.4 Continuous Withdrawal of an RCC Control Bank 4.4.1 Place the Rod Motion Control Selector switch to the MAN position. 4.4.2 IF RCC control cannot be maintained manually, THEN trip the Reactor and Turbine and go to 3-EOP-E-0, 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION. 4.5 Control Bank D D Demanded Demanded Past 230 Steps 4.5.1 None W97:/JWB/dtlev/ev W97:/JWB/dtJev/ev
Procedure No.: Procedure
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Page: 10 Approval Date: 3-ONOP-028 3-0NOP-02S Reactor Control System Malfunction 11/11/04 11111104 5.0 SUBSEQUENT ACTIONS 5.1 Immovable RCC 5.1.1 DO . NOT increase reactor power without perrmSSIOn permission from the Reactor I Engineering Supervisor and the Shift Manager. 5.1.2 Maintain steady state condition as follows:
- 1. Maintain Tavg equal to Tref.
- a. Borate/dilute as necessary OR
- b. Change turbine load as necessary.
- 2. IF possible, THEN avoid insertion of the control rods.
5.1.3 Notify the following:
- 1. Reactor Engineering Supervisor or designee.
- 2. I&C Supervisor to verify RPI indication and to investigate CRDM System for possible failure.
5.1.4 IF one or more RCC is inoperable due to being immovable because of excessive Tiction or mechanical interference OR known to be untrippable, THEN proceed mction as follows:
- 1. Determine that the shutdown requirement of Technical Specification 3.1.1.1 satisfied within 11 hour AND; is satisfied
- 2. Be in Hot Standby within 6 hours, in accordance with 3-GOP-103, Power Operation to Hot Standby.
5.1.5 WHEN more than one full length rod is inoperable Q OR misaligned from the position by more than plus or minus 12 steps, AND group step counter demand positIOn RTP is greater than 90 percent, THEN within 11 hour, perform the following:
- 1. Restore all indicated rod positions to within the Allowed Rod Misalignment (plus or minus 12 steps),
OR
- 2. Reduce RTP to less than 90 percent AND confirm that all indicated rod Misalignment (plus or minus 18 steps),
positions are within the Allowed Rod MIsalIgnment OR
- 3. Be in Hot Standby within 6 hours.
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Procedure No.: Procedure No.; Procedure
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Procedure
Title:
Page: Page: 11 11 Approval Date: Approval Date: 3-ONOP-028 3-0NOP-028 System Malfunction Reactor Control System 11/11104 11/11/04 5.1.6 WHEN more than one full le~gth length rod is inoperable OR misaligned from the group step counter demand posItIOnposition by more than plus or minus 18 18 steps AND RTP is equal to or less than 90 percent, THEN within 11 hour perform the following:
- 1. Restore all indicated rod positions to within the Allowed Rod Misalignment (plus or minus 18 steps),
OR
- 2. Be in Hot Standby within 6 hours.
5.1.7 WHEN one RCC is trippable but inoperable due to causes other than addressed in Step 5.1.4, THEN power operation may continue provided that within 11 hour:
- 1. The RCC is restored to an operable status OR
- 2. The RCC is declared inoperable and the remainder of the RCCs in the bank with the inoperable RCC are aligned to within 12 steps with power greater than 90 percent RTP, OR within 18 steps when power is less than or equal to 90 percent RTP of the inoperable rod while not exceeding the rod sequence AND insertion limits using the Plant Curve Book, Section VII Figure 33 AND,
- a. The thermal power level shall be restricted in accordance with Technical Specification 3.1.3.6 during subsequent operation, OR
- 3. The RCC is declared inoperable and the shutdown margin requirement of Technical Specification 3.1.1.1 is satisfied. Power operation may then continue provided that:
- a. The thermal power level is reduced to less than or equal to 75 percent within 11 hour, and within the next 4 hours the power range high neutron flux trip setpoint is reduced to less than or equal to 85 percent of rated thermal power, AND;
- b. The shutdown margin requirement of Technical Specification 3.1.1.1 is determined at least once per 12 hours, AND;
- c. A power distribution map is obtained from the incore movable F,mN are verified to be within the limits within detectors and FQ(Z) and FZHN 72 hours, AND;
- d. A re-evaluation of each accident analysis listed in Enclosure 11 is performed within 55 days to confirm the previously analyzed results of these accidents remain valid under these conditions.
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ProcedureNo.: Procedure No.:
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Procedure
Title:
Procedure Page: Page: 12 12 Approval Approval Date: Date: 3-ONOP-028 3-0NOP-028 Reactor Control Reactor Control System System Malfunction Malfunction 11/11/04 11/11/04 5.1.8 5.1.8 Mode 33 or Mode or 44 - Within
- Within 11 hour hour after after detection detection of of an an inoperable inoperable control control rod(s) rod(s) and and at at least once least once per 12 hours per 12 hours thereafter thereafter while while the the rod(s) rod(s) isis inoperable inoperable the the shutdown shutdown margin shall margin shall be determined to be determined to be be greater greater than than or or equal equal toto 11 percent percent LlkIk.
Ak/k. 1.
- 1. IF the IF inoperable rod the inoperable rod is is immovable immovable or or untrippable, untrippable, THEN THEN the the shutdown shutdown margin shall shall be be increased increased by boron boron addition addition toto compensate compensate for for the the withdrawn worth of the immovable of the immovable or or untrippable control control rod.
5.1.9 5.1.9 Mode 5 - Within 11 hour after detection of an inoperable control rod(s) and at least Mode - once per 12 12 hours thereafter while the RCC(s) is inoperable the shutdown margin shall be determined to be greater than or equal to 11 percent L1kIk. shall Ak/k.
- 1. IF the inoperable control rod is immovable or untrippable, THEN the shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable RCC.
5.1.10 At the discretion of the Shift Manager, attempt to move one RCC at a time as I follows:
- 1. Obtain permission from the Reactor Engineering Supervisor or designee.
- 2. Place all the lift coil disconnect switches for the misaligned rod bank to the disconnect position (toggle switch down) EXCEPT the immovable rod switch which is left in the connect position (toggle switch up) up)..
r --- NOTE 1 I The ROD CONTROL URGENT FAILURE, B 9/4 and the RCC power cabinet URGENT FAILURE will alarm for the group with the lift coils disconnected. The RCC(s) in the cabinet with the Urgent Failure shall be considered inoperable until the system is restored to normal and the Shift Manager determines the RCC(s) to be operable. I
~-----------------------~
- 3. Position the Rod Motion Control Selector switch to the RCC bank which has the immovable RCC.
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Procedure No.: Procedure Procedure
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Procedure
Title:
Page: Page: 13 Approv& Date: Approval 3-ONOP-028 3-0NOP-028 Reactor Control System Malfunction 11111/04 11/11/04 (Contd) 5.1.10 (Cont'd)
- 4. Record the step position for the immovable RCC group step counter in the I Unit Narrative Log as follows:
a. a. Bank Bank
- b. Group c.
c. Position Position ______ steps
- 5. Attempt to move the RCC by placing the Rod Motion Lever to the IN/OUT position, as applicable:
- a. IF the RCC moves, THEN:
(1) IF the RCC is to be inserted, THEN adjust Turbine load to maintain Tref equal to Tavg. (2) IF the RCC is to be withdrawn, THEN borate as necessary to maintain steady state Reactor power. (3) Align the RCC with the rest of the bank.
- 6. Place all lift coil disconnect switches to the connect position (toggle switch up).
- 7. Manually set the associated group step counter to the position recorded in Substep 5.1.10.4.
------------~g----------~
NOTE I I The Pulse Analog Converter is located in the Control Room in Rod Position Detector and I I Bistable Assemblies Rack OR-70. QR-70. I
~-----------------------~
a a _I
- 8. IF the immovable RCC is in a control bank, THEN reset the Pulse Analog Converter as follows:
- a. Place the Automatic/Manual AutomaticlManual switch to the MANUAL Position.
- b. Place the Bank Position Display switch to the immovable rod bank.
- c. Pulse the Up/Down switch to obtain a position recorded In in Substep 5.1.10.4.
- d. Return the Automatic/Manual AutomaticlManual switch to the AUTOMATIC position.
- e. Place the Bank Position Display switch in the DISPLAY OFF position.
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Procedure No.: Procedure
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Page: 14 Approval Date: 3-0NOP-028 Reactor Control System Malfunction 4/12/02 5.1.11 5.1.11 IF another IF another RCC RCC is is to be moved, to be moved, THEN THEN repeat repeat Step Step 5.1.10. 5.1.10. 5.1.12 After the malfunction has has been corrected andand prior to increasing power, monitor following parameters to ensure the flux the following flux distribution is normal: 1.
- 1. Power range Power range nuclear instrumentation instrumentation - less
- less than than 33 percent difference difference between between any two detectors any detectors atat the same same elevation elevation
- 2. Core exit thermocouples - less than 10°F
- 10°F difference between any two channels at like symmetric locations
----------------------- NOTE NOTE I Performing an incore flux map is optional, at the discretion of the Reactor Engineering I L _______________________
I Supervisor. Supervisor. ~ I L _
- 3. No significant axial power shape difference from symmetric assemblies as determined by the Reactor Engineering Supervisor.
- 4. Axial flux indicators - less than 3 percent difference between any two channels 5.1.13 IF unit shutdown is required, THEN Reactor power should be reduced by decreasing Turbine Load and Boration to maintain programmed Tavg, in 3-GOP-i 03, Power Operation to Hot Standby.
accordance with 3-GOP-103, 5.1.14 WHEN the malfunction has been corrected, THEN place Rod Control I Selector Switch to MANUAL or AUTOMATIC position. I WQ7 1. IWRJdf/p.v/v W97:/JWB/dUev/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 15 15 Approval Approval Date: Date: 3-ONOP-028 3-0NOP-028 Reactor Control Reactor Control System System Malfunction Malfunction 5/31105 5/31/05 5.2 5.2 Failure of Failure of anan RCC Control Bank RCC Control Bank to to Insert Insert with Reactor Control with Reactor Control inin Automatic Automatic CAUTION CAUTION For URGENT FAILURE For URGENT FAILURE condition condition rod rod motion motion isis blocked. blocked. The The cause cause must must bebe corrected before corrected moving rods. before moving rods. Resetting Resetting the the Urgent Urgent Failure Failure prior prior to to correcting correcting could result in racheting the problem could the mechanisms when when the the RESET pushbutton is depressed. 5.2.1 DO NOT increase reactor power without permission from the Reactor Engineering Supervisor and the Shift Manager. 5.2.2 Manually position the RCC control bank to restore steady state conditions.
- 1. IF the RCC control bank will still not move, THEN maintain steady state conditions with Tavg equal to Trefby: Tref by:
- a. Borationldilution.
OR
- b. Changing turbine load.
5.2.3 Notify the following:
- 1. Reactor Engineering Supervisor or designee.
- 2. I&C Supervisor to verify RPI indication and to investigate CRDM System for possible failure.
5.2.4 Take actions required by Subsection 5.1, Immovable RCC. 5.2.5 IF unit shutdown is required, THEN Reactor power should be reduced by ~y decreasing Turbine load and boration to maintain programmed Tavg, in III accordance with 3-GOP- 103, Power Operation to Hot Standby. 3-GOP-103, 5.3 Continuous Insertion of an RCC Control Bank 5.3.1 5.3.1 Adjust rods or reduce turbine load as determined by by the Shift manager to restore I Tavg equal to Tref. 5.3.2 5.3.2 IF PT-3-446 or PT-3-447 PT-3-447 has failed, THEN THEN place place Channel Select First Stage Stage I Control Control to the operable channel. 5.3.3 5.3.3 Compare rod position Compare position to to control rod insertion limits control rod limits using the the Rod Rod Position Position Bank Bank I Recorders Recorders (VPA) (VPA) oror using using the Plant Curve the Plant Curve Book, Book, Section Section VII, VII, Figure Figure 3.3. tI\107i tAIPidf/,/s, W97:/JWB/dtJev/ev
Procedure No.: Procedure
Title:
Page: 16 Approval Date: 3-0NOP-028 Reactor Control System Malfunction 5/31105 5 .3.4 5.3.4 IF the control banks insertion IF insertion limits limits are exceeded, THEN perform the following: following: 1.
- 1. Borate at equal to or greater than 16 16 gpm using O-OP-046, CVCS - BORON CONCENTRATION CONTROL, until control rods are above the Low Limit.
- 2. Ensure compliance with Technical Specifications by performing one of the following:
- a. Restore the control banks to within the limits within 2 hours.
OR
- b. Reduce thermal power within 2 hours to less than or equal to the fraction of rated thermal power that is allowed by the bank position Plant Curve Book Section VII, Figure 3.
OR
- 3. Be in Hot Standby within 6 hours.
5.3.5 II? Power Range Channel 4 has failed, THEN perform to 3-0NOP-059.8, IF 3-ONOP-059.8, I POWER RANGE NUCLEAR INSTRUMENTATION MALFUNCTION. 5.3.6 PT-3 -447 has failed, THEN perform the following: IF PT-3-446 or PT-3-447
.- - - - - - - - - - - -NOTE NOTE - - - - - - - - - - -.I A few minutes needs to elapse between the time First Stage Pressure is transferred and Rod Control is returned to Automatic. This will preclude the possibility of the power mismatch circuitry causing undesired rod motion.
I I_.
~-----------------------~
a
- 1. Verify Channel Select First Stage Press Control has been placed to an operable channel AND place the Rod Motion Control Selector switch in AUTO.
- 2. 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY Perform 3-0NOP-049.1, I RELATED OR REACTOR PROTECTION CHANNELS.
5.3.7 Check TI-3-412D, 422D, 432D for possible indication of a failure of TM-408, Medium Signal Selector. IF a failure is indicated, THEN notify I&C and refer to 3-ONOP-049.l, Deviation or Failure of Safety Related Reactor Protection 3-0NOP-049.1, Channels. 5.3.8 Place a caution tag on the Rod Control Selector switch stating that placing rods in auto may result in undesired rod motion until the system is restored to normal. (N/A if rods were restored to AUTO.) 5.3.9 Notify I&C of the problem with the Rod Control System. W97:lJWBldtIevlev W97:/JWB/dtJev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 17 17 Approval Approval Date: Date: 3-ONOP-028 3-0NOP-028 Reactor Control Reactor Control System System Malfunction Malfunction 5/31105 5/31/05 5.4 5.4 Continuous Withdrawal Continuous Withdrawal of of an an RCC RCC Control Bank Control Bank 5.4.1 5.4.1 Adjust rods Adjust rods to to maintain maintain Tavg Tavg equal equal to to Tref. Tref. 5.4.2 5.4.2 Notify I&CI&C Department Department toto investigate investigate failure failure of of the the rod rod control control system. system. 5.4.3 5.4.3 Operate rods in manual Operate manual until cause of rod control system failure failure has been been found and corrected. 5.4.4 5.4.4 Place a caution tag on the Rod Control SelectorSelector switch switch stating that placing rods in auto may result in auto in undesired rod motion until the system system is restored to normal. 5.5 Control Bank D Demanded Past 230 Steps CAUTION Demanding RCC(s) to step past 230 230 steps may cause failure of the stationary gripper(s) and result in a misaligned, partially inserted or dropped rod. 5.5.1 Check for indications of misaligned or dropped RCC(s). 5.5.2 IF a RCC(s) is determined to be misaligned, THEN go to 3-0NOP-028.1, 3-ONOP-028.1, RCC MISALIGNMENT. 5.5.3 IF a RCC(s) is determined to be dropped, THEN go to 3-0NOP-028.3, 3-ONOP-028.3, DROPPED RCC. 5.5.4 Manually set both Control Bank D group demand step counters to 230 steps. r-----------NOrE----------. r NOTE 1 I II The Pulse Analog Converter is located in the Control Room in Rod Position Detector and I Bistable Assemblies Rack QR-70.OR-70. I I 5.5.5 Reset the Pulse Analog Converter as follows: 1.
- 1. Place the Bank Position Display Display switch to Control Bank D.
- 2. Place the Automatic/Manual AutomaticlManual switch to the MANUAL position.
3.
- 3. Pulse the DOWN switch to obtain a reading of 230.
of230.
- 4. Place the Automatic/Manual Place Automatic/Manual switch to AUTOMATIC.
5.
- 5. Place the Bank Place Bank Position Display Display switch to DISPLAY DISPLAY OFF. OFF.
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Procedure No.: Procedure
Title:
Page: 18 Approval Date: 3-0NOP-028 Reactor Control System Malfunction 5/31105
------------------------- NOTE NOTE LII The Bank Overlap Bank Overlap Counter The Counter is is located in 3B located in MCC Room 3B MCC Room inin the the Rod Rod Control Control Logic Logic Cabinet.
Cabinet. ~ L 5.5.6 5.5.6 Reset the Reset the Bank Bank Overlap Overlap Counter Counter as as follows: follows: 1.
- 1. Depress the Minus pushbutton to obtain a reading of 614.
Depress 5.5.7 5.5.7 Verify the Rod Motion Control Selector switch switch is is in MAN. 5.5.8 Insert Control Bank D to All Rods Out as defined in the Core Operating Limits I Report OR other position as directed by the Shift Manager. 5.5.9 Place Rod Control Selector Switch to MANUAL or AUTOMATIC AUTOMATIC position. WQ7I. IWR/dt/v/iv W97:/JWB/dtJev/ev
Procedure No.: Procedure
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Page: 19 Approval Date: 3-0NOP-028 Reactor Control System Malfunction 5/31105 6.0
6.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCES/RECORDS REQUIRED/COMMITMENT DOCUMENTS DOCUMENTS 6.1 References 6.1.1 Technical Specifications 1.
- 1. Section 3/4.1.1, Section 3/4.1.1, Reactivity Control System System - Shutdown
- Shutdown Margin
- 2. Section 3/4.1.3, Reactivity Control Systems - Movable Control Assemblies
- 3. Section 3/4.2.1, Power Distribution Limits - Axial Flux Difference
- 4. Section 3/4.2.3, Power Distribution Limits - Nuclear Enthalpy Rise Hot Channel Factor
- 5. Section 3/4.2.4, Power Distribution Limits - Quadrant Power Tilt Ratio 6.1.2 FSAR
- 1. Section 14.1.2, Uncontrolled RCCA Withdrawal at Power
- 2. Section 14.1.4, Rod Cluster Assembly (RCCA) Drop 6.1.3 Plant Procedures
- 1. O-ADM-555, Reactivity Management 0-ADM-555,
- 2. 3-ARP-097.CR, Control Room Annunciator Response - Panel B -
- 3. 3-GOP-103, 3-GOP-I03, Power Operation to Hot Standby
- 4. 3-ONOP-049. 1, Deviation or Failure of Safety Related or Reactor Protection 3-0NOP-049.1, Channels
- 5. 3-ONOP-059.4, 3-0NOP-059.4, Excessive Axial Flux Difference
- 6. 3-ONOP-059.8, 3-0NOP-059.8, Power Range Nuclear Instrumentation Malfunction
- 7. 3-OSP-028.6, 3-0SP-028.6, RCCA Periodic Exercise
- 8. O-OSP-040.5, O-OSP-040.5, Nuclear Design Verification Verification W97:/JWB/dtlev/ev W97:/JWB/dtJev/ev
Procedure No.: Procedure
Title:
Page: 20 Approval Date: 3-0NOP-028 Reactor Control System Malfunction 5/31105 6.1.4 6.1.4 Plant Curve Plant Curve Book,Book, Unit Unit 33 1.
- 1. Section VII, Section Figure 3, VII, Figure Control Rod 3, Control Rod Insertion Insertion Limits Limits (graph)
(graph) 6.1.5 6.1.5 INPO INPO 1.
- 1. SOER 84-2 SOER 84-2 (1,2, (1,2, and and 8), Control Rod 8), Control Rod Mispositioning Mispositioning
- 2. Mispositioning - Addendum SOER 84-2, Control Rod Mispositioning -
6.2 Records Required Records 6.2.1 Completed copies of the below listed item(s) constitute Quality Assurance records and shall be transmitted to QA Records for retention in accordance with Quality requirements: Assurance Records Program requirements: 1.
- 1. None 6.3 Commitment Documents Commitment 6.3.1 None END OF TEXT W97/JWB/dt/ev/ev W97:/JWB/dUev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 21 21 Approval Approval Date: Date: 3-ONOP-028 3-0NOP-028 Reactor Control Reactor Control System System Malfunction Malfunction 5/31/05 5/31/05 ENCLOSURE 11 ENCLOSURE (Page 11 of (Page of 1) 1) ACCIDENT ANALYSES REQUIRING REQUIRING RE-EV ALUATION RE-EVALUATION IN THE EVENT OF AN IN AN INOPERABLE INOPERABLE RCC RCC Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Control Assembly Misalignment Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in Large Pipes Which Actuates the Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal at Full Power Major Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident) Major Secondary Coolant System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) FINAL PAGE W97:/JWB/dt/v/v W97:/JWB/dUev/ev
1** Appendix C Job Performance Measure Form ES-C-1 ES-C-I Worksheet Facility: Turkey Point ____________
-=T~u~rk~e~y~P~o~i~nt~ Task No:
Test the Source RangeRange NIS MS Job Performance Task
Title:
Channel (Shutdown) Measure No: _S.::.y~s:..:te::::..:m..:...:..::..s_--.::d=-- Systems d ____________ 015 A4.02 (3.9/3.9) K/A
Reference:
KIA 015 A4.03 (3.8/3.9) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulator
-=~==~-------------------------------------------------------
Simulated Performance Actual Performance Yes
-------------------- ----------~~---------
Classroom Classroom Simulator ------.....:....::=-=------- Yes Plant _________ Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Unit 3 is in Mode 4 for a short notice outage
- 2. The Shift Manager has authorized performance of 3-0SP-059.1, 3-OSP-059.1, "SourceSource Range Nuclear Operationa) Test" Instrumentation Analog Channel Operational Test for channel N-32
- 3. You are relieving the RO who has successfully completed 3-0SP-059.1, 3-OSP-059.1, Section 7.3.2 through step 7.3.2.16
- 4. N-32 reads 90 counts per second at the start of the test
- 5. Containment access doors are closed and no personnel are inside containment Task Standards:
- 1. Setpoints are verified to be within specification
- 2. Protective actuations verified
- 3. Tested channel returned to normal following completion of the surveillance Required Materials:
- 1. 3-OSP-059.1 3-0SP-059.1 General
References:
3-OSP-059.1
- 1. 3-0SP-059.1 1.
Initiating Cue: Shift Manager permission has been granted to continue with the surveillance on source range detector channel N-32, starting at step 7.3.2.17 of 3-OSP-059.1 3-0SP-059.1 Time Critical Task: Yes/No Validation Time: 20 minutes
Appendix C Appendix C Page 22 of Page of 99 Form Form ES-C-1 ES-C-I INSTRUCTIONS TO INSTRUCTIONS TO OPERA OPERATOR TOR READ TO READ TO OPERA OPERA TOR: TOR: WHEN II TELL WHEN TELL YOU YOU TO TO BEGIN, BEGIN, YOU YOU AREARE TOTO PERFORM PERFORM THE ACTIONS AS THE ACTIONS AS DIRECTED DIRECTED IN IN THE THE INITIATING INITIATING CUES. II WILL CUES. WILL DESCRIBE DESCRIBE THETHE GENERAL GENERAL CONDITIONS CONDITIONS UNDER UNDER WHICH WHICH THIS THIS TASK TASK IS IS TO TO BE BE PERFORMED PERFORMED AND PROVIDE AND PROVIDE THE THE NECESSARY NECESSARY TOOLSTOOLS WITH WITH WHICH WHICH TO PERFORM THIS TO PERFORM THIS TASK. TASK. BEFORE BEFORE STARTING, STARTING, II WILL EXPLAIN WILL EXPLAIN THETHE INITIAL INITIAL CONDITIONS, CONDITIONS, WHICHWHICH STEPS STEPS TOTO SIMULATE SIMULATE OR OR DISCUSS, DISCUSS, ANDAND PROVIDE PROVIDE INITIATING CUES. INITIATING CUES. WHEN WHEN YOU YOU COMPLETE COMPLETE THE THE TASK TASK SUCCESSFULLY, SUCCESSFULLY, THE THE OBJECTIVE OBJECTIVE FORFOR THIS THIS JOB JOB PERFORMANCE PERFORMANCE MEASURE MEASURE WILL WILL BEBE SATISFIED. SATISFIED. HAND JPM HAND JPM BRIEFING BRIEFING SHEET SHEET TO TO OPERATOR OPERATOR AT THIS THIS TIME! TIME! INITIAL CONDITIONS: CONDITIONS: 1.
- 1. Unit 3 is in Mode 4 for a short 3 short notice outage Shift Manager
- 2. The Shift Manager has has authorized performance performance of 3-0SP-059.1, 3-OSP-059.1, "Source Source Range Range Nuclear Nuclear Instrumentation Analog Channel Instrumentation Channel Operational Operational Test" Test for channel channel N-32 N-32
- 3. You are relieving the RO who has successfully completed 3-0SP-059.1,3-OSP-059.1, Section 7.3.2 through step 7.3.2.16
- 4. N-32 reads 90 counts per second at the start of the test
- 5. Containment access doors are closed and no personnel are inside containment INITIATING INITIA TlNG CUE:
Shift Manager permission has been granted to continue with the surveillance on source range detector channel N-32, starting at step 7.3.2.17 of 3-0SP-059.1. 3-OSP-059.1. TERMINATION TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. NOTES TO EVALUATOR AND IIF I/F OPERATOR: 10-140. If IC-140
- 1. Reset simulator to IC-14 or IC-140. lC-140 used, skip ahead to step 10.
- 2. Unit 3 3 is in Mode 4.
- 3. Place simulator in run.
- 4. Verify the NR-45 console recorders are displaying N31/N32 & N35/N36.
- 5. Adjust N-32 high flux at shutdown setpoint inside N-32 drawer to 300 counts per seconds. Refer to 3-OSP-059.6 as required.
- 6. Verify the N-32 level trip switch is in BYPASS.
- 7. Verify the N-32 high flux at shutdown switch is in BLOCK.
- 8. Acknowledge alarms and freeze simulator.
- 9. Store temporary IC if needed for repeat runs of this JPM.
- 10. Mark placards above N-31 &
- 10. & N-32 shutdown setpoint ==300 cps and todays N-32 with high flux at shutdown today's date.
- 11. Hang shutdown
- 11. Hang shutdown placards placards on on the the following valves:
** MOV-3-843NB MOV-3-843A/B ** MOV-3-866A1B MOV-3-866A/B ** MOV-3-869 MOV-3-869 ** MOV-3-865A!BIC MOV-3-865A/B/C
I Appendix C Page 3 of 9 ES-C-I I Form ES-C-1 Denote critical steps with a check mark Start Time Obtained procedure STEP 1 1 :
- - SAT
- - UNSAT STANDARDS: 1. 3-OSP-059.1 obtained Procedure 3-0SP-059.1
- 2. 3-OSP-059.1 Precautions & Limitations reviewed before continuing 3-0SP-059.1 CUE: A marked up copy of 3-0SP-059.1 3-OSP-059.1 shall be provided to the operator.
Level adjust potentiometer position verified STEP 2 :
- - SAT
- - UNSAT STANDARD: Level adjust potentiometer verified in the full counterclockwise position.
Operation selector switch positioned STEP 3 : - - SAT
- - UNSAT STANDARD: Operation selector switch positioned to the LEVEL ADJ position NOTE: Annunciator B-7/3 alarms (NIS CHANNEL IN TEST)
Tested high flux at shutdown alarm STEP 4 : - - SAT UNSAT STANDARDS: NOTE: Containment evacuation alarm announcement nla n/a 1
-.J 1. Placed high flux at shutdown switch to NORMAL
- 2. Verified annunciator B-4/2 (SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED) off
, 3. Turned Level Adj potentiometer slowly clockwise until N-32 drawer
-.J HI FLUX AT SHUTDOWN status light on
- 4. Recorded High Flux at Shutdown bistable trip point, N-32 (Source Range CPS) on Attachment 2
- 5. Verified N-32 drawer HIGH FLUX AT SHUTDOWN status light on
- 6. Verified annunciator B-4/1 (SOURCE RANGE HI FLUX AT SHUTDOWN) on
Appendix C of 9 Page 4 of9 ES-C-I Form ES-C-1 High flux at shutdown switch alignment restored STEP 5 : -- SAT
- - UNSAT STANDARDS: NOTE: Containment evacuation alarm verification n/a J
..J 1. Level Adj potentiometer turned slowly counterclockwise until the N-32 drawer HIGH FLUX AT SHUTDOWN status light turns off
- 2. Recorded High Flux at Shutdown bistable reset point, N-32 (Source Range CPS) on Attachment 2
- 3. Verified N-32 drawer HIGH FLUX AT SHUTDOWN status light turns off
- 4. Verified annunciator B-4/1 (SOURCE RANGE HI FLUX AT SHUTDOWN) off Verified Enclosure 1 1 acceptance criteria met STEP 6 : SAT UNSAT STANDARD: NOTE: Containment evacuation alarm verification n/a J
..J Verified high flux at shutdown acceptance criteria for alarm and reset met per Enclosure 1 1 Blocked high flux at shutdown signal STEP 7 : --
SAT
- - UNSAT STANDARDS:
1..J 1. Placed high flux at shutdown switch to BLOCK
- 2. Verified annunciator B-4/2 (SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED) on NOTE: Containment evacuation alarm announcement n/a
I Appendix C Page 5 of 9 ES-C-I I Form ES-C-1 STEP 8 : Determined Level Trip bistable setpoint SAT UNSAT STANDARDS: q
..J 1. Turned Level Adj potentiometer slowly clockwise until N-32 drawer LEVEL TRIP status light on
- 2. Recorded Level Trip bistable trip point, N-32 (Source Range CPS) on Attachment 2
- 3. SOURCE RANGE HI FLUX NC32D VPB status light verified on Level Trip switch alignment restored STEP 9 : SAT
- - UNSAT STANDARDS:
q
..J 1. Level Adj potentiometer turned slowly counterclockwise until the N-32 drawer LEVEL TRIP status light turns off
- 2. Recorded Level trip bistable reset point, N-32 (Source Range CPS) on Attachment 2
- 3. SOURCE RANGE HI FLUX NC32D VPB status light verified off Verified Attachment 2 acceptance criteria met STEP 10 : --
SAT UNSAT STANDARD: J..J Verified level trip acceptance criteria for alarm and reset met per Attachment 2 Level Adj potentiometer returned to normal position STEP 11 11 : -- SAT UNSAT STANDARD: J..J Turned Level Adj potentiometer fully counterclockwise
Appendix C of 9 Page 6 of9 ES-C-I Form ES-C-1 STEP 12 : Returned N-32 drawer to normal
- - SAT
- - UNSAT STANDARD:
~J Placed N-32 Operation Selector switch in NORMAL N-32 conditions verified as returned to normal STEP 13 :
- - SAT UNSAT STANDARDS: 1. Verified N-32 count rate returned approximately to value observed at start of test (90 cps)
- 2. Verified N-32 drawer status lights returned to normal
- a. INSTRUMENT POWER ON status light on
- b. CONTROL POWER ON status light on
- c. CHANNEL ON TEST status light off
- d. LOSS OF DETECTOR VOL VOLT.
T. status light off
- e. LEVEL TRIP status light off
- f. HIGH FLUX AT SHUTDOWN status light off
- g. BISTABLE TRIP SPARE status light off
- 3. Verified annunciator B-7/3, B-713, NIS CHANNEL IN TEST not alarming STEP Returned N-32 switches on drawer to normal 14 - - SAT UNSAT STANDARDS:
J~ 1. Placed N-32 drawer High Flux at Shutdown switch in NORMAL
- 2. B-4!2, SOURCE RANGE HI FLUX AT Verified annunciator B-4/2, SHUTDOWN BLOCKED not alarming J~ 3. Placed N-32 drawer Level Trip Switch switch in NORMAL
- 4. Verified N-32 drawer LEVEL TRIP BYPASS status light off
- 5. Verified VPA N-32 IN BYPASS status light off
- 6. Verified annunciator B-814, B-8/4, NIS TRIP BYPASSED not alarming
I Appendix Appendix CC Page 77 of Page of 99 Form Form ES-C-1 ES-C-I I Returned console NR-45 recorders to normalnormal forfor mode mode 44 STEP STEP 15 15 : Returned console NR-45 recorders to SAT
- - SAT
- - UNSAT UNSAT STANDARD:
STANDARD: Verified highest Verified highest reading reading SR SR && IR IR nuclear nuclear instruments instruments displayed displayed on on console NR-45 console NR-45 recorders recorders NOTE: Requirement NOTE: Requirement forfor audio audio count count rate selected to rate selected to operable operable channel channel n/a in n/a in mode mode 44 Terminating Terminating 3-OSP-059.I section 7.3.2 3-0SP-059.1 7.3.2 completed completed STOP STOP Cue: Cue: Stop Time
Appendix C Appendix C Page 88 of Page of 99 Form ES-C-1 Form ES-C-I Verification of of Completion Completion Job Performance Performance Measure Measure No. No. _S"'-ys_t'--e Systems m....::s_-_dd_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Examinees Name: Examinee's Examiners Name: Examiner's Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiners Examiner's signature signature and and date: date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
JPM BRIEFING SHEET CONDITIONS: INITIAL CONDITIONS:
- 1. Unit 3 is in Mode 4 for a short notice outage 1.
3-OSP-059.1, "Source
- 2. The Shift Manager has authorized performance of 3-0SP-059.1, Source Range Nuclear Test for channel N-32 Instrumentation Analog Channel Operational Test" 3-OSP-059.1, Section 7.3.2 through step
- 3. You are relieving the RO who has successfully completed 3-0SP-059.1, 7.3.2.16
- 4. N-32 reads 90 counts per second at the start of the test
- 5. Containment access doors are closed and no personnel are inside containment INITIATING INITIA TlNG CUE:
Shift Manager permission has been granted to continue with the surveillance on source range detector 3-OSP-059.1. channel N-32, starting at step 7.3.2.17 of 3-0SP-059.1. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 ci. c 3-0SP-059.1 - o)
Title:
Source Range Nuclear Instrumentation Analog Channel Operational Test Safety Related Procedure Responsible Department: Operations Revision Approval Date: 4/1/040 4/1/04C RTSs 88-0382P, 89-0472, 89-0672P, 90-0997, 91-1364W, 92-1718P, 93-1178P, 96-1090P, 97-1315, 98-1096P, 99-0478P, 03-0217P, 04-0288P OTSCs 5161, 0442-94, 0422-01 PC/Ms 90-508,93-047,02-085 PCIMs 90-508, 93-047, 02-085 W97:/TNM/dtlmrg/mrg W97:ITNM/dt/mrg/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 22 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 4/1104C 4/1104C LIST OF EFFECTIVE PAGES Revision Revision Page Date Date Page Date Date 11 04/01/04C 04/01l04C 21 04/01104 04/01/04 2 04/01/04C 04/01l04C 22 04/01104 04/01/04 3 09/16/01 09/16/01 23 09/16/01 09/16/01 4 09/16/01 09/16101 24 09/16/01 5 03/26/03 25 09/16/01 09/16/0 1 6 09/16/01 26 09/16/01 7 09/16/01 27 09/16/01 8 03/26/03 28 09/16/01 09/16/0 1 9 09/16/01 29 09/16/01 10 09/16/O1C 09/16/01C 30 09/16/01 11 09/16/01 31 09/16/01 12 09/16/01 32 09/16/O1C 09/16/01C 13 09/16/01 33 09/16/O1C 09/16/01C 14 04/01/04 04/01104 34 09/16/01 15 09/16/01 35 09/16/O1C 09/16/01C 16 03/26/03 36 09/16/O1C 09/16/01C 17 09/16/01 37 09/16/01 18 09/16/O1C 09/16/01C 38 09/16/O1C 09/16/01C 19 09/16/01 39 09/16/01 20 09/16/01 40 09/16/01 41 09/16/O1C 09/16/01C 42 09/16/01 43 09/16/01 W97:ITNM/dtlmr Imr
ProcedureNo.: Procedure No.:
Title:
ProcedureTitle: Procedure Page: Page: 33 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 TABLE OF TABLE OF CONTENTS CONTENTS Section Section Page 1.0 1.0 PURPOSE PURPOSE..................................................................................................................... 44 2.0
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCES/RECORDS REQUIRED/COMMITMENT DOCUMENTS........ DOCUMENTS 44 3.0 3.0 PREREQUISITES PREREQUISITES....................................................................................................... 66 4.0 PRECAUTIONS/LIMITATIONS PRECAUTIONS/LIMITATIONS.............................................................................. 66 5.0 TOOLS/EQUIPMENT SPECIAL TOOLS/EQUIPMENT............................... ............................................... 6 6.0 ACCEPTANCE CRITERIA....................................................................................... CRITERIA 6 7.0 PROCEDURE PROCEDURE.............................................................................................................. 7 ENCLOSURE/ATTACHMENTS Enclosure 11 High Flux at Shutdown - Acceptance Criteria for Alarm and Reset.................
- Reset 31 Attachment 11 Source Range Channel N-3 N-311 Test Data (Shutdown) .......................... ............... 32 Attachment 2 Source Range Channel N-32 Test Data (Shutdown) ......................................... 35 Attachment 33 Source Range Channel Channel N-3 N-311 Test Data (Operating)
(Operating).......................................... 38 38 Attachment Attachment 44 Source Source Range Channel Channel N-32 N-32 Test Test Data Data (Operating) (Operating).......................................... 41 41 W97:/TNM/dtlmra/mra W97:/TNM/dtlmr Imr
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 44 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 provides the prereqUIsItes, This procedure provides prerequisites, precautions, limitations and and instructional guidance to perform the required surveillance prior to reactor reactor startup and monthly surveillance of the SourceSource Range Nuclear Instrumentation. Instrumentation. This surveillance satisfies the requirements of requirements of Reference Reference 2.1.1. 2.1.1.
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT DOCUMENTS 2.1 References 2.1.1 Technical Specifications
- 1. Section 2.2.1, Table 2.2-1, Item 4, Reactor Trip System Instrumentation Setpoints
- 2. Section 4.3.1.1, Table 4.3-1, Item 4, Reactor Trip System Instrumentation Surveillance Requirements
- 3. Section 4.9.2, Items band b and c, Refueling Operations Instrumentation Surveillance Requirements
- 4. Section 3.9.2, Refueling Operations Instrumentation 2.1.2 Final Safety Analysis Report
- 1. Section 7.2, Protective Systems
- 2. Section 7.4, Nuclear Instrumentation 2.1.3 Plant Procedures
- 1. 0-ADM-724, Instrumentation Protection Channel Determination of Channel Operability
- 2. 3-ONOP-059.5, 3-0NOP-059.5, Source Range Nuclear Instrumentation Malfunction
- 3. 0-OP-003.3, 120V 120V Vital Instrument AC System
- 4. 3-OSP-059.6, 3-0SP-059.6, High Flux at Shutdown W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 55 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 3/26/03 3/26/03 2.1.4 2.1.4 Miscellaneous Documents Miscellaneous Documents (i.e., (i.e., PCIM, PC/M, Correspondence) Correspondence) 1.
- 1. Inter-Office Correspondence, Inter-Office Correspondence, PTN-TECH-89-121, PTN-TECH-89-121, J.J. M. M. Donis Donis to to R.
R. G. G. Mende, dated Mende, dated January 31, 1989, January 31, subject: 3/4-0SP-059.1, 1989, subject: 3!4-OSP-059.1, Acceptance Acceptance Criteria Criteria For Control For Control Room Indicators Operability Room Indicators Operability of of Sources Range Channels Sources Range Channels 2.
- 2. PC/M 90-508, PCIM 90-508, Implementation Implementation of of Setpoint Setpoint Methodology Methodology
- 3. PC/M 93-047, Annunciator Dark Board PCIM
- 4. PC/M (MSP) 02-085, PCIM 02-08 5, Replace Recorder NR-45 2.2 Records Required 2.2.1 The date, time and section completed shall be logged in the Reactor Control Operator (RCO) logbook(s). Also, any problems encountered while performing the procedure should be logged (i.e., malfunctioning malfunctioning equipment, delays due to changes in plant conditions, etc.).
2.2.2 Completed copies of the below listed item(s) document the compliance with Technical Specification surveillance requirements and shall be transmitted to QA Records for retention in accordance with Quality Assurance Records Program requirements: requirements:
- 1. Section 7.0
- 2. Attachments 1, 2, 33 and 4 2.2.3 Completed copies of the below listed item(s) shall be transmitted to System Engineer for information.
- 1. Attachments 1, 1,2,3and4 2, 3 and 4 2.3 Commitment Documents Commitment 2.3.1 JPN-PTN-SE NP-94-014, Evaluation of Technical Specification Surveillance JPN-PTN-SENP-94-014, Interval on RPS and ESFAS ESF AS Hagan Rack Instrumentat Instrumentation ion Wq7ITNM/dt/mrn/mrc W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 6 Source Range Nuclear Instrumentation Source Approval Date: Approval Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Test 9/16/01 3.0 PREREQUISITES 3.1 Instrument AC Panels 3P06 and 3P07 should be powered from their nonnal normal sources per 0-OP-003.3, 120V Vital Instrument AC System, during this test. 3.2 Instrument & & Controls Department available to jumper high volts. 4.0 PRECAUTIONS/LIMITATIONS 4.1 performed on only one source range channel at a time. The channel not Tests shall be perfonned under test must be operable except as indicated in the note below. I~-----------------------I NOTE I With only one source range channel operable, the Nuclear Plant Supervisor may authorize I testing the operable channel after reviewing the applicable Action Statements of Technical Specification 3.3.1, Table 3.3-1, item 4, and Section 3.9.2. I
~------------------
a a a a a a _ _ _ _ - II a 4.2 Any nuclear instrumentation channel should be energized for at least one hour prior to being tested. 4.3 range channel should not be tested when neutron flux level changes in the source A source ~ange in progress. range are III 4.4 Discrepancies noted during this test shall be investigated for their effect on channel 3-ONOP-059.5, Source Range Nuclear Instrumentation operability and actions taken per 3-0NOP-059.5, Malfunction, as applicable. 4.5 The Nuclear Plant Supervisor shall be notified immediately if any acceptance criteria is not met or any malfunction or abnonnal abnormal conditions occur. This infonnation information shall also be recorded in the Remarks Section. 5.0 TOOLS/EQuIPMENT SPECIAL TOOLS/EQillPMENT 5.1 None 6.0 ACCEPTANCE CRITERIA 6.1 Instrumeijtation Trip Setpoint for the Source Range, Neutron The Reactor Trip System Instrumentation Flux shall be less than or equal to 10 105 CPS. W7:ITNM/dt/mra/mro W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 77 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 7.0 7.0 PROCEDURE PROCEDURE INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Started: Date/Time Started: --------------~~-------- // 7.1 7.1 Obtain pennission Obtain permission from from the the Nuclear Plant Plant Supervisor Supervisor to perform this test. to perfonn 7.2 Notify I&C to prepare to jumper high volts, Sub Substep step 7.3.1.10 and/or 7.3.2.10.
~-----------------------I I I 10 NOTE I Source Range Source Range NISNIS test methodology is test methodology is dependent dependent onon the the plant operational operational mode mode at at the the I time of performance. Only the sections applicable should be performed, the others marked I
N!A. NIA. II
~----------------- _ _ _ _ _ _ II a
7.3 Source Range Channel Testing during Mode 2, Startup (Below P-6 Interlock); Mode 3, Hot Standby; Mode 4, Hot Shutdown; Mode 5, Cold Shutdown and Mode 6, Refueling. 7.3.1 Perform testing of SOURCE RANGE N-31 as follows: Perfonn
- 1. At NIS panel, N-31 N-3 1 drawer, record the following:
- a. AVERAGE SOURCE RANGE CPS NEUTRON LEVEL ___________
LEVEL
- b. SOURCE RANGE DETECTOR VOLTS x 100 _ _ _ __
- 2. IF in Operational Mode 4, Hot Shutdown; Mode 5, Cold Shutdown or Mode 6, Refueling; THEN verify the High Flux at Shutdown alarm alann setpoint is valid for the existing Source Range Neutron Level as follows:
- a. Calculate the High Flux at Shutdown setpoint at one-half decade above SOURCE RANGE CPS NEUTRON LEVEL recorded in Substep 7.3.1.1: (MarkN/A (Mark N/A if core is off loaded) 3.16 x CPS = _____________ Alarm
= Alann CPS (1) IF core is off loaded, THEN use the High Flux at Shutdown alann setpoint that was used immediately prior to core off-load alarm AND record below:
High Flux at Shutdown alarmalann setpoint: _______________ Alarm Alann CPS CPS W97:/TNM/dtlmrci/mrcj W97:ITNM/dt/mr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 88 Source Range Source Nuclear Instrumentation Range Nuclear Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational TestTest 3/26/03 3/26/03 INITIAL S INITIALS CKD VERIF CK'D VERIF 7.3.1.2 (Cont'd) 7.3.1.2 (Contd) b.
- b. Compare the Compare the Alarm Alarm CPS from above CPS from above with with the the current current High High Flux Flux at at Shutdown alarm Shutdown setpoint utilizing alarm setpoint utilizing Enclosure Enclosure 1.1.
(1) (1) IF the IF the Alarm Alarm CPS CPS is within the is within currently set the currently set ALARM ALARM VALUE VALUE acceptance criteria, acceptance criteria, THEN THEN the alarm setpoint setpoint is satisfactory. satisfactory. (2) IF j the Alarm CPS is NOT within the currently set set ALARM VALUE acceptance criteria, THEN perform 3-0SP-059.6, 3-OSP-059.6, HIGH FLUX AT SHUTDOWN SHUTDOWN FOR SOURCE SOURCE RANGE CHANNEL N N-3 1, prior to proceeding with this procedure.
-31,
- 3. Position an NIS recorder to monitor source range N-31. N-3 1.
- 4. At AUDIO COUNT RATE CHANNEL (NIS (MS panel, N-34), place CHANNEL SELECTOR switch to SR N32.
- a. IF in Operational Mode 6 or preparing to enter Mode 6, Refueling; THEN verify audible indication in the Control Room and Containment.Containment.
- 5. At NIS panel, N-31, verify the following:
- a. INSTRUMENT POWER ON status light ON.
INSTRUMENT
- b. CONTROL POWER ON status light ON.
- c. CHANNEL ON TEST status light OFF.
- d. LOSS OF DETECTOR VOLT status light OFF.
- e. LEVEL TRIP status light OFF.
- f. LEVEL TRIP BYPASS status light OFF.
- g. HIGH FLUX AT SHUTDOWN status light OFF.
- h. BISTABLE TRIP SPARE status light OFF.
- 6. Place LEVEL TRIP switch (NIS panel, N-3 1) to BYPASS.
N-31) W97:ITNM/dtlmra/mra W97:rfNM/dVmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 99 Source Range Nuclear Source Range Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 INITIALS INITIALS CKD VERIF CK'D VERIF 7.3.1 (Cont'd) 7.3.1 (Contd) 7.
- 7. Verify the Verify the following:
following: a.
- a. LEVEL TRIP LEVEL TRIP BYPASS status status light light (NIS (NIS panel, panel, N-31)
N-3 1) ON. ON.
- b. N-3 1 IN BYPASS status light (VPA) ON.
N-31
- c. Annunciator B 8/4, 8/4, NIS TRIP BYPASSED, is ON.
8.
- 8. Place HIGH FLUX AT SHUTDOWN SHUTDOWN switch (NIS (MS panel, N-31) to BLOCK.
- 9. Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is ON.
- 10. Have I&C personnel perform the following steps:
10.
- a. Obtain keys for access to rear of Rack 59, open rack door.
- b. Install jumper between TB 123-1 and TB 123-2.
I&C: ____~--~~~~----__ Jumper Installed Print I&C/OPS:_______________________ I&C/OPS:---=-~_-:----=---:::-- _ __ Independent Verification Print
- 11. Verify the following:
- a. LOSS OF DETECTOR VOLT status light is ON.
- b. Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE is ON.
- 12. Place OPERATION SELECTOR switch (NIS panel, N-3 N-31)
- 1) to 60 CPS.
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Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 10 Source Range Nuclear Instrumentation Source Date: Approval Date: Approval 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Test 9/16/01C 9/16/O1C INITIALS INITIALS CKD VERIF CK'D 7.3.1 (Cont'd) (Contd)
- 13. Verify the following:
- a. CHANNEL ON TEST status light (NIS panel, N-31) N-3 1) is ON.
- b. Annunciator B 7/3, NIS CHANNEL IN TEST, is ON.
- 14. Place the OPERATION SELECTOR switch (NIS panel, N-31) N-3 1) III in the positions listed in Attachment 1, 1, recording data as indicated.
- 15. Have I&C personnel perform the following:
- a. Remove jumper installed in Sub Substepstep 7.3.1.10, between TB 123-1 and TB 123-2.
I&C: ____~--~----~__---- Jumper Removed Print I&C/OPS: I&CIO PS :---=---:--__-:-----:::-::-----,-",----_ __ Independent Verification Print
- 16. Verify the following:
- a. LOSS OF DETECTOR VOLT status light is OFF.
- b. Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE, is OFF.
- 17. Verify LEVEL AD] ADJ potentiometer (NIS panel, N-31)
N-3 1) is fully counterclockwise.
- 18. Place the OPERATION SELECTOR switch (NIS panel, N-31) N-3l) to LEVEL ADJ.
W97:ITNM/dtlmra/mro W97:/TNM/dt/mr /mr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 11 11 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 INITIALS INITIALS VERIF CKD VERIF CK'D 7.3.1 (Cont'd) 7.3.1 (Contd)
~-----------------------I I
iiOF NOTE I I Plant P.A. Plant phone announcements P.A. phone announcements concerning concerning the the containment containment Evacuation Evacuation Alarm actuation I Alarm actuation I during High Flux during High Flux at at Shutdown Shutdown alarmalarm testing testing are are necessary ifif personnel are in containment. I Th containment.
- 19. Announce distinctly over the plant P.A. phone, ATTENTION ALL 19.
PERSONNEL, THE CONTAINMENT EVACUATION ALARM IS BEING TESTED (Mark NIA if no personnel are in containment). N/A ifno
- 20. Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-31) to NORMAL.
- 21. Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is OFF (Mark NIA N/A if Annunciator B 4/2 is ON due to Source Range N-32, HIGH FLUX AT SHUTDOWN switch in BLOCK).
- 22. Adjust LEVEL AD] ADJ potentiometer (NIS panel, N-31) N-3 1) slowly clockwise until HIGH FLUX AT SHUTDOWN status light (NIS panel, N-31) turns ON.
- 23. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-3l) N-31) for High Flux at Shutdown bistable trip point on Attachment I. 1.
- b. Verify HIGH FLUX AT SHUTDOWN status light (NIS panel, N-3 N-31) 1)
is ON.
- c. Verify Annunciator B 4/1, 411, SOURCE RANGE HI FLUX AT SHUTDOWN, is ON.
- d. Verify containment Evacuation Alarm is ON. (Mark N/A NIA if no personnel are in containment).
- 24. Adjust LEVEL ADJ AD] potentiometer (NIS panel N-31) slowly counterclockwise until HIGH FLUX AT SHUTDOWN status light (NIS panel, N-31) turns OFF.
Wq7ITNM/dllmro/mro W97:ITNM/dt/mr Imr
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 12 12 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Analog Channel Operational Test Test 9/16/01 9/16/01 INITIAL S INITIALS CKD VERIF CK'D VERIF 7.3.1 (Cont'd) 7.3.1 (Contd)
- 25. Perform the following:
a.
- a. Record SOURCE SOURCE RANGE RANGE CPS CPS NEUTRON LEVEL (NIS (NIS panel, N-31) for High Flux for Flux at at Shutdown Shutdown bistable reset point onon Attachment 1. 1.
- b. Verify HIGH FLUX AT SHUTDOWN status light (NIS panel, N-31) is OFF.
- c. Verify Annunciator B 411, 4/1, SOURCE RANGE HI FLUX AT SHUTDOWN, is OFF.
- d. Verify Containment Evacuation Alarm is OFF. (Mark NI N/A A if no personnel are in containment).
- e. Verify High Flux at Shutdown bistable reset point is within acceptance criteria range of Enclosure 1.
- 26. Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-31) N-3 1) to BLOCK.
- 27. Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED is ON.
- 28. Announce distinctly over the plant P.A. phone, ATTENTION ALL PERSONNEL, THE CONTAINMENT EVACUATION ALARM TEST IS COMPLETE. (Mark NIA if no personnel are in containment).
N/A ifno
- 29. Adjust LEVEL ADJ AD] potentiometer (NIS panel, N-3N-31)1) slowly clockwise until LEVEL TRIP status light (NIS panel, N-3 N-31)
- 1) turns ON.
- 30. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-31) for Level Trip bistable trip point on Attachment 1.
- b. Verify REACTOR PROTECTION LOGIC status light (VPB),
SOURCE RANGE HI FLUX NC31D is ON. W97:/TNM/dt/mro/mro W97:ITNM/dtlmr /mr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 13 13 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 INITIALS INITIALS CKD VERIF CK'D VERIF 7.3.1 (Cont'd) 7.3.1 (Contd)
- 31. Adjust
- 31. Adjust LEVEL LEVEL AD] ADJ potentiometer potentiometer (NIS (NIS panel, N-31) N-31) slowlyslowly counterclockwise until LEVEL counterclockwise LEVEL TRIPTRIP status status light light (NIS (NIS panel, N -31)
N-3 1) turns turns OFF. OFF. following:
- 32. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-31) for Level Trip bistable reset point on Attachment 1.1.
- b. Verify REACTOR PROTECTION LOGIC status light (VPB),
SOURCE RANGE HI FLUX NC31D is OFF.
- 33. Adjust LEVEL AD] ADJ potentiometer (NIS panel, N-31) fully counterclockwise.
- 34. Place OPERATION SELECTOR switch (NIS panel, N-31) N-3 1) to NORMAL.
- 35. Verify SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-31) indication returns to approximately the CPS level recorded in Substep Sub step 7.3.1.1 of this test.
- 36. At NIS panel, N-31, verify the following:
- a. INSTRUMENT POWER ON status light ON.
- b. CONTROL POWER ON status light ON.
- c. CHANNEL ON TEST status light OFF.
- d. LOSS OF DETECTOR VOLT status light OFF.
- e. LEVEL TRIP status light OFF.
- f. HIGH FLUX AT SHUTDOWN status light OFF.
- g. BISTABLE TRIP SPARE status light OFF.
- 37. Verify Annunciator B B 7/3, NIS CHANNEL IN TEST, is OFF.
- 38. Place HIGH FLUX AT SHUTDOWN switch switch (NIS panel, N-31) N-3l) to NORMAL.
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Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 14 14 Source Range Nuclear Instrumentation Source Instrumentation Approval Date: Approval Date: 3-OSP-059.1 3-0SP-059.1 Test Analog Channel Operational Test 4/1/04 4/1/04 INITIAL S INITIALS CK'D VERIF (Contd) 7.3.1 (Cont'd)
- 39. Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is OFF (Mark N/A if Annunciator B 4/2 is ON due to Source Range N-32, HIGH FLUX AT SHUTDOWN switch in BLOCK).
- 40. Place LEVEL TRIP switch (NIS panel, N-31) N-3 1) to NORMAL.
- 41. Verify the following:
- a. LEVEL TRIP BYPASS status light (NIS panel, N-31) is OFF.
- b. N-3 1 IN BYPASS status light (VPA) is OFF.
N-31
- c. Annunciator B 8/4, NIS TRIP BYPASSED, is OFF (Mark N/A if Annunciator B 8/4 is ON due to another NIS channel in BYPASS).
I
- 42. Position the NIS recorders to monitor the highest reading source range and the highest reading intermediate range channels.
- 43. IF in Mode 6, OR preparing to enter Mode 6, THEN place the Audio Count Rate Channel Selector Switch to an operable channel.
Date/Time Completed: _ _ _ _ _ _ _ _ _/_ _ _ __ PERFORMED BY (Print) INITIALS VERIFIED BY (Print) INITIALS REVIEWED BY: _ _ _---:;-:;:--;,----::::-:;-_=--_-:--_--=:-:::-::::---:--_ __ Nuclear Plant Supervisor or SRO Designee Wq7rrNM/rff/mrn!mrn W97:fTNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 15 15 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16101 INITIALS INITIALS CK'D VERIF CKD VERIF Date/Time Date/Time Started: Started: _ _ _ _ _ _ _--.!....//_ _ _ __ 7.3.2 7.3.2 Perform testing Perform testing ofof SOURCE SOURCE RANGE RANGE N-32 N-32 as follows: as follows: 1.
- 1. At NIS At MS panel, N-32 N-32 drawer, drawer, record the the following:
following:
- a. AVERAGE SOURCESOURCE RANGE CPS NEUTRON LEVEL ___________
LEVEL
- b. DETECTOR VOLTS x 100 SOURCE RANGE DETECTOR 100 _ _ __
- 2. IF in Operational Mode 4, Hot Shutdown; Mode 5, Cold Shutdown or Mode 6, Refueling; THEN verify the High Flux~ Flux at Shutdown alarm setpoint is valid for the existing Source Range Neutron Level as follows:
- a. Calculate the High Flux at Shutdown setpoint at one-half decade above SOURCE RANGE CPS NEUTRON LEVEL recorded in Substep N/A 7.3.2.1: (Mark N/ off loaded)
A if core is offloaded) x CPS = _ _ _ _ _ _ _ _ _ Alarm CPS 3.l6xCPS= 3.16 (1) IF core is off loaded, THEN use the High Flux at Shutdown alarm setpoint that was used immediately prior to core off-load AND record below: High Flux at Shutdown alarm setpoint: _ _ _ _ _ _ _ _ _ Alarm CPS
- b. Compare the Alarm CPS from above with the current High Flux at Shutdown alarm setpoint utilizing Enclosure 1.
(1) IF the Alarm CPS is within the currently set ALARM VALUE acceptance criteria, THEN the alarm setpoint is satisfactory. (2) IF the Alarm CPS is NOT within the currently set ALARM VALUE acceptance criteria, THEN perform 3-OSP-059.6 3-0SP-059.6,, High Flux at Shutdown for Source Range Channel N-32, prior to proceeding with this procedure. W97:/TNM/dtlmrci/mra W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 16 16 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 3/26/03 3/26/03 INITIALS INITIALS CKD VERIF CK'D VERIF 7.3.2 (Cont'd) 7.3.2 (Contd)
- 3. Position an NIS recorder to monitor source rangerange N-32.
4.
- 4. At AUDIO At AUDIO COUNTCOUNT RATE RATE CHANNEL CHANNEL (NIS (NIS Panel, Panel, N-34), place CHANNEL SELECTOR CHANNEL SELECTOR switch to SR switch to N3 1.
SR N31.
- a. IF in Operational Mode 6 OR preparing to enter Mode 6, Refueling; THEN verify audible indication in the Control Room and Containment.
- 5. At NIS Panel, N-32, verify the following:
- a. INSTRUMENT POWER ON status light ON.
- b. CONTROL POWER ON status light ON.
- c. CHANNEL ON TEST status light OFF.
- d. LOSS OF DETECTOR VOLT status light OFF.
- e. LEVEL TRIP status light OFF.
- f. LEVEL TRIP BYPASS status light OFF.
- g. HIGH FLUX AT SHUTDOWN status light OFF.
- h. BISTABLE TRIP SPARE status light OFF.
- 6. Place LEVEL TRIP switch (NIS panel, N-32) to BYPASS.
- 7. Verify the following:
- a. LEVEL TRIP BYPASS status light (NIS panel, N-32) ON.
- b. N-32 IN BYPASS status light (VPA) ON.
- c. Annunciator B 8/4, NIS TRIP BYPASSED, is ON.
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Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 17 17 Source Range Source Range Nuclear Instrumentation Nuclear Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 INITIALS INITIALS VERIF CKD VERIF CK'D 7.3.2 7.3.2 (Cont'd) (Contd)
- 8. Place HIGH HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to BLOCK.
9.
- 9. Verify Annunciator B Verify B 412, 4/2, SOURCE SOURCE RANGE RANGE HI FLUX AT SHUTDOWN SHUTDOWN BLOCKED, is is ON.
- 10. Have I&C personnel perform the following steps:
- a. Obtain keys for access to rear of rack 60, open rack door.
- b. Install jumper between TB 223-1 and TB 223-2.
I&C: __~~__~~~~______ Jumper Installed Print
- --=-----::-__~--=-----;,...__--
I&C/OPS:_______________________ I&CIOPS Independent Verification Print
- 11. Verify the following:
- a. LOSS OF DETECTOR VOLT status light is ON.
- b. Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE, is ON.
- 12. Place OPERATION SELECTOR switch (NIS panel, N-32) to 60 CPS.
13.. Verify the following: 13
- a. CHANNEL ON TEST status light (NIS panel, N-32) is ON.
- b. Annunciator B 7/3, NIS CHANNEL IN TEST is ON.
- 14. Place the OPERATION SELECTOR switch (NIS panel, N-32) in III the positions listed in Attachment 2, recording data as indicated.
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Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 18 18 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01C 9/16/O1C INITIALS INITIALS CKD VERIF CK'D VERW 7.3.2 (Cont'd) 7.3.2 (Contd)
- 15. Have
- 15. Have I&C personnel perform the following:
- a. Remove the jumper installed in Sub step 7.3.2.10 between TB 223-1 Substep and TB 223-2.
and I&C: __________------------ Jumper Removed Print I&CIOPS:. ______________ I&C/OPS:____________________ VerfIcation Independent Verification Print
- 16. Verify the following:
- a. LOSS OF DETECTOR VOLT status light is OFF.
- b. Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE, is OFF.
- 17. Verify LEVEL AD] ADJ potentiometer (NIS panel, N-32) is IS fully counterclockwise.
- 18. Place the OPERATION SELECTOR switch (NIS panel, N-32) to LEVEL ADJ.
.- - - - - - - - - - - NOTE NOTE
-- -- -- -- -- - I I
I Plant P.A. PA. phone announcements concerning the containment Evacuation Alarm actuation I I during High Flux at Shutdown alarm testing are necessary if personnel are in containment. I L _______________________ L.a a a a a a a I I
- 19. Announce distinctly over the plant P.A. phone, ATTENTION ALL PERSONNEL, THE CONTAINMENT EVACUATION ALARM IS BEING TESTED. (Mark N/A if ifno no personnel are in containment).
- 20. Place HIGH FLUX AT SHUTDOWN SHUTDOWN switch (NIS panel, N-32) to NORMAL.
W97:ITNM/dtlmra/mro W97:ITNM/dtlmr Imr
Procedure No.: Procedure
Title:
Page: 19 Source Range Nuclear Instrumentation Approval Date: 3-0SP-059.1 Analog Channel Operational Test 9/16/01 INITIALS INITIALS CKD VERIF CK'D VERIF 7.3.2 (Cont'd) 7.3.2 (Contd)
- 21. Verify
- 21. Verify Annunciator Annunciator B B 4/2, 4/2, SOURCE SOURCE RANGE RANGE HIHI FLUX FLUX AT AT SHUTDOWN SHUTDOWN BLOCKED, is BLOCKED, is OFF OFF (Mark N/A if (Mark NIA if Annunciator Annunciator B 4/2 is B 4/2 is ON ON due due toto Source Source Range N-31, HIGH HIGH FLUX FLUX ATAT SHUTDOWN SHUTDOWN switch switch in in BLOCK).
BLOCK).
- 22. Adjust LEVEL ADJ potentiometer (NIS panel, N-32) slowly clockwise until HIGH FLUX AT SHUTDOWN status light (NIS tunis ON.
(MS panel, N-32) turns following:
- 23. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for High Flux at Shutdown bistable trip point on Attachment 2.
- b. Verify HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) is ON.
- c. Verify Annunciator B 4/1, SOURCE RANGE HI FLUX AT SHUTDOWN, is ON.
- d. Verify containment Evacuation Alarm is ON. (Mark NIAN/A if no personnel are in containment).
- 24. Adjust LEVEL ADJ potentiometer (NIS panel N-32) slowly counterclockwise until HIGH FLUX AT SHUTDOWN status light (NIS (MS panel, N-32)N.-32) turns OFF.
- 25. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for High Flux at Shutdown bistable reset point on Attachment 2.
- b. Verify HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) is OFF.
- c. Verify Annunciator B B 4/1, SOURCE RANGE HI FLUX AT SHUTDOWN, is OFF.
- d. Verify Containment Evacuation Alarm is OFF (Mark N/A NIA if no personnel personnel are in containment).
- e. Verify High Flux at Shutdown bistable reset point is within acceptance criteria range of Enclosure 1.
1. W97:/TNM/dt/mra/mra W97:rrNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 20 20 Source Range Nuclear Source Range Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 INITIALS INITIALS ççj VERIF CK'D VERIF 7.3.2 (Cont'd) 7.3.2 (Contd)
- 26. Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to BLOCK.
- 27. Verify Annunciator B 4/2,
- 27. 4/2, SOURCE SOURCE RANGE HI HI FLUX AT SHUTDOWN SHUTDOWN BLOCKED, is ON. ON.
- 28. Announce distinctly over the plant P.A. phone, ATTENTION ALL PERSONNEL, THE CONTAINMENT EVACUATION ALARM TEST IS COMPLETE. (Mark NIA N/A ifno if no personnel are in containment).
- 29. Adjust LEVEL ADJ potentiometer (NIS panel, N-32) slowly clockwise until LEVEL TRIP status light (NIS panel, N-32) turns ON.
- 30. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for Level Trip bistable trip point on Attachment 2.
- b. Verify REACTOR PROTECTION LOGIC status light (VPB),
SOURCE RANGE HI FLUX NC32D is ON.
- 31. Adjust LEVEL ADJ potentiometer (NIS panel N-32) slowly counterclockwise until LEVEL TRIP status light (NIS panel, N-32) turns OFF.
- 32. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for Level Trip bistable reset point on Attachment 2.
- b. Verify REACTOR PROTECTION LOGIC status light (VPB),
SOURCE RANGE HI FLUX NC32D is OFF.
- 33. Adjust LEVEL ADJ potentiometer (NIS panel, N-32) fully counterclockwise.
- 34. Place OPERATION SELECTOR switch (MS (NIS panel, N-32) to NORMAL.
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Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 21 21 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 4/1/04 4/1/04 INITIALS INITIALS CKD VERIF CK'D VERIF 7.3.2 (Cont'd) (Contd
- 35. Verify SOURCE SOURCE RANGE CPS NEUTRON LEVEL LEVEL (NIS panel, N-32) indication returns to approximately thethe CPS level level recorded recorded in in Substep 7.3.2.1 of this of this test.
- 36. At NIS panel, N-32, verify the following:
- a. INSTRUMENT POWER ON status light ON.
- b. CONTROL POWER ON status light ON.
- c. CHANNEL ON TEST status light OFF.
- d. LOSS OF DETECTOR VOLT. VOLT, status light OFF.
- e. LEVEL TRIP status light OFF.
- f. HIGH FLUX AT SHUTDOWN status light OFF.
- g. BISTABLE TRIP SPARE status light OFF.
- 37. Verify Annunciator B 7/3, NIS CHANNEL IN N TEST, is OFF.
- 38. Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to NORMAL.
- 39. Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is OFF (Mark N/A 412 is ON due to Source NIA if Annunciator B 4/2 Range N-3 1, HIGH FLUX AT SHUTDOWN switch in BLOCK).
N-31,
- 40. Place LEVEL TRIP switch (NIS panel, N-32) to NORMAL.
- 41. Verify the following:
- a. LEVEL TRIP BYPASS status light (NIS panel, N-32) is OFF.
- b. N-32 IN BYPASS status light (VPA) is OFF.
- c. Annunciator Annunciator B B 8/4, NIS TRIP BYPASSED, BYPASSED, is OFF. (Mark N/A NIA if Annunciator BB 8/4 8/4 is ON due to another NIS channel in BYPASS).
Wq7ITNM/dt/mrn/mro W97:rrNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 22 22 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 4/1/04 4/1/04 INITIAL S INITIALS CKD VERIF CK'D VERIF 7.3.2 (Cont'd) (Contd)
- 42. Position the NIS recorders to monitor the highest reading sourcesource range andand the highest reading intermediate range channels.
- 43. IFIF inin Mode Mode 6, 6, OR OR preparing to enter enter Mode Mode 6, THEN place the Audio Count 6, THEN Count Rate Channel Selector Switch to an operable channel.
Date/Time Completed: _ _ _ _ _ _ _ _---'//_ _ _ __ PERFORMED BY (Print) iNITIALS INITIALS VERIFIED BY (Print) INITIALS REVIEWED BY: _ _ _---::-:;:--;;----;:::-:;-_=-_--:--_----;:::;-;:~;::::___:__--_ REVIEWED Nuclear Plant Supervisor or SRO Designee W7ITNM/dffmrn/mro W97:fTNM/dUmr Imr
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 23 23 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 7.4 7.4 Source Range Source Range Channel Channel Testing during Mode Testing during Mode 1,1, Power Power Operation Operation and and Mode Mode 2, 2, Startup Startup (Above P-6 Interlock). (Above INITIALS INITIALS CKD VERIF CK'D Date/Time Started: _ _ _ _ _ _ _---'/'----_ / _ __ 7.4.1 7.4.1 Perform testing of SOURCE RANGE of SOURCE RANGE N-31 N-31 as follows: follows:
- 1. Record Intermediate Range Amperes Neutron Level (NIS panel).
N-35 _ _ _ _ AMPERES N - - - AMPERES
- 2. Verify the following:
- a. AUDIO COUNT RATE CHANNEL (NIS panel N-34), CHANNEL SELECTOR switch is OFF.
- b. Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is OFF.
- c. Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE, is OFF.
- d. lO5 CPS TRIP BLOCKED status light (VPA) is ON.
10
- 3. At NIS panel, N-3 1, verify the following:
N-31,
- a. ThJSTRUMENT INSTRUMENT POWER ON status light ON.
- b. CONTROL POWER ON status light ON.
- c. CHANNEL ON TEST status light OFF.
- d. LOSS OF DETECTOR VOLT status light ON.
- e. LEVEL TRIP status light OFF.
- f. LEVEL TRIP BYPASS status light OFF.
- g. HIGH FLUX AT SHUTDOWN status light OFF.
- h. BISTABLE TRIP SPARE SPARE status light OFF.
OFF.
- 4. Place LEVEL TRIP switch (NIS panel, N-3 N-31)1) to BYPASS.
W97:ItNM/dtlmrQ/mrq W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 24 24 Source Range Nuclear Source Range Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 INITIALS INITIALS CK'D VERIF CKD VERIF 7.4.1 (Cont'd) 7.4.1 (Contd) 5.
- 5. Verify the following:
a.
- a. LEVEL TRIP LEVEL TRIP BYPASS status status light light (NIS (NIS panel, N-31) ON.ON.
- b. N-3 1 IN N-31 IN BYPASS status light (VPA) ON.
- c. Annunciator B 8/4, NIS TRIP BYPASSED, is ON.
- 6. Place OPERATION SELECTOR switch (NIS panel, N-31) to 60 CPS.
- 7. Verify the following:
- a. CHANNEL ON TEST status light (NIS panel, N-31) N-3 1) ON.
- b. Annunciator B 7/3, NIS CHANNEL IN TEST, is ON.
- 8. Place the OPERATION SELECTOR switch (NIS panel, N-31) in the positions listed in Attachment 3, recording data as indicated.
- 9. Verify LEVEL ADJ potentiometer (NIS panel, N-31)
N-3l) is fully counterclockwise.
- 10. Place the OPERATION SELECTOR switch (NIS panel, N-31) to LEVEL ADJ.
- 11. Adjust LEVEL ADJ potentiometer (NIS panel, N-31) N-3 1) slowly clockwise until HIGH FLUX AT SHUTDOWN status light (MS (NIS panel, N-3 N-31)1) turns ON.
- 12. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-3 N-31)1) for High Flux at Shutdown bistable trip point on Attachment 3.
- 13. Adjust LEVEL ADJ potentiometer (NIS panel, N-31) slowly counterclockwise until HIGH FLUX AT SHUTDOWN status light (NIS panel, N-31) turns OFF.
- 14. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-3l) N-31) for High Flux at Shutdown bistable reset point on Attachment 3. 3.
W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 25 25 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 INITIALS INITIALS CKD VERIF CK'D VERIF 7.4.1 (Cont'd) 7.4.1 (Contd)
- 15. Verify
- 15. Verify High High Flux Flux atat shutdown shutdown bistable bistable reset reset point point is is within within acceptance acceptance criteria range criteria range of of Enclosure Enclosure 1.1.
- 16. Adjust
- 16. Adjust LEVEL LEVEL ADJ potentiometer (NIS (NIS panel, N-31)
N-31) slowly slowly clockwise clockwise until LEVEL TRIP status status light (NIS panel, N-31) N-3 1) turns ON.
- 17. Perform the following:
17.
- a. SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-31)
Record SOURCE for Level Trip bistable trip point on Attachment 3.
- b. Verify REACTOR PROTECTION LOGIC status light (VPB),
SOURCE RANGE HI FLUX NC31D is ON.
- 18. Adjust LEVEL ADJ potentiometer (NIS panel, N-31)
- 18. N-3 1) slowly counterclockwise until LEVEL TRIP status light (NIS panel, N-31) N-3 1) turns OFF.
- 19. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-31) for Level Trip bistable reset point on Attachment 3.
- b. Verify REACTOR PROTECTION LOGIC status light (VPB),
SOURCE RANGE HI FLUX NC31D is OFF.
- 20. Adjust LEVEL ADJ potentiometer (NIS panel, N-31) N-3 1) fully counterclockwise.
- 21. Place OPERATION SELECTOR switch (NIS panel, N-31) to NORMAL.
- 22. Place LEVEL TRIP switch (NIS panel, N-3 N-31)
- 1) to NORMAL.
- 23. At NIS panel, N-31, verify the following:
- a. INSTRUMENT POWER ON status light ON.
- b. CONTROL POWER ON status light ON.
- c. CHANNEL ON TEST status light OFF.
WQ7ITNM/Ht/mrn/mrn W97:ITNM/dUmr Imr
Procedure No.: Procedure
Title:
Page: 26 Source Range Nuclear Instrumentation Approval Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Test 9/16/01 9/16/0 1 INITIAL S INITIALS CKD VERIF CK'D 7.4.1.23 (Cont'd) (Contd)
- d. LOSS OF DETECTOR VOLT. status light ON.
- e. LEVEL TRIP status light OFF.
- f. LEVEL TRIP BYPASS status light OFF.
- g. HIGH FLUX AT SHUTDOWN status light OFF.
- h. BISTABLE TRIP SPARE status light OFF.
Verify N-3 1 IN BYPASS status light (VPA) OFF.
- 24. VerifyN-31
- 25. Verify the following:
- a. Annunciator B 8/4, NIS TRIP BYPASSED, is OFF.
- b. Annunciator B 7/3, NIS CHANNEL IN TEST is OFF.
Date/Time Completed:. Completed: _ _ _ _ _ _ _ _ _ /_ _ _ __ PERFORMED BY (Print) INITIALS VERIFIED BY (Print) INITIALS REVIEWED REVIEWED BY: BY: ------::--=--=-----=-c:----:::-----,-------::=--=--=-----:---- Nuclear Plant Supervisor or SRO Designee W97:ITNM/dt/mr Imr W97:/TNM/dtImro/mrQ
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 27 27 Source Range Nuclear Source Range Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Started: DatelTime Started: 1/
--------------~-------
7.4.2 7.4.2 Perform testing Perform testing ofof SOURCE SOURCE RANGE RANGE N-32 N-32 as as follows: follows: 1.
- 1. Record Intermediate Range Record Intermediate Range Amperes Amperes Neutron Level Level (NIS (NIS panel).
N-3 5 _ _ _ _ AMPERES N-35 N - - - AMPERES
- 2. Verify the following:
- a. AUDIO COUNT RATE CHANNEL (NIS panel, N-34), CHANNEL SELECTOR switch is OFF.
- b. Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED is OFF.
- c. Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE is OFF.
- d. 55 CPS TRIP BLOCKED status light (VPA) is ON.
i0 10
- 3. At NIS panel, N-32, verify the following:
- a. INSTRUMENT POWER ON status light ON.
- b. CONTROL POWER ON status light ON.
- c. CHANNEL ON TEST status light OFF.
- d. LOSS OF DETECTOR VOLT status light ON.
- e. LEVEL TRIP status light OFF.
- f. LEVEL TRIP BYPASS status light OFF
- g. HIGH FLUX AT SHUTDOWN status light OFF.
- h. BISTABLE TRIP SPARE status light OFF.
- 4. Place LEVEL TRIP switch switch (NIS panel, N-32) to BYPASS.
W97ITNM/dt/mrn/mrri W97:ITNM/dt/mr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 28 28 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 INITIAL S INITIALS CKD VERIF CK'D VERIF 7.4.2 (Cont'd) 7.4.2 (Contd) 5.
- 5. Verify the Verify the following:
following: a.a. LEVEL TRIP LEVEL TRIP BYPASS BYPASS status status light light (NIS (NIS panel, N-32) ON. ON.
- b. N-32 INN BYPASS status light (VPA) ON.
- c. Annunciator B 8/4, NIS TRIP BYPASSED is ON.
- 6. Place OPERATION SELECTOR SELECTOR switch (NIS panel, N-32) to 60 CPS.
- 7. Verify the following:
- a. CHANNEL ON TEST status light (NIS panel, N-32) ON.
- b. Annunciator B 7/3, NIS CHANNEL IN N TEST is ON.
- 8. Place the OPERATION SELECTOR switch (NIS panel, N-32) in the positions listed in Attachment 4, recording data as indicated.
- 9. Verify LEVEL ADJ potentiometer (NIS panel, N-32) is fully counterclockwise.
- 10. Place the OPERATION SELECTOR switch (NIS panel, N-32) to LEVEL ADJ.
- 11. Adjust LEVEL ADJ potentiometer (NIS panel, N-32) slowly clockwise until HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) turns ON.
NIGH
- 12. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for High Flux at Shutdown bistable trip point on Attachment 4.
- 13. Adjust LEVEL ADJ potentiometer (NIS panel, N-32) slowly counterclockwise until HIGH FLUX AT SHUTDOWN status light (NIS panel N-32) turns OFF.
- 14. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for 14.
High Flux at Shutdown bistable reset point on Attachment 4. W97:ITNM/dtlmra/mro W97:rrNM/dtlmr Imr
ProcedureNo.: Procedure No.: ProcedureTitle:
Title:
Page: Page: Procedure 29 29 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval ApprovalDate: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational TestTest 9/16/01 9/16/0 1 INITIALS INITIALS CKD VERIF CK'D VERIF 7.4.2 (Cont'd) 7.4.2 (Contd)
- 15. Verify High
- 15. Verify High Flux Flux atat Shutdown Shutdown bistable bistable reset reset point point isis within within acceptance acceptance criteria range criteria range ofofEnclosure Enclosure 1.1.
- 16. Adjust
- 16. Adjust LEVELLEVEL ADJ ADJ potentiometer potentiometer (NIS (NIS panel, panel, N-32)
N-32) slowly slowly clockwise clockwise until until LEVEL TRIP LEVEL TRIP status status light light (NIS (NIS panel, panel, N-32) turns ON. N-32) turns ON.
- 17. Perform
- 17. Perform the the following:
following: a.a. Record SOURCE Record SOURCE RANGE RANGE CPS CPS NEUTRON NEUTRON LEVEL LEVEL (NIS (NIS panel, panel, N-32) N-32) for Level for Level Trip Trip bistable trip point on on Attachment Attachment 4. 4. b.
- b. Verify REACTOR Verify REACTOR PROTECTION PROTECTION LOGIC LOGIC status status light light (VPB),
(VPB), SOURCE RANGE HI FLUX NC32D is ON. SOURCE
- 18. Adjust LEVEL ADJ potentiometer
- 18. potentiometer (NIS (NIS panel, N-32) slowly slowly counterclockwise until LEVEL TRIP status light (NIS panel, N-32) turns counterclockwise OFF.
- 19. Perform the following:
- a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for Level Trip bistable reset point on Attachment 4.
- b. Verify REACTOR PROTECTION PROTECTION LOGIC status light (VPB),
SOURCE RANGE HI FLUX NC32D is OFF.
- 20. Adjust LEVEL ADJ potentiomete potentiometerr (NIS panel, N-32) fully counterclock counterclockwise.wise.
- 21. Place OPERATION SELECTOR switch (NIS panel, N-32) to NORMAL.
- 22. Place LEVEL TRIP switch (NIS panel, N-32) to NORMAL.
23.
- 23. AtAt NIS panel, N-32, verify verify the following:
a.a. INSTRUME INSTRUMENT NT POWER POWER ON ON status status light light ON. ON. b.
- b. CONTROL POWER POWER ON status light ON status light ON.
ON. c.c. CHANNEL CHANNEL ON TEST status ON TEST status light light OFF. OFF. W97:rrNM/dtlmr Imr
Procedure No.: Procedure Procedure
Title:
Procedure Page: 30 Source Range Nuclear Instrumentation Approval Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Test 9/16/01 INITIALS CKD VERIF CK'D 7.4.2.23 (Cont'd) (Contd)
- d. LOSS OF DETECTOR VOLT. VOLT, status light ON.
- e. LEVEL TRIP status light OFF.
- f. LEVEL TRIP BYPASS status light OFF.
- g. HIGH FLUX AT SHUTDOWN status light OFF.
- h. BISTABLE TRIP SPARE status light OFF.
- 24. Verify N-32 IN BYPASS status light (VPA) OFF.
- 25. Verify the following:
- a. Annunciator B 8/4, NIS TRIP BYPASSED, is OFF.
- b. Annunciator B 7/3, NIS CHANNEL IN TEST, is OFF.
Date/Time Completed: _ _ _ _ _ _ _ _ _./_ _ _ __ /____________ PERFORMED BY (Print) INITIALS VERIFIED BY (Print) INITIALS REVIEWED REVIEWED BY: BY: ------:;-:;,-------;---::::-:;------:::-------:--::::-::::-::0-=--:---- Nuclear Plant Supervisor or SRO Designee END OF TEXT W97:ITNM/dtlmrci/mrci W97:ITNM/dtlmr Imr
0C C Cz0 0 C I Page: Co Procedure No.: Procedure
Title:
31 Source Range Nuclear Instrumentation Approval Date: 0 00 00 C 3-0SP-059.1 (I rD .. Analog Channel Operational Test 9/16/01 ENCLOSURE 1 (DC (Page 1 of 1) o 0:: HIGH FLUX AT SHUTDOWN - ACCEPTANCE CRITERIA FOR ALARM AND RESET I 0 0 CD z 0 W97:ITNM/dVmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 32 32 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/O1C 9/16/01C ATTACHMENT 11 ATTACHMENT (Page 11 of3) (Page of 3) SOURCE RANGE SOURCE RANGE CHANNEL CHANNEL N-31 N-31 TEST TEST DATA DATA (SHUTDOWN) (SHUTDOWN) QA RECORD PAGE QA RECORD PAGE II II (Page 11 of3) of 3) r - - - - - - - - - - NoTe iOF - - - - - - - - - - - I1 I II The NIS Drawer Meter is to be used for channel operability requirements. Deficiencies in The I the console indications should be brought to the attention of the I&C I&C Department, with II appropriate prioritization with with respect to plant mode. I LLa... _______________________ II Ref Step Ref. 7.3.1 .14 7.3.1.14 Operation Selector switch range verification. r----------NoTe-----------1 i_ Iboi1 a I The symbol +xxx in the acceptance criteria represents greater than 1.0x10 66 CPS by an 1.0x10 I II amount less than orequa/to amountless or equal to the meter deflection between 8x10 5 5 CPS and 1.0x10 8x10 66 CPS. 1.0x10 I
~----------------- _ _ _ _ _ _ II a a S a OPERATION NIS CONSOLE* CONSOLE*
SELECTOR Meter Meter Recorder POSITION N-31 N-3-31 NR-3-45, Channel S Si1 60 CPS 60 CPS Acceptance Criteria: (50 to 75 CPS) 103 CPS Acceptance Criteria: (8 x 102 to 1.2 x i0 CPS) 105 CPS Acceptance Criteria: (8 x i0 4 to 1.2 x CPS) 1066 CPS 10 Acceptance Criteria: (8 x i0 5 to +xxx) 10 CPS PREAMP______ 10CPS-PREAMP~ (N 0 Acceptance (No Acceptance Criteria) 10.24x103 CPS 10.24x10 3 CPS - PREAMP
- PREAMP (No Acceptance Acceptance Criteria)
Criteria) Return Return toto Step Step 7.3.1.15 7.3.1.15 W97:/TNM/dtlmra/mra W97:ITNM/dtlmr Imr
Procedure No.: Procedure Procedure
Title:
Procedure
Title:
Page: 33 Source Range Nuclear Instrumentation Approval Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Test 9/16101C 9/16/01C ATTACHMENT 11 of 3) (Page 2 of3) SOURCE RANGE CHANNEL N-31 TEST DATA (SHUTDOWN) IIf f QA RECORD PAGE of 3) IIf (Page 2 of3) 7.3.1.23 High Flux at Shutdown bistable trip point, N-31 Source Range _ _ _ _ _ _ CPS 7.3.1.25 High Flux at Shutdown bistable reset point, N-31 Source Range _ _ _ _ _ _ CPS 7.3.1.30 Level Trip bistable trip point, N-31 Source Range _ _ _ _ _ _ CPS Acceptance Criteria (::::; i05 CPS) ( 10
- FOR REVIEW ONLY 7.3.1.32 Level Trip bistable reset point, N-31 N-3 1 Source Range _ _ _ _ _ _ CPS Acceptance Criteria (4.1 x 10 iü4 to 6.2 x 104 CPS)
Acceptance Criteria specified in this Attachment has been satisfied. Results Satisfactory _ _ _ _-:::;:-_ _ _ _ _ _ _ _ _ __ Signature Date IF results are unsatisfactory, THEN declare the channel inoperable and perform actions 3-ONOP-059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION required by 3-0NOP-059.5, MALFUNCTION.
~
I
- - - - - - - - - - NOTE I
I If channel(s) did not meet acceptance criteria, then notify I&C l&C to perform O-ADM-724, I I Instrumentation Protection Channel Determination of Channel Operability, for the failed Instrumentation I channels. [Commitment - Step 2.3.1] 2.3.1J L _______________________ II L_________ W97:/TNM/dtlmrcj/mrcj W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 34 34 Source Range Source Nuclear Instrumentation Range Nuclear Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 ATTACHMENT 11 ATTACHMENT (Page 33 of3) (Page of 3) SOURCE RANGE SOURCE CHANNEL N-31 RANGE CHANNEL N-31 TEST TEST DATA DATA (Shutdown) (Shutdown) QA RECORD QA RECORD PAGE PAGE II II of 3) (Page 3 of3) REMARKS: REMARKS:_________________________________________________________ PERFORMED BY (Print) PERFORMED INITIALS REVIEWED BY: _____------=-::---::----=::------=-_ _--,-_ _------::::::::-::::-:::---,-_____ Nuclear Plant Supervisor or SRO Designee W97:ITNM/dt/mrQ/mrq W97:ITNM/dVmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 35 35 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Operational Test Channel Operational Test 9/16/01C 9/16/O1C ATTACHMENT 22 ATTACHMENT of 3) (Page 11 of3) (page SOURCE RANGE SOURCE RANGE CHANNELCHANNEL N-32 N-32 TEST TEST DATA DATA (SHUTDOWN) (SHUTDOWN) QA RECORD PAGE QA PAGE II II (Page 11 of3) of 3) I..__ r----------No~-----------I 1 I The NIS Drawer Meter is to be used for channel operability requirements. Deficiencies in The in I II the console indications should be be brought to the attention of the I&C Department, with I appropriate prioritization with respect to plant mode. I L _______________________ II a a a a Ref. Step 7.3.2.14 Operation Selector switch range verification. r -- -- -- -- -- a a a a a NO~ -- -- -- -- -- - a a I I The symbol +xxx in the acceptance criteria represents greater than 1.0x10 1. Ox I 66 CPS by an I II amount less than or equal to the meter deflection between 8x10 8xIO 5 5 CPS and 1. 6 6 Ox1 0 CPS. 1.0x10 I
~----------------- _ _ _ _ _ _ II a a a a a a OPERATION NIS CONSOLE* CONSOLE*
SELECTOR Meter Meter Recorder POSITION N-32 N-3-32 NR-3-45, Channel S2 60 CPS Acceptance Criteria: (50 to 75 CPS) 10 3 CPS Acceptance Criteria: (8 x 102 to 1.2 x i0 3 CPS) 10 5 CPS Acceptance Criteria: Criteria: (8 x IO to 1.2 x 10: CPS) 106 106 CPS Acceptance Criteria: (8 xX 110 5 to +xxx) 10 CPS PREAMP_________ 10CPS-PREAMP~ (No Acceptance Acceptance Criteria) 10.24x103 CPS 10.24x10 3 CPS - PREAMP
- PREAMP (N 0 Acceptance Criteria)
(No Criteria) Return to Return to Step Step 7.3.2.15 7.3.2.15 W97:ITNM/dVmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 36 36 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01C 9/16/O1C ATTACHMENT 22 ATTACHMENT (Page 22 of3) (Page of 3) SOURCE RANGE SOURCE RANGE CHANNEL CHANNEL N-32 TEST TEST DATA DATA (SHUTDOWN) (SHUTDOWN) III QARECOIW QA RECORD PAGE PAGE II of 3) (Page 2 of3) 7.3.2.23 Shutdown bistable trip point, N-32 High Flux at Shutdown Source Range _ _ _ _ _ _ CPS 7.3.2.25 High Flux at Shutdown bistable reset point, N-32 Source Range _ _ _ _ _ _ CPS 7.3.2.30 Level Trip bistable trip point, N-32 Source Range _ _ _ _ _ _ CPS Acceptance Criteria (:S; i05 CPS) ( 10
** FOR REVIEW ONLY 7.3.2.32 Level Trip bistable reset point, N-32 Source Range _ _ _ _ _ _ CPS Acceptance Criteria (4.1 x 10 i04 to 6.2 Xx 104 CPS)
Acceptance Criteria specified in this Attachment has been satisfied. Results Satisfactory _ _ _ _~----------- Signature Date IF results are unsatisfactory, THEN declare the channel inoperable and perform actions required by 3-ONOP-059.5, 3-0NOP-059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION MALFUNCTION. MALFUNCTION .
....- - - - - - - - - - a - - - -
- NOTE - a- - - - - - -a-a, I I I If channel(s) did not not meet acceptance criteria, then notify l&C Instrumentation Protection I&C to perform perform O-ADM-724, O-ADM-724, I I Protection Channel Determination Determination ofof Channel Channel Operability, Operability, for the the failed I channels. [Commitment - Step Step 2.3.1]
2.3.1J L _______________________ __a_ajI L___a W97:ITNM/dtlmra/mra W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 37 37 Source Range Source Range Nuclear Instrumentation Nuclear Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Analog Channel Operational Test Test 9/16/01 9/16/01 ATTACHMENT 22 ATTACHMENT (Page 3 of3) (Page of 3) SOURCE RANGE CHANNEL N-32 TEST DATA (SHUTDOWN) QA RECORD PAGE QA RECORD PAGE II II of 3) (Page 3 of3) REMARKS: _________________________________________________________ PERFORMED BY (Print) INITIALS REVIEWED REVIEWED BY: BY: ------------,,-=--~_,.,_:______:_------___:::=_=c__=_------ Nuclear Plant Supervisor or SRO Designee W97:ITNM/dtlmr Imr
Procedure No.: Procedure
Title:
Title: Page: 38 Source Range Nuclear Instrumentation Approval Approval Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Test 9/16/01C 9/16/O1C ATTACHMENT 3 (Page 11 of3) of 3) SOURCE RANGE CHANNEL N-31 TEST DATA (OPERATING) f II QA RECORD PAGE (Page 11 of3) of 3) II r - - - - - - - - - - NOTE - - - - - - - - - - - I II N/S Drawer Meter is to be used for channel operability requirements. Deficiencies in The NIS I the console indications should be brought to the attention of the I&C l&C Department. I I Ref. Step 7.4.1.8 Operation Selector switch range verification. I~-----------------------I NOTE I I The symbol +xxx in the acceptance criteria represents greater than 1.0x10 1.Ox 1066 CPS by an I 5 or equal to the meter deflection between 8x10 amount less than orequa/to 5 CPS and 1.0x10 8x10 66 CPS. 1.0x10 L _______________________ L_________ __iI OPERATION NIS CONSOLE* SELECTOR Meter Meter POSITION N-.31 N-31 N-3-31 60 CPS 60 Acceptance Criteria: (50 to 75 CPS) io 3 10 3 cis CPS Acceptance Criteria: (8 x 102 to 1.2 x CPS) 10 5 CPS Acceptance Criteria: (8 x 10 to 1.2 x i0 CPS) 1066 CPS 10 Acceptance Criteria: I 5 to +/-xxx) (8 x 10 +xxx) CPS PREAMP________ 10CPS-PREAMP~ 10 - ______ (No Acceptance Criteria) 10.24x103 CPS - PREAMP 10.24x10 3 - (No Acceptance Criteria) Return to Step 7.4.1.9 W97:/TNM/dtlmrci/mrci W97:ITNM/dtlmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 39 39 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 ATTACHMENT 33 ATTACHMENT (Page 22 of3) (Page of 3) SOURCE RANGE SOURCE RANGE CHANNEL CHANNEL N-31 TEST TEST DATA DATA (OPERATING) (OPERATING) II QA RECORD PAGE QA PAGE IIi of 3) (Page 2 of3) 7.4.1 .12 7.4.1.12 Shutdown bistable trip point, N-31 High Flux at Shutdown N-3 1 Source Range _ _ _ _ _ _ CPS 7.4.1.14 High Flux at Shutdown bistable reset point, N-31 N-3 1 Source Range _ _ _ _ _ _ CPS
** FOR REVIEW ONLY 7.4.1.17 Level Trip bistable trip point, N-31 Source Range _ _ _ _ _ _ CPS Source Range Acceptance Criteria (::::10(<1O5 CPS) 7.4.1.19 Level Trip bistable reset point, N-31 N-3 1 Source Range _ _ _ _ _ _ CPS Acceptance Criteria (4.1 x 10 iO4 CPS) lO4 to 6.2 Xx 10 Acceptance Criteria specified in this Attachment has been satisfied.
Results Satisfactory _ _ _ _-:::--_ _ _ _ _ _ _ _ _ __ Signature Date IF results are unsatisfactory, THEN declare the channel inoperable and perform actions required by 3-ONOP-059.5, 3-0NOP-059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION MALFUNCTION. r-- - - - - - - - - - - - - - - I NOTE I I If channel(s) not meet acceptance criteria, then notify I&C to perform O-ADM-724, channel(s) did not Instrumentation Protection Channel I I Channel Determination Determination of Channel Operability, for the of Channel the failed I II channels. [Commitment Step 2.3.1] Lh~n:.~c:m:m:-~te~.~1J_ _ _ _ _ _ _ _ _ _ _ _ _ _ 1___ W97:ITNM/dt/mr Imr
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 40 40 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/0 1 ATTACHMENT 33 ATTACHMENT (Page 33 of3) (Page of 3) SOURCE RANGE SOURCE RANGE CHANNEL CHANNEL N-31N-31 TEST TEST DATA DATA (OPERATING) (OPERATING) fl II QARECORDPAGE (Page 33 of3) (Page of 3) II REMARKS: REMARKS:_______________________________________________________ PERFORMED BY (Print) PERFORMED INITIALS REVIEWED REVIEWEDBY: BY: ______~~~~--=_--~--~~~~----- Nuclear Plant Supervisor or SRO Designee Wq7)TNM/dt/mrn!mrn W97:ITNM/dt/mr Imr
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 41 41 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9116/01C 9116101C ATTACHMENT 44 ATTACHMENT (Page 11 of (Page of 3) 3) SOURCE RANGE CHANNEL N-32 TEST DATA (OPERATING) III QARECORDPAGE QA RECORD PAGE II (Page 11 of3) of 3) r----------~TE-----------I io:j: II N/S Drawer Meter is to be used for channel operability requirements. Deficiencies in The NIS I the console indications should be brought to the attention of the I&C l&C Department. I I Ref. Step 7.4.2.8 Operation Selector switch range verification. I~-----------------------I NOTE I 6 I The symbol +xxx in the acceptance criteria represents greater than 1.0x10 6 CPS by an 1.0x10 I 5 6 amount less than or equal to the meter deflection between 8x10 5 CPS and 1.0x10 8x10 6 CPS. 1.0x10 LL___ _______________________ _______JI OPERATION NIS CONSOLE* SELECTOR Meter Meter POSITION N-32 N-3-32 60 CPS Acceptance Criteria: (50 to 75 CPS) 103 CPS Acceptance Criteria: (8 x 102 to 1.2 x i0 CPS) io 5 10 5 CPS Acceptance Criteria: (8 x 10 to 1.2 x 10 CPS) 106 106 CPS CPS Acceptance Acceptance Criteria: 105 to (8 xx iü to +xxx)
+xxx) 10 CPS PREAMP______
10CPS-PREAMP~ (N 0 Acceptance (No Acceptance Criteria) Criteria) 10.24x103 CPS 10.24x10 3 CPS - PREAMP
- PREAMP (No Acceptance (No Acceptance Criteria)
Criteria) Return Return to Step Step 7.4.2.9 7.4.2.9 W97ITNM/dtlmro/mro W97:ITNM/dUmr Imr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 42 Source Range Nuclear Instrumentation Source Approval Date: Approval Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Operational Test 9/16/01 9/16/0 1 ATTACHMENT 4 of 3) (Page 2 of3) SOURCE RANGE CHANNEL N-32 TEST DATA (Operating) III QARECORDPAGE QA RECORD PAGE II of 3) (Page 2 of3) 7.4.2.12 High Flux at Shutdown bistable trip point, N-32 Source Range _ _ _ _ _ _ CPS 7.4.2.14 High Flux at Shutdown bistable reset point, N-32 Source Range _ _ _ _ _ _ CPS
** FOR REVIEW ONLY 7.4.2.17 Level Trip bistable trip point, N-32 Source Range _ _ _ _ _ _ CPS Acceptance Criteria (::s iO5 CPS)
(< 10 7.4.2.19 Level Trip bistable reset point, N-32 Source Range _ _ _ _ _ _ CPS Acceptance Criteria (4.1 x 10 44 to 6.2 x 10 i0 iO4 CPS) Acceptance Criteria specified in this Attachment has been satisfied. Results Satisfactory _ _ _ _::;:-_ _ _ _ _ _ _ _ _ __ Signature Date IF results are unsatisfactory, THEN declare the channel inoperable and perform actions required by 3-ONOP-059.5, 3-0NOP-059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION MALFUNCTION.. MALFUNCTION I Ibo.i1 NOTE a I I If channel(s) did not meet acceptance criteria, then notify I&C l&C to perform O-ADM-724, Instrumentation Protection Channel Determination of Channel Operability, for the failed II I I channels. [Commitment Step 2.3.1]
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Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 43 43 Source Range Source Range Nuclear Nuclear Instrumentation Instrumentation Approval Approval Date: Date: 3-OSP-059.1 3-0SP-059.1 Analog Channel Analog Channel Operational Operational Test Test 9/16/01 9/16/01 ATTACHMENT 44 ATTACHMENT (Page 3 of3) (Page of 3) SOURCE RANGE CHANNEL SOURCE CHANNEL N-32 TEST TEST DATA (OPERATING) (OPERATING) IIf QA RECORD PAGE QA PAGE II of 3) (Page 3 of3) REMARKS: REMARKS:_______________________________________________________ PERFORMED BY (Print) INITIALS REVIEWED REVIEWEDBY: BY: ______~~--~--=_--~--~~~~----- Nuclear Plant Supervisor or SRO Designee FINAL PAGE W97:ITNM/dtlmr Imr
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Appendix C Job Performance Measure Form ES-C-1 ES-C-I Worksheet Facility: Facility: Turkey Point Turkel Point No: Task No: Respond to Component Respond Water System Cooling Water Performance Job Performance Task
Title:
Malfunctions Malfunctions Measure No: Measure Systems - e Slstems 008 A2.01 (3.3/3.6) K/A
Reference:
KIA (3.1/3.4) 062 A2.04 {3.1/3.4} Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulator Simulated Performance Actual Performance Yes
------------------- ---------~~--------
Classroom - - - - - - - - - - - - - - Simulator ----------------- Yes Plant - - - - - - - - - - - - - Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Unit 3 is in Mode 3
- 2. Unit 4 is in mode 11 at 100% power
- 3. 3A CCW pump is out of service
- 4. Station Area Operations performing visual inspection of 3D 4kV bus relays Task Standards:
3-ONOP-004.5
- 1. 3D 4kV bus is re-energized using 3-0NOP-004.5
- 2. CCW system flow restored by starting 3C CCW pump Required Materials:
- 1. 3-ARP-097.CR 3-ONOP-030
- 2. 3-0NOP-030 3-ONOP-004.5
- 3. 3-0NOP-004.5 General
References:
- 1. 3-ARP-097.CR 3-ONOP-030
- 2. 3-0NOP-030 3-ONOP-004.5
- 3. 3-0NOP-004.5 3-OP-030
- 4. 3-0P-030 Initiating Cue:
Respond to plant conditions as Unit 33 Reactor Operator Time Critical Task: Yes/No Validation Time: 10 minutes 10
Appendix C Appendix C Page 22 of Page of 88 Form ES-C-I Form ES-C-1 INSTRUCTIONS TO TO OPERA OPERATOR TOR READ TO READ TO OPERA OPERATOR:TOR: WHEN II TELL WHEN TELL YOUYOU TO TO BEGIN, BEGIN, YOU YOU ARE ARE TO TO PERFORM PERFORM THE THE ACTIONS ACTIONS AS DIRECTED DIRECTED IN IN THE THE INITIATING INITIATING CUES. II WILL CUES. WILL DESCRIBE DESCRIBE THE THE GENERAL GENERAL CONDITIONS CONDITIONS UNDER UNDER WHICHWHICH THIS THIS TASK TASK IS IS TO TO BEBE PERFORMED PERFORMED AND PROVIDE AND PROVIDE THE THE NECESSARY NECESSARY TOOLS TOOLS WITH WITH WHICH WHICH TO TO PERFORM PERFORM THIS THIS TASK. BEFORE STARTING, TASK. BEFORE STARTING, II EXPLAIN THE INITIAL WILL EXPLAIN INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS:
- 1. Unit Unit3isinMode3 3 is in Mode 3
- 2. Unit 4 is in mode 11 at 100% power
- 3. 3A CCWCOW pump is out of service
- 4. Station Area Operations performing visual inspection of 3D 4kV bus relays INITIATING INITIA TlNG CUE:
Respond to plant conditions as Unit 3 Reactor Operator. TERMINATION TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. NOTES TO EVALUA EVALUATOR TOR AND IIF I/F OPERATOR:
- 1. Reset simulator to IC-13 IC-i 3 or IC-141.
IC-i 41. If IC-13 10-13 used perform steps 2 through 11 ii below. If IC-141 10-141 used, go directly to step 12.
- 2. Unit 3 is in Mode 3.
- 3. Place simulator in run.
- 4. Place control switches for both groups of backup heaters in AUTO
- 5. Open reactor trip breakers and acknowledge alarms
- 6. Depress rod control startup reset pushbutton
- 7. Place rod control selector switch in MANUAL
- 8. Start 3A ICW pump and stop 30 3C lOW ICW pump
- 9. Place 3A COW CCW pump out of service as follows: Click on Schema ~ MAIN POWER DISTRIBUTION
~ > 4KV & 480VAC ~
48OVAC > 3A 4KV BUS ~
> breaker 12 ~
12 > TAK1A12P - 3AA12 BREAKER POSITION >
- ~
select RACKOUT then INSERT.
- 10. Setup the spurious 3D 4kV bus lockout and reset as follows: Click on Schema >
- 10. ~ MAIN POWER DISTRIBUTION ~ 4KV & 48OVAC480VAC * ~ 3D 4KV BUS ~ 4160V 3D 86/3D ~ TFE2Z53S - 863AD 86/30 > -
SPURIOUS ACTUATION * ~ enter condition = Ki = = OGO4R, enter delay time 2 sec, enter TRUE then K10G04R, INSERT INSERT > ~ 4160V 3D 3D 86/3D 86/30 * ~ TFE2Z53S - 863AD
- 863AD SPURIOUS ACTUATION > ~ enter condition = =
IME2D86R, IME2D86R, enter FALSE FALSE then INSERT INSERT ii.
- 11. Store Store temporary IC IC ifif needed for repeat runs of of this JPM JPM
- 12. Open
- 12. Open & & execute lesson lesson file NRC NRC SRO SRO XXIII JPM JPM e.e.
- 13. When task performance begins, place simulator
- 13. simulator in in run and and insert insert failure as follows: Click Click on on Schema Schema
~ COMMON
> COMMON SERVICES -> ~ COMPONENT COOLING > ~ 3P21 3P211lB ~ TVKAOO2X B -÷ TVKA002X - 3P21
- 3P211lBB COW CCW PPPP BB BRG BRG FRICTION FRICTION VARIABLE * ~ enter enter selected =
selected value = 1.0, 1.0, enter = enter ramp time = 22 mm,min, then INSERT INSERT or trigger Q!: trigger lesson lesson step step 3B 3B CCWP CCWP BEARING FAILURE. FAILURE.
II Appendix C Page 3 of 8 ES-C-I I Form ES-C-1 Denote critical steps with a check mark Start Time Performed immediate operator actions of 3-0NOP-030 3-ONOP-030 STEP 1 1 :
- - SAT
- - UNSAT STANDARDS: NOTE: Operator may recognize hi amps on 38 3B CCW COW pump and manually trip the pump. Otherwise 38 3B CCW COW pump will automatically trip on overcurrent due to the failed bearing.
Either behavior is acceptable
- 1. Determined no CCW flow in either header
- 2. Started 3C30 CCW COW pump
- 3. Recognized/reported trip of 3C 30 CCW COW pump and again no flow in either header J
-V 4. Stopped all RCPs J
-V 5. Isolated letdown and determined excess letdown isolated
-V
- 6. Increased one running charging pump speed to maximum J
-V 7. Tripped other running charging pump
-V 8. Directed Primary Operator (PO)
(P0) align emergency cooling from service water to one shutdown charging pump
- 9. Verified CCW COW surge tank level = = 100% and stable Respond as PO P0 when directed to align emergency cooling water to a shutdown charging pump. To align service water for this purpose, click on Schema -+ -* COMMON SERVICES -+
- COMPONENT COOLING -+ >
1fF IfF VCPC - SERV WTR TO CHRG PP MKUP -+ TAKAVCPC TAKA -
- enter selected OPERATOR value = 1.0 then INSERT -+ -* 737D -+
> TAKA737D - CHG PP OIL CLR CUE: OUTLET -+ = 0.0 then INSERT -+
- enter selected value = 737E -+*
TAKA737E - CHG PP OIL CLR INLET -+
-
- enter selected value = 0.0 then INSERT OR trigger lesson step CHG PUMP EMERG COOLING.
Report when complete. 3-ONOP-030 and verifies immediate operator Obtained copy of 3-0NOP-030 STEP 2 -- SAT actions
- - UNSAT STANDARDS: 1. 3-ONOP-030 Obtained control room copy of 3-0NOP-030
- 2. Reviewed steps 1 1 &2
- 3. Reviewed foldout page
Appendix C Appendix C Page 44 of Page of 88 Form ES-C-1 Form ES-C-I STEP When informed When informed byby PO PC that that service service water water emergency emergency cooling cooling is is STEP 33 SAT SAT aligned, starts aligned, starts that that charging charging pump pump and and adjusts adjusts speed speed to to minimum minimum for for -- seal injection seal injection
- - UNSAT UNSAT STANDARDS:
STANDARDS: informed by When informed by PO PC that service service water emergency emergency cooling cooling is is aligned aligned
- 1. Starts
- 1. Starts charging charging pump pump with emergency cooling cooling reduces reduces speed speed to minimum for seal injection minimum injection
- 2. Stops charging pump running at maximum maximum speed Checked if CCW headers should be tied together STEP 4 : SAT
- - UNSAT STANDARD: 1. Determined CCW COW headers not split (already tied together)
- 2. Skipped forward to step 32 As US, tell candidate that another operator will continue in 3-0NOP-3-ONOP-030. Inform candidate that Station Area Operations (SAO) personnel CUE: inadvertently actuated the 3D 4kV bus lockout relay. Direct candidate to restore power to 3D 4kV bus from 3A 4kV bus using 3-0NOP- 3-ONOP-004.5.
3-CNCP-004.5 Obtained copy of 3-0NOP-004.5 STEP 5 : SAT UNSAT STANDARD: Obtained control room copy of 3-ONOP-004.5 3-0NOP-004.5 Checked 3D 4kV bus lockout relay reset STEP 6 :
- - SAT UNSAT
- - UNSAT STANDARD: 1. Determined 3D 4kV bus lockout
- 1. lockout relay tripped
- 2. Determined
- 2. Determined that SAOSAO personnel errorerror was the cause for the the lockout lockout J..J 3.
- 3. Reset 3D 3D 4kV 4kV bus bus lockout lockout relay by depressing relay by depressing the associated reset the associated pushbutton pushbutton on on VPA VPA
I Appendix Appendix C C Page 55 of Page of 88 Form ES-C-1 Form ES-C-I I Checked 3A 3B 4kV 4kV bus STEP STEP 77 : Checked 3A && 38 bus status status
- - SAT SAT
- - UNSAT UNSAT STANDARDS:
STANDARDS: Determined both Determined both 3A 3A && 38 3B 4kV buses buses energized energized Disconnected loads from from 3D 3D 4kV 4kV bus bus STEP STEP 88 : Disconnected loads SAT
- - UNSAT STANDARDS: 1. 30 ICW Verified 3C lOW pump breaker 3AD05 open
- 2. 30 CCW pump breaker 3AD04 open Verified 3C NOTE: Operator may place 3C CCW COW pump control switch in Pull-to-COW pumps are running and CCW Lock. Since no CCW COW system pressure is near zero, once 3D 4kV bus power is restored, the 30 CCW pump will automatically start after 30 sec delay 3C (CCW system low pressure auto start feature).
Determined source of power for 3D 4kV bus STEP 9 : SAT
- - UNSAT STANDARDS: 1.
- 1. Determined 3A & 38 3B 4kV buses both energized
- 2. Determined that US/SM directed 3A 4kV bus to be aligned to 3d 4kV bus Re-energized 3D 4kV bus from 3A 4kV bus STEP 10 10 :
- - SAT
- - UNSAT STANDARDS: 1.
- 1. Verified breakers 3AB1 3A8199 && 3AD06 3AD06 open J-Y 2. Closed breaker 3ADO1 3AD01 J-Y 3.
- 3. Closed breaker 3AA17 3M 17
Appendix C Appendix C Page 66 of Page of 88 Form ES-C-I Form ES-C-1 Verified 3D bus ready ready for loading loading STEP STEP 11 11 : Verified 3D 4kV bus SAT SAT UNSAT UNSAT STANDARD: 1. Verified 3D 4kV bus energized from 3A 4kV bus NOTE: Verification that 3D 4kV bus may be accomplished using supply breaker position lights on VPA, ERDADS and/or local indication.
- 2. Directed field operator to locally verify no breaker targets on 3D 4kV bus Respond as field operator when directed to locally verify no breaker targets on 3D 4kV bus. Report that there are no breaker targets on 3D CUE: 4kV bus. If asked, also report that 3D 4kV bus is energized and conditions are normal. Report bus voltage if field operator requested to locally determine that parameter.
- Restored CCW system flow STEP 12 SAT
- - UNSAT STANDARDS: 1.. Determined that SM/US directed restart 3C 1 cow 30 CCW pump
..J 2. Restarted 3C 30 CCW 00W pump
- 3. Informed SM/US that 3-0NOP-004.5 3-ONOP-004.5 now requires return to procedure and step in effect (3-0NOP-030)
(3-ONOP-030) Terminating 3C CCW pump restarted and CCW system flow restored STOP Cue: Stop Time _ _ __
II Appendix C Page 7 of 8 ES-C-I I Form ES-C-1 Verification of Completion of Completion Performance Measure Job Performance Measure No. --'-S.Lys.:....t:..::.e.:..c.m.:....:s_-_e Systems e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Examinees Name: Examinee's Examiners Name: Examiner's Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Examiners
JPM BRIEFING SHEET JPM BRIEFING SHEET INITIAL CONDITIONS: INITIAL CONDITIONS:
- 1. Unit3isinMode3
- 1. Unit 3 is in Mode 3
- 2. Unit 44 isis in
- 2. Unit in mode mode 11 at 100% power at 100% power
- 3. 3A
- 3. COW pump 3A CCW pump is is out out of of service service
- 4. Station Area Operations performing visual inspection of 3D 4kV bus relays INITIATING
!NITIA TlNG CUE: CUE: Respond to plant conditions as Unit 3 Reactor Operator. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
CAUTION REACTIVITY REACTIVITY MANAGEMENT MANAGEMENT PROCEDURE PROCEDUR E Performance of this procedure may affect core reactivity
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 3-0NOP-030
Title:
Component Cooling Water Malfunction Safety Related Procedure Responsible Department: Operations Revision Approval Date: 3129104C 3/29/04C RTSs RTSs 92-1249P, 93-0145P, 93-0145P, 93-1062P, 94-1315P, 94-1568P, 95-0967P, 95-0967P, 95-0778P, 95-0981P, 95-0981 P, 95-0988P, 95-1039P, 95-1039P, 95-1 95-1124P, 124P, 96-0268P, 97-0866P, 98-0356P, 98-0356P, 98-0799P, 98-0799P, 00-0584P, 02-0294P, 02-0873P, 04-01 85P 04-0185P PC/Ms 1-064, 92-03 1, 92-108, 93-034, 94-096, 96-092, 96-093, 00-016 PCIMs 991-064,92-031, OTSCs OTSCs 10906, 10906, 0543-00, 0543-00, 030 1-02, 0195-03 0301-02, 0195-03 W97/daj/ev/ev W97/daj/ev/ev
ProcedureNo.: Procedure No.:
Title:
ProcedureTitle: Procedure Page: Page: 22 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 3/29/04C 3/29/04C LIST OF LIST OF EFFECTIVE EFFECTIVE PAGES PAGES Revision Revision Revision Revision Page Date Date Page Date Date 11 03/29/04C 03/29/04C 19 19 05/24/02 05/24/02 2 03/29/04C 03/29/04C 20 05/24/02 05/24/02 33 05/24/02 05124102 21 05/24/02 05/24/02 4 05/24/02 22 05124102 05/24/02 5 06/09/03 23 05124102 05/24/02 6 05/24/02 24 05124102 05/24/02 7 05/24/02 25 05/24/02 8 05/24/02 26 05/24/02 9 06/09/03 27 05124102 05/24/02 10 05/24/02 05124/02 28 05/24/02 11 05/24/02 29 03/29/04 12 05/24/02 30 05/24/02 13 03/29/04 31 05/24/02 14 05/24/02 32 05/24/02 15 05/24/02 05124102 33 05/24/02C 16 05/24/02 05124102 34 05124/02C 05/24/02C 17 17 06/09/03 35 05/24/02 18 005/24/02 5/24/02 Foldout 005/24/02 5/24/02 W97/dai/ev/ev W97/da*lev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 3 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 This procedure This procedure provides provides instructions instructions to to be be followed followed in the event in the event of of aa malfunction malfunction or or failure failure in the Component in the Component Cooling Cooling Water System. Water System. 1.2 1.2 This procedure applies to loss of Component Cooling of Component Cooling Water duedue to system system leakage leakage or or due due to high system to high temperatures. system temperatures. 2.0 SYMPTOMS OR ENTRY CONDITIONS CONDITIONS 2.1 Visible evidence of system leakage. 2.2 Rapid decrease in CCW Surge Tank Level, LI-3-613A, or CCW Head Tank Level, LI-3-614A. 2.3 Component Cooling Water Supply Header Temperature, Temperature, TI-3-607A, greater than 120°F. 120°F. 2.4 Loss of intake cooling water flow to CCW Heat Exchangers as determined by 3-ONOP-019, INTAKE COOLING 3-0NOP-019, COOL]NG WATER MALFUNCTION. MALFUNCTION. 2.5 Annunciators 2.5.1 A 1/1, RCP THERMAL BARR COOLING WATER HI FLOW 2.5.2 A 1/3, RCP THERMAL BARR COOLING WATER LO FLOW 2.5.3 H 7/3, RHR PP A COOLING WATER LO FLOW 2.5.4 H 7/4, RHR PP B COOLING WATER LO FLOW 2.5.5 H 7/5, CSP A/B AlB COOLING WATER WATERLO LO FLOW 2.5.6 H 7/6, CCW SURGE TANK LO LEVEL 2.5.7 H 8/1, CCW PP A/B/C AlBIC TRIP 2.5.8 H 8/2, CCW PP A/B/C AlBIC MOTOR OVERLOAD 2.5.9 H 8/3, CCW HEADER LO PRESS 2.5.10 H 8/4, CCW PP SUCTION HI TEMP 2.5.11 H 8/5, CCW HX OUTLET HI TEMP 2.5.12 H 8/6, CCW HEAD TANK HI/LO HIILO LEVEL 2.5.13 H H 9/5, RCPRCP MOTOR BRG BRG COOLING COOLING WATER LO LO FLOW FLOW 2.5.14 2.5.14 X 3/6, SI SIPPPP COOLING COOLING WATERWATERLO LO FLOW W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 4 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 3.0
3.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCES/RECORDS REQUIRED/COMMITMENT DOCUMENTS DOCUMENTS 3.1 References 3.1.1 Technical Specifications 1.
- 1. Section 3/4.5.2, Section 3/4.5.2, ECCS Subsystems Subsystems - Tavg
- Greater Than Tavg Greater Than or or Equal Equal to to 350°F 350°F
- 2. Section 3/4.5.3, ECCS Subsystems - Tavg Less Than 350°F
- 3. Section 3/4.7.2, Component Cooling Water System
- 4. Section 3/4.9.8, Residual Heat Removal and Coolant Circulation 3.1.2 FSAR
- 1. Section 9, Auxiliary and Emergency Systems 3.1.3 Operating Diagrams
- 1. 5613-M-3047, Sheets 11 and 2, CVCS - Charging and Letdown System
- 2. 5613-M-3030, Sheets 11 through 5, Component Cooling Water System Outside Containment
- 3. 5613-M-3020, Sheets 11 and 2, Primary Water System 3.1.4 Procedures
- 1. EPJP-20101, EPIP-20101, Duties of Emergency Coordinator
- 2. 3-EOP-E-0, Reactor Trip Or Safety Injection
- 3. 3-ONOP-019, 3-0NOP-019, Loss of Intake Cooling Water
- 4. 3-ONOP-04l 3-0NOP-041.1, .1, Reactor Coolant Pump Off-Normal
- 5. 0-OP-012, Service Water System
- 6. 3/4-OP-030, 3/4-0P-030, Component Cooling Water System
- 7. 3-OP-041.1, 3-0P-041.l, Reactor Coolant Pump
- 8. PC/M 00-016, CRN M-10471, Replacement M-10471, CCW Surge Tank Level Indicator I W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 5 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 6/9/03 6/9/03 3.1.5 3.1.5 Miscellaneous Documents Miscellaneous Documents (i.e, (i.e, PCIM, PCIM, Correspondence) Correspondence) 1.
- 1. PC/M 91-064, Charging Pump Service PCIM Service Water Connections Connections 2.
- 2. PC/M 92-108, Replacement of Raw Water and PCIM and Service Water Systems 3.
- 3. PC/M 93-034, PCIM 93-034, CCW System Reconfiguration CCW System Reconfiguration to HHSI Pumps Pumps Seal/Thrust Seal/Thrust Bearing Coolers
- 4. PC/M 94-096, Removal of Valves CV-3-2202 PCIM
- 5. PC/M 96-093, Addition of Unit 4 CCW Head Tank PCIM
- 6. PC/M 96-092, Addition ofU-3 PCIM of U-3 CCW Head Tank
- 7. Precautions, Limitations, and Setpoint Document
- 8. PC/M 00-016, CRN M-10471, CCW Surge Tank Level Indicator PCIM Replacement 3.2 Records Required 3.2.1 None 3.3 Commitment Documents 3.3.1 NRC Inspection Report 89-053, March 14, 1990 3.3.2 JPN-PTN-SENP-95-026, Safety Evaluation for CCW Flow Balance and Post Accident Alignment Requirements to Support Current and Uprated Conditions (LER 250/95-006)
W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I CAUTION CAUTION If any If any RCP RCP bearing bearing temperature temperature annunciator annunciator alarm alarm actuates actuates ANDAND its its associated associated motor bearing temperature is motor bearing temperature greater than is greater than 195<F, THEN trip 195 CF. THEN trip the the reactor reactor and and stop stop the the affected RCP(s). affected RCP(s). r----------N~S----------I I II
- Steps 1I and Steps are IMMEDIATE and 22 are IMMEDIATE ACTION steps. steps.
I
- I
- Foldout page Foldout should be page should be monitored monitored throughout throughout this procedure.
this procedure. I I
- I .
- A time delay exists on TR-320 TR-320 from when an RCP parameter exceeds its setpoint to I I when the recorder provides indication and alarm. Use the RCP mimic display on II ERDADS as a backup to TR-320 TR-320 to monitor affected RCPRCP parameters.
I ERDADS I 1 Verify Flow In Both Component Cooling Perform the following: Water Headers - NORMAL
- a. IF starting an idle CCW pump will QI NOT
- FT-3-613A for header A overload an EDG, THEN start CCW pumps as necessary to establish flow in
- FT-3-613B for header 8 FT-3-6138 B both headers.
- b. IF CCW flow to RCPs can NOT be established, THEN manually trip the reactor AND verify reactor trip using the EOP Network, THEN stop all RCPs.
- c. Isolate Letdown and Excess Excess Letdown.
d.
- d. IF IF any any charging pump pump is running, THEN operate atat maximum speed untiluntil Attachment I1 isis completed.
e.
- e. Dispatch Dispatch anan operator operator to to establish establish emergency cooling emergency cooling water water to desired desired charging pump charging pump using using Attachment I. 1.
W97/daj/ev/ev W97/daj/ev/ev
ProcedureNo.: Procedure No.:
Title:
ProcedureTitle: Procedure Page: Page: 7 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling WaterWater Malfunction Malfunction 5/24/02 5/24/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT OBTAINED NOTOBTAINED Ip NOTES NOTES I I . . The top The top of of the the component component cooling cooling water water surge surge tank tank divider divider plate plate isis located located at at I II approximately 25% approximately indicated level. 25% indicated level. II I . If aa cross If cross tie tie valve valve between between the units is the units is leaking leaking or or open, open, thethe surge surge tank tank on on the the opposite opposite I I unit may unit may be be experiencing experiencing level control problems. level control problems. II I .* If in If in Modes Modes 1I through through 3, 3, and CCW System and CCW level is System level is NOT NOT maintained maintained within within the the CCW CCW I II Head Tank, Head Tank, restore restore CCW CCW System System level level to to be within the be within the CCW CCW Head Head Tank within 24 Tank within 24 *I hours. I I II ** Ll-3-613A and L/-3-614A L/-3-613A Ll-3-614A are NOT NOT overlapping (i.e., L/-3-614A Ll-3-614A will will go off scale low II I before L/-3-613A before Ll-3-613A comes off its high peg with decreasing level). II a... _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ a a a a a 2 Verify Component Cooling Water Surge Perform the following: Tank Level Being Maintained
- 1. Open Component Cooling Water Surge
- a. Component Cooling Water Surge Tank Tank Makeup, MOV-3-832 as necessary Level, U-3-613A-Ll-3-613A - to add makeup.
- GREATER THAN 25% 2. IF Component Cooling Water Surge Tank Level can NOT be maintained, AND THEN perform the following:
- STABLE OR INCREASING a) Trip the reactor.
b) Stop all RCPs. c) Perform 3-EOP-E-O, REACTOR TRIP OROR SAFETY SAFETY INJECTION, while continuing with this this procedure. procedure. 3.
- 3. OBSERVE OBSERVE NOTESNOTES PRIOR PRIOR TO TO STEP STEP 66 and Go and Go To To Step Step 6.6.
W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE II II RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 33 Check IfIf Component Check Component Cooling Cooling Water Headers Water Headers Should Be Should Be Tied Tied Together: Together:
- a. Check CCW
- a. Check CCW headers headers - SPLIT
- SPLIT a.
- a. Go Go toto Step Step 32.
32.
- b. Check
- b. Check ifif flow flow has been lost has been lost in any CCW in any CCW b.
- b. IF IF flow flow in in both both CCW CCW headers headers is is normal, normal, header header THEN THEN go go to to Step Step 32.
32.
- FT-3-613A for FT-3-613A header A for header A
- FT-3-613B for FT-3-613B for header header B B 4 Tie Component Cooling Tie Component Cooling Water Water Headers Headers Together:
- a. Direct operator to terminate activities which require splitting CCW headers
- Heavy load transport in cask wash area
- In-service testing
- b. Locally open CCW pump Suction Header Sectionalizing valves:
Sectionalizing
** 3-787A 3-787A
** 3-787B 3-787B
- c. Locally open CCW pump Discharge Header Sectionalizin Sectionalizing g valves:
** 3-787C 3-787C
** 3-787D 3-7870
- d. Locally
- d. Locally open open allall Component Component Cooling Cooling Water Water Heat Exchanger Outlet Heat Outlet Header Header Sectionalizin Sectionalizing g valves:
** 3-787E 3-787E
** 3-787F 3-787F
** 3-787G 3-787G
** 3-787H 3-787H 55 Go To Go Step 32 To Step 32 W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 9 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 6/9/03 STEP f ACTION/EXPECTED ACTION/EXPECTED RESPONSE RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I I* NOTES NOTES I II . . Steps 66 through Steps through 31 Water System 31 are are only applicable when only applicable when leakage leakage from from thethe Component Component Cooling Cooling II I* Water System isis in in progress. progress. II II .* When leakage When leakage has with Step has been been located located and isolated, recovery and isolated, recovery actions actions shall shall continue continue starting starting II Step 25. 25. L _______________________ II I with ~ L________.____J 6 Establish Stable Establish Stable Plant Parameters Plant Parameters
- a. Station
- a. Station aa watch at at Header Header BB local local surge surge tank level tank indicator, U-3-615 level indicator, Ll-3-615
- b. Isolate Letdown and Excess Letdown
- c. Dispatch an operator to establish emergency cooling water to desired charging pump using Attachment 11
- d. Dispatch an operator to locate and isolate d. if the system walkdown fails to identify IF COW System leakage by performing a CCW the leak and CCW Surge Tank Level is System Walkdown. still decreasing OR Q makeup still required, THEN perform the following:
- 1. Stop and PULL-TO-LOCK all but one CCW Pump.
- 2. Attempt to determine if the leak is in a Heat Exchanger by removing ONLY one COW CCW Heat Exchanger from service at aa time using the CCW isolation following COW isolation valves:
HX Inlet Outlet 3A 3A 3-712A 3-712A 3-713A 3-713A 3B 3B 3-712B 3-712B 3-713B 3C 30 3-712C 3-7120 3-713C 3-7130 W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 10 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Component Cooling Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP I I ACTION/EXPECTED I STEP II II RESPONSE ACTION/EXPECTED RESPONSE RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 7 Check IfIf Additional Check Additional Makeup Makeup Is Is Required: Required:
- a. Component Cooling
- a. Component Cooling Water Surge Tank Water Surge Tank a.
- a. Perform Perform the the following:
following: Level, LI-3-613A Level, Ll-3-613A-- DECREASING DECREASING OR OR EMPTY EMPTY 1)
- 1) IF surge tank level can NOT be IFsurgetanklevelcanNOTbe maintained during subsequent subsequent recovery actions, THEN do Steps Steps 7b, 7b, 7c 7c and and 7d.
7d.
- 2) Go to Step 8.
GotoStep8.
- b. Locally open Component Cooling Water Header A Makeup Water Isolation, 3-711A 3-71 1A
- c. Throttle closed DWDS-001 DWDS-OO1 to provide Demin Water Flow to the CCW Surge Tank
- d. Locally throttle Demin Water Supply Valve, 3-724D, as necessary to maintain surge tank level stable or increasing 8 Verify CCW Pump(s) - NOT CAVITATING:
- Stop any cavitating CCW pump(s) and place all CCW pumps in Pull-To-Lock.
- a. Running CCW pump amps - STABLE -
- b. Component Cooling Water Header Flows- Flows -
STABLE
- FI-3-613A
- FI-3-613B W97/daj/ev/ev W97/daj/ev/ev
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 11 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Malfunction Water Malfunction 5/24/02 5/24/02 STEP f ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE f RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED I CAUTION CAUTION After dispatching After dispatching an an operator operator toto locally locally split split the the Component Component Cooling Cooling Water Water headers, headers, the Control the Control Room Room operator operator shall shall continue continue with with Step Step 11. 11. 9 Check IfIf Headers Check Headers Should Should Be Split Between Be Split Between The BAnd The B And C CCW Pumps: C CCW Pumps:
- a. Leakage - KNOWN
- a. Leakage - KNOWN TO EXIST EXIST ON ON a. IFf leakage leakage is is on on header header A OR Q location location of HEADER B HEADER B leakage is NOT known, is NOT known, THEN go to to Step 13.
Step 13.
- b. Check on one of the following pumps - - b.
- b. Perform the following:
RUNNING RUNNING 1)
- 1) IFIF CCW pumps were placed in
- 3A CCW Pump 3ACCW PULL-TO-LOCK PULL-TO-LOCK due to cavitation, THEN DO NOT start the 3A or 3B OR CCW Pump AND go to Step 9c.
- 3B CCW Pump 2) E IF ONLY 3C CCW Pump running, THEN start 3A or 3B CCW Pump.
- c. Place the 3C CCW Pump in STOP and PULL-TO-LOCK PULL-TO-LOCK 10 10 Isolate BB CCW Header Locally close the listed valves to separate the headers.
- a. Check the CCW Header Sectionalizin Sectionalizing g valves closed
- CCW Hx Outlet Hdr Sect Valve, 3-787G OR CCW Hx Hx Outlet Hdr Hdr Sect Valve, Valve, 3-787H 3-787H
- CCW Pump CCW Pump Dischg Dischg Hdr Hdr Sect Sect Valve, Valve, 3-787D 3-7870
** CCW Pump CCW Pump SuctSuct Hdr Hdr Sect Sect Valve, Valve, 3-787B 3-787B
- CCW CCW Sys Sys Demin Water Primary Demin Water Primary Water Water Supply, 3-737C Supply,3-737C 11 11 Check Check CCWCCW PumpPump Operation Operation Start either Start either 3A 3A oror 3B 3B CCW CCW Pump.
Pump.
- a. Either
- a. Either 3A 3A or 3B CCW or 3B CCW Pump Pump running running 12 12 GotoStepl6 Go to Step 16 W97/dajlev/ev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 12 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I I~----------NmE----------- NOTE I I 3C CCW 3C CCW PumpPump should should be be off off ifif 38 3B CCW CCW Pump Pump is available available to to minimize minimize the the potential potential for for I I* exceeding the exceeding the flow flow limits limits onon the the CCWCCW Heat Heat Exchangers. Exchangers. I L... 1 3~-----------------------~ a a a a 13 Check If If Headers Should Be Be Split Between The A A And And B B CCW Pumps:Pumps:
- a. Check
- a. Check on on one one ofof the following following pumps pumps - - a. Perform
- a. Perform the following:
RUNNING RUNNING
- 1) IF CCW pumps were placed in in
- 3 B CCW Pump 3B P ump PULL-TO-LOCK due to cavitation, OR THEN DO NOT start the 3B or 3C
- 3000W 3C CCW Pump CCW Pump AND go to Step 13b.
- 2) IF ONLY 3A CCW Pump running, THEN start 3B or 3C CCW COW Pump.
- b. Place the 3A CCW COW Pump in STOP and PULL-TO-LOCK 14 Isolate A CCW Header Locally close the listed valves to separate the header.
- a. Check the CCW COW Header Sectionalizing valves closed
- COW Hx Outlet Hdr Sect Valve, 3-787E CCW OR COW CCW Hx Outlet Hdr Sect Valve, 3-787F
- COW CCW Pump Dischg Hdr Sect Valve, 3-7870 3-787C
- COW Pump Suct Hdr Sect Valve, CCW 3-787A
- CCW Sys Demin Water Primary Water COW Supply, 3-7370 Supply,3-737C 15 Check CCW Pump Operation 3C COW Start either 3B or 30 CCW Pump.
Pump.
- a. Either
- a. Either 3B or 30 3B or 3C COWCCW Pump Pump running 16 Check If If Components Supplied By The B B Go to Step 21.
Header Should Should Be Shutdown: Shutdown:
- Header Header BB Flow, FI-3-613B - NO Flow, FI-3-613B - NO FLOW FLOW OR OR
- Local Header BB Surge Local Header Surge TankTank Level, Level, LI-3-61 U-3-615 5
- EMPTY
- EMPTY OR OR
- Local Header BB Surge Local Header Surge TankTank Level, Level, Ll-3-61 U-3-615 5
- DECREASING
- DECREASING IN IN AN AN UNCONTROLLED UNCONTROLLED MANNER MANNER W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 13 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 3/29/04 3/29/04 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I I NOTE I I The remainder The remainder of TRIP OR OR SAFETY of this procedure shall this procedure SAFETY INJECTION, shall be performed concurrently be performed concurrently withwith E-O, E-O, REACTOR REACTOR I TRIP INJECTION, and and anyany other applicable Emergency other applicable Emergency Operating Operating I Procedures. Procedures. I L _______________________ J 1717 Shutdown Components Components Cooled Cooled By By The B B Component Cooling Component Cooling Water Header: Header:
- a. Manually trip
- a. Manually trip the the reactor reactor
- b. Place the following in Pull-To-Lock or Off:
** RCPs All RCPs All
** 3BRHRPum 3B RHR Pump p
- 3B Containment Spray Pump
- 3B Emergency Containment Cooler
- 3C Emergency Containment Cooler
- c. Check component cooling water to Unit 3 c. Go to Step 18.
High-Head SI pumps - ALIGNED TO UNIT 3 UNIT3
- d. Place the following in Pull-To-Lock:
- 3A High-Head SI pump
- 3B High-Head SI pump
- e. Realign Unit 3 High-Head SI pumps component cooling water to Unit 4 per 3-OP-030, Subsection 7.3 3-0P-030,
- f. WHEN the Unit 33 High-Head SI pumps have been realigned to Unit 4, THEN place the Unit 33 High-Head SI pumps back in AUTO 1188 Check The Following Valves Closed:
- a. HCV-3-137, HCV-3-137, ExcessExcess Letdown Flow a. Close HCV-3-137.
Controller Controller
- b. WHEN HCV-3-137 HCV-3-137 has has been closed for
- b. CV-3-387, Excess
- b. Excess Letdown Heat Heat 12 hours, THEN cose close CV-3-387.
IL hours, Exchanger Isolation Exchanger Isolation Valve From Cold Valve From Cold Leg Leg - - To Excess To Excess Letdown Letdown 119 9 Check Check If If Components SuppliedSupplied ByBy Cask Cask Go to Go to Step Step 21. 21. Wash Area Piping Wash Area Piping Should Should BeBe Isolated: Isolated:
- Check Check component cooling water component cooling water cask cask wash wash area piping - ALIGNED area piping - ALIGNED TO TO THE THE BB HEADER PRIOR HEADER PRIOR TO TO COMPONENT COMPONENT COOLING COOLING WATER WATER MALFUNCTION MALFUNCTION W97/dajlev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 14 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 IFáiEP STEP I IFACTIONIE ACTION/EXPECTED XPECTED RESPONSE RESPONSE II II RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I CAUTION CAUTION Operation of Operation of the the Charging Charging Pump Pump without without cooling cooling at at less less than than maximum maximum speed speed will will result in result in excessive excessive couplmg coupling oil oil temperatures. temperatures. TheseThese temperatures temperatures may may exceed exceed the the design limits within design limits within 2020 seconds seconds at at half half load. load. AtAt maximum maximum speed,speed, temperature temperature limits limits are expected are expected to remain within to remain within specification specification limits limits indefinitely. indefinitely. 20 Isolate Components Isolate Components SuppliedSupplied By By Cask Cask Wash Area Piping: Piping: letdown orifice
- a. Close all letdown orifice isolation isolation valves valves
- b. Close
- b. High Pressure Close High Pressure Letdown Letdown Isolation Isolation From Loop B Cold Leg, LCV-3-460
- c. Increase charging flow to maximum on one pump
- d. Start and stop charging pump at maximum speed as necessary to maintain Pressurizer level and RCP seal temperatures
- e. Dispatch operator to establish emergency cooling water to desired charging pumps using ATTACHMENT 11
- f. WHEN cooling water established to charging pump, THEN operate the pump as necessary to maintain Pressurizer level and RCP seal cooling
- g. Verify cask wash area component cooling g. Dispatch operator to close the following:
water piping - NOT LEAKING
- 1) Both CCW Header Supply To Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx.
- 3-835E
- 3-835F
- 2) Both CCW Header Return From Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx.
- 3-835G
- 3-835H 3-835H 21 Check If If Components Supplied By The A Go to Step 25.
Header Should Be Shutdown: Shutdown:
- Header Flow, FI-3-613A Header A Flow, FI-3-613A - NO
- NO FLOW FLOW OR OR
- Header Surge Tank Header A Surge Tank Level, Level, LI-3-613A LI-3-613A
- EMPTY
- EMPTY OR OR
- Header Header A A Surge Surge Tank Level, LI-3-613A Tank Level, LI-3-613A
- DECREASING
- DECREASING IN IN AN AN UNCONTROLLED UNCONTROLLED MANNER MANNER W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 15 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 I STEP STEP I I ACTION/EXPECTED ACTION/EXPECTED RESPONSE RESPONSE II II RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 22 Shutdown Components Shutdown Components Cooled Cooled ByBy The The AA Component Cooling Component Cooling Water Water Header: Header:
- a. Place
- a. Place the following in the following Pull-To-Lock or in Pull-To-Lock or Off:
Off:
** 3ARHRPum 3A RHR Pump p
** 3A Containment Spray 3A Containment Spray Pump Pump
** 3A Emergency Containment 3A Emergency Containment Cooler Cooler
- b. Check component cooling water to Unit 4
- b. b.
- b. Go to Step 23.
High-Head SI pumps - ALIGNED TO UNIT 3 UNIT3
- c. Place the following pump in Pull-To-Lock:
- 4A High-Head SI Pump
- 4B High-Head SI Si pump
- d. Realign Unit 4 High-Head SI pump component cooling water to Unit 4 per 4-OP-030, Subsection 7.3 4-0P-030,
- e. WHEN the Unit 4 High-Head SI pumps have be realigned to Unit 4 component cooling water, THEN place the Unit 4 High-Head SI pumps back in AUTO 23 Check If Components Supplied By Cask Wash Area Piping Should Be Isolated:
Go to Step 25.
- Check component cooling water cask wash area piping - ALIGNED TO THE A HEADER HEADER PRIOR TO COMPONENT COOLING WATER MALFUNCTIONMALFUNCTION W97/daj/ev/ev W97/daj/ev/ev
ProcedureNo.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 16 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 I STE19 ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I CAUTION CAUTION Operation of Operation of the the Charging Charging Pump Pump without without cooling cooling atat less less than than maximum maximum speed speed will will result in excessive result in excessive coupling coupling oil oil temperatures. temperatures. TheseThese temperatures temperatures maymay exceed exceed thethe design limits within design limits within 20 seconds at 20 seconds at half load. At half load. maximum speed, At maximum speed, temperature temperature limits limits are expected to are expected remain within to remain within specification specification limits limits indefinitely. indefinitely. 24 Isolate Components Isolate Components SuppliedSupplied By By Cask Cask Wash Area Piping:
- a. Close all letdown orifice isolation valves Pressure Letdown Isolation
- b. Close High Pressure Isolation From Loop 8B Cold Leg, LCV-3-460
- c. Increase charging flow to maximum on one pump
- d. Start and stop charging pump at maximum speed as necessary to maintain Pressurizer level and RCP seal temperatures
- e. Dispatch operator to establish emergency cooling water to desired charging pumps using ATTACHMENT 1 I
- f. WHEN cooling water established to a charging pump, THEN operate the pump as necessary to maintain Pressurizer level and RCP seal cooling
- g. Verify cask wash area component cooling g. Dispatch operator to close the following:
water piping - NOT LEAKING
- 1) Both 80th CCW Header Supply To Charging Pumps, Spent Fuel Pit Hx, Hx, And Seal Non-Regen Hx, Seal Water Hx.Hx.
- 3-835E
- 3-835F 3-835F 2)
- 2) Both 80th CCW CCW Header Header Return Return From From Charging Pumps, Pumps, Spent Spent Fuel Fuel Pit Pit Hx, Hx, Non-Regen Hx, Non-Regen Hx, And And Seal Seal Water Water Hx.
Hx.
- 3-835G
** 3-835H 3-835H W97/daj/ev/ev W97/daj/ev/ev
[Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 17 17 L 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction Approval Approval Date: Date: 6/9/03 6/9/03 STEP I I ACTION/EXPECTED I STEP If I RESPONSE ACTION/EXPECTED RESPONSE RESPONSE RESPONSE NOT NOTOBTAINED OBTAINED I 25 Check IfIf Headers Check Headers Are Are Leaking: Leaking:
- a. Locally check
- a. Locally check Header Header B B Surge Surge Tank Level, Tank Level, a. Go
- a. Go to to Step Step 25d.
25d. LI-3-615 - LEVEL LI-3-615 ABOVE BOTTOM LEVEL ABOVE BOTTOM OF OF SIGHTGLASS SIGHTGLASS
- b. Stop makeup to the B
- b. B header c.
- c. IF header B is intact, THEN go to
- c. Check header
- c. Check header B B surge surge tank tank level level -
- Step Step 32.
32. DECREASING DECREASING
- d. Go to Step 26.
GotoStep26.
- d. Check Header A Surge Tank Level, LI-3-613A - GREATER THAN 0%
- e. Stop makeup to the A header
- f. IF header A is intact, THEN OBSERVE
- f. Check Header A Surge Tank Level - - CAUTION AND NOTE PRIOR TO DECREASING STEP 27 and go to Step 27.
26 Try To Establish One Intact Component Cooling Water Header:
- a. Continue efforts to locate and isolate Component Cooling Water System leakage
- b. Continue adding makeup to intact portions of the Component Cooling Water System
- c. Return to Step 77 W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 18 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED CAUTION CAUTION Transferring components Transferring components to to the the A header may A header may cause cause surge surge tank tank level level to to decrease decrease rapidly.
~-----------------------~
I IL __ Steps Steps __ 27 through ___ 31 are _only NOTE NOTE applicable when only applicable when the B CCW ___ CCWheaderis _header _ _is_ not_ intact. II
~ I 27 Transfer Components Supplied By Cask Wash Area Piping To The A Header:
- a. Verify cask wash area piping - INTACT
- a. Go to Step 28.
- b. Isolate cask wash piping from the B header: b. Go to Step 28.
- 1) Close CCW Header B Return From Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx, 3-835H
- 2) Close CCW Header B B Supply To Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx, 3-835E
- c. Align cask wash area piping to the A header:
- 1) Open CCW Header A Supply To 1)
Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, Hx, And Seal Water Hx, Hx, 3-835F
- 2) Open
- 2) Open CCW CCW Header Header A Return Return From From Charging Charging Pumps, Pumps, Spent Spent Fuel Fuel Pit Pit Hx, Hx, Non-Regen Non-Regen Hx, Seal Water Hx, And Seal Water Hx, Hx, 3-835G W97/daj/ev/ev W97/daj/ev/ev
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 19 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Malfunction Water Malfunction 5/24/02 5/24/02 STEP If I ACTION/EXPECTED I STEP II II RESPONSE ACTIONIEXPECTED RESPONSE RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 28 Transfer 3C Transfer Emergency Containment 3C Emergency Containment Cooler Cooler To The To The A A Header: Header:
- a. Isolate 3C
- a. Isolate Emergency Containment 3C Emergency Containment Cooler Cooler a. Go
- a. Go to to Step Step 29.
29. from the from header: the BB header:
- 1) Close
- 1) Close Emergency Emergency CoolerCooler C Tie To C Tie To CCW Header CCW Header B, B, 3-652 3-652
- 2) Close
- 2) Close CCW CCW Header Header BB Tie Tie To To Emergency Containment Emergency Containment Cooler Cooler C,C, 3-650 3-650
- b. Align 3C
- b. Align Emergency Containment 3C Emergency Containment Cooler Cooler to to the A header:
- 1) Open CCW Header A Tie To Emergency Containment Cooler C, 3-651
- 2) Open Emergency Cooler C Tie To CCW Header A, 3-653 29 Transfer Components To The A Header:
- a. Isolate components from the B B header: a. Go to Step 30.
- 1) Close CCW Return Header B B Isolation, 3-835B
- 2) Close CCW Header B B Supply To RCP, Containment Coolers, Rod Drive Coolers, Primary Shield, Excess Letdown Hx, Hx, Evaporator Evaporator Coolers, Coolers, And Sample Coolers, 3-835C b.
- b. Align components components to to the the A header:
header:
- 1) Open CCW
- 1) Open CCW HeaderHeader A A Supply Supply To To RCP, RCP, Containment Containment Coolers, Rod Drive Coolers, Rod Drive Coolers, Primary Shield, Coolers, Primary Shield, Excess Excess Letdown Letdown Hx, Hx, Evaporator Evaporator Coolers, Coolers, And And Sample Sample Coolers, Coolers, 3-835D 3-8350 2)
- 2) Open Open CCWCCW Return Return Header Header A A Isolation, Isolation, 3-835A 3-835A W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 20 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 I STEP I I ACTIONIEXPECTED ACTION/EXPECTED RESPONSE II II RESPONSE NOT OBTAINED II 30 Isolate CCW Pump B B From The B B Header:
- a. Place CCW pump C C in Pull-To-Lock
- b. Check CCW pump B B - ALIGNED TO
- IF CCW pump B
- b. IE B is already aligned to HEADER B HEADER B header A, THEN go to Step 32.
- c. Place CCW pump BB in in Pull-To-Lock Pull-To-Lock
- d. Locally isolate CCW pump BB from the BB d. CCW pump B
- d. IF COW B can NOT be isolated isolated header: from the B B header, THEN perform the following:
- 1) Locally close at least one Component 1)
Cooling Water Heat Exchanger Outlet a) Locally verify at least one Header Sectionalizing valve: Component Cooling Water Heat Exchanger Outlet Header 3-787G Sectionalizing valves - CLOSED:
- 3-787H
- 3-787E
- 2) Locally close CCW pump Discharge ** 3-787F Header Sectionalizing Valve, 3-787D b) Locally verify CCW pump Discharge
- 3) Locally close CCW pump Suction Header Sectionalizing Valve, 3-Header Sectionalizing Valve, 3-787B 787C - CLOSED c) COW pump Suction Locally verify CCW Header Sectionalizing Valve, 3-787A
- CLOSED d) GoGotoStep32.
to Step 32. 31 Align CCW Pump B To The A Header:
- a. Locally open both Component Cooling Water Heat Exchanger Outlet Header Sectionalizing valves:
- 3-787E
- 3-787F
- b. Locally open CCWCOW Pump Discharge Header Sectionalizing Valve, 3-787C
- c. Locally open CCWCOW Pump Suction Header Sectionalizing Valve, 3-787A
- d. Check flow on the A header d. Start the CCWCOW Pump B W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 21 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 STEP I I ACTION/EXPECTED I STEP II II RESPONSE ACTIONIEXPECTED RESPONSE RESPONSE RESPONSE NOT NOTOBTAINED OBTAINED I 32 Verify Component Verify Component Cooling Cooling Water Water From From Unit 44-- NOT Unit NOT REQUIRED: REQUIRED:
- a. Unit
- a. Unit 33 CCW CCW headers headers filled filled and and intact intact a. Return
- a. to Step 2.
ReturntoStep2.
- b. Verify CCW pumps - AT LEAST
- b. - LEAST ONE b. Start a Standby CCW pump.
b. RUNNING RUNNING
- c. Verify flow
- c. flow in in at at least least one one intact intact CCW CCW c. Perform Perform the following:
header: header:
- 1) Try to establish flow in at least one
- Fl-3-61 3A for header A FI-3-613A intact CCW header.
** FI-3-613B for header B 2) IF flow in at least one intact CCWCOW header can NOT be established, THEN OBSERVE NOTE PRIOR TO STEP 34 and go to Step 34.
- d. Verify intake cooling water flow to all in d. Perform the following:
service CCW heat exchangers
- 1) Try to establish intake cooling water
- Fl-3-1407 for Hx A FI-3-1407 flow to in-service CCW COW heat exchangers.
- Fl-3-1408 for Hx B FI-3-1408 B
- 2) Stop components cooled by
- FI-3-1409 for Hx C component cooling water as necessary to stabilize component cooling water temperature.
- 3) IF any component cooled by component cooling water must be operated JjQ AND stable component cooling water temperature can NOT maintained, THEN OBSERVE be maintained, NOTE PRIOR TO STEP 34 and go go to Step 34.
33 OBSERVE CAUTION PRIOR TO STEP 41 And GoGo To Step 41 To Step 41 W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 22 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I I NOTE NOTE I Steps 34 Steps 34 through through 40 are are only only applicable applicable when when component component cooling cooling water water from from Unit Unit 4 isis I L _______________________
*p required and required and the the Unit Unit 33 CCW CCW Headers Headers are are intact intact and and filled.
filled.
~
Ii L __._J 34 Prepare To Establish CCW Prepare CCW Flow From Unit 4: Unit4:
- a. Obtain permission from Nuclear Plant a. DO NOT CROSS-CONNECT CCW Supervisor to cross-connect Unit 3 and SYSTEMS. OBSERVE CAUTION Unit 4 component cooling water systems PRIOR TO STEP 41 and go to Step 41.
- b. Verify Unit 4 component cooling water b. Direct Unit 4 RCO to perform the headers - TIED TOGETHER
- following:
- 1) Stop spent fuel transfer in Unit 4 cask wash area.
- 2) Tie Unit 4 component cooling water headers together using 4-0P-030, 4-OP-030, COMPONENT COOLING WATER SYSTEM.
- c. Verify Unit 4 CCW pumps - AT LEAST
- c. Direct Unit 4 RCO to start CCW pumps TWO RUNNING as necessary to establish two Unit 4 CCW pumps running.
- d. Verify Unit 4 CCW Heat Exchangers - ALL - d. Direct personnel to restore out-of-IN SERVICE service CCW Heat Exchanger to service.
- e. Direct Unit 4 RCO to start intake cooling water pumps as necessary to establish at least two Unit 44 intake cooling water pumps running
- f. Direct Direct Unit Unit 4 RCO to closely monitor monitor Unit Unit 44 CCW CCW System
- g. Locally Locally verify thethe following valves - OPEN
- 3-789A, 3-789A, PASS Gas Gas Compressors Compressors And Boric Boric Acid Evaporator CCW Acid Evaporator CCW Supply Supply
- 3-7898, 3-789B, PASS PASS GasGas Compressors Compressors And And Boric Boric Acid Acid Evaporator Evaporator CCW CCW Outlet Outlet
- 4-789A, PASS 4-789A, PASS GasGas Compressors Compressors And And Boric Boric Acid Evaporator CCW Acid Evaporator CCW Supply Supply
** 4-789B, 4-789B, PASS PASS GasGas Compressors Compressors And And Boric Boric Acid Evaporator CCW Acid Evaporator CCW Outlet Outlet W97/daj/evlev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 23 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Malfunction Water Malfunction 5124/02 5/24/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I NOTE NOTE I I Unit 33 CCW Unit CCW surge surge tanks tanks are isolated to are isolated prevent loss to prevent of Unit loss of component cooling Unit 44 component cooling water water I L _______________________ I through Unit through surge tank Unit 33 surge tank vent lines when vent lines when thethe CCW CCW Systems Systems areare cross-connected. cross-connected. ~ I L 35 35 Isolate Unit Isolate Unit 33 CCW CCW Surge Surge Tank:
- a. Locally check
- a. check Component Component Cooling Water a. Locally close
- a. Locally close 3-711A.
3-71 1A. Header A Header A Makeup Makeup Water Water Isolation, Isolation, 3-711A-3-71 1A - CLOSED
- b. Locally close the following valves:
- 3-710A, CCW Header A Surge Tank Isolation Isolation
- 3-710B, CCW Header B Surge Tank Isolation 36 Establish CCW Flow From Unit 4:
- a. Locally unlock both Unit 3 - Unit 4 CCW Tie Between Boric Acid Evaporator And Waste Gas Compressor valves
** 779A 779A
** 779B 779B
- b. Direct Unit 4 RCO to locally open both CCW Header Makeup Isolation Valves
** 4-711A 4-711A
** 4-711B 4-711B
- c. Stop all Unit 3 CCW pumps
- d. Locally
- d. Locally throttle open Unit 33 - Unit
- Unit 44 CCW CCW Tie Between Boric Acid Evaporator And Waste Gas Compressors (Inlet), 779A 37 Maintain Maintain Stable Unit 44 CCW Stable Unit CCW Inventory:
Inventory: Direct Direct Unit Unit 44 RCO RCO to to add add makeup makeup as as necessary to stabilize necessary stabilize Unit Unit 44 CCW CCW System
- LI-4-614A - Stable Stable inventory using inventory using one one oror both both of of the the following:
- LI-4-61 3A - Stable LI-4-613A - Stable
- Open component Open component Cooling Cooling Water Water Surge Surge Tank Makeup, Tank Makeup, MOV-4-832.
MOV-4-832.
- Locally Locally throttle throttle Demin Demin Water Water Supply Supply Valve,4-724D.
Valve, 4-724D. W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 24 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Component Cooling Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I
** NOTE NOTE I The top The of the top of the component component cooling cooling water water surge surge tank tank divider divider plate plate is is located located at at I approximately 25%
approximately 25% indicated indicated level. level, I L _______________________ J Ia L________J 38 Surge Tank Level, L1-4-613A Maintain Unit 44 Surge Ll-4-613A Perform the following: GREATER THAN 25%
- GREATER
- a. Locally Locally close close both both Unit Unit 33 - Unit
- Unit 4 CCW CCW Tie Between Boric Acid Evaporator And Waste Gas Compressor valves
- 779A
- 779B
- b. Determine and try to correct cause for Unit 4 CCW System level decrease.
- c. IF the cause for Unit 4 CCW System level decrease can be corrected, THEN return to Step 36.
- d. IF the cause for Unit 4 CCW System level decrease can NOT be corrected, THEN perform the following:
- 1) Locally open the following valves:
- 3-710A, CCW Header A Surge Tank Isolation
- 3-710B, CCW Header B B Surge Tank Isolation
- 2) Restart any previously running Unit 33 CCW pumps.
- 3) Locally
- 3) Locally lock lock both both Unit Unit 33 - Unit
- Unit 44 CCW Tie CCW Tie Between BoricBoric Acid Evaporator And Waste Gas Evaporator Gas Compressor valves
- 779A 779A
** 779B 779B
- 4) WHEN
- 4) WHEN makeup makeup to to Unit Unit 44 CCW CCW System is System is no no longer longer required, THEN THEN direct Unit direct Unit 44 RCO RCO to to locally locally close close CCW Header CCW Header Makeup Makeup Isolation Isolation Valve,4-711A Valve, 4-71 1A
- 5) GotoStep4l.
- 5) Go to Step 41.
W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 25 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 STEP I I ACTION/EXPECTED I STEP II II RESPONSE ACTIONIEXPECTED RESPONSE RESPONSE RESPONSE NOT NOTOBTAI OBTAINED NED I 39 Fully Open Fully Open Both Both Unit Unit 44 CCW Unit 33 - Unit
- Tie CCW Tie Between Boric Between Boric Acid Acid Evaporator Evaporator And Waste And Waste Gas Compressor Gas Compressor ValvesValves
** 779A 779A
** 779B 7798 40 Maintain Unit Maintain Unit 44 Component Component Cooling Cooling Water Water Temperatures:
Temperatures:
- a. Check Unit 4 Component Cooling Water a. Stop Unit 3 and Unit Unit 4 components as Header Temperature - LESS Supply Header - LESS THAN necessary to reduce necessary reduce heat heat load load on Unit Unit 4 120°F 120°F Component Cooling Water System.
- Tl-4-607A TI-4-607A
- Tl-4-607B TI-4-6078 W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 26 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED I CAUTION CAUTION If component If component cooling cooling waterwater to any any component component hashas been been lost lost and and can can not not bebe restored, that restored, that component component shall shall bebe maintained maintained in in PulI-To-Lock Pull-To-Lock or Off to prevent or Off prevent equipment damage. equipment damage. 41 Component Cooling Verify Component Cooling Water Is Is Being Being Perform the Perform the following: Supplied To The Following Supplied Following Components: Components:
- a. Verify headers headers are not not leaking, leaking, THEN
- High-head SI pumps locally align valves as necessary to establish component cooling water flow
- RHR pumps to each component. Refer to 3-0P-030, 3-OP-030, COMPONENT COOLING WATER
- Containment spray pumps SYSTEM for proper valve alignment.
- b. IF component cooling water can NOT be
- Emergency containment coolers established to any component, THEN perform the following:
- 1) Place the affected component(s) in Pull-To-Lock or Off.
- 2) DO NOT START AFFECTED COMPONENT(S) in subsequent steps.
- 3) DO NOT PLACE AFFECTED COMPONENT(S) IN STANDBY in subsequent steps.
42 Verify Proper Component Alignment:
- a. Restart previously running components
- High-head High-head SI pumps
- RHR pumps
- Containment Containment spray spray pumps pumps
- Emergency containment coolers
- b. Place
- b. idle components Place idle components in in standby standby
- High-head High-head SI SI pumps pumps
- RHR RHR pumps pumps
- Containment Containment spray spray pumps pumps
- Emergency containment Emergency containment coolers coolers W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 27 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP I I ACTION/EXPECTED I STEP II II RESPONSE ACTION/EXPECTED RESPONSE RESPONSE RESPONSE NOT OBTAINED NOT OBTAINED I 43 Establish Charging Establish Charging Flow:Flow:
- a. Locally verify
- a. Locally verify component component cooling cooling water flow a. Verify emergency
- a. emergency cooling cooling water has has from charging from charging pumps, pumps, FI-3-660 FI-3-660 been been established established to to desired desired charging charging pump pump using using attachment attachment 1. 1.
Check charging
- b. Check charging pumps pumps - AT LEAST
- LEAST ONE ONE b.
- b. IF any any charging charging pumps pumps were running running RUNNING RUNNING prior prior to component component cooling cooling water malfunction, malfunction, THEN start one one charging pump.
- c. Maintain minimum charging flow for RCP seal injection 44 Verify CCW To RCPs - AVAILABLE
- Perform the following:
- a. Verify component cooling water to RCPs - - 1. Verify reactor - tripped AVAILABLE
- 2. Verify all rcps - stopped
- b. Verify CCW Inlet valves - OPEN-
- 3. Close rcp thermal barrier ccw outlet,
- MOV-3-71 6A MOV-3-716A MOV-3-626.
- MOV-3-71 6B MOV-3-716B 4. Adjust charging flow and charging flow to regen heat exchanger, HCV-3-121 to maintain thermal barrier zP ~P greater than Oo inches of water.
- 5. Verify natural circulation.
- 6. Go to step 47.
Gotostep47. 45 Verify RCP Bearing CCW Outlet, MOV-3-730 Perform the following: OPEN
-OPEN
- a. Verify reactor - tripped
- b. Verify all
- b. all rcps - stopped Verify natural
- c. Verify natural circulation.
46 Verify RCP RCP Thermal Barrier CCW CCW Outlet, Outlet, Adjust charging flow and and charging flow to MOV-3-626 MOV-3-626 - OPEN
- OPEN regen heat regen heat exchanger, exchanger, HCV-3-121 HCV-3-121 to to maintain thermal maintain thermal barrier barrier DP DP greater greater thanthan 00 inches of inches of water.
water. W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 28 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 STEP I I ACTION/EXPECTED I STEP II I RESPONSE ACTION/EXPECTED RESPONSE RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 47 Verify Containment Verify Containment Cooling: Cooling:
- a. Check
- a. normal containment Check normal containment coolers coolers -
a.
- a. Go to Step 48.
GotoStep48. RUNNING RUNNING Establish normal containment cooling:
- b. Establish
- b. b. Consult with with Nuclear Nuclear Plant Plant Supervisor to determine if one of the following
- 1) Verify component
- 1) component cooling cooling water toto methods should be used methods should used to cool cool normal containment coolers normal containment coolers -
- containment:
containment: AVAILABLE
** Emergency containment coolers.
- 2) Verify Component Cooling Water To Normal Containment Cooler valve - - OR OPEN
** Containment purge.
- MOV-3-1417
- MOV-3-1418 48 Maintain Reactor Coolant System Circulation:
- a. Check RCPs - ALL STOPPED
- a. Go to Step 49.
GotoStep49.
- b. Obtain permission from Nuclear Plant b. Perform the following:
Supervisor to start RCP(s) 1)
- 1) Verify natural circulation.
- 2) Go to Step 49.
GotoStep49.
- c. Start RCP(s) using 3-OP-041.1, 3-0P-041.1, REACTOR COOLANT PUMP 49 Check If Letdown Letdown Or Excess Letdown Letdown Goto Go to Step 51.
Should Be Placed In Service:
- a. Charging
- a. pumps - AT LEAST Charging pumps - LEAST ONEONE RUNNING
- b. Letdown OR excessexcess letdown letdown - IN
- IN SERVICE PRIOR TO COMPONENT COOLING WATER WATER MALFUNCTION MALFUNCTION
- c. Letdown
- c. Letdown AND excess letdown AND excess letdown - SECURED
- SECURED W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 29 29 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 3/29/04 3/29/04 STEP I I ACTION/EXPECTED I STEP II II RESPONSE ACTION/EXPECTED RESPONSE RESPONSE RESPONSE NOT NOTOBTAINED OBTAINED I 50 Establish Letdown: Establish Letdown: Establish Establish excess excess letdown letdown
- a. Verify letdown
- a. Verify letdown orifice orifice isolation isolation valves valves -
- 1. Verify Excess
- 1. Excess Letdown Letdown Heat Heat Exchanger Exchanger CLOSED CLOSED CCW CCW outlet, outlet, CV-3-739, CV-3-739, OPEN.
OPEN. Locally verify Component Cooling Water
- b. Locally
- b. 2. Verify Excess Excess Letdown Letdown Flow Flow Controller, Flow From Flow From Non-regen Non-regen Heat Heat Exchanger, Exchanger, HCV-3-137 HCV-3-137 - CLOSED.
FI3620 or Controlotron Flow FI-3-620 Flow Indicator, Indicator, if 3. Verify Excess
- 3. Excess Letdown Isolation Isolation Valve installed installed CV-3-387 CV-3-387 - CLOSED.
CLOSED. Open Letdown
- c. Open Letdown From From Regen Regen Heat Heat 4. Locally Locally verify Component Component Cooling Cooling Water Exchanger Isolation, CV-3-204CV3204 Flow From Excess Letdown Heat
- d. Open High Pressure Letdown Isolation Exchanger, FI-3-624. IF flow is NOT From Loop B Cold Leg, LCV-3-460 available, THEN go to Step 51.
- 5. Verify Excess Letdown From Heat
- e. Manually control Low Pressure Letdown Exchanger to VCT Or RCDT, CV-3-389, Controller, PCV-3-145, to limit pressure is in the desired position:
spike when opening letdown orifice isolation valves ** RCDT - Divert
- f. Open letdown orifice isolation valves to OR establish desired letdown flow
- VCT - Normal
- g. Place Low Pressure Letdown Controller, PCV-3-145, in Automatic 6. Slowly open Excess Letdown Flow Control Valve, HCV-3-137.
- h. Place Charging pump controls in Automatic to maintain Pressurizer level 7. Close Excess Letdown Flow Control Valve, HCV-3-137.
- 8. Open Excess Letdown Heat Exchanger Isolation Valve From Cold Leg To Excess Letdown, CV-3-387.
- 9. Open Excess Letdown Flow Controller, HCV-3-137.
HCV-3-1 37.
- 10. Verify Excess Letdown Heat
- 10. Heat Exchanger Outlet Temperature, TI-3-139 -less - less than 190°F.
190°F.
- 11. IF
- 11. IF volume volume control tank temperature increases to greater increases greater than than 130°F, 130°F, THEN THEN Excess Letdown place Excess Letdown FromFrom Heat Heat Exchanger To VCT Or Or RCDT, CV-3-389, in RCDT in RCDT - Divert
- Divert position.
position.
- 12. Continue
- 12. Continue efforts efforts to to establish establish normal normal letdown. WHEN letdown. WHEN normal normal letdown letdown has has been established, THEN been THEN stop stop excess excess letdown. Continue letdown. Continue with with Step Step 51.
51. W97/daj/ev/ev W97/daj/ev/ev
ProcedureNo.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 30 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 STEP I I ACTION/EXPECTED I STEP II II RESPONSE ACTION/EXPECTED RESPONSE RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 51 Locally Verify Locally Verify Component Component Cooling Cooling Water Water Perform Perform the the following: following: Flow From Flow Seal Water From Seal Water Heat Heat Exchanger, Exchanger, Fl-3-618 FI-3-618 a. Place Excess
- a. Place Excess Letdown Letdown From From Heat Heat Exchanger To Exchanger To VCT VCT Or Or RCDT, RCDT, CV-3-389, CV-3-389, in RCDT in RCDT - Divert
- Divert position.
position.
- b. Close
- b. Close Excess Excess Letdown Letdown And RCP RCP Seal Seal Return To VCT, MOV-3-381.
Return MOV-3-381. 52 Locally Verify Component Locally Component Cooling Cooling Water Perform Perform the following: Flow From Spent Fuel Pool Heat Exchanger, Fl-3-622 FI-3-622 a. Monitor spent fuel pool pool temperatures. temperatures.
- b. Add makeup as necessary necessary to maintain spent fuel pool level greater than 7 inches below normal level of 57 feet.
53 Direct Nuclear Plant Supervisor To Evaluate Plant Conditions:
- a. Check for applicability to conditions listed in EPIP-20101, DUTIES OF EMERGENCY COORDI NATOR COORDINATOR
- b. Verify applicable Technical Specification b. Perform applicable Technical Limiting Conditions for Operation -- Specification corrective actions.
SATISFI ED SATISFIED 54 Verify Component Cooling Water System - - Perform the following: ALIGNED FOR NORMAL OPERATIONS
- a. WHEN normal system operation is possible, THEN realign the system using 3-OP-030, 3-0P-030, COMPONENT COOLING WATER SYSTEM
- b. f IF component cooling water is being supplied by Unit 4, THEN place both units units in in cold shutdown as soon as possible.
55 Go To Appropriate Plant Procedure As Determined Determined By By The The Nuclear Nuclear Plant Plant Supervisor Supervisor END OF END OF TEXT TEXT W97/dajlev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 31 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 ATTACHMENT 11 ATTACHMENT of 5) (Page 11 of5) (Page CONTROL OF CONTROL EMERGENCY COOLING OF EMERGENCY COOLING WATER WATER TO TO CHARGING CHARGING PUMPS PUMPS I-------------------------~ i NOTES NOTES I II .* Emergency cooling Emergency cam lock cooling water lock fitting SUPPLY water SUPPL hose has Y hose has aa quick quick disconnect disconnect fitting fitting onon one one endend andand I I aa cam on the fitting on other end. the other end. I II .* Loss of Loss of off-site seivice off-site power water pump power inin coincidence coincidence with with aa loss loss of of CCW CCW will require the will require the diesel diesel driven driven I I service water pump to to be be in service in in service order to in order provide emergency to provide emergency cooling cooling water water to to the the II I charging pumps.
~~~~ I 1.
Connect cam lock fitting end of emergency cooling water supply hose to Service Water Connection Inside Unit 3 Charging Pump Room, 3-70-179A.
- 2. Consult with Unit 3 RCO to determine desired charging pump.
- 3. Verify desired charging pump is stopped OR running at maximum speed.
- 4. Connect quick disconnect fitting end of emergency cooling water supply hose to emergency hose connection on desired charging pump.
- a. Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-291 3-10-29 1 OR
- b. Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-289 OR
- c. Emergency Hose Connection to Charging Pump C C Oil Cooler, 3-10-299
_ _ _ _ _ _ 1_ _ _ _ _ _ _ _ _ _ _ - _ - - _ - - 1-NOTE II I II Emergency cooling water OUTLET hose hose has a quick disconnect fitting on one one end end andand no no II I fitting on the other end. I 5.
- 5. Connect Connect quick quick disconnect disconnect fitting end end ofof emergency emergency cooling cooling water water outlet outlet hosehose to to emergency emergency hosehose connection connection on on desired desired charging charging pump.
pump. a.a. Emergency Emergency Hose Hose Connection Connection to to Charging Charging Pump Pump A Oil Cooler, A Oil Cooler, 3-10-290 3-10-290 OR b.
- b. Emergency Emergency Hose Hose Connection Connection to to Charging Charging Pump Pump BB OilOil Cooler, Cooler, 3-10-28 3-10-288 8 OR c.c. Emergency Emergency Hose Hose Connection Connection to to Charging Charging PumpPump CC OilOil Cooler, Cooler, 3-10-298 3-10-298 W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 32 32 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 ATTACHMENT 11 ATTACHMENT (Page 22 ofS) (Page of 5) CONTROL OF CONTROL EMERGENCY COOLING OF EMERGENCY COOLING WATERWATER TO TO CHARGING CHARGING PUMPS PUMPS 6.
- 6. Remove cover Remove cover from from floor floor drain drain to to be used in Charging Charging Pump Room.
Room.
- 7. Route open end of emergency cooling water outlet hose to floor floor drain being used in Charging Pump Room.
- 8. Isolate CCW to hydraulic oil cooler on desired desired charging pump:
- a. Close CCW to A Charging Pump Oil Cooler Inlet, 3-82SA 3-825A OR
- b. Close CCW to B Charging Pump Oil Cooler Inlet, 3-82SC 3-825C OR
- c. Close CCW to C Charging Pump Oil Cooler Inlet, 3-82SE 3-825E
- 9. Isolate CCW from hydraulic oil cooler on desired charging pump:
- a. Close CCW from A Charging Pump Oil Cooler Inlet, 3-82SB 3-825B OR
- b. Close CCW from B Charging Pump Oil Cooler Inlet, 3-82SD 3-825D OR
- c. Close CCW from C Charging Pump Oil Cooler Inlet, 3-825F 3-82SF
- 10. Open Service Water Connection Inside Unit 33 Charging Pump Room Root Valve, 3-70-179.
- 11. Open Service Water Connection Inside Unit 33 Charging Pump Room, 3-70-179A. 3-70-179A.
- 12. Establish service water to desired Charging Pump:
- a. Open Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-291 OR
- b. Open Emergency Hose Connection to Charging Pump B B Oil Cooler, 3-10-289 3-10-289 OR
- c. Open Emergency Hose Connection to Charging Pump C C Oil Cooler, 3-10-299 3-10-299 W97/dajlev/ev W97/daj/ev/ev
Procedure No.: Procedure No.:
Title:
Predure
Title:
Procedure Page: Page: 33 33 Approval Approval Date: Date: 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02C 5124/02C ATTACHMENT 11 ATTACHMENT (Page 33 ofS) (Page of 5) CONTROL OF CONTROL OF EMERGENCY COOLING WATER TO CHARGING CHARGING PUMPS 13.
- 13. Adjust service service water water flow flow from from desired desired charging charging pump toto provide maximum flow.flow.
- a. Open Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-290 OR
- b. Open Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-288 3-10-28 8 OR
- c. Open Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-298
- 14. IF service water flow is not obtained, THEN have the Service Water System placed in service using 0-OP-012, SERVICE WATER SYSTEM, using any available pump including the diesel driven SWP D.
- 15. Notify Unit 3 RCO that emergency cooling water has been established to desired charging pump.
CAUTION Maximum charging pump oil temperature is 220 'F. F.
- 16. Monitor oil temperatures on running charging pump.
- 17. IF hydraulic coupling oil outlet temperature on running charging pump exceeds 185°F, 18SoP, THEN perform the following:
- a. Notify Unit 33 RCO that operating charging pump should be stopped.
- b. Consult with Unit 33 RCO to determine if emergency cooling water should be realigned to a different charging pump.
- c. IF Unit 33 RCO determines that emergency cooling water must be realigned to a different charging pump, THEN go to Step 20 of this attachment.
18.
- 18. IF Unit 33 RCO determines that emergency emergency cooling water to charging pumps is no longer required, THEN go to Step 20 of this attachment.
19.
- 19. Return to Step Step 16 16 of of this attachment.
attachment. 20.
- 20. Verify charging Verify charging pump pump being supplied with being supplied with emergency cooling water is emergency cooling is stopped.
stopped. W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 34 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02C ATTACHMENT ATTACHMENT 11 (Page (Page 44 of5) of 5) CONTROL OF CONTROL EMERGENCY COOLING OF EMERGENCY COOLING WATER WATER TOTO CHARGING CHARGING PUMPSPUMPS 21.
- 21. Isolate emergency Isolate emergency cooling cooling water flow flow from from previously running charging charging pump:
- a. Close Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-290 OR
- b. Close Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-288 3-10-28 8 OR
- c. Close Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-298
- 22. Isolate emergency cooling water flow to previously running charging pump:
- a. Close Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-291 OR
- b. Close Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-289 OR
- c. Close Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-299
- 23. Reestablish CCW to hydraulic oil cooler on previously running charging pump:
- a. Open CCW to A Charging Pump Oil Cooler Inlet, 3-825A OR
- b. Open CCW to B B Charging Pump Oil Cooler Inlet, 3-825C OR
- c. Open CCW to C C Charging Pump Oil Cooler Inlet, 3-825E W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure
Title:
Page: 35 Approval Date: 3-0NOP-030 Component Cooling Water Malfunction 5/24/02 ATTACHMENT 11 ATTACHMENT (Page 55 of5) (page of 5) CONTROL OF EMERGENCY COOLING COOLING WATERWATER TO CHARGING PUMPS 24.
- 24. CCW from Reestablish CCW from hydraulic oil oil cooler cooler on on previously running running charging charging pump.
- a. Open CCW from A Charging Pump Oil Cooler Inlet, 3-825B OR
- b. Open CCW from B Charging Pump Oil Cooler Inlet, 3-825D OR
- c. Open CCW from C Charging Pump Oil Cooler Inlet, 3-825F
- 25. Disconnect emergency cooling water outlet hose from previously running charging pump.
- 26. Close Service Water Connection Inside Unit 3 Charging Pump Room Root Valve,3-70-179.
- 27. Close Service Water Connection Inside Unit 3 Charging Pump Room, 3-70-179 A.
3-70-l79A.
- 28. Disconnect emergency cooling water supply hose from previously running charging pump.
- 29. jIF emergency cooling water must be realigned to a different charging pump, THEN return to Step 2.
- 30. Disconnect emergency cooling water supply hose from Service Water Connection Inside Unit 33 Charging Pump Room, 3-70-179A.
3-70-l79A.
- 31. Return emergency cooling water supply and outlet hoses to their designated storage locations.
- 32. Replace cover on floor drain used for emergency cooling water.
- 33. Notify Unit 33 RCO that emergency cooling water alignment has been terminated.
Notif FINAL FINAL PAGE W97/daj/ev/ev W97/daj/ev/ev
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: Foldout Foldout Approval Approval Date: Date: ,~~ 3-ONOP-030 3-0NOP-030 Component Cooling Component Cooling Water Water Malfunction Malfunction 5/24/02 5/24/02 FOLDOUT FOR FOLDOUT FOR 3-0NOP-030 3-ONOP-030
- 1. TOTAL LOSS TOTAL LOSS OF OF CCWCCW FLOW FLOW A.
A. Manually trip Manually trip the the reactor, reactor, verify reactor reactor trip the EOP trip using the EOP network, network, THEN THEN stopstop the the RCPs. RCPs. B. B. letdown and Isolate letdown and excess excess letdown. letdown. C. Establish one charging pump running at maximum speed AND dispatch operator to establish emergency cooling water to one of the remaining two charging pumps using Attachment 1. 1. Monitor RCS pressure closely while running charging pump at maximum speed. speed. D. WHEN Attachment 11 is complete, THEN operate charging pump supplied with emergency cooling as necessary to maintain RCP seal cooling.
- 2. LOSS OF CCW TO ANY COMPONENT IF component cooling water flow to any component cooled by CCW is lost, THEN shut down the affected component.
- 3. CHARGING PUMP EMERGENCY COOLING CRITERIA IF Cooling Water is NOT available to charging pumps, THEN charging pump operation shall be at maximum speed until cooling is restored from CCW System or using Attachment 1.
CCW PUMP STOPPING CRITERIA IF any Component Cooling Water Pump is cavitating, THEN stop the affected Component Cooling Water Pump(s) and place in Pull-To-Lock.
- 5. REACTOR TRIP CRITERIA IF tripping a RCP is required, THEN manually trip the reactor prior to stopping the RCP.
- 6. RCP STOPPING CRITERIA IF any RCP bearing temperature annunciator alarm actuates AND its associated motor bearing temperature is greater than 195°F, THEN trip reactor and stop the affected RCP(s).
- 7. CCW System operation once CCW System Hdr has been restored shall shall be within the operating restrictions of 3-OP-030 summarized as follows: [Commitment - Step 3.3.2]
of3-0P-030 - CCW Pumps, Heat Exchangers, and Flows/Loads.
- N-i N-1 CCW CCW Pumps (where N = number of CCW Hxs aligned to ofCCW to CCW)
- All CCW CCW Hxs in in service when RHR in when RHR in service service OR with with only 22 CCW Hxs in service, place 22 CCW Pumps in in Pull-To-Lock.
- Maximum of 55 out of 66 CCW Heat Heat Loads.
W97/daj/ev/ev W97/daj/ev/ev
Florida Power & Light Company C Turkey Point Nuclear Plant -I. This procedure may be affected by an 0. T.S. C. (On The Unit 3 Spot Change) verify information prior to use. C C I * (Il Date verUled Initials_________
Title:
ICD Loss of 3D 4KV Bus Safety Related Procedure (I) CD CD -o 1 o o CD
- 0. 1 CD Responsible Department: Operations c5 CD Ci)
OQ)
-i0) CI)
Revision Approval Date: CD CI) CD 7/31/00C s. RTSs 91-1561P, 95-0945P, 00-0403P
-l 0)0) j0 (0 Cr 0 PCIMs 87-265 WC097:bc o 0 CD C,
Procedure No.: Procedure
Title:
Page: 2 2 Approval Date: 3-ONOP-004.5 3-0NOP-004.S Loss of 3D 4KV Bus 7131./OOC 7/31100C LIST OF EFFECTIVE PAGES Revision Page Date 1 1 07/31/000 07/31100C 2 07/31100C 07/31/OOC 33 07/31/00 07/31100 4 07/31100 07/31/00 55 07/31/00 07/31100 6 07/31100 07/31/00 7 07/31/00 07/31100 8 07/31100 07/31/00 W97:bc
Procedure No.: Procedure
Title:
Page: 3 Approval Date: 3-0NOP-004.S Loss of 3D 4KV Bus 7/31/00 1.0 1.0 PURPOSE PURPOSE 1.1 This procedure provides instructions to be followed in the event of a complete loss of power to the 3D 4KV bus. 2.0 S1PTOMS OR ENTRY CONDITIONS SYMPTOMS 2.1 Miscellaneous annunciator alarms associated with loss of operating components powered from the 3D 4KV bus 2.2 Lockout relay actuation for 3D 4KV bus 2.3 Bus stripping action for 3D 4KV bus 2.4 Loss of the following major components: 2.4.1 3C component cooling water pump 2.4.2 3C intake cooling water pump
3.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT DOCUMENTS 3.1 References 3.1.1 Technical Specifications
- 1. Section 3/4.8.1, AC Sources
- 2. Section 3/4.8.3, Onsite Power Distribution 3.1.2 FSAR
- 1. Section 8.2, Emergency Power
- 2. Section 14.1.12, Loss of A.C. Power 3.1.3 Operating Diagrams
- 1. 561O-T-E-1591, Sheet 11 - Electrical Distribution 5610-T-E-1591, -
- 2. 5610-T-L1, 5610-T-Ll, Sheet 12 - Emergency Load Sequencer
- 3. 5610-T-L1, 5610-T-Ll, Sheet 13 - 3A Loss of Voltage and Bus Stripping
- 4. 5610-T-L1, 561O-T-Ll, Sheet Sheet 13A 13A - 3B
- 3B Bus Loss of of Voltage and Bus Bus Stripping Stripping W97:bc W97:bc
Procedure No.: Procedure
Title:
Page: 4 Approval Date: 3-ONOP-004.5 3-0NOP-004.5 Loss of 3D 4KV Bus 7/31/00 7/31100 3.1.4 Breaker List 5610-E-855 3.1.5 Procedures
- 1. 3-ONOP-004.2, LOSS OF 3A 4KV BUS 3-0NOP-004.2,
- 2. 3-ONOP-004.3, LOSS OF 3B 4KV BUS 3-0NOP-004.3, 3.1.6 Plant Change/Modifications
- 1. PC/M 87-266, Swing Switchgear 3D and Transfer ofICW of ICW & CCW 4C Pumps 3.1.7 Miscellaneous Documents
- 1. JPE-L-86-74, Safety Evaluation Turkey Point Units 33 and 4 (PTPN)
Emergency Diesel Generator Load Evaluation
- 2. JPN-PTN-SENJ-89-048, Turkey Point Units 33 and 4 Emergency Power System Enhancement Project Supplement No.
No.2:2: Safety Analysis
- 3. JPN-PTN-SENJ 136, Response to NRC on Station Blackout Open Items JPN-PTN-SENJ-89-136,
- 4. JPN-PTN-SENP-95-026, CCW Flow Balance and Post-Accident Alignment Requirements to Support Thermal Up-Rate 3.2 Records Required 3.2.1 None 3.3 Commitment Documents 3.3.1 LER 250/95-006, Analysis Shows CCW Heat Exchangers Incapable of Handling Full Accident CCW Flow W97:bc
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: 5 Approval Date: 3-ONOP-004.5 3-0NOP-004.5 Loss of Loss of 3D 3D 4KV Bus 4KV Bus 7/31100 I STEP STEP I LACTION/EXPECTED RESPONSE J IERESPONSE I ACTIONIEXPECTED RESPONSE j RESPONSE NOT NOT OBTAINED OBTAINED I 1I Check 3D Check 3D 4KV 4KV Bus Lockout Relay Bus Lockout Relay - RESET
- RESET Perform Perform the the following:
following: a.
- a. Direct Direct Electrical Electrical Maintenance Maintenance to to determine and determine and correct correct cause cause ofof lockout lockout relay actuation.
relay actuation.
- b. WHEN cause of 3D 4KV bus lockout lockout relay relay actuation actuation has has been been determined determined and and corrected, corrected, THEN THEN reset reset lockout lockout relay.
- c. WHEN 3D 3D 4KV bus lockout relay has been reset, THEN OBSERVE NOTE PRIOR TO STEP 2 and go to Step 2.
PRIOR I NOTE I I I Efforts to re-energize 3A and 38 4KV buses may restore power to 3D 4KV I bus. /fIf the 3D 4KV bus will be used to re-energize 3A or 38 4KV bus using I I station blackout tie line, the remainder of this procedure shall not be used. _ _ =- _ _ _ ~ ___ ~ .. =- _ _ _ _ .. ~_=_ ___ I i__.I a a - a a a a 2 Check 3A And 3B 4KV Buses - AT LEAST Perform the following: ONE ENERGIZED
- a. Try to re-energize 3A 4KV bus using 3-ONOP-OO42, 3-0NOP-004.2, LOSS OF 3A 4KV BUS.
- b. Try to re-energize 3B 4KV bus using 3-ONOP-004.3, LOSS OF 3B 4KV BUS.
3-0NOP-004.3,
- c. Continue with procedure and step in effect.
3 Disconnect Loads From 3D 4KV Bus
- a. Verify SC 3C Intake Cooling Water Pump breaker, 3AD05 - OPEN -
- b. Verify 3C Component Component Cooling Water Pump breaker, 3AD04 - OPEN W97:bc W97:bc
ProcedureNo.: Procedure No.:
Title:
ProcedureTitle: Procedure Page: Page: 6 Approval ApprovalDate: Date: 3-ONOP-004.5 3-0NOP-004.5 Loss of Loss of3D 3D 4KV 4KV Bus Bus 7/31100 7/31/00 I STEP STEP I ILACTIONIE ACTION/EXPECTED XPECTED RESPONSERESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED I 44 Determine Source Determine Source Of Power For Of Power For 3D 3D 4KV 4KV Bus Bus
- a. Check 3A
- a. Check and 3B 3A and 3B 4KV 4KV buses buses - BOTH
- BOTH a.
- a. Perform the Perform the following:
following: ENERGIZED ENERGIZED
- 1) IF
- 1) IF 3A 3A 4KV 4KV busbus isis energized, energized, THEN THEN go go to to Step Step 5.5.
- 2) IF
- 2) IF 3B 33 4KV 4KV busbus is is energized, energized, THEN THEN go go to to Step Step 7.7.
- b. Consult with Nuclear
- b. Consult Nuclear Plant Plant Supervisor to determine desired determine desired source source of of power power for for 3D 3D bus:
4KV bus:
- 3A4KV bus 3A4KV OR
- 3B4KVbus 3B 4KV bus
- c. Check desired source of power for 3D 4KV c. Go to Step 7.
bus-3A4KV bus - 3A 4KV bus 5 Re-energize 3D 4KV Bus From 3A 4KV Bus Go to Step 7.
- a. Open Feeder To 4KV Bus 3D, 3AB19
- b. Open Supply From 4KV Bus 3B, 3AD06
- c. Close Supply From 4KV Bus 3A, 3ADO1 3AD01
- d. Close Feeder To 4KV Bus 3D, 3AA17 3M17 6 GoToStep8 Go To Step 8 77 Re-energize 3D 3D 4KV 4KV Bus From 3B Bus From 3B 4KV 4KV Bus Bus
- a. Open
- a. Open Feeder Feeder ToTo 4KV 4KV Bus Bus 3D, 3D, 3AA17 3M 17
- b. Open Supply
- b. Open Supply From From 4KV Bus 3A, 4KV Bus 3A, 3ADO1 3AD01
- c. Close Supply
- c. Close Supply From From 4KV Bus 3B, 4KV Bus 3B, 3AD06 3AD06
- d. Close
- d. Close Feeder Feeder To To 4KV 4KV Bus 3D, 3AB19 Bus 3D, 3AB19 W97:bc W97:bc
Procedure No.: Procedure
Title:
Page: 7 Approval Date: 3-0NOP-004.S Loss of 3D 4KV Bus 7/31100 STEP I IEAGTION/E I STEP RESPONSE I I RESPONSE I ACTION/EXPECTED XPEcIED RESPONSE I I RESPONSE NOT NOTOBTAI OBTAINED NED 88 Verify 3D Verify 3D 4KV 4KV Bus ENERGIZED BUS Bus - ALIGNED BUS
- ALIGNED TO TO AN AN Perform the Perform the following:
following: ENERGIZED 3A 4KV busbus a.
- a. Notify Nuclear Notify Nuclear Plant Plant Supervisor Supervisor that that 3D 3D
- 3A4KV 4KV bus 4KV bus cannot cannot be be re-energized.
re-energized. OR OR b.
- b. Continue efforts Continue efforts to to re-energize re-energize 3D 3D 4KV 4KV 3B 4KV 4KV busbus bus bus from from one one of of the the following:
following:
- 38
** 3A 4KV 3A 4KV busbus using using Step Step 55
** 38 4KV 38 4KV busbus .using using Step Step 77 c.
- c. WHEN 3D 3D 4KV 4KV bus bus has has been been re-energized, THEN re-energized, THEN do do Steps Steps 99 and 10.
10.
- d. Continue with procedure and step step in effect.
CAUTION If a loss of all AC power has occurred, safeguards equipment shall be restarted as directed in the Emergency Operating Procedures or 3-ONOP-004, LOSS OF OFFSITE POWER. 3-0NOP-004, 9 Locally Verify No Breaker Targets Exist On fIF any 3D 4KV bus breaker target is in, 3D 4KV Bus Breakers THEN DO NOT ENERGIZE ASSOCIATED COMPONENT until cause of breaker target has been determined and corrected. W97:bc W97:bc
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0NOP-004.S Loss of 3D 4KV Bus 7/31100 I[STEP STEP II II ACTION/EXPECTED RESPONSE RESPONSE I I RESPONSE II I I RESPONSE NOTNOT OBTAINED OBTAINED CAUTION CCW System load requirements for the EOP network, and the SHUTDOWN LOCA ONOPs, 3-0NOP-041.7 3-ONOP-041.7 and 3-0NOP-041.B 3-ONOP-041.8 SHALL NOT be exceeded. These requirements are:
- 1. The number of running CCW pumps shall be one less than the number of In-Service CCW Heat Exchangers.
- 2. No more than 5 of the following loads shall be on the CCW system at one time.
- a. Normal Containment Coolers [equals 1I Load]. Loadj.
- b. RHR Heat Exchanger [each HX equals 1 I load].
loadj.
- c. Emergency Containment Coolers [each (each ECC equals 1I load, and for a loss of instrument air - ALL ARE IN-SERVICE LOADS].
- LOADSJ.
- 3. If only 2 CCW Heat Exchangers are in service and CCW valves MOV-3-479A and MOV-3-749B are open, two CCW Pumps are required to be in Pull-To-Lock.
10 10 Restart Components Supplied By 3D 4KV Bus As Directed By Nuclear Plant Supervisor
- 3C Intake Cooling Water Pump
- 3C Component Cooling Water Pump 11 Return To Procedure And Step In Effect END OF TEXT FINAL PAGE W97:bc W97:bc
/1 I
Appendix CC Appendix Job Performance Measure Job Performance Measure Form Form ES-C-1 ES-C-I Worksheet Worksheet Facility: Facility: Turkey Point Turkey Point Task No: Task No: Performance Job Performance Job Task
Title:
Task
Title:
Emergency Borate Emergency Borate the the RCS RCS Measure No: Measure No: Systems -ff Systems A2.06 (4.2/4.3) 004 A2.06 004 (4.2/4.3) KIA
Reference:
K/A
Reference:
A2.14 {3.8/3.9} 004 A2.14 004 (3.8/3.9) Examinee: Examinee: NRC Examiner: NRC Examiner: Facility Evaluator: Facility Evaluator: Date: Date: Method of testing: Method Simulator Simulated Performance Actual Performance Yes
------------------- ---------~~---------
Classroom Classroom Simulator Yes Plant - - - - - - - - - - - - Plant Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating initiating cues. When you performance measure complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Unit 3 is in Mode 3 preparing for startup. Just completed diluting to the Estimated Critical Condition RCS boron concentration
- 2. Currently performing step 5.10.2 of 3-GOP-301
- 3. Two charging pumps are operating with a total flow rate of 90 gpm
- 4. Two letdown orifices are in service (60 gpm & 45 gpm)
- 5. Equipment out of service
- a. 3B3BSGFP SGFP
- b. 3B2 Circ Water Pump
- c. 3B Boric Acid Transfer Pump Task Standards:
- 1. Emergency borate the RCS until adequate shutdown margin restored Required Materials:
- 1. 3-GOP-301
- 2. 3.-ONOP-046.1 3-0NOP-046.1
- 3. 3-ARP-097.CR General
References:
1.
- 1. 3-GOP-301
- 2. 3-ONOP-046.1 3-0NOP-046.1
- 3. 3-ARP-097.CR
- 4. 3-EOP-FR-S.2 3-EOP-FR-S.2 Curve Book
- 5. Plant Curve Initiating Cue:
Respond to plant conditions Respond conditions as Unit Unit 33 Reactor Operator Time Critical Time Task: Yes/No Critical Task: Yes/No Validation Time: Validation Time: 10 10 minutes minutes
AppendixCC Appendix Page22 of Page of88 Form Form ES-C-1 ES-C-I INSTRUCTIONS TO INSTRUCTIONS TO OPERA OPERATOR TOR READ TO READ TO OPERA OPERATOR TOR:: WHEN I I TELL WHEN TELL YOU YOU TOTO BEGIN, BEGIN, YOUYOU ARE ARETO TO PERFORM PERFORM THE THE ACTIONS ACTIONS AS AS DIRECTED DIRECTED IN IN THE THE INITIATING INITIATING CUES. I I WILL CUES. WILL DESCRIBE DESCRIBE THE THE GENERAL GENERAL CONDITIONS CONDITIONS UNDER UNDERWHICH WHICH THIS THIS TASK TASK IS IS TO TO BE BE PERFORMED PERFORMED AND PROVIDE AND PROVIDE THE THE NECESSARY NECESSARYTOOLS TOOLS WITHWITHWHICH WHICH TO TO PERFORM PERFORM THIS THIS TASK. TASK. BEFORE BEFORE STARTING, STARTING, I I WILL EXPLAIN THE WILL EXPLAIN THE INITIAL INITIAL CONDITIONS, CONDITIONS, WHICH WHICH STEPS STEPS TO TO SIMULATE SIMULATE OR OR DISCUSS, DISCUSS, AND AND PROVIDE PROVIDE INITIATING CUES. INITIATING CUES. WHEN WHEN YOU YOU COMPLETE COMPLETE THE THE TASK TASK SUCCESSFULLY, SUCCESSFULLY, THE THE OBJECTIVE OBJECTIVE FORFOR THIS THIS JOB JOB PERFORMA NCE MEASURE PERFORMANCE MEASURE WILL BE WILL BE SATISFIED. SATISFIED. HAND JPM HAND JPM BRIEFING BRIEFING SHEET SHEET TO TO OPERATOR OPERATOR AT AT THIS THIS TIME! TIME! IN! TIAL CONDITIONS: INITIAL CONDITIONS:
- 1. Unit 3
- 1. Unit 3 isis in in Mode Mode 33 preparing preparing for for startup.
startup. Just Just completed completed diluting diluting to to the the Estimated Estimated Critical Critical Condition Condition RCS boron concentration RCS boron concentration
- 2. Currently
- 2. Currently performing performing step step 5.10.2 5.10.2 of of 3-GOP-301 3-GOP-301
- 3. Two
- 3. Two charging charging pumps pumps areare operating operating with with aa total total flow flow rate rate of of 90 90 gpm gpm
- 4. Two
- 4. Two letdown letdown orifices orifices are are in in service service (60 (60 gpm gpm & & 45 45 gpm) gpm)
- 5. Equipment out
- 5. Equipment out of of service service
- a. 3BSGFP
- a. 3B SGFP
- b. 3B2
- b. 3B2 Circ Circ Water Pump Pump
- c. 3B
- c. 3B Boric Boric Acid Acid Transfer Pump Pump INITIATING INITIA TlNG CUE: CUE:
Respond to plant conditions as Unit 3 Reactor Operator. Respond to plant conditions TERMINAT TERMINA ION CUE: TlON CUE: WHEN YOU FEEL WHEN YOU FEEL THAT THAT YOU HAVE SATISFACTORILY SATISFACTORILY COMPLETEDCOMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET JPM BRIEFING SHEET BACK TO ME. DO DO YOU YOU HAVE HAVE ANY QUESTIONS? ANY QUESTIONS? YOU YOU MAY MAY BEGIN. BEGIN.
I Appendix Appendix C C Page 33 of Page of 88 Form ES-C-1 Form ES-C-I I NOTES TO NOTES TO EVALUATOR EVALUATOR AND AND IfF I/F OPERATOR: OPERATOR:
- 1. Reset
- 1. Reset simulator simulator to Ic-i 3 or to IC-13 or IC-142.
IC-i 42. IfIf IC-13 IC-i 3 used perform steps used perform steps 22 through through 11 ii below. below. IfIf IC-142 IC-i 42 used, used, go directly to go directly to step step 12. 12.
- 2. Unit
- 2. Unit 33 isis inin Mode Mode 3. 3.
- 3. Place
- 3. Place simulator simulator in in run.
run.
- 4. Place control switches
- 4. Place control switches for for both both groups groups of of backup backup heaters heaters inin AUTO AUTO
- 5. Open
- 5. reactor trip Open reactor trip breakers breakers andand acknowledge acknowledge alarmsalarms
- 6. Depress rod
- 6. Depress rod control control startup startup reset reset pushbutton pushbutton
- 7. Secure
- 7. Secure 3B2 3B2 CWP.CWP. Verify Verify 3B 3B BATP BATP control control switch switch in in STOP STOP and and 3A 3A BATP BATP control control switch switch in in AUTO.
AUTO.
- 8. Verify
- 8. letdown orifice Verify letdown isolation valves orifice isolation valves CV-3-200A CV-3-200A && CV-3-200B CV-3-200B openopen with with CV-3-200C CV-3-200C closed.
closed. Verify Verify two charging pumps two charging pumps running running
- 9. Set source range audio multiplier to the x1 xiOO position 00 counts position
- 10. Place
- 10. Place 3B SGFP & 3B2 CWP out of service as as follows: Click on on Schema ~ MAIN POWER
> MAIN POWER DISTRIBUTION ~ >4KV 4KV & 48OVAC ~
& 480VAC
- 3C 3C 4KV 4KV BUSBUS ~ breaker 14 14 ~ TAF1D1BP -- 3AC14
> TAF1D1BP 3AC14 BRK POSITION ~ RACKOUT then INSERT
> select RACKOUT INSERT ~ BUS TIE
> BUS TIE BKR 3AB22 *. ~
BKR 3AB22 3B 4kV bus
-÷ 3B bus bkr 18 ~
bkr 18 > TAK4DP - 3AB18 CWP 3B2 BREAKER POSITION ~ > select RACKOUT then INSERT ~ >*
- CIRC WATER PP 3B2 ~ MV-3-i4i3 ~
- MV-3-1413 3 i4i3 309i7 LOCAL CLOSE = T ~
- TCK4DVM - MV 3141330917
- = > select FALSE then INSERT.
ii. Place
- 11. Place 3B BATP out of service & MOV-3-350 failed as is as follows: Click on Schema ~ > CHEMICAL VOLUME CONTROL SYSTEM ~ > CVCS MAKE-UP ~ B BORIC ACID PUMP ~ TCB1 BMC --
3P203B 30610 CLOSED BA CHG PUMP B ~ > enter FALSE then INSERT ~ MOV35O ~
- MOV350
- TFBVC63
- MOV 350 FAILED CLOSED ~ > enter TRUE then INSERT i2. Store temporary IC if needed for repeat runs of this JPM 12.
- 13. Place ECO information tags on 3B SGFP, 3B2 CWP & 3B BATP
- 14. Place copy of 3-GOP-301 on RO desk with steps signed off through step 5.10.1 5.i0.i
- 15. Open & execute lesson file NRC SRO XXIII JPM f.
i6. When task performance begins, place simulator in run and insert failure as follows: Click on 16. SpeedU/SIowD ~ SpeedU/SlowD > TABMBOR - DESIRED BORON CONCENTRATION PPM ~
- =
> Enter Value = 1300 ppm ~ > Press Enter key ~ > TABMTIME - TIME DELAY TO DESIRED BORON CONC. SPEEDUP FACTOR > =
~ Enter value = 120 > ~ Press Enter key.
Appendix CC Appendix Page 44 of Page of 88 Form Form ES-C-1 ES-C-I Denote critical Denote critical steps steps with with aa check check markmark Start Start Time Time Obtained copy Obtained copy of of 3-0NOP-046.1 3-ONOP-046.1 STEP STEP 11 :
- - SAT SAT
- - UNSAT UNSAT STANDARDS:
STANDARDS: NOTE: Operator NOTE: Operator maymay refer refer toto 3-EOP-FR-S.2 3-EOP-FR-S.2 as as aa yellow yellow path path FRP FRP or or 3-ARP-097.CR before 3-ARP-097.CR before entering entering 3-0NOP-046.1. 3-ONOP-046.1. Either Either behavior is behavior is acceptable acceptable 1.
- 1. Determined source Determined source rangerange counts counts increasing increasing at at an an uncontrolled uncontrolled rate rate
- 2. Obtained control room copy of 3-0NOP-046.1 3-ONOP-046.1 Initiated emergency boration boration STEP STEP 22 : Initiated emergency
- - SAT
- - UNSAT STANDARDS:
STANDARDS: 11.. Verified at least one charging pump running J
..j 22.. Placed RCS makeup control switch in STOP J
..j 3. Started 3A Boric Acid transfer pump
- 4. Attempted to open MOV-3-350. Recognized/reported Recognized/reported MOV-3-350 failed to open open..
J..j 5. Opened FCV-3-1 FCV-3-113A 1 3A & FCV-3-1 FCV-3-113B1 3B J..j 6.
- 6. Directed Primary Operator (P0) (PO) to locally open 3-356
- 7. When 3-356 reported open, closed FCV-3-113B
- 8. Verified HCV-3-121 open 9.
- 9. Verified CV-3-310A CV-3-310A open 10.
- 10. Established Established flow on on FI-3-122 FI-3-122 >> 45 45 gpm gpm NOTE:
NOTE: HCV-3-121 HCV-3-121 && CV-3-310A CV-3-310A should should already already be be open open and and Fl FI 122 charging 122 charging flow flow with with two two charging charging pumps pumps should should be> be > 45 45 gpm gpm without without operator operator action. action. NoNo flow flow indicated indicated in in FI-3-110 FI-3-11 0 due due to to MOV-3-350 MOV-3-350 failure. failure. hF IfF Respond Respond as PO when as P0 when directed directed to to locally locally open open 3-356. 3-356. Click Click on on Schema Schema OPERATOR OPERATOR ~ CHEMICAL
-> CHEMICAL AND AND VOLUME VOLUME CONTROLCONTROL SYSTEM SYSTEM ~ CVCS CVCS MAKE MAKE-CUE:
CUE: UP UP > ~ 356 356 *~ TABM356 TABM356 - BM - 356 VALVE BM 356 VALVE PORT PORT AREA AREA > ~ enter enter selected value ==1.0 selected value then INSERT 1.0 then INSERT OR OR trigger trigger lesson step OPEN lesson step OPEN 3 356. Report when complete. 356. Report when complete.
I Appendix AppendixCC Page 55 of Page of88 I Form ES-C-I I Form ES-C-1 Stopped any charging charging pump pump operating operating on on full full flow flow recirculation recirculation STEP STEP 33 : Stopped any
- - SAT SAT
- - UNSAT UNSAT STANDARDS: Determined STANDARDS: Determined from from US/SM US/SM no no charging charging pumps pumps running running on full flow on full flow recirculation.
recirculation. CUE: CUE: IfIf asked asked as US/SM, tell as US/SM, tell candidate candidate that that no no charging charging pumps pumps are are onon full full flow recirculation flow recirculation. . Checked plant status status STEP STEP 44 : Checked plant
- - SAT SAT
- - UNSAT UNSAT STANDARDS:
STANDARDS: 1. Determined reactor
- 1. Determined reactor power power below below the point point ofof adding adding heat heat
- 2. Determined
- 2. Determined 3-0NOP-046.1 3-ONOP-046.1 not entered entered following a reactor trip Determined no SG pressure decreasing in an uncontrolled manner
- 3. Determined 3.
NOTE: Candidate should perform steps 3a, 4a & 6a before NOTE: proceeding to step 7. proceeding STEP Verified dilution stopped Verified dilution stopped STEP 5 5 : SAT
- - UNSAT STANDARD STANDARDS: S:
J..j 1.
- 1. Placed Placed FCV-3-1 FCV-3-114A 1 4A control control switch switch inin CLOSE CLOSE
- 2. Determined
- 2. Determined reactorreactor power power below below point point of of adding adding heatheat J..j 3. Continued
- 3. Continued boration boration until at least until at least 540 540 gallons gallons using using BAST BAST as as source source of borated of borated water water forfor emergency emergency boration boration NOTE:
NOTE: Since Since thethe maximum maximum boric boric acid acid flow flow through through FCV-3-113A FCV-3-113A (MOV-3-350 (MOV-3-350 flowpathflowpath not not available) available) isis 40 40 gpm, the required gpm, the required time to add 540 gallons boric acid time to add 540 gallons boric acid isis 13.5 13.5 minutes minutes rather rather than than the the 99 minutes minutes in in step step 7c. 7c. 4.4. Checked Checked dilution dilution stopped stopped Once Once 40 40 gpm gpm boric boric acid acid flow flow established established and and candidate candidate has has correctly correctly indicated indicated how how long long that that boric boric acid acid flow flow will be required, will be required, tell tell the the CUE* CUE: . candidate candidate that that source source range range counts counts areare decreasing decreasing and and the the required required time time hashas elapsed. elapsed.
Appendix CC Appendix Page 66 of Page of88 Form Form ES-C-1 ES-C-I Determined emergency borationboration stopping stopping criteria criteria met met STEP STEP 66 : Determined emergency
- - SAT SAT
- - UNSAT UNSAT STANDARD:
STANDARD: 1. Determined time
- 1. Determined time requirement requirement of of step step 77 met met
- 2. Determined
- 2. Determined source source range range counts counts stable stable oror decreasing decreasing I/F IIF Respond ifif called Respond called as Chemistry regarding as Chemistry regarding shutdown shutdown margin.
margin. Report Report OPERATOR OPERATOR that shutdown that shutdown margin margin isis adequate. adequate. CUE: CUE: STEP Stopped emergency boration boration STEP 77 :
- - SAT SAT
- - UNSAT STANDARDS:
STANDARDS: 1. Stopped 3A Boric Acid transfer pump
- 2. Determined MOV-3-350 already closed 3.
- 3. Directed POP0 locally close 3-356 1fF IIF Respond when called as PO P0 to locally close 3-356. Click on Schema OPERATOR OPERATOR ~
> CHEMICAL AND VOLUME CONTROL SYSTEM -> ~ CVCS MAKE-CUE:
CUE: UP >~ 356 >~ TABM356 - BM 356 VALVE PORT AREA >
- ~ enter
=
selected value = 0.0 then INSERT OR trigger lesson step CLOSE 3-356. Report when complete. CUE: Tell candidate that another operator will complete the remaining steps of 3-ONOP-046 3-0NOP-046.1 .1 Terminating Terminating Manual Manual emergency emergency boration boration lineup lineup secured. secured. STOP STOP Cue: Stop Time Stop Time - - - -
II Appendix C I Page 77of8 of 8 ES-C-I I Form ES-C-1 Verification of Completion Job Performance Measure No. Systems - f
--~--------------------------------------------------
Examinees Name: Examinee's Examiners Name: Examiner's Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's signature and date: ___________________________________ Examiners
JPM BRIEFING JPM BRIEFING SHEET SHEET INITIAL CONDITIONS: INITIAL CONDITIONS:
- 1. Unit
- 1. Unit 33 isis inin Mode Mode 33 preparing preparing for for startup.
startup. Just Just completed completed diluting diluting to to the the Estimated Estimated Critical Critical Condition Condition RCS boron concentration RCS boron concentration
- 2. Currently
- 2. Currently performing performing step step 5.10.2 5.10.2 of of 3-GOP-301 3GOP301
- 3. Two charging
- 3. Two charging pumps pumps are are operating operating with with aa total total flow flow rate rate of of 90 90 gpm gpm
- 4. Two letdown
- 4. Two letdown orifices orifices are are in service (60 in service gpm && 45 (60 gpm 45 gpm) gpm)
- 5. Equipment out of
- 5. Equipment of service
- a. 3B 3BSGFP SGFP
- b. 3B2 Circ Water Pump
- c. 3B
- c. 3B BoricBoric Acid Transfer Pump Pump INITIATING INITIA TlNG CUE:
Respond to plant conditions as Unit 3 Reactor Operator. HAND THIS PAPER BACK TO YOUR EVALUATOR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY SATISFACTORILY COMPLETED COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 c-s.
.c) c.)
c_)
Title:
Emergency Boration Safety Related Procedure Responsible Department: Operations Revision Approval Date: 4/17/06 RTSs 88-1435P, 89-2446, 90-1985P, 91-1215, 91-1917, 91-2841P, 92-1256P, 92-1604P, 92-2101P, 93-1 128P, 95-1 93-1128P, 163P, 97-0033, 95-1163P, 97-0345P, 00-0705P, 01-0355P, 02-0425P, 06-0069P PCIMs 90-440, 92-031 PC/Ms OTSCs 10263, 10263, 0436-93 W97:/FRZJdtIev/dw W97:/FRZldtlev/dw
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 22 Approval Approval Date: Date: 3-ONOP-046.1 3-0NOP-046.1 Emergency Boration Emergency Boration 4/17/06 4/17/06 LIST OF EFFECTIVE PAGES Revision Revision Page Date Date 11 04117/06 04/17/06 2 04117/06 04/17/06 3 04/17/06 04/17/06 4 04117106 04/17/06 5 04117/06 04/17/06 6 04117/06 04/17/06 7 04117/06 04/17/06 88 04/17106 04/17/06 9 04117106 04/17/06 WQ7/FP7/di/pv/dw W9Y:/FRlJdtlevldw
Procedure No.: Procedure
Title:
Page: 3 Approval Date: 3-0NOP-046.1 Emergency Boration 4117/06 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 This procedure provides This procedure provides instructions instructions for unplanned and for unplanned and uncontrolled uncontrolled increases increases in in reactivity reactivity requiring immediate requiring injection of immediate injection of concentrated concentrated boric boric acid acid solution solution when when the the unit unit isis shutdown (EOPs shutdown (EOPs not in use), in in use), in refueling, refueling, or or when when directed directed by by the the EOPs. EOPs. 2.0 2.0 SYMPTOMS OR SYMPTOMS OR ENTRY ENTRY CONDITIONS CONDITIONS 2.1 Excessive control rod insertion insertion for greater than 11 hour for a critical critical reactor 2.1.1 8/2, ROD BANKAIBIC/D B 8/2, BANK A/B/C/D EXTRA La LO LIMIT 2.1.2 Control rod position indicators are below the bank insertion limit (Plant Curve Book, Sect 2, Fig 10 or 11) 2.2 An uncontrolled decrease in any RCS Cold Leg temperature below 525°F for any reason and the RCS not borated to cold shutdown concentration as required by 3-GOP-305, Hot Standby to Cold Shutdown. 2.2.1 Decreasing pressurizer level 2.2.2 Decreasing pressurizer pressure 2.3 Uncontrolled reactivity increase 2.3.1 Uncontrolled increase in reactor power and RCS temperature with no control rod movement. 2.3.2 Uncontrolled increase in source range count rate when subcritical. 2.3.3 Chemistry sample indicates less than required RCS boron concentration for a shutdown reactor. 2.4 Two or more control or two or more shutdown rods not fully inserted after a reactor shutdown or trip, and shutdown margin is not confirmed to be in compliance with Figure 3.1-1 of Technical Specifications. 2.4.1 Rod position indicators indicate rods are not fully insçrtedinserted and rod bottom lights are out. 2.4.2 Rod position indicators and bottom lights are out-of-service. 2.5 EOP network requires Emergency Boration. W97:/FRZIdtJev/dw W97:/FRZldUev/dw
Procedure No.: Procedure
Title:
Page: 4 Approval Date: 3-0NOP-046.1 Emergency Boration 4/17/06 3.0
3.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCES/RECORDS REOUIRED/COMMITMENT DOCUMENTS DOCUMENTS 3.1 3.1 References References 3.1.1 3.1.1 Technical Specifications Technical Specifications 1.
- 1. Section 3/4.1.1 Section 3/4.1.1 Boration Boration Control Control
- 2. Section 3/4.1.2 Boration Systems Section Systems 3.1.2 FSAR
- 1. Section 9.2 Chemical and Volume Control System 3.1.3 Plant Curve Book
- 1. Section 2, Figure 10, 10, 11
- 2. Section 3, Figure 11 3.1.4 Operating Diagrams
- 1. 5613-M-3047, Shts 11 &
5613-M-3047, & 2, CVCS-Charging CVCS-Charging and Letdown
- 2. 5610-T-D-19, Boron Concentration 5610-T-D-19, Concentration Control System 3.1.5 Plant Procedures
- 1. 3-GOP-305, Hot Standby to Cold Shutdown
- 2. 3-ONOP-028, Rod Control System Malfunction 3-0NOP-028,
- 3. 0-OP-028.2, Shutdown Margin Calculation
- 4. 0-OP-046, CVCS - Boron Concentratio
- Concentrationn Control 3.1.6 CE Report Number 849963-MPS 849963-MPS-S -S MISC-003, Boric Acid Concentratio Concentration n Reduction Technical Basis and Operational Analysis 3.2 Records Required 3.2.1 Reportable Occurrence Report filed, if applicable 3.3 Commitmen Commitmentt Documents 3.3.1 3.3.1 Generic Letter 85-05, NRC Generic 85-05, Inadvertent Inadvertent Boron Boron Dilution Dilution Events, Events, January January 31, 1985 31, 1985 (CTRAC (CTRAC 86-1332) 86-1332) 3.3.2 3.3.2 Combustion Combustion Engineering Letter, Letter, F-CE-8418, F-CE-8418, Boron Boron Dilution, Dilution, February February 26, 1985 1985 (CTRAC (CTRAC 86-1332) 86-1332)
Wq7/FR7/di/pv/Hw W97:/FRZJdtJev/dw
Procedure No.: Procedure
Title:
Page: 5 Approval Date: 3-0NOP-046.1 Emergency Boration 4117/06 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE 1 I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I
~-
r
----------------------1 NOTE I I
IfIf Emergency Emergency Operating directed by by the Operating Procedures EOPs. the EOPs. Procedures are are inin effect, effect, this this procedure procedure shallshall be be used used only only as as I directed I 1I Initiate Emergency Initiate Emergency Baratian Boration Of Of The The ReSRCS
- a. Verify charging
- a. Verify charging pumpspumps - AT
- AT LEAST LEAST ONE ONE RUNNING RUNNING
- b. Turn the
- b. Turn RCS Makeup the RCS Makeup Control Control Switch Switch to STOP STOP
- c. c. Perform the Perform the following:
following:
- c. Manually start Boric Manually Boric Acid Pump 3A or 3B
- 1) Align charging pump suction to the 1)
RWST.
- 2) Hold closed LCV-3-115C.
LCV-3-1 I 5C.
- 3) Direct an operator to open Breaker LCV-3-1 I 5C.
30669 for LCV-3-115C.
- 4) WHEN 30669 is open, THEN release LCV-3-115C Control Switch.
- 5) GotoSteple.
Go to Step 1e.
- d. Open Emergency Boration Valve, d. Perform the following:
MOV-3-350
- 1) Open Boric Acid to Blender, FCV-3-1 FCV-3-113A.I 3A.
- 2) Open Blender Flow to Charging Pump, FCV-3-113B.
- 3) Locally open Manual EmergencyEmergency Boration Boration Valve 3-356.
- 4) WHEN Valve 3-356 is open, THEN close close FCV-3-113B.
FCV-3-113B.
- 5) Continue
- 5) Continue withwith Step Step 11e.
e. e.
- e. Open Open Charging Charging Flow Flow to to Regen Regen Heat Heat Exchanger, Exchanger, HCV-3-1 HCV-3-121 21 f.f. Verify Verify Loop Loop A A Charging Charging Isolation, Isolation, f.f. Open Open Loop Loop C C Charging Charging Isolation, Isolation, CV-3-310A CV-3-310A - OPEN OPEN CV-3-3 CV-3-310B.
lOB.
- g. Establish
- g. Establish emergency emergency boration boration flow flow g. Start
- g. Start additional additional charging charging pumps pumps andand align valves align valves asas necessary necessary to to establish establish
** FI-3-1 10-- GREATER FI-3-110 GREATER THAN THAN 60 60 GPM GPM emergency emergency boration boration flow.
flow.
** Fl-3-122A FI-3-122A - GREATER
- GREATER THAN THAN 45 45 GPM GPM W97JFRZIdtIev/dw W97:/FRZJdtJev/dw
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 3-0NOP-046.1 Emergency Boration 4/17/06 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 22 Stop Any Stop Any Charging Charging Pump Pump Operating Operating OnOn Full Full Flow Recirculation Flow Recirculation
.-- - a ItiO**F NOTE
- - - - - - - - - - 1i II I Lh:
Control Banks Control Banks shall shall not not remain S::: _____________ I remain below the Reactor is critical (Tech Spec 3.1.3.6). R::t: i:::ti:al!::.C: below their
~ 1~.
their rod rod insertion insertion limit limit for for more more than than 22 hours hours when when 3 Respond To Respond To Reactivity Reactivity Increase Increase AtAt Power Power
- a. Check
- a. Check Reactor Reactor - ABOVE
- ABOVE POINTPOINT OFOF a. Go
- a. Go to to Step Step 4.
4. ADDING HEAT ADDING HEAT
- b. Check control
- b. Check control rods rods - ABOVE BANK
- BANK b. Perform Perform the following:
INSERTION LIMITS 1)
- 1) Verify Emergency Emergency Boration Boration is is having having desired effect:
** Reactor Power - DECREASING
- DECREASING OR Tavg - DECREASING
- DECREASING
- 2) WHEN Emergency Boration is having desired effect, THEN withdraw control rods to above bank insertion limits.
- 3) Continue with Step Step 3c.
- c. Check Tavg - MORE THAN 3°F GREATER GREATER c. Go to Step 3e.
THAN Tref THAN Tref
- d. Insert
- d. Insert control rods d.
- d. IF IF control control rods do do NOT NOT movemove in in Automatic or Automatic or Manual, Manual, THEN THEN concurrently perform concurrently perform 3-ONOP-028 3-0NOP-028,, ROD ROD CONTROL SYSTEM CONTROL SYSTEM MALFUNCT MALFUNCTION ION AND continue AND continue with with Step Step 3e. 3e.
- e. Maintain
- e. Maintain Tavg Tavg - WITHIN WITHIN 3°F 3°F OF OF Tref Tref
- 1) Continue
- 1) Continue Emergency Emergency Boration Boration OR OR 2)
- 2) Adjust Adjust control control rodsrods toto maintain maintain desired desired Tavg Tavg OR OR 3)
- 3) Adjust Adjust turbine turbine load as directed load as directed by bythe the Shift Shift Manager Manager f.f. Go Go to to Step Step 77 W97:/FRZJd tIev/dw W97 :/FRZJdUev/dw
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Pagc: Page: 7 Approval Approval Date: Date: 3-ONOP-046.1 3-0NOP-046.1 Emergency Boration Emergency Boration 4/17/06 4/17/06 STEP j ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I
- .h_hh NOTE
----------1 I 2340 gallons 2340 gallons of (92 minutes minutes at of BAST at 60 BAST water gpm) will 60 gpm) water (39 raise RCS will raise minutes at (39 minutes 60 gpm) at 60 gpm) oror 5510 gallons of 5510 gallons of RWST RWST water water I (92 RCS boron boron concentration concentration approximately approximately 195 195 ppm.
ppm. I I
~ -
- -- S -- - - - S - -a- - - - - _ _ _ _ _ 5 _ a 1I 4 Determine Stuck Determine Stuck Rod Criteria Following Rod Criteria Following A A Reactor Trip Reactor Trip Check this procedure
- a. Check
- a. procedure entered following aa a. GoGo to to Step Step 6.
6. reactor trip reactor
- b. Check control rods
- b. Check rods - TWO OR
- MORE OR MORE b.
- b. Go Go to to Step Step 5.
5. STUCK OUT OUT
- c. Continue boration at greater than or equal to 60 gpm 60gpm
- 39 minutes for each rod not fully inserted using BAST water
- 92 minutes for each rod not fully inserted using RWST water
- NOTE I Under worst case conditions, 10380 gallons of BAST water (173 minutes at 60 gpm) or I 16000 gallons of RWST water (4.5 hours at 60 gpm) must be injected to ensure adequate I shutdown margin at 200 F. 'F.
I I 5 Determine Uncontrolled Uncontrolled Cooldown Cooldown Criteria Following Reactor Trip
- a. Check
- a. Check any RCS Cold any RCS Cold Leg Leg temperature - - a. Go
- a. Go to to Step Step 7.
7. LESS LESS THAN THAN 525°F 525°F b.
- b. Continue Continue boration boration at greater than at greater or equal than or equal toto 60 gpm for 60 gpm for
- 173 minutes 173 minutes using using BASTs BASTs
- 4.5 hours 4.5 using RWST hours using RWST OR Cold shutdown Cold shutdown boronboron concentration concentration hashas been verified been verified c.c. Go Go to Step 88 to Step W97:/FRZ/dt/ev/dw W97:/FRZJdt/ev/dw
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0NOP-046.1 Emergency Boration 4/17/06 STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I 6 Determine Uncontrolled Determine With Reactor With Uncontrolled Cooldown Reactor Below Below Point Cooldown Criteria Point OfOf Adding Criteria Adding Heat Heat
- a. Check
- a. pressure in Check pressure in all SIGs - ANY all S/Gs - ANY S/G SIG a. Go
- a. Go toto Step Step 7.
7. PRESSURE DECREASING PRESSURE DECREASING IN AN IN AN UNCONTROLLED MANNER UNCONTROLLED MANNER OR OR PARTIALLY DEPRESSURIZED PARTIALLY DEPRESSURIZED
- b. Check any
- b. Check RCS Cold any RCS Cold LegLeg temperature temperature - - b. Go
- b. Go toto Step Step 7.
7. LESS THAN 525°F LESS
- c. Continue boration
- c. Continue boration at greater than at greater or equal than or equal to to 60 gpm 60gpm
- 173 minutes using BASTs 173
- 4.5 hours using RWST RWST OR Cold shutdown boron concentration has been verified
- d. GotoStep8 Go to Step 8 r--:--------- - -NOTE
__. a iOF I I 540 gallons of BAST water or 840 gallons of RWST water will insert approximately f I 500 pcm of negative reactivity. 7 Stop Dilution FCV-3-1 14A control switch - CLOSE
- a. Verify FCV-3-114A
- b. Check Reactor - BELOW POINT OF
- b. Go to Step 7d.
ADDING HEAT
- c. Continue boration at greater than or equal to 60 gpm 60gpm
- 9 minutes using BASTs
- 14 14 minutes using RWST
- d. Check dilution - STOPPED
- d. IF dilution is continuing, THEN dispatch an operator to perform the following:
- 1) Stop both primary water pumps 1) 2)
- 2) Verify the following valves are are closed:
** FCV-3-1 FCV-3-114A14A
** 10-563, PW System Header 10-563, Header Tie Valve Valve
** 3-353A, PW 3-353A, PW toto Charging Charging PumpPump Suction Suction
** 3-359A, PW 3-359A, PW to Chem Chem MixMix Tank Tank
** 3-246, PW 3-246, PW toto Demin Demin A
** 3-232C, 3-232C, PWPW toto Demin Demin BB
** 3-232B, PWPW toto Demin Demin C C
** 3-236A, 3-236A, PWPW toto Demin Demin D D
** 3-234A, 3-234A, PWPW toto Demin Demin EE
** 3-233, PW 3-233, PW toto Demin Demin D D andand EE
- 3) Report
- 3) any deviations Report any deviations of of valve valve alignments alignments toto the the Shift Shift Manager.
Manager. W97:/FRZIdt/ev/dw W97 :/FRZldtJev/dw
Procedure No.: Procedure
Title:
Page: 9 Approval Date: 3-0NOP-046.1 Emergency Boration 4117/06 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE II II RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED II 88 Verify Applicable Emergency Verify Applicable Stopping Criteria Criteria Is Emergency Boration Met Is Met Boration Perform the Perform the following: following: Stopping a.
- a. WHEN WHEN stopping stopping criteria criteria isis met, met, THEN THEN
- Time requirements Time requirements of of Steps Steps 4,4, 5, 5, 6, 6, 77 -
- perform perform Step Step 9.9.
SATISFIED SATISFIED
- b. Continue
- b. Continue with with Step Step 10.
10.
- Control rods Control - ABOVE BANK rods - ABOVE BANK INSERTION INSERTION LIMITS LIMITS
- Source range count Source range count rate rate - STABLE
- STABLE OR OR DECREASING DECREASING
- Uncontrolled reactivity Uncontrolled reactivity increase increase - STOPPED
- STOPPED
- All RCS Cold Leg temperatures - GREATER -
THAN OR EQUAL EQUAL TO 525°F FOLLOWING FOLLOWING REACTOR TRIP Adequate shutdown margin - CONFIRMED
- CONFIRMED 9 Stop Emergency Boration
- a. Stop operating Boric Acid Pump
- b. Close MOV-3-350
- c. Close or verify closed Manual Emergency Boration valve 3-356
- d. Close or verify closed breaker 30669 for LCV-3-1 LCV-3-115C 1 5C
- e. Restore CVCS Makeup System to automatic operation operation using 0-OP-046, CVCS - BORON -
CONCENTR CONCENTRATION ATION CONTROL
- f. Restore PRZ level to normal
- g. Restore PRZ
- g. PRZ level level control to automatic automatic operation operation 10 10 Sample Sample RCSRCS For For Boron Boron Concentratio Concentration n 11 11 Restore BAST Restore BAST And And RWST RWST To To Normal Normal Levels Levels 12 12 Verify Verify BAST BAST And And RWST RWST Meet Meet Tech Tech Spec Spec Requirement Requirements s For For Both Both Units Units 13 13 Return Return ToTo Procedure Procedure And Step In And Step In Effect Effect END END OF OF TEXT TEXT FINAL FINAL PAGE PAGE W97:/FRZ/dtlev/dw W97:/FRZJdUev/dw
ww I Appendix C Job Performance Measure ES-C-I Form ES-C-1 Worksheet Facility: Turkey Point Task No: Respond to Loss of 3C Job Performance Task
Title:
Transformer Measure No: Systems - 9 K/A
Reference:
KIA 062 A2.05 {2.9/3.3} (2.9/3.3) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulator Simulated Performance Actual Performance Yes
-------------------- ----------~~--------
Classroom Simulator Yes Plant -------------- Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. initial Conditions: Initial
- 1. Unit 3 is in Mode 1 1 at 50% power awaiting permission from reactor engineering to increase power to 100%.
- 2. 3A SGFP is in service Task Standards:
- 1. 3C 4kV bus and associated load centers are reenergized from the 4C Transformer Required Materials:
3-ONOP-004.4
- 1. 3-0NOP-004.4 General
References:
3-ONOP-004.4
- 1. 3-0NOP-004.4 3-ONOP-092.4
- 2. 3-0NOP-092.4 Initiating Cue:
Respond to plant conditions as Unit 3 RO Time Critical Task: Yes/No Validation Time: 20 minutes
Appendix C Page 2 of 9 ES-C-I Form ES-C-1 INSTRUCTIONS TO TO OPERA OPERATOR TOR " READ TO TO OPERA OPERATOR: TOR: WHEN II TELL YOU TO BEGIN, BEGIN, YOU ARE TO PERFORM PERFORM THE ACTIONS AS DIRECTED IN IN THE INITIATING INITIATING CUES. II WILL DESCRIBE DESCRIBE THE GENERAL CONDITIONS UNDER UNDER WHICH THIS TASK IS IS TO BE BE PERFORMED PERFORMED PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM AND PROVIDE PERFORM THIS TASK. BEFORE STARTING, II WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS:
- 1. Unit 3 is in Mode 11 at 50% power awaiting permission from reactor engineering to increase power to 100%.
- 2. 3A SGFP is in service INITIATING INITIA TlNG CUE:
Respond to plant conditions as Unit 3 RO. TERMINATION TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. EVALUATOR NOTES TO EVALUA I/F OPERATOR: TOR AND IIF
- 1. Reset simulator to IC-2.
10-2.
- 2. Unit 3 is in Mode 1 1 at 50% power
- 3. Place simulator in run
- 4. When directed by examiner, initiate 3C Transformer lockout as follows: Click on Schema ~
GENERATOR AND GRID ~ LARGE TRANSF LOGIC & PROT ~ 30-BUS Transformer 86 relay ~
> 3C-BUS
- TFP1 C38S - 1 86/3CBT SPURIOUSLY ACTUATES ~
038S - 186/3CBT > enter TRUE then INSERT.
I Appendix Appendix C C Page 33 of9 Page of 9 I Form ES-C-1 Form ES-C-I I Denote critical Denote critical steps with a check steps with check mark mark Start Time Obtained copy of 3-0NOP-004.4 3-ONOP-004.4 STEP STEP 11 : SAT SAT
- - UNSAT STANDARD: Obtained Control Room copy of 3-0NOP-004.4 3-ONOP-004.4 NOTE: Candidate may initially refer to 3-ARP-097.CR for annunciator J-1/2, 4KV BUS C LOSS OF VOLTAGE. The annunciator 3-ONOP-004.4.
response directs the operator to refer to 3-0NOP-004.4. runback STEP 2 : Checked turbine run back not in progress SAT UNSAT STANDARD: runback Determined turbine run back not occurring STEP 3 : Checked 3A & 3B 4kV buses at least one energized
- - SAT
- - UNSAT STANDARD: Determined 3A & 3B 4kV bus both energized 4 : Checked 3C 4kV bus lockout reset STEP --
SAT
- - UNSAT STANDARD: Determined 3C 4kV bus lockout reset (VPB blue light on steady)
De-energized load centers supplied by 3C 4kV bus STEP 5 : -- SAT
-- UNSAT STANDARDS:
J..J 1.
- 1. Opened Opened 3E 3E load center supply breaker 3AC04 J..J 2.
- 2. Opened Opened 3F13G 3F/3G load load center supply breaker 3AC1 3AC111
Appendix C of 9 Page 4 of9 ES-C-I Form ES-C-1 30 STEP 6 : Verified all 3C 4kV bus supply breakers open
- - SAT UNSAT STANDARD: 3AC1 6 (supply from 3C Determined breakers 3AC16 30 Transformer) & 3AC01 3ACO1 (supply from 4C40 Transformer) both open Locally verified all 3C 4kV bus breakers open STEP 7 :
- - SAT
- - UNSAT STANDARD: Directed Secondary Operator (NPO) to locally verify all 3C 30 4kV bus breakers open hF IIF Respond as Secondary Operator when directed to locally verify all 3C 30 OPERATOR 4kV bus breakers open. Report all 3C 30 4kV bus breakers open.
CUE: Checked 3C 30 transformer lockout relay reset STEP 8 : -- SAT
- - UNSAT STANDARD: Determined 3C transformer lockout relay tripped (blue light on VPB flashing)
NOTE: Candidate should proceed to step 10 when 3C 30 transformer lockout relay identified as tripped with cause unknown. Inform candidate that the US has directed another operator to try to CUE: determine and correct cause of 30 3C transformer lockout relay actuation using 3-ONOP-092.4. 3-0NOP-092.4. Checked if 404C transformer lockout relay is reset STEP 9 : -- SAT
- - UNSAT STANDARD: Directed unit 4 RO to check status of 40 4C transformer lockout relay lIE IIF Respond as unit 4 RO when directed to check status of 40 4C OPERATOR transformer lockout relay. Report 404C transformer lockout relay reset.
CUE:
I Appendix C Page 5 of 9 ES-C-I I Form ES-C-1 10 : breakers at least one closed Checked if 4C transformer supply breakers STEP 10
- - SAT
- - UNSAT STANDARD: RD to check 4C transformer breakers 8W16 or 8W75 Directed unit 4 RO closed.
I/F IIF Respond as unit 4 RORD when directed to check status of 4C OPERATOR transformer supply breakers 8W16 & 8W75. Report both 4C 40 CUE: transformer supply breakers closed. 11 Re-energized 3C 4kV bus from 4C transformer STEP 11 :
- - SAT
- - UNSAT STANDARDS: 1. Determined 3C 4kV bus normal supply breaker 3AC16 open J
..j 2. Placed 3C 4kV bus synch switch from 4C transformer breaker 3ACO1 to ON 3AC01 J
..j 3ACO1
- 3. Closed breaker 3AC01
- 4. Placed 3C30 4kV bus synch switch from 4C40 transformer breaker 3ACO1 to OFF 3AC01
- 5. Determined 3C 30 4kV bus energized
- 30 4kV bus Locally verified no breaker targets on 3C STEP 12 --
SAT UNSAT STAN DARD* STANDARD: Directed Secondary Operator to locally verify no breaker targets on 3C 4kVbus 4kV bus hF IIF Respond as Secondary Operator when directed to locally verify no OPERATOR breaker targets on 3C 30 4kV bus. Report no breaker targets on 303C 4kV CUE: bus.
Appendix C Page 6 of 9 ES-C-I Form ES-C-1 STEP 13 : Re-energized load centers supplied by 3C 30 4kV bus
- - SAT
- - UNSAT STANDARDS:
..j J 1..
1 Closed 3E load center supply breaker 3AC04 J
..j 2. 3A01 1 Closed 3F/3G load center supply breaker 3AC11 Checked motor control centers to be energized STEP 14 : SAT UNSAT STANDARD: Directed field operators to locally verify the following motor control centers to be energized:
*. 3B MCC 38 MOO non-vital
*. 30 MCC 3C MOO non-vital
*. 3B43 MCC 3843 MOO (condensate polishing)
*. MOO (water treatment/intake area) 3E & F MCC
*. 3ATOB 3A TC8 Amertap panel NOTE: Voltage on some of the above motor control centers can be checked using ERDADS.
I/F IfF Respond when directed as field operator to locally verify motor control OPERATOR centers powered from 3C 30 4kV bus to be energized. Report that all of CUE: the above except motor control centers 3E & F are energized. Inform candidate that another operator will attend to re-energization of CUE: motor control centers 3E & F. Restarted components supplied by 3C 30 4kV bus as directed by SM STEP 15 : STANDARD: Asked SM if any of the following components powered by 3C 30 4kV bus need to be started:
*. 30 condensate pump 3C
*. 3BSGFP 38 SGFP
*. ASSGFP A SSGFP When asked as SM, tell candidate that no components powered by 3C 30 CUE: 4kV bus need to be restarted at this time.
I Appendix C Page 7 of 9 I ES-C-I I Form ES-C-1 Terminating Terminating Completion of 3-0NOP-004.4. 3-ONOP-004.4. STOP Cue: Stop Time _ _ __
Appendix C Appendix C Page 88 of Page of 99 Form ES-C-1 Form ES-C-I of Completion Verification of Completion Job Pe~rmanceMeasureNo. Job Performance Measure No. _S~ys_t_e_m_s_-~g~~~~~~~~~~~~~~~~~~~~~~ Systems Examinees Name: Examinee's Examiners Name: Examiner's Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiners Examiner's signature signature and and date: date: ~~~~_~_~_ _ _ _ _ _ _ _ __
JPM BRIEFING SHEET '" INITIAL CONDITIONS: INITIAL CONDITIONS:
- 1. Unit
- 1. Unit 3 is in Mode is in Mode 11 at 50% power power awaiting permission permission from reactor reactor engineering engineering to increase increase power power to to 100%.
100%.
- 2. 3A SGFP is in service INITIATING INITIA TlNG CUE:
Respond to plant conditions as Unit 3 RO. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3
Title:
Loss of 3C 4KV Bus Safety Related Procedure ResponsIble Responsible Department: Operations Revision Approval Date: 10/21/04 RTSs 91-1561P, 91-1561P, 92-2118P, 95-0498P, 96-1376P, 97-0904P, 97-0904P, 98-0713P, 03-0204P, 04-0967P OTSC 10712 10712 PC/Ms PCIMs 87-265, 94-059, 96-096, 9 7-039 87-265,94-059,96-096,97-039 W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 2 Approval Date: Approval Date: 3-ONOP-004.4 3-0NOP-004.4 Loss of 3C 4KV Bus 10/21104 10/21/04 LIST OF EFFECTIVE PAGES Revision Page Date 11 10/21/04 2 10/21/04 10/21104 3 10/21/04 10/21104 4 09/15197C 09/15/97C 5 08/17/98 6 10/21/04 10/21104 7 11/04/96 11104/96 8 11/04/96 11104/96 9 11/04/96 11104/96 10 11/04/96 11104/96 11 11/04/96 11104/96 12 10/21/04 10/21104 13 08/17/98 08117/98 14 09/15/97C 09115/97C W97:bc/ev/mrg W97:bc/ev/mr
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 33 Approval Approval Date: Date: 3-ONOP-004.4 3-0NOP-004.4 Loss of Loss of 3C 4KV Bus 3C 4KV Bus 10/21104 10/21/04 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 procedure provides instructions to be followed This procedure followed in the event of aa complete loss of power to the 3C 4KV bus. 2.0 2.0 SYMPTOMS OR SYMPTOMS OR ENTRY ENTRY CONDITIONS CONDITIONS 2.1 Miscellaneous annunciator alarms associated with loss of operating components powered from the 3C 4KV bus 2.2 Turbine runback if unit was operating above 60% power 2.3 Possible reactor trip if3Cif 3C Condensate Pump was in service prior to loss of the 3C 4KV bus I 2.4 Voltage indication at zero for 3C 4KV bus 2.5 Lockout relay actuation for 3C 4KV bus. 2.6 Bus stripping action for 3C 4KV bus 2.7 Loss of the following major components: 2.7.1 3B Steam Generator Feedwater Pump 2.7.2 A Standby Steam Generator Feedwater Pump 2.7.3 3B RCP Oil Lift Pump 2.7.4 3C RCP Oil Lift Pump 2.7.5 Water Treatment Plant 2.7.6 Polishing Demineralizer Hold Pumps 2.7.7 Traveling Screens 2.7.8 Circulating Water Pump Discharge MOVs 2.7.9 Primary Water Pumps W97:bcfev/mra W97:bc/ev/mr
Procedure No.: Procedure
Title:
Page: 4 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 9115/97C 3.0
3.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT DOCUMENTS REFERENCES/RECORDS 3.1 References 3.1.1 3.1.1 Technical Specifications Technical Specifications 1.
- 1. Section 3/4.8.1, AC Sources
- 2. Section 3/4.8.3, On Onsite site Power Distribution 3.1.2 FSAR
- 1. Section 8.2, Emergency Power
- 2. Section 14.1.12, Loss of A.c. A.C. Power 3.1.3 Operating Diagrams
- 1. 5610-T-E-1591, Sheet 11 - Electrical Distribution 561O-T-E-1591, -
- 2. 5610-T-L1, Sheet 2 - Reactor Trip Signals 561O-T-L1, -
- 3. 5610-T-Ll, Sheet 4E3 - Cranking Diesel Feed To 4KV Bus C and Bus 561O-T-Ll, -
A or B AorB
- 4. 5610-T-L1, Sheet 6C - Generator Details
- 5. 5610-T-L1, 5610-T -L 1, Sheet 12 - Emergency Load Sequencer
- 6. 5610-T-Ll, 5610-T-L1, Sheet 13 - Loss of Voltage and Bus Stripping
- 7. 5610-T-L1, Sheet 13A - Relay Actions 4KV Bus Stripping 3.1.4 Breaker List 5610-E-855 3.1.5 Procedures
- 1. 3-ONOP-004.1, 3-0NOP-004.1, SYSTEM RESTORATION FOLLOWING LOSS OF OFFSITE POWER
- 2. 3-ONOP-004.2, 3-0NOP-004.2, LOSS OF OF 4A 4KV 4KV BUS BUS
- 3. 3-ONOP-004.3, 3-0NOP-004.3, LOSS OF 4B 4KV 4KV BUS 4.
- 4. 3-ONOP-089, 3-0NOP-089, TURBINE TURBINE RUNBACK 5.
- 5. 3/4-0NOP-92.4, C 3/4-ONOP-92.4, C BUS BUS TRANSFORMER MALFUNCTION MALFUNCTION 6.
- 6. 3-OP-006, 3-0P-006, 480 VOLT VOLT SWITCHGEAR SYSTEM SYSTEM 7.
- 7. 3-0P-007, 480 3-OP-007, 480 VOLT VOLT MOTORMOTOR CONTROL CONTROL CENTER CENTER W97:bc/ev/mm W97:bc/ev/mr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 5 Approval Approval Date: Date: 3-ONOP-004.4 3-0NOP-004.4 Loss ofof 3C 4KV Bus 8/17/98 8/17/98 3.1.6 Change/Modifications Plant ChangelModifications
- 1. PC/M 87-265, Swing Switchgear 3D and Transfer of ICW &
PCIM & CCW 3C Pumps
- 2. PC/M 94-059, Diesel Engine Driver for Standby Steam Generator Feedwater PCIM Pump P82B
- 3. PCIM Plant/C-Bus Reliability Improvement Modifications PC/M 96-096, PlantlC-Bus
- 4. PC/M 97-039, Plant Reliability Improvement Modifications (C-Bus) 3.1.7 Miscellaneous Documents
- 1. JPE-L-86-74, Safety Evaluation Turkey Point Units 3 and 4 (PTN)
Emergency Diesel Generator Load Evaluation
- 2. JPN-PTN-SENJ-89-048, Turkey Point Units 3 and 4 Emergency Power System Enhancement Project Supplement No 2: Safety Analysis
- 3. JPN-PTN-SENJ-89-136, Response to NRC on Station Blackout Open Items 3.2 Records Required 3.2.1 None 3.3 Commitment Documents 3.3.1 None W97:bc/ev/mra W97:bc/ev/mr
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 10/21104 STEP I IEACTION/E I STEP ACTION/EXPECTED XPECTRES PONSE II II RESPONSE RESPONSE RESPONSE NOT NOTOBTAI OBTAINED NED II 1 Check Turbine Runback Check Turbine Runback - NOT
- NOT IN IN Perform the Perform the following:
following: PROGRESS PROGRESS
- a. Stabilize
- a. Stabilize plant plant conditions conditions using using 3-0NOP-089, 3-ONOP-089, TURBINE TURBINE RUN BACK.
RUNBACK. b.
- b. WHEN plant WHEN plant conditions conditions are are stable, stable, THEN go to Step THEN Step 2.
2 Check 3A Check 3A And 3B ENERGIZED 3B 4KV Buses - AT LEAST 4KV Buses LEAST Perform the Perform the following: following: ONE ENERGIZED
- a. Try to re-energize 3A 4KV bus using 3-0NOP-004.2, 3-ONOP-004.2, LOSS OF 3A 3A 4KV BUS.
BUS.
- b. Try to re-energize 3B 4KV bus using 3-ONOP-004.3, LOSS OF 3B 4KV BUS.
3-0NOP-004.3,
- c. IF 3C 30 4KV bus is required to restore power to 3A or 3B 4KV bus, THEN go to Step 3.
- d. Continue with procedure and step in effect.
3 Check 3C 4KV Bus Lockout I Perform the following: RelayRese Relay - Resett I
- a. Direct Electrical Maintenance to determine and correct cause of 3C 30 4KV I Bus Lockout Relay actuation.
- b. WHEN cause of 3C 30 4KV Bus Lockout Relay actuation has been determined and corrected, THEN locally reset Bus Lockout Relay.
- c. WHEN 30 3C 4KV Bus Lockout Relay has been reset, THEN go to Step 4.
- d. Continue with procedure fQ AND step in effect.
W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 7 Approval Approval Date: Date: 3-ONOP-004.4 3-0NOP-004.4 3C 4KV Bus Loss of 3C 1114/96 11/4/96 STEP I I ACTION/EXPECTED RESPONSE I STEP RESPONSE I I RESPONSE I I I RESPONSE NOT NOT OBTAINED OBTAINED 4 De-energize Load Centers Supplied By 3C De-energize 4KV Bus:
- Open 3E Load Center Supply Breaker (Polishing Area), 3AC04
- 3F13G Load Center Supply Breaker Open 3F/3G 3AC1 1 (Intake Area), 3AC11 5 Verify All Supply Breakers To 3C 4KV Bus - -
OPEN
- 3AC16, 3C Bus Supply From 3C 30 Transformer
- 3ACO1, 3C Bus Alternate Supply From 4C 3AC01, Transformer 6 Locally Verify All Breakers On 3C 4KV Bus - -
OPEN 7 Check 3C Transformer Lockout Relay - - Perform the following: RESET
- a. Try to determine and correct cause of 30 transformer lockout relay actuation 3C 3ONOP-092.4, C BUS using 3-0NOP-092.4, TRANSFORMER MALFUNCTION.
- b. WHEN cause of 3C 30 transformer lockout relay actuation has been determined and corrected, THEN reset lockout relay.
- c. Continue with Step 10.
10. W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 1114/96 STEP I I ACTION/EXPECTED I STEP RESPONSE J I RESPONSE II f ACTION/EXPECTED RESPONSE I L RESPONSE NOT NOT OBTAINED OBTAINED 8 Check 3C Check 3C Transformer Transformer Supply Supply Breakers Breakers - AT
- AT Perform the Perform the following:
following: LEAST ONE LEAST ONE CLOSED CLOSED a.
- a. IFIF offsite offsite power power is is NOT QI available, available, THEN THEN
- 8W118 8W118 perform perform the following:
OR OR 1)
- 1) WHEN offsiteoffsite power power isis available, THEN restore restore power power to 3C 3C 4KV 4KV bus
- 8W154 8W154 from from 3C 3C transformer using using 3-0NOP-004.1, 3-ONOP-004.1, SYSTEM SYSTEM RESTORATION FOLLOWING LOSS OF OFFSITE POWER.
- 2) Continue ContLnue with Step 10.
- b. IFIF offsite power is available, THEN locally close at least one 3C Transformer Supply Breaker
** 8W118 OR
** 8W154
- c. IF neither 3C 30 Transformer Breaker can be closed, THEN go to Step 10.
9 Try To Re-energize 3C 4KV Bus From 3C Transformer:
- a. Place 3C30 Bus Sync From 3C Transformer 3AC16 to On
- b. Close 3C Bus Normal Supply Breaker, 3AC1 3AC16 6
- c. Place 303C Bus Sync From 30 3C Transformer 3AC16 to Off and remove handle
- d. Check 304KV3C 4KV bus - ENERGIZED
- d. IF breaker 3AC16 IF 3AC16 failed to close, THEN gogo to Step Step 10.
10.
- e. GotoStepl3
- e. Go to Step 13 W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure
Title:
Page: 9 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 11/4/96 I STEP STEP I I ACTION/EXPECTED RESPONSE I I RESPONSE ACTIONIEXPECTED RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED II 10 10 Check 4C Check 4C Transformer Transformer Lockout Relay - Lockout Relay - Perform the Perform the following: following: RESET RESET a.
- a. Try to Try determine and to determine and correct correct cause cause of of 4C transformer lockout lockout relay relay actuation using using 4-0NOP-092.4, 4-ONOP-092.4, C C BUS BUS TRANSFORMER MALFUNCTION.
b.
- b. WHEN causecause ofof 4C transformer transformer lockout lockout relay actuation has relay has been been determined and corrected, THEN reset lockout relay.
- c. IF lockout relay can NOT be reset, THEN return to Step 2 when either 3C or 4C Transformer can be energized.
Return to procedure AND step in effect. 11 Check 4C Transformer Supply Breakers - AT
- Perform the following:
LEAST ONE CLOSED
- a. IF offsite power is available, THEN
- locally close at least one 4C
- 8W16 Transformer Supply Breakers OR
** 8W16
- 8W75 OR 8W75
- b. IF neither 4C Transformer Supply Breaker can be closed, THEN return to Step 2 when either 3C or 4C Transformer can be energized. Return to procedure ffl AND step in effect.
W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure
Title:
Page: 10 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 11/4/96 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I CAUTION CAUTION Breaker 3AC16 Breaker 3AC16 must must be be open open in order to in order to close close 3AC01. 3ACOI. 12 12 Try To Re-energize 3C 3C 4KV 4KV Bus Bus From From 4C 4C Perform the following: Transformer: Transformer: 1.
- 1. WHEN either either 3C or 4C Transformer can can
- a. Verify 3C BUS Normal Supply Breaker, be energized. THEN return to Step 2.
3AC16, - OPEN
- b. Place 3C Bus Sync From 4C Transformer 2. fjQ step in effect.
Return to procedure AND 3ACO1 to On 3AC01
- c. Close 3C Bus Alternate Supply Breaker 3ACO1 3AC01
- d. Place 3C Bus Sync From 4C Transformer 3ACO1 to Off and remove handle 3AC01
- e. Check 3C 4KV bus - ENERGIZED 13 13 Locally Verify No Breaker Targets Exist On IF any 3C 4KV bus breaker target is in, 3C 4KV Bus THEN DO NOT ENERGIZE ASSOCIATED COMPONENT until cause of breaker target has been determined and corrected.
W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure
Title:
Page: 11 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 1114/96 L.iJ I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
...------------------------~
. NOTES NOTES ..
I I I
- If any If component powered from any component from a de-energized de-energized Load Load Center Center or or Motor Motor II I
- Control Center Control Center must must be be started, started, the affected Load the affected Load Center Center oror Motor Motor I Control Center shall be re-energized using 3-0P-006, Control 3-OP-006, 480 Volt Volt I Switchgear System or 3-0P-007, 3-OP-007, 480 VoltVolt Motor Control Center.
I
*I III ** Units 3 and 4 loads that may be required A listing of Units provided in Attachment 1. 1.
required to be energized is I
- II I ** If Unit 3 was supplying power to Unit 4 loads, power should also be I I restored to the Unit 4 loads after the required Unit 3 loads have been II II restored.
re~~ II 14 14 Re-energize Load Centers Supplied By 3C Perform the following: 4KV Bus:
- a. Restore affected load center(s) to
- Close 3E Load Center Supply Breaker normal alignment using 3-0P-006, 3-OP-006, 480 (Polishing Area), 3AC04 VOLT SWITCHGEAR SWITOHGEAR SYSTEM.
- Close 3F/3G Load Center Supply Breaker b. IF any load center can NOT be (Intake Area), 3AC11 3AC1 I re-energized from 3C 30 4KV bus, THEN re-energize affected load center(s) from Unit 4 using 3-0P-006, 3-OP-006, 480 VOLT SWITCHGEAR SYSTEM.
15 Check Motor Control Centers To Be IF any motor control center did NOT Energized re-energize when power to the load centers were restored, THEN re-energize the
- MOO 3B Non-vital MCC affected MCCs MOOs using 3-OP-007, 3-0P-007, 480 VOLT MOTOR CONTROL CENTER.
- MOO MCC 303C Non-vital
.* Condensate Polishing MOO MCC 3B43
- Water Treatment Treatment Plant/Intake Plant/Intake Area MOO MCC FF and and MOO MCC 3E 3E
- Amertap Panel 3ATCB 3ATCB W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure
Title:
Page: 12 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 10/21104 I STEP STEP I I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE I I RESPONSE I I RESPONSE NOT NOT OBTAINED OBTAINED II 16 16 Restart Components Restart Components Supplied Supplied By By 3C 3C 4KV 4KV Bus As Bus Directed By As Directed By the Shift Manager: the Shift Manager:
- 3C Condensate 3C Condensate Pump Pump
- 3B Steam 3B Steam Generator Feedwater Pump Generator Feedwater Pump
- AA Standby Steam Steam Generator Feedwater Feedwater Pump Pump 17 17 Return To Procedure And Step In Effect END OF TEXT W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure
Title:
Page: 13 Approval Date: 3-0NOP-004.4 Loss of 3C 4KV Bus 8/17/98 ATTACHMENT 11 ATTACHMENT (Page 11 of2) (Page of 2) LOADS REQUIRED LOADS REQUIRED TO TO RESTORE RESTORE PLANT PLANT SYSTEMS SYSTEMS NOTE NOTE I I I If Unit If Unit 44 loads were were powered from from Unit Unit 3, power power should should be restored to the I I same Load same Load Centers, Centers, Motor Motor Control Control Centers, Centers, and and Loads Loads thatthat were were being being I supplied prior to
- supplied to the loss of the loss of 3C Bus. List 3C Bus. List isis not not all all inclusive.
inclusive. I LL ______ _ 3E LOAD 3E LOAD CENTER FUEL AREA MCC 3C NON-VITAL
** Reactor Reactor Area Area MCC 3B 3B Non-Vital ** RHR Rm 3B Area Sump Pump A
** Condo Cond. Polishing Polishing MCC3B43 ** RHR Hx Area Sump Pump A
** Amertap Amertap panel3ATCB panel 3ATCB ** RHR RHRRm3AAreaSumpPumpA Rm 3A Area Sump Pump A
** 3CM Instrument Air Compressor 3CM Instrument ** WDS Basement Sump Pump 3
** Service Service Air Air Compressor Compressor (East) ** Gas Stripper Feed Pump
** PWST Deaereater Equipment 3F LOAD CENTER ** RPICVT
** Radwaste Radwaste Building MCC RB ** SFP Lighting and Dist Panels
** WTP/Intake WTP/Intake MCC F and 3E ** Containment Entrance Lighting
** Service Service Water Water Pump Pump B ** SFP Exhaust Fan
** Service Service Water Pump C ** SFP Hx Room Supply Fan
** #3 Waste Gas Compressor 3G LOAD CENTER ** Fuel Transfer Equipment
** Fuel Fuel Area MCC 3C Non-Vital
- 3B Containment Sump Pump
- CCW CCW AreaArea MCC 3H
- 3BRCDTPump 3B RCDT Pump
- Service Water Pump
- Service Pump A *
- RWST Purification Pump
- Service Air Compressor (West)
- Service *
- A Monitor Tank Pump
- New Fuel Rm SupplySupply Fan REACTOR AREA MCC 3B NON-VITAL
- 3B Iso Phase Bus
- 3B Iso Bus Fan Fan WTP/INTAKE AREA MCC MCC F & 3E 3E
- Turb Area Lighting
- Turb Lighting & Dist Dist Panels Panels
- WTPIlntake Lighting
- WTP/Intake Lighting and and Dist.
Dist. (Rx (Rx Vessel Level Level Indication) Indication) *
- BB Fire Fire Water Jockey Jockey Pump Pump
- Cont. Lighting && Dist
- Cont. Lighting Dist Panels Panels *
- Unit 33 Traveling Traveling Screens Screens
- Aux Bldg
- Aux Bldg Lighting Lighting & & Dist Dist Panels Panels *
- 33 && 3S 3S Screen Screen Wash Wash Pumps Pumps
- DC DC End End Bldg Bldg HVAC HV AC AirAir Handler Handler *
- 3B 3B CWP Lube Water CWP Lube Water Pump Pump
- Rod Control B/U
- Rod Control BIU Transformer Transformer
- 3B 3B Primary Primary Water Water Pump Pump CONDENSATE CONDENSATE POLISHINGPOLISHING MCC MCC 3B43 3B43
- 3A RCDT Pump
- 3ARCDTPump *
- CC Bus X-former Panel Bus X-former Panel Alt Alt Supply Supply
- 3A 3A Containment Containment Sump Sump Pump Pump *
- Condensate Condensate Polishing Polishing Equipment Equipment
- Containment Elevator
- Containment Elevator *
- Inveier Inverter 3Y25 3Y25
- 3A Mn Stm
- 3A Mn Stm Pent Pent Cooling Cooling FanFan *
- CC Bus Bus Battery Battery Charger Charger 3D32 3D32
- 3B SGFP Rm
- 3B SGFP Rm Exhaust Exhaust FanFan *
- CC Bus Bus Battery Battery Charger Charger 3D33 3D33
- 3A Feedwater Pent
- 3A Feedwater Pent Cooling Cooling Fan Fan
- Aux, Mn,
- Aux, Mn, && S/U S/U X-former X-former Panel Panel Alt Alt Supplies Supplies RADWASTE RADWASTE BUILDINGBUILDING MCC MCC RB RB
- 3B Condensate Pit 3B Condensate Pit Sump Sump Pump Pump *
- Liquid Liquid Waste Waste Processing Processing Equip Equip
- B Sewage Pump
- B Sewage Pump
- RW Bldg Lighting
- RW Bldg Lighting &
& Dist Dist Panels Panels
- RW Bldg
- RW Bldg Supply Supply && Exhaust Exhaust Fans Fans W97:bc/ev/mrg W97:bc/ev/mrg
Procedure No.: Procedure
Title:
Page: 14 Approval Date: 3-0NOP-004.4 Loss of3C 4KV Bus 9/15/97C ATTACHMENT ATTACHMENT 11 (Page 2 of2) (Page of 2) LOADS REQUIRED TO RESTORE PLANT SYSTEMS UNIT 4 POTENTIAL LOADS LOADS 4E LOAD CENTER FUEL AREA AREA MCC 4C NON-VITAL
** Reactor Reactor Area MCC 4B4B Non-Vital ** RHR RHR Rm 4B 4B Area Area Sump Sump Pump Pump AA
** Condo Cond. Polishing MCC4B43 MCC4B43 ** RHR Hx Hx Area Sump Sump Pump A
** Amertap panel4ATCB panel 4ATCB ** RHR Rm Rm 4A 4A Area Sump Sump Pump Pump A
** 4CM Instrument Air Compressor ** WDS Basement Sump Pump 4
** Gas Stripper Feed Pump 4 4F LOAD CENTER ** PWST Deaereater Equipment
** Radwaste Building MCC RA ** RPICVT
** Intake 4E ** SFP Lighting and Dist Panels
** Containment Entrance Lighting 4G LOAD CENTER ** SFP Exhaust Fan
** Fuel Area MCC 4C Non-Vital ** SFP Hx Room Supply Fan
** CCW Area MCC 4H ** #4 Waste Gas Compressor
** Fuel Transfer Equipment REACTOR AREA MCC 4B NON-VITAL ** 4B Containment Sump Pump
** 4B Iso Phase Bus Fan ** 4B RCDT Pump
** Turb Area Lighting & Dist Panels ** RWST Purification Pump (Rx Vessel Level Indication) ** Spare Battery Charger D51 D5 1
** Cont. Lighting & Dist Panels ** New Fuel Rm Rrn Supply Fan
** Aux Bldg Lighting & Dist Panels ** Elect Equip Rm chiller Unit E234
** DC Enc1 End Bldg HVHVAC AC Air Handler
- Rod Control B/U BIU Transformer INTAKE AREA 4E
- 4A RCDT Pump
- WTP!Intake Lighting and Dist.
- WTP/Intake
- 4A Containment Sump Pump
- Unit 4 Traveling Screens
** Containment Elevator ** 4 Screen Wash Pumps
** 4A Mn Stm Pent Cooling Fan ** 4A CWP Lube Water Pump
** 4B SGFP Rm Exhaust Fan
- Feedwater Pent Cooling Fan
- 4A CONDENSATE CONDENSATE POLISHING MCC 4B43
- Aux, Mn,
& S/U SIU X-former Panel Alt Supplies *
- C Bus X-former Panel Alt Supply
- Condensate Pit Sump Pump
- 4B
- Condensate Polishing Equipment
- Inverter 4Y25
- C Bus Battery Charger 4D32 RADWASTE RADWASTE BUILDING BUILDING MCC MCC RA
- Liquid Waste Waste Processing Equip
- RW
- RW Bldg Lighting & Dist Panels
- RW RW Bldg Supply & Exhaust Fans Bldg Supply FINAL FINAL PAGE PAGE W97:bc/ev/mrg W97:bc/ev/mrg
1. r. b%I%hIIt
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Appendix C Appendix C Job Performance Measure Job Performance Measure Form Form ES-C-1 ES-C-I Worksheet Worksheet Facility: Facility: Turkey Turke~ Point Point Task No: Task No: Job Performance Job Performance Task
Title:
Task
Title:
Reduce PRT Reduce PRT Tem~erature Temperature Measure No: Measure No: Systems - hh Systems K/A
Reference:
KIA
Reference:
010 AAl1.03
.03 (2.9/3.2}
(2.9/3.2) Examinee: Examinee: NRC Examiner: NRC Examiner: Facility Evaluator: Facility Evaluator: Date: Date: Method of testing: Method Simulator Simulated Performance Performance Performance Actual Performance Yes Classroom Classroom Simulator ---.:...-=-:=------ Yes Plant ------------ Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Unit 3 is in mode 11 at 100% power
- 2. PRT temperature is 122°F after a PORV spuriously opened
- 3. PRT level in normal operating band (68% - 83%) -
Task Standards:
- 1. PRT temperature reduced below 120°F
- 2. PRT level maintained in normal operating band (68% - 83%) -
Required Materials:
- 1. 3-0P-041.3 3-OP-041.3 General
References:
- 1. 3-OP-041.3 3-0P-041.3 Initiating Cue:
The Unit 33 Unit Supervisor directs you as Unit 33 Reactor Operator to reduce PRT temperature below 120°F. 120°F. Time Critical Critical Task: Yes/No Validation Time: 15 minutes 15
Appendix C Appendix C Page 22 of Page of 77 Form Form ES-C-1 ES-C-I INSTRUCTIONS TO INSTRUCTIONS OPERATOR TO OPERA TOR " READ TO READ TO OPERA OPERA TOR: TOR: WHEN II TELL WHEN TELL YOU YOU TO TO BEGIN, BEGIN, YOU YOU ARE ARE TO PERFORM THE TO PERFORM THE ACTIONS ACTIONS AS AS DIRECTED DIRECTED IN IN THE THE INITIATING INITIATING CUES. II WILL CUES. WILL DESCRIBE DESCRIBE THE THE GENERAL GENERAL CONDITIONS CONDITIONS UNDER UNDER WHICH WHICH THIS THIS TASK TASK IS IS TO TO BE BE PERFORMED PERFORMED AND PROVIDE THE AND PROVIDE THE NECESSARY NECESSARY TOOLSTOOLS WITHWITH WHICH WHICH TOTO PERFORM PERFORM THIS THIS TASK. TASK. BEFORE BEFORE STARTING, STARTING, II WILL EXPLAIN THE WILL EXPLAIN THE INITIAL INITIAL CONDITIONS, CONDITIONS, WHICHWHICH STEPS STEPS TO SIMULATE OR TO SIMULATE OR DISCUSS, DISCUSS, ANDAND PROVIDE PROVIDE INITIATING CUES. INITIATING CUES. WHEN WHEN YOU YOU COMPLETE COMPLETE THE THE TASK TASK SUCCESSFULLY, SUCCESSFULLY, THE OBJECTIVE FOR THE OBJECTIVE FOR THIS THIS JOB JOB PERFORMANCE PERFORMANCE MEASURE MEASURE WILLWILL BE BE SATISFIED. SATISFIED. HAND JPM HAND JPM BRIEFING BRIEFING SHEET SHEET TO TO OPERA OPERA TORTOR AT THIS THIS TIME! TIME! INITIAL CONDITIONS: CONDITIONS.
- 1. Unit 33 is in mode 11 at 100% power at 100%
PRT temperature is
- 2. PRT 122°F after a PORV is 122°F PORV spuriously spuriously opened
- 3. PRT level
- 3. PRT level in in normal normal operating band band (68%
(68% - 83%) INITIATING INITIA TlNG CUE: The Unit 3 Unit Supervisor directs you as Unit 3 Reactor Reactor Operator to reduce PRT temperature below 120°F. 120°F. TERMINATION TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? MAYBEGIN. YOU MAY BEGIN. NOTES TO EVALUATOR AND IIF I/F OPERA OPERATOR.TOR:
- 1. Reset simulator to IC-1 IC-i or IC-143.
IC-i 43. If IC-143 10-143 used, skip ahead to step 7.
- 2. Unit 3 is in Mode Model. 1.
- 3. Place simulator in run.
- 4. Click on Schema -; > REACTOR COOLANT SYSTEM -; PRESSURIZER RELIEF TANK -; T-471 T-47l -;
TVH1471O - T-471 TEMPERATURE SENSOR OFFSET -; enter selected value = TVH14710 - - = 0.045 then INSERT
- 5. Allow TI-3-471 on console to stabilize (l22°F).(===122°F).
- 6. Open & execute lesson file NRC SRO XXIII JPM h.
- 7. Freeze simulator.
- 8. Place simulator in run when directed by examiner.
I Appendix C I Page 3 of 7 ES-C-I I Form ES-C-1 Denote critical steps with a check mark Start Time Obtained procedure STEP 11 : -- SAT UNSAT STANDARDS: 1. Procedure 3-0P-041.3 3-OP-041 .3 obtained
- 2. Procedure checked for OTSCs
- 3. 3-OP-041 .3 Precautions & Limitations reviewed before continuing 3-0P-041.3 CUE CUE:
3-OP-041 .3 section 7.2 shall be provided to the A marked up copy of 3-0P-041.3
. candidate once this procedure and section have been identified.
Raised PRT level STEP 2 : SAT
- - UNSAT STANDARDS:
J~ 1. Opened CV-3-519B
/~ 2. Opened CV-3-519A Ll-3-470
- 3. PRT level monitored on U-3-470 CUES: 1. After CV-3-519A opened, annunciator 1-5/6 may alarm indicating the standby primary water pump is running. After this annunciator is acknowledged, tell candidate that it will be addressed by another operator.
- 2. Another annunciator that may alarm is A-7/1 for PRT high pressure.
If the candidate decides to stop filling due to high pressure, as US tell candidate that another operator will address this condition while PRT fill continues. Terminated PRT fill at 83% level STEP 3 : - - SAT UNSAT STANDARDS: When PRT level reaches 83%: J~ 1.
- 1. Closed CV-3-51 CV-3-519A9A J~ 2. Closed CV-3-519B
Appendix C Appendix C Page 44 of Page of 77 Form Form ES-C-1 ES-C-I Commenced draining PRT PRT STEP STEP 44 : Commenced draining SAT SAT UNSAT UNSAT STANDARDS: STANDARDS:
..jJ 1. Directed
- 1. Directed Primary Primary Operator (SNPO)
(SNPO) toto locally locally close LCV-3-1003A LCV-3-1 003A Waste Boron (from Waste Boron Panel) Panel)
..jJ 22.. Opened CV-3-523
..j 3. Directed Primary Operator (SNPO) to locally start either 3A or 3B RCDT pump hF ifF Respond as Primary Operator (SNPO) when directed to:
OPERATOR CUE: Locally close LCV-3-1003A. Click on Schema ~ > WASTE DISPOSAL ~ > LIQUID WASTE DISPOSAL ~ LCVIOO3A ~
> LCV1003A >
TAA21 003 - LCV-1003A CS FOR LCV-1003A ~
- > enter CLOSE then INSERT OR trigger lesson step LOCAL CLOSE LCV 1 003A. Report when complete.
1003A. Start 3A or 383B RCDT pump. From LIQUID WASTE DISPOSAL system mimic, click on A or B RCDT pump as directed ~ > TAA2PTA (TAA2PTB) - P218A (P218B) CS OF RCDT PUMP A
~ enter ON then INSERT OR trigger lesson step START 3A (B)
RCDTP.. Report when complete. (3B) RCDTP CUE: Once PRT temperature drops below 120°F with PRT level decreasing, in the interest of time, the examiner may tell the candidate that PRT level is now 68%. STEP Stopped draining PRT at 68% level 55 :
- - SAT
- - UNSAT STANDARDS:
STANDARDS: J..j 1. Directed Primary Operator (SNPO) to locally stop the running 1. RCDT RCDT pump pump q..j 2. Closed CV-3-523
- 2. Closed CV-3-523
- 3. Directed Primary
- 3. Directed Primary Operator Operator (SNPO)
(SNPO) toto locally locally place place LCV-3-1003A LCV-3-1003A in in auto auto (from (from Waste Waste Boron Boron Panel) Panel)
I Appendix Appendix C C Page 55 of Page of 77 Form ES-C-1 Form ES-C-I I hF IIF Respond as Respond as Primary Primary Operator Operator (SNPO) (SNPO) when when directed directed to: to: OPERATOR OPERATOR CUE: CUE: Stop 3A Stop 3A or or 38 38 RCDT RCDT pump. pump. From From LIQUID LIQUID WASTE WASTE DISPOSAL DISPOSAL system mimic, system mimic, clickclick on on AA or or 8B RCDT RCDT pump pump as directed --+ as directed > TAA2PTA (TAA2PT8) TAA2PTA (TAA2PTB) - P218A
- P218A (P2188)
(P218B) CSCS OF OF RCDT RCDT PUMP PUMP A A (B) --+ (8) enter OFF
- enter OFF then then INSERT INSERT OR OR trigger trigger lesson lesson step step STOP STOP 3A 3A (3B) RCDTP.
(38) RCDTP. Report Report when when complete. complete. Locally place Locally place LCV-3-1003A LCV-3-1003A in in auto. auto. From From LIQUID LIQUID WASTE WASTE DISPOSAL system mimic, click on LCV1003A --+ DISPOSAL ÷ TAA21 TAA21003003 - LCV-
- LCV 1 003A CS FOR LCV-1003A 1003A LCV-1 003A --+> enter AUTO then INSERT OR trigger lesson step LOCAL LOCAL AUTO LCV-3-1003A. Report when complete.
STEP 6 : Verified PRT temperature within specification SAT UNSAT STANDARD: Verified PRT temperature below 120°F using TI-3-471 Tl-3-471 Terminating 3-OP-041.3 section 7.2 completed 3-0P-041.3 Cue: STOP Stop Time
Appendix C Appendix C Page 66 of Page of 77 Form Form ES-C-1 ES-C-I Verification of Verification of Completion Completion Job Performance Job Performance Measure Measure No. No. --"-SSystems ys.:..;tc::.e.:..:.m.c..::s_---"-hh_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Examinees Name: Examinee's Name: Examiners Name: Examiner's Name: Date Performed: Date Performed: Facility Evaluator: Number of Attempts: Number Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiners Examiner's signature signature and and date: date:
JPM BRIEFING SHEET JPM BRIEFING SHEET INITIAL CONDITIONS: INITIAL CONDITIONS:
- 1. Unit
- 1. Unit 33 isis inin mode mode 11 at 100% power at 100% power
- 2. PRT
- 2. temperature isis 122°F PRT temperature 122°F after after aa PORV PORV spuriously spuriously opened opened
- 3. PRT
- 3. PRT level level in in normal normal operating operating band band (68%
(68% - 83%)
- 83%)
INITIATING INITIA TlNG CUE: CUE: The Unit The Unit 33 Unit Supervisor directs Unit Supervisor directs you you as Unit 33 Reactor as Unit Reactor Operator Operator to to reduce reduce PRT PRT temperature temperature below below 120°F. 120°F. HAND THIS PAPER BACK TO YOUR EVALUATOR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY SATISFACTORILY COMPLETED COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 ci 3-0P-041.3
Title:
Pressurizer Relief Tank Safety Related Procedure Responsible Department: Operations Revision Approval Date: 7/2/03 RTSs RTSs 88-0382P, 88-081 7P, 88-2982P, 91-1135W, 92-1263P, 95-0574P, 88-0817P, 98-1214P, 00-0351P, 00-0351P, 00-0497P, 02-0026P, 03-0361P OTSCs 7626, 0768-96, 0475-98, 0476-98, OTSCs 7626, 0476-98, 008 0081-03 1-03 PC/Ms PCIMs 89-581, 89-581, 95-102 W97:JM/sr/Ir/ev/mrg W97:JM/sr/lr/ev/mrg
Procedure No.: Procedure
Title:
Page: 2 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 7/2/03 LIST OF EFFECTIVE PAGES Revision Page Date 11 07/02/03 2 07/02103 07/02/03 3 07/02/03 4 09/08/00 5 09/08/00 6 09/08/00 7 09/08/00 8 03/04/02 9 09/08/00 10 03/04/02 11 09/08/00 12 03/04/02 13 07102/03 07/02/03 14 03/04/02 15 09/08/00 16 09/08/00 17 03/04/02 18 09/08/00 19 09/08/00 20 09/08/00 21 07/02/03 22 07/02/03 23 07/02103 07/02/03 24 07/02/03 25 07/02/03 26 07/02/03 W97:JM/sr/lr/ev/mr WQ7 IM/cr/Ir/,/mr,
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 33 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 7/2/03 7/2/03 TABLE OF CONTENTS Section 1.0 1.0 PURPOSE .................................................................................................................... . PURPOSE 4
2.0 REFERENCES
/RECORDS REQUIREDI REFERENCESIRECORDS REQUIRED! COMMITMENT DOCUMENTS .............................................................................. . 4 3.0 PREREQUISITES ...................................................................................................... . 6 4.0 PRECAUTIONS/LIMITATIONS ............................................................................ .. PRECAUTIONSILIMITATIONS 7 5.0 STARTUP/NORMAL OPERATION ...................................................................... .. 8 5.1 Establishing Normal Conditions ...................................................................... .. 8 6.0 SHUTDOWN ................................................................................................................ 9 7.0 OPERATION INFREQUENT OPERATION.................................................................................... 10 7.1 DrainingthePRT Draining the PRT ............................................................................................... 10 7.2 Temperature Reducing PRT Liquid Temperature................................................................... 11 7.3 Purging/Reducing PurginglReducing PRT Pressure Pressure........................................................................ 13 7.4 Removing Air from the PRT Following Maintenance ...................................... 15 7.5 Purging the PRT to Reduce Oxygen or Hydrogen Concentration (Major Gas Volume) Volume).......................................................................................... 18 7.6 Depressurizing the PRT Prior to Opening for Maintenance Maintenance.............................. 22 ATTACHMENT Attachment 11 Valve Alignment Alignment................................................................................................ 24 AIfl7. W97:JM/srllr/ev/mr
Procedure No.: Procedure
Title:
Page: 4 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 9/8/00 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 This procedure This procedure provides provides the the prerequisites, prerequisites, precautions/limitations, precautions/limitations, and and instructions instructions for for the the startup/normal operations startup/normal operations and and infrequent infrequent operation operation of ofthe the Pressurizer Pressurizer Relief ReliefTank Tank (PRT). (PRT). 2.0
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCES/RECORDS REOUIRED/COMMITMENT DOCUMENTS DOCUMENTS 2.1 2.1 References References 2.1.1 2.1.1 FSAR FSAR 1.
- 1. Section 4.2.2, Section 4.2.2, Reactor Reactor Coolant Coolant System System Components Components 2.1.2 Operating Diagrams 1.
- 1. 5613-M-3041, Reactor Coolant 5613-M-3041, Coolant System System
- 2. 5613-M-3061, Waste Disposal System Liquids 5613-M-3061, 2.1.3 Operating Procedures
- 1. 0-ADM-215, Plant Surveillance Tracking Program
- 2. 3-OP-041 .2, Pressurizer Operation 3-0P-041.2,
- 3. 3-OP-061.3, Reactor Coolant Drain Tank System 3-0P-061.3,
- 4. 0-OSP-200.l, Schedule of Plant Checks and Surveillances 0-OSP-200.1, 2.1.4 Miscellaneous Documents (i.e., PC/M, Miscellaneous Correspondence)
PCIM, Correspondence)
- 1. PC/M PCIM 89-581, Containment Isolation Features Design Basis Implementat Implementation ion
- 2. PC/M PCIM 95-102, Abandonmen Abandonmentt of the C07 Panel and Sample Train Reconfigurat Reconfiguration ion
- 3. Setpoint Change #88, PRT Operating Bands and Pressure/Tem Pressure/Temp. p. High Alarms
- 4. Precautions, Limitations, and Setpoints, Setpoints, Section Section A. 14 A.14 MQ7. IFA!,rIIr!.,ir.,,,
W97:JM/sr/lr/ev/mr
Procedure No.: Procedure
Title:
Page: 5 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 9/8/00 2.2 2.2 Records Required Records Required 2.2.1 2.2.1 The date, time The date, time and and section section completed completed shall shall be be logged logged inin the the Reactor Reactor Control Control Operator (RCO) Operator (RCO) logbook. logbook. Also, Also, any any problems problems encountered encountered while while performing performing thethe procedure should procedure should be logged (i.e., be logged (i.e., malfunctioning malfunctioning equipment, equipment, delays delays due due toto changes in changes in plant conditions, etc.). plant conditions, etc.). 2.2.2 2.2.2 Completed copies Completed copies of of the the below below listed item(s) constitute listed item(s) constitute Quality Quality Assurance Assurance records records and shall and shall be be transmitted transmitted to to QA QA Records Records forfor Retention Retention in in accordance accordance withwith Quality Quality Assurance Records Assurance Records Program Program requirements: requirements: 1.
- 1. Section 5.0 Section 5.0
- 2. Section 7.0 3.
- 3. Attachment 11 2.2.3 Completed copies of the below listed item(s) shall be retained in the Nuclear Plant Superviso?s file until the next performance of that section, enclosure, or Supervisor's attachment:
- 1. Attachment 11 2.2.4 Completed attachments listed below, that have the TAG column colunm checked ch (I),
shall be copied and transmitted to the Labeling Coordinator:
- 1. Attachment 11 2.3 Commitmen Commitmentt Documents 2.3.1 None W97:JM/sr/Ir/ev/mra W97:JM/sr/ir/ev/mr
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 9/8/00 3.0 3.0 PREREQUISITES PREREQUISITES 3.1 The following systems are operable or are operable or in operation operation to support operation of the PRT: 3.1.1 All plant electrical systems are operable to supply power and control functions All functions to to support Pressurizer Relief Tank support Tank operation. operation. 3.1.2 3.l.2 Primary Water System 3.1.3 Waste Disposal System 3.1.4 Nitrogen Supply System 3.2 The Pressurizer Relief Tank valve alignment has been verified by completion of Attachment 1. 3.3 All instruments and control devices are in service for the Pressurizer Relief Tank operation with no surveillance required, outstanding PWOs, clearances, or temporary system alterations that affect system operability as per the following: 3.3.1 3.3.l 0-ADM-215, Plant Surveillance Tracking Program and 0-OSP-200.1, Schedule of Plant Checks and Surveillances (No surveillances have exceeded the date required on the surveillance use of grace sheet.) 3.3.2 Temporary System Alteration (TSA) Log 3.3.3 Clearance Log 3.3.4 Out-of-Service Log 3.4 If performing Subsection 7.4, Removing Air from the PRT Following Maintenance, then Maintenance assistance will be required. W97:.JM/sr/Ir/ev/mra W97:JM/sr/lr/ev/mr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 77 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 9/8/00 9/8/00 4.0 4.0 PRECAUTIONS/LIMITATIONS PRECAUTIONS/LIMITATIONS 4.1 Water temperature should should not exceed 120°F 120°F during normal operations. 4.2 Pressure should not exceedexceed 10.0 10.0 psig during normal normal operations. 4.3 Oxygen concentration Oxygen concentration shallshall be maintained below 2 percent by volume. 4.4 Water level should be maintained between 68 percent and 83 percent. 4.5 All work in a radiation area shall be performed in accordance with the requirements of the Radiation Work Permit and ALARA program. 4.6 Hydrogen concentration shall be less than 4 percent by volume prior to the PRT being opened to atmosphere for maintenance. W97:JM/sr/Ir/ev/mra W97:JM/sr/ir/ev/mr
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 3/4/02 5.0 5.0 STARTUP/NORMAL OPERATION STARTUP/NORMAL OPERATION 5.1 5.1 Establishing Nonna1 Establishing Normal Conditions Conditions INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Date/Time Started: Started: _ _ _ _ _ _ _ _ _ _ __ 5.1.1 Initial Conditions Initial 1.
- 1. All applicable prerequisites listed in Section 3.0 have been satisfied.
5.1.2 Procedure Steps Steps CAUTION If Containment Isolation or Safety Injection signal is actuated, CV-3-519B must be to ensure containment integrity. closed to
- 1. normal water level of 68 to 83 percent by opening the following Establish the nonna1 valves:
- a. Isol, CV-3-5l9A Primary Water To Cntmt Iso1, CV-3-5 1 9A
- b. PRT Makeup Valve, CV-3-519B
- 2. WHEN PRT level is between 68 and 83 percent, THEN close the following:
- a. PRT Makeup Valve, CV-3-519B
- b. Primary Water to Cntmt Isol, CV-3-519A
- 3. Adjust the Nitrogen Regulator, PCV-3-473, to establish the normal nonnal operating cover gas pressure of at least 6 psig.
- 4. Verify that the oxygen content is less than 2 percent of volume.
- 5. Verify all log entries specified in Subsection 2.2 have been logged.
Date/Time Completed:_________________________ Completed: _ _ _ _ _ _ _ _ __ PERFORMED BY (Print) iNITIALS INITIALS REVIEWED BY: RCO RCO oror Designee Designee W97JM/sr/Ir/p.v/mrc W97:JM/sr/ir/ev/mr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 99 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 9/8/00 9/8/00 6.0 6.0 SHUTDOWN SHUTDOWN 6.1 6.1 None W97:JM/sr/lr/ev/mra W97:JM/sr/lr/ev/mr
Procedure No.: Procedure
Title:
Page: 10 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 3/4/02 7.0 7.0 INFREQUENT OPERATION INFREQUENT OPERATION 7.1 7.1 Draining the Draining the PR PRT T INITIALS INITIALS CKD CK'D VERIFVERIF Date/Time Started: Date/Time Started: 7.1.1 initial Conditions Initial 1.
- 1. All applicable prerequisites in Section 3.0 are satisfied.
- 2. An excessive level exists or maintenance is to be performed.
CAUTION PORV open, may affect RCS draindown Changes in PRT level with a PORVopen, drainclawn level indication. 7.1.2 Procedure Steps
- 1. Close the RCDT to Pump Suction Valve, LCV-3-1003A.
- 2. CV-3-523.
Open the PRT Drain Valve, CV-3-S23.
- 3. Start either RCDT pump, 3A or 3B. Pump Started: ____________
- 4. WhEN the desired level is attained, THEN stop the RCDT pump.
WHEN
- 5. Close the PRT Drain Valve, CV-3-523.
CV-3-S23.
- 6. LCV-.3-1003A, to AUTO.
Place the RCDT to Pump Suction Valve, LCV-3-1003A,
- 7. Verify all log entries specified in Subsection 2.2 have been logged.
Date/Time Completed:__________________ Completed: _ _ _ _ _ _ _ _ __ PERFORMED BY (Print) INITIALS REVIEWED BY: RE Vifi WED BY: RCO RCO or or Designee Wq7. IMkrIIrIcvImrn W97:JM/sr/lr/ev/mr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 11 11 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 9/8/00 9/8/00 7.2 7.2 Reducing PRT Reducing PRT Liquid Liquid Temperature Temperature INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Started: Date/Time Started: ------------------------------ 7.2.1 7.2.1 Initial Conditions Initial Conditions 1.
- 1. All applicable prerequisites listed in Section 3.0 3.0 are satisfied.
o 2.
- 2. liquid temperature is in excess of 120 PRT liquid 120°F.P.
7.2.2 Procedure Steps Steps CAUTIONS
** When adding Primary Water Water to the PRT, level and pressure shall be closely monitored to prevent overpressurization of the the PRT.
** If a Containment Isolation or Safety Injection signal is actuated, CV-3-5198 CV-3-519B must be closed to ensure containment integrity.
- 1. Increase the PRT level to 83 percent with Primary Water by opening the following valves:
- a. PRT Makeup Valve, CV-3-519B
- b. Primary Water To Cntmt Isol, CV-3-519A
- 2. WHEN PRT level reaches 83 percent, THEN close the following valves:
- a. CV-3-5 1 9A Primary Water To Cntmt Isol, CV-3-519A
- b. PRT Makeup Valve, CV-3-519B W97:JMlsr/lr/ev/mro W97:JM/srllr/ev/mr
Procedure No.: Procedure No. Procedure
Title:
Procedure
Title:
Page: Page: 12 12 Approval Date: Approval Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Tank Pressurizer 3/4/02 3/4/02 NIT (Contd) 7.2.2 (Cont'd)
- 3. Drain the PRT to 68 percent by performing the following steps:
- a. Locally close the RCDT to Pump Suction, LCV-3-1003A.
- b. Open the PRT Drain Valve, CV-3-523.
- c. Locally start either RCDT Pump, 3A or 3B.
Pump started. _ _ _ _ _ _ _ __ Pump started.
- d. WHEN 68 percent level is reached, THEN stop the RCDT pump.
- e. Close the PRT Drain Valve, CV-3-523.
- f. Locally place the RCDT to Pump Suction Valve, LCV-3-1003A, to AUTO.
- 4. Repeat Substeps 7.2.2.1 through 7.2.2.3, as necessary, until a satisfactory temperature of less than or equal to 120°F is attained. (Use additional procedure sections as necessary to document repeating substeps.)
- 5. Verify all log entries specified in Subsection 2.2 have been logged.
Completed:__________________ Date/Time Completed: _ _ _ _ _ _ _ _ __ PERFORMED BY (Print) NITIALS INITIALS REVIEWED BY: RCO or Designee W97:JM/sr/Ir/ev/mrn W97:JM/sr/ir/ev/mr
Procedure No.: Procedure
Title:
Page: 13 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 7/2/03 7.3 7.3 Purging/Reducing PRT Purging/Reducing PRT Pressure Pressure INITIAL S INITIALS CK'D VERIF CKD VERIF Date/Time Started: Started: _ _ _ _ _ _ _ _ _ _ __ 7.3.1 7.3.1 Initial Conditions Initial Conditions 1.
- 1. All applicable prerequisites listed in Section 3.0 are satisfied.
- 2. PRT pressure approaches 10.0 psig, OR oxygen concentration is 2 percent or greater by volume, OR 2J3 hydrogen concentration is 4 percent or greater by volume.
7.3.2 Procedure Steps
- 1. Verify that the PRT level is in the normal band of 68 percent to 83 percent.
- 2. Verify that the nitrogen regulator PCV-3-473 is supplying gas to the PRT and (N/A is adjusted at 6 psig to 8 psig (N/A if not purging)
- 3. Verify a waste gas compressor is operable in AUTO, OR start a waste gas compressor.
CAUTION PRT pressure should not decrease below 6.0 psig to prevent addition of oxygen.
- 4. Open the PRT Vent Valve, CV-3 -549.
CV-3-549.
- 5. IF purging the PRT, THEN notify Chemistry to monitor the PRT until I oxygen concentration is less than 2%, and hydrogen concentration is less than 4%. (N/A if not purging)
- 6. WHEN 6 to 88 psig is attained, as indicated on P1-3-472, PI-3-472, THEN close the PRT Vent Valve, CV-3-549.
W97:JM/sr/Ir/ev/mrci W97:JM/sr/lr/ev/mr
ProcedureNo.: Procedure No.:
Title:
ProcedureTitle: Procedure Page: Page: 14 14 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer ReliefTank Tank 3/4/02 3/4/02 INITIALS INITIALS CKD VERIF CK'D VERIF 7.3.2 (Cont?d) 7.3.2 (Cont'd) 7.
- 7. Verify all Verify all log entries specified log entries specified in in Subsection Subsection 2.2 2.2 have have been been logged.
logged. Date/Time Completed: Date/Time _ _ _ _ _ _ _ _ __ Completed:________________________ PERFORMED BY BY (Print) (Print) INITIALS REVIEWED BY: RCOorDesignee RCO or Designee W97JM/sr/Irkv/mro W97:JM/srllr/ev/mr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 15 15 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 9/8/00 9/8/00 7.4 7.4 Removing Air Removing Air from from thethe PRT PRT Following Following Maintenance Maintenance INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Started: Started: _ _ _ _ _ _ _ _ _ _ __ 7.4.1 7.4.1 Initial Conditions Initial Conditions 1.
- 1. All applicable prerequisites listed in Section 3.0 are satisfied.
- 2. The PRT has been opened to atmosphere during maintenance operations.
- 3. The unit is in Modes 3 through 6.
7.4.2 Procedure Steps
- 1. Close the Nitrogen Regulator Isol Valve, 3-550.
- 2. Verify that the PRT Vent Valve, CV-3-549, is closed.
- 3. Remove the flange from the PRT Vent to Cntmt Atmosphere Valve, 3-517A.
- 4. Install a vent rig over vent line at Vlv 3-517A, 3517A, PRT Vent to Cntmt Atmosphere.
- 5. Station an operator at PRT Vent to Cntmt Atmosphere Vlv 3-517A Vent Vlv.
- 6. Open the PR PRTT Vent to Cntmt Atmosphere Valve, 33-517A.
-517 A.
- 7. Station an operator at the Waste/Boron Panel to open the PR PRT T Drain to Sump, LCV LCV-3-11003 003B, B, in the event of a rapid, uncontrolled pressure increase.
CAUTIONS
- PRT pressure should not exceed 10.0 psig during this evolution.
- If a Containment Isolation or Safety Injection signal is actuated, CV-3-519B CV-3-5198 shall be closed to ensure containment integrity.
- 8. Open the following valves to fill the PRT to a level of of90%.
90%.
- a. Primary Water Primary Water to Cntmt Cntmt Isol, Isol, CV-3-519A CV-3-519A b.
- b. PRT Makeup Valve, CV-3-519B W7:JM/sr/Ir/v/mro W97:J M/sr/lr/ev/mr
Procedure No.: Procedure
Title:
Page: 16 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 9/8/00 INITIALS INITIALS CKD VERIF CK'D VERIF 7.4.2 (Cont?d) 7.4.2 (Cont'd) 9.
- 9. Close PRT Close PRT Makeup Makeup Valve, Valve, CV-3-519B CV-3-519B whenwhen one one of ofthethe following following occurs:
occurs: a.a. PRT level reaches PRT level reaches 90 90 percent percent on on LI-3-470, LI-3 -470, OR
- b. PRT pressure approaches PRT approaches 10 10 psig psig on on PI-3-472, P1-3-472, OR
- c. 3-517A.
Water is observed at vent 3-517 A.
- 10. IF PRT Makeup Valve, CV-3-519B
- 10. CV-3-519B was closedclosed in in Substep Substep 7.4.2.9 7.4.2.9 AND water was not observed at Vent 3-517A, THEN cycle/jog PRT Makeup CV-3-5 1 9B open and closed until PRT level is approximately Valve, CV-3-519B approximately 90%.
- 11. Establish a Nitrogen Feed to the PRT.
- a. OPEN Nitrogen Regulator Isolation Valve, 3-550.
- b. Verify Air Flow from Vent 3-517A for 5-10 minutes.
- c. CLOSE PRT Vent to Containment Atmosphere, 3-517 3-517A.A.
- 12. Verify PRT pressure maintained at least 6.0 psig on Console Pressure Indicator PI-3-472.
P1-3-472.
- 13. Reduce PRT level to 68 to 83 percent by performing Subsection 7.1.
- 14. Obtain a PRT oxygen sample from Chemistry.
- 15. Repeat Substeps
- 15. Sub steps 7.4.2.5 through 7.4.2.14 until a satisfactory sample is obtained from Chemistry, or perform Subsection 7.5, Purging the PRT to Reduce Oxygen Concentratio Concentration,n, to purge the PRT.
PRT.
- 16. Close Primary Water to Containment Valve,
- 16. Valve, CV-3-5 1 9A.
CV-3-519A.
- 17. Verify closed
- 17. closed PRT PRT Makeup Valve, CV-3-519B.
CV-3-519B. 18.
- 18. Remove vent vent rig installed on on Vent Vent 3-5l7A.
3-517A. W97:JM/sr/Ir/ev/mrQ W97:JM/sr/lr/ev/mr
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 17 17 Approval ApprovalDate: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 3/4/02 3/4/02 INITIAL S INITIALS CKD VERIF CK'D VERIF 7.4.2 d) T (Cont 7.4.2 (Cont'd)
- 19. Replace
- 19. Replace flange flange on on the the PRT PRT Vent Vent to Containment Atmosphere to Containment Atmosphere Valve, Valve, 3-517 A.
3-517A.
- 20. Verify
- 20. Verify all all log log entries entries specified specified in in Subsection Subsection 2.2 2.2 have have been been logged.
logged. Date/Time Completed: Date/Time Completed:__ _____ PERFORMED BY PERFORMED (Print) BY (Print) INITIALS INITIALS REVIEWED BY: REVIEWED BY: RCO or Designee W97:JM/sr/Ir/ev/mro W97:JM/srllr/ev/mr
ProcedureNo.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 18 18 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 9/8/00 9/8/00 7.5 7.5 Purging the Purging the PRT PRT to Reduce Oxygen to Reduce Oxygen or or Hydrogen Hydrogen Concentration Concentration (Major (Major GasGas Volume) Volume) INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Started: Date/Time Started: 7.5.1 7.5.1 Initial Conditions Conditions 1.
- 1. Section 3.0 are satisfied.
All applicable prerequisites listed in Section
- 2. Oxygen concentration of the PRT is 2 percent by volume or greater, OR hydrogen concentration is 4 percent by volume or greater. -
--------------------------- NOTE I I II Large Large volumes volumes of gases from from other other sources are not not expected toto be vented vented to to the the vent vent II ILh:a header during this evolution.
Z I
- 3. No evolutions are planned which would require letdown to the CVCS Holdup Tanks while the PRT is being vented.
- 4. A waste gas compressor is in operation or in AUTO and operable.
7.5.2 Procedure Steps I NOTES Ii I
- II PRT pressure should not exceed 10.0 psig during this evolution. I I I I
- II Vent header pressure should not exceed 3.0 psig during this evolution.
II I
- II An operator should be stationed at the Waste/Boron Panel to monitor this evolution I I and should notify the RCO immediately if the process should need to be discontinued I due to Vent Header pressure, compressor malfunction, etc.
I I a a a a a
.... -----------------------~
a a a
- 1. Open or verify open Primary Water to Cntmt Isol, CV-3-5 CV-3-519A.
1 9A. W97:JM/sr/Ir/ev/mra W97:JM/sr/lr/ev/mr
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 19 19 Approval Approval Date: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer Relief Tank Tank 9/8/00 9/8/00 INITIAL S INITIALS CKD VERIF CK'D VERIF 7.5.2 (Cont'd) 7.5.2 (Contd)
------------------------~ NOTE NOTE II II II In the In following steps, the following steps, the the process process may may be be limited limited by by Vent Vent Header Header oror PRT PRT vent vent capability capability to to I I dispense of dispense closed and of the and reopened pressure resulting the pressure reopened as resulting from as required required to from the the makeup.
to continue makeup. CV-3-549 CV-3-549 and and CV-3-519a CV-3-519B should should bebe II closed continue filling filling and venting the and venting the PRT PRT until until the the desired desired levelisobtain II level ed. L _______________________ II is obtained. ~ L_________J 2.
- 2. Close Holdup Close Holdup Tanks Tanks Header to VH, 1122. 1122.
3.
- 3. Close VH to Cover Gas Supply Cross Connection, 4627.
- 4. Place the Control Switch for either A or B waste gas compressor in the OFF position and the other in AUTO.
- 5. Isolate the compressor with its Control Switch in OFF by closing valves. I (N/A valves left in OPEN position)
- a. 4630A/4633A Unit A 4630Al4633A OR
- b. Unit B 4630/4633B
- 6. Open nitrogen supply to the waste gas compressor that is in the AUTO position. (N/A valves left in CLOSED position)
- a. UnitA Unit A 4631A 463lA OR
- b. Unit B B 4631B 463lB
- 7. Start the waste gas compressor that is in the AUTO position by placing its its Control Control Switch Switch to the ON ON position.
position.
- 8. Open or verify open open PRT Vent Valve, CV-3-549.
CAUTION CAUTION If aa Containment If Containment Isolation or or Safety Safety Injection Injection signal signal is is actuated, actuated, CV-3-519B CV-3-519B mustmust bebe closed closed to to ensure ensure containment containment integrity. integrity. 9.
- 9. Open Open PRT PRT Makeup Makeup Valve, Valve, CV-3-519B.
CV-3-5l9B. W97:JM/sr/Ir/ev/mra W97:JM/sr/lr/ev/mr
Procedure No.: Procedure
Title:
Page: 20 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 9/8/00 INITIALS INITIALS cici VERIF CK'D VERIF 7.5.2 (Cont'd) 7.5.2 d) t (Cont
- 10. WHEN
- 10. WHEN PRT PRT level level approaches approaches 95 percent on 95 percent on LI-3-470, LI-3-470, OR PRT PRT pressure pressure approaches 10 approaches 10 psig psig on P1-3-472, THEN on PI-3-472, THEN close close PRT PRT Makeup Makeup Valve,Valve, CV-3-519B.
CV-3-519B.
- 11. Maintain
- 11. Maintain the the PRT PRT level level at at 90 to 95%
90 to for 25 95% for 25 to to 35 35 minutes. minutes. I
- 12. Place
- 12. Place aa Waste Waste GasGas Compressor Compressor control control switch switch inin the the AUTO AUTO position position AND verify OR position verify OR position the the other other waste waste gas gas compressor I
AND compressor control control switch switch in the in the OFFOFF position. position. I
- 13. Close or
- 13. or verify verify closed closed the following following nitrogen nitrogen supply supply valves valves to to the the waste waste gas gas compressors:
compressors: I
- a. Unit A 4631A
- b. Unit B 4631B I
- 14. Open or verify open the following waste gas compressor isolation valves: I
- a. Unit A 4630Al4633A 4630A14633A
- b. Unit B 4630/4633B I
- 15. WHEN PRT pressure indicated on P1-3-472 PI-3-472 has decreased to approximately approximately 6 psig (as controlled by nitrogen supply regulator), THEN close PRT Vent Valve, CV-3-549.
- 16. Have Chemistry monitor the PRT until the oxygen reading is less than 2 percent percent oxygen oxygen by volume.
CAUTION CAUTION DO NOT proceed proceed withwith this section section of of the procedure untiluntil oxygen oxygen levels in in the PRT are are reduced reduced to to less less than than 22 percent percent byby volume. volume. 17.
- 17. Close Close Primary Primary Water Water toto Cntmt Cntmt Isol, Isol, CV-3-519A CV-3-519A W97:JM/sr/I r/ev/mra W97:JM/srllr/ev/mr
ProcedureNo,: Procedure No.: ProcedureTitle:
Title:
Page: Page: Procedure 21 21 Approval ApprovalDate: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer ReliefTank Tank 7/2/03 7/2/03 INITIAL S INITIALS CKD VERIF CK'D VERIF 7.5.2 (Cont'd) 7.5.2 (Contd)
- 18. Open Holdup
- 18. Open Holdup Tanks Tanks Header Header to to VH, VH, 1122.
1122.
- 19. Open VH
- 19. Open VH toto Cover Cover Gas Gas Supply Supply Cross Cross Connection, Connection, 4627.
4627.
- 20. Drain
- 20. Drain PRT PRT to to normal normal operating operating band band in in accordance accordance with with Subsection Subsection 7.1, 7.1, Draining the Draining the PRT.
PRT.
- 21. Verify
- 21. Verify all log entries all log entries specified specified in in Subsection Subsection 2.2 2.2 have have been been logged.
logged. Date/Time Date/Time Completed: Completed:_ _ _____ PERFORMED BY (Print) PERFORMED (Print) INITIALS iNITIALS REVIEWED BY: REVIEWED BY: RCO or Designee Wq7.lM/sr/Ir kv/mrn W97:JM/sr/lr/ev/mr
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 22 22 Approval ApprovalDate: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer ReliefTankTank 7/2/03 7/2/03 7.6 7.6 Depressurizing the Depressurizing the PRTPRT Prior Prior to to Opening Opening for for Maintenance Maintenance INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Date/Time Started: Started: _ _ _ _ _ _ _ _ _ _ __ 7.6.1 7.6.1 Initial Initial Conditions Conditions 1.1. All All applicable applicable prerequisites prerequisites listed listed in in Section Section 3.0 3.0 are are satisfied. satisfied. 2.
- 2. PRT hydrogen PRT hydrogen concentration concentration hashas been been reduced reduced to to less less than percent by than 44 percent by I volume volume usingusing Subsection 7.3 of Subsection 7.3 of this this procedure.
procedure.
- 3. The The PRT and/or andlor Pressurizer Relief Valves will be opened for for maintenance.
maintenance. 7.6.2 7.6.2 Procedure Steps Procedure Steps CAUTION subsection shall not be used for normal purging or pressure This procedure sUbsection reductions.
- 1. Verify that the PRT level is in the normal band of 68 percent percent toto 83 83 percent.
percent.
- 2. Isolate that the nitrogen regulator PCV-3-473 as follows:
- a. Close Nitrogen Regulator Isol Iso1 Vlv, V1v, 3-550.
- 3. Verify a waste gas compressor is operable in AUTO, AUTO, OR start start aa waste waste gas gas compressor.
- 4. Open the PRT Open Vent Valve, CV-3-549.
PRT Vent 5.
- 5. WHEN PRT WHEN PRT pressure pressure stops stops decreasing decreasing (at(at approximatel approximately vent header y vent header pressure) as pressure) as indicated indicated on on P1-3-472, PI-3-472, THEN close the THEN close the PRT PRT VentVent Valve, Valve, CV-3-549.
W97:JM/sr/I r/ev/mrci W97:JM/sr/lr/ev/mr
ProcedureNo.: Procedure No.: ProcedureTitle:
Title:
Page: Page: Procedure 23 23 Approval ApprovalDate: Date: 3-OP-041.3 3-0P-041.3 Pressurizer Relief Pressurizer ReliefTank Tank 7/2/03 7/2/03 INITIALS INITIALS CKD VERIF CK'D VERIF 7.6.2 (Cont'd) 7.6.2 d) T (Cont 6.
- 6. Verify all Verify all log log entries entries specified specified in Subsection 2.2 in Subsection 2.2 have have been been logged.
logged. Date/Time Date/Time Completed: Completed:__ _ _ _ ________ PERFORMED BY PERFORMED BY (Print) (Print) INITIALS INITIALS REVIEWED BY: RCO or Designee END OF TEXT W97:JM/sr/I r/ev/mra W97:JM/sr/lr/ev/mr
Procedure No.: Procedure
Title:
Page: 24 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 7/2/03 ATTACHMENT11 ATTACHMENT (Page 11 of3) (Page of 3) VALVEALIGNMENT VALVE ALIGNMENT PERSON (S) PERSON PERFORMING OR (5) PERFORMING ORVERIFYING VERIFYINGALIGNMENT ALIGNMENT INITIALS INITIALS (PRINT) (PRINT) Check CV) Check (J) Tag Tag column column iftag if tag is missing, mislabeled, illegible, or improperly secured REMARKS REMARKS - Indicate any component not in the "Normal" Indicate ?NorjT1a1?I position and note the reason. For For component under clearance, provide clearance number. Alignment Alignment Started: Started: Time: _ _ _ _ __ Time: Date: - - - - - - Date: Alignment Alignment Completed: Completed: Time: Time: - - - - - - Date: _ _ _ _ __ Date: Approved Approved by: by: -~--;--=-o---=----:-- Time: _ _ _ _ __ Time: Date: _ _ _ _ __ Date: Nuclear Nuclear Plant Plant Supervisor Supervisor or orSRO SRODesignee Designee W97:JM/sr/I rlv/mro W97:JM/srlir/ev/mr
Procedure No.: Procedure
Title:
Page: 25 Approval Date: 3-0P-041.3 Pressurizer Relief Tank 7/2/03 ATTACHMENT ATTACHMENT11 (Page 22 of3) (Page of 3) VALVE VALVE ALIGNMENT ALIGNMENT (INSIDE (INSIDE CONTAINMENT) CONTAINMENT) Pressurizer Pressurizer Relief ReliefTank Tank Checked Checked Component Tag Tag&&Vlv Vlv Component Component Component Description Description Normal Normal No. Pos No. Position Position (J) (-V) Init Init LCV-3-1003B LCV-3-1003B PRT PRT Drain Drain Valve Valve to to Sump Sump CLOSE CLOSE CV-3-523 CV-3-523 PRT Drain PRT Drain Valve Valve CLOSE CLOSE 3-521A 3-521A LI-3-470 LI-3-470 Upper Upper Root Root Valve Valve OPEN OPEN 3-521B 3-521B LI-3-470 LI-3-470 Lower Lower Root Root Valve Valve OPEN OPEN 3-511 3-511 Nitrogen Supply Supply Isol OPEN OPEN CV-3-549 CV-3-549 PRT Vent PRT Vent Valve Valve CLOSE CLOSE 3-517A 3-517A PRT Vent Cntmt Atmosphere PRT Vent to CLOSE CLOSE 3-517B 3-517B Gas Analyzer Line Isol OPEN CV-3-519B CV-3-519B PRT Makeup Valve CLOSE CLOSE Pipe and Valve Room Checked Checked Component Tag&Vlv Tag & Vlv Component Component Description Component Description Normal Normal No. Pos No. Position Position (1) (-V) Init CV-3-516 CV-3-516 Cont Iso Vlv PRT to 6A CLOSED 3-516A Test CLOSED & CLOSED 3-516A Test Corm Conn Before Before SV-3-6385 SV-3-6385 CAPPED CAPPED 3-516B Test CLOSED & CLOSED & 3-516B Test Conn Conn Before Before CV-3-516 CV-3-516 CAPPED CAPPED 3-516C Test Test Conn Conn Between Between CV-3-516 CV-3-516 and and CLOSED & CLOSED & 3-516C SV-3-6385 SV-3-6385 CAPPED CAPPED 3-552 3-552 Iso Vlv Cont Iso Cont Vlv PRT PRT toto 6A 6A OPEN OPEN W97:JM/sr/I rlev/mra W97:JM/sr/lr/ev/mr
Procedure No.: Procedure
Title:
Page: 26 Approval Date: 3-OP-0 3-0P- 044L3 1.,3 I _ ---~=~:Pressu
- ...;=rizer Relief Tank
- .:.. __ ____l'___ _ 7/2/03 ATTA CHMENT 1 (Page 3 of3) of 3)
VALVE ALIGALIGN MENT NMEN T (INSIDE CONT AINM ENT) Controoll Room Contr Checked Compo Comp nent onent Norm Tag & Vlv Compo Comp nent Description onent Norma all No. Position Pos POS (,J) Init CV-3-5516 16 PRT to Gas Analyzer CLOSED CLOSE D SW SWINA AUTO UTO SV-3 -6385 SV-3-6 385 PRT to Gas Analyzer CLOSED CLOSE D SWINA AUTO UTO C289A Panel Panel - Chem
- Chemiistry stry Hot Lab Checked Compo Comp nent onent Norm Tag & Vlv Tag&Vl v Compo Comp nent Description onent Norma all No. Position Pos (q)
(,J) mit Init CV-3-516 CV 5l6 PRT to Gas Analyzer Selector Sw SV-3-6385 Selector Switch PRT to Gas Analyzer CLOSED f Selector Sw Selector Switch CLOSED I FINAL PAGE W97:JM/ W97:JMIsr/I sr/lr/ev/m rIAvImro ra
Appendix C Job Performance Measure ES-C-I Form ES-C-1 Worksheet Facility: Turkey Point Task No: 01051011100
-=--~-----------~------
Enter Containment Via Job Performance Task
Title:
Emergency _E:.:.:.:..;..m;..:e-' Access Hatch
-'rg"'-e;..:n..:...:cCLy...:.A...:.c:....:c;..:e;..:s-"-s-'-H..:...:a::..:tc.=..:h-'-___ Measure No: Systems __i _____________
_S"-ys_t_e_m_s_- K/A
Reference:
KIA 103 A2.05 (2.9/3.9) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: _J.=..:P--'M~ JPM _______________________________________________________ Simulated Performance Yes Actual Performance No
-------------------- -----------~-------
Classroom - - - - - - - - - - - - - - Classroom Simulator - - - - - - - - - - - - - - Plant - - - - - - - X- - - - - - Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. Entry into Unit 3(4) Containment is required through the Emergency Access Hatch
- 2. Emergency Access Hatch inner and outer doors are closed
- 3. An active RWP is in place
- 4. The Shift Manager has authorized entry
- 5. HP has removed the Very High Rad Area lock from the containment personnel air lock Task Standards:
- 1. Containment entered through the Emergency Access Hatch
- 2. Emergency Access Hatch handles properly positioned after entry Required Materials:
- 1. Emergency Access Hatch key
- 2. 3(4 3(4)-OP-051
)-OP-051.1,.1, Emergency Access Hatch Operating Instructions General
References:
3(4)-OP-051 .1, Emergency Access Hatch Operating Instructions
- 1. 3(4)-OP-051.1, Initiating Cue:
You have been directed by the Shift Manager to enter Unit 3(4) Containment through the Emergency Access Hatch. Time Critical Task: No Validation Time: 15 minutes
Appendix C Page 2 of 9 Form ES-C-1 ES-C-I INSTRUCTIONS TO OPERA OPERATORTOR READ TO TO OPERA OPERATOR: TOR: WHEN II TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED DIRECTED IN THE INITIATING CUES. II WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM PERFORM THIS TASK. BEFORE STARTING, II WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS:
- 1. Entry into Unit 3(4) Containment is required through the Emergency Access Hatch
- 2. Emergency Access Hatch inner and outer doors are closed
- 3. An active RWP is in place
- 4. The Shift Manager has authorized entry
- 5. HP has removed the Very High Rad Area lock from the containment personnel air lock INITIATING INITIA TlNG CUE:
You have been directed by the Shift Manager to enter Unit 3(4) Containment through the Emergency Access Hatch. NOTE 1:I: Conduct JPM Briefing outside RCA to allow candidate to show how to obtain keys from Control Room before RCA entry. NOTE 2: Examiner/Evaluator must specify on which unit this JPM is to be performed. NOTE 3: Inform examinee to simulate performance of steps involving hands on manipulation of plant equipment during this JPM. NOTE 4: This JPM requires entry into the RCA. Ensure candidate observes all requirements for entering and exiting the RCA. Procedures for this JPM should be obtained before entering the RCA and disposed of after exiting the RCA. Do you have any questions? You may begin.
I Appendix C of 9 Page 3 of9 ES-C-I II Form ES-C-1 Denote critical steps with a check mark ((vJ vf Start Time Obtain a copy of 3(4)-OP-051.1, Emergency Access Hatch Operating STEP 1 1 : Instructions and check for active OTSCs. - - SAT Review precautions/limitations, prerequisites and initial conditions - - UNSAT 3(4)-OP-051 .1 using Lotus Notes on LAN PC
- 1. Obtains copy of 3(4)-OP-051.1 3(4)-OP-051 .1 for active OTSCs
- 2. Checks 3(4)-OP-051.1 STANDARDS: 3(4)-OP-051 .1 section 3.0 to ensure prerequisites met.
- 3. Reviews 3(4)-OP-051.1
- 4. Reviews 3(4)-OP-051.1 3(4)-OP-051 .1 section 4.0 for applicable precautions/
limitations. 3(4)OP-051.1 section 5.1.1 initial conditions met.
- 5. Ensures 3(4)-OP-051.1 CUE*
CUE: 3(4)-OP-051. I section 3.0, state as Shift When candidate reviews 3(4)-OP-051.1
. Manager that the prerequisites have for this procedure are met.
NOTE: This step should be conducted prior to RCA entry. Determine status of emergency access hatch inside door (closed) STEP 2 : - - SAT v Unlock emergency access hatch as follows: UNSAT
- a. Obtain emergency hatch key from Control Room key locker --
- b. Notify Plant Security to unlock emergency hatch AND post a
, guard as necessary
- c. Notify HP to remove HP lock on emergency hatch door (procedure step 5.1.2.1.a)
- 1. Determines emergency access hatch inside door closed.
- 2. Obtains emergency hatch key from Control Room key locker STANDARDS: 3. Notifies Security to unlock emergency hatch and post a guard as necessary (NOTE: Posting guard not critical to this task.)
- 4. Notifies HP to remove HP lock on emergency access hatch door I. When candidate correctly locates Control Room key locker and 1.
describes what to do to obtain the key, tell candidate that the Shift Manager has provided them the key.
- 2. Respond as Security when notified of need to unlock emergency CUES CUE:
. hatch and post guard as necessary. Tell candidate that the the lock has been removed and a guard posted.
--- 3. Respond as HP when notified of need to remove emergency hatch HP lock. Tell candidate that this lock has been removed. NOTE: This step should be conducted prior to RCA entry.
Appendix C C Page 44 of9 Page of 9 Form ES-C-1 Form ES-C-I Turn Emergency Turn Emergency Airlock Airlock Vent to to Atmosphere (equalizing) (equalizing) Valve, Valve, 3(4)- 3(4)- STEP 33 SAT STEP S9Ato OPEN S9A to OPEN - - SAT V
./
(procedure step step 5.1.2.1.b) 5.1.2.1.b) -- UNSAT UNSAT (procedure STANDARD: Turns 3(4)-S9A to OPEN. When candidate correctly describes how to open valve, confirm
- 1. When new valve position.
CUE:
- 2. If candidate indicates that air movement would be heard, confirm this indication as it is a normal occurrence for this procedure step.
Pl-3(4)-866 Root Isolation Valve 3(4)-S9G open
- 1. Verify PI-3(4)-866 STEP 4 : SAT
- 2. Verify differential pressure (atmosphere - air lock) gauge reads less than 11 psid UNSAT (procedure steps 5.1.2.1.c & .d)
- 1. Determines 3(4 3(4)-S9G
)-S9G open (PI-3(
(PI-3(4)-866 4 )-866 unisolated) STANDARDS: 2. Determines differential pressure (atmosphere - air lock) gauge reads less than 1 1 psid - 1. When candidate correctly locates 3(4)-S9G and describes how to determine it is open, confirm open indication.
- 2. When atmosphere - air lock dp gauge is correctly identified:
CUE CUE:
- a. If 3(4)-S9A correctly opened, point to PI P1 reading of 0.5 psid
- b. If 3(4)-S9A not properly operated, point to PI P1 reading of 1.2 psid. Tell candidate this value is stable.
I Appendix Appendix C C Page 55 of Page of 99 Form ES-C-1 Form ES-C-I I Operate emergency Operate emergency access access hatch hatch outside outside door door to to enter enter hatch: hatch: STEP STEP 55 SAT
- a. Turn outside outside door
- - SAT v a. door latch latch handle handle to to the UNLATCHED UNLATCHED position position
- b. Open outside door UNSAT
- - UNSAT
- c. Enter emergency access hatch
- d. Close outside door (from inside hatch)
- e. Turn outside door latch handle to the LATCHED position (from inside hatch)
(procedure steps 5.1.2.1.e thru .h)
- 1. Turns outside door latch handle to the UNLATCHED (up) position STANDARDS: 2. Opens outside door, enters hatch, then closes outside door
- 3. Turns outside door latch handle to the LATCHED position (from insude hatch)
- 1. When candidate correctly locates and describes how to operate the outside door latch handle open/closed, confirm operation of the CUE: door latch handle
- 2. When candidate correctly describes how to open/close outside door, confirm door operation Turn Emergency Airlock Vent to Atmosphere (equalizing) Valve, 3(4)-
STEP 6 SAT S9A to CLOSE (from inside hatch) -- vV UNSAT (procedure step 5.1.2.1.i) -- STANDARD: Turns 3(4 3(4)-S9A
)-S9A to CLOSE.
When candidate correctly describes how to close valve, confirm new CUES CUES: . valve position. Turn Emergency Airlock Vent to Containment (equalizing) Valve, 3(4)- STEP 7 S9B S98 to OPEN (from inside hatch) - - SAT v (procedure step 5.1.2.1.j) I UNSAT STANDARD: STANDARD: Turns 3(4)-S9B 3(4 )-S98 to OPEN. OPEN. CUE* When candidate correctly describes how to open valve, confirm new CUE: ~~~~., valve position.
Appendix CC Appendix Page 66 of Page of 99 Form Form ES-C-1 ES-C-I STEP Verify differential pressure Verify differential pressure gauge gauge (air (air lock lock - containment) containment) reads reads less less 88 STEP than 1 than 1 psidpsid - - SAT SAT (procedure steps (procedure steps 5.1.2.1.k) 5.1.2.1.k) - - UNSAT UNSAT Determines differential Determines differential pressure pressure (air lock - containment) (air lock containment) gauge gauge reads reads STANDARD* STANDARD: less than 1 less than 1 psid psid When air When air lock lock - containment
- containment dp dp gauge gauge is is correctly correctly identified:
identified:
- a. IfIf 3(4)-S98
- a. 3(4)-S9B correctly correctly opened, opened, point point to to PI reading of P1 reading of 0.5 0.5 psid psid CUEs CUEs:
- b. IfIf 3(4)-S98
- b. 3(4)-S9B not not properly properly operated, operated, pointpoint toto PI P1 reading reading ofof 1.2 1.2 psid. Tell psid. Tell candidate candidate this this value value is is stable.
stable. STEP Operate emergency emergency accessaccess hatch hatch inside inside door door to to enter enter containment: containment: STEP 99 : SAT v a. Turn inside door latch handle to the UNLATCHED UNLATCHED position
- b. Open inside door - - UNSAT
- c. Enter containment
- d. Close inside door (from containment)
- e. Turn inside door latch handle to the LATCHED position (from
~~ containment) (procedure steps 5.1.2.1.1 thru .0)
- 1. Turns inside door latch handle to the UNLATCHED
- 1. UNLATCHED position STANDARD STANDARDS: S: 2. Opens inside door, enters containment, then closes inside door
- 3. Turns inside door latch handle to the LATCHED position 1.
- 1. When candidate correctly locates and describes how to operate the inside door latch handle open/closed, open!closed, confirm operation of the CUE: door latch handle (may use figure provided for inside containment) containment)..
- 2. When candidate correctly correctly describes how to open/close open/close inside door, confirm door operation STEP Turn Turn Emergency Emergency Airlock Airlock Vent to Atmosphere Vent to Atmosphere (equalizing)
(equalizing) Valve, Valve, 3(4 3(4)- STEP 10 10 SAT SAT S9B to CLOSE (from inside containment) S9B to CLOSE (from inside containment) -- v UNSAT (procedure (procedure step step 5.1.2.1.p) 5.1.2.1. p) - - UNSAT STANDARD STANDARDS: S: Turns Turns 3(4)-S9B 3(4 )-S9B to to CLOSE. CLOSE.
- When When candidate candidate correctly correctly describes describes how how to close valve, to close valve, confirm new confirm new CUE.
CUE: valve valve position position (may (may useuse figure figure provided provided for for inside inside containment) containment)..
I Appendix C Page 7 of 9 Form ES-C-1 ES-C-I I Terminating Terminating Tell candidate that JPM is complete. STOP Cue: Stop Time _ _ __
Appendix C Page 8 of 9 Form ES-C-1 ES-C-I Verification of Completion Job Performance Measure No. ~SLys~t~e~m~s~-~i~~~~~~~~~~~~~~~~~~~~~~ JobPe~rmanceMeasu~No. Systems Examinees Name: Examinee's Examiners Name: Examiner's Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: ~,-~~~~~~-~~~~-~~~~~~~~~~~~~~~~~~~~~~~~~~
Response
Result: Satisfactory/Unsatisfactory Examiners Examiner's signature and date: _~~~_~~~~~~~~_ _~~_
JPM BRIEFING JPM BRIEFING SHEETSHEET INITIAL CONDITIONS: INITIAL CONDITIONS:
- 1. Entry
- 1. Entry into into Unit Unit 3(4) Containment isis required 3(4) Containment required through through the the Emergency Emergency Access Access Hatch Hatch Emergency Access Hatch
- 2. Emergency Hatch inner inner and outer doors are closed
- 3. An active RWP
- 3. RWP is in place is in place Shift Manager
- 4. The Shift Manager has has authorized entry
- 5. HP has removed the Very High Rad Area lock from the containment personnelpersonnel air lock lock INITIATING
!NITIA TlNG CUE: You have been directed by the Shift Manager to enter Unit 3(4) Containment through the Emergency Access Hatch. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 3 ci. c 3-0P-051.1 c) c_)
Title:
Emergency Access Hatch Operating Instructions Safety Related Procedure Responsible Department: Operations Revision Approval Date: 3/9/04 95-0047P, 9S-0369P, RTSs 92-0128P, 93-0466P, 94-1013P, 9S-0047P, 95-0369P, 97-0837P, 02-0598P, 04-0200P 02-0S98P, PC/Ms 89-S42, PCIMs 89-542, 9S-039 9 5-039 0 740-94, 0394-97 OTSCs 0740-94, 0394-9 7 W97:/JAM/Ir/ev/mrg W97:1JAM/ir/ev/mrg
Procedure No.: Procedure
Title:
Page: 2 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 3/9/04 LIST OF EFFECTIVE PAGES Revision Page Date 11 03/09/04 03109/04 2 03/09/04 3 09/10/97 4 05/30103 05/30/03 55 09/10/97 09110197 6 09/10/97 7 03/09/04 8 03/09/04 9 09110197 09/10/97 10 09/10/97 09110/97 11 09110/97 09/10/97 12 09/10/97 09110/97 13 09/10/97 09110/97 14 09/10/97 09110/97 15 09/10/97 16 09/10/97 09110197
Procedure No.: Procedure
Title:
Page: 3 Approval Date: 3-0P-051.1 Emergency Access Hatch Operating Instructions 9/10/97 TABLE OF CONTENTS Section 1.0 PURPOSE .....................................................................................................................
. 4
2.0 REFERENCES
/RECORDS REQUIREDI REFERENCESIRECORDS REQUIRED! COMMITMENT DOCUMENTS ............................................................................... 4 3.0 PREREQUISITES ....................................................................................................... 6 4.0 PRECAUTIONS/LIMITATIONS PRECAUTIONS/LIMITATIONS.............................................................................. 7 5.0 STARTUP/NORMAL OPERATION ........................................................................ STARTUPINORMAL 8 6.0 ShUTDOWN SHUTDOWN................................................................................................................ 13 7.0 INFREQUENT OPERATIONS ................................................................................. 14 ATTACHMENT Attachment l'1 Emergency Access Hatch Alignment Verification ...................... ...... ................ 16 Wq7!. AM/Ir/w/mrn
Procedure No.: Procedure
Title:
Page: 4 Approval Date: 3-0P-051.1 Emer2ency Access Hatch Operating Instructions 5/30/03 1.0 1.0 PURPOSE 1.1 This procedure provides the prerequisites, precautions/limitations, and instructional of the Containment Emergency Access Hatch. guidance for normal operation ofthe
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT DOCUMENTS REFERENCESIRECORDS 2.1 References 2.1.1 Technical Specifications
- 1. Section 3.6.1.3, Containment Air Locks
- 2. Section 3.9.4, Containment Building Penetrations 2.1.2 FSAR
- 1. Section 5.1.5.1, Access Air Locks and Doors 2.1.3 Vendor Technical Manuals
- 1. Pittsburgh - Des Moines Steel Co., Instruction Manual for containment access doors and locks 2.1.4 Plant Procedures
- 1. 0-ADM-215, Plant Surveillance Tracking Program
- 2. 0-OSP-200.1, Schedule of Plant Checks and Surveillances 0-OSP-200.l, 2.1.5 PCIM, Correspondence)
Miscellaneous Documents (i.e., PC/M,
- 1. QAO-PTN-87-807; Corrective Action Request CAR 87-051
- 2. PCIM 95-039, Emergency Hatch Gauge Qualification PC/M 2.2 Records Required 2.2.1 The date, time and section completed shall be entered in the narrative RCO log.
Also, any problems encountered while performing the procedure should be entered (i.e., malfunctioning equipment, delays due to changes in plant conditions, etc.).
Procedure No.: Procedure
Title:
Page: 5 Approval Date: 3-0P-051.1 Emergency Access Hatch Operating Instructions 9/10/97 2.2.2 2.2.2 Completed copies Completed copies of of the the QA QA Record Record Page(s) Page(s) for for the the below below listed listed item(s) item(s) constitute Quality Assurance records and shall constitute shall be transmitted to QAQA Records for for retention in accordance retention accordance with Quality Assurance Records Program requirements: 1.
- 1. Section 7.0 Section
- 2. Attachment 11 2.2.3 Completed copies of the below listed item(s) shall be retained in the Nuclear Plant Supervisors file until the next performance of that section, enclosure, or Supervisor's attachment:
- 1. Section 7.0
- 2. Attachment 11 2.3 Commitment Documents 2.3.1 PTN-PMN-87-475, Corrective Action in Response to QAO-PTN-87-807 (CAR-87-051), October 15, 1987 2.3.2 PTN-PMN-87-532, Corrective Action in Response to QAO-PTN-914, November 16, 1987 1107*!
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 9/10/97 3.0 3.0 PREREOUISITES PREREQUISITES 3.1 Security Personnel will unlock and permit access to the containment only after direct Security direct authorization is is received from thethe on-shift Nuclear Plant Supervisor. 3.2 3.2 instruments and All instruments and control devices are control devices are in in service service for for the the Emergency Emergency Access Hatch System System operation with no surveillance required, outstanding PWOs, clearances, or temporary system alterations that affect system operability as per the following: 3.2.1 O-ADM-215, Plant Surveillance 0-ADM-215, Surveillance Tracking Program and 0-OSP-200.l, O-OSP-200.1, Schedule of Plant Checks and Surveillances. (No surveillances have exceeded the date required on the Surveillance Use of Grace Sheet.) 3.2.2 Temporary System Alteration (TSA) Log 3.2.3 Clearance Log 3.2.4 Out-of-Service Log Mn?.I IAaII.-I-,I.,.-,.
Procedure No.: Procedure
Title:
Page: 7 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 3/9/04 4.0 PRECAUTIONS/LIMITATIONS 4.1 The Operations Support Supervisor shall review all changes to this procedure, verify that the change does not effect the emergency access hatch plaques and, if required shall ensure that the same change is also made to the applicable plaque. [Commitment - Step 2.3.2] 4.2 All Florida Power and Light safety work practices shall be followed. 4.3 All work in the Radiation Controlled Area shall be performed in accordance with the requirements of the Radiation Work Permit and ALARA Program. 4.4 The following interlocks are associated with the containment personnel and emergency air locks: 4.4.1 Prevents both doors from being opened at the same time. This interlock can be defeated, which would violate containment integrity and is permitted only during conditions specified in Technical Specifications, Section 3.6.1.3. 4.4.2 of the doors unless the associated equalizing valve is open. Prevents the opening ofthe 4.4.3 Prevents the closing of the equalizing valve unless the associated door is closed. 4.4.4 Prevents both equalizing valves from being open at the same time. 4.4.5 Prevents opening the inside door with the air lock pressure greater than 11 psig above containment pressure. 4.4.6 Prevents opening the outside door with atmospheric pressure greater than 11 psig above air lock pressure. 4.5 Extreme caution must be taken to stand clear of the air lock door when opening the inside door from inside containment or the outside door from inside the air lock. If a higher pressure exists on the closing face of these doors, they will open with considerable force when unlatched. 4.6 The key operated locking mechanism in the outer door is under the control of the Nuclear Plant Supervisor and shall be kept locked except for entry of authorized personnel. (The design of the lock permits unrestricted exit from inside the containment, for inoperable containment air lock door refer to Tech Spec 3.6.1.3) 4.7 The containment personnel air lock shall have its very high rad area lock removed by HP prior to use of the emergency access hatch to allow for an alternate means of exit from containment in case of emergency access hatch malfunction. 4.8 During and after access hatch operation, door position shall be verified by checking the I light indication on VPB.
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 3/9/04 5.0 STARTUP/NORMAL OPERATION 5.1 Emergency Air Lock Doors 5.1.1 Initial Conditions 1.
- 1. All applicable prerequisites as listed in Section 3.0 are satisfied.
- 2. Ensure HP has removed the very high rad area lock from the containment personnel air lock.
5.1.2 Procedure Steps
- 1. Perform the following to enter the containment with the inside door closed:
CAUTION Use of excessive force may damage the interlock, hindering operation of the airlock. Any difficulties in the interlock or door operation shall be reported to the control room.
- - - - - - - - - -.- -NOTE - -- -- -- -- -- - ~
I II Security personnel will unlock and permit access to the containment only after direct II I authorization is received from the on-shift Nuclear Plant Supervisor. I LI__ _______________________ J a a a a a
- a. Have the emergency personnel hatch unlocked as follows:
(1) Obtain the emergency hatch key from the key locker in the Control Room. (2) Notify Plant Security to unlock the emergency hatch AND post a guard as necessary. (3) Notify Health Physics to remove the HP lock on the emergency hatch door.
- b. Turn the Emergency Airlock Vent to Atmosphere Valve, 3-S9A (equalizing valve) to the OPEN position.
- c. Verify Open, P1-3-866 PI-3-866 Root Isolation Valve, 3-S9G.
Procedure No.: Procedure
Title:
Page: 9 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 9/10/97 5.1.2.1 (Cont'd) 5.1.2.1 (Confd)
- d. Verify that the differential pressure gauge reads reads less less than 11 psi.
- e. Turn the Outside DoorDoor Latch handle to the the UNLATCHED UNLATCHED position.
f.f. Push the outside door Push door open.
- g. WhEN you have entered the airlock, THEN push the outside door WHEN closed.
- h. Turn the Outside Door Latch handle to the LATCHED position.
i.
- 1. Turn the Emergency Airlock Vent to Atmosphere Valve, 3-S9A (equalizing valve) handle to the CLOSED position.
- j. Proceed to the inside door AND turn the Emergency Airlock Vent to Containment Valve, 3-S9B (equalizing valve) handle to the OPEN position.
- k. Verif, that the differential pressure gauge reads less than 11 psi.
Verify
- 1. Turn the inside door latch handle to the UNLATCHED position.
- m. Push the inside door open.
- n. WHEN you have entered the containment, THEN push the inside door closed.
- o. Turn the inside door latch handle to the LATCHED position.
- p. Turn the Emergency Airlock Vent to Containment Valve, 3-S9B (equalizing valve) handle to the CLOSED position.
WQ7/.lAM/Ir/vImro
Procedure No.: Procedure
Title:
Page: 10 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 9/10/97 5.1.2 (Cont'd) 5.1.2 d) T (Cont
- 2.
- 2. Perform the Perform the following following to to close close inner inner airlock airlock door door from from outside outside containment:
containment: r-----------NOrE----------. NOTE I_i I II I The following The following steps allow entering the allow entering the containment containment from from atmosphere to the mechanical interlocking between the two doors atmosphere with with the the inside inside door door I open. Due to doors the the outside outside door cannot cannot I opened when be opened when the inside inside door door is open. The The following steps outline outline the procedure procedure for II II closing the closing inside door the inside door from from the the atmosphere atmosphere side side of of the the outside outside door. door. II
- a. Rotate the inside door handwheel, located on the atmosphere side of the outside door bulkhead, to the CLOSED position, closing the inside door.
- b. Turn the inside door latch handle to the LATCHED position, latching the inside door.
- c. Turn the Emergency Airlock Vent to Containment Valve, 3-S9B
((equalizing equalizing valve) handle to the CLOSED position, closing the emergency airlock vent to containment valve.
- d. Proceed with containment entry as described in Substep 5.1.2.1 of this procedure, if desired.
- 3. Perform the following to leave the containment with the outside door closed:
- a. Turn the Emergency Airlock Vent to Containment Valve, 3-S9B (equalizing valve) handle to the OPEN position.
- b. Verify that the differential pressure gauge reads less than 11 psi.
- c. Turn the inside door latch handle to the UNLATCHED position.
- d. Pull the inside door open.
- e. WHEN you have entered the airlock, THEN pull the inside door closed.
A!Q7L IAMIIrkr,Imrr,
Procedure No.: Procedure
Title:
Page: 11 Approval Date: 3-0P-051.1 Emer~ency Access Hatch Operatin~ Instructions 9/10/97 5.1.2.3 (Cont'd) 5.1.2.3 (Contd)
- f. Turn the inside door latch latch handle to the LATCHED position.
- g. Turn the Emergency Airlock Vent to ContainmentContainment Valve, 3-S9B (equalizing valve) handle (equalizing handle to the CLOSED position.
position.
- h. Proceed to the outside door AND turn the Emergency Airlock Vent to Atmosphere Valve, 3-S9A 3-S9A (equalizing valve) handle to the OPEN position.
i.
- 1. Verify that the differential pressure gauge reads less than 11 psi.
CAUTION Stay clear of the door when unlatching. j. J. Turn the outside door latch handle to the UNLATCHED position.
- k. Pull the outside door open.
- 1. WHEN WhEN you have passed through the door to the outside, THEN pull the outside door closed.
rn.
- m. Turn the outside door latch handle to the LATCHED position.
- n. Turn the Emergency Airlock Vent to Atmosphere Valve, 3-S9A (equalizing valve) handle to the CLOSED position.
NOTE I I Locking is not required when a security guard is posted outside of the hatch. I Locking
------=----------------------
a a a a a- a a a a a a -
- o. WhEN WHEN personnel access is no longer necessary j3 OR IF the Containment is posted as a locked high radiation area, THEN contact Security to lock the hatch.
[Commitment [Commitment - Step
- Step 6.2.1]
6.2.1] p.
- p. Notify HP Notify HP Supervisor Supervisor to ensure aa very high rad area area lock is placed on containment personnel air lock.
the containment WQ7I. IAM/Ir/u/mrri
Procedure No.: Procedure
Title:
Page: 12 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 9/10/97 5.1.2 (Cont'd) 5.1.2 (Contd) 4.
- 4. Perform the Perform the following following to close the to close the outer outer airlock airlock door door fromfrom inside inside containment:
containment: I
- - - - - - - - - - - - NOTE - -- -
NOTE I I The following steps allow leaving the Containment The following Containment with with the outside door door open. Due to to the the I II mechanical interlocking between the two doors the the inside door cannot cannot be opened when when the the II I outside door is outside door from the door from is open. open. The the Containment The following Containment side following steps side of steps outline outline the the procedure procedure for for closing closing the the outside outside I door of the the inside inside door. door. I II
- a. Rotate the outside door handwheel, located on the containment side of the inside door bulkhead, to the CLOSED position, closing the outside door.
- b. Turn the outside door latch handle to the LATCHED position, latching the outside door.
- c. Turn the Emergency Airlock Vent to Atmosphere Valve, 3-S9A (equalizing valve) handle to the CLOSED position, closing the emergency airlock vent to atmosphere valve.
- d. IF desired, THEN proceed leaving containment as described III in Substep 5.1.2.3 of this procedure.
55.. Verify all log entries specified in Subsection 2.2 have been recorded.
- 6. Notif NotifY the Nuclear Plant Supervisor that the emergency access hatch has been operated AND that Attachment 11 of this procedure should be performed to verify containment integrity.
\AI7-L IAMIIrIwIm rn
Procedure No.: Procedure
Title:
Page: 13 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 9/10/97 6.0 6.0 SHUTDOWN SHUTDOWN 6.1 None
Procedure No.: Procedure
Title:
Page: 14 Approval Date: 3-0P-OS1.1 Emergency Access Hatch Operating Instructions 9/10/97 7.0 INFREOUENT OPERATIONS INFREQUENT 7.1 Defeating Emergency Air Lock Doors Interlocks Date/Time Started:- - - - - - 7.1.1 Initial Conditions
- 1. All applicable prerequisites as listed in Section 3.0 are satisfied.
7.1.2 Procedure Steps CAUTIONS
- Both doors may be opened at the same time. However this would constitute a violation of containment integrity. Be certain that requirements, as stated in the Technical Specifications, 3.6.1.3 are complied with before opening both doors at the same time.
** In order to open both doors, the interlock must be defeated.
- 1. IF desired and allowed by Technical Specifications Section 3.6.1.3 to leave both doors open, THEN notify the Mechanical Maintenance Department to defeat the interlock.
- 2. Verify all log entries specified in Subsection 2.2 have been recorded.
Procedure No.: Procedure
Title:
Page: 15 Approval Date: 3-0P-051.1 Emergency Access Hatch Operating Instructions 9/10/97 QA RECORD PAGE II II (Page!1 of 1) (Page 7.1 Defeating Emergency Air Lock Doors Interlocks Procedure Revision Date: REIVL4RKS: _________________________________________________________ RE~S: Date/Time Started -------------------- Date/Time Completed _ _ _ _ _ _ _ _ __ Performed By: (Print) Initials I have reviewed this procedure and it has been satisfactorily performed. Any deviation(s) or OTSC(s) utilized in the performance of this procedure has (have) been listed in the Remarks Section. Reviewed Reviewed By: By: -----::-=----::----::-::----::c------------::=-==-=----------- Date: ________________ Nuclear Plant Supervisor or SRO Designee END OF TEXT AIO7i I
Procedure No.: Procedure
Title:
Page: 16 Approval Date: 3-0P-OS1.1 Emereency Access Hatch Operating Instructions 9/10/97 ATTACHMENT 11 ATTACHMENT (Page 11 of (Page of 1) 1) EMERGENCY ACCESS EMERGENCY ACCESS HATCH HATCH ALIGNMENT ALIGNMENT VERIFICATION VERIFICATION IIf QA RECORD PAGE QA RECORD PAGE II (Page 11 of (Page of 1) 1) Date/Time Date/Time Started: Started: _ _ _ _ _ _ _ _ _ _ __ Component Component Component Component Checked by: Checked IV'd Wd by: Number Component Description Component Position (Initials) (Initials) NNA Inside Air Lock Door Latch LATCHED Emergency Air Lock Vent to 3-S9B Containment CLOSED Emergency Air Lock Vent to 3-S9A CLOSED Atmosphere OPEN! OPEN/ 3-S9G P1-3-866 Root Isolation Valve PI-3-866 GAUGE INSTALLED NNA Outside Air Lock Door Latch LATCHED Date/Time Completed: _ _ _ _ _ _ _ _ _ __ Performed By (Print) Initials Ind. Verified By (Print) md. Initials Reviewed By: ---:-::----;----::::7---;::;----:----=~_:;::____:_--- Date: Reviewed By: Date: _ _ _ _ _ _ __ Nuclear Nuclear Plant Plant Supervisor Supervisor or or SRO Designee Designee FINAL FINAL PAGEPAGE AIO7I ItjIIIrI,Irnrn
*1*
aa ,. ~ ( ( (. I
Appendix C Appendix C Job Performance Job Performance Measure Measure Form Form ES-C-1 ES-C-I Worksheet Worksheet Facility: Facility: Turkey Turke~ Point Point Task No: Task No: 24061006100 24061006100 Perform Gaseous Perform Radwaste Gaseous Radwaste Job Performance Job Performance Task
Title:
Task
Title:
Release {SNPO} Release (SNPO) Measure No: Measure No: Systems -jj Systems KIA
Reference:
K/A
Reference:
A4.26 {3.1/3.9} 071 A4.26 071 (3.1/3.9) Examinee: Examinee: Examiner: NRC Examiner: NRC Facility Evaluator: Facility Evaluator: Date: Date: Method of of testing: JPM Simulated Performance Simulated Performance Yes Actual Performance No
--------~~-------
Classroom Classroom
-------- Simulator - - - - - - - - Plant Plant X Read to the examinee:
II will explain the initial conditions, which steps to simulate or discuss, and provide initiating initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. The Unit 3 3RD RO has completed 0-OP-061.14, Waste Gas Disposal System Controlled Radioactive Gas Release, Section 7.1, Controlled Radioactive Gas Release through step 7.1.2.3
- 2. An active RWP is in in place
- 3. The Unit 3 RO RD has provided you the copy of 0-OP-061.14 0-OP-061 .14 section 7.1 and the Gas Decay Tank Release Permit (0-NCOP-004, Attachment 1) currently in use
- 4. The Auxiliary Building Ventilation System is in service with A & B Supply Fans and A Exhaust Fan running. The B Exhaust Fan is in standby.
Task Standards:
- 1. Performed gaseous waste release from a Gas Decay Tank in accordance with 0-OP-061.14 and the Radioactive Gas Release Permit
- 2. Release terminated at at:::; 6 psig Gas Decay Tank pressure
- 3. Waste Gas Disposal System realigned to normal
- 4. Required information recorded on the Gas Decay Tank Release Permit Required Materials:
1.
- 1. 0-NCOP-004, Attachment 1, 1, Gas Decay Tank Release Permit
- 2. 0-OP-061 0-OP-061.14,.14, Waste Gas Disposal System Controlled Radioactive Gas Release General
References:
- 1. 0-OP-061
- 1. .14, Waste Gas 0-OP-061.14, Gas Disposal System Controlled Controlled Radioactive Gas Release 2.
- 2. 0-NCDP-004, 0-NCOP-004, Preparation Preparation of of Gas Gas Release Permits Permits Initiating Initiating Cue:
Cue: You You havehave been been directed directed by by the Unit 33 RD the Unit to perform RO to the Auxiliary perform the Auxiliary Building Building actions actions for for aa Controlled Controlled Radioactive Gas Gas Release Release fromfrom the the C Gas Decay "C" Gas Decay Tank Tank beginning beginning with with step step 7.1.2.4. 7.1.2.4.
Appendix C Appendix C Page 22 of Page of 12 12 Form Form ES-C-1 ES-C-f Time Critical Time Task: No Critical Task: No Validation Time: Validation Time: minutes 20 minutes 20
I Appendix Appendix C C Page 33 of Page of 12 12 Form ES-C-I I Form ES-C-1 INSTRUCTIONS TO INSTRUCTIONS TO OPERA OPERATOR TOR READ TO READ TO OPERA OPERATOR:TOR: WHEN II TELL WHEN TELL YOU YOU TO TO BEGIN, BEGIN, YOU YOU ARE ARE TO TO PERFORM PERFORM THE ACTIONS AS THE ACTIONS AS DIRECTED DIRECTED IN IN THE THE INITIATING INITIATING CUES. II WILL CUES. WILL DESCRIBE DESCRIBE THETHE GENERAL GENERAL CONDITIONS CONDITIONS UNDER UNDER WHICH WHICH THIS THIS TASK TASK IS IS TO TO BE BE PERFORMED PERFORMED AND PROVIDE AND PROVIDE THETHE NECESSARY NECESSARY TOOLS TOOLS WITH WITH WHICH WHICH TO TO PERFORM PERFORM THIS THIS TASK. TASK. BEFORE BEFORE STARTING, STARTING, II WILL EXPLAIN WILL EXPLAIN THETHE INITIAL INITIAL CONDITIONS, CONDITIONS, WHICH WHICH STEPS STEPS TO SIMULATE OR TO SIMULATE OR DISCUSS, DISCUSS, AND AND PROVIDE PROVIDE INITIATING CUES. INITIATING CUES. WHEN WHEN YOU YOU COMPLETE COMPLETE THE THE TASK TASK SUCCESSFULLY, SUCCESSFULLY, THE THE OBJECTIVE OBJECTIVE FORFOR THIS THIS JOB JOB PERFORMANCE MEASURE PERFORMANCE MEASURE WILL WILL BE BE SATISFIED. SATISFIED. HAND JPM HAND JPM BRIEFING BRIEFING SHEET SHEET TO TO OPERATOR OPERATOR AT THIS THIS TIME! TIME! INITIAL CONDITIONS:
- 1. The
- 1. The Unit Unit 33 RO RO has has completed completed O-OP-061.14, O-OP-061.14, Waste GasGas Disposal Disposal System System Controlled Controlled Radioactive Radioactive Gas Release, Section 7.1, Controlled Radioactive Gas Release through step 7.1.2.3
- 2. An active RWP is in place
- 3. The Unit 3 RO has provided you the copy of O-OP-061.14 O-OP-061 .14 section 7.1 and the Gas Decay Tank Release Permit (O-NCOP-004, Attachment 1) 1) currently in use
- 4. The Auxiliary Building Ventilation System is in service with A & B Supply Fans and A Exhaust Fan running. The B Exhaust Fan is in standby.
INITIATING INITIA TlNG CUE: You have been directed by the Unit 3 RO to perform the Auxiliary Building actions for a Controlled Radioactive Gas Release from the "C" C Gas Decay Tank beginning with step 7.1.2.4. NOTE 1: Inform examinee to simulate performance of steps involving hands on manipulation of plant equipment during this JPM. NOTE 2: This JPM requires entry into the RCA. Ensure candidate observes all requirements for entering and exiting the RCA. Procedures for this JPM should be obtained before entering the RCA and disposed of after exiting the RCA. Do you have any questions? You may begin.
Appendix C Appendix C Page 44 of Page of 12 12 Form Form ES-C-1 ES-C-I Denote critical Denote critical steps steps withwith aa check check markmark (vf ( Start Start Time Time
- 1. Obtain
- 1. Obtain working working copycopy of of 0-OP-061.14, 0-OP-061.14, Waste Waste Gas Gas Disposal Disposal System System STEP STEP 11 SAT SAT Controlled Radioactive Gas Release, Section Controlled Radioactive Gas Release, Section 7.1, Controlled7.1, Controlled --
Radioactive Gas Radioactive Release completed Gas Release completed through step step 7.1.2.3 7.1.2.3 UNSAT
- - UNSAT
- 2. Obtain
- 2. Obtain Gas Gas Decay Decay Tank Release Release Permit Permit (O-NCOP-004, (0-NCOP-004, Attachment 1) 1) currently inin use use
- 3. Review Review precautions/limitations precautions/limitations & completed steps of 0-OP-061.14
- 1. Obtains working copy of 0-OP-061.14,
- 1. 0-OP..061.14, Section 7.1 completed thru step 7.1.2.3
- 2. Obtains Gas Decay Decay Tank Release Permit (O-NCOP-004, (0-NCOP-004, STANDARDS: Attachment 1) currently in use
- 3. Reviews 0-OP-061.14 section 4.0 for applicable precautions/
limitations.
- 4. Reviews 3(4)-OP-051.1 section 7.1 steps already completed Provide the following to the candidate:
- 1. Working copy of 0-OP-061.14, O-OP-061. 14, Waste Gas Disposal System CUE*
CUE: Controlled Radioactive Gas Release, Section 7.1, Controlled "~,, Radioactive Gas Release completed through step 7.1.2.3
- 2. Gas Decay Tank Release Permit (0-NCOP-004, (O-NCOP-004, Attachment 1) currently in use I
Perform channel check on Plant Vent SPING-4 Channel 10 (Effluent STEP 2 SAT System Flowrate Measuring Device) as follows: --
- a. Set selector thumbwheel to 10 at the Plant Vent SPING-4 (Aux --
UNSAT Bldg fan room)
- b. Check the Plant Vent SPING-4 green NORMAL light illuminated.
(procedure step 7.1.2.4) 1.
- 1. Locates Plant Vent SPING-4 in Aux Bldg fan room.
STANDARDS: 2. Sets Plant Vent SPING-4 selector thumbwheel to 10 10
- 3. Check the Plant Vent SPING-4 green NORMAL
- 3. NORMAL light illuminated.
illuminated. 1.1. When candidate correctly correctly locates and and describes how how toto set set Plant Plant Vent SPING-4 SPING-4 selector thumbwheel thumbwheel to to 10, 10, confirm confirm this operation. operation. CUE: CUE:
- 2. candidate correctly
- 2. When candidate correctly locates Plant Vent SPING-4SPING-4 green green NORMAL light, NORMAL light, tell tell candidate candidate that that the the light light is is ON.
ON.
I Appendix C I Page 5 of 12 I ES-C-I I Form ES-C-1 J STEP 3 : 0-OP-061 .14, Attachment 3, Part A valve alignment Complete 0-OP-061.14,
- - SAT
.,/
I. (procedure step 7.1.2.5)
- - UNSAT Verifies the following valve alignment as specified in 0-OP-061.14, 0-OP-061 .14, Attachment 3 Part A:
** PCV-1038A, Compressor Discharge Hdr to C GDT - CLOSED
** CV-4639C, Re-Use Header Valve - CLOSED
** PCV-1 038B, C GDT to Gas Analyzer - CLOSED PCV-1038B, -
** 46420, 4642C, N2 Supply to C GDT - LOCKED CLOSED
- 4643C, C GDT Drain to Drain Header - LOCKED CLOSED STANDARDS: ** 40-907, Instrument Air Supply to RCV-014 - LOCKED OPEN
** RCV-014, GDT to Plant Vent Valve - CLOSED
** 4638A, A GDT to Plant Vent - LOCKED CLOSED
** 4638B, B GDT to Plant Vent - LOCKED CLOSED
** 4638D, D GDT to Plant Vent - LOCKED CLOSED
/'~,
** 4638E, E GDT to Plant Vent - LOCKED CLOSED
** 4638F, F GDT to Plant Vent - LOCKED CLOSED
** 4638C, C GDT to Plant Vent - LOCKED OPEN When candidate correctly locates and describes how to place valve into the required condition, confirm valve position.
CUE: When candidate requests Independent Verification, acknowledge request and tell candidate that for the purpose of the JPM, Independent Verification can not be provided. Review the Radioactive Gas Release Permit to verify the C Gas STEP 4
. Decay Tank alignment performed matches the C Gas Decay Tank - - SAT specified on the Radioactive Gas Release Permit, AND document review on QA Record Page - - UNSAT (procedure step 7.1.2.6)
- 1. Determines C Gas Decay Tank specified on Gas Decay Tank 0-OP-Release Permit which is consistent with performance of O-OP-061.14 Attachment 3 STANDARDS:
0-OP-061 .14, Section 7.1 QA Record Page
- 2. Documents review on 0-OP-061.14, by writing in Gas Release Permit Number and circling the C Gas Decay Tank
/-,
Appendix C 12 Page 6 of 12 ES-C-I Form ES-C-1
- 1. Record
- 1. Record the following information information on the GasGas Decay Decay Tank Release Release STEP 5 SAT Permit (0-NCOP-004, Attachment 1) 1) in in use use --
./
Number of Aux Bldg
- a. Number Exhaust Fans Bldg Exhaust Fans operating UNSAT
- - UNSAT
- b. Wind speed & direction (obtain from Control Room)
- c. Meteorological ~T AT (obtain from Control Room)
- d. Plant vent flow estimate, if required.
- e. Initial Gas Decay Tank pressure
- 2. Record initial pressures for all remaining Gas Decay Tanks on 0-OP-061.14, Attachment 7 (procedure step 7.1.2.7)
- 1. Records following information in Part IV of 0-NCOP-004 .
Attachment 11 in use:
- a. From initial conditions, determines number of Aux Bldg Exhaust
=
Fans operating = 11
- b. Calls Control Room and determines wind speed & direction =
=
15mph 15 12000 mph from 120 STANDARDS: c. Calls Control Room and determines Meteorological ~ AT T =
= -0.5°F
- d. Plant vent flow estimate not required since Plant Vent SPING-4
-~. green NORMAL light observed at procedure step 7.1.2.4
- e. From Waste Boron Panel, determines Initial Gas Decay Tank
=
pressure = 94 psig
- 2. Record initial pressures for all remaining Gas Decay Tanks on 0-OP-061.14, Attachment 7 from actual readings on Waste Boron Panel.
- 1. Respond as Unit 3 RO when asked for wind speed, wind direction
& 60 meter met tower L1 zlT. 12000 & -0.5 or:
T. Provide values of 15 mph, 120 F respectively. CUE: 2. When candidate correctly locates Gas Decay Tank pressure gauges on Waste Boron Panel, point to 94 psig on the C Gas Decay Tank pressure indicator then allow candidate to use actual readings for the remaining tanks.
I Appendix Appendix CC Page 77 of Page of 12 12 I Form ES-C-1 Form ES-C-I II STEP Notify Unit Notify Unit 33 RO RO to initiate required to initiate required monitoring monitoring ofof gas gas release release by by at at STEP 66 least one least one of of the following: the following: - - SAT SAT
** R-14 on R-14 associated PRMS on associated PRMS drawer drawer - - UNSAT UNSAT
** RAD-6304 (Plant RAD-6304 (Plant Vent SPING-4)
SPING-4)
** Station dedicated Station dedicated operator operator at local Plant at local Plant Vent Vent SPING-4 SPING-4 display display panel with panel constant communications with constant communications to Unit 33 RO to Unit RO (procedure step (procedure step 7.1.2.8) 7.1.2.8)
Notifies Unit Unit 3 RO initiate required RO to initiate required monitoring monitoring of gas release release by by at STANDARD* STANDARD: one of the methods least one methods listed above. Respond as UnitUnit 3 RO RO when when notified to to initiate required required monitoring of CUES: CUES:' gas release through Plant Vent. Vent Reply that monitoring will be performed using the indication on the R-14 PRMS drawer.
Appendix C Page 8 of 12 ES-C-I Form ES-C-1 Initiates gas release as follows: STEP 7 SAT increase RCV-014
- a. Slowly increase loader setting to the maximum RCV-014 loader maximum allowed on Part IIII of the Gas Decay Tank Release Release Permit Permit UNSAT
- - UNSAT (100%)
- b. When release flow established, has Unit 3 RO verify that R-14 R-1 4 reading is less than that allowed on Part II of the Gas Decay Tank Release Permit (27k)
- c. Terminate release if R-14 reading exceeds that allowed on Part II of the Gas Decay Tank Release Permit (27k)
- d. Record initial set of Release Data on Part IV of the Gas Decay (Start column)
Tank Release Permit ("Start"
- e. Record all Gas Decay Tank pressures every 15 minutes on Attachment 7
- f. Record a set of Release Data every 15 minutes on Part IV of the Gas Decay Tank Release Permit ("Start" (Start column)
(procedure steps 7.1.2.9 & .10) STANDARDS: v
./ a. Slowly increases RCV-014 loader setting to 100%. Observes red valve open light illuminate.
~~~"
- b. When release flow established, has Unit 3 RO verify that R-14 reading is less than 27k cc.. Terminates release if R-14 reading exceeds 27k
./
- d. Records initial set of Release Data on Part IV of the Release Permit ("Start" (Start column). Calls Control Room and determines plant
=
vent flow = 74500 scfm.
- e. Records all GDT pressures every 15 minutes on Attachment 7
- f. Record a set of Release Data every 15 minutes on Part IV of the Release Permit (Start
("Start" column)
- 1. When candidate correctly describes how to increase RCV-014 loader setting to 100%, confirm operation, new loader setting and red valve position light illuminates.
- 2. Respond as Unit 3 RO when asked about R-14 reading. After flow established, report R-14 reading increased to 400 cps and stable.
- 3. Respond as Unit 3 RO when asked for wind speed, wind direction CUES*
CUES: & 60 meter met tower zlT. LI T. Provide values of 15mph, 120°& 15 mph, 120 0
-0.5 or=
& -0.5°F respectively.
- 4. When asked about C liC" GDT GOT pressure, point to 90-95 psig on Waste Boron Panel pressure indicator once release estblished (demonstrate a slow perceptible decrease). Other GDT GOT pressures
,,~,
are as indicated on the Waste Boron Panel.
- 5. Respond as Unit 3 RO when asked for plant vent flow. Provide value of 74500 scfm.
I
I Appendix C Page 9 of 12 ES-C-I Form ES-C-1 I As soon as initial data taking complete for Release Permit Start column filled out) & Attachment (Release Data "Start" Aftachment 7, tell CUE: CUE: candidate that the release has proceeded to the point where "C" C CDT GDT pressure reads as now indicated and point to 6-8 psig on the associated pressure indicator. When pressure of the Gas Decay Tank being released reaches 6-8 STEP 8 psig, then terminate the release as follows: - - SAT V
./
- a. Close RCV-014 by reducing the hand loader pressure to zero. - - UNSAT
- b. Verify valve stem position indicator on RCV-014 indicates fully closed.
- c. Record final set of readings on the Release Data table in Part IV of the Gas Decay Tank Release Permit
- d. Record final set of Gas Decay Tank pressures on Attachment 7 (procedure steps 7.1.2.11)
STANDARD: When "C"C GOT GDT pressure reaches 6-8 psig, terminates the release:
- a. Closes RCV-014 by reducing hand loader pressure to zero
- b. Determines RCV-014 valve stem indicator indicates fully closed
- c. Records final set of readings on the Release Data table "Stop" Stop
~~" column in Part IV of the Release Permit
- d. Records final set of GOTGDT pressures on Attachment 7
- 1. When candidate correctly describes how to increase RCV-014 loader setting to 0%, confirm operation and new loader setting.
- 2. Respond as Unit 3 RO when asked about R-14 reading. After flow established, report R-14 reading decreased back to 360 cps.
- 3. Respond as Unit 3 RO when asked for wind speed, wind direction
& 60 meter met tower ziT. 12000 & -0.5 L L1 T. Provide values of 15 mph, 120 'F CUES*
CUES: respectively.
- 4. When asked about "C" GDT pressure, point to 6-8 psig on Waste C GOT Boron Panel pressure indicator. Other GOT GDT pressures are as indicated on the Waste Boron Panel.
- 5. Respond as Unit 3 RO when asked for plant vent flow. Provide value of 74500 scfm.
Appendix C Page 10 of 12 Form ES-C-1 ES-C-I Complete 0-OP-061.14, Attachment 3, Part A valve alignment STEP 9 - - SAT (procedure step 7.1.2.12) UNSAT Verifies the following valve alignment as specified in 0-OP-061.14, Attachment 3 Part B: STANDARDS: ** RCV-01 4, GDT to Plant Vent Valve - CLOSED RCV-014, -
** 40-907, Instrument Air Supply to RCV-014 - LOCKED CLOSED
** 4638C, C GDT to Plant Vent - LOCKED OPEN When candidate identifies need to return to valve gallery to perform this step, state that another operator will complete the rest of the CUE CUE:
procedure. In the interest of minimizing exposure, do not re-enter the valve gallery. Terminating Terminating Tell candidate that JPM is complete. STOP Cue: Stop Time _ _ __
II Appendix Appendix C C Page 11 Page 11 of of 12 12 Form Form ES-C-1 ES-C-I Verification of Verification of Completion Completion Job Performance Job Performance Measure Measure No. No. Systems - j Systems
~~~~-L
________________ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ Examinees Name: Examinee's Name: Examiners Name: Examiner's Name: Performed: Date Performed: Date Facility Evaluator: Number of Attempts: Number Time to Complete: Question Documentation: Question:
Response
Result: Satisfactory/Unsatisfactory Examiners Examiner's signature and date: signature and date: _______________________________
JPM BRIEFING JPM BRIEFING SHEET SHEET INITIAL CONDITIONS: INITIAL CONDITIONS:
- 1. The
- 1. The Unit Unit 33RD RO has completed O-OP-061.14, has completed O-DP-061.14, Waste Waste Gas Disposal System Gas Disposal System Controlled Controlled Radioactive Radioactive Gas Release, Section Gas Release, Section 7.1, 7.1, Controlled Controlled Radioactive Radioactive Gas Release through step Gas Release step 7.1.2.3 7.1.2.3
- 2. An active RWPRWP isis in in place place
- 3. The
- 3. Unit 33 RO The Unit RD has provided you has provided the copy you the copy of O-OP-061 .14 section of O-OP-061.14 section 7.1 and the 7.1 and the Gas Gas Decay Decay Tank Tank Release Permit (O-NCOP-004, Release Permit (O-NCOP-004, Attachment 1) currently
- 1) currently in in use use
- 4. The Auxiliary Building Ventilation System is in service with A & B Supply Fans and A Exhaust Fan running. The B Exhaust Fan is in running. in standby.
INITIATING INITIA TlNG CUE: You have been directed by the Unit 3 RO RD to perform the Auxiliary Building actions for a Controlled Radioactive Gas Release from the "C" C Gas Decay Tank beginning with step 7.1.2.4. HAND THIS PAPER BACK TO YOUR EVALUATOR EVALUATOR WHEN YOU FEEL THAT SATISFACTORILY COMPLETED YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
'iR/)..1/)%IN.fl\JC N IN G USE L)S Procedure No.:
Procedure Procedure
Title:
Procedure Page: 25 25 Approval Date: Approval 0-NCOP-004 0-NCOP-004 Preparation Preparation of of Gas Gas Release Release Permits Permits 3/11102 3/11/02 ATTACHMENT ATTACHMENT 1 1 (Page 11 of 1) 1) GAS DECAY TANK RELEASE PERMIT I I FLORIDA POWER AND LIGHT COMPANY Gas Release No. GAS DECAY TANK II TURKEY POINT PLANT GRP- 0.7 O1-xX - xxx RADIOACTIVE GAS RELEASE PERMIT Date: (Ref: 0-OP-061.14) 0-OP-061 .14) k !I<~ r-')( f,cx fx~ Jy,c Gas Decay Tank: C.. C, I Approx. Act. to be Released 7.53 3E-4 7.538 £.-4 Ci PART I: Pre-release Data R-14 PV SPING Noble Gas Activity flCi/cc lICi/cc 5977 [;-0 5,971 I-JI/.. Background, cpm 345 flCi/cc lICi/cc i-J/
)/ A Expected response cpm 349 IIC i/cc flCi/cc ui;).
Administrative Limit 300,000 cpm iCi/cc 1.0 E-2 flCilcc Sample Date/Time fx/.c/ Xxh**~J*i.x. /Ioe)l;.)<lOt; )(X Count Date/Time y;:Jx'£Ixy: / )C:x: c: )(.,l( cx Count time shall be within 2 hours of sample time I Special Instructions Oper O(>e0 urdDoder
.xIder slol.cI\..I Lou.I .
PART II: Limits R-14 Alarm Setpoint = 3b Içcpm (N/A ifR-14 Kcpm if R-14 is OOS) RCV-014 Tank Release Rate Limit: RCV -014 Loader Setting =iCO 100 % Terminate Release if Maximum Expected Monitor Reading, 21;;" 27 L , is exceeded PART III: Authorizations and Approvals Permit Prepared by ~ Technician Analysis Approved by ~
,i..- Radiochemistry Supervisor Release Approved by v------ Nuclear Plant Supervisor PART: IV: Release Data Fans: Aux. Bldg I SS II I iI Cont. Purge II SS I Release Performed by:
I E I Ei II E II E 1 Start Every 15 minutes Stop Time Date Wind Speed, MPH Wind Direction, Degrees Delta T or Sigma Theta RCV-0l4 RCV-014 Loader Setting % CPM or llCi/cc Monitor Reading, CPM flCi/cc Decay Tank Pressure Gas Decay Ever Ever. 15 15 minutes Plant Vent Flow SCFM REMARKS: WC:PS/bc/ev/mrg WC:PS/bc/ev/mra
Florida Power & & Light Company Turkey Point Nuclear Plant H ,>I O-OP-061.14 S. - t) ) c) .-
Title:
Waste Gas Disposal System Controlled Radioactive Gas Release Quality Related Procedure Responsible Department: Operations Revision Approval Date: 2/6/02 2/6/02 RTSs 94-1333P, 94-1333P, 96-0978, 97-0839, 97-0839, 01-0509, 02-0108P 02-0108P OTSCs OTSCs 0463-96, 0463-96, 0508-96, 0508-96, 05 10-96, 0208-01 0510-96, 0208-01 W97:JEC/Ir/ev/ma W97:JEC/lr/ev/ma
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 22 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-06 1.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 2/6/02 2/6/02 LIST OF EFFECTIVE PAGES Revision Revision Revision Revision Page Date Date Page Date Date 11 02/06/02 02106/02 21 09/25/01 09/25/01 2 02/06/02 22 05/28/01 05/28/0 1 3 05/28/01 05/28/01 23 09/25/01 09/25/01 4 05/28/0 1 05/28/01 24 05/28/01 05/28/0 1 5 05/28/01 25 09/25/01 6 05/28/01 26 05/28/01 7 05/28/01 27 09/25/01 88 05/28/01 28 OS/28101 05/28/01 9 05/28/0 1 OS/28/01 29 09/25/01 09/25/0 1 10 05/28/01 30 05/28101 05/28/01 11 05/28/01 OS/28101 31 09/25/01 12 05/28/01 32 05/28/01 13 05/28/01 33 05/28/01 14 05/28/01 15 05/28/01 16 05/28/01 OS/28101 17 05/28/01 18 02/06/02 02106102 19 05/28/01 20 05/28/01 W97:JEC/Ir/ev/ma W97:JEC/lr/ev/ma
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 33 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 TABLE OF CONTENTS Section Section 1.0 1.0 PURPOSE ..................................................................................................................... PURPOSE 55
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT DOCUMENTS ........ REFERENCESIRECORDS 5 3.0 PREREOUISITES ....................................................................................................... PREREQUISITES 88 4.0 PRECAUTIONS/LIMITATIONS .............................................................................. 9 5.0 STARTUP/NORMAL OPERATION 5.1 Waste Gas System Startup ................................................................................. 10 6.0 SHUTDOWN 6.1 Shutdown Waste Gas System Shutdown............................................................................. 11 7.0 INFREQUENT OPERATIONS 7.1 Controlled Radioactive Gas Release .................................................................. 12 Wo7.IIr./lr/iv/ma W97:JEC/lr/ev/ma
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 44 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-06L14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 TABLE OF CONTENTS Section ENCLOSURE/ATTACHMENTS ENCLOSURE/ATTACHMENTS Enclosure 11 Plant Vent Fan Configuration Table .................................................................. 19 19 Attachment 11 A Gas Decay Tank Release Valve Alignment ....... .... ......... .... ........ ...... ...... ...... 20 Attachment 2 B Gas Decay Tank Release Valve Alignment ..... ..... .... .......... .... .... .... ...... ........ 22 Attachment 3 C Gas Decay Tank Release Valve Alignment ...... ............. ....... ........... ...... ....... 24 Attachment 4 B Gas Decay Tank Release Valve Alignment ..... ...... .... ......... .... .... ............ ...... D 26 Attachment 55 E Gas Decay Tank Release Valve Alignment ... ........... .............. .... .... ........ ...... 28 Attachment 66 F Gas Decay Tank Release Valve Alignment Alignment................................................... 30 Attachment 7 Gas Decay Tank Pressures (During Release) ...... .......... .... .......... .... .... ........ ....... 32 W97:.lECIlr/ev/m W97:JEC/lr/ev/ma
Procedure No.: Procedure No: Procedure
Title:
Procedure
Title:
Page: Page: 55 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 provides the prerequisites, This procedure provides prerequisites, precautions andand instructional guidance for Controlled Radioactive Gas releases. 2.0
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCES/RECORDS REQUIRED/COMMITMENT DOCUMENTS DOCUMENTS 2.1 References 2.1.1 Technical Specifications 1.
- 1. Table 3.3-8, Radioactive Gaseous Effluent Monitoring Instrumentation
- 2. Table 4.3-6, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 2.1.2 FSAR
- 1. Section 11.1.2, Waste Disposal Component Code Requirements
- 2. Section 11.1-3, Secondary Shield Design Parameters
- 3. Figure 11.1-2, Waste Disposal System Gas - Operating Diagram 2.1.3 Operating Procedures
- 1. 0-OP-060, Auxiliary Building HV HVACAC
- 2. 3-ONOP-067, Radioactive Effluent Release 3-0NOP-067,
- 3. 4-ONOP-067, 4-0NOP-067, Radioactive Effluent Release
- 4. 0-NCCP-210, SPING and DAM Monitor Channel Checks
- 5. 0-NCOP-004, Preparation of Gas Release Permits
- 6. OP-5503.1, OP-5503.l, WDS - Gaseous Disposal System Operation 2.1.4 Operating Diagrams 1.
- 1. 5610-M-3061, 5610-M-3061, Sh Sh 1, 1, Waste Disposal System System - Gas Waste Decay Tanks
- 2. 5610-M-8, 561O-M-8, Sh Sh 1, 1, Auxiliary Building Ventilation System 1Mr7. IIfil.I,-,, .1.-....
W97:JEC/lr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 66 Waste Gas Waste Disposal System Gas Disposal System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive GasGas Release Release 5/28/01 5/28/01 2.1.5 2.1.5 Miscellaneous Documents Miscellaneous Documents (i.e., PC/M, Correspondence) (i.e., PCIM, Correspondence) 1.
- 1. Regulatory Guide Regulatory Guide 1.33, 1.33, Quality Assurance Quality Assurance Program Program Requirements Requirements (Operations)
(Operations) 2.
- 2. American National American National Standards Standards Institute Institute N18.7-1976, N18.7-1976, Administrative Administrative Controls Controls and Quality and Quality Assurance Assurance for for the the Operational Operational Phase Phase of of Nuclear Nuclear Power Power Plants Plants 3.
- 3. Offsite Dose Offsite Dose Calculation Calculation Manual Manual 2.2 Records Required 2.2.1 2.2.1 The date, date, time and section completed shall be logged logged in the Reactor Control Operator (RCO) Logbook. Also, any problems encountered while performing the procedure should be logged (i.e., equipment malfunctions, malfunctions, delays due to changes in plant conditions, etc.)
2.2.2 Completed copies of the QA RecordPage(s) Record Page(s) for the below listed item(s) constitute Quality Assurance records and shall be transmitted to QA Records for retention in accordance with Quality Assurance Records Program requirements:requirements:
- 1. Subsection 7.1
- 2. Attachment 11
- 3. Attachment 2
- 4. Attachment 33
- 5. Attachment 4
- 6. Attachment 55
- 7. Attachment 6 A!O7 Ipr/Ir1,/n W97:JEC/lr/ev/ma
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 77 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive GasGas Release Release 5/28/01 5/28/01 2.2.3 2.2.3 Completed copies Completed copies ofthe of the below below listed listed item(s) item(s) shall shall be be retained retained in in the the Nuclear Nuclear Plant Plant Supervisors file Supervisor's file until the next next performance performance of of that section, section, enclosure, enclosure, oror attachment: attachment: 1.
- 1. Subsection 7.1 Subsection 7.1 2.
- 2. Attachment 11 Attachment 3.
- 3. Attachment 2 Attachment
- 4. Attachment 3 5.
- 5. Attachment 4
- 6. Attachment 5
- 7. Attachment 6 2.3 Commitment Documents Commitment 2.3.1 PTN-PMN-88-03 0,
Subject:
Memorandum PTN-PMN-88-030,
- 1. FSAR not updated to address Gas Releases with PRMS-R-14 inoperable, and
- 2. Procedural inadequacies for Gas Releases, CAR-87-082,CAR-87-082, dated January 20, 1988 (CTRAC Number 88-0094-34) 2.3.2 PTN-PMN-88-181,
Subject:
Memorandum PTN-PMN-88-181, Follow-up corrective actions, CAR-87-082, dated March 30, 1988 CAR-87-082, AIQ7 IrIrI,1n,, W97:JEC/lr/ev/ma
ProcedureNo.: Procedure No.:
Title:
ProcedureTitle: Procedure Page: Page: 88 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive GasGas Release Release 5/28/01 5/28/01 3.0 3.0 PREREOUISITES PREREQUISITES 3.1 3.1 Prior to Prior to performing performing aa gas gas release release ofof aa Gas Gas Decay Decay Tank, Tank, the the tank tank shall shall bebe sampled, sampled, analyzed, aa Gas analyzed, Release Permit Gas Release Permit issued issued and and thethe release release approved approved byby the the Nuclear Nuclear Plant Plant Supervisor. Supervisor. 3.2 3.2 If Plant Vent If Plant Vent Monitor Monitor R-14 R-14 isis Out-of-Service, Out-of-Service, thenthen I&C I&C Maintenance Maintenance will will bebe required required toto install and install and remove remove jumpers as directed by as directed this procedure. by this procedure. 3.3 3.3 Plant Vent Vent Gas Monitor, Channel R-14 R-14 shall shall be inin service. service. OR 3.4 If the Plant Vent Gas Monitor, Channel R-14 is out of service, then verify Chemistry Department personnel are performing the required actions of 0-NCCP-210, SPING SP1NG and DAM Monitor Channel Check. [Commitment - Step 2.3.1] 2.3.11 3.5 Plant Vent SPING-4 shall be in service. OR 3.6 If the Plant Vent SPING-4 is out of service, then verify Chemistry Department personnel are performing the required actions of 0-NCCP-210, 0-NCCP-2 10, SPING and DAM Monitor Channel Check. [Commitment - Step 2.3.1] - 3.7 Plant Vent SPING-4, SPTNG-4, Channel 10 should be in service. 3.8 If the Plant Vent SPING-4, SPfNG-4, Channel 10 is out of service, then the Plant Vent flowrate will need to be estimated using Enclosure 11 (Tech Spec Table 3.3-8). 3.9 A minimum of one Auxiliary Building Ventilation Exhaust Fan is in service. 3.10 The following systems are operable or in operation to support the Gas Decay Tank release: 3.10.1 3.10.1 Instrument Air System 3.10.2 3.10.2 120V 120V DC DC Electrical System 3.10.3 3.10.3 480V 480V AC AC Electrical Electrical System 3.11 The Operations 3.11 The Operations Manager has has been been notified if the notified if the Plant Plant Vent Vent Monitor Monitor R-R-14 AND the 14 AND the Plant Plant Vent SPING-4 monitor Vent SPING-4 monitor are are both both out out of of service. service. W97:JEC/lr/ev/ma W97:JECllr/ev/ma
ProcedureNo.: Procedure No. ProcedureTitle: Procedure
Title:
Page: Page: 99 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 4.0 4.0 PRECAUTIONS/LIMITATIONS PRECAUTIONS/LIMITATIONS 4.1 4.1 The maximum allowable The maximum allowable RCV-014 RCV-014 loader loader setting setting andand the the maximum maximum expected expected value value for for the the Plant Vent Plant Vent GasGas Monitor, Monitor, Channel Channel R-14 R-14 should should be be monitored monitored closely closely toto prevent prevent exceeding exceeding the release limits. the release limits. 4.2 4.2 The Plant The Plant Vent Vent Gas Monitor, Channel Gas Monitor, Channel R-14R-14 or or alternate alternate monitor monitor (may (may require require aa dedicated dedicated operator if operator utilizing local if utilizing local instrumentation), instrumentation), should should be be monitored monitored at at least least once once per per 55 minutes minutes during the during the gas gas release release to to assure assure the the count count rate rate isis not not approaching approaching thethe alarm alarm setpoint. setpoint. 4.3 4.3 If the If observed count the observed count rate rate exceeds exceeds the the maximum maximum expectedexpected reading reading listed listed inin Part Part II II of of the the Release Permit, Release Permit, then then terminate terminate thethe release release and contact the and contact the Chemistry Chemistry Department Department for for corrective actions. 44 4.4 If the high setpoint on on R-14 actuates, then physically verify RCV-014 is closed, close the Decay Tank to the Plant Vent Manual Valve, 40-907, verify the count rate is Gas Decay decreasing on R-14, and perform the required actions of 3-0NOP-067, 3-ONOP-067, Radioactive Effluent Release. 4.5 If the high setpoint on R-14 actuates, verify the Gas Decay Tank that was being released is Ifthe isolated from the rest of the Waste Gas System, and do not re-initiate the gas release until authorized by the Nuclear Plant Supervisor. 4.6 If the high setpoint on R-14 actuates, then loading pressure on PCV-014 must be reduced to zero in order to reset RCV RCV-014.
-014.
4.7 If the Auxiliary Building Veritilation Ventilation System fan configuration requires alteration or is altered, then terminate the release and contact the Chemistry Department to recalculate the R-14 R -14 high setpoint and expected count rates for the new flowrates as required. 4.8 When the RCO has completed the initial portion of this procedure (steps marked RCO), then the remaining actions required to initiate the release should progress without delays to maintain continuity in the operation and initiating data. 4.9 During a Gas Decay Tank release, the non affected Gas Decay Tanks shall be monitored for an unexplained decrease in pressure. If the pressure in a tank other than the Gas Decay Tank being released is observed decreasing for an unknown reason, then the release shall be terminated terminated until the cause of the decreasing pressure is ofthe is identified and corrected. 4.10 Plant Vent SP1NG-4, SPING-4, Channel Channel 55 shallshall not be used to to satisfy the minimum channel operability requirements or in lieu lieu of the sampling sampling requirements of of Technical Technical Specification Specifications, s, Table 3.3-8. 3.3-8. Wq7. IFfl/fr/p.v/m W97:JEC/lr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 10 10 Waste Gas Waste Disposal System Gas Disposal System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Release Gas Release 5/28/01 5/28/01 5.0 5.0 STARTUP/NORMAL OPERATION STARTUPINORMAL OPERATION 5.1 5.1 Waste Gas Waste Gas System System Startup Startup r r---------~NOrE----------1 i__I II II I This section This section of perform an of the an infrequent procedure left the procedure infrequent evolution evolution of left blank blank intentionally. intentionally. The function of The function of this this procedure procedure is is to to I perform of aa waste waste gas gas release. release. II II W97:JEC/Ir/ ev/ma W97:JEC/lr/ev/ma
Procedure No.: Procedure No.:
Title:
Procedure
Title:
Procedure Page: Page: 11 11 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 6.0 6.0 SHUTDOWN SHUTDOWN 6.1 Waste Gas System Shutdown System Shutdown r----------NOrE----------. II I I This section This section of of the the procedure left left blank blank intentionally. an infrequent evolution of a waste intentionally. The waste gas release. The function function of this this procedure is toto I perform an release. II I W97:JEC/lr/ev/ma W97:JEClir/ev/ma
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 12 12 Waste Gas Waste Gas Disposal System Disposal System Approval Approval Date: Date: 0-OP-061 .14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 7.0 7.0 INFREQUENT OPERATIONS INFREQUENT OPERATIONS 7.1 7.1 Controlled Radioactive Controlled Radioactive Gas Gas Release Release INITIALS INITIALS CKD VERIF CK'D VERIF Date/Time Started: Date/Time Started: _ _ _ _ _ _ ?X x-,-,x,-,-// ~x,-,' K..::;... ::.::X-",-_ _
)c.)(
77.1.1
.1.1 Initial Conditions
- 1. All applicable prerequisites as listed in Section 3.0 are satisfied.
- 2. Record the number of of the approved Gas Gas Release Permit AND the Gas Decay Tank (GDT) on the QA Record Page.
- 3. Release of the Gas Decay Tank has been approved by the on-shift Nuclear Plant Supervisor.
7.1.2 Procedure Steps
- 1. Reset the Process Radiation Monitor R-14 R- 14 High Alarm setpoint AND Warning Limit by performing the following (Mark N/A if R-14 is inoperable):
~ RCO
- a. Slide R-14 drawer forward to gain access to the thumbwheel RCO switches.
I NOTES -. I ** The thumbwheel switch settings are used to select the setpoint as follows: I
* =digit I 1. Forward switch setting =
I
- 2. Middle switch setting = = decimal and digit
- I 3. Rear switch setting == exponent I
I I
- For example: a setting of 4.03 is equal to 4.0 X 103 or 4 Kcpm; a setting of 1.05 is equaltol.OXl o
5 equalrlOOKcpm. 5 to 1.0 X 10 or 100 Kcpm. O
- b. Position the High Alarm setpoint thumbwheel switches to the R-R-1414 High Alarm specified on the Gas Release permit.
- c. Position the Warning Limit thumbwheel switches to the R-14 maximum expected monitor reading specified on on the Gas Release Permit.
Permit. ISA. d. Close the R-14 drawer. RCO W97:JEC/Ir/ev/ma W97:JEC/lr/ev/ma
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 13 Gas Disposal System Waste Gas System Date: Approval Date: Approval 0-OP-061.14 Controlled Radioactive Gas Release 5/28/01 5/28/01 INITIALS INITIALS CKD VERIF CK'D VERIF 7.1.2.1 (Cont'd) 7.l.2.1 (Contd) ~1L
?c( y_ e. Depress the HIGH ALARM pushbutton AND verify the RCO RCO digital display CPM indication equals the High Alarm setpoint on the Gas Release Permit.
~ f. Release the HIGH ALARM pushbutton. RCO
;<x. .x --'iLy_ g. Depress the WARNING LIMIT pushbutton AND verify the RCO RCO digital display CPM indication equals the maximum expected monitor reading on the Gas Release Permit.
~ h. Release the WARNING LIMIT pushbutton. RCO .EL i.
- 1. Depress the SOURCE CHECK pushbutton AND verify the RCO digital display CPM indication responds to the source.
CAUTIONS
- Plant Vent SPING-4, Channel 5 shall not be used to satisfy the minimum channel operability requirements of Technical Specifications, Table 3.3-8.
- Plant Vent SPING-4, Channel 5 readings shall not be used in lieu of the required sampling specified in Technical Specifications, Table 3.3-8.
1,.:L 2. IF Plant Vent Monitor R-14 is not operable, THEN verify that RCO Chemistry personnel have completed the required sampling requirements AND verification of release calculations as specified in Technical Specifications, Table 3.3-8 for the Plant Vent Monitor Channel R-14, Out-of-Service.
- 3. IF Plant Vent Monitor Channel R- 14 is out of service, THEN direct I&C R-14 Maintenance to install the following jumpers on RT-14 in QR-66:
1J/A a. On TB600 from Terminal Terminall1 to Relay K850 Cl I&c I&c fii b. On TB600 from Terminal 2 to Relay K850 C2 I&c I&c -tdIL JJlt!L c. WHEN the jumpers are installed, THEN place a RCO RCO RCO RCO CAUTION tag on the front of the drawer to alert the operator(s) that a jumper is installed. Wq7.IFr./IrIcv/ma W97:JEClir/ev/ma
Procedure No.: Procedure Procedure
Title:
Procedure Page: 14 Waste Gas Disposal System Approval Date: 0-OP-061.14 Controlled Radioactive Gas Release 5/28/01 INITIALS CKD VERIF CK'D (Contd) 7.1.2 (Cont'd)
- 4. Perform a channel check on Plant Vent SPING-4 SPLNG-4 Channel 10 (Effluent System Flowrate Measuring Device) as follows:
- a. Set the selector thumbwheel to 10 at the Plant Vent SNPO SPING-4 (located in the Auxiliary Building Fan Room).
- b. Check the green NORMAL light to be illuminated.
SNPO
5. Complete Part A of the appropriate attachment for the Gas SNPO SNPO Decay Tank to be aligned for release.
6. Review the Radioactive Gas Release Permit to verify the tank SNPO SNPO alignment performed matches the tank specified on the Radioactive Gas Release Permit, AND document this review on the QA Record Page.
CAUTION The Independent Verification requirements of Substep 7.1.2.5 and 7.1.2.6 above are required to be completed prior to continuing with this procedure.
- 7. Record the following information on the Radioactive Gas Release Permit (Attachment 11 of 0-NCOP-004, Preparation of Gas Release Permits):
- a. Number of Auxiliary Building Exhaust Fans operating SNPO
- b. Control Room)
Wind speed and direction (obtain from the C()ntrol SNPO
- c. Meteorological Delta (A.)
(,:1) T (obtain from the Control Room) SNPO
- d. IF the green NORMAL light on the Plant Vent SPING-4 SNPO did not illuminate in Substep 7.l.2.4.b, 7.1.2.4.b, THEN calculate the estimated flow using Enclosure 11 as required by Technical Specifications Table 3.3-8.
- e. Initial Gas Decay Tank pressure.
SNPO
- f. Initial Gas Decay Tank Pressures for all remaining Gas SNPO Decay Tanks Attachment 7 (Prior to Release).
W97:JEC/lr/evlma W97:JECllr/ev/ma
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 15 15 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: O-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 INITIALS INITIALS CKD VERIF CK'D VERIF 7.1.2 (Cont'd) 7.1.2 (Contd)
- 8. Notify the RCO to initiate the required to initiate required monitoring of the gas SNPO SNPO release by at least one of the following methods (method(s) used release used will depend on instrumentation on instrumentation availability availability and and manpower):
manpower):
- a. PRMS R-14 Monitor Drawer
- b. ERDADS indication for RAD-6304 on the RAD Screen
- c. Dedicated operator at the local SPING-4 SPTNG-4 display panel with constant communications with the Unit 3 RCO
- 9. Initiate the gas release as follows:
- a. Slowly increase the RCV-014 loader setting to the SNPO maximum allowed setting as delineated in Part II of the Radioactive Gas Release Permit.
- b. WHEN the release flowrate has been established, THEN SNPO method(s) established by the RCO verify that the indicated reading (by methodes) in Substep 7.1.2.8) does not exceed the maximum expected value delineated in Part II of the Radioactive Gas Release Permit.
- c. IF E the indicated reading exceeds the maximum expected SNPO value stated on the Radioactive Gas Release Permit, THEN terminate the release.
- d. Record the initial set of readings on the Data Table in SNPO Part IV of the Radioactive Gas Release Permit.
- e. Record all Gas Decay Tank Pressures every 15 minutes SNPO while release is in progress.(Attachment 7)
- 10. Record a complete set of readings every 15 minutes SNPO on the Data Table in Part IV of the Radioactive Gas Release Permit.
On
- 11. WHEN the pressure of the Gas Decay Tank being released reaches 6 psig to 88 psig, THEN terminate the release as follows:
- a. Close RCV-014 RCV -014 by reducing the hand loader pressure to SNPO SNPO zero.
- b. Verify the valve stem position indicator on RCV-014 RCV -014 SNPO SNPO indicates the valve indicates the valve isis fully closed.
c.c. Record final set Record set of of readings onon the the Data Data Table Table in in Part Part IV IV SNPO SNPO of the Radioactive of the Radioactive GasGas Release Permit. Permit.
- d. Record final setset of of Gas Decay Tank Pressures Pressures SNPO SNPO (Attachment (Attachment 7).7).
AIfl7. W97:JECllr/ev/ma
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 16 16 Waste Gas Waste Disposal System Gas Disposal System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 INITIALS INITIALS CKD VERIF CK'D VERIF (Contd) 7.1.2 (Cont'd) 7.1.2
- 12. Restore the
- 12. Restore the Gas Decay Tank Gas Decay Tank alignment alignment using using Part Part B B of of the the SNPO SNPO SNPO SNPO attachment completed attachment completed in in Substep 7.1.2.5 above.
Substep 7.1.2.5 above.
- 13. Return
- 13. Return the completed Radioactive the completed Radioactive Release Release Permit Permit to the Chemistry to the Chemistry SNPO SNPO Department upon completion of the release.
- 14. IF R-14 is in
- 14. in service, THEN reset the Process Radiation Monitor R-14 High Alarm setpoint AND Warning Limit by performing the following (Mark N/A if R-14 is inoperable):
ifR-14 inoperable):
- a. Slide R-14 drawer forward to gain access to the RCO thumbwheel switches.
r--'- - -NOTES -----'------,- -, II II I
- The thumbwheel switch settings are used to select the setpoint as follows:
I I 1. Forward switch setting = = digit II I 2. Middle switch setting =decimal and digit
=
I I Rear switch setting =exponent I 3. = II II ** For example: a setting of 4.03 is equal to 4.0 X 3 3 or 4 Kcpm; a setting of 1.05 is X 10 1O I I equaltol.OXl o 5 rlOOKcpm. equal 5 to 1.0 X 10 or 100 Kcpm. O II L- _
- b. Position the High Alarm setpoint thumbwheel switches RCO RCO to the R-14 High Alarm specified on the R-14 drawer.
- c. Position the Warning Limit thumbwheel switches to the RCO RCO R-14 Warning Limit specified on the R-14 drawer.
- d. Close the R-14 drawer.
RCO
- e. Depress the HIGH ALARM pushbutton AND verify the RCO digital display CPM indication equals the High Alarm setpoint on the R-14 drawer.
- f. Release the HIGH ALARM pushbutton.
RCO g.
- g. Depress the WARNING W ARNIN G LIMIT pushbutton AND verify RCO RCO the digital display display CPM CPM indication equals the Warning Limit Limit on the drawer.
W97:JEC/Ir/ev/ma W97:JEC/lr/ev/ma
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 17 17 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Release Gas Release 5/28/01 5/28/01 INITIALS INITIALS CKD VERIF CK'D VERIF 7.1.2.14 (Cont'd) 7.1.2.14 (Contd)
- h. Release the WARNING LIMIT pushbutton.
RCO RCO i.
- 1. the SOURCE CHECK pushbutton AND Depress the AND verify RCO the digital display CPM indication responds to the Source.
- 15. IF Plant Vent Monitor Channel R-14
- 15. R- 14 is out of service AND no more gas releases are to be performed, THEN direct I&C Maintenance to remove the following jumpers on RT-14 in QR-66.
- a. TB600 from Terminal 1ito Cl.
to Relay K850 C1. I&c I&C I&c I&C
- b. TB600 from Terminal 2 to Relay K850 C2.
I&c I&C I&c I&C
- c. WHEN the jumpers are removed, THEN remove the RCO RCO CAUTION tag from the front of the drawer.
- 16. Verify all log entries specified in Subsection 2.2 have been RCO recorded.
- 17. Verify the QA Record Page has been completed for this section.
RCO iIo7. IPflhI/,/r, W97:JECllr/ev/ma
No.: Procedure No.: Procedure Procedure
Title:
Procedure
Title:
I Page: Page: I 18 18 Waste Gas Waste Disposal System Gas Disposal System I Approval Approval Date: Date: O-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive GasGas Release Release 2/6/02 2/6/02 II QA RECORD QA RECORD PAGE PAGE II (Page 11 of (Page of 1) 1) Procedure Revision Procedure Date Revision Date / //
------~------~-------
7.1 Controlled Radioactive Gas Release 7.1.1.2 Gas Release Permit Number: GRP- Gc.p 0-701-- )('iClC' Gas Decay Tank A B @ () D E F (Circle (Circle one) 7.1.2.6 Gas Release Permit Number: _ _-,---_----,-.,-_ __ Gas Decay Tank ABC A B C D E F (Circle one) REMARKS: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ REMARKS:__________________________________________________ Date/Time Started_ _ _ _,/_ _ __ /__________ Date/Time Completed: _ _ _ _ _/_ _ _ __ /_____________ PERFORMED BY (Print) INITIALS INDEPENDENT VERIFY (Print) INITIALS II have reviewed reviewed this procedure and it has been satisfactorily satisfactorily performed. performed. Any deviation(s) or OTSC(s) utilized in the performance of of this procedure has (have) been been listed in thethe Remarks Section. Section. REVIEWED BY: BY: _ _ _ _ _ _ _ _--=-:::-::_--=-_ _ _ _ _ __ RCO or RCO or Designee / END END OF OF TEXT TEXT W97:JEC/Ir/ev/ma W97:JEClir/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 19 19 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.l4 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 ENCLOSURE 1 ENCLOSUREl (Page 11 of (page 1) of 1) PLANT VENT PLANT VENT FAN FAN CONFIGURATION CONFIGURATION TABLE* TABLE* FAN FAN NUMBER OF NUMBER OF OPERATING OPERATING FANSFANS Containment Purge Containment Purge Exhaust 00 00 00 11 11 22 22 Exhaust Auxiliary Building Exhaust Auxiliary Exhaust 00 11 2 11 2 11 22 Spent Fuel Spent Fuel Pit Exhaust Pit Exhaust 11 11 11 11 11 11 11 Radwaste Building Exhaust 2 2 2 2 2 2 2 Laundry System Exhaust 11 11 11 11 11 11 11 Plant Vent Flow X 7 cc/sec 7 lO 1.45 3.82 4.31 4.74 5.07 5.66 5.99 10 cc/sec
- if SPIIIG-4 CH 10 is OOS to satisfy TS 3.3.3.6, Table 3.3-8 Table to be used ifSPING-4 W97.IPC/lr/p .v/ma W97:JEC/lr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 20 20 Waste Gas Waste Gas Disposal Disposal System System Approval ApprovalDate: Date: 0-OP-06L14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 ATTACHMENT 11 ATTACHMENT (Page 11 of2) (Page of 2) AA GAS GAS DECAY DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT III QARECORD QA RECORD PAGE PAGE Ii (Page 11 of (Page of 1) 1) Procedure Revision Procedure Revision Date Date _ _ _",:,//_ _ _~/,- / _ __ Check (J) Tag column Check (..,f) column iftag if tag is is missing, mislabeled, mislabeled, illegible illegible or or improperly improperly secured. secured. RENU\RKS: REMARKS: __________________________________________________________ Date/Time Started_ _ _ _./_ _ __ /_________ Date/Time Completed: _ _ _ _ _,/_ _ _ __ /____________ PERFORME PERFORMED D BY (Print) INITIALS iNITIALS INDEPENDE INDEPENDENT NT VERIFY VERIFY (Print) (Print) INITIALS iNITIALS II have have reviewed reviewed thisthis procedure procedure and and itit has has been been satisfactorily satisfactorily performed. performed. Any Any deviation(s) deviation(s) or or OTSC(s) OTSC(s) utilized utilized in the performance in the performance of this procedure ofthis procedure has has (have) (have) been been listed listed in in the the Remarks Remarks Section. Section. REVIEWED REVIEWED BY: BY: _ _ _ _ _--:,.-----=-::-_ _ _ _ _---==---=-_ _ _ ___ Nuclear Nuclear Plant Plant Supervisor Supervisor or or SRO SRO Designee Designee W97:JECllr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
I Page: Page: 2121 Waste Gas Waste Disposal System Gas Disposal System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive GasGas Release Release 9/25/01 9/25/01 ATTACHMENT ATTACHMENT 11 (Page 22 of2) (Page of 2) A GAS A GAS DECAY DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT PART A PART A Checked Checked Ind Ver IndVer Component Component Required Required Component Component Description Description Tag Tag && VlvPos Vlv Pos Tag Tag && VlvPos Vlv Pos No. No. Position Position (-Y) (1) Init mit (-Y) (q) Init mit Compressor Discharge Compressor Discharge PCV-1036A PCV-1036A CLOSED CLOSED Hdr to HdrtoA GDTA GDT CV-4639A CV-4639A Re-use Header Valve CLOSED CLOSED PCV-1036B PCV-I036B AA GDTGDT to Gas Analyzer to Gas Analyzer CLOSED CLOSED LOCKED 4642A 2z Supply to A GDT N N CLOSED LOCKED 4643A A GDT Drain to Drain Header CLOSED listrument Air Supply to Instrument LOCKED 40-907 RCV-014 OPEN RCV-014 GDT to Plant Vent Valve CLOSED LOCKED 4638B B GDT to Plant Vent CLOSED LOCKED 4638C C GDT to Plant Vent CLOSED LOCKED 4638D 4638D D GDT to P to Plant Vent CLOSED CLOSED LOCKED LOCKED 4638E 4638E E GDTGDT to to Plant Plant Vent Vent CLOSED CLOSED LOCKED LOCKED 4638F 4638F FF GDT GDT to to Plant Plant Vent Vent CLOSED CLOSED LOCKED LOCKED 4638A 4638A AA GDTGDT to to Plant Plant Vent Vent OPEN OPEN PARTB PART B Checked Checked Ind Ver md Ver Component Component Required Required Tag & VlvPos Component Description Component Description Tag & Tag Vlv Pos
& VIv Pos Tag & Vlv Pos No.
No. Position Position (J) (-Y) Init mit (-Y) (J) Init mit RCV-014 RCV-014 GDT to GDT to Plant Plant Vent Vent Valve Valve CLOSED CLOSED 40-907 Instrument LOCKED LOCKED 40-907 InstrumentAir Air Supply Supplytoto RCV-014 RCV-014 CLOSED CLOSED 4638A AA GDT LOCKED LOCKED 4638A GDTto to Plant PlantVent Vent CLOSED CLOSED W97:JEC/Ir/ ev/ma W97:JECllr/ev/ma
ProcedureNo.: Procedure No. ProcedureTitle: Procedure
Title:
Page: Page: 22 22 Waste Gas Waste Gas Disposal Disposal System System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Gas Controlled Radioactive Gas Release Release 5/28/01 5/28/01 ATTACHMENT 22 ATTACHMENT (Page 11 of2) (Page of 2) GAS DECAY BB GAS DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT III QARECORD QA RECORD PAGE PAGE IIf (Page 11 of (Page of 1) 1) Procedure Revision Procedure Revision Date Date ~_ _--:-..// _ _ _..:-//_ _ __ Check (1)./) Tag Check C""' Tag column column iftag if tag is is missing, mislabeled, mislabeled, illegible illegible or or improperly improperly secured. secured. RE1iARKS: REMARKS: __________________________________________________________ Date/Time Started_____/_ _ __ /_________ Date/Time Completed: _ _ _ _---'//_ _ _ __ PERFORME PERFORMED D BY (Print) INITIALS INDEPENDE INDEPENDENT NT VERIFY VERIFY (Print) (Print) INITIALS INITIALS II have have reviewed reviewed this this procedure procedure and and itit has been satisfactorily has been satisfactorily performed. performed. Any Any deviation(s) deviation(s) oror OTSC(s) OTSC(s) utilized utilized inin thethe performance performance of ofthis this procedure procedure has has (have) (have) been been listed listed in in the the Remarks Remarks Section. Section. REVIEWED REVIEWED BY: BY: ----------,,.---=-=--=-----=,.-,::-=c-------- Nuclear Nuclear Plant Plant Supervisor Supervisor or orSRO SRO Designee Designee WQ7. IFflhtrIvIma W97:JECllr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page; 23 23 Waste Waste Gas Gas Disposal Disposal System System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Controlled Radioactive Radioactive GasGas Release Release 9/25/01 9/25/01 ATTACHMENT ATTACHMENT 2 2 (Page (Page 22 of2) of 2) B GAS B GAS DECAY DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT PART A PART A Checked Checked Ind md Ver Ver Component Component Required Required Component Description Component Description Tag Tag && Vlv Vlv Pos Pos Tag Tag && VlvVlv Pos Pos No. No. Position Position (~) (q) lnit mit (~) (i) lnit mit Compressor Discharge Compressor Discharge PCV-1037A PCV-1037A CLOSED CLOSED HdrtoB GDT HdrtoB GDT CV-4639B CV-4639B Header Valve Re-use Header Valve CLOSED PCV-1037B PCV-1037B BB GDT GDT to to Gas Gas Analyzer CLOSED CLOSED LOCKED 4642B 4642B 2 Supply N N2 Supply to B GDT CLOSED LOCKED 4643B 4643B B GDT Drain to Drain Header CLOSED Instrument Air Supply to LOCKED 40-907 40-907 RCV-014 OPEN RCV-014 RCV-014 GDT to Plant Vent Valve CLOSED LOCKED 4638A A GDT to Plant Vent CLOSED LOCKED 463 4638C 8C C GDT to Plant Vent CLOSED LOCKED 4638D 4638D D GDT to Plant Vent CLOSED LOCKED 4638E 4638E E GDT to Plant Plant Vent Vent CLOSED CLOSED LOCKED 4638F 4638F F GDT GDT to to Plant Plant Vent Vent CLOSED CLOSED LOCKED LOCKED 463 4638B SB BB GDT GDT to to Plant Plant Vent Vent OPEN OPEN PART PARTB B Checked Checked Ind Ver md Ver Component Component Required Required Tag & Tag & Vlv VlvPos Pos Tag & Tag & Vlv VlvPos Pos Component Description Component Description No. No. Position Position (~) (I) mit lnit (~) (1) mit lnit RCV-014 RCV-014 GDT to GDT to Plant Plant Vent Vent Valve Valve CLOSED CLOSED 40-907 Instrument LOCKED LOCKED 40-907 Instrument Air Air Supply Supply to to RCV-0 RCV-01414 CLOSED CLOSED 4638B BB GDT LOCKED LOCKED 4638B GDT to Plant Vent to Plant Vent CLOSED CLOSED W07. IFz(.IIrIvIma W97:JEClir/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 24 24 Waste Gas Waste Gas Disposal Disposal System System Approval ApprovalDate: Date: 0-OP061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 ATTACHMENT 33 ATTACHMENT (Page 11 of2) (page of 2) GAS DECAY CC GAS DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT QA RECORD II QA RECORD PAGE PAGE II (Page 11 of (Page 1) of 1) Procedure Revision Procedure Revision Date Date _ _ _-:-..1/ _ _ _~//_ _ __ Check (~) Check (1) Tag column if Tag column if tag tag is is missing, missing, mislabeled, mislabeled, illegible illegible or or improperly improperly secured. secured. RE11ARKS: REMARKS:____________________________ ~ ____________________________ Date/Time Started_____I_ _ __ /_________ Date/Time Completed: _ _ _ _----ll_ _ _ __ /____________ PERFORME PERFORMED D BY (Print) INITIALS iNDEPENDE INDEPENDENT NT VERIFY VERIFY (Print) (Print) INITIALS iNITIALS II have have reviewed reviewed thisthis procedure procedure and and itit has has been been satisfactorily satisfactorily performed. performed. Any Any deviation(s) deviation(s) oror OTSC(s) OTSC(s) utilized utilized in the performance in the performance of ofthis this procedure procedure has has (have) (have) been been listed listed in in the the Remarks Remarks Section. Section. REVIEWED REVffiWEDBY: BY: ______~~--~----------~~-------- Nuclear Nuclear Plant Plant Supervisor Supervisor or or SRO SRO Designee Designee WQ7. IPChIrIpvImr W97:JECllr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle:
Title:
Page: Page; Procedure 25 25 Waste WasteGas GasDisposal DisposalSystem System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled RadioactiveGas Gas Release Release 9/25/01 9/25/01 ATTACHMENT ATTACHMENT 33 (Page 22 of2) (Page of 2) CC GAS GAS DECAY DECAY TANK TANKRELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT PART AA PART Checked Checked Ind md Ver Ver Component Component Required Required Component Description Component Description Tag && Viv Tag VIv Pos Pos Tag Tag && VivPos Vlv Pos No. No. Position Position (J) ('>/) Init mit (q) ('>/) Init mit Compressor Discharge Compressor Discharge PCV-1038A PCV-1038A CLOSED CLOSED Hdr to C GDT HdrtoC GDT CV-4639C CV-4639C Re-use Header Re-use Header Valve Valve CLOSED CLOSED PCV-1038B PCV-1038B C GDT C GDT to to Gas Gas Analyzer Analyzer CLOSED CLOSED 4642C Supply to 2 Supply N to C LOCKED 4642C N2 C GDT CLOSED CLOSED 4643C LOCKED 4643C C GDT Drain to Drain Header CLOSED Instrument Air Supply to LOCKED 40-907 40-907 RCV-014 OPEN RCV-014 RCV-014 GDT to Plant Vent Valve CLOSED 4638A LOCKED 4638A A GDT to Plant Vent CLOSED 4638B B GDT to Plant Vent LOCKED 4638B CLOSED 4638D D GDT to Plant Vent LOCKED 4638D CLOSED 4638E E GDT to LOCKED LOCKED 4638E to Plant Plant Vent CLOSED CLOSED 4638F FF GDT LOCKED LOCKED 4638F GDT to to Plant Plant Vent Vent CLOSED CLOSED 4638C C LOCKED LOCKED 4638C C GDT GDT to to Plant Plant Vent Vent OPEN OPEN PARTB PART B Checked Checked Ind Ver md Ver Component Component Required Required Component Component Description Description Tag Tag & VivPos
& Vlv Pos Tag Tag & Viv Pos
& Vlv Pos No.
No. Position Position (J) ('>/) Init mit (J) ('>/) Init mit RCV-0 RCV-014 14 GDT GDTto to Plant PlantVentVent Valve Valve CLOSED CLOSED 40-907 Instrument LOCKED LOCKED 40-907 Instrument Air Air Supply Supplytoto RCV-0 RCV-01414 CLOSED CLOSED 4638C CC GDT LOCKED LOCKED 4638C GDTto to Plant PlantVent Vent CLOSED CLOSED AIO7 IrIIrI,fr.. W97:JECllr/ev/ma
ProcedureNo.: Procedure No. ProcedureTitle:
Title:
Page: Page: Procedure 26 26 WasteGas Waste GasDisposal DisposalSystem System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled RadioactiveGas Controlled Radioactive GasRelease Release 5/28/01 5/28/01 ATTACHMENT 44 ATTACHMENT (Page lof2) (page 1 of 2) GAS DECAY DP GAS DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT II QA RECORD QA RECORD PAGE PAGE IIf (Page 11 of (Page ofl) 1) Procedure Revision Procedure Revision Date Date _ _ _...:./_ / _ _...../'-_
/ __
Check (1/) Check (q) Tag Tag column column if iftag tag isis missing, missing, mislabeled, mislabeled, illegible illegible or or improperly improperly secured. secured. RE11ARKS: REMARKS:_______________________________________________________ Date/Time Started_ _ _----e//_ _ __ Date/Time Completed: _ _ _ _~//_ _ _ __ PERFORME PERFORMED D BY (Print) INITIALS INDEPENDE INDEPENDENT NT VERIFY VERIFY (Print) (Print) INITIALS iNITIALS II have have reviewed reviewed thisthis procedure procedure and and itit has has been been satisfactorily satisfactorily performed. performed. Any Any deviation(s) deviation(s) oror OTSC(s) OTSC(s) utilized utilized in the performance in the performance of this procedure ofthis procedure has has (have) (have) been been listed listed in in the the Remarks Remarks Section. Section. REVIEWED REVffiWEDBY: BY: ______-=~--~~~~~--~~~------ Nuclear NuclearPlant PlantSupervisor Supervisoror orSRO SRODesignee Designee Wt7flhIr/v/m W97:JECllr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
I Page: Page: 27 27 Waste Gas Waste Gas Disposal Disposal System System Approval Approval Date: Date O-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 9/25/01 9/25/01 ATTACHMENT ATTACHMENT 44 (Page (Page 2 2 of2) of 2) D GAS D GAS DECAY DECAY TANK TANK RELEASE RELEASE VALVEVALVE ALIGNMENT ALIGNMENT PART A PART A Checked Checked Ind md Ver Ver Component Component Required Required Tag Tag && VlvPos Vlv Pos Tag && VlvPos Tag Vlv Pos No. Component Component Description Description No. Position Position (-V) (I) mit Init (-V) (I) Init mit Compressor Discharge Compressor Discharge PCV-1039A PCV-1039A CLOSED CLOSED HdrtoD GDT HdrtoD GDT CV-4639D CV-4639D Header Valve Re-use Header CLOSED CLOSED PCV-1039B PCV-1039B D GDT to to Gas Analyzer CLOSED LOCKED 4642D 2z Supply to D GDT N N CLOSED 4643D LOCKED D GDT Drain to Drain Header CLOSED Instrument Air Supply to LOCKED 40-907 RCV-014 OPEN RCV-014 GDT to Plant Vent Valve CLOSED LOCKED 4638A A GDT to Plant Vent CLOSED LOCKED 4638B B GDT to Plant Vent CLOSED LOCKED 4638C C GDT to Plant Vent CLOSED LOCKED 4638E E GDT to Plant Vent CLOSED CLOSED LOCKED 4638F F GDT to Plant Plant Vent Vent CLOSED CLOSED LOCKED LOCKED 4638D 4638D D GDTGDT to to Plant Plant Vent Vent OPEN OPEN PARTB PART B Checked Checked Ind Ver md Ver Component Component Required Required Tag Tag & VlvPos
& VIv Pos Tag &
Tag VlvPos
& Vlv Pos Component Description Component Description No.
No. Position Position (q) (-V) mit Init (J) (-V) mit Init RCV-014 RCV-014 GDT to GDT to Plant Plant Vent Vent Valve Valve CLOSED CLOSED 40-907 Instrument LOCKED LOCKED 40-907 Instrument Air Air Supply Supply to to RCV-014 RCV-014 CLOSED CLOSED 463 LOCKED LOCKED 8D 4638D D GDT D GDT to to Plant Plant Vent Vent CLOSED CLOSED JUO7. W97:JEC/lr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 28 28 Waste Gas Waste Disposal System Gas Disposal System Approval Approval Date: Date: 0-OP-061.14 O-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 ATTACHMENT 55 ATTACHMENT (Page 11 of2) (page of 2) GAS DECAY EE GAS DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT QA RECORD QA RECORD PAGE PAGE II II (Page 11 of (page of 1) 1) Procedure Revision Procedure Revision Date Date 1/ 1/
------~----~-------
Check (~)(J) Tag column iftagif tag is missing, mislabeled, illegible or improperly secured. secured. RE11ARKS: REMARKS:__________________________________________________________ Date/Time Started_ _ _--'I/_ _ __ Date/Time Completed: _ _ _ _--'I/_____ PERFORMED BY (Print) PERFORMED INITIALS INDEPENDE INDEPENDENT NT VERIFY (Print) INITIALS II have have reviewed this procedure reviewed this procedure and and itit has has been been satisfactorily satisfactorily performed. performed. Any Any deviation(s) deviation(s) or or OTSC(s) OTSC(s) utilized in the utilized in the performance performance of this procedure ofthis has (have) procedure has (have) been been listed listed in in the the Remarks Remarks Section. Section. REVIEWED REVIEWED BY: BY: -----~~o--__=_=-----_=,..-,,-=__---- Nuclear Nuclear Plant Plant Supervisor Supervisor oror SRO SRO Designee Designee AIO7 ICII.-I,I,- W97:JEClir/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 29 29 Waste Waste GasGas Disposal Disposal System System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled Controlled Radioactive Radioactive GasGas Release Release 9/25/01 9/25/01 ATTACHMENT ATTACHMENT 5 5 (Page 22 of2) (Page of 2) EE GASGAS DECAY DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT ART ARTA A Checked Checked Ind md VerVer Component Component Required Required Component Component Description Description Tag && VlvPos Tag Vlv Pos Tag && Vlv Tag Vlv Pos Pos No. No. Position Position (J) C-V) mit Init (I) C-V) Init mit Compressor Discharge Compressor Discharge PCV-l 052A PCV-I052A CLOSED CLOSED Hdr to E Hdrto E GDT CV-4639E Re-use Header Re-use Valve Header Valve CLOSED PCV-1052B E GDT to Gas E Gas Analyzer Analyzer CLOSED 2z Supply to E GDT N LOCKED 4642E N CLOSED LOCKED 4643E E GDT Drain to Drain Header CLOSED h1strument Air Supply to Instrument LOCKED 40-907 RCV-014 OPEN RCV-014 GDT to Plant Vent Valve CLOSED LOCKED 4638A A GDT to Plant Vent CLOSED LOCKED 4638B B GDT to Plant Vent CLOSED LOCKED 4638C C GDT to Plant Vent CLOSED CLOSED LOCKED 463 4638D SD D GDT to Plant Vent CLOSED CLOSED LOCKED LOCKED 4638F F GDT to Plant Plant Vent Vent CLOSED CLOSED LOCKED LOCKED 4638E 4638E EE GDT GDT to to Plant Plant Vent Vent OPEN OPEN PARTB PART B Checked Checked Ind Ver md Ver Component Component Required Required Component Description Component Description Tag & Tag VlvPos
& Vlv Pos Tag &
Tag VlvPos
& Vlv Pos No.
No. Position Position (J) C-V) mit Init C-V) (q) mit Init RCV-014 RCV-014 GDT to GDT to Plant Plant Vent Vent Valve Valve CLOSED CLOSED 40-907 Instrument LOCKED LOCKED 40-907 Instrument Air Air Supply Supply to to RCV-0 RCV-01414 CLOSED CLOSED 4638E EE GDT LOCKED LOCKED 4638E GDT to to Plant Plant Vent Vent CLOSED CLOSED W97:JEC/lr/ev/ma W97:JEC/lr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 30 30 Waste Gas Waste Gas Disposal DisposalSystem System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 ATTACHMENT 66 ATTACHMENT (Page 11 of2) (page of 2) FF GAS GAS DECAY DECAY TANK TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT IIIi QARECORD QA RECORD PAGE (Page 11 of (Page PAGE of 1) 1) II Procedure Revision Procedure Revision Date Date ~_ _-,--// _ _ _. :. ./_ _ __ Check (-Y) Check (1) Tag Tag column column iftag if tag is is missing, missing, mislabeled, mislabeled, illegible illegible or or improperly improperly secured. secured. RE1iARKS: REMARKS: ______________________________________________________ Date/Time Started_ _ _ _/_ _ __ /_________ Date/Time Completed: _ _ _ _---!//_ _ _ __ PERFORME PERFORMED D BY (Print) INITIALS INDEPENDE INDEPENDENT NT VERIFY VERIFY (Print) (Print) INITIALS iNITIALS II have have reviewed reviewed thisthis procedure procedure and and itit has has been been satisfactorily satisfactorily performed. performed. Any Any deviation(s) deviation(s) oror OTSC(s) OTSC(s) utilized utilized in the performance in the performance of ofthis this procedure procedure has has (have) (have) been been listed listed in in the the Remarks Remarks Section. Section. REVIEWED REVIEWED BY: BY: -----~::---c:;--_=:c;_--_=:__------_=:-::::-=___-,------ Nuclear Nuclear Plant Plant Supervisor Supervisor or or SRO SRO Designee Designee IAI(rV. IZIf I,!.,,, W97:JECllr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 31 31 Waste Gas Waste Disposal System Gas Disposal System Approval Approval Date: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Gas Controlled Radioactive Gas Release Release 9/25/01 9/25/01 ATTACHMENT 66 ATTACHMENT (Page 22 of2) (page of 2) FF GAS DECAY TANK GAS DECAY TANK RELEASE RELEASE VALVE VALVE ALIGNMENT ALIGNMENT PART A PART A Checked Checked Ind md Ver Ver Component Component Required Required Component Description Component Description Tag & Tag & VlvPos Vlv Pos Tag Tag & & VlvPos Vlv Pos No. No. Position Position (-J) (q) mit Init (-J) (q) mit Init Compressor Discharge Compressor Discharge PCV-1053A PCV-I053A CLOSED CLOSED Hdr to F GDT HdrtoF GDT CV-4639F Re-use Header Valve CLOSED CLOSED PCV-1053B PCV-I053B FF GDT to Gas Analyzer CLOSED LOCKED 4642F 2 Supply to FF GDT N N2 CLOSED LOCKED 4643F F GDT Drain to Drain Header CLOSED Instrument Air Supply to LOCKED 40-907 RCV-014 OPEN RCV-014 GDT to Plant Vent Valve CLOSED LOCKED 4638A A GDT to Plant Vent CLOSED LOCKED 4638B B GDT to Plant Vent CLOSED LOCKED 4638C C GDT to Plant Vent CLOSED CLOSED LOCKED LOCKED 4638D 4638D D GDT to Plant Vent Vent CLOSED LOCKED LOCKED 4638E 4638E E GDT GDT to to Plant Plant Vent Vent CLOSED CLOSED 4638F LOCKED LOCKED 4638F FF GDTGDT to to Plant Plant Vent Vent OPEN OPEN PART PARTB B Checked Checked Ind Ver md Ver Component Component Required Required Component Component Description Description Tag Tag & & Vlv VlvPos Pos Tag Tag & & Vlv Vlv Pos Pos No. No. Position Position (-J) (I) mit Init (-J) (]) mit Init RCV-014 RCV-014 GDT GDT to to Plant Plant Vent Vent Valve Valve CLOSED CLOSED 40-907 Instrument LOCKED LOCKED 40-907 Instrument Air Supply to Air Supply to RCV-014 RCV-014 CLOSED CLOSED 4638F FF GDT LOCKED LOCKED 4638F GDT to to Plant Plant Vent Vent CLOSED CLOSED \A107 Ii(IIrks,!r,,, W97:JEClir/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 32 32 Waste Gas Waste Gas Disposal Disposal System System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled Radioactive Controlled Radioactive Gas Gas Release Release 5/28/01 5/28/01 ATTACHMENT 77 ATTACHMENT (Page 11 of2) (Page of 2) GAS DECAY GAS DECAY TANK TANK PRESSURES PRESSURES (DURING (DURING RELEASE) RELEASE) IIIi QARECORD QA RECORD PAGE (Page 11 of (Page PAGE of 1) 1) II Procedure Revision Procedure Revision Date Date ~_ _....:...-// _ _ _,.:..//_ _ __ Check (J) Tag Check (-,J) column iftag Tag column if tag is is missing, missing, mislabeled, mislabeled, illegible illegible or or improperly improperly secured. secured. RENU\RKS: REMARKS: ________________________________________________________ Date/Time Started_ _ _ _/_ _ __ Date/Time Completed: _ _ _ _----'/_ _ _ __ /____________ PERFORME PERFORMED D BY (Print) INITIALS have reviewed II have reviewed thisthis procedure procedure and and itit has has been been satisfactorily satisfactorily performed. performed. Any Any deviation(s) deviation(s) or or OTSC(s) OTSC(s) utilized in the performance utilized in the performance of ofthis this procedure procedure has has (have) (have) been been listed listed in in the the Remarks Remarks Section. Section. REVWWED REVIEWED BY: BY: ________---:,--~-------_=-,,------- Nuclear Nuclear Plant Plant Supervisor Supervisor oror SRO SRO Designee Designee AI(7. W97:JECllr/ev/ma
ProcedureNo.: Procedure No.: ProcedureTitle:
Title:
Page: Procedure Page: 33 33 WasteGas Waste GasDisposal DisposalSystem System Approval ApprovalDate: Date: 0-OP-061.14 0-OP-061.14 Controlled RadioactiveGas Controlled Radioactive GasRelease Release 5/28/01 5/28/01 ATTACHMENT77 ATTACHMENT (Page22 of2) (Page of 2) GAS DECAY GAS DECAYTANK TANKPRESSURES PRESSURES (During(During Release) Release) GDT GDT GUT GDT GDT GDT GDT GDT GDT GDT GDT GUT All All B/2 B/2 C/3 C/3 D/4 D14 E/5 E15 F/6 Ff6 GDT PRESS GDTPRESS PRIOR PRIOR TO TO RELEASE RELEASE GDT PRESS GDTPRESS T-O MINS T-O MINS (AT START) (AT START) GDT PRESS GDTPRESS T+15 MINS T+15 MINS GDT PRESS GDTPRESS T+30 MINS T+30 MINS GDT PRESS GDTPRESS T+45 MINS T+45 MINS GDT PRESS GDTPRESS T+60 T+60MINSMINS GDT GDTPRESSPRESS T+75 T+75 MINS MINS GDT GDTPRESSPRESS (AT END) (AT END) FINAL FINAL PAGE PAGE AIQ7 IuIrI,In, W97:JEC/lr/ev/ma
Procedure No.: Procedure
Title:
Page: 25 Approval Date: 0-NCOP-004 Preparation of Gas Release Permits 3/11/02 ATTACHMENT 11 ATTACHMENT (Page 11 ofl) of 1) GAS DECAY TANK RELEASE PERMIT GAS DECAY TANK RELEASE PERMIT I I FLORIDA POWER AND LIGHT COMPANY Gas Release No. TURKEY POINT PLANT ____________ GRP GRP-GAS DECAY TANK RADIOACTIVE GAS RELEASE PERMIT Date: (Ref: 0-OP-06 1.14) 0-OP-061.14) Gas Decay Tank: I Approx. Act, to be Released Approx, Act. Ci PART I: Pre-release Data R-14 PV SPING Noble Gas Activity f..lCi/cc liCi/cc Background, cpm f..lCi/cc llCi/cc Expected response cpm pCi/cc f..lCi/cc Administrative Limit 300,000 cpm 1.0 E-2 jiCi/cc 1,0 f..lCiicc Date/Time Sample DatelTime Count Date/Time Count time shall be within 2 hours of sample time Special Instructions PART II: Limits R-14 Alarm Setpoint == if R-14 is OOS) cpm (N/A ifR-14 Tank Release Rate Limit: RCV-014 Loader Setting == % Terminate Release if Maximum Expected Monitor Reading, , is exceeded PART III: Authorizations and Approvals Permit Prepared by Technician Analysis Approved by Radiochemistry Supervisor Release Approved by Nuclear Plant Supervisor PART: IV: Release Data I S I I Cont. Purge I S I Release Performed by: Fans: Aux, Aux. Bldg I E I r ET I Start Every 15 minutes Stop Time Date Wind Speed, MPH Wind Direction, Degrees Delta T or Sigma Theta RCV-014 Loader Setting % jiCi/cc Monitor Reading, CPM or f..lCi/cc Gas Decay Tank Pressure Ever 15 minutes Ever Plant Vent Flow SCFM REMARKS: WC:PS/bc!ev/mrq WC:PS/bclev/mrq
Procedure No.: Procedure Procedure
Title:
Procedure
Title:
Page: 25 Approval Date: Approval 0-NCOP-004 Preparation of Gas Release Permits 3/11102 3/11/02 ATTACHMENT 11 (Page 11 of 1)1) GAS DECAY TANK RELEASE PERMIT I I FLORIDA POWER AND LIGHT COMPANY Gas Release No. TURKEY POINT PLANT GRP GRP-GAS DECAY TANK RADIOACTIVE GAS RELEASE PERMIT Date: 0-OP-061 .14) (Ref: 0-OP-061.14) Gas Decay Tank: I Approx. Act. to be Released Ci PART I: Pre-release Data R- 14 R-14 PV SPING Noble Gas Activity flCi!cc lICi/cc Background, cpm flCi/cc IJ.Ci/cc Expected response cpm jiC i/cc flCi/cc Administrative Limit 300,000 cpm 1.0 E-2 flCi/cc liCi/cc Date/Time Sample DatelTime Count Date/Time Count time shall be within 2 hours of sample time Special Instructions PART II: Limits R-14 Alarm Setpoint = if R-14 is OOS) cpm (N/A ifR-14 Tank Release Rate Limit: RCV-014 Loader Setting = = % Terminate Release if Maximum Expected Monitor Reading, , is exceeded PART III: Authorizations and Approvals Permit Prepared by Technician I I Analysis Approved by I I Radiochemistry Supervisor Release Approved by Nuclear Plant Supervisor PART: IV: Release Data Fans: Aux. Bldg I S I II Cont. Purge I SS I Release Performed by: I E I I E I I Start Every 15 minutes Stop Time Date Wind Speed, MPH Wind Direction, Degrees Delta T or Sigma Theta RCV-014 RCV -014 Loader Setting % Monitor Reading, CPM CPM or liCi/cc flCi/cc Gas Decay Tank Pressure Ever Ever: 1515 mini minutes ites Plant Vent Flow SCFM Plant REMARKS: SCFM t WC:PS/bc/ev/mrg WC:PS/bc/ev/mro
Procedure No.: Procedure
Title:
Procedure
Title:
Page: 25 25 Approval Date: 0-NCOP-004 Preparation of Gas Release ReLease Permits 3/11102 3/11/02 ATTACHMENT 1 (Page 11 of 1) 1) GAS DECAY TANK RELEASE PERMIT I FLORIDA POWER AND LIGHT COMPANY Gas Release No. I TURKEY POINT PLANT ____________ GRP GRP-GAS DECAY TANK RADIOACTIVE GAS RELEASE PERMIT Date: 0-OP-061 .14) (Ref: 0-OP-061.l4) Gas Decay Tank: I Approx. Act. to be Released Ci PART I: Pre-release Data R-14 PV SPING Noble Gas Activity [.lCi/Cc IICi/cc Background, cpm [.lCi/Cc l.tCi/cc Expected response cpm [.lCi/cc
!.tCi/cc Administrative Limit 300,000 cpm 1.0 E-2 [.lCi/cc lICi/cc Date/Time Sample DatelTime Count Date/Time Count time shall be within 2 hours of sample time Special Instructions PART II: Limits R-l4 Alarm Setpoint =
R-14 if R-l4 is OOS) cpm (N/A ifR-14 Tank Release Rate Limit: RCV-014 Loader Setting == % Terminate Release if Maximum Expected Monitor Reading, , is exceeded PART III: Authorizations and Approvals Permit Prepared by Technician Analysis Approved by Radiochemistry Supervisor Release Approved by Nuclear Plant Supervisor PART: IV: Release Data Fans: Aux. Bldg I S I II Cont. Purge I SS I Release Performed by: I E I I E I Start Every 15 minutes Stop Time Date Wind Speed, MPH Wind Direction, Degrees Delta T or Sigma Theta RCV-014 RCV -014 Loader Setting % CPM or pCi/cc Monitor Reading, CPM [.lCi/cc Gas Decay Tank Pressure Ever Ever: 1515 minutes Plant Plant Vent Flow SCFM REMARKS: WC:PS/bc/ev/mra WC:PS/bc/ev/mra
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 25 Approval Date: Approval Date: 0-NCOP004 0-NCOP-004 Preparation of Preparation of Gas Gas Release Release Permits Permits 3/11102 3/11/02 ATTACHMENT 11 (Page 11 of (Page ofi) 1) GAS DECAY TANK RELEASE PERMIT I I FLORIDA POWER AND LIGHT COMPANY Gas Release No. TURKEY POINT PLANT ___________ GRP GRP-GAS DECAY TANK RADIOACTIVE GAS RELEASE PERMIT Date: 0-OP-06 1.14) (Ref: 0-OP-061.14) Gas Decay Tank: I Approx. Act. to be Released Ci PART I: Pre-release Data R-l4 R-14 PV SPING Noble Gas Activity l.tC i/cc J..lCi/cc Background, cpm tCi/cc J..lCi/Cc Expected response cpm .tCi/cc J..lCi/Cc Administrative Limit 300,000 cpm tCi/cc 1.0 E-2 J..lCi/cc Date/Time Sample DatelTime Count Date/Time Count time shall be within 2 hours of sample time Special Instructions PART II: Limits R-14 Alarm Setpoint == if R-14 is OOS) cpm (N/A ifR-14 Tank Release Rate Limit: RCVRCV-0l4 -014 Loader Setting = % Terminate Release if Maximum Expected Monitor Reading, , is exceeded PART III: Authorizations and Approvals Permit Prepared by Technician Analysis Approved by Radiochemistry Supervisor Release Approved by Nuclear Plant Supervisor PART: IV: Release Data Fans: Aux. Bldg I S I II Cont. Purge I SS I Release Performed by: I E I I E I Start Every 1515 minutes Stop Time Date Wind Speed, MPH Wind Direction, Degrees Delta T or Sigma Sigma Theta RCV-014 RCV -014 Loader Loader Setting Setting % Monitor Monitor Reading, CPM CPM oror lICi/cc J..lCi/cc Gas Gas Decay Decay Tank Tank Pressure Pressure Ever Ever: 15 15 minutes minutes Plant Plant Vent Vent Flow Flow SCFM SCFM REMARKS: WC:PS/bc/ev/mra
Appendix C Appendix C Performance Measure Job Performance Job Measure Form Form ES-C-I ES-C-1 Worksheet Worksheet Facility: Facility: Turkey Turkey Point Point Task Task No: No: 4023030500 4023030500 Unit 44 EDG Recover from aa Unit Recover EDG Job Job Performance Performance Task
Title:
Task
Title:
Auto Start Failure Auto Start Failure Measure No: Measure No: Systems Systems - kk KIA
Reference:
K/A
Reference:
064 064 A4.01 (4.0/4.3) (4.0/4.3} Examinee: Examinee: NRC Examiner: Evaluator: Facility Evaluator: Date: Method of testing: JPM Performance Simulated Performance Yes Actual Performance No No Classroom - - - - - - - - - - - - - Classroom Simulator - - - - - - - - - - - - Plant X Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: A Loss of Offsite Power has occurred and 4A(B) EDG has failed to energize the 4A(B) 4kV bus. Task Standards:
- 1. 4A(B) EDG is started locally
- 2. 4A(B) EDG is locally loaded on 4A(B) 4kV bus Required Materials
- 1. EDG key(s)
- 2. Sync plug
- 3. 4-0NOP-023.2, 4-ONOP-023.2, Emergency Diesel Generator Failure General
References:
- 1. 4-0NOP-023.2, 4-ONOP-023.2, Emergency Diesel Generator Failure Initiating Cue:
You have been directed by the Unit 4 RO to respond to a failure of 4A(B) EDG to automatically start and energize the 4A(B) 4kV bus. Time Critical Task: No Validation Time: 30 minutes
Appendix C Page 2 of 12 ES-C-I Form ES-C-1 INSTRUCTIONS TO OPERA OPERATOR TOR READ TO OPERA TOR: WHEN II TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. II WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, II WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS: A Loss of Offsite Power has occurred and 4A(8) 4A(B) EDG has failed to energize the 4A(8) 4A(B) 4kV bus. INITIATING INITIA TlNG CUE: You have been directed by the Unit 4 RO to respond to a failure of 4A(8) 4A(B) EDG to automatically start and energize the 4A(8) 4A(B) 4kV bus. NOTE 1:I: Inform examinee to simulate performance of steps involving hands on manipulation of plant equipment during this JPM. NOTE 2: DO NOT PERFORM THIS JPM ON THE UNIT 4 PROTECTED TRAIN EDG. Identify the protected train before beginning the JPM and brief JPM performance on the non- non EDO. protected EDG. Do you have any questions? You may begin.
I Appendix Appendix C C Page 33 of Page of 12 12 I Form ES-C-I Form ES-C-1 I Denote critical Denote steps with aa check critical steps check mark (vi mark (J Start Time Start Time Obtains controlled copy Obtains aa controlled copy of 4-0NOP-023.2, Emergency of 4-ONOP-023.2, Emergency Diesel Diesel STEP STEP 11 : Failure. Failure. SAT
- - SAT Observes Cautions and Notes Notes prior to step 1.
- 1. UNSAT
- - UNSAT 4-0NOP-023.2 obtained in the 4A(B)
- 1. Controlled copy of 4-ONOP-023.2
- 1. 4A(8) EDG Room.
- 2. Reviews Caution regarding the affected EDG Normal/Isolate Isolate resets the breaker anti-switch. Taking the switch to Isolate STANDARDS: pumping relays. Returning switch to Normal allows EDG output breaker auto-closure.
- 3. Reviews note defining affected EDG.
- 4. Reviews note that all controls & indications located on affected EDG engine electrical control panel (unless noted otherwise).
CUE: CUE Normailisolate switch to If operator requests permission to place the Normal/Isolate Isolate, grant him permission as the US or SM. 4A(B) EDG - STOPPED. Check 4A(8) - STEP 2 - - SAT (procedure step 1) UNSAT STANDARD: 4A(B) EDG stopped. Determines 4A(8) When asked by the candidate for specific indications locally available, CUE: provide them consistent with a stopped EDG (e.g., no EDG noise,
= =
engine speed 0 RPM, EDG voltage = 0, EDG frequency = 0). = 4A(B) EDG Master Control Switch in LOCAL. Place 4A(8) STEP 3 : - - SAT V
./ (procedure step 2)
- - UNSAT STANDARDS: 4A(B) EDG Master Control Switch in LOCAL.
Places 4A(8) CUE: If candidate simulates operating switch, confirm new switch position.
Appendix C Page 4 of 12 ES-C-I Form ES-C-1 Check 4A(B) EDG Starting Air Line Pressure is Between 193 and 202 STEP 4 : psig. - - SAT (procedure step 3) - - UNSAT STANDARD: Determines 4A(B) EDG Starting Air Line Pressure 193 193-- 202 psig, When 4A(8) 4A(B) EoG EDG Starting Air Line Pressure indicator is correctly
- CUE: identified, point to 200 psig on the indicator.
Check 4A(B) EDG Control Power Light - ON. STEP 5 : -
- - SAT (procedure step 4)
- - UNSAT STANDARD: Determines 4A(B) EDG Control Power Light is ON.
4A(B) EoG When 4A(8) EDG Control Power indicating light is correctly identified, CUE: state that the light is ON. ,P'~' Check the 4A(B) EDG Day Tank Level- Level ABOVE THE LOW LEVEL STEP 6 ALARM - - SAT (procedure step 5) - - UNSAT Determines 4A(B) EDG Day Tank Level above the Low Level Alarm STANDARD: setpont. 4A(B) EoG
- 1. When 4A(8) EDO Day Tank Level indicator is correctly identified, point to 90% on the indicator.
CUES:
- 2. When 4A(B) 4A(8) EDG EoG Day Tank Low Level alarm indicator is correctly identified, state that the alarm is clear.
I Appendix C Page 5 of 12 ES-C-I Form ES-C-1 II Check the following 4A(B) EDG Local Panel Alarms. STEP 7 - - SAT
** 3/2, ENGINE OVERSPEED TRIP - CLEAR -
- 4/2, LUBE OIL HIGH TEMPERATURE TRIP - CLEAR -
- - UNSAT
** 4/4, EXHAUST HIGH TEMPERATURE TRIP - CLEAR -
** 4/5, COOLING WATER HIGH TEMP TRIP - CLEAR -
** 5/2, MAIN MANIFOLD LUBE OIL LOW PRESSURE TRIP- TRIP -
CLEAR
** 5/5, COOLING WATER LOW PRESSURE TRIP - CLEAR -
** 6/1, ENGINE HIGH VIBRATION TRIP - CLEAR -
** 6/2, PISTON COOLING OIL LOW PRESSURE TRIP - CLEAR -
- 6/4, CRANKCASE HIGH PRESSURE TRIP - CLEAR -
(procedure step 6) Determines each of the 4A(B) EDG local panel alarms listed above are STANDARD STANDARD: clear. CUE CUE: 4A(B) EDG local panel alarm indicators listed above As each of the 4A(8)
- are correctly identified, state that the alarm is clear.
Check status of the following 4A(B) EDG relays STEP 8 : - - SAT
** Loss of Field Relay (140) - NO FLAG
- Voltage Balance Relay (160) - NO FLAG
- - UNSAT
** Reverse Power Relay (132) - NO FLAG
** Overcurrent phase A (151V PH A) - NO FLAG
** Overcurrent phase B B (151V PH B) - NO FLAG
** (151V Overcurrent phase C (151 V PH C) - NO FLAG
** Differential phase A (187G PH A) - NO FLAG
- Differential phase B (187G PH B) - NO FLAG
- Differential phase C (187G PH C) - NO FLAG (procedure step 7)
Determines each of the 4A(B) EDG relays listed above have no flags STANDARD: dropped. CUEs CUEs: 4A(B) EDG relays listed above are correctly identified, As each of the 4A(8) state that the no flags are dropped for each relay.
Appendix C Page 6 of 12 ES-C-I Form ES-C-1 4A(B) EDG Start Failure Annunciator - OFF Verify 4A(S) - STEP 9
- - SAT (procedure step 8)
- - UNSAT 4A(B) EDG local alarm panel Start Failure Determined that the 4A(S)
STANDARDS STANDARDS: Annunciator (9/4) is OFF 4A(B) EDG Start Failure Annunciator is correctly identified, state When 4A(8) CUE: that the alarm is clear. Verify 4A(S) 4A(B) Diesel Generator Lockout Relay - RESET STEP 10
- - SAT (procedure step 9)
- - UNSAT STANDARDS: 4A(B) EDG Lockout Relay is reset (blue light on)
Determined that the 4A(S) When the candidate correctly describes how to determine if the /- CUE: 4A(B) EDG lockout relay is reset lockout relay is reset, confirm that the 4A(8) and blue light on.. Check 4A(B) 4A(S) Diesel Generator - AUTO STARTED: STEP 11
- - SAT
- a. 4A(B) Diesel Generator - RUNNING Check 4A(S) -
UNSAT (procedure step 10) 4A(B) EDG did not auto start and is not
- 1. Determines that the 4A(S)
STANDARD: running
- 2. Proceeds to procedure step 11 11 When asked by the candidate for specific indications locally available, CUE: provide them consistent with a stopped EDG (e.g., no EDG noise,
= =
engine speed 0 RPM, EDG voltage = 0, EDG frequency = 0). =
I Appendix C Page 7 of 12 ES-C-I I Form ES-C-1 Locally Start 4A(B) Diesel Generator: STEP 12
- - SAT
- a. Push 4A(B) EDG Engine EMERGENCY START pushbutton
- b. Verify 4A(B) EDG - RUNNING
- - - UNSAT
- c. Verify 4A(B) EDG output breaker automatically closes (procedure step 11)
STANDARDS: V
,/ 1. Pushes 4A(B) EDG Engine EMERGENCY START pushbutton
- 2. Determines 4A(B) EDG running
- 3. Determines 4A(B) EDG output breaker did not automatically close
- 4. Proceeds to procedure step 12
- 1. When candidate correctly locates and describes how to operate the 4A(B) EDG Engine Emergency Start pushbutton, confirm operation of the pushbutton
- 2. After correct emergency start pushbutton operation, when asked CUES*
CUES: by the candidate for specific indications locally available, provide them consistent with a running EDG (e.g., presence of EDG EDO noise, engine speed approx. 900 RPM, EDG voltage approx. 4160V, EDG frequency approx. 60 Hz).
- 3. When 4A(B) EDG Output Breaker indicating lights correctly identified, state that the green light is ON and the red light is OFF.
I Check 4A(B) Diesel Generator: STEP 13 : - - SAT
- 1. At the 4A(B) EDG Engine Control Panel, verify 4A(B) Diesel Generator speed - BETWEEN 880 - 920 RPM
- - UNSAT
- 2. At the 4A(B) EDG Generator Control Panel, verify 4A(B) Diesel Generator frequency - BETWEEN 58.8 - 61.2 HZ
- 3. Verify 4A(B) Diesel Generator voltage - BETWEEN 3740-
- 3740 -
4580 VOLTS (procedure step 12) STANDARDS: 1. Determined 4A(B) EDG speed between 880 - 920 RPM-
- 2. Determined 4A(B) EDG frequency between 58.8 - 61.2 Hz
- 3. Determined 4A(B) EDG voltage between 3740-4580 V
- 1. When 4A(B) EDG speed indicator is correctly identified, point to 900 RPM on the indicator.
CUE-CUE: 2. When 4A(B) EDG frequency meter is correctly identified, point to 60 Hz on the meter.
- 3. When 4A(B) EDG voltage meter is correctly identified, point to 4200 Von V on the meter.
Appendix C Page 8 of 12 ES-C-I Form ES-C-1 Notify RO That 4A(B) Diesel Generator is Available to Power Its STEP 14 SAT Associated Bus -- (procedure step 13) - - UNSAT STANDARD: Informs Unit 4 RO that 4A(B) EDG is available to power the 4A(B) 4kV bus. CUE: 4A(B) EDG is available to As Unit 4 RO, acknowledge report that 4A(8) power the 4A(8) 4A(B) 4kV bus. Obtain Permission from RO to Locally Energize 4KV Bus Associated STEP 15 -- SAT with Running Diesel Generator (procedure step 14) - - UNSAT STANDARD: Obtains permission from Unit 4 RO to locally energize 4A(B) 4kV bus from 4A(B) EDG. CUE: When requested as Unit 4 RO, grant permission to locally energize 4A(8) 4A(B) EDG. 4A(B) 4kV bus from 4A(8) f/""~
I Appendix C Page 9 of 12 I ES-C-1 I Form ES-C-I Locally Energize 4A(B) 4KV Bus STEP 16 16 -- SAT
- a. Verify 4A(B) Diesel Generator Master Control switch in LOCAL
- b. Verify 4A(B) Diesel Generator isolation switches (Engine Control - - UNSAT Cubicle) positioned to ISOLATE
- c. Place synchronization switch for 4A(B) Diesel Output Breaker to ON
- d. Have RO verify all breakers on 4A(B) 4kV bus - OPEN-
- e. At 4A(B) EDG Electrical Control Panel, close 4A(B) Diesel Generator Output Breaker
- f. Place 4A(B) EDG synchronizing switch to OFF AND remove handle
- g. Check 4A(B) Diesel Generator Output Breaker status - CLOSED-(procedure step 15)
STANDARDS: 1. Determines 4A(B) EDG Master Control switch already in LOCAL v 2. Places 4A(B) EDG isolation switches on Engine Control Cubicle to ISOLATE vV 3. Places 4AA20(4AB21) synchronization switch to ON
- 4. Requests Unit 4 RO verify all 4A(B) 4kV bus breakers OPEN vV 5. Closes 4AA20(4AB21) from 4A(B) EDG Electrical Control Panel
,/~-'
- 6. Places 4AA20( 4AB21) synchronization switch to OFF 4AA20(4AB21)
- 7. Removes 4AA20(4AB21) synchronization switch handle 4AA20(4AB21)
- 8. Determines 4AA20( 4AB21 ) closed (EDG powering 4kV bus)
- 1. When 4A(B) EDG Master Control Switch correctly identified, show candidate that switch is positioned to LOCAL
- 2. When 4A(B) EDG isolation switches on Engine Control Panel correctly identified and candidate simulates operating switch, confirm new switch position.
- 3. When 4AA20(4AB21) sync switch correctly identified and candidate simulates operating switch, confirm new switch position.
- 4. When asked as Unit 4 RO, report a/l all 4A(B) 4kV bus breakers open CUES*
CUES:
- 5. When 4AA20(4AB21) control switch correctly identified, when candidate simulates operating switch, confirm new switch position.
- 6. When 4AA20(4AB21) sync switch correctly identified and candidate simulates operating switch, confirm new switch position.
- 7. When 4AA20(4AB21) sync switch handle removal correctly described, confirm handle removal.
- 8. When 4A(B) EDG Output Breaker 4AA20(4AB21) indicating lights correctly identified, state that green light is OFF & red light is ON.
/~ NOTE NOTE: Synchronizing switch handle is typically left installed in the Control Panel. Candidate may elect to leave switch in place. I
Appendix CC Page 10 of 12 ES-C-I Form ES-C-1 Maintain 4A(B) Diesel Generator STEP 17 : -- SAT ,~"
- a. Verify voltage - BETWEEN 3740 - 4580 V
- b. Verify frequency - BETWEEN 58.8 - 61.2 HZ
- - - - UNSAT
- c. Verify load - LESS THAN 2500 KW
- d. Operate 4A(B) Diesel Generator controls as directed by Unit 4 RO
- 1. Determines 4A(B) EDG voltage between 3740 - 4580 V
- 2. Determines 4A(B) EDG frequency bewteen 58.8 - 61.2 Hz STANDARDS:
- 3. Determines 4A(B) EDG load less than 2500 KW
- 4. Requests further direction from Unit 4 RO 4A(B) EDG voltage meter is correctly identified, point to
- 1. When 4A(8) 4200 Von the meter.
4A(B) EDG frequency meter is correctly identified, point to
- 2. When 4A(8) 60 Hz on the meter.
CUE CUE: 4A(B) EDG load (KW) meter is correctly identified, point to
- 3. When 4A(8) 1200 KWon the meter.
- 4. When requested as Unit 4 RO, tell candidate to standby for further direction Terminating Terminating Tell candidate that JPM is complete. STOP Cue:
Stop Time - - - -
I Appendix CC Page II 11 of 12 12 Form ES-C-I ES-C-1 I Verification of Completion JobPe~rmanceMeasureNo. Job Performance Measure No. _S~ys~t~e~m~s_-~k~~~~~~~~~~~~~~~~~~~~~~ Systems k Examinee's Name: Examinees Examiner's Examiners Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: ,/0"'~",_~~~~~~~~~~~~~~~~~~~~~~~~_~~~~~~~~_~ _ __
Response
Result: Satisfactory/Unsatisfactory Examiner's Examiners signature and date: _ _ _ _ _~_ _ _ _~~~_ _ _~_
JPM BRIEFING SHEET INITIAL CONDITIONS: 4A(B) EDG has failed to energize the 4A(8) A Loss of Offsite Power has occurred and 4A(8) 4A(B) 4kV bus. INITIATING INITIA TlNG CUE: 4A(B) EDG to automatically start and You have been directed by the Unit 4 RO to respond to a failure of 4A(8) 4A(B) 4kV bus. energize the 4A(8) HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant Unit 4
Title:
Emergency Diesel Generator Failure Safety Related Procedure Responsible Department: Operations Revision Approval Date: 8/22/05 RTSs 91-1224P, 94-0603P, 97-0342P, 97-1433P, 98-1423P, 04-0898P OTSCs 0726-93, 0138-94 PCIMs 87-263, 87-264, 04-036 W97:/JEE/bsm/ev/ev W97:1JEE/bsm/ev/ev
Procedure No.: Procedure
Title:
Page: 2 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 LIST OF EFFECTIVE PAGES Revision Page Date 11 08/22/05 2 08/22/05 08/22105 33 08/22/05 4 08122105 08/22/05 55 08/22/05 6 08/22/05 77 08/22/05 88 08/22/05 9 9 08/22/05 10 08/22/05 11 08/22/05 12 08/22/05 13 08/22/05 14 08/22/05 WQ7I. I/hm/c!v/v
Procedure No.: Procedure
Title:
Page: 3 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 1.0 PURPOSE This procedure provides instructions for local operator action in the event an emergency diesel generator fails to energize its associated 4KV buses when required. 2.0 SYMPTOMS 2.1 Loss of voltage on the 4A or 4B 4KV bus 2.2 Annunciator F 8/2 - EDG A TROUBLE alarmed 2.3 Annunciator F 8/3 - EDG - EDO A BKR OVERCURRENT TRIP alarmed 2.4 Annunciator F 8/5 - EDG A MASTER CONTROL SW OFF-NORMAL alarmed 2.5 Annunciator F 9/2 - EDG B TROUBLE alarmed 2.6 Annunciator F 9/3 - EDG B BKR OVERCURRENT TRIP alarmed 2.7 Annunciator F 9/5 - EDG - EDO B MASTER CONTROL SW OFF-NORMAL alarmed 2.8 Diesel generator Ready To Start red light - OFF
Procedure No.: Procedure
Title:
Page: 4 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05
3.0 REFERENCES
/RECORDS REQUIRED/ REFERENCESIRECORDS REQUIRED! COMMITMENT DOCUMENTS 3 1 3.1 References 3.1.1 Technical specifications
- 1. 3/4.8.1, A.c. Sources Section3/4.8.1,A.C.Sources Section 3.1.2 FSAR
- 1. Section 8, Electrical
- 2. Section 9.15, Emergency Diesel Generator Auxiliaries 3.1.3 Plant Drawings
- 1. 561 4-M-3022, Sheet 1, Emergency Diesel Engine and Oil System EDG 4A 5614-M-3022, Air Starting System
- 2. 5614-M-3022, Sheet 2, Emergency Diesel Engine and Oil System EDG 4B Air Starting System
- 3. 5614-M-3022, Sheet 3, Emergency Diesel Engine and Oil System EDG 4A Fuel System
- 4. 5614-M-3022, Sheet 4, Emergency Diesel Engine and Oil System EDG 4B Fuel System
- 5. 5614-M-3022, Sheet 5, Emergency Diesel Engine and Oil System DG 4A Lo and Cooling Water
- 6. 5614-M-3022, Sheet 6, Emergency Diesel Engine and Oil System DG 4A Lo and Cooling Water
- 7. 5610-E-855, Breaker List
- 8. 5614-T-L1, Sheet 9Al 5614-T-Ll, 9A1 - EDG Start
- 9. 5614-T-L1, 5614-T-Ll, Sheet 9A2 - EDG Engine Start
- 10. 561 4-T-L 1, Sheet 9A3 - Diesel Gen Governor and Voltage Regulator Control 5614-T-Ll, -
Logic
- 11. 5614-T-L1, 5614-T-Ll, Sheet 9A4 - Diesel Engine and Generator Stop and Lockout Logic
- 12. 5614-T-Ll, Sheet 9A5 - Diesel Gen Breaker and Fuel Oil Pump Control 5614-T-L1, -
- 13. 5614-T-Ll, 5614-T-L 1, Sheet 9A6 9A6 - Diesel Engine and Generator Annunciation and Indication Logic
- 14. 5614-T-L1, 5614-T-Ll, Sheet 9A7 - Diesel Engine Generator Annunciation and Indication Logic 22
- 15. 5610-T-L1, 5610-T-Ll, Sheet 12A - Sequencer AIO7/
Procedure No.: Procedure
Title:
Page: 5 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 3.1.3 (Cont'd) (Contd) 16.
- 16. 5610-T-Ll, Sheet 12B - Sequencer 56IO-T-LI, -
- 17. 5614-T-L1, Sheet 13 - Bus 4A Loss of Voltage and Bus Stripping 5614-T-Ll, -
- 18. 5614-T-L1, Sheet 13A - Bus 4B Loss of Voltage and Bus Stripping 5614-T-LI, -
3.1 .4 3.1.4 Quality Oualitv Instructions/Plant Procedures
- 1. 3/4-EOP-ECA-O.O, Loss of All AC Power
- 2. O-ONOP-105, Control Room Evacuation O-ONOP-I05,
- 3. 4-ONOP-004.2, Loss of 4A 4KV Bus 4-0NOP-004.2,
- 4. 4-ONOP-004.3, Loss of 4B 4KV Bus 4-0NOP-004.3,
- 5. 4-OP-022, Emergency Diesel Generator Fuel Oil System 4-0P-022,
- 6. 4-OP-023, Emergency Diesel Generator 4-0P-023, 3.1.5 Miscellaneous Documents (i.e., PC/M, Correspondence)
- 1. JPN-PTP-90-0485, Turkey Point Units 33 and 4 Emergency Diesel Generator Voltage Tolerance IS MOD
- 2. PC/M 87-263, New EDGs Installation
- 3. PC/M 87-264, EDG 3B/4B, EDG 3A/4A and New EDG Building Tie-Ins 3.2 Records Required 3.2.1 The date and time completed shall be entered in the Unit Narrative Log. Also, problems encountered while performing the procedure should be entered; i.e.,
malfunctioning equipment delays due to changes in plant conditions, etc. 3.3 Commitment Documents 3.3.1 None
Procedure No.: Procedure Procedure
Title:
Procedure
Title:
Page: 6 Approval Date: Approval 4-ONOP-023.2 Emergency Diesel Generator Failure 8/22/05 4-0NOP-023.2 STEP f ACTION/EXPECTED ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I CAUTIONS If either 4KV bus is deenergized, the Normal I/ Isolate switches for the affected EDG 4KV bus breaker is placed in Isolate to reset the anti-pumping relays. The affected EDG breaker may auto-close when the switch is returned to Normal. NOTES I ** started.. Affected refers to the diesel generator which is being started I II .
- Unless otherwise noted all controls and indications are located on the affected I I emergency diesel engine electrical control panel. i L- a a I 1 Check Affected Emergency Diesel Generator a. Locally verify all breakers on affected
- STOPPED
- 4KV buses - OPEN
- b. Perform the following at the affected EDG breaker, 4AA20, 4AB21:
- 1) Place Normal/Isolate switch in ISOLATE
- 2) Normal/Isolate Place Normaillsolate switch in NORMAL
- c. Go to Step 12.
W97:IJEE/bsmlev/ev W97:/JEE/bsm/ev/ev
Procedure No.: Procedure
Title:
Page: 7 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 I STEP I I ACTION/EXPECTED ACTION!EXPECTED RESPONSE I r RESPONSE NOT OBTAINED 1 I II 2 Place Affected Emergency Diesel Generator Master Control Switch In LOCAL 3 Check That The Starting Air Line Pressure Perform the following: Is Between 193 And 202 psig
- a. Check for an air leak in:
- 1) Starting air lines
- 2) Air Receiver Tanks
- b. IF an air leak is found, THEN isolate the leak as necessary.
- c. Verify the electric air compressor is running.
- 1) IF the air compressor will NOT run in AUTO, THEN place the air compressor switch to RUN.
- 2) IF the air compressor does QI NOT start, THEN start the diesel air compressor using 4-0P-023, 4-OP-023, EMERGENCY DIESEL GENERATOR.
- d. IF Air Receiver Tank pressure is between 193 and 202 psig AND the Engine Start Air Press-Left or Right indicates less than 183 psig, THEN verify the EDG Air Start System valve alignment using 4-OP-023, 4-0P-023, EMERGENCY DIESEL GENERATOR.
W97:/JEE/bsm/ev/ev
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 STEP AóNiE*iDiiPiiE ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 4 Check Control Power Light-ON
- a. Request RO RD to verify affected Emergency Diesel Generator Flashing and Control Power Breaker ON:
- 4D23A-28 for 4A EDG
- 4D01-47for4BEDG 4D01-47for 4B EDG
- b. Verify the local distribution panel breaker is ON:
isON:
- 4D35-06 for 4A EDG 4035-06
- 4D36-06 for 4B EDG 4036-06 5 Check The EDG Day Tank Level ABOVE a. Check the Fuel Oil Transfer Pump as THE LOW LEVEL ALARM follows:
- 1) Place Fuel Transfer switch to RUN fj.Q verify the red Fuel Transfer AND light is ON.
- 2) IF the red Fuel Transfer light is OFF, ffl THEN verify closed breaker 45112 (45212), DG 4A (B) Fuel Oil Transfer Pump.
- 3) IF the Fuel Oil Transfer Pump will NOT start, THEN transfer fuel to the Day Tank by cross-tying EDG Fuel 4-OP-022, Oil Systems using 4-0P-022, EMERGENCY DIESEL GENERATOR FUEL OIL SYSTEM.
- b. j IF the Fuel Oil Transfer Pump is running and Day Tank level is NOT increasing, THEN open 4-70-400A(B) to bypass SV-4-3434A(B).
SV4-3434A(B).
- c. IF the Day Tank level is still NOT E
increasing, THEN verify the Fuel Oil System valve alignment using 4-0P-022, EMERGENCY DIESEL 4OP022, GENERATOR FUEL OIL SYSTEM. W97:/JEE/bsm/ev/ev
Procedure No.: Procedure
Title:
Page: 9 Approval Date: 4-0NOP-023.2 Emen~ency Diesel Generator Failure 8/22/05 STEP ACTION/EXPECTED RESPONSE I [ RESPONSE NOT OBTAINED I 6 Check The Following EDG Local Panel Perform the following: Alarms
- a. Correct cause of abnormal indication.
- 3/2, ENGINE OVERSPEED TRIP - CLEAR -
- 1) IF the cause is an overspeed trip,
- 4/2, LUBE OIL HIGH TEMPERATURE THEN relatch the overspeed trip TRIP - CLEAR
- lever AND pull the lever a second time to ensure full engagement.
- 4/4, EXHAUST HIGH TEMPERATURE TRIP - CLEAR
- b. IF cause can NOT be identified or corrected, THEN perform the following:
- 4/5, COOLING WATER HIGH TEMP TRIP- TRIP -
CLEAR 1) IF the Unit Supervisor grants permission to continue starting the
- 5/2, MAIN MANIFOLD LUBE OIL LOW affected generator, THEN go to PRESSURE TRIP - CLEAR -
Step 7.
- 2) IF local start of second emergency
- 5/5, COOLING WATER LOW PRESSURE TRIP - CLEAR diesel generator is required, THEN return to Step 1.
- 6/1, ENGINE HIGH VIBRATION TRIP- TRIP -
- 3) IF the Unit Supervisor does NOT CLEAR grant permission to continue starting the affected diesel generator, THEN
- 6/2, PISTON COOLING OIL LOW return to procedure and step in PRESSURE TRIP - CLEAR effect.
- 6/4, CRANKCASE HIGH PRESSURE TRIP
- CLEAR W97:/JEE/bsm/ev/ev W97:/ J EE/bsm/ev/ev
Procedure No.: Procedure
Title:
Page: 10 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 STEP ACTION/EXPECTED RESPONSE RESPONSE RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED I 7 Check Affected Diesel Generator Relay Status Perform the following:
- Loss of Field Relay (140) - NO FLAG
- FLAG
- a. Report relay flag status to the RO.
- Voltage Balance Relay (160) - NO FLAG
- b. Notify the RO that assistance is required
- Reverse Power Relay (132) - NO FLAG to repair affected diesel generator.
- Overcurrent phase A (151V PH A) - NO -
- c. IF jf local start of second emergency FLAG diesel generator is required, THEN return to Step 11..
- Overcurrent phase B (151V PH B) - NO -
FLAG d. IF local start of second emergency jf diesel generator is NOT required, THEN
- Overcurrent phase C (151V PH C)- NO return to procedure and step in effect.
FLAG
- Differential phase A (187G PH A) - NO -
FLAG
- Differential phase B B (187G PH B) - NO FLAG
- Differential phase C (187G PH C) - NO -
FLAG 8 Verify Start Failure Annunciator - OFF Push alarm reset pushbutton. CAUTION The affected EDO EDG may Auto-start when the Lockout Relay is reset. 9 Verify Diesel Generator Lockout Relay - - Perform the following: RESET
- a. Reset Diesel Generator Lockout Relay.
W97:/JEE/bsmfev/ev W97:/JEE/bsm/ev/ev
Procedure No.: Procedure
Title:
Page: 11 Approval Date: 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 I ACTION/EXPECTED ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I CAUTION When the affected Diesel Generator attains voltage and frequency, the EDG output breaker will automatically close and required requIred emergency loads will automatically sequence onto the bus if the sequencer associated with the 4KV Bus is operable. 10 Check Affected Diesel Generator - AUTO STARTED
- a. Affected Diesel Generator - RUNNING
- a. GotoStepil.
Go to Step 11.
- b. Affected EDG output breaker automatically b. GotoStepl2.
Go to Step 12. closed
- c. Required emergency loads automatically c. Observe caution prior to Step 16 and go sequence onto the Bus to Step 16.
- d. Observe caution prior to Step 16 and go to Step 16 11 Locally Start Affected Diesel Generator
- a. Push affected Diesel Generator Engine EMERGENCY START pushbutton
- b. Verify affected Diesel Generator - - b. Perform the following:
RUNNING
- 1) Notify RO that affected diesel generator will not start.
- 2) Continue attempts to start diesel generator(s) as directed by RO.
- 3) ReturntoStepl.
Return to Step 1.
- c. Verify EDG output breaker automatically c. GotoStepl2.
Go to Step 12. closes
- d. Verify required emergency loads automatically sequence onto the Bus
- e. Observe caution prior to Step 1616 and go to Step 16 16 W97:/JEE/bsm/ev/ev
Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 12 Approval Date: 4-ONOP-023.2 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 STEP ACTIONIEXPECTED RESPONSE ACTION/EXPECTED I I RESPONSE NOT OBTAINED 12 12 Check Affected Diesel Generator
- a. At the Engine Control Panel, verify affected a. Adjust Governor Control Switch.
diesel generator speed - BETWEEN 880 AND 920 RPM
- b. On Generator Control Panel, verify affected b. Adjust Governor Control Switch.
diesel generator frequency - BETWEEN 58.8 AND 61.2 HZ
- c. Verify affected diesel generator voltage -
- c. Adjust Voltage Control Switch.
BETWEEN 3740 AND 4580 VOLTS 13 13 Notify RO That Affected Diesel Generator Is Available To Power Its Associated Bus 14 14 Obtain Permission From RO To Locally Perlorm the following: Perform Energize 4KV Bus Associated With Running Diesel Generator a. IF 4KV bus will be energized from f Control Room, THEN place affected diesel generator Local/Normal Selector Switch to NORMAL.
- b. IF 4KV bus can NOT be energized from Control Room, THEN go to Step 15.
- c. IF local start of second emergency diesel generator is required, THEN return to Step 1.
- d. WHEN Unit 4 4KV buses have been energized from Control Room, THEN return to procedure and step in effect.
W97:/JEE/bsm/ev/ev
Procedure No.: Procedure No, Procedure
Title:
Procedure
Title:
Page: Page: 13 13 Approval Approval Date: Date: 4-ONOP-023.2 4-0NOP-023.2 Generator Failure Emergency Diesel Generator 8/22/05 8/22/05 I STEP I I ACTION/EXPECTED RESPONSE I I RESPONSE II ACTIONIEXPECTED RESPONSE I L RESPONSE NOT NOT OBTAINED OBTAINED 15 Locally Energize DesiredDesired 4KV Bus
- a. Verify affected diesel generator Master a. Place affected diesel generator Master Control switch in LOCAL Control Switch in LOCAL.
- b. Verify affected diesel generator Isolation b. Place the affected diesel generator switches (Engine Control Cubicle) are Isolation switches to ISOLATE.
Isolation ISOLATE positioned to ISOLATE
- c. Place synchronizing switch for diesel output breaker to be closed to ON
- d. Have the RO verify all breakers on associated 4KV bus - OPEN-
- e. At EDG Electrical Control Panel, close diesel generator output breaker
- f. Place appropriate synchronizing switch to OFF AND remove handle
- g. Check diesel generator output breaker status - CLOSED W97:/JEE/bsm/ev/ev W97:/JEE/bsm/ev/ev
Procedure No.:
Title:
Procedure
Title:
Page: Page: 14 Approval Date: Approval Date: 4-ONOP-023.2 4-0NOP-023.2 Emergency Diesel Generator Failure 8/22/05 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I
. CAUTION Operating the isolation switches with the EDG loaded, will trip the EDG.
16 16 Maintain Running Diesel Generator(s)
- a. Verify voltage - BETWEEN 3740 AND 4580
- a. Adjust Voltage Adjust Control Switch.
VOLTS
-VOLTS
- b. Verify frequency - BETWEEN 58.8 AND
- b. Adjust Governor Control Switch.
61.2HZ
- c. Verify load - LESS THAN 2500 KW
- c. Notify RO to shed non-essential loads. I
- d. Operate diesel generator controls as directed by the RO 17 17 Obtain Permission To Transfer Affected Perform the following:
Emergency Diesel Generator Operation To Control Room a. IF Control Room has been evacuated, THEN return to 0-ONOP-105, CONTROL ROOM EVACUATION.
- b. Return to Step 16.
18 18 Place Affected Emergency Diesel Generator Master Control Switch In NORMAL 19 19 Check Unit 4 Emergency Diesel Generators - - IF local start of second emergency diesel BOTH RUNNING generator is required, THEN return to Step 1. 1. 20 Return To Procedure and Step In Effect END OF TEXT FINAL PAGE W97:/JEE/bsm/ev/ev
ES-301 Administrative Topics Outline ES-301-l Form ES-301-1 Facility: Turkey Point Units 3 & &4 Date of Examination: 04/2007 Exam Level: RO 2007-30 1 Operating Test Number: 2007-301 Administrative Topic Type Code Describe Activity to be performed (See Note) (See Note) A. l.a Al.a Conduct a 11M l/M Plot CR N CR,N Conduct of Operations - - & 015 K5.05 - 4.114.4) (G2.2.34 - 2.8/3.2, 001 K5.75 - 2.9/3.5 & - 4.1/4.4) Initiate a Containment Purge and Respond to Termination A 1 b Al.b
. S,M Criteria Conduct of Operations
- - & 073 A2.0.2 - 2.7/3.2)
(G2.3.9 - 2.5/3.4, 029 Al.02 - 3.4/3.4 & - Write Equipment Clearance Order to remove equipment from A2 A2.
. CR,P service (Charging Pump)
Equipment Control (G2.2.13 - 3.6/3.8) A.3 A3 Radiation Control A.4 A4 - RO Make Emergency Notifications as Communicator CM C,M Emergency Plan (G2.4.43 - 2.8/3.5) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 55 are required.
- Types and Codes (C) Control Room (5)(S) Simulator (CR) Classroom (D)irect from bank (( 3 S4 for SROs)
- 3 for ROs,
- S4 (N)ew or (M)odified from bank (?1) (~1)
(P)revious 22 Exams (l(::;1 Randomly selected)
ES-301 Administrative Topics Outline Form FOnTI ES-301-1 Facility: Turkey Point Units 33 & 4 04/2007 Date of Examination: 0412007 Exam Level: SRO (I) Operating Test Number: 2007-301 Administrative Topic Type Code Describe Activity to be performed (See Note) (See Note) A. l.a A1.a Verify Adequate Shutdown Margin CR,N Conduct of Operations (G2.1.7 3.7/4.4 & 001 A4.11-3.5/4.1) (G2.1.7-3.7/4.4&001
- A4. 11 3.5/4.1)
Initiate a Containment Purge and Respond to Termination A.l.b A1.b S ,M S,M Criteria Conduct of Operations
- Al.02 - 3.4/3.4 & 073 .0.2 (G2.3.9 - 2.5/3.4, 029 A1.02 - A2.0.2 - 2.7/3.2)
Write Equipment Clearance Order to remove equipment from A.2 A2 CR,P service (Charging Pump) Equipment Control (G2.2.l3 - 3.6/3.8) (G2.2.13 - A.3 Read a Survey Map and Apply RWP requirements CR,M Radiation Control (G2.3.10 - 2.9/3.3) (G2.3.1O - A.4 AA - SRO
- Review NRCOC Notification Form CR,N Emergency Plan (G2.4.43 - 2.8/3.5)
(G2AA3 - NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 55 are required.
- Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank (::;3 4 for SROs)
( 3 for ROs, ::;4 (N)ew or (M)odified from bank (2:1) (1) (l Randomly selected) (P)revious 2 Exams (::;1
Appendix C Appendix C Job Performance Measure Job Performance Measure Form Form ES-C-1 ES-C-I Worksheet Worksheet Facility: Facility: _T-'-Turkey
-"'-urc.,:. k:c:.eLyc.,:. PPoint-"o.: .;. in.: .;. t_ _ _ _ _ _ _ Task No:
Task No: Perform 11IM Perform 1M Plot Plot During During Job Performance Job Performance Task
Title:
Task
Title:
,-,RReactor c.:. e.: .;. ac.: . .:tc.:. o,-r.:Startup Measure No:
.;. S-'-'ta__rt""u=p_ _ _ _ _ _ Measure No: A.1 .a - Conduct A.1.a - Conduct of of Ops Ops 11 (RO)
(RO) 001 K5.75 001 K5.75 (2.9/3.5) (2.9/3.5) KIA
Reference:
K/A
Reference:
015 K5.05 015 K5.05 (4.1/404) (4.1/4.4) Examinee: Examinee: NRC Examiner: NRC Examiner: Facility Evaluator: Facility Evaluator: Date: Date: Method of testing: Classroom
~~~-"'-----------------------------
Simulated Performance Actual Performance Yes
-------------- ---------~~--------
Classroom Classroom Yes Yes Simulator - - - - - - - - - - - Simulator Plant Plant ________
----.:-:::..:.~--
Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: A Unit 3 startup is in progress per 3-GOP-301, "Hot Hot Standby to Power Operation" Operation through Step 5.15.3. The RO is preparing to withdraw control banks to bring the reactor critical. Currently, conditions are as follows: Unit 3 Cycle: 22 Core Burnup: 10,000 MWDIMTU MWD/MTU RCS Pressure: 2235 psig Tavg: 547°F 54rF SR N-31: 340 cps (Highest reading SR) IR N-35: 1 .2E-1 1 amps (Highest reading IR) 1.2E-11 The ECC estimated critical rod position is D/76. 0/76. Assigned Task: Perform aa 11M 1/M plot for the approach to criticality per 3-GOP-301, applying all appropriate precautions. Task Standard: Perform the 1/M 11M plot in accordance with the guidance in 3-GOP-301, Attachment 1. 1. Correctly fill in 3 doubling ~ rd critical data on Page 2 of 3-GOP-301, 3-GOP-301 , Attachment 1. 1. Predict the critical rod height at the 3 rd rod height D-149. 0-149. Stop the startup following the 3 3 doubling. Required Materials: Materials:
- 1. Plant Curve Book 1.
- 2. 3-GOP-301, Hot "Hot Standby to Power Operation Operation"
- 3. Completed
- 3. Completed 0-OSP-040.4, 0-OSP-04004, Estimated Conditions", Attachment 33 "Estimated Critical Conditions, 4.
- 4. Calculator
- 5. Straight
- 5. Straight edge edge
- 6. Pencils
- 6. Pencils General
References:
General
References:
- 1. 3-GOP-301,
- 1. 3-GOP-301, Hot "Hot Standby Standby to to Power Power Operation Operation"
- 2. Plant Curve
- 2. Plant Curve Book Book
- 3. 0-OSP-040.4,
- 3. 0-OSP-04004, Estimated Estimated Critical Critical Conditions Conditions
Appendix C Page 2 of 9 ES-C-I Form ES-C-1 Initiating Cue: You have been directed to perform a 11M 1/M plot for the approach to criticality per GOP-301. GOP-301 The examiner will act as the US and the RO at the controls and will provide cues related to source range count rate, intermediate range power level and rod position at each doubling. When you are ready to begin and when you have completed entering data and plotting the 11M I/M at each doubling, you will announce your readiness to continue by telling the US (examiner) you are ready for the RO at the controls to continue with the next rod pull. Time Critical Task: No Validation Time: 30 minutes
I Appendix C Page 3 of 9 ES-C-I I Form ES-C-1 INSTRUCTIONS TO OPERA OPERATOR TOR OPERATOR: READ TO OPERA TOR: WHEN II TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. II WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, II WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS: A Unit 3 startup is in progress per 3-GOP-301, "Hot Hot Standby to Power Operation" Operation through Step 5.15.4. RD is preparing to withdraw control banks to bring the reactor critical. Currently, conditions are as The RO follows: Unit 3 Cycle: 22 Core Burnup: MWD/MTU 10,000 MWO/MTU RCS Pressure: 2235 psig Tavg: 54rF 547°F SR N-31: 340 cps (Highest reading SR) IR N-35: 1.2E-11 amps (Highest reading IR) D176. The ECC estimated critical rod position is 0/76. INITIATING
!NITIA TlNG CUE:
You have been directed to perform a 11M1/M plot for the approach to criticality per 3-GOP-301. The examiner will act as the US and the RORD at the controls and will provide cues related to source range count rate, intermediate range power level and rod position at each doubling. When you are ready to begin and when you have completed entering data and plotting the 11M IIM at each doubling, you will announce your readiness to continue by telling the US (examiner) you are ready for the RO at the controls to continue with the next rod pull. TERMINATION TERMINA TlON CUE: When you feel that you have satisfactorily completed the assigned task, hand your JPM briefing sheet back to me. Do you have any questions? You may begin.
Appendix C of 9 Page 4 of9 ES-C-I Form ES-C-1 Denote critical steps with a check mark( mark(-Jvf Start Time Review 3-GOP-301 Precautions and Limitations and/or guidance STEP 1 1 : provided on Attachment 1 1 and 0-OSP-040A 0-QSP-040.4 Completed Attachment 3. SAT
- - UNSAT STANDARD*
STANDARD: Reviews 3-GOP-301, P&Ls, Attachment 1, Plant Curve Book and 0-OSP-040.4, Attachment 3. OSP-040A, NOTE NOTE: Verify required materials listed on Page 1 1 of JPM are available to the candidate. Enter correct values on Attachment 1, Row Co, , based on JPM Briefing 0 C STEP 2 : Sheet initial conditions. - - SAT
- - UNSAT Enters following values on Attachment 1 1 page 2 Row Co::
0 C STANDARD: CPS = 340 N-31 == 340 N-35 = 1 .2E-1 1
= 1.2E-11
/'~'" Inform US ready for start of control rod withdrawal to 1 1 51St doubling. STEP 3 : -- SAT
- - UNSAT 55t 1t STANDARD*
STANDARD: Informs US (examiner) ready for start of control rod withdrawal to 1 doubling. Once candidate indicates readiness to begin control rod withdrawal, tell the candidate: CUE* CUE: Rods have been withdrawn to Control Bank D at 4 steps.
. Count rate has stabilized at the first doubling.
N-31 countrate is 700 cps. N-35 is reading 1.3 E-11 amps.
I Appendix CC I Page 55 of Page of 99 I Form ES-C-1 Form ES-C-I I
- 1. Enter
- 1. Enter correct correct values values for CPS, CPS, N-31 N-31 && N-35 N-35 onon Attachment 1, 1, page page STEP STEP 44 SAT 2, Row 2, Row C ,
1 C 1 , based based on on Examiner Examiner Cue. Cue. - - SAT V r/
- 2. Calculate 11M 1/M for N-31 N-31 and N-35 N-35 based based on examiner cue cue and and UNSAT
- - UNSAT enters values on on Attachment 1, 1, page page 2, 2, Row Row C C.
1.
- 3. 1/M vs. rod position on Attachment 1, Plot 11M 1, page 3.
- 4. Make prediction of critical rod height and enters predicted values on Attachment 1, page 2, Row C .1.
1 C
- 5. Inform US ready for control rod withdrawal to 22 nnd d
doubling.
- 1. Enters following values on Attachment 1, page 2, Row C :
1 C1: CPS == 680 N-31 == 700 N-35 = I .3E-1 1
= 1.3E-11 Actual Rod Height, Bank = = D & Step = = 4
- 2. Calculates & enters following values on Attachment 1, page 2, Row 11 1/M:
C C 1IM: Column II (N-31) = 0.48 0.48-0.49
- 0.49 STANDARDS: Column II (N-35) = = 0.92 - 0.93
- 3. On Attachment 1, page 3, plots N-31 line from upper left corner to intersection of 0.48-0.49 & D/4.
N-35 line from upper left corner to intersection of 0.92-0.93 & D/4. D14.
- 4. On Attachment 1 1 ,page 3, extends N-31 & N-35 lines and determines neither crosses x-axis within confines of graph. On Attachment 1, page 2, enters Predicted Rod Height >D/230 in column II (N-31) and >D/230 in column II (N-35).
nd 2
- 5. Informs US (examiner) ready for control rod withdrawal to 2 nd doubling.
NOTE: Only standards related to N-31 are critical. Once candidate indicates readiness to resume control rod withdrawal, tell the candidate: CUE Rods have been withdrawn to Control Bank D at 80 steps. CUE:
. Count rate has stabilized at the second doubling.
N-31 countrate is 1400 cps. N-35 is reading 1.4 E-11 amps.
- Appendix C Page 6 of 9 ES-C-I Form ES-C-1
- 1. Enter correct values for CPS, N-31 & N-35 on Attachment 1, page STEP 5 2, Row C 22 , based on Examiner Cue.
C - - SAT vV
- 2. 1/M for N-31 and N-35 based on examiner cue and Calculate 11M - - UNSAT enters values on Attachment 1, page 2, Row C .2.
2 C
- 3. 1/M vs. rod position on Attachment 1, page 3.
Plot 11M
- 4. Make prediction of critical rod height and enters predicted values on Attachment 1, page 2, Row C 22.
C
- 5. Inform US ready for control rod withdrawal to 3rd doubling.
- 1. Enters following values on Attachment 1, page 2, Row C :1 :
1 C CPS = = 1360 N-31 = = 1400 N-35 = 1 .4E-1 1
= 1.4E-11 Actual Rod Height, Bank = D & Step =
= 0 = 80
- 2. Calculates & enters following values on Attachment 1, page 2, Row 11 1/M:
C C Column II (N-31) = 0.24-0.25
= 0.24 - 0.25 Column II (N-35) = 0.85 - 0.86 STANDARD: 3. On Attachment 1, page 3, plots D14 to intersection of N-31 line from intersection of 0.48-0.49 & 0/4 D180.
0.24-0.25 & 0/80. ~-~ N-35 line from intersection of 0.92-0.93 & 0/4 D/4 to intersection of D180. 0.85-0.86 & 0/80.
- 4. On Attachment 1, page 3, extends N-31 & N-35 lines and determines neither crosses x-axis within 0/230.
D/230. On Attachment 1, D/152 (0/140 page 2, enters Predicted Rod Height 0/152 (D1140 - 01160
- D1160 acceptable) in column II (N-31) and >0/230
>D/230 in column II (N-35).
- 5. Inform US (examiner) ready for control rod withdrawal to 3rd doubling.
NOTE: Only standards related to N-31 are critical. Once candidate indicates readiness to resume control rod withdrawal, tell the candidate:
. Rods have been withdrawn to Control Bank D at 120 steps.
CUE. CUE: Count rate has stabilized at the third doubling. N-31 countrate is 2800 cps. N-35 is reading 1.7 E-11 amps.
I Appendix CC Page 77 of 9 I Form ES-C-I ES-C-1 I /J STEP 6
- 1. Enter correct values for CPS, N-31 & N-35 on Attachment 1, page 1.
2, Row CC3 , based on Examiner Cue. 3 -- SAT
,/
1/M for N-31 and N-35 based on examiner cue and
- 2. Calculate 11M - - UNSAT enters values on Attachment 1, page 2, Row C .
3 C3. 1/M vs. rod position on Attachment 1, page 3.
- 3. Plot 11M
- 4. Make prediction of critical rod height and enters predicted values on Attachment 1, page 2, Row C .
3 C3.
- 5. Determine pcm difference between ECC predicted value and 11M l/M predicted value exceeds 300 pcm and startup is required to be stopped.
- 1. Enters following values on Attachment 1, page 2, Row C :1 :
1 C
=
CPS = 2720
=
N-31 = 2800
=
N-35 = 1.7E-11
=
Actual Rod Height, Bank = 0D & Step = 120 =
- 2. Calculates & enters following values on Attachment 1, page 2, Row C
C 1IM: 11 1/M: Column II (N-31) = 0i2 --0.13
= 0.12 0.13 Column II (N-35) = = 0.70 - 0.71
- 3. On Attachment 1, page 3, plots N-31 line from intersection of 0.24-0.25 & 0/80 D/80 to intersection of D/120.
0.12-0.13 & 0/120. D/80 to intersection of 0.85-086 & 0/80 N-35 line from intersection of 0.85-0.86 STANDARD: D/120. 0.70-0.71 & 0/120.
- 4. On Attachment 1, page 3, extends N-31 & N-35 lines and determines N-31 crosses x-axis at approximately 0/160 D/160 (acceptable value 0/150 D1150 - 0/170)
- D!170) while N-35 crosses x-axis
>D/230. On Attachment 1, page 2, enters Predicted Rod Height
>0/230.
>D/230 in column II (N-35).
D/160 in column II (N-31) and >0/230 01160
- 5. 0-OSP-040.4, Attachment 3, or PCB, Section Refers to completed 0-OSP-040A, 2, Figure 5 and notes ECC predicted critical IRW at 0/76 D/76 is 675
=
D/160 IRW = 325 pcm. When compared to the 11M pcm while 0/160 IIM predicted critical rod height worth, the difference exceeds 300 pcm requiring at least Shift Manager permission to continue.
- 6. Informs US (examiner) he recommends discontinuing the reactor startup until Shift Manager permission to continue is obtained.
NOTE: criticaL Only standards related to N-31 are critical. Terminating Candidate recommendation to discontinue reactor startup until STOP Cue: Shift Manager permission to continue obtained. Stop Time - - - -
Appendix C C Page 8 of of9 9 Form ES-C-I ES-C-1 Verification of Completion A.1 .a Conduct Job Performance Measure No. .-:A.-:.:....:.1.-:.;.a=---.
- t-=o-,-f-=0-L:p..::.s.-:1~(>..:...R.:...:O:...J.)'---
.: .C. : .o,;. :nd::;:. .u: :.;c:.,:of Ops 1 (RO) _ _ _ _ _ _ _ _ _ _ _ _ __
Examinee's Examinees Name: Examiner's Examiners Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: r~-----------------------------------------------------------------------------
Response
Result: Satisfactory/Unsatisfactory Examiners signature and date: Examiner's
JPM BRIEFING SHEET INITIAL CONDITIONS: A Unit 3 startup is in progress per 3-GOP-301, "Hot Hot Standby to Power Operation" Operation through Step 5.15.4. The RO is preparing to withdraw control banks to bring the reactor critical. Currently, conditions are as follows: Unit 3 Cycle: 22 Core Burnup: 10,000 MWD/MTU RCS Pressure: 2235 psig Tavg: 54rF 547°F SR N-31: 340 cps (Highest reading SR) lR N-35: IR 1 .2E-1 1 amps (Highest reading IR) 1.2E-11 D176. The ECC estimated critical rod position is D/76. INITIATING /NITIA TlNG CUE: You have been directed to perform a 11M1/M plot for the approach to criticality per 3-GOP-301. The examiner will act as the US and the RO at the controls and will provide cues related to source range count rate, intermediate range power level and rod position at each doubling. When you are ready to begin and when you have completed entering data and plotting the 11M IIM at each doubling, you will announce your readiness to continue by telling the US (examiner) you are ready for the RO at the controls to continue with the next rod pull. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Procedure No.: Procedure
Title:
Page: Page: 76 Approval Date: 3-GOP-301 Hot Standby to Power Operation 2/16/06 ATTACHMENT 11 ATTACHPvIENT (Page 1 1 of 3) of3) INVERSE COUNT RATE DATA AND PLOT SHEET Unit Number: _ _ _ _ _ _ _ __ Time - - - - - - - Completed By: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date - - - - - - - Estimated Critical Rod Position: Bank_____________________ Bank._ _ _ _ _ _ _ __ Steps _ _ _ _ _ __ Directions:
- 1. Note AND record the initial counts/current. The highest reading Source Range AND highest reading Intermediated Range channels should be used.
- 2. Pull control rods until the count rate approximately doubles.
- 3. Wait one minute (minimum), THEN record the actual count rate AND rod height. Calculate and 1/M below land on the graph. Predict the critical rod height AND record below.
record 11M
- 4. Repeat Steps 2 and 33 until 1JM-. 125 (3 doublings). Follow the guidance of Precautions and IIM-.I25 Limitations Section, Subsection 4.27, prior to continuing.
r -. - -- - '_. - -,'- - -NO"'fE"'-'- NOTE - I1 I If there a significant difference between the Source Range and Intermediate Range I I predicted critical rod height, the Source Range should be used. I L _______________________ II a a a - a a a a
- 5. Continue repeating Steps 2 and 33 until criticality is achieved.
W2003:TNMlld/mr W2OO3:TNM/d/mro/mraImr
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 77 77 Approval Approval Date: Date: 3-GOP-301 3-GOP-301 Hot Standby Hot Standby to Power Operation to Power Operation 2/16/06 2/16/06 ATTACHMENT 11 ATTACHMENT (Page 22 of 3) of3) INVERSE COUNT RATE DATA AND PLOT SHEET INVERSE I
- - - - - - - - -.-NO~
- a
-'.- - - - -.- - _.- - --II a a II not achieved prior to de-energizing the Source Range, the Intermediate If criticality is not be used for predicting the critical rod height.
should be II Range channel reading the highest should II..- _ _ _ _ _ _ . . _ _. _ _ _ , _ _ . _ _ _ ." _ _ ._ _ _ _ _ I
. a a - - .
Count Rate 1JM 11M Actual Predicted Doubling (CPS/Amps) (Co/Ct) (CO/Ci) Rod Height Rod Height No. CPS N-3( )) N-3( )) I II Bank Step I II Co 0 C 1.0 1.0 A 00 Cl CI C 22 C C3 3 C C 44 C C 55 C C6 6 C C 77 C Cg 8 C C 99 C CIO 0 Cl W2003:TNMlld/mr W2003:TNM/ld/mrqirnrgImr
ProcedureNo.: Procedure No.: )) ProcedureTitle Procedure
Title:
) Page: Page: )I 78 ApprovalDate: Approval Date: 3-GOP-301 3-GOP-301 Hot Standby Hot Standbyto to Power Power OperationOperation 2/16/06 2/16/06 __i_1 ATTACHMENT I1(Page ATTACHMENT (Page33of3) of 3) 1 MM 11M Vs 1/M Vs RodRod Position Position RodPosition Rod Position I'i7r INVERSE COUNT INVERSE COUNTRATE RATEDATA DATAAND ANDPLOT PLOTSHEET SHEET n .r art 1.0 1.0 1.0 1.0 0.9 0.9 0.9 0.9 0.8 0.8 * . . . . . . . . . . . . . . . 0.8 0.8 0.7 0.7
- 0.7 0.7 0.6 0.6 0.6 0.6 0.5 0.5 0.5 0.5
* ..... * .... o * *
- 0.4 0.4 0.4 0.4 0.3 0.3 V 0.3 0.3 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1 0.0 0.0 0.0 0.0 111111111111111111111111111,,~~f,,1111111111111111l111111I1 1111111111111111111111111,,~~fl,1111111111111111111111111II 00 40 40 8080 120 120 160160 200 200 230 230 00 40 40 80 80 120 120 160 160 200 200 230 230 F-020 - Rev.
F-020 Rev.00(2/3/03 {2/3/03*
*-GOP-301
-GOP-3O1 I I I I111111111111111111111111 I
I I ~ "~~r,,lllllllllllllllllllllllill CBB IIII III I i I I I I IIIIIIIIIIIIIIIIIIIIIIII"~~?'IIIIIIIIIIIIIIIIIIIIIIII1III1 I I I I CBD I I I I i I it 00 40 40 80 100 80 100 128 128 160 160 200 200 230 230 00 4040 80 120 160 160 200 200 230 230 80 120 W2003:TNM/ld/mrg/mrg W2003:TNM/Id/mrg/mrg
Procedure No No. ) Title Procedure
Title:
) Page Page:
-)
Approval Date 0-OSP-040.4 0-OSP-040A Estimated Critical Conditions 5/8/01 ATTACHMENT 3 (Page 11 of 1) ACCEPTANCE CRITERIA WORKSHEET ** From 1000 pcm early 500 pcm early 400 pcm early 300 pcm early 200 pcm early pcm late 200 pcmlate 300 pcm late 400 pcm late 500 pcm late 1000 pcm late Attachment 1I Rod Worth in Pcm Estimated Rod Position From PCB The critical rod position is allowed to vary from the estimated critical rod position by
+/-200 pcm. If greater than +/-200 pcm, Reactor Engineering shall reView review the calculations within 55 working days.
If after the 3rd doubling the projected critical rod position deviates from the ECC rod position by greater than 300 pcm but less than or equal to 400 Eee pcm, permission to pull to critical shall be obtained from the Nuclear Plant Supervisor or his designee. If after the 3rd doubling the projected critical rod position deviates from the EeeECC rod position by greater than 400 pcm but less than or equal to 500 pcm, permission to pull to critical shall be obtained fro*mfrom the Reactor Engineering Supervisor or his designee. If after the 3rd doubling the projected critical rod position deviates from the EeeECC rod position by greater than 500 pcm but less than 1000 pcm, the control banks shall be reinserted and the Eee ECC calculation reevaluated. If the error cannot be determined, permission of the Operations Manager and the Reactor Engineering Supervisor or their designees must be obtained prior to making the reactor critical under l/M plot. the guidance of the 11M Early Reactivity means adding the number of pcm (i.e., 200 pcm, 300 pcm, etc.) to the estimated rod worth of the HZP estimated critical rod Early position. Late reactivity means subtracting the number ofpcm of pcm from the estimated rod worth of the HZP estimated critical rod position. W97:GLM/bc/Ir/mrg W97:GLM/bc/lr/mrg
Procedure No,: No.: Procedure
Title:
Page: 76 Approval Date: 3-GOP-301 Hot Standby to Power Operation 2/16/06 ATTACHMENT 11 (Page 11 of3) of 3) INVERSE COUNT RATE DATA AND AN]) PLOT SHEET Unit Number: 3
------~----------
Time xccX:', i'X
çx Completed By: anSI.ui2"u anG( ,tj t:e_ L{ Date ~
x/cxl7< ;<:1
,c/?oc xx:
Estimated Critical Rod Position: Bank,--_~D"",- Bank____________________ _ _ _ ___ Steps 70 7, Directions:
- 1. Note AND record the initial counts/current. The highest reading Source Range AND highest reading Intermediated Range channels should be used.
- 2. Pull control rods until the count rate approximately doubles.
- 3. Wait one minute (minimum), THEN record the actual count rate AND rod height. Calculate and 1IM below land on the graph. Predict the critical rod height AND record below.
record 11M
- 4. Repeat Steps 2 and 33 until IIM-.125 1/M-. 125 (3 doublings). Follow the guidance of Precautions and Limitations Section, Subsection 4.27, prior to continuing.
r - -
- - - - - -NO-fE' NOTE - - - - - - - - - --)1 I If there a significant difference between the Source Range and Intermediate Range III I predicted critical rod height, the Source Range should be used. I L
L.. _______________________ JI
- 5. Continue repeating Steps 2 and 33 until criticality is achieved.
W2003:TNMlld/mr Imr W2003:TNM/ld/mro/mra
Procedure No.: Procedure
Title:
Page: 77 Approval Date: 3-GOP-301 Hot Standby to. to Power Operation 2/16/06 ATTACHMENT 11 (Page (page 2 of of3)3) INVERSE COUNT RATE DATA AND PLOT SKEET SHEET r--"':::_"
- ~,,:- ':-~'.-" _::. _ .."._."._:'_." -,. _ . " _::::- :_:,._,.. _."
NO~ NOTE
~
II If criticality is not achieved prior to de-energizing the Source Range, the Intermediate I Range channel reading the highest should be used for predicting the critical rod height. *
.'--.,. _'(._.: _:::_.:::_r.:.,_.,._::,_"
..; : ::a: : .: ..,;::_::."_, '_"'_'::::__\1':__::'_
fl ;,., ,:. : _, ~ ._,*._",,:_;:.1J Count Rate 1JM 11M Actual Predicted Doubling (CPS/Amps) 1
/
0 (C
) C (CO/Ci) Rod Height Rod Height No. CPS N-3(i)
N-3(r) N-3() N-3(5) I . II Bank Step I II 0 C Co 340 340 34() L1.£-H 1.0 1.0 A 0 .- C Clj ~,.3 E- II 0,92. 4-4 >Di2?>Q
>D1230 >D)1Z3O 12-36 bf'>>
(,() 700 7CC) E-1t OA-9 049 D C) 22 C C (..%0 (.Y,O C40C) 1,4 i400 i,4i(E:-I( (j,24-o24- oB(, D-S" D C) 130 Df.l52, Df6z >Dj?:~C
>Dt?3c 3
C C3 2.120 2??O 23O0 L1
'2-800 E-f~ 0_l2 4.7&i4 tZ 0, 071 "Ii DC) '~20 iZO Dllw D/16() ;>D/z30 ;>D/zo 4
C C4 Cs 6 C C6 77 C C Cg 8 C 99 C C CIO 0 Cl W2003:TNMlld/mr W2flflTNMIHImrnImrn Imr
ProcedureNo. Procedure No. \1 ProcedureTitle: Procedure
Title:
) Page: Page: ) 7b 7b ApprovalDate: Approval Date: 3-GOP-301 3-GOP-301 HotStandbyto Hot Standby to Power PowerOperation Operation 2/16/06 2/16/06
-'M 11M Vs 1/M Vs Rod Rod Position Position ATTACHMENT ATTACHME NT I1(Page (Page33ofon)
- 3) RodPosition Rod Position 1 INVERSE COUNT INVERSE COUNTRATE RATEDATA DATAAND ANDPLOTPLOTSHEET SHEET d '1ri
--wr rr 1.0 \ cten ørt,rirl 1flNI T 0.9 IWIWIUll4111llh1IilWf{
l * ........ l {ffflThJflJflflffl llf[Iflfl 1.0 1.0 0.9 0.9 0.8 0.8 0.8 0.8 0.7 0.7 IF * ... 0.7 0.7 0.6 0.6 0.6 0.6 0.5 0.5 0.5 0.5
. . - .. . - .. -0
- _ *
* ... . .. * .. . ....... . . * * * * * '0 0.4 0.4 0.4 0.4
* . * ..... * .... * * * * -0
- _ *
- 0.3 0.3 0.3 0.3 0.2 0.2 0.2 0.2 0.1 0.1 0.0 0.0 00 40 40 fi 8080 120 120
* .0 * *
- IIIIIIIIIIIIIIIIIIIIIIIIIII'I~~~I,IIIIIIIIIIIIIIIIIIIII1II1 11111111111 I I 1111111111 Ii i 11111 I I 111111111111111 160 160 200 200 230 230 00 I . .. * ..
11111 I 11111 liii! I III liii 4040 80 80 120 120 I 1111111111111111111111111,,~~f,,111111111111111111111111II1 1111111111111 11111111 I 11111 160 160 200 200 230 230 iLl 0.1 0.1 0.0 0.0 F*020 -Rev. F-020 Rev.0 0(2/3/03 -
'-GOP-301 (213/03 - -GOP-301 1)11111111111111 IllIlli ~ 11~~f,,11111111111111111111111111 I111111111111111111111111 CBB 111111 II,lIIIIIIIIIIIIIIIIIIIIIIIII IIIIIIIIIIIIIIIIIIIIIIII'I~~?I,IIIIIIIIIIIIIIIIIIIIIIII1III IIIIIIIIIIIIIIII i CBD IIIIIIIIIIIIIIIIII, IIIIIIIIIIIIIIIIIIII Jill i
00 4040 8080 100 100 128 128 160 200 230 160 160 200 230 00 40 40 80 80 120 120 160 200 200 230 230 W2003:TNM/ld/mrg/mrg W2003:TNMIId/mrg/mrg
1 Procedure 1\ i I Page: Page: } Procedure
Title:
29 Approval Date Date 0-OSP-040.4 Estimated Critical Conditions 5/8/01 ATTACHMENT 3 (Page 11 of ofi) 1) ACCEPTANCE CRITERIA WORKSHEET ** From 1000 pcm pcm early 500 pcm early 400 pcm early 300 pcm early 200 pcm early 200 pcm late 300 pcm late 400 pcm pcrn late 500 pC11llate pcm late 1000 pcm late late Attachment_1I Attachment Rod Worth in Pcm Pcm 1675 H75 1075 975 875 815 075 475 375 215 275 1'15 ~ Estimated Rod Estimated Position From L.. Position From PCB ctco C/i CO D(Z3 D{Z3 D/35 Df 35 D/45 D/S6 Dl7 D/7-6 D/(2i D/(Zi D(i49 Df49 '0/1""1-0
/to D!iB7-D/iE ,-
PCB The critical rod position is allowed to vary from the estimated critical rod position position by
+/-200 pcm. If greater than +/-200 pcm, Reactor Engineering shall review the calculations within 55 working days.
If after the 3rd 3rd doubling the projected projected critical rod position position deviates from the ECC rod position position by greater than than 300300 pcm but less than than or equal to 400 pcm, permission to pull to critical shall shall be obtained obtained from the Nuclear Plant Supervisor or or his designee. If If after the 3rd 3rd doubling the projected projected critical critical rod position position deviates from the the ECC ECC rod position position by by greater than 400 400 pcm but but less less than oror equal equal to to 500 pcm, permission 500 pcm, permission to to pull to to critical critical shall shall be be obtained from the the Reactor Reactor Engineering Engineering Supervisor Supervisor or or his his designee. designee. If If after the the 3rd 3rd doubling thethe projected projected critical critical rod rod position position deviates deviates from the the ECC ECC rod rod position position by by greater than than 500 500 pcm pcm butbut less less than 1000 1000 pcm, pcm, thethe control control banks banks shall shall be be reinserted reinserted and and the the ECC ECC calculation calculation reevaluated. If If the the error error cannot cannot bebe determined, permission permission of of the the Operations Manager Manager and and the the Reactor Engineering Engineering Supervisor Supervisor or or their their designees designees must be obtained must be obtained prior prior to to making making the the reactor reactor critical critical under under the the guidance guidance ofof the 11M plot. the l/M plot.
- Early Early Reactivity Reactivity means means adding adding thethe number number of of pcm pcm (i.e.,
(i.e., 200 200 pcm, pcm, 300 300 pcm,pcm, etc.) etc.) toto the the estimated estimated rod rod worth worth of of the the HZP HZP estimated estimated critical critical rod rod position. position. Late Late reactivity reactivity means means subtracting subtracting the the number number of ofpcm pcm from the the estimated estimated rod rod worth worth of of the the HZP HZP estimated estimated critical critical rod rod position. position. W97:GLM/bc/lr/mrg W97:GLM/bcllr/mrg
Appendix C a Job Performance Measure Form ES-C-I ES-C-1 Worksheet Facility: Turkey Point_ _ _ _ _ _ _ _T_ur_k_e..<...y_P_o_in_t Task No: Verify Adequate Shutdown Job Performance A.1 A.1.a .a - Conduct of Ops 11 Task
Title:
~M:..:::a~rgz.:.in:....:....._-,------.,-- Margin _____ Measure No: (SRO) _ _ _ _ _ _ _ __
-l.;(S::..:R..:..0=.L)
G2.1.7 (3.7/4.4) K/A KIA
Reference:
001 A4.11 (3.5/4.1) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Classroom
~~~~~---------------------------
Simulated Performance - - - - -Yes Actual Performance Classroom - - - - . . . : .Yes Classroom Yes Simulator - - - - - - - - - Simulator Plant - - - - - - - Read to the examinee: II will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- 1. The time is 0800. At 0700, the Unit 4 reactor tripped from 100% power due to loss of an SGFP. All rods inserted.
- 2. 4-EOP-ES-0.1 4-EOP-ES-O.1 is in use awaiting completion of step 23 (shifting slg s/g feedwater from AFW to standby feedwater).
- 3. All 3 Unit 4 RCPs are in use
- 4. 4A & 4B charging pumps are in service with letdown orifices isolation valves CV-4-200A & B open
- 5. RCS Tavg =
= 547 OF °F being maintained on the atmospheric steam dumps
- 6. All Unit 4 4kV buses are on offsite power
- 7. Current Unit 4 Cycle 23 burnup = MWD/MTU
= 4522 MWDIMTU
- 8. Current Unit 4 RCS boron concentration as of 0600 =
= 1022 ppm
- 9. Reactor Engineering informs you that the reactivity worth of Xenon can not be easily determined.
Assigned Task: The Shift Manager has directed you, as Unit 4 Unit Supervisor, to verify adequate shutdown margin per 0-OP-028.2, "Shutdown Shutdown Margin Calculation" Calculation for maintaining Unit 4 at hot standby (54rF) (547°F) for 0800 tomorrow. Task Standards:
- 1. Required RCS boron concentration is determined based on projected plant conditions
- 2. Required RCS boron concentration is compared to the existing boron concetration to determine if adequate shutdown margin exists.
- 3. If adequate shutdown margin does not exist, directs appropriate corrective action to establish adequate shutdown margin for projected plant conditions.
Appendix C Page 2 of 10 ES-C-I Form ES-C-1 Required Materials: Pant Curve Book
- 1. Unit 4 Plant Reactor Trip Response"
- 2. 4-EOP-ES-O.1, "Reactor Response O-OP-028.2, "Shutdown
- 3. 0-OP-028.2, Shutdown Margin Calculation" Calculation General
References:
- 1. Unit 4 Plant Curve Book 4-EOP-ES-O.1, "Reactor
- 2. 4-EOP-ES-0.1, Reactor Trip Response"
Response
O-OP-028.2, "Shutdown
- 3. 0-OP-028.2, Shutdown Margin Calculation" Calculation
- 4. Technical Specifications Initiating Cue:
The Shift Manager has directed you, as Unit 4 Unit Supervisor, to verify adequate shutdown margin per Shutdown Margin Calculation" O-OP-028.2, "Shutdown 0-OP-028.2, Calculation for maintaining Unit 4 at hot standby (547°F) for 0800 tomorrow. Time Critical Task: No Validation Time: 40 minutes
I Appendix C Page 3 of 10 ES-C-I I Form ES-C-1 INSTRUCTIONS TO OPERA OPERATORTOR READ TO OPERA TOR: WHEN II TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. II WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, II WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! INITIAL CONDITIONS:
- 1. The time is OBOO.
0800. At 0700, the Unit 4 reactor tripped from 100% power due to loss of an SGFP. All rods inserted. s/g feedwater from AFW to standby
- 2. 4-EOP-ES-0.1 is in use awaiting completion of step 23 (shifting slg feedwater).
- 3. All 3 Unit 4 RCPs are in use
- 4. 4A & 484B charging pumps are in service with letdown orifices isolation valves CV-4-200A & B open
- 5. RCS Tavg =
= 547 OF
°F being maintained on the atmospheric steam dumps
- 6. All Unit 4 4kV buses are on offsite power
- 7. Current Unit 4 Cycle 23 burnup =
= 4522 MWDIMTU MWD/MTU B. Unit.4 RCS boron concentration as of 0600
- 8. Current Unit4 =
= 1022 ppm
- 9. Reactor Engineering informs you that the reactivity worth of Xenon can not be easily determined.
INITIATING
!NITIA TlNG CUE:
The Shift Manager has directed you, as Unit 4 Unit Supervisor, to verify adequate shutdown margin per 0-OP-02B.2, 0-OP-028.2, "Shutdown Calculation for maintaing Unit 4 at hot standby (547°F) until OBOO Shutdown Margin Calculation" 0800 tomorrow. TERMINATION TERMINA TlON CUE: When you feel that you have satisfactorily completed the assigned task, hand your JPM briefing sheet back to me. Do you have any questions? You may begin. EXAMINER NOTES:
- 1. This task is to be performed in the classroom.
4-EOP-ES-0.1 and 0-OP-028.2 should be provided to the student along with the JPM
- 2. Copies of 4-EOP-ES-O.1 Briefing Sheet
- 3. Provide a copy of the current Unit 4 Plant Curve Book after the candidate has indicated a need to use it (the ILC frozen version does not contain data appropriate to the completion of this task).
taSk).
- 4. Provide a copy of PTN Technical Specifications if the candidate indicates a need to use it.
Appendix C Page 4 of 10 ES-C-I Form ES-C-1 Denote critical steps with a check mark( mark(J vf Start Time O-OP-028.2 and: Obtain 0-OP-028.2 STEP 11 : -- SAT
- 1. Check procedures for active OTSCs
- 2. Review Precautions & Limitations - - UNSAT
- 3. Determine section 7.2 applies requiring completion of Attachment 2
- 4. Initiate use of Attachment 2 O-OP-028.2 and:
Obtains 0-OP-028.2
- 1. Checks procedures for active OTSCs STANDARD: 2. Reviews Precautions & Limitations
- 3. Determines section 7.2 applies
- 4. Initiates use of Attachment 2 O-OP-028.2 Attachment 2 Record reference conditions on 0-OP-028.2 STEP 2 : - - SAT (attachment step 1)
- - UNSAT
/r-" Records the following reference conditons on 0-OP-028.2 O-OP-028.2 Att. 2:
- 1. Unit =
= 4 (from initial conditions)
STANDARD: 2. Cycle == 23 (from initial conditions)
- 3. Shutdown = todays date & 0700
= today's
- 4. Cycle burnup = = 4522 MWD/MTU (from initial conditions)
I Appendix C Page 5 of 10 I ES-C-I I Form ES-C-1 STEP 0-OP-028.2 Attachment 2 Record calculation point conditions on 0-OP-02B.2 3 -- SAT (attachment step 2)
- - UNSAT 0-OP-028.2 Att. 2:
Records the following reference conditons on 0-OP-02B.2
- 1. Calculation point = 0800 tomorrow (from initiating cue)
= OBOO
- 2. Time since shutdown = I + 24 =
= 1 = 25 hr (from initial conditions)
- 3. Most recent RCS boron concentration = = 1022 ppm, sample date STANDARD: and time = = current date & 2 hr ago (from initial conditions)
- 4. Average RCS temperature at calculation point time = 54YOF 547°F (from initial conditions)
- 5. Mode = = Mode 3, Hot Standby, RCS temperature 350-547°F
- 6. Number of control rods not fully inserted = = 0 (from initial conditions)
If asked as SM, state that US should anticipate maintaining current CUE: RCS conditions for the next 24 hrs. Shutdown margin should be ReS verified adequate over that time span.
Appendix C Page 6 of 10 Form ES-C-I ES-C-1 Review NOTES prior to 0-OP-028.2 Attachment 2 Step 3 STEP 4
- - SAT Determine minimum required RCS boron concentration on 0-OP-028.2 Attachment 2
- - UNSAT (attachment step 3)
STANDARDS: 1. Reviews NOTES prior to 0-OP-028.2 Attachment 2 Step 3 and determines method for determining Minimum Shutdown Boron Concentration (MSBC) (uses conservative method outlined in NOTES)
- 2. Determines MSBC:
- a. Records minimum average RCS temperature over the next 24 hrs ==547°F (from initial conditions)
- b. Records RCS temperature statepoint/curve used for calculating
=
MSBC 547°F (from initial conditions)
- c. Obtains U4 Plant Curve Book (PCB) and finds Sect. III, Ill, Fig. 5A, Minimum Shutdown Boron Concentration (ppm) vs RCS "Minimum Temperature as a Function of Burnup (ARI-1, No Xe) Xe)" table v d. Using the "conservative" conservative (interpolate burnup only) method:
1)) Located burnup values (4000 & 6000 MWD/MTU) that 1 bound the burnup provided in the initial conditions (4522 MWD/MTU) along top row of table.
- 2) Located current moderator temperature (547°F) found in far left column of table.
- 3) Located intersection of these values on table (1119 ppm &
995 ppm) and interpolates between them
-[(11 19-995) x ((4522-4000)/(6000-4000))] =
1119 -[(1119-995) = 1119 --[124x0.261)}= = [124 x 0.261)] 1087 ppm (+/- 15 ppm)
- e. Confirms RCS temperature =547°F used throughout the
=
MSBC calculation CUE-CUE: As Shift Manager direct use of the preferred and recommended (conservative) method to determine MSBC.
- 1. Verify Unit 4 Plant Curve Book made available once candidate identifies need to use it.
- 2. In U4 PCB Sect III Figure 5A table, candidate should read NOTE: MWD/MTU columns 547°F row with 4000 & 6000 MWOIMTU intersection of 547<F and read boron concentrations =
= 1119 & 995 ppm respectively.
By initials in step 3.4, acknowledge Verified By"
- 3. If candidate asks for "Verified request but state that verification can not be provided during JPMs.
II Appendix CC Page 7 of 10 Form ES-C-I ES-C-1 I Review CAUTION & NOTES prior to 0-OP-028.2 Attachment 2 Step 4 STEP 55 -- SAT Using time since shutdown, determine Boron Equivalent of the Xenon Worth. -- UNSAT (attachment step 4) Reviews CAUTION & NOTES prior to 0-OP-028.2 Attachment 2 Step 4 STANDARD: Since time for shutdown margin verification exceeds 20 hours, enters Boron Equivalent of the Xenon Worth = 0 Review NOTE prior to 0-OP-028.2 Attachment 2 Step 4 STEP 6 -- SAT Calculate RCCA correction per 0-OP-028.2 Attachment 2. (attach ment step 5) (attachment - - UNSAT Reviews NOTE prior to 0-OP-028.2 Attachment 2 Step 5 STANDARD: Since all rods inserted (from initial conditions), determines RCCA
=
correction 0 ppm Record corrected MSBC J STEP 7 - - SAT (attachment step 6)
- - UNSAT Since Boron Equivalent of the Xenon Worth & RCCA corrections both STANDARD: equal zero ppm, enters previously calculated MSBC as the corrected MSBC (see JPM step 4 results above)
Determine if shutdown margin is adequate for projected plant STEP 8 : conditions. -- SAT V
./
(attachment step 7) -- UNSAT
- 1. Current RCS boron concentration is compared to the MSBC
- 2. For the initial conditions given, determines adequate shutdown margin does not exist to maintain hot standby for at least 24 hours STANDARD*
STANDARD: since current RCS boron concentration (1022 ppm) is less than MSBC (1087+/-15 ppm)
- 3. Goes to attachment 2 step 9 to determine required boration
Appendix C Appendix C Page 88 of Page of 10 10 Form Form ES-C-I ES-C-1 Report results of Report of shutdown margin verification to shutdown margin to Shift Shift Manager Manager STEPSTEP 99 -- SAT SAT UNSAT UNSAT STANDARD: (examiner) unit 4 shutdown margin not adequate for Informs SM (examiner) STANDARD projected plant conditions.
- 1. As SM acknowledge report of inadequate shutdown margin on Unit 1.
4. CUE:
- 2. As SM, direct candidate to take actions as appropriate to address the inadequate shutdown margin.
Calculate gallons of Acid required to increase the RCS Boron STEP 10 10 : Concentration to greater than or equal to MSBC SAT v Direct RO to initiate boration to raise RCS boron concentration above - - UNSAT minimum required for adequate shutdown margin. Calculates gallons of Acid required to increase the RCS Boron /~"- Concentration to greater than or equal to MSBC as follows: MSBC = = 1087+/-15 ppm, calculates gallons of boric Acid required: 1087+/-15 STANDARDS: ln[(5245 - 1022)/(5245 - 1087)] = 50790 gal x In[(5245 - - ln[(4223)/(4158)] = 50790 gal x In[(4223)/(4158)] 0.01 55 =
= 50790 gal x 0.0155 = 788 gal (acceptable range 605 gal to 971 gal) 3-ONOP-046.1 Directs RO add calculated volume of Boric Acid using 3-0NOP-046.1 Terminating Candidate direction to RO to add calculated volume of Boric Acid STOP Cue: using 3-0NOP-046.1.
3-ONOP-046.1. Stop Time
I[ Appendix C Page 9 of 10 Form ES-C-I ES-C-1 I Verification of Completion Job Performance Measure No. A.1.a - Conduct of Ops 1
- 1 (SRO)
Examinee's Examinees Name: Examiner's Examiners Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: /~--------------------------------------
Response
Result: Satisfactory/Unsatisfactory Examiner's Examiners signature and date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
JPM BRIEFING SHEET INITIAL CONDITIONS:
- 1. The time is 0800. At 0700, the Unit 4 reactor tripped from 100% power due to loss of an SGFP. All rods inserted.
4-EOP-ES-0.1 is in use awaiting completion of step 23 (shifting slg
- 2. 4-EOP-ES-O.1 s/g feedwater from AFW to standby feedwater).
- 3. All 3 Unit 4 RCPs are in use
- 4. 4A & 4B charging pumps are in service with letdown orifices isolation valves CV-4-200A & B open
- 5. RCS Tavg = °F being maintained on the atmospheric steam dumps
= 547 OF
- 6. All Unit 4 4kV buses are on offsite power
- 7. Current Unit 4 Cycle 23 burnup = MWD/MTU
= 4522 MWO/MTU
- 8. Current Unit 4 RCS boron concentration as of 0600 =1022 ppm
=
- 9. Reactor Engineering informs you that the reactivity worth of Xenon can not be easily determined.
INITIATING INITIA TlNG CUE: The Shift Manager has directed you, as Unit 4 Unit Supervisor, to verify adequate shutdown margin per Shutdown Margin Calculation" 0-OP-028.2, "Shutdown Calculation for maintaing Unit 4 at hot standby (547°F) until 0800 tomorrow. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Florida Power & & Light Company Turkey Point Nuclear Plant c-i.c) O-OP-028.2 it c_)
Title:
Shutdown Margin Calculation Safety Related Procedure Responsible Department: Reactor Engineering Revision Approval Date: 10/3/06 94-0031P, 97-1224, 98-1189P, 00-0624, 01-0314, 02-0564P, RTSs94-0031P, RTSs 03-0744P, 04-0663P, 05-0065P, 06-0476, 06-0761P OTSC 0032-99, 0177-06 W97:PS/mrg/mrg/ln W97:PS/mrg/mrg/In
Procedure No.: Procedure
Title:
Page: 2 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 LIST OF EFFECTIVE PAGES Revision Page Date 11 10/03/06 10103/06 2 10/03/06 10103/06 3 10103/06 10/03/06 4 05/25/06 05125106 55 10/03/06 10103/06 66 10/03/06 10103/06 77 05/25/06 88 05/25/06 05125106 99 10/03/06 10103/06 10 10/03/06 10103/06 11 10/03/06 10103/06 12 10/03/06 10103/06 13 10/03/06 10103106 14 10/03/06 10103/06 15 10103/06 10/03/06 16 10103/06 10/03/06 17 10103106 10/03/06 18 10103106 10/03/06 19 10/03/06 10103106 20 10/03/06 10103/06 21 10/03/06 10103/06 W97:.IPH/mra/mro/ln W97:JPH/mr Imr lin
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 33 Approval Approval Date: Date: 0-OP-028.2 0-OP-028.2 Shutdown Shutdown Margin Margin Calculation Calculation 10/3/06 10/3/06 TABLE OF CONTENTS Section igc 1.0 1.0 PURPOSE ..................................................................................................................... 44
2.0 REFERENCES
IRECORDS REQUIRED/COMMITMENT DOCUMENTS REFERENCES/RECORDS DOCUMENTS........ 44 3.0 3.0 PREREQUISITES ....................................................................................................... 55 4.0 PRECAUTIONSILIMITATIONS.............................................................................. PRECAUTIONS/LIMITATIONS 55 5.0 TOOLSIEQUIPMENT....................................... ....................................... SPECIAL TOOLS/EQUIPMENT 77 6.0 ACCEPTANCE CRITERIA CRITERIA....................................................................................... 7 7.0 PROCEDURE 7.1 Modes 1 and 2.................................................................................................... Modesland2 88 7.2 Modes 3, 4 and 5................................................................................................ Modes3,4and5 88 ATTACHMENTS Attachment 11 2 Shutdown Margin Calculation For Modes 11 and 2............................................ 9 Attachment 2 5 Shutdown Margin Calculation for Modes 3, 4 and 5......................................... 16 W97:JPH/mr Imr lin W97IPH/mrri/mrn/In
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 44 Approval Approval Date: Date: 0-OP-028.2 0-OP-02S.2 Shutdown Margin Shutdown Margin Calculation Calculation 5/25/06 5/25/06 1.0 1.0 PURPOSE PURPOSE 1.1 1.1 This procedure This provides administrative procedure provides administrative and and technical technical guidance guidance for: for: 1.1.1 1.1.1 Verifying Shutdown VerifYing Shutdown Margin Margin in accordance with in accordance with Tech Tech Spec Spec 3.1.1.1 3.1.1.1 forfor Modes Modes 1, 1, I 2,33 and 2, and4, and 4, and 1.1.2 1.1.2 Verifying Shutdown Margin in accordance with Tech Spec 3.1.1.2 for Mode VerifYing Mode 5.
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCESIRECORDS REOUIRED/COMMITMENT DOCUMENTS 2.1 References 2.1.1 Technical Specifications 1.
- 1. 3/4.1.1.1
- 2. 3/4.1.1.2
- 3. 3/4.1.3.1
- 4. 3/4.1.3.6
- 5. 3/4.10.1
- 6. 1.25 2.1.2 Plant Procedures
- 1. 0-ADM-554, Plant Curve Book
- 2. 3/4-EOP-ES-0.1, Reactor Trip Response 3/4-EOP-ES-0.l,
- 3. 3/4-EOP-ES- 1.1, SI Termination 3/4-EOP-ES-1.1,
- 4. 3/4-ONOP-028.1, 3/4-0NOP-028.1, RCC Misalignment
- 5. 3/4-ONOP-028.2, 3/4-0NOP-028.2, RCC Position Indication Malfunction
- 6. 3/4-ONOP-028.3, 3/4-0NOP-028.3, Dropped RCC
- 7. 3/4-ONOP-046.1, 3/4-0NOP-046.1, Emergency Boration
- 8. 0-OSP-040.4, 0-OSP-040A, Estimated Critical Conditions 9.
- 9. 0-OSP-040.16, 0-OSP-040 .16, Initial Criticality after Refueling and Nuclear Design Design Verification Verification 10.
- 10. 3/4-OP-046, 3/4-0P-046, CVCS-Boron CVCS-Boron Concentration Concentration Control Control WQ7.IPI-lfmrn/mrn/In W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 5 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/03/06 2.2 Records Required 2.2.1 Completed copies of the below listed items constitute Quality Assurance records and shall be transmitted to QA Records for retention in accordance with Quality Assurance Records Program requirements:
- 1. Attachment 11
- 2. Attachment 2 2.3 Commitment Documents 2.3.1 FPL Calculation Number PTN-ENG-SEFJ-06-013, Turkey Point Unit 33 Cycle 22 Shutdown Margin and Minimum Shutdown Boron Concentration Analysis to Support Implementation of Proposed License Amendment on Inoperable Rod Position Indicator, L-2006-209.
2.3.2 Turkey Point Unit 3, Proposed License Amendment - Inoperable Rod Position Indication, Docket No 50-251, 50-25 1, L-2006-209, dated September 7, 2006. 3.0 PREREQUISITES 3.1 None 4.0 PRECAUTIONS/LIMITATIONS PRECAUTIONSILIMITATIONS r-----------------------, r NOTE I I During Unit 3 Cycle 22, the position of Rod M-6 in Control Bank C will be determined by an alternate method other than the Analog Rod Position Indication System, until the repair of the indication system for this rod is completed. The alternate method to verify verifv Rod M-6 position is an installed Yokogawa recorder to monitor stationary stationaiy gripper coil current. Rod M-6 is verified to be fully withdrawn following a flux map verification and verification the L_______________________ I stationaiy gripper coil does not change state. stationary ~ I L _ _ _ I 4.1 With the shutdown margin less than the applicable value shown in Tech Spec Figure 3.1-1 1, 2, 3 and 4), immediately initiate and continue boration at greater than or equal to (Modes 1,2,3 16 gpm of a solution containing greater than or equal to 3.0 wt % (5245 ppm) boron or equivalent until the required shutdown margin is restored. [Tech Spec 3.1.1.1] 4.2 With the shutdown margin less than 11 % L1kik Ak/k (Mode 5), immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt % (5245 ppm) boron or equivalent until the required shutdown margin is restored. [Tech Spec 3.1.1.2] 4.3 If any control bank is inserted more deeply than the Rod Bank Insertion Limit specified in the Plant Curve Book, Section 7, Figure 3, Rod Insertion Limit vs Thermal Power, restore the control banks to the allowed limits within 11 hour or initiate an emergency boration 3!4-ONOP-046.1, EMERGENCY BORATION, until the required shutdown margin using 3/4-0NOP-046.l, is restored. [TS 3.1.3.6] W97.lPHImrn/mrn/In W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 0-OP-02S.2 Shutdown Margin Calculation 10/03/06 4.4 Shutdown margin shall be determined to be greater than required by Technical Specification 3.1.1.1, Figure 3.1-1: 4.4.1 Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours thereafter while the control rod(s) is inoperable. 4.4.2 When in Mode 11 or 2 with Keff Keff greater than or equal to 11 at least once per 12 hours by verifying control rods are withdrawn beyond their rod insertion limits. 4.4.3 When in Mode 3 or 4 at least once per 24 hours by consideration of the following factors:
- 1. RCS Boron Concentration
- 2. Control Rod Position
- 3. RCS Average Temperature
- 4. Fuel Burnup based on Gross Thermal Energy Generation
- 5. Xenon Concentration
- 6. Samarium Concentration 4.4.4 The required shutdown margin shall be determined with an increased allowance for the worth of ALL immovable or untrippable control rods.
4.5 Attachment 2 is applicable for typical shutdown conditions, that is, all rods expected to be fully inserted. 4.5.1 Calculation/Verification IF a Shutdown Margin CalculationN erification is required for initial startup following refueling or for Low Power Physics Testing, THEN refer to O-OSP-040.16, Initial Criticality After Refueling And Nuclear Design Verification. 4.5.2 Calculation/Verification is required for non-initial cycle IF a Shutdown Margin CalculationNerification startup, THEN refer to O-OSP-040.4, Estimated Critical Conditions. 4.6 IF a Shutdown Margin CalculationNerification is required for any atypical condition (e.g., one or more rods stuck out or stuck partially inserted), THEN consult Reactor Engineering. 4.7 During Unit 33 Cycle 22, the position of Rod M-6 in Control Bank C will be determined by an alternate method other than the Analog Rod Position Indication System, until the repair of the indication system for this rod is completed. The alternate method cannot determine if Rod M-6 is fully inserted following a reactor trip. The alternate method to verify Rod M-6 M -6 withdrawn position is the recorder installed to track parameters of the stationary gripper coil of Rod M-6 control rod drive mechanism. Rod M-6 is verified to be fully withdrawn when its stationary gripper coil has not changed state since the last time it was verified to be fully withdrawn by a flux map. 4.7.1 When calculating shutdown margin on Unit 33 Cycle 22 for Modes 1 1 and 2, Rod M-6 is assumed to be fully withdrawn if its stationary gripper coil has not changed state. 4.7.2 When calculating shutdown margin on Unit 33 Cycle 22 for Modes 3, 44 and 5, Rod M-6 is assumed to be fully withdrawn following reactor trip. Wc7 IPH/mrn/mrn/In W97:JPH/mr Imr lin
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 77 Approval Date: Approval Date: 0-OP-028.2 Shutdown Margin Calculation Shutdown 5/25/06 5.0 5.0 SPECIAL TOOLSIEQUIPMENT TOOLS/EQUIPMENT 5.1 The Plant Curve Book, and/or other approved analysis for the appropriate unit and cycle. 6.0 ACCEPTANCE CRITERIA 6.1 The Shutdown Margin shall be: 6.1.1 Greater than or equal to the value shown in Tech Spec, Figure 3.1-1 for Modes 1, 2,33 and 4, and 2, 6.1.2 Greater than or equal to 11% Ak/k for Mode 5.
% L1k/k W07 IPI-l/mrn/mrn/In W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 5/25/06 7.0 PROCEDURE CAUTION With the Shutdown Margin less than that required by Technical Specification 3.1.1.1 or 3.1.1.2, as applicable, boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt % % (5245 ppm) boron or equivalent shall be immediately initiated and continued until the required shutdown margin is restored. r----------~ru----------- 1 I..__II NOTES I I
- Values determined by precise modeling with neutronics codes are more accurate than I
- first principles implementation of generic curves. Therefore, documented values I supplied by vendor or staff may be substituted for calculated values. I I .* If the actual worth of the inoperable RCCA is NOT known, then the worth of the most I reactive rod should be used. I I ** Obtain as much of the Reference conditions as possible from measurement. I I I Design values for this procedure are required to be taken from either:
I I I - Plant Curve Book, OR I
- Approved analysis I 7.1 Modes 1land2 and 2 7.1.1 IF the unit is in Mode 11 or 2, THEN complete Attachment 1.
7.2 Modes 3, 4 and 55 7.2.1 IF the unit is in Mode 3, 4, or 5, THEN complete Attachment 2. END OF TEXT W97:JPH/mr Imr lin WQ7. IPI-llmrnlmrnlln
Procedure No.: Procedure
Title:
Page: 9 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 ATTACHMENT 11 (Page 11 of7)of 7) SHUTDOWN MARGIN CALCULATION FOR MODES 11 AND 2
- 1. IF one or more Rod Control Cluster Assembly is dropped partially or fully into the core, THEN IMMEDIATELY go to 3/4-0NOP-028.3, 3/4-ONOP-028.3, DROPPED RCC, and continue with this procedure.
- 2. IF one or more Rod Control Cluster Assembly is misaligned with its associated bank, THEN IMMEDIATELY go to 3/4-0NOP-028.1, 3/4-ONOP-028.1, RCC MISALIGNMENT, and continue with this procedure.
- 3. Unit ..................................................................................................................... . I
- 4. Date ...................................................................................................................... . I I
- 5. Time ..................................................................................................................... .
..a a a a a a a a a n NOTE a a a a a ;
I During Unit 3 Cycle 22, Rod M-6 in Control Bank C is verified to be fully withdrawn when its stationary coil has not changed state since the last time it was verified to be fully I a withdrawn by a flux map. If its stationary gripper coil has changed state since the last time Rod M-6 was verified, then go to O-OSP-059.14, O-OSP-059. 14, Rod Position Indication (RPI) Verification, to verify Rod M-6 remains fully withdrawn, and continue with this procedure.
~-----------------
a a a a a a a a __ a __ a I __ I
- 6. Record the number of Control Rods that are dropped ......................................... . I I aaaaaaaaaaaaa;
~ - -- - -
NOTE II During Unit 3 Cycle 22, Rod M-6 in Control Bank C is experiencing a problem with its II Ii associated Analog Rod Position Indication System, which does not affect its ability to trip. I i L _______________________ I a a a a a a a a a a a a a a a a a I
- 7. Record the number of Control Rods that are known to be UNTRIPPABLE ...... . I I
- 8. IF Step 7 is greater than one (1), THEN contact Reactor Engineering and/or Nuclear Fuels for assistance in completing the Shutdown Margin Calculation.
- 9. Record the following current critical conditions:
9.1 Fractional Reactor Power ........................................................................... . 9.2 Tavg ............................................................................................................ . I I 9.3 Tref ............................................................................................................. . I W97:JPH/mr Imr lin W97:JPH/mrci/mrci/In
Procedure No.: Procedure Procedure
Title:
Procedure Page: 10 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 ATTACHMENT 11 of 7) (Page 2 of7) SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND AN]) 2 r-----------------------~ I I N OTE NOTE The measured RCS boron concentration entered below should be from the most recent I sample. Contact Primary Nuclear Chemistry or access the Chemistry Department (PI) (P1) II IL database to obtain the _______________________ ~ latest RCS boron concentration, and the date/time dateltime of the sample. I a a a a a Date Time 9.4 Most recent RCS Boron Concentration .......... L-I___-IL ....... Il...-__----'1 L-I___p_p_m-l ppm l
-------------------------- NOTE p II Burnup value in the PCB, Section 5, Figure 4 is periodically updated by Reactor The Cycle Bumup II Ii Engineering. Although the actual bumup burnup can be approximately determined to account for Ii core burnup since the last update, recording the most recent value from PCB Section 5, I III Figure 4 in Step 1.4 will produce conservative results. To approximately determine the actual burnup, increase the bumup burnup by adding 30 MWD/MTU for each day of full power I i
operation (and/or fraction thereof, e.g., add 10 MWD/MTU for 8 hours at full power or 15 I ILI MWD/MTU _ _ _ for _24 _hours __ at 50% __ power, __ etc.,_
)) since
__ the _ date_ and _time _of_the_ last_ update. __ ~ I I I 9.5 Burnup (PCB Section 5, Figure 4) I MWD/MTU MWDIMTU II I
------------------------ NOTES I
Ii ** 8CC is defined as 150 MWD/MTU. EOC is the projected cycle burnup and can be BOC Ip found in the Plant Curve Book (PCB), Section 3, Figure 7, 7 Summary of Reactivity I II Requirements and Shutdown Margin. I I
- In Steps 9.6 and 9.7 a linear interpolation between 8CC BOC and EOC is appropriate. II
~-----------------------~
9.6 Using the Burnup from Step 9.5 and the PCB, Section 3, Figure 7 (Summary of Reactivity Requirements and Shutdown Margin), record the (1)
"(1) Total Control Bank Requirements.
Requirements". pcm 9.7 Using the Burnup from Step 9.5 and the PCB, Section 3, Figure 7 (Summary of Reactivity Requirements and Shutdown Margin), record the (2)
"(2) Less Uncertainty Uncertainty" pcm W97.
W97:JIPI4/mm/mrri/In PH/mra/mralln
Procedure No.: Procedure
Title:
Procedure Page: Page: 11 11 Approval Date: 0-OP-02S.2 0-OP-028.2 Shutdown Shutdown Margin Margin Calculation Calculation 10/3/06 10/3/06 ATTACHMENT ATTACHMENT 1 1 of 7) (Page 3 of7) SHUTDOWN SHUTDOWN MARGIN CALCULATION CALCULATION FOR FOR MODES MODES 1 1 AND AND 2 2 r-- - - - - - - - - - - - - - - - - - - - - - --, I NOTES I
- In Steps 9.8 through 9.13, it is not necessary to record the RPI for rods greater than or I
equal to 228 steps.
** During Unit 3 Cycle 22, Rod M-6 in Control Bank C is verified to be fully withdrawn when its stationary gripper coil has not changed state since the last time it was verified to be fully withdrawn. I
~----------------- _ _ _ _ _ _
Ia 9.8 9.8 RPIforCBA RPlforCBA G5 E9 111 Jil L7 J5 E7 Gll Gil L9 9.9 RPIforCBB RPI forCBB F2 B10 BlO K14 P6 K2 B6 F14 P10 PlO 9.100 RPI 9.1 RPIforCBC for CBC F4 DID DiO K12 M6 K4 D6 F12 M1O MID 9.11 RPIRPIforCBD forCBD D8 M8 H4 H8 H12 - I 9.12 RPI for SBA
- G3 C9 113 J13 N7 J3 C7 G13 Gi3 N9 9.13 RPIRPIforSBB for SBB
- E5 L11 Lii L5 Ell Eli H6 RiO HID F8 K8 W07.IPI-limrn/mrn/In W97:JPH/mr Imr lin
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 12 12 Approval Approval Date: Date: 0-OP-028.2 0-OP-02S.2 Shutdown Margin Shutdown Margin Calculation Calculation 10/3/06 10/3/06 ATTACHMENT 11 ATTACHMENT (Page 44 of7) (Page of 7) SHUTDOWN MARGIN SHUTDOWN MARGIN CALCULATION CALCULATION FOR FOR MODESMODES 11 AND AN]) 22 a a a a
- I NOTE Step 10 Step 10 calculates calculates the the worth worth of of inserted inserted rods rods by comparing each by comparing each to to the worth of the worth of CBD.
CBD. L-_____________________ Dropped rods Dropped a rods ARE ARE NOT a NOT considered a considered in a a the determination in the determination of a a of most a most deeply a deeply inserted. inserted. I I 10.
- 10. EXCLUDING DROPPED RODS, calculate the inserted EXCLUDING inserted rod worth as follows: follows:
10.1 CBA 10.1 The most deeply The deeply HFP integral rod HFP rod worth ofof CBD CBD Inserted RCCA from Inserted from at this insertion at CBA conversion conversion factor factor Step 9.8 Step Section 2, Figure (PCB Section FigureS)
- 5) (PCB Section (PCB Section 3, Figure 7) 7)
10.2 CBB B pcm X ~------IIJ cml pcml The most deeply HFP integral rod worth of CBD Inserted RCCA Inserted RCCA fromfrom at this insertion CBB conversion factor Step 9.9 (PCB Section 2, Figure 5) (PCB Section 3, Figure 7) B [L--II ---"p=,-,cm pcm I X '------------II] I LI = cmI pcml 10.3 CBC The most deeply HFP integral rod worth of CBD CBD Inserted Inserted RCCA RCCA from at this insertion CBC conversion factor Step 9.10 (PCB (PCB Section 2, Figure 5) (PCB Section 3,3, Figure 7) 7) B pcm X = pcm 10.4 1004 CBD The The most most deeply deeply HFP integral HFP rod worth integral rod worth of of CBD CBD Inserted RCCA from Inserted RCCA from at this insertion at this insertion CBD conversion CBD conversion factor factor Step Step 9.11 9.11 (PCB (PCB Section Section 2,2, Figure Figure 5)
- 5) (PCB (PCB Section Section 3, 3, Figure Figure 7) 7)
B pcm XX 1.00 ---11 ] 1....--1.0_0 pcm W97:JPH/m[q/mrp/h W97:JPH/mr Imr lin
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 13 13 Approval Date: Approval Date: 0-OP-028.2 Shutdown Margin Calculation Shutdown 10/3/06 10/3/06 ATTACHMENT 1 of 7) (Page 5 of7) SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND 2 10.5 SBA most deeply The most deeply integral rod worth of CBD HFP integral HFP Inserted RCCA Inserted RCCA from from this insertion at this SBA conversion factor Step 9.12 Step 9.12 (PCB Section (PCB Section 2,2, Figure Figure 5)
- 5) (PCB Section (PCB Section 3, 3, Figure Figure 7) 7)
B [I PcJ1 pcm X IJ pcJ pcm 10.6 SBB The most deeply HFP integral rod worth of CBD Inserted RCCA from at this insertion SBB conversion factor Step 9.13 (PCB Section 2, Figure 5) (PCB Section 3, Figure 7) B [I pcm1 pcm X IJ pcm pcml 10.7 Record the total inserted rod worth (the sum of Steps 10.1 through 10.6) cm 12pcm
- 11. Record the worth of those rods known to be UNTRlPP UNTRIPPABLE ABLE as follows:
11.1 IF Step 7 equals one (1), THEN using the burnup from Step 9.5 and the PCB Section 3, Figure 7 (Summary of Reactivity Requirements and Shutdown Margin), record the interpolated worth of the Most Reactive PAIR of Stuck Rods Worth of most reactive Pair of rods stuck Out out Most reactive stuck rod (from notes) worth pcm pcm 11.2 IF Step 7 is greater than one (1), THEN contact Reactor Engineering for untrippable rod worth and record that value here, otherwise NI N/AA this step. WQ7.IPH/mrn/mra/In W97:JPH/mr Imr lin
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 14 14 Approval Approval Date: Date: 0-OP-028.2 0-OP-028.2 Shutdown Margin Shutdown Margin Calculation Calculation 10/3/06 10/3/06 ATTACHMENT 11 of 7) (Page 6 of7) SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND 2
- 12. Record the rod worth reactivity balance as follows:
Inserted Rod Worth (Step 10.7) --------+. 1~__~p_em~1 cm1 Untrippable Rod Worth (Step 11.1, 11.2 or NI N/A) A) ---------... +1~
+ __---,p_em~1 pcm Step66 Step -
[1' --------_1 1 L_______________ X X 200 pcmIRCCA pemJRCCA I]
----+. + L - - I pcm
------,----,pem1
=11
= pcml pem 1
- 13. Determine the Calculated Shutdown Margin as follows:
Step 9.7 --------+. 1~__~p_em~1 I pcm Step 9.1 Step 9.6 X
~mpcm IJ * - 1
- pcml pem I
---+
Reactivity Balance (Step 12) -------+ - - I pcm pem I
---.,;~~-
* = I pcm pem I
- 14. Using the RCS Boron Concentration from Step 9.4, determine the required Shutdown Margin as follows:
14.1 IF Step 9.4 is greater than or equal to 750 ppm, THEN the Required Shutdown Margin is ................................................. . 1000 1000 pcm pem I 14.2 14.2 IF Step 9.4 is less than 750 ppm, THEN the Required Shutdown Margin is: IJ Step 9.4 1770 [h02 ppm ppm pcm W97:JPH/mra/mra/ln W97:JPH/mr Imr lin
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 15 15 Approval Approval Date: Date: O-OP-028.2 0-OP-028.2 Shutdown Margin Shutdown Margin Calculation Calculation 10/3/06 10/3/06 ATTACHMENT 11 ATTACHMENT (Page 70f7) (Page 7 of 7) SHUTDOWN MARGIN CALCULATION FOR MODES 11 AND AND 2 Yes Yes No No 15.
- 15. Is Step 13 13 greater greater than than oror equal equal to to Step Step 14.1 14.1 or or Step Step 14.2, 14.2, asas applicable?
applicable? D D 16.
- 16. IF Step 15 15 is NO, THEN THE UNIT DOES NOT HAVE ADEQUATE SHUTDOWN MARGIN. IMMEDIATELY INITIATE AND AN]) CONTINUE BORATION 3/4-ONOP-046.1, Emergency Boration, and perform the following:
using 3/4-0NOP-046.1, 16.1 Calculate the Required Boron Concentration as follows: 16.1 Step 14.1 Step 14.1 or or 14.2 14.2 Step 13 ] Step 9.4 [ I'---------'----'pcm I - I pcm pcm I X 0.143 O.143 ppm + pcm pcm
+ ppm I= ppm 16.2 Calculate the gallons of Acid required to increase the RCS Boron Concentration
~45Ppm
[45 ppm I Step 9.4 Step9.4 ~ I D ppm gal xx In 50,790 gal in
~45Ppm ~
Step 16.1 St,p 16.1 [45 ppm II I ppm_jj ppm 16.3 Add the volume of Acid from Step 16.2 using 3/4-ONOP-046.1, 3/4-0NOP-046.1, Emergency Boration RE1iARKS: _______________________________________________________ REMARKS: Performed By: _ _ _ _ _ _ _ _ ___ Date: _ _ _ _ __ Date: Verified By: By: Date: _ _ _ _ __ Date: W97:JPH/mra/mra,9n W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 16 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 ATTACHMENT 2 (Page 11 of6)of 6) SHUTDOWN MARGIN CALCULATION FOR MODES 3, 3,44 AND 5
- 1. Record the following reference conditions:
1.1 Unit ............................................................................................................. . I I 1.2 Cycle ........................................................................................................... . I I Date Time Time 1.3 Shutdown ........................................................................ . I I I I I 1-~--------NmE----------1 NOTE I I The Cycle Burnup value in the PCB, Section 5, Figure 4 is periodically updated by Reactor I Engineering. Although the actual burnup can be approximately determined to account for I core burnup since the last update, recording the most recent value from PCB Section 5, I Figure 4 in Step 1.4 will produce conservative results. To approximately determine the I bumup, increase the burnup by adding 30 MWD/MTU for each day of full power actual burnup, I operation (and/or fraction thereof, thereof e.g., add 10 MWD/MTU for 8 hours at full power or 15 I MWD/MTU for 24 hours at 50% power, etc., etc.,)) since the date and time of the last update. I 1.4 burnup (Plant Curve Book (PCB), Cycle bumup Section 5, Figure 4) MWDIMTU MWD/MTU 1r----------~TE-----------I a id!F 1 I I CALCULATION The CALCULA TlON POINT is the point in time post shutdown at which the Shutdown I II Margin is to be calculated. It is not necessarily the present time. I I
- 2. Record the following calculation point conditions:
Date Time 2.1 Calculation Point ............................................................ . I I I 2.2 Time since Shutdown ................................................................................. . I hrs his I 1 - - - - - - ' - - , - _NOTE a a a a I.. The measured RCS boron concentration entered below should be from the most recent sample. Contact Primary Nuclear Chemistry or access the Chemistry Department (PI) (P1) database to obtain the latest RCS boron concentration, and the date and time of the l _sample.______________________ ~ I a a a a a: a : - 11IIII111 2.3 Most Recent RCS Boron Concentration .................................................... . I ppm ppm Sample Date Time IL.. I_ _ _ _---'I 2.4 Average RCS Temperature at Date/Time in Step 2.1 ................................ . W97.IPH/mrn/mrn/In W97:JPH/mr Imr /In
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 17 17 Approval Approval Date: Date: 0-OP-028.2 0-OP-02S.2 Shutdown Margin Shutdown Margin Calculation Calculation 10/3/06 10/3/06 ATTACHMENT 22 ATTACHMENT (Page 22 of6) (Page of 6) SHUTDOWN MARGIN CALCULATION FOR MODES MODES 3, 4 AND 5 3,4 2.5 The Mode: The Mode: Mode Mode 3: 3: Hot Standby Hot Standby RCS RCS temperature at 350 - 547°P at 350 - 547°F D Mode 4: Hot Shutdown RCS temperature at 200 - 350 350°F 0 P Mode 5: Cold Shutdown RCS temperature below 200 200°F 0 P D D During Unit 3 Cycle 22, the position of rod M-6 in Control Bank C will be determined by an alternate method. Por For the purpose of calculating shutdown margin for Unit 3 Cycle 22, Modes 3, 4 and 5, Rod M-6 is assumed to be fully withdrawn following a reactor trip. The number of rods not fully inserted is determined as follows:
- IF all rods except M-6 are fully inserted following a reactor trip, THEN the number of rods not fully inserted equals 1.
- IF another control rod(s) other than Rod M-6 does not fully insert following a reactor trip, THEN Rod M-6 is not counted when determining the number of rods inserted. Rod M-6 is not counted in this case, because this rod is specifically accounted for as being fully withdrawn in the reactivity values used to calculate subsequent steps.
2.6 Record the number of Control Rods that are NOT fully inserted .............. . I I
~-----------------------
NOT 1 NOTES ES i The Minimum Shutdown Boron Concentration (MSBC) calculated in Step 3 is a a function of RCS Temperature and Bumup. There are three methods available to determine MSBC as I follows: I I
. A very conservative reactivity determination of MSBC may be made without I interpolation by using the applicable PCB Section 3, Figure 5A and choosing the burnup bumup statepoint/cuive statepoint/curve and the RCS temperature statepoint/cuive statepoint/curve that are less than the burnup bumup in Step 1.4 1.4 and temperature in Step 2.4, respectively. However, using this I method, the result may be a higher value than what is desired for the actual plant condition.
I I .* A conservative reactivity determination of A interpolation ofof burnup bumup using the applicable of MSBC may be made applicable PCB Section Section 3, made by 3, Figure 5A and by aa single and choosing choosing I the temperature statepoint/curve statepoint/curve that is less than or or equal equal to the temperature in I Step 2.4. 2.4. This is the preferred and recommended method. I
- Accepting Accepting thethe built-in built-in conservatism conservatism inin unit/cycle specific data, unit/cycle specific data, an an accurate accurate reactivity reactivity I determination determination of RCS RCS temperature of MSBC MSBC may temperature using may be be made made by the applicable using the by aa double interpolation applicable PCB PCB Section 3, Figure Section 3, of burnup interpolation of Figure 5A.
bumup and and average 5A. Using this average this method, method, the the result isis the the lowest lowest acceptable value achievable, acceptable value achievable, which which may may bebe desired desired for the the actual actual plant plant condition. condition. I a a a a a a I JVQ7IPI-1/mrn/mrn/In W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 18 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 ATTACHMENT 2 of 6) (Page 2 of6) SHUTDOWN MARGIN CALCULATION FOR MODES 3, 3,44 AND 5
- 3. Determine the Minimum Shutdown Boron Concentration 3.1 Record the minimum average RCS temperature that will be assumed in the calculation and will bound the actual temperature in Step 2.4 and expected changes in plant Operations input, over the next 24 hours.
conditions, based on Operations' Assumed Minimum Average RCS Temperature °F CAUTION To preclude a non-conservative reactivityreactivIty determination of Minimum Shutdown Boron Concentration, the temperature statepointicurve statepoint/curve used in Step 3.2 must be less than or equal to the actual average RCS Temperature recorded in Step 2.4 or the lowest average RCS temperature expected by Operations due to potential changes in plant conditions during the ensuing 24 hours, as applicable. 3.2 Record the RCS temperature statepointlcurve statepoint/curve that will be used to calculate the Minimum Shutdown Boron Concentration. N/A if double interpolation is used. RCS Temperature statepoint/curve °F ________ r NOTES I In Step 3.3 below, Plant Curve Book Section 3, Figure 5A already includes the reactivity I i effects of the minimum, Hot Full Power, steady state Samarium concentration. Figure 5A i conservatively does NOT take credit for the additional build-up of Samarium that occurs I after Unit shutdown. I . During Unit 3 Cycle 22, for the purposes of calculating shutdown margin in Modes 3, 4 and I 5, Rod M-6 in Control Bank C is assumed to be fully withdrawn following a reactor trip. I
*. If all rods except Rod M-6 are fully inserted following a reactor trip, use PCB Section 3, I Figure 5A (Minimum Shutdown Boron vs. RCS Temperature as a function of Burnup (ARI-1, No-Xenon).
I .* If another control rod other than M-6 does not fully insert following a reactor trip, use PCB Section 3, Figure 5A (Minimum Shutdown Boron vs. RCS Temperature as aa function of Burnup (ARI-1-M6, No-Xenon). 3.3 Using a a a a a a a a bumup from Step 1.4, the temperature from Step 3.2, AND the U sing the burnup I applicable PCB Section 3, Figure 5A SA (Minimum Shutdown Boron vs RCS Temperature as a function of Burnup), Bumup), record the Minimum Shutdown Boron Concentration ppm W97:JPH/mr Imr lin W97:JPH/mrci/mro/ln
Procedure No.: Procedure Procedure
Title:
Procedure Page: 19 Approval Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 10/3/06 ATTACHMENT 2 of 6) (Page 4 of6) SHUTDOWN MARGIN CALCULATION FOR MODES 3, 3,44 AND AN]) 5 3.4 Confirm the temperature in Step 3.1 is greater than or equal to the temperature statepoint/curve selected in Step 3.2, and used in Step 3.3 and the proper treatment of burnup OR confirm the correct temperature/burnup statepoints/curves were used in Step 3.3 and check the interpolation calculation results as applicable and proceed to Step 4. If not, then return to Step 3.1. Performed By: By:___________________ By:_______________________ Verified By: _ _ _ _----:-:-:-_ _ __ Initials Initials CAUTION An assumption is made in Step 4 to set Xenon Wolth Worth equal to zero pcm (e.g., Xenon-free Condition) or to use the MINIMUM Xenon Wolth Worth that will exist in the core for up to 24 hours past the calculation point. This will assure that at no time between this shutdown margin (SDM) calculation and the next SDM calculation (i.e., the Tech Spec 24 hour time interval)inteival) will the transient Xenon Wolth Worth challenge satisfying the Tech Spec Minimum SDM requirement. This approach is also consistent with 3/4-GOP-103 that allows Operations flexibility to delay boration of the RCS to the Xenon-free condition for up to 20 hours post trip. IF zero pcm is assumed and Operations has not borated to the Xenon-free condition, THEN the calculation may show the minimum SDM requirement requIrement is not met in Step 7. hhuhhhh
~------------------ N OTES NOTES The amount of negative reactivity in the core post trip due to Xenon varies with core I burnup, the initial power level, power changes pre-trip, and time since trip. The Xenon concentration in the core peaks at 6 to 8 hours post trip, decays to approximately the value I downpower/trip condition at 13 to 20 hours post trip, and fully decays to prior to the downpowerltrip essentially zero pcm at 100 hours post trip.
i There are two methods available to determine the Boron Equivalent of the Xenon Worth as follows:
.* If the Xenon Worth cannot be easily determined AND the time since shutdown is >> 20 I hours, then it may be set equal to zero. Using a zero value assumes no credit is taken in the SDM calculation for the negative reactivity associated with the actual Xenon present in the reactor core. This is the preferred method when the Unit is borated to the Xenon-free condition.
I ** If the time since shutdown is :5 20 hours, a a conservative determination of the Boron Equivalent of the Xenon Worth is made by interpolating between the burnup tables in I the PCB Section 2, Figure 2A. Interpolate using the Xenon Worth that will bound the MINIMUM Xenon Worth that will exist in the core for up to 24 hours past the I calculation point point. L _____________________ _
- 1. a a a a a a a a a a a I
- 4. Using the Time Since Shutdown from Step 2.2, AND the PCB, Section 2, Figure 2A (Xenon Worth vs Time After Shutdown), or the ERDADS Poison Program, record the Boron Equivalent of the Xenon Worth as follows:
Xenon_Worth Xenon Worth I pcm -'I ÷
'--_ _ _--l:..:pcc;:.;m' I 15.5 pcm/ppm I ppm ppm II W97:.IPH/mro/mro/In W97:JPH/mr Imr lin
ProcedureNo.: Procedure No.: ProcedureTitle: Procedure
Title:
Page: Page: 20 20 Approval ApprovalDate: Date: 0-OP-028.2 0-OP-02S.2 Shutdown Margin Shutdown Margin Calculation Calculation 10/3/06 10/3/06 ATTACHMENT 22 ATTACHMENT (Page 55 of6) (Page of 6) SHUTDO4 MARGIN SHUTDOWN MARGIN CALCULATION CALCULATION FOR FOR MODES MODES 3, 3,44 AND AND 55 a
~-----------------------I I
I I NOTE I In Step In Step 5, linear interpolation 5, aa linear interpolation for for Most Most Reactive Reactive Stuck Stuck RodRod Worth Worth between between BOG BOC and and I EOG using the EOC using the Bumup Bumup in in Step Step 1.41.4 is appropriate. is appropriate. L _______________________ I 5.
- 5. Calculate the RCCA RCCA correction as as follows:
follows: 5.1 IF Step 2.6 equals zero or one, THEN the RCCA correction equals zero ppm. 0o ppm ppm 5.2 jj Step 2.6 is greater than one, THEN using the PCB, Section 3, Figure 7, Summary of IF of Requirements and Shutdown Margin, record the Boron equivalent of those rods Reactivity Requirements not fully inserted as follows: Most Reactive Step 2.6 Step 2.6 ] Stuck Rod Worth G-L- I _---'II_J
,---I x X '--_ _ _ _p_cm-ll pcm ÷ 7.0 pcm/ppm I ppm ppm I I
- 6. Record the Corrected Minimum Shutdown Boron Concentratio Concentration n as follows:
Step 3.3 Step 4 Step 5.1 or 5.2 I'--_ _---"pct:;.pm::..J1I ppm - I L-I_ _ _ --S;p:cpm. ppm::..J1I - I ppm ppm I = ppm
~
NOTE II AA YES answer answer in in Step Step 7 confirms confirms the the minimum minimum required SHUTDOWN MARGIN MARGIN per per II I Technical Technical Specification Specifications s isis being being met. met. i 7.
- 7. Is Step 66 less Is Step less than than oror equal equal to to Step Step 2.3?
2.3? ........................................................ 0 YES YES 0 NO NO 8.8. IF IF Step Step 77 isis YES, YES, THENTHEN calculate calculate the the Excess Excess SHUTDOWN SHUTDOWN MARGIN MARGIN as as follows: follows: E[ Step Step 2.32.3 Step 61 Step 6] [ 1-1_..LJpp=m-l1 -II ppm I- _--"p=pm~1 ppm 1 X 7.0 X 7.0 pcm/ppm pcm/ppm = pcm pcrn I W97:JPH/mr W97:JPH/mr ci(mrci/ln Imr lin
Procedure No.: Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 21 21 Approval Approval Date: Date: 0-OP-028.2 0-OP-028.2 Shutdown Margin Shutdown Margin Calculation Calculation 10/3/06 10/3/06 ATTACHMENT 22 (Page 66 of6) (Page of 6) SHUTDOWN MARGIN MARGIN CALCULATION FOR MODES 3, 3,44 AND AND 5 9.
- 9. IF Step IF is NO, THEN Step 77 is THEN IMMEDIATELY IMMEDIATELY perform the following:
following: 9.1 Calculate the gallons of Acid required to increase the RCS Boron Concentration to greater than or equal to that of Step 5 as follows: Step Step 2.3 (5245 ppm - ppm I ln 50,790 gal x In Step 6
= gal (5245 ppm - - ppm I 9.2 Add the volume of Acid from Step 9.1, using 3/4-0NOP-046.l, 3/4-ONOP-046.l, EMERGENCY B ORATION.
BORATION. 9.3 After sufficient time for mixing, obtain a new RCS chemistry sample and reperform Steps 2 through 9 to confirm SHUTDOWN MARGIN per Technical Specifications is being met. REMARKS: _________________________________________________________ Performed By: ______________________ Date: ----------------- Verified By:_ By: _____________________ Date: ----------------- FINAL FINAL PAGE PAGE Wq7. IPI-lImrn/mrri/In W97:JPH/mr Imr lin
<-P M A _f\,2)
JJPM -SRO Florida Power & Light Company Turkey Point Nuclear Plant ci.c) O-OP-028.2
,% 4) c_)
- r
Title:
Shutdown Margin Calculation Safety Related Procedure Responsible Department: Reactor Engineering Revision Approval Date: 10/3/06 98-1 189P, 00-0624, 01-0314, 02-0564P, RTSs 94-0031P, 97-1224, 98-1189P, 06-04 76, 06-0761P 03-0744P, 04-0663P, 05-0065P, 06-0476, OTSC 0032-99, 0177-06 W97:PS/mrg/mrg/in W97:PS/mrg/mrg/In
Procedure No.: Procedure
Title:
Page: 2 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 LIST OF EFFECTIVE PAGES Revision Page Date 11 10/03/06 10103/06 2 10/03/06 10103106 3 10/03/06 10103106 4 05/25/06 05125/06 55 10/03/06 10103/06 66 10/03/06 10103/06 77 05/25/06 88 05/25/06 99 10/03/06 10103/06 10 10/03/06 10103/06 11 10/03/06 10103/06 12 10/03/06 10103/06 13 10/03/06 10103/06 14 10/03/06 10103106 15 10/03/06 10103/06 16 10/03/06 10103106 17 10/03/06 10103/06 18 10/03/06 10103/06 19 10/03/06 10103/06 20 10/03/06 10103/06 21 10/03/06 10103/06 Imr lIn W97:JPH/mra/mra/ln W97:JPH/mr
Procedure No.: Procedure
Title:
Procedure Page: 3 Approval Date: Approval 0-OP-028.2 Shutdown Margin Calculation 10/3/06 10/3/06 TABLE OF CONTENTS Section ige 1.0 PURPOSE PURPOSE..................................................................................................................... 4
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT DOCUMENTS........ REFERENCESIRECORDS DOCUMENTS 4 3.0 PREREQUISITES....................................................................................................... PREREQUISITES 5 4.0 PRECAUTIONS/LIMITATIONS PRECAUTIONSILIMITATIONS.............................................................................. 5 5.0 SPECIAL TOOLSIEQUIPMENT..................................... TOOLS/EQUIPMENT ......................................... 7 6.0 CRITERIA ACCEPTANCE CRITERIA....................................................................................... 7 7.0 PROCEDURE 7.1 Modes 1land2 and 2.................................................................................................... 8 7.2 Modes3,4and5 Modes 3, 4 and 5 ................................................................................................ 8 ATTACHMENTS Attachment 11 Shutdown Margin Calculation For Modes 11 and 2 ............................................ 9 Attachment 2 5 Shutdown Margin Calculation for Modes 3, 4 and 5......................................... 16 AIrr7. IDLJI......,,I.-.-..-,.iI... W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Procedure Page: 4 Approval Date: Approval 0-OP-028.2 Shutdown Margin Calculation 5/25/06 1.0 1.0 PURPOSE 1.1 This procedure provides administrative and technical guidance for: 1.1.1 Verifying Shutdown Margin in accordance with Tech Spec 3.1.1.1 for Modes 1, I 2, 3 and 4, and 1.1.2 Verifying Shutdown Margin in accordance with Tech Spec 3.1.1.2 for Mode 5.
2.0 REFERENCES
/RECORDS REQUIRED/COMMITMENT REFERENCESIRECORDS REOUIRED/COMMITMENT DOCUMENTS 2.1 References 2.1.1 Technical Specifications
- 1. 3/4.1.1.1
- 2. 3/4.1.1.2
- 3. 3/4.1.3.1
- 4. 3/4.1.3.6
- 5. 3/4.10.1
- 6. 1.25 2.1.2 Plant Procedures
- 1. 0-ADM-554, Plant Curve Book
- 2. 3/4-EOP-ES-0.1, Reactor Trip Response
- 3. 3/4-EOP-ES1.1, SI Termination 3/4-EOP-ES-1.1,
- 4. 3/4-0NOP-028.1, RCC Misalignment 3/4-ONOP-028.1,
- 5. 3/4-0NOP-028.2, RCC Position Indication Malfunction 3/4-ONOP-028.2,
- 6. 3/4-ONOP-028.3, 3/4-0NOP-028.3, Dropped RCC
- 7. 3/4-ONOP-046.
3/4-0NOP-046.1, 1, Emergency Boration
- 8. 0-OSP-040.4, Estimated Critical Conditions
- 9. 0-OSP-040.16, 0-OSP-040 .16, Initial Criticality after Refueling and Nuclear Design Verification 3/4-0P-046, CVCS-Boron Concentration Control
- 10. 3/4-OP-046, 10.
W97:JPH/mro/mra/ln W97:JPH/mr Imr /In
Procedure No.: Procedure
Title:
Procedure
Title:
Page: Page: 5 Approval Date: Approval 0-OP-028.2 Shutdown Margin Calculation 10/03/06 2.2 Records Required 2.2.1 Completed copies of the below listed items constitute Quality Assurance records and shall be transmitted to QA Records for retention in accordance with Quality Assurance Records Program requirements:
- 1. Attachment 11
- 2. Attachment 2 2.3 Commitment Documents 2.3.1 FPL Calculation Number PTN-ENG-SEFJ-06-013, Turkey Point Unit 3 Cycle 22 Shutdown Margin and Minimum Shutdown Boron Concentration Analysis to Support Implementation of Proposed License Amendment on Inoperable Rod Position Indicator, L-2006-209.
2.3.2 Turkey Point Unit 3, Proposed License Amendment - Inoperable Rod Position Indication, Docket No 50-251, L-2006-209, dated September 7,2006. 7, 2006. 3.0 PREREQUISITES PREREOIDSITES 3.1 None 4.0 PRECAUTIONS/LIMITATIONS PRECAUTIONSILIMITATIONS r-----------------------, r I NOTE I During Unit 3 Cycle 22, the position of Rod M-6 in Control Bank C will be determined by an alternate method other than the Analog Rod Position Indication System, until the repair of the indication system for this rod is completed. The alternate method to verify verifv Rod M-6 stationaiy gripper coil current. Rod position is an installed Yokogawa recorder to monitor stationary M-6 is verified to be fully withdrawn following a flux map verification and verification the I stationaiy gripper coil does not change state. stationary I L _______________________ J L _ _ _ _ _ _ _ _ _ _ 4.1 With the shutdown margin less than the applicable value shown in Tech Spec Figure 3.1-1 (Modes 1,2,3 1, 2, 3 and 4), immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt % (5245 ppm) boron or equivalent until the required shutdown margin is restored. [Tech Spec 3.1.1.1] 4.2 With the shutdown margin less than 11 % Ak/k i1k1k (Mode 5), immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt % (5245 ppm) boron or equivalent until the required shutdown margin is restored. [Tech Spec 3.1.1.2] 4.3 If any control bank is inserted more deeply than the Rod Bank Insertion Limit specified in the Plant Curve Book, Section 7, Figure 3, Rod Insertion Limit vs Thermal Power, restore the control banks to the allowed limits within 11 hour or initiate an emergency boration using 3/4-ONOP-046.1, 3/4-0NOP-046.1, EMERGENCY BORATION, until the required shutdown margin is restored. [TS 3.1.3.6] 3.1.3.6] W97:JPH/mrci/mro/In W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 6 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/03/06 4.4 Shutdown margin shall be determined to be greater than required by Technical Specification 3.1.1.1, Figure 3.1-1 3.1-1:: 4.4.1 Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours thereafter while the control rod(s) is inoperable. 4.4.2 When in Mode 11 or 2 with Keff Keti greater than or equal to 11 at least once per 12 hours by verifying control rods are withdrawn beyond their rod insertion limits. 4.4.3 When in Mode 3 or 4 at least once per 24 hours by consideration of the following factors:
- 1. RCS Boron Concentration
- 2. Control Rod Position
- 3. RCS Average Temperature
- 4. Fuel Burnup based on Gross Thermal Energy Generation
- 5. Xenon Concentration
- 6. Samarium Concentration 4.4.4 The required shutdown margin shall be determined with an increased allowance for the worth of ALL immovable or untrippable control rods.
4.5 Attachment 2 is applicable for typical shutdown conditions, that is, all rods expected to be fully inserted. 4.5.1 Calculation/Verification IF a Shutdown Margin CalculationN erification is required for initial startup following refueling or for Low Power Physics Testing, THEN refer to O-OSP-040.16, Initial Criticality After Refueling And Nuclear Design Verification. 4.5.2 Calculation/Verification is required for non-initial cycle IF a Shutdown Margin CalculationNerification startup, THEN refer to O-OSP-040.4, Estimated Critical Conditions. 4.6 IF a Shutdown Margin Calculation/Verification CalculationNerification is required for any atypical condition (e.g., one or more rods stuck out or stuck partially inserted), THEN consult Reactor Engineering. 4.7 During Unit 33 Cycle 22, the position of Rod M-6 in Control Bank C will be determined by an alternate method other than the Analog Rod Position Indication System, until the repair of the indication system for this rod is completed. The alternate altemate method cannot determine if Rod M-6 is fully inserted following a reactor trip. The alternate method to verify Rod M-6 withdrawn position is the recorder installed to track parameters of the stationary gripper coil of Rod M-6 control rod drive mechanism. Rod M-6 is verified to be fully withdrawn when its stationary gripper coil has not changed state since the last time it was verified to be fully withdrawn by a flux map. 4.7.1 When calculating shutdown margin on Unit 33 Cycle 22 for Modes 11 and 2, Rod M-6 is assumed to be fully withdrawn if its stationary gripper coil has not changed state. 4.7.2 When calculating shutdown margin on Unit 33 Cycle 22 for Modes 3, 44 and 5, Rod M-6 is assumed to be fully withdrawn following reactor trip. Wq7:.IPI-{/mrn/mrn/In W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 7 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 5/25/06 5.0 5.0 SPECIAL TOOLSIEQUIPMENT SPECIAL TOOLS/EQUIPMENT 5.1 5.1 The Plant The Plant Curve Curve Book, and/or other Book, and/or approved analysis other approved analysis for the appropriate for the appropriate unit unit and and cycle. cycle. 6.0 6.0 ACCEPTANCE CRITERIA ACCEPTANCE CRITERIA 6.1 6.1 The Shutdown The Shutdown Margin Margin shall shall be: 6.1.1 6.1.1 Greater than or equal to the value shown in Tech Spec, Figure 3.1-1 for Modes 1, Greater 1, 2,33 and 2, and4, 4, and 6.1.2 Greater than or equal to 11% % ~k/k Ak/k for Mode 5. Wq7:.IPF-1/mrn/mrn/In W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 8 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 5/25/06 7.0 PROCEDURE CAUTION With the Shutdown Margin less than that required by Technical Specification 3.1.1.1 or 3.1.1.2, as applicable, boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt % (5245 ppm) boron or equivalent shall be immediately initiated and continued until the required shutdown margin is restored. r----------ooru----------- I_I.... NOTES 1 I I
- Values determined by precise modeling with neutronics codes are more accurate than I
- first principles implementation of generic curves. Therefore, documented values I supplied by vendor or staff may be substituted for calculated values. I
** If the actual worth of the inoperable RCCA is NOT known, then the worth of the most I reactive rod should be used. I I .* Obtain as much of the Reference conditions as possible from measurement.
I I Design values for this procedure are required to be taken from either: I I I - Plant Curve Book, OR I
- Approved analysis 7.1 Modes 1land2 and 2 7.1.1 IF the unit is in Mode 11 or 2, THEN complete Attachment 1.
----<"""----~
Modes 3 4 and 5 - 7.2 "-'-"'=""'--',--'-~-= '-"" _7_.2_._1__I_F_t_h_e unit is in Mode 3, 4, or 5, THE~V E1D OF TEXT END W97:JPH/mrcj/mrcj/ln W97:JPH/mr Imr lin
Procedure No.: Procedure
Title:
Page: 16 Approval Date: 0-OP-0 28.2 Shutdown Margi Margin n Calculation 10/3/06 10/3/06 ATTA CHMENT 2 (Page lof6) 1 of 6) SHUT DOWN MARGIN CALCULATION FOR MODES 3, 3,44 AND 5
- 1. Record the following reference conditi conditions: ons:
1.1 Unit .......................................................................................................... Unit.... 4 1.2 Cycle ........ .......... ........ .... ............... ...... ............ ...... .... ........ ......... ........... Cycle..
..... 223'3.
Time 1.3 Shutdown ........................................................................ . I I I NOTE The Cycle Burnup Burnup value in the PCB, Section I Engineering. Enginee ring. Althoug Although Section 5, Figure 4 is periodic h the actual burnup can be approxi approximatel periodically mately ally updated updated by Reactor y determined to account for I core bumup burnup since the last update, update, recordinrecording g the most recent value from PCB Section Section 5, I Figure 4 in Step 1.4 will produce conserv I actual burnup, conservative burnup, increase the burnup by adding 30 MWD/M ative results. results. To approxi MWD/MTU approximatel mately y determi TU for each day of full power determine ne the I operation operatio n (and/or (and/or fraction fraction thereof, thereof e.g., add 10 MWD/M MWD/MTU TU for 8 hours at full power or 15 i MWD/MTU MWD/M TU for 24 hours at 50% power, etc.,) since the date and time of the I If, _.- _ ~ _ ~ _ ~ _ _ _ _: ____ _ _. ___ ~ last update. update. _ _ _ _ I 1.4 Cycle bumup burnup (Plant Curve Book (PCB), (PCB), Section 5, Figure 4) Section I i-su. 462.2. r -- - -- - - - -- - -- - NO'TE: -- - - - -- - -- - - - - I a a a MWDIMTU MWDJMTU I I I The CALCUCALCULAT LA TlON ION POINT is the point in time post shutdow Margin is to be calculat calculated. ed. It is not necess necessarily shutdown arily the present time. n at which the Shutdown I 2. I
- - ng- calcula
-Record-- -the followi D
following
- -- tion - point -- - - - -- - - - -- - -- - - - --. I conditions:
conditi ons: Date Time 2.1 Calculation Point ............................................................ . I ,!;l(/"l-Isx f'N(
*tt;rI\<;1 r..:
Ct(VJ ~v ) t....) I 080(.'J 2.2 Time since Shutdown ............................................................................. a
~ __
~ ____ -. __ ~ __ -..E _ _ _; _ _ _: __ -. _____
.... . I 25 2S hrs I - a a .
a NOTE The measur measured ed RCS boron concentration entered below should be from the most recent sample. Contact Primary Primary Nuclear Chemis Chemistry try or access the Chemis Chemistry try Departm Department ent (PI) database databas e to obtain the latest RCS boron concen concentration tration,, and the date and time of the I _ sample I _ _ a a a a _______ ~ I a a a a a 2.3 Most Recent RCS Boron Concen Concentratio trationn .................................................... . IiO"l"z.. ppm jzz. ppm Sample Sample Date 1 y;x./'l..v:
/cie/ .{y." Time I b""'O-"'C.J'---_--'I
--"'O...
(1",,";"(\0'( 1-1 (-{zi rr) ","\.01.;;) 2.4 Average RCS Temperature at Date/Time in Step 2.1 ................................
. I 547-tv OF
°F W97:JPH W97:JPH/mr /mrct/mrg/ln Imr lin
ProcedureNo.: Procedure No.: ProcedureTitle:
Title:
Procedure Page: Page: 1717 Approval ApprovalDate: Date: 0-OP-028.2 0-OP-028.2 ShutdownMargin Shutdown MarginCalculation Calculation 10/3/06 10/3/06 ATTACHMENT22 ATTACHMENT (Page22of6) (Page of 6) SHUTDOWNMARGIN SHUTDOWN MARGINCALCULATION CALCULATIONFOR FORMODES MODES3,3,4 4 AND AN])55 2.5 The TheMode: Mode: Mode 2.5 Mode3:3: Mode 4:4: Mode HotStandby Hot Hot Standby Shutdown RCS Hot Shutdown RCStemperature RCS temperatureatat350 RCS temperature 350 - 547°F
- 547°F M temperatureatat200 200 - 350°F3 50°F Mode 5:5:
Mode Cold Shutdown Cold Shutdown RCS RCS temperature temperature below below 200°F 200°F D D During Unit During Unit 33 Cycle Cycle 22, 22, the the position position of of rod rod M-6 M-6 in in Control Control Bank Bank CC will will be be determined determined by alterna te method. For by anan alternate method. For the the purpose purpose of calculating shutdown ofcalculating shutdown marginmargin for for Unit Unit 33 Cycle Cycle 22, 22, Modes Modes 3,3, and 5, 44 and Rod M-6 5, Rod M-6 isis assumed assumed to to be be fully fully withdrawn withdrawn following following aa reactorreactor trip. trip. The The number number of not fully fully inserted inserted isis determined ofrods rods not determined as as follows: follows: j all IF all rods rods except except M-6 M-6 are are fully fully inserted inserted following following aa reactorreactor trip, trip, THENTHEN the the number number of rods not fully of rods not fully insertedinserted equals equals 1. 1. another control IF another control rod(s) rod(s) other other than than RodRod M-6 does not M-6 does not fully fully insert insert following following a reactor reactor trip, trip, THEN Rod M-6 is not counted THEN counted when determining determining the number number of rods inserted. inserted. Rod Rod M-6M-6 is not counted counted in this case, because is not because this rod is specifically specifically accounted accounted for as as being being fully fuily withdrawn in the reactivity withdrawn reactivity values used to calculate calculate subsequent subsequent steps. 2.6 Record the the number number of Control Q 2.6 Record Control Rods that are NOT fully frilly inserted inserted ............... I C)
...... - - - - - - - - - - NOTES - - - - - - - - - - - - -.
i The The Minimum Minimum ShutdoShutdown wn Boron Conce ntration (MSBC) calcula Concentration calculatedted in Step 3 is aa function function of of i RCS RCS Tempe rature and Temperature and Burnup. There are are three metho methods available ds availab determine le to determ MSBC as I follows: follows: ine MSBC as I AA veiy I
... very consei vative reactivity conservative reactivity deteim ination of determination of MSBC MSBC may may be be made made withoutwithout I interpo burnup lation by interpolation by using using the the applica ble PCB applicable PCB Sectio Section Figure 5A n 3,3, Figure 5A and and choosi choosing ng thethe burnup statepo int/cuive and statepointlcurve and the the RCS RCS temper ature statepo temperature statepointlcurve int/curve that that are are less less than than the the burnup burnup in in Step Step 1.41.4 and and temper ature in temperature in Step Step 2.4, respectively.
2.4, respec However, using tively. However, using this this metho method, condition. d, the condition. the result result may may be be aa higher higher value value than than what what is is desired desired for for the the actual actual plant plant II I I ... AA conser vative reactiv conservative interpo lation of ity determ reactivity ination of determination of MSBC MSBC may may be be made made by by aa single single I interpolation ofburnup burnup usmg using the the applica applicableble PCB PCB Section Section 3,3, Figure Figure 5A5A andand choosi choosing ng ~O(. the the temper ature statepo temperature int/cuive that statepointlcurve that isis less less than than or or equal equal to to the the temper temperatureature Thin Step Step 2.4. 2.4. This This isis the the preferr preferreded and andrecomm recommended ended method method. . I
*.. Accep Acceptingting the the built-in built-in conser vatism inin unit/cycle conservatism unitlcycle specifi specific data, an an accura accurate reactivity l c data, te reactiv ity I determ ination of determination RCS ofMSBC MSBCmay maybe bemade madeby byaa double double interpo interpolation lation of ofburnup burnup and andaverag average e RCS temper ature using temperature using thethe applica applicableble PCB PCB Section Section 3,3, Figure Figure 5A. 5A. Using Using this this method method, ,
the the result result isis the the lowest lowest accept able value acceptable value achiev achievable, which may able, which may be be desired desired for for thethe I actual plant condition. actual plant condition.
-s.-, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I WQ7.IPI-tlmrn!mrn/In W97:JPH/mr Imr lin
ProcedureNo.: Procedure No.: ProcedureTitle:
Title:
Page: Procedure Page: 1818 Approval ApprovalDate: Date: 0-OP-028.2 0-OP-028.2 ShutdownMargin Shutdown MarginCalculation Calculation 10/3/06 10/3/06 ATTACHMENT22 ATTACHMENT (Page22of6) (Page of 6) SHIJTDOWNMARGIN SHUTDOWN MARGINCALCULATION CALCULATIONFOR FORMODES MODES3,3,4 4 ANDAND55 3.3. Determinethe Determine theMinimum Minimum Shutdown ShutdownBoron BoronConcentration Concentration 3.1 3.1 Recordthe Record the minimum minimum average average RCS RCS temperature temperature that thatwill will bebe assumed assumed in in the the calculation calculation and will bound the and will bound the actual actual temperature temperature inin Step Step 2.4 2.4 andand expected expected changes changes inin plant plant conditions, based conditions, based on on Operations' Operations input, input, overover the the next next 2424 hours. hours. Assumed MinimumMinimum Average Average RCS RCS Temperature Assumed Temperature L 547 j °F CAUTION CAUTION To preclude To preclude aa non-conservative non-conservative reactivity reactivity determination determination of of Minimum Minimum Shutdown Shutdown Boron Concentration, Boron Concentration, the the temperature temperature statepointicurve statepoint/curve used used in Step 3.2 in Step 3.2 must must be be less than less than or or equal equal to to the the actual actual average average RCS RCS Temperature Temperature recordedrecorded in in Step Step 2.42.4 or or the lowest the lowest average average RCS RCS temperature temperature expected expected by by Operations Operations due due to to potential potential changes in changes in plant plant conditions conditions during during the the ensuing ensuing 24 hours, as applicable. applIcable. 3.2 3.2 Record the RCS temperature statepoint/curve Record statepoint/curve that will be used to calculate the Minimum Minimum Shutdown Boron Concentration. Shutdown Concentration. N/A if double interpolation is used. RCS Tempe RCS rature statepoint/curve Temperature statepoint/curve °F i~ - - -. -- - - - -- -- -- .. - - -- ... - NOTE NOTES S I In In Step Step 3.3 3.3 below, below, Plant Plant Curve Curve BookBook Section Section 3, 3, Figure 5A 5A already already includes includes thethe reactivity reactivity I effects effects of of the the minimum, minimum, Hot Hot Full Full Power, Power, steady steady statestate Samarium Samarium concentration concentration.. Figure Figure 5A 5A conservative conservatively ly does does NOTNOT take take credit credit for the the additional additional build-up build-up of of Samarium Samarium that that occurs occurs s after after Unit Unit shutdown. shutdown. I During During Unit Unit 33 Cycle Cycle 22, 22, for for the the purposes purposes of of calculating calculating shutdown shutdown margin margin in in Modes Modes 3, and 3, 44 and 5,5, Rod Rod M-6 M-6 inin Control Control Bank Bank CC is is assumed assumed to to be be fully fully withdrawn following aa reactor withdrawn following reactortrip. trip. I
** IfIfall I all rods rods except except RodRod M-6 M-6 areare fully fully inserted inserted following following aa reactor reactortrip, trip, use use PCB PCB Section Section 3,3, I Figure (ARI-1, 5A (Minimum Shutdown Figure 5A (Minimum Shutdown Boron Boron vs. vs. RCS RCS Temperature Temperature as as aa function function of ofBurnup Burnup j
(ARI-1, No-Xenon). No-Xenon). I *
- IfIfanother PCB anothercontrol control rod rod other other thanthan M-6M-6 does does not not fully fully insert following aa reactor insert following reactor trip, trip, use use PCB Section Section 3,3, Figure Figure 5A 5A (Minimum (Minimum Shutdown Shutdown BoronBoron vs. vs. RCS RCS Temperature Temperature as as aa function function of ofBurnup Burnup(ARI-1-M6, (ARI-1-M6, No-Xenon).
No-Xenon). -. ____ I Ia t- a a a I 3.3 3.3 Using U singthe thebumup bumupfrom from Step Step 1.4, 1.4,thethetemper temperature ature fromfrom Step Step3.2,3.2,AND ANDthe the applica ble PCB Section applicable PCB Section 3, Figure5A 3, Figure 5A(Minimum (MinimumShutdown ShutdownBoron Boronvs vs RCS RCSTempe rature asasaafunction Temperature functionof ofBurnup), Burnup),record recordthe theMinim Minimum um Shutdown ShutdownBoron BoronConcentratio Concentration n ItO~7 ttS 4O7 - ppm ppm inter poli'1"\ (;"1\ {H 9 "" rriH9 ~?*.ilS))t(zz4 fy;ZZ-40(.'(J'\] o r.. 4CCO}
\j;COt,-WV W97:JPH/mr W97:JPH/mr a/mro/ln Imr lin - (i 24)( ti.'2b () :::- Q7 i II 9*- (124,c to e'fpDfO (atow (z"llow:i:
i\ i SPP-\h
Procedure No.: Procedure
Title:
Page: 19 Approval Date: 0-OP-028.2 Shutdown Margin Calculation 10/3/06 ATTACHMENT 2 of 6) (Page 4 of6) SHUTDOWN MARGIN CALCULATION FOR MODES 3, 3,44 AND 5 3.4 Confirm the temperature in Step 3.1 is greater than or equal to the temperature statepoint/curve selected in Step 3.2, and used in Step 3.3 and the proper treatment of temperature/burnup statepoints/curves were used in Step burnup OR confirm the correct temperatureiburnup 3.3 and check the interpolation calculation results as applicable and proceed to Step 4. If not, then return to Step 3.1. Performed By: By:___________________
'Ie: 'I.. " By:_______________________
Verified By: ,,')(' x Initials Initials CAUTION An assumption is made in Step 4 to set Xenon Worth equal to zero pcm (e.g., Xenon-free Condition) or to use the MINIMUM Xenon Worth that will exist in the core for up to 24 hours past the calculation point. This will assure that at no time between this shutdown margin (SDM) calculation and the next SDM calculation (i.e., the Tech Spec 24 hour time interval) will the transient Xenon Worth challenge satisfying the Tech Spec Minimum SDM requirement. This approach is also consistent with 3/4-GOP-I 03 that allows Operations flexibility to delay boration of the RCS to the 3/4-GOP-103 Xenon-free condition for up to 20 hours post trip. IF zero pcm is assumed and Operations has not borated to the Xenon-free condition, THEN the calculation may show the minimum SDM requirement is not met in Step 7.
~-----------------------I S
N OTES NOTES I The amount of negative reactivity in the core post trip due to Xenon varies with core burnup, the initial power level, power changes pre-trip, and time since trip. The Xenon bumup, II concentration in the core peaks at 6 to 8 hours post trip, decays to approximately the value I downpower/trip condition at 13 to 20 hours post trip, and fully decays to prior to the downpowerltrip essentially zero pcm at 100 hours post trip. There are two methods available to determine the Boron Equivalent of the Xenon Worth as follows:
~
I I I
*. If the Xenon Worth cannot be easily determined AND the time since shutdown is >
hours, then it may be set equal to zero. Using a zero value assumes no credit is taken I ~ '"
> 20(
20 I 2() f'$ P min the SDM calculation for the negative reactivity associated with the actual Xenon 1 I ....... present in the reactor core. This is the preferred method when the Unit is borated to the Xenon-free condition. ..-) II I
- If the time since shutdown is ::; 20 hours, a conservative conseivative determination of the Boron II Equivalent of the Xenon Worth is made by interpolating between the bumup burnup tables in I the PCB Section 2, Figure 2A. Interpolate using the Xenon Worth that will bound the MINIMUM Xenon Worth that will exist in the core for up to 24 hours past the I calculation point.
L _______________________ II S a a a
- 4. Using the Time Since Shutdown from Step 2.2, AND the PCB, Section 2, Figure 2A (Xenon Worth vs Time After Shutdown), or the ERDADS Poison Program, record the Boron Equivalent of the Xenon Worth as follows:
Xenon Worth Xenon Worth I pcm -ll L...-_ _ _----"..:pc:.:.::m' I 15.5 pcm/ppm
.;- 15.5
÷ I o 0 ppm ppm II W97:JPH/mra/mra/In W97:JPH/mr Imr lin
ProcedureNo.: Procedure No.: ProcedureTitle:
Title:
Page: Procedure Page: 2020 Approval ApprovalDate: Date: 0-OP-028.2 0-OP-028.2 ShutdownMargin Shutdown MarginCalculation Calculation 10/3/06 10/3/06 ATTACHMENT22 ATTACHMENT (Page55 of6) (Page of 6) SNIITDOWNMARGIN SHUTDOWN MARGINCALCULATION CALCULATIONFOR FORMODES MODES3,3,4 4 ANDAND 55
~-----------------------I I
I NOTE I I InIn Step Step 5,5, aa linear linear interpolation interpolation for for Most Most Reactive Reactive StuckStuck Rod Rod Worth Worth between between BOe BOC and and I _______________________ 1 EOC using Eoe using the the Bumup Burnup inin Step Step 1.4 1.4 isis appropriate. appropriate. L 5.
- 5. Calculate the Calculate the RCCA RCCA correction correction as as follows:
follows: 5.1 5.1 IF Step IF Step 2.6 2.6 equals equals zerozero or or one, one, THEN THEN the the RCCA RCCA correction correction equalsequals zerozero ppm. ppm. 00 ppm ppm 5.2 5.2 IF Step IF Step 2.6 is greater than one, is greater one, THEN THEN using the PCB, PCB, Section Section 3, 3, Figure 7, 7, Summary Summary of Reactivity Requirements of Reactivity Requirements and and Shutdown Shutdown Margin,Margin, recordrecord the Boron Boron equivalent equivalent of of those those rods rods not fully inserted as as follows: Most Reactive Step 2.6 Step 2.6 ] Stuck Rod Worth G- ,-------,I J_] X X '--_ _ _ _ pcm pc_m-JI +
÷ 7.0 pcm/ppm = ppm ppm II 6.
- 6. Record the Corrected Minimum Shutdown Boron Concentratio Record Concentration n as follows:
Step 3.3 Step 4 Step 5.1 or 5.2 IW15 WB7 ! t 5 ppm ppm II - I1.-1_ _--=O~p=pm::...J1ppm - II 0 ppm 0 ppm =II = Iic1! liDS::;! i3 ppm I 15 ppm
~
NOTE NOTE i I iI AA YES answer answer in in Step Step 77 confirms confirms the the minimum minimum required required SHUTDOWN SHUTDOWN MARGIN MARGIN per per II I Technical Technical Specification Specifications s isis being being met. met. I 7.
- 7. Is Step Is Step 66 less less thanthan or or equal equal to to Step Step 2.3?
2.3? ........................................................ LI 0 YES YE5 00 NO NO 8.8. IF IF Step Step 77 isis YES, YES, THENTHEN calculate calculate the the Excess Excess SHUTDOWN SHUTDOWN MARGIN MARGIN as as follows: follows: [ Step2.3 Step 2.3 Step6 Step 6] L I [
~~==~
ppm \ - \~--~~ ppm ppm \ ppm jj XX 7.0 7.0 pcm/ppm pcm/ppm = pcm pcm I W97JFH/rn W97:JPH/mr iciimrg/In Imr lin
Procedure No. ProcedureTitle: Procedure No.: Procedure
Title:
Page: Page: 2121 Approval ApprovalDate: Date: 0-OP-028.2 0-OP-028.2 ShutdownMargin Shutdown MarginCalculation Calculation 10/3/06 10/3/06 ATTACHMENT22 ATTACHMENT (Page66of6) (Page of 6) SHUTDOWNMARGIN SHUTDOWN MARGINCALCULATION CALCULATIONFOR FORMODES MODES3,3,4 4 AND AND55 9.9. IFStep IF Step77isisNO, NO,THENTHENIMMEDIATELY IMMEDIATELYperform performthe thefollowing: following: 9.1 9.1 Calculatethe Calculate the gallons gallons of ofAcid Acid required required toto increase increasethe the RCS RCS Boron Boron Concentration Concentration toto greater than or equal greater to that of Step than or equal to that of Step 55 as as follows: follows: Step Step2.3 2.3 50,790 gal gal xx In In ppm - (5245ppm (5245 I '\0"22. 402Z ppmppm I = 50,790 -
= 1700:: Ie:') gal I Step Step 66 b3 gal ppm -
(5245 ppm (ct5- 9:n (tlJ5- 9:r gol)
.L) 3 (5245 -
I j We'l1-i{Sppm we;14ppm 1 9.2 9.2 Add the Add the volume volume of of Acid Acid from from StepStep 9.1, 9.1, using using 3/4-0NOP-046.1, 3/4-ONOP-046.1, EMERGENCY EMERGENCY BORA TION. BORATION. D"fect~ '1<0 -to do ** i do -{'{'lIS. 9.3 9.3 After sufficient After sufficient time time for mixing, mixing, obtain a new RCS chemistry chemistry sample and and reperform reperform Steps 22 through Steps through 9 to confirm SHUTDOWN SHUTDOWN MARGIN MARGIN per TechnicalTechnical Specifications is Specifications is being met. being met. REMA REMARKS: RKS:_____________________________________________________ Perform Performed ed By:___ By: _ ______ _ _______ _______ Date:, _ _ _ _ _ _ _ ___ Date:_ Verifie Verified d By:___ By: _ _ _____ _ __ Date: Date: FINAL FINALPAGE PAGE W97:JPH/mrci/mra/In W97:JPH/mr Imr lin
Section3,3,FigureS Section Figure 5 26 26OctOct2006 2006 UNIT 44 CYCLE UNIT CYCLE 23 23 wJP Minimum Shutdown Minimum Shutdown Boron Boron vs ReS Temperature vs RCS Temperature function of as aa function as Burnup (ART-I, ofBurnup (ARl-I, No No Xe)Xe) 1800 1800 I.. ,.......
....I... :.... .* _..........__.... " .. i ...,...__ ...... I..
1600 600 Mode 55 Mode
- 1. Mode Mbde4 4 Mode 33 Mode oMWDIMTU OMWD1MTU .. ,
2000MWOIMTU 2000 MWDIMTU i .. 4000 MWD/MTU ...:..-:. *_..t-**_*- --1--"- ...._-*.".. , 1400 1400 6000 MWDIMTV 8000 MWDIMTU WD1U; S 1200-1200
- 0. 0.. . 0MWDTU . . I . : *. :.
0.. '0.
):::;
14000 MWD1MTU . .go:j 1000
- 1000-b DMWOIU
~
- 6) ~
c)):::; (.) ::. :z.i I:: o0 800 800 U U ..,
):::;
2008 .j. &:Q 600 600 400 400 EN 200 200 Note: IF Note: IF the the actual actual burnup burnup falls faBs between between twotwo lines, THEN a conservative estimate lines, THEN estimate isis to to move up to move up the next to the next (less(less burnup) burnup)
. line.
line. In In lieu of this lieu of this adjustment, adjustment, Section Section 33 Figure Figure 5A can be 5A can be used, used, by interpolating between by interpolating burnup and between bumup temperature steps. nnd temperature steps. . . 00 I,; III! 600 00 100 100 200 200 300 300}}