ML112650250
| ML112650250 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 09/21/2011 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML112650250 (297) | |
Text
{{#Wiki_filter:DUKE ENERGY McGuire Nuclear Station 2011 INITIAL LICENSE ROISRO Admin JPMs LEAD EXAMINER: Edwin Lea
ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (Rev 041311) Facility: McGuire Date of Examination: 6/27/11 Examination Level: RD Operating Test Number: Nil-i Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.20 (4.6) Ability to interpret and execute procedure Conduct of Operations steps M,R JPM: Perform a Manual Shutdown Margin Calculation 2.1.25 (3.9) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc. M,R JPM: Calculate Dilution Needed for a Specified Rod Change 2.2.3 (3.8) Knowledge of the design, procedural, and Equipment Control operational differences between units. D R JPM: Use Main Generator Capability Curve 2.4.34 (4.2) Knowledge of RD responsibilities Emergency performed outside the main control room Procedures/Plan during an emergency and the resultant N, R operational effects. JPM: Independently Verify Spent Fuel Pool Level Adjustment NOTE: All items (5 total) are required for SROs. RD applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (4)
(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1) (N)ew or (M)odified from bank (> 1) (3) (P)revious 2 exams ( 1; randomly selected) (0) NUREG-l 021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-l DRAFT (Rev_041 311) RO Admin JPM Summary Ala This is a modified version bank JPM ADM-NRC-Al-0l1. The operator will be told that Unit 1 was shutdown to Mode 3, 15 minutes ago, that they are the OATC, that the reactivity computer (REACT) is out of service, and that preparations are being made to commence a plant cooldown. The operator will be directed to perform a Shutdown Margin Calculation per OPIO/A161001006 Enclosure 4.5 (Shutdown Margin Unit Shutdown, Modes 5, 4, or 3 Without Xenon Credit), and identify whether or not the cooldown can be initiated under the present conditions. The operator by completing Enclosure 4.5 of 0P111A161001006 (Reactivity Balance Calculation) will determine the Effective Boron Concentration to assure SDM to be 1382 ppm, and identify that the NC System must be borated to this value before the cooldown can be initiated. Aib This is a modified JPM using Bank JPM OP-MC-JPM-ADM-214 as its basis. The operator will be given a set of initial conditions and told that it is desired to insert the Bank D Control Rods about 35 steps. The Operator will be given the Core Data Book and asked to manually determine the amount of Reactor Makeup Water that will be necessary to add, to complete the rod height adjustment. A2 This is Bank JPM-ADM-NRC-A2-003. The operator will told that Unit I is at 74% reactor power, given a set of Main Generator conditions, and that a power increase to 100% is imminent. The operator will be directed to determine the maximum permissible generator load, the maximum reactive load the desired voltage per the Generator Voltage Operating Schedule assuming a power factor of 0.85 is maintained constant during the power increase. The operator will select the correct Generator Capability Curve and use it to determine the maximum permissible generator load and reactive load; and then determine the desired voltage per the Generator Voltage Operating Schedule. A4 The operator will be told that the Emergency Plan has been implemented due to an attack on the facility, that the hostile threat has been eliminated and the plant is now recovering, however heavy damage has been sustained. The operator will also be told that AP111A15500124 (Loss of Plant Control Due to Fire or Sabotage) has been implemented on Unit 1, that the Standby Makeup Pump is operating to provide inventory to the NC System, and that the crew is attempting to maintain Spent Fuel Pool Level greater than minus 2 feet in accordance with Enclosure 4.4 (Spent Fuel Pool Level Control) of OPI1/A162001005 (Spent Fuel Cooling System). The operator will be provided with paperwork associated with the control of the SEP level and other pertinent data, and then directed perform an independent verification (IV) ensuring that the total desired SEP Level change is within the guidance of the Enclosure 4.4 of 0P111A162001005; and then to identify any corrections or changes that are needed. The operator will be expected to review Table 4.4-1 of Enclosure 4.4 of OP/11A162001005 and identify three errors, and make the required corrections. NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Ala RO 2011 Admin JPM Ala RO (REV_041111)
- NUREG 1021, Revision 9
Appendix C Page 2 of 14 Form ES-C-i
. JOb Performno Measure WOrkhe Facility: McGuire Task No.:
Task
Title:
Perform a Manual Shutdown Margin JPM No.: 2011 Admin JPM Ala Calculation RD K/A
Reference:
GK/A 2.1.20 (4.6) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant 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:
- Unit I was shutdown to Mode 3, 15 minutes ago.
- You are the Unit I Operator at the Controls (OATC).
- The reactivity computer (REACT) is out of service.
- Unit 1 OAC is available.
- Preparations are being made to commence a plant cooldown to Mode 5.
Task Standard: The operator, by completing Enclosure 4.5 of OP/I /A161 00/006 (Reactivity Balance Calculation) will determine the Effective Boron Concentration to assure SDM to be 1382 ppm, and identify that the NC System must be borated to this value before the cooldown can be initiated. Required Materials: Calculator General
References:
OP/0/A/6100/006 (Reactivity Balance Calculation), Rev 72 OP/l/A/6100/SD-l (Prepare for Cooldown), Rev 34 McGuire 1 Cycle 21 Core Operating Limits Report, Rev 30 OP/l/A/6100/022 (Unit 1 Data Book) Cycle 21, Rev 480 2011 Admin JPM Al a RD
- NUREG 1021, Revision 9
Appendix C Page 3 of 14 Form ES-C-i Jol, Performance Measure Worksheet - Handouts: McGuire 1 Cycle 21 Core Operating Limits Report 0P101A161001006 (Reactivity Balance Calculation), Enclosure 4.5 (Shutdown Margin Unit Shutdown Modes 5, 4 or 3 Without Xenon Credit) OP/0/A/6100/006 (Reactivity Balance Calculation), Enclosure 4.8 (Fission Product Correction Calculation) OPI1/A16i00122, Enclosure 4.3, Table 1.15, Cycle 21 Emergency Procedure (EP) Setpoints 0P111A16100122, Enclosure 4.3, Table 6.5, Shutdown Boron Concentration, McGuire I Cycle 21, 1.0% Shutdown Margin OP/1/A16100/22, Enclosure 4.3, Table 6.5, Shutdown Boron Concentration, McGuire 1 Cycle 21, 1.3% Shutdown Margin OP/1/A/6100/22, Enclosure 4.3, Table 6.7, Shutdown Fission Product Correction, Unit 1 Cycle 21 OP/i/A16100/22, Enclosure 4.3, Table 6.10, ARI Differential Boron Worth as a Function of Temperature and Burnup, Unit I Cycle 21 OP/I/A16100/22, Enclosure 4.3, Table 6.13, Shutdown Boron ARI, McGuire 1 Cycle 21, Required Boron Concentration for 1.0% Shutdown Margin as a Function of Temperature and Burnup. OP/1/A16100/22, Enclosure 4.3, Table 6.13, Shutdown Boron ARI, McGuire I Cycle 21, Required Boron Concentration for 1.3% Shutdown Margin as a Function of Temperature and Burnup. Initiating Cue:
- Based on the information provided to you on the Data Sheet, perform a Shutdown Margin Calculation per OP/0/AI6IOO/006 Enclosure 4.5 (Shutdown Margin Unit Shutdown, Modes 5, 4, or 3 Without Xenon Credit).
- Identify whether or not the cooldown can be initiated under the present conditions.
Time Critical Task: NO Validation Time: 30 minutes 2011 Admin-JPMA1aRO NUREG 1021, Revision 9
Appendix C Page 4 of 14 Form ES-C-I PERFORMANCE INFORMAT[ON (Denote Critical Steps with an asterisk*) Provide Candidate with Initial ConditionslCue and Data Sheet (Last two (2) Pages of this JPM), and the ten (10) Handouts identified in this JPM. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Step 3.1) If NC Boron concentration> refueling The operator recognizes boron concentration for that the present Boron COLR: Concentration is NOT (Step 3.1.1) Shutdown greater than Refueling Margin is met. Boron Concentration, and (Step 3.1.2) Exit this proceeds to Step 3.2. procedure. (Operator may check Section 2.15.1 of COLR). 2 (Step 3.2) Record the The operator records Unit 1, following: Cycle 21, and 200 EFPD (Step 3.2.1) Unit (Information from Data Cycle Sheet) (Step 3.2.2) Burnup (P1457) 2011 Admin-JPMA1aRO NUREG 1021, Revision 9
Appendix C Page 5 of 14 Form ES-C-i
-- PERFORMANCE iNFORMATIOFsf STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT *3 (Step 3.2) Record the following:
(Step 3.2.3) NC System Effective Boron Concentration The operator recognizes (Step 3.2.3.1) IF OAC is that the OAC is available, unavailable and proceeds. (Step 3.2.3.2) IF OAC is available: Record B-i 0 Atom Percent, The operator records 19.8 Best Estimate (P5613) (Information from Data Sheet) Record the Current boron The operator records 1013 concentration (Information from Data Sheet) Calculate the effective The operator records 1013 boron concentration: (Step ppm (1013 x 19.8/19.8 = 3.2.3.2B x Step ) 3.2.3.2A)/19.8 = (Step 3.2.3.3) Record the The operator records the effective Boron Effective Boron Concentration: Concentration as 1013 (Step 3.2.3.IB or Step ppm. 3.2.3.2C) = 4 (Step 3.2.4) Desired NC system temperature for The operator records 33°F shutdown margin (Information from Data calculation Sheet) 5 (Step 3.2.5) Number of known inoperable RCCAs The operator records 0 (Information from Data Sheet) 2011 Admin JPM Al a RO
- NUREG 1021, Revision 9
Appendix C Page 6 of 14 Form ES-C-i PERFORMAP.ICE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Step 3.2.6) IF Step 3.2.5> The operator recognizes 0 that Step 3.2.5 is NOT> 0, and proceeds. 7 (Step 3.2.7) IF burn up from step 3.2.2 is > 0 EFPD, The operator records 0 record the difference (Information from Data between equilibrium and Sheet) present samarium worth (P1475, Samarium program on OAC or REACT) 8 (Step 3.2.8) IF burnup from step 3.2.2 is> 12 EFPD The operator recognizes AND unit has been that the Unit has been shutdown > 48 hours shutdown for 15 minutes (Information from Data Sheet), and proceeds 9 (Step 3.3) IF desired, perform automated The operator recognizes calculations using that the REACT computer is REACT.... NOT available (Information from Initial Conditions) 10 (Step 3.4) Manual Calculations The operator addresses Table 1.15 in the Data Book (Step 3.4.1) Stuck Rod and determines the Stuck Boron Concentration: Rod Boron Concentration to (Step 3.4.1.1) Determine be 172 ppm. the Stuck Rod Boron Concentration (Data Book Table 1.15) (Step 3.4.1.2) Record value The operator records 172 in Table 4.5 Line A on Line A of Table 4.5. 2011 Admin-JPMA1aRO NUREG 1021, Revision 9
Appendix C Page 7 of 14 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT II (Note prior to Step 3.4.2) The operator reads the Either the DRPI screen on NOTE and proceeds. the control board OR the OAC may be used to check control rod position.
*12 (Step 3.4.2) Shutdown Boron Concentration:
(Step 3.4.2.1) IF both trains of DRPI indicate all rods on bottom, determine the Shutdown Margin Boron Concentration by the following: The operator determines (Step 3.4.2.1.A) IF Step that Step 3.2.4 is 140°F, 3.2.4 > 200°F and proceeds. (Step 3.4.2.1.B) IF Step The operator addresses 3.2.4 200°F determine the Table 6.13 in the Data Book required shutdown margin and determines the boron concentration for Shutdown Margin Boron burnup of Step 3.2.2 and Concentration to be 1382 33°F (Data Book Table ppm. 6.13, 1.0% Shutdown Margin). (Step 3.4.2.1.C) Record The operator records 1382 value in Table 4.5 Line B on Line B of Table 4.5. (Step 3.4.2.1.D) N/A Step 3.4.2.2 and go to Step The operator will place an 3.4.3. N/A in 2011 Admin-JPMA1a RO NUREG 1021, Revision 9
Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 13 (Step 3.4.3) All rods in Differential Boron Worth: (Step 3.4.3.1) Determine the ARI differential boron worth by the following: (Step 3.4.3.1 .A) IF Step The operator determines 3.2.4 > 200°F that Step 3.2.4 is 140°F, and proceeds. (Step 3.4.3.i.B) IF Step The operator addresses 3.2.4 200°F, determine Table 6.10 in the Data Book the differential boron worth and determines the for burnup of Step 3.2.2 and differential boron worth to lowest tabulated be -9.29. temperature (Data Book Table 6.10). The operator records -9.29 (Step 3.4.3.2) Record value on Line C of Table 4.5. in Table 4.5 Line C 14 (Step 3.4.4) Zero Power Physics Testing Penalty: (Step 3.4.4.1) Determine the ZPPT penalty: If the shutdown margin is being determined after refuel and before ZPPT The operator recognizes (Step 3.4.4.1.B) IF this that this shutdown is being shutdown margin is being performed after the ZPPT, determined after the ZPPT, and that the penalty is 0 the penalty is 0 ppm. ppm. (Step 3.4.4.2) Record value The operator records 0 ppm in Table 4.5 Line D on Line D of Table 4.5. 2011 Admin-JPMA1aRO NUREG 1021, Revision 9
Appendix C Page 9 of 14 Form ES-C-i PERFORMANCE INFORMAT[ON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 15 (Step 3.4.5) Calculations: (Step 3.4.5.1) Record The operator records 0 on values of Steps 3.2.5, 3.2.7 Line E of Table 4.5. and 3.2.8 in Table 4.5. The operator records 0 on Line F of Table 4.5. The operator records 2 on Line G of Table 4.5. (Step 3.4.5.2) Complete Table 4.5, recording 0 for any NAd reference steps. The operator calculates H H = E x A (0 x 172) 0 and records 0 on Line H of Table 4.5. The operator calculates I I = F/C (01-8.9) = 0 and records 0 on Line I of Table 4.5. The operator calculates SDM = (B+D÷G+H)
= SDM and records 1382 on (1382+0+0+0) 0 = 1382 Line SDM of Table 4.5.
2011 Admin-JPMA1aRO NUREG 1021, Revision9
Appendix C Page 10 of 14 Form ES-C-I PERFORMANCE [NFORMATIOI STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*16 (Step 3.5) Results: The operator recognizes that the Effective Boron (Step 3.5.1) IF Effective NC Concentration is < Table Boron Concentration of 4.5, and proceeds.
Step 3.2.3.3 > Table 4.5 or REACT output (Step 3.5.2) IF Effective Boron Concentration of The operator identifies that Step 3.2.3.3 < Table 4.5 or the Effective Boron REACT Output: Concentration must be raised to 1382 ppm before (Step 3.5.2.1) If OAC is the cooldown can be available, increase initiated. measured NC Boron Concentration to the following value prior to decreasing to or maintaining temperature of Step 3.2.4. [Table 4.5] x 19.8/Step 3.2.3.2A = [1382] x 19.8/19.8 = 1382 (Step 3.5.2.2) IF OAC is unavailable Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2011 Admin JPM Al a RO
- NUREG 1021, Revision 9
Appendix C Page 11 of 14 Form ES-C-i VER[F[CAT[ON OF COMPLET[ON Job Performance Measure No.: 2011 Admin JPM Ala RO Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin JPM Al a RO
- NUREG 1021, Revision 9
Appendix C Page 12 of 14 Form ES-C-i
- VERIFICATION OF COMPLETION KEY:
Table 4.5: Shutdown margin Modes 5, 4 or 3 Without Xenon Credit Description Reference Value A. Stuck Rod Boron Step 3.4.1 l72ppm Concentration B. Shutdown Boron Step 3.4.2 1382ppm Concentration
- C. ARI DBW Step 3.4.3 -9.29 pcm/ppm D. ZPPT Penalty Step 3.4.4 Oppm E. Number of Stuck RCCAs Step 3.4.5 0 F. Duff from Eq Sm Worth Step 3.4.7 Opcm G. Shutdown Fission Product Step 3.4.8 Oppm Worth H. Stuck Rod Penalty ExA Oppm 0 x 172 I. Samarium Adjustment F ÷ C Oppm 0 ÷ -9.29 Shutdown Margin Modes 5, ( B +D ÷ G + H) I i382ppm 4or3 (1382+0+0+0)(0) 2011 Admin JPM Ala RO
- NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMCUESHEET DATA SHEET Unit I Current Cycle 21 Inoperable Control Rod(s) None Current Power Level 0% Present NC system temperature 557 degrees Desired NC system temperature 140 degrees Cycle Burnup (P1457) 200 EFPD Present NCS Boron Concentration (sample) 1013 ppm B-b Atom Percent, Best Estimate (P561 3) 19.8 A Samarium from equilibrium (P1475) 0 pcm DRPI Indication (Both Trains) All rods on Bottom NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMCUESHEET Initial Conditions:
- Unit 1 was shutdown to Mode 3, 15 minutes ago.
- You are the Unit 1 Operator at the Controls (OATC).
- The reactivity computer (REACT) is out of service.
- Unit 1 OAC is available.
- Preparations are being made to commence a plant cooldown to Mode 5.
INITIATING CUE:
- Based on the information provided to you on the Data Sheet, perform a Shutdown Margin Calculation per 0P101A161001006 Enclosure 4.5 (Shutdown Margin Unit Shutdown, Modes 5, 4, or 3 Without Xenon Credit).
- Identify whether or not the cooldown can be initiated under the present conditions.
NUREG 1021, Revision 9
Duke Egy Procedure No. McGuire Nuclear Station oP/O/A/6loo/oo6 Reactivity Balance Calculation Revision No. 072 Electronic Reference No. MC0046X5 Continuous Use PERFORMANCE I UNCONTROLLED FORPRINT* * * * * * * * * * (ISSUED) PDF Format
Eac1Qs11r OP/OiA/100/006 Shutdown Margin Unit Shutdown
- Page 1 of 6 Modes 5, 4 or 3 Without Xenon Credit NOTE: Enclosure 4.5 can be used to verify shutdown margin for an intermediate temperature above 200°F. For temperatures equal to or below 200°F the 33°F shutdown margin values shall be used.
- 1. Limits and Precautions 1.1 Shutdown margin shall be 1000 pcm in Mode 5 per Technical Specification 3.1.1.
1.2 Shutdown margin shall be 1300 pcm in Mode 2 with Keff< 1.0, Mode 3 and Mode 4 per Technical Specification 3.1.1. 1.3 NC System Effective Boron Concentration shall be shutdown margin required boron concentration for a new system Tavg before beginning NC system Tavg change in Modes 3, 4and5. 1.4 Shutdown margin shall be verified prior to any intentional controlled cooldown below 550 °F. 1.5 Use Enclosure 4.6 if it is desired to take credit for Xenon in the shutdown margin. 1.6 This Enclosure may be used to verify shutdown margin while in Mode 2 with Keff < 1.0. 1.7 Shutdown Margin is satisfied if NC boron concentration is above the minimum refueling boron concentration value provided in the COLR.
- 2. Initial Conditions None
- 3. Procedure NOTE: All curves/tables used in this procedure are found in OP/i (2)/A16 100/022 (Unit One (Two) Data Book). These procedures will be referred to as the Data Book.
3.1 IF NC Boron Concentration refueling boron concentration from COLR: Iv D 3.1.1 Shutdown Margin is met. Q 3.1.2 Exitthis Enclosure. 3.2 Record the following: Q 3.2.1 Unit Cycle C 3.2.2 Bumup (P1457) EFPD
Enchsure - oOiioomo6 Shutdown Margin Unit Shutdown
- Page 2 of 6 Modes 5, 4 or 3 Without Xenon Credit 3.2.3 NC System Effective Boron Concentration 3.2.3.1 IF OAC is unavailable:
U A. Record the current NC Boron Concentration: ppm U B. Apply 100 ppm B-10 correction penalty: (Step 3.2.3.1A 100)
-100)= ppm 3.2.3.2 IF OAC is available:
U A. Record B-lU Atom Percent, Best Estimate (P5613): % U B. Record the current NC boron concentration: ppm U C. Calculate the Effective Boron Concentration: (Step 3.2.3.2B x Step 3.2.3.2A) ÷ 19.8 x ppm U 3.2.3.3 Record the Effective Boron Concentration: (Step 3.2.3.1B or Step 3.2.3.2C) = ppm U 3.2.4 Desired NC system temperature for shutdown margin calculation U 3.2.5 Number of known inoperable RCCAs 3.2.6 IF Step 3.2.5 > 0, record Inoperable RCCA core location(s) 3.2.7 IE burnup from Step 3.2.2 is > 0 EFPD, record the pcm difference between equilibrium and present samarium worth (P 1475, Samarium program on OAC or REACT). {MCEI-0400-150} 3.2.8 jbumup from Step 3.2.2 is> 12 EFPD AND unit ppm has been shutdown> 48 hours, perform Enclosure 4.8 to determine Shutdown Fission Product Worth Correction.
Enclosure 4 oP/O/A/61001Oo6 Shutdown Margin Unit Shutdown
- Page 3 of 6 Modes 5, 4 or 3 Without Xenon Credit 3.3 IF desired, perform automated calculations using REACT (Reactivity Balance SDM - -
Mode 5, 4 or 3 module) by performing the following: D 3.3.1 Enter data from Section 3.2 into REACT and calculate, ensuring the Effective Boron Concentration from Step 3.2.3.3 is used as the Present NC System Boron concentration. D 3.3.2 Attach REACT output to this Enclosure. D 3.3.3 N/A Step 3.4 and go to Step 3.5. 3.4 Manual Calculations: 3.4.1 Stuck Rod Boron Concentration: Q 3.4.1.1 Determine the Stuck Rod Boron Concentration (Data Book Table 1.15). Q 3.4.1.2 Record value in Table 4.5 Line A. NOTE: Either the DRPI screen on the control board j3 the OAC may be used to check control rod position. 3.4.2 Shutdown Boron Concentration: 3.4.2.1 IF both trains of DRPI indicate ALL rods on bottom, determine the Shutdown Margin Boron Concentration by the following: A. IF Step 3.2.4> 200°F, determine the required shutdown margin boron concentration for burnup of Step 3.2.2 and temperature of Step 3.2.4 from Data Book Table 6.13, 1.3% Shutdown Margin with ART. B. j Step 3.2.4 200°F, determine required shutdown margin boron concentration for burnup of Step 3.2.2 and 33°F from Data Book Table 6.13, 1.0% Shutdown Margin with ART. Q C. Record value in Table 4.5 Line B. D D. N/A Step 3.4.2.2 and go to Step 3.4.3.
Enchsure OP/O/A!6100/006 Shutdown Margin Unit Shutdown
- Page 4 of 6 Modes 5, 4 or 3 Without Xenon Credit 3.4.2.2 Determine the Shutdown Margin Boron Concentration by the following:
A. j Step 3.2.4> 200 °F, determine the required shutdown margin boron concentration for bumup of Step 3.2.2 and temperature of Step 3.2.4 from Data Book Table 6.5, 1.3% Shutdown Margin. B. IF Step 3.2.4 200 °F, determine the required shutdown margin boron concentration for burnup of Step 3.2.2 and 33°F from Data Book Table 6.5, 1.0% Shutdown Margin. fl C. Record value in Table 4.5 Line B. 3.4.3 All Rods In Differential Boron Worth: 3.4.3.1 Determine the ART differential boron worth by the following: A. IF Step 3.2.4 > 200 °F, determine the differential boron worth for bumup of Step 3.2.2 and temperature of Step 3.2.4 (Data Book Table 6.10) B. IF Step 3.2.4 200 °F, determine the differential boron worth for burnup of Step 3.2.2 and lowest tabulated temperature (Data Book Table 6.10). Q 3.4.3.2 Record value in Table 4.5 Line C. 3.4.4 Zero Power Physics Testing penalty: 3.4.4.1 Determine the ZPPT penalty: A. this shutdown margin is being determined after refuel and before ZPPT, the penalty is 100 ppm. B. IF this shutdown margin is being determined after ZPPT, the penalty is 0 ppm. Q 3.4.4.2 Record value in Table 4.5 Line D.
Enclosure 4S oP/O/A/6 1 OO!O06 Shutdown Margin - Unit Shutdown Page 5 of 6 Modes 5, 4 or 3 Without Xenon Credit
3.4.5 Calculations
0 3.4.5.1 Record values of Steps 3.2.5, 3.2.7 and 3.2.8 in Table 4.5. O 3.4.5.2 Complete Table 4.5, recording 0 for any N/Ad reference steps. Table 4.5: Shutdown Margin Modes 5, 4 or 3 Without Xenon Credit Description Reference Value A. Stuck Rod Boron Concentration Step 3.4.1 ppm B. Shutdown Boron Concentration Step 3.4.2 ppm C. ARI DBW Step 3.4.3 pcmlppm D. ZPPT Penalty Step 3.4.4 ppm B. Number of Stuck RCCAs Step 3.2.5 F. Diff from Eq Sm Worth Step 3.2.7 pcm G. Shutdown Fission Product Worth Step 3.2.8 ppm H. Stuck Rod Penalty ExA X ppm I. Samarium Adjustment F + C ppm Shutdown Margin Modes 5, 4 or 3 (B+D+G+H)-I (___ +
+ +
ppm
nc1osur 4.5-OP/O/A16100!006 Shutdown Margin Unit Shutdown
- Page 6 of 6 Modes 5, 4 or 3 Without Xenon Credit
3.5 Results
3.5.1 IF Effective NC Boron Concentration of Step 3.2.3.3 Table 4.5 or REACT output, adequate shutdown margin exists for temperature of Step 3.2.4.
3.5.2 Effective NC Boron Concentration of Step 3.2.3.3
3 EFPD from previous shutdown to current shutdown: El 3.1.1.1 Use Data Book Table 6.7 to determine the shutdown fission product correction: El 3.1.1.2 Number of hours shutdown hrs El 3.1.1.3 Shutdown Fission Product Correction: ppm 3.1.2 IF Unit operated < 1 EFPD from previous shutdown to current shutdown: El 3.1.2.1 Use Data Book Table 6.7 to determine the shutdown fission product correction based on the number of hours since the first shutdown: El 3.1.2.2 Number of hours since shutdown hrs U 3.1.2.3 Shutdown Fission Product Correction: ppm Encksure L2 - OP/O/A!6100/0fl6 Fission Product Correction Calculation Page 2 of 2 3.1.3 fl Unit operated between 1 EFPD and 3 EFPD from previous shutdown to current shutdown and current shutdown <72 hours use Data Book Table 6.7 to determine the shutdown fission product correction based on the following: 3.1.3.1 Previous Shutdown: a A. Number of hours during previous shutdown: hrs a B. Shutdown fission product correction: ppm 3.1.3.2 Current Shutdown: D A. Number of hours since current shutdown: hrs a B. Shutdown fission product correction: ppm a 3.1.3.3 Shutdown Fission Product Correction: (Step 3.1.3.1B x 0.5) + Step 3.1.3.2B = ppm 3.1.4 fl Unit operated between 1 EFPD and 3 EFPD from previous shutdown to current shutdown and current shutdown> 72 hours: a 3.1.4.1 Use Data Book Table 6.7 to determine the shutdown fission product correction using the time of the current shutdown only. a 3.1.4.2 Number of hours shutdown hrs a 3.1.4.3 Shutdown Fission Product Correction: ppm OF 00!022 of 2 1 U 1 Enclosure 4.3 Table 6.5 Shutdown Boron Concentration McGuire I Cycle 21 1.0% Shutdown Margin Required Boron Concentration for 1.0% Shutdown Margin as a Function of Temperature and Burnup Core Average Temperature (°F) BURNUP (EFPD) 33 68 70 80 90 100 110 120 130 140 150 160 170 180 190 200 0 1622 1614 1614 1612 1610 1608 1606 1604 1603 16ó1 1599 1597 1595 1593 1590 1588 4 1621 1613 1613 1611 1609 1607 1605 1604 1602 1600 1598 1596 1594 1592 1590 1587 25 1615 1607 1607 1605 1603 1602 1600 1598 1597 1595 1593 1591 1589 1587 1585 1582 50 1606 1599 1599 1597 1596 1594 1592 1591 1589 1588 1586 1584 1582 1580 1577 1575 75 1596 1589 1589 1587 1586 1584 1582 1581 1579 1578 1576 1574 1572 1570 1568 1565 - 100 1581 1575 1575 1573 1572 1570 1569 1567 1566 1564 1562 1561 1559 1556 1554 1552 125 1563 1557 1557 1555 1554 1552 1551 1549 1548 1546 1544 1542 15403 1538 1536 1533 - : 150 1540 1533 1533 1531 1530 1528 1526 1525 1523 1522 1520 1518 15i 1514 1512 1509 175 1510 1501 1500 1498 1497 1495 1494 1492 149,1 1489 1488 1486 1484 1482 1479 1476 200 1475 1463 i463 1460 1459 14S7 1456 1454 1453 1452 1450 1448 t446 1444 1441 1437 .j. 225 1432 1421 t421 1419 1417 14I5 1414 1412 1411 1409 1408 1406 14@3- 1401 1398 1395 250 1384 1376 1376 1374 1372 1370 1368 1367 1365 1363 1361 1359 1357 1354 1352 1349 275 1336 1328 1327 1325 1324 1322 1320 1318 1316 1314 1312 1310 1308 1305 1302 1300 300 1285 1277 1276 1274 1272 1270 1269 1267 1265 1262 1260 1258 1255 1253 1250 1247 325 1232 1223 1223 1221 1218 1216 1214 1212 1210 1208 1206 1203 1201 1198 1195 1191 350 1177 1167 1167 1164 1162 1160 1158 1156 1154 1151 1149 1146 1144 1140 1137 1133 375 1120 1108 1108 1105 1103 1101 1099 1097 1094 1092 1090 1087 1084 1080 1077 1072 400 1060 1048 1047 1045 1042 1040 1038 1035 1033 1031 1028 1025 1022 1019 1014 1010 425 999 986 985 982 980 977 975 972 970 967 965 962 958 955 951 946 450 936 922 921 918 916 913 911 908 906 903 900 897 893 889 885 880 475 871 857 857 854 851 848 845 843 840 837 834 831 827 823 818 813 485 844 831 830 827 825 822 819 816 813 810 807 804 800 796 791 786 524 737 728 727 725 722 719 716 713 709 706 702 698 694 690 685 680 Note: Most Reactive Rod Stuck Out, boron in PPM UNIT I u OF 1001022 Enclosure 4.3 Table 6.5 2 of Shutdown Boron Concentration McGuire I Cycle 21 1.3% Shutdown Margin Required Boron Concentration for I 3% Shutdown Margin as a Function of Temperature and Burnup Core Average Temperature (°F) BURNUP (EFPD) 200 225 250 275 300 325 350 375 400 425 450 475 500 525 550 557 0 1626 1623 1619 1614 1609 1603 1595 1586 1575 1562 1544 1522 1494 1458 1414 1400 4 1625 1622 1618 1613 1607 16Q1 1593 1584 1573 1560 1544 1522 1494 1458 1414 1400 25 1622 1618 1613 1606 1599 1591 1582 1574 1564 1553 1537 1516 1489 1455 1412 1398 50 1615 1611 1605 1597 1589 1579 1570 1561 1552 1540 1525 1505 1479 1445 1402 1388 75 1605 1600 1594 1586 1577 1567 1557 1548 1537 1525 1509 1489 1462 1428 1385 1371 100 1591 1586 1579 1571 1562 1552 1542 1531 1518 1505 1488 1467 1440 1405 1361 1346 125 1572 1566 1560 1552 1543 i533 1522 1509 1495. 1480 1462 1439 1411 1375 1329 1315 150 1547 1541 1534 1527 1518 :Th08 1496 1482 1465 1450 1430 1406 1376 1338 1291 1276* 175 1514 .1508. 1501 1493 1484 1473 1460 1446 .t430 - 1412 1392 1366 1334 1294 1245 1230-200 1475 1470 1463 1454 1444-1432 1419 1405 1388. 1370 1348 1321 1287 1245 1194 1178 225 1432 1427 -1419 1410 1400 -1387 1374 1359 1341 1322 1299 1271 :236 1192 1139 1122 250 1386 1379 1371 1362 1351 1338 1324 1308 1290 1270 1246 1217 1180 1135 1079 1061 275 1336 1.329 1321 1311 1299 1286 1271 1254 1235 1214 1189 1159 1120 1073 1015 996 300 1283 1275 1266 1256 1244 1230 1215 1197 1177 1155 1129 1097 1057 1008 947 928 325 1228 1219 1209 1198 1186 1172 1155 1137 1115 1093 1066 1032 991 939 876 856 350 1169 1160 1149 1138 1125 1110 1093 1073 1051 1027 999 964 921 868 802 781 375 1108 1098 1087 1075 1061 1046 1028 1007 984 959 929 893 848 792 724 703 400 1045 1034 1023 1010 996 979 960 939 914 888 857 819 773 715 644 622 425 979 969 957 943 928 911 891 869 843 816 783 744 695 635 562 539 450 913 902 889 875 859 841 820 797 770 741 708 666 616 554 479 455 475 845 834 820 805 789 769 748 723 696 666 631 588 536 472 394 370 485 818 806 792 777 760 741 719 694 665 635 600 556 504 439 360 336 524 711 697 683 666 648 627 604 577 547 515 477 432 377 310 228 202 Note: Most Reactive Rod Stuck Out, boron in PPM . UNIT I UNIT I OP/I 1N61 00/22 ENCLOSURE 4.3 TABLE 1.15 CYCLE 21 EMERGENCY PROCEDURE (EP) SETPOINTS Sources: MCC-1 552.08-00-0208, Rev. 23, Emergency Procedure Setpoints MCEI-0400-231, Rev. 0 McGuire 1 Cycle 21 Startup and Operational Report The Imperfect Mixing Boron Concentration must be at least 150 ppm.REFERENCE:
EPI1/AI5000IES-0.2, Natural Circulation Cooldown The Stuck Rod Boron Concentration Allowance must be at least 172 ppm
REFERENCE:
EP/1/A/5000/ES-0.1, Reactor Trip 1(. UNIT I
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OJ 00I022 UI Enclosure -.3 Table 6.10 ARI Differential Boron Worth as a function of Temperature and Burnup (pcm!ppm) Unit I Cycle 21 BURNUP TEMPERATURE (EFPD) 68 100 150 200 250 300 350 400 450 500 520 540 550 557 0 -9.00 -8.95 -8.82 -8.63 -8.42 -8.20 -7.95 -7.68 -7.37 -7O5 -6.89 -6.73 -6.66 -6.60 4 -9.00 -8.95 -8.82 -8.63 -8.42 -8.20 -7.95 -7.68 -7.37 -7.05 -6.89 -6.73 -6.65 -6.60 25 -9.01 -8.96 -8.83 -8.64 -8.42 -8.21 -7.96 -7.68 -7.37 -7.05 -6.89 -6.73 -6.65 -6.60 50 -9.03 -8.98 -8.84 -8.65 -8.43 -8.21 -7.96 -7.69 -7.37 -7.05 -6.89 -6.73 -6.65 -6.59 75 -9.04 -8.99 -8.85 -8.66 -8.44 -8.22 -7.97 -7.69 -7.37 -7.05 -6.89 -6.73 -6.65 -6.59 100 -9.08 -9.02 -8.88 -8.69 -8 -8.25 -8.00 -7:72 -7.40 -7.08 -6:92 -6.76 -6.68 -&.62 125 -9.11 9:;Q5 -8.92 -8,73 -80 -8.28 -8.03 -7;75 -7.43 -7.11 -&E95 -6.79 -6.71 -665 150 -9.15 -9.09.. -8.95 -8.76 -8.5.3 -8.31 -8.06 *-7..78. -7.46 -7.14 -6.98 -6.82 -6.74 ** -68 175 -9.22 -9.6 -9.02 -8.83 * -8:60 -8.37 -8.12 -734 -7.52 -7.20 -7O3 -6.87 -6.79 -&74 200 -9.29 -9.24 -9.09 -8.90 -8:67. -8.44 -8.18 -7.90 -7.58 -7.25 -7.09 -6.93 -6.85 -6.79 225 -9.39 -9.34 -9.19 -8.99 -8.76 -8.53 -8.27 -7.98 -7.65 -7.32 -7.16 -7.00 -6.92 -6.86 250 -9.49 -9.43 -9.28 -9.08 -8.84 -8.61 -8.35 -8.06 7.73 -7.40 -7.24 -7.07 -6.99 -6.93 275 -9.62 -9.56 -9.41 -9.20 * -8.96 -8.72 -8.46 -8.16 -7.83 -7.50 -7.33 -7.17 -7.09 -7.03 300 -9.75 -9.68 -9.53 -9.32 -9.08 -8.83 -8.57 -8.27 -7.93 -7.60 -7.43 -7.27 -7.18 -7.13 325 -9.88 -9.81 -9.65 -9.44 -9.19 -8.95 -8.67 -8.37 -8.03 -7.69 -7.53 -7.36 -7.28 -7.22 350 -10.01 -9.94 -9.78 -9.56 -9.31 -9.06 -8.78 -8.47 -8.13 -7.79 -7.63 -7.46 -7.38 -7.32 375 -10.18-10.10 -9.94 -9.72 -9.46 -9.21 -8.92 -8.61 -8.27 -7.92 -7.76 -7.59 -7.51 -7.45 400 -10.34 -10.27 -10.11 -9.87 -9.61 -9.35 -9.07 -8.75 -8.40 -8.06 -7.89 -7.72 -7.63 -7,58 425 -10.50 -10.43 -10.27 -10.03 -9.77 -9.50 -9.21 -8.88 -8.54 -8.19 -8.02 -7.85 -7.76 -7.70 450 -10.67 -10.60 -10.43 -10.19 -9.92 -9.65 -9.36 -9.02 -8.67 -8.32 -8.15 -7.98 -7.89 -7.83 475 -10.87 -10.80 -10.62 -10.38 -10.10 -9.83 -9.53 -9.19 -8.83 -8.48 -8.31 8.14 -8.05 -8.00 485 -10.95 -10.88 -10.70 -10.45 -10.17 -9.90 -9.60 -9.26 -8.90 -8.54 -8.37 -8.21 -8.12 -8.06 524 -11.26 -11.19 -11.00 -10.74 -10.46 -10.17 -9.86 -9.52 -9.15 -8.79 -8.63 -8.46 -8.38 -8.32 UNIT 1.
UI. 4. OP. 00I022 of Enclosure 4.3 Table &13 Shutdown Boron ARI McGuire I Cycle 21 Shutdown Margin with ARI Required Boron Concentration for 1.0% Shutdown MargiA as a Function of Temperature and Burnup Core Average Temperature (°F) BURNUP (EFPD) 33 68 70 80 90 100 110 120 130 140 150 160 170 180 190 200 0 1550 1543 1543 1540 1538 1535 1532 1529 1526 1523 1520 1517 1513 1510 1507 1503 4 1548 1541 1540 1538 1535 1533 1530 1527 1524 1521 1518 1515 1512 1508 1505 1501 25 1539 1530 1529 1526 1524 1521 1519 1516 1513 1511 1508 1505 1502 1499 1496 1493 50 1526 1516 1515 1513 1510 1508 1505 1503 1500 1498 1495 1493 1490 1487 1484 1481 75 1511 1501 1500 1498 1495 1493 1491 1488 1486 1483 1481 1479 1476 1473 1471 1468 100 1493 1484 1483 1481 . 1479 1476 1474 1472 1469 1467 1464 1462 1459 1457 1454 1452 125 . 171. 1464 1463 1461.1459 1456 1454 .1452 1449 1447 1444*1442 1439 1437 ... 1434 1432 150 .1446 1439 1439 1436I 1434 1432 1430 1427 1425 1422 1420.. 1417 1415 1412 .; 1410 1407 175 1418 1410 1409 1407. 1405 1403 140t.. 1399.. 1396 1394 1391 - 1389 1386 1383 1380 1377 200 -1382 1373 1373 137Q 1368 1366 1364 .i362 - 1360 1357 1355 - 1352 1350 1347.- 1344 .1340 225 1332 1323 1322 1320 1318 1316 1314 - i3T2 1310 1307 130 1303 1300 1297 - 1294 1291 250 1275 1267 1267 1264 1262 1260 1258 1256 1253 1251 1249 1247 1244 1242 1240 1237 275 1227 1218 1218 1215 1213 1211 1209 1206 1204 1202 1200 1197 1195 1192 1190 1187 300 1181 1170 1170 1167 1165 1162 1160 1158 1156 1153 1151 1149 1146 1143 1141 1138 325 1134 1122 1122 1119 1116 1114 1111 1109 1107 1104 1102 1099 1097. 1094 1091 1087 350 1086 1072 1071 1068 1066 1063 1061 1058 1056 1053 1051 1048 1045 1042 1039 1035 375 1028 1014 1013 1010 1007 1005 1002 1000 998 996 . 993 991 988 984 981 977 400 967 952 952 949 946 944 942 939 937 935 933 930 927 924 920 916 425 903 889 889 886 883 881 879 877 875 873 870 868 865 862 858 854 450 838 825 824 822 819 817 815 813 811 808 806 803 800 797 793 789 475 . 772 760 759 757 754 752 750 748 745 743 741 738 735 731 727 723 485 745 734 733 731 728 726 724 722 719 717 714 711 708 704 700 696 524 641 633 633 630 628 625 622 619 616 613 610 606 603 599 595 590 UNIT 1
OP. 1OOIO22 ui Enclosure 4.3 Table 6.13 zofZ Shutdown Boron ARI McGuire I Cycle 21 Shutdown Margin with ARI Required Boron Concentratio for 1.3% SDM as a Function of Temperature and Burnup n Core Average Temperature (°F) BURNUP (EFPD) 200 225 250 275 300 325 350 375 400 425 450 475 500 525 550 557 0 1516 1510 1504 1497 1490 1482 1472 1461 1447 1432 1412 1388 1357 1318 1269 1254 4 1515 1509 1503 1497 1490 1481 1472 1461 1447 1432 1413 1389 1358 1319 1271 1256 25 1508 1503 1497 1492 1486 1478 1470 1459 1446 1432 1414 1390 1360 1323 1276 1261 50 1498 1493 1488 1483 1478 1471 1463 1453 1441 1427 1409 1386 1357 1320 1273 1258 75 1485 1480 1476 1471 1466 1460 1452 1442 1430 1416 1398 1375 1346 1309 1262 1247 100 1469 1464 1459 1455 1450 1444 1436 1426 1414 1400 1382 .1358 1328 1290 1242 1227 125 1448... 1443 1439 1434 -1429 1423 1415 1405: 1393 1378 1359 --4335 1304 1264 -1215 1199 150 1423 1418 1414 1409 1403 1396 1388 1378 1365 1350 13301305 1272 1231 . 1180 1164 175 .1392 1387 1382 1377 13.71 1363 1354 -1344 1331 1315 1294 1267 1233 1191 --1138 1121 200 135.6 1352 1347 1341 1334 1326 1316 1305 1291 1274 1252 1225 1189 1144 1089 1072 225 1316 1312 1307 1301 1Q93 1284 1274 1262 1247 1229 1206 Y1177 1140 1093 1036 1017 250 1273 1269 1263 1256 1248 1238 1227 1214 1199 1180 1156 1125 1086 1037 977 958 275 1227 1222 1216 1208 1199 1189 1177 1163 1147 1127 1101 1069 1028 977 914 895 300 1177 1172 1165 1157 1148 1136 1123 1109 1091 1070 1043 1009 966 913 848 828 325 1125 1119 1112 1103 1092 1080 1066 1050 1032 1009 980 945 900 845 778 757 350 1070 1063 1055 1045 1034 1021 1006 989 969 945 915 877 831 774 705 683 375 1011 1003 995 984 972 959 943 925 903 878 846 807 759 700 628 606 400 950 941 932 921 908 894 877 858 835 808 775 734 684 623 549 526 425 886 877 867 855 842 827 809 789 764 736 702 659 607 544 468 444 450 821 811 800 788 774 758 739 718 692 663 627 583 529 464 385 360 475 754 744 732 719 704 687 667 645 618 588 550 505 449 382 301 275 485 727 717 705 691 676 659 639 616 588 557 519 473 417 349 267 241 524 621 609 596 582 565 546 524 500 471 438 398 350 291 220 135 108 UNIT
Appendix C Job Performance Measure Form ES-C-i Worksheet JPMAIbRO 2011 Admin-JPMA1b RO(Rev_041111) NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-i Job Performance lvieasure Worksheet Facility: McGu ire Task No.: Task
Title:
Calculate Dilution Needed for a JPM No.: 2011 Admin JPM Al b Specified Rod Change RO K/A
Reference:
GKIA 2.1.25 (3.9/4.2) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Class room X Simulator Plant 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: . Unit #1 Reactor Power is at 100%, Steady State.
- Core burnup is 200 EFPD.
- NC Boron Concentration = 918 PPM.
- Present Control Rods Bank D at 215 steps.
- Desired Rod Height is Control Rods Bank D at 180 steps.
Task Standard: Dilution of approximately 1407 gallons is calculated within +/- 100 gallons. All critical tasks evaluated as satisfactory. Required Materials: Calculator General
References:
OP/1/A/6150/009 (Boron Concentration Control), Rev 106 OP/1/A/6l00/022 (Unit 1 Data Book) Cycle 21, Rev 480 Handouts: OP/l/A/6100/022 (Unit 1 Data Book) Cycle 21, Enclosure 4.3 Section 5.1 Boration and Dilution Tables OP/l/A/6100/022 (Unit 1 Data Book) Cycle 21, Enclosure 4.3 Table 6.3.3 Integral Rod Worth in Overlap HFP, Equilibrium Xenon OP/1/A161 00/022 (Unit 1 Data Book) Cycle 21, Enclosure 4.3 Graph 6.11 Differential Boron Worth (HFP, ARC, Eq Xe, Eq Sm) 2011 Admin JPM Al b RO
- NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-i Job Performance Measure Worksheet Initiating Cue: The CRS has directed you to determine the amount of reactor makeup water needed to obtain the desired Control Rod Height using the McGuire Unit 1 Data Book. Time Critical Task: NO Validation Time: 20 minutes 2011 Admin JPM Al b RO
- NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*) Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout the three listed handouts. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR U N SAT
*1 Operator determines 215 Initial inserted steps integral rod worth reactivity worth =
using the 151-250 EFPD column of 14 pcm OP/I /A161 00/22, Enclosure 4.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
*2 Operator determines 180 Desired Rod height steps integral rod worth inserted reactivity using the 151 -250 EFPD worth =
column of OP/1/A/6100/22, 126 pcm Enclosure 4.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
*3 Operator determines the Change in reactivity to change in reactivity be compensated due to required for the rod rod insertion =
insertion 126 pcm
-14 pcm 112 pcm
*4 Using OP/1/A/6100/22, Operator determines the Enclosure 4.3, Graph Differential Boron Worth 6.1 1 Differential Boron from the graph to be =
Worth (HFP, ARO, Eq -6.27 pcm/ppm Xe, Eq Sm, Unit 1 Cycle
- 21) determines the Differential Boron Worth for present conditions (200 EFPD) 2011 Admin JPM Al b RO
- NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-i PERFORMANCE INFORMATiON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 Using the Differential Operator determines the Boron Worth and the change in Boron Change in reactivity, Concentration to be = determines the change in 112! -6.27 pcmlppm Boron Concentration
= -17.9 ppm 6 Operator determines Change in Boron =
Boron Concentration 918 18 ppm required 900 ppm
*7 Using 0P111A16100122, Using Present Boron Enclosure 4.3 Section 5.1 Concentration 918 ppm Boron and Dilution and the Desired Boron Tables, determines the Concentration of 900 Reactor Makeup Water ppm, determines from addition Table that change from 920-900 ppm will require the addition of 1481 gallons of reactor makeup water.
OR Calculation: 67388 x Ln(918/900) = 1334 gallons. Total Makeup Water to add = 1407+/- 100 gallons (1307-1 507 gallons). Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2011 Admin JPM Al b RO
- NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-i VERIFICATiON OF COMPLTiON V V V Job Performance Measure No.: 2011 Admin JPM Al b RO Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin JPM Al b RO NUREG 1021, Revision 9
Appendix C Form ES-C-i
- JPfvtCUE SHEET INITIAL CONDITIONS:
- Unit #1 Reactor Power is at 100%, Steady State.
- Core burnup is 200 EFPD.
- NC Boron Concentration = 918 PPM.
- Present Control Rods Bank D at 215 steps.
- Desired Rod Height is Control Rods Bank D at 180 steps.
INITIATING CUE: The CRS has directed you to determine the amount of reactor makeup water needed to obtain the desired Control Rod Height using the McGuire Unit 1 Data Book. NUREG 1021, Revision 9
OPIIIAI6I 00122 Enclosure 4.3 - Section 5.1 Boration and Dilution Tables lhe attached tables provide the information to determine the number of gallons of boric acid or demineralized water to accomplish a boron change between 10 ppmB and 2700 ppmB. In the compilation of these tables, it was assumed that makeup concentrations for dilution and boration were 0 ppmB and 7000 ppmB, respectively. While all possible boron changes could not be listed in the tables, the volumes are additive and any maneuver between 10 ppmB and 2700 ppmB can be determined. Instructions: A. Note the present Reactor Coolant System (N CS) boron concentration and proceed to the table which includes this value. B. In the left column, find the NCS boron concentration that is desired. (If the desired boron concentration is not on this table, an additive method must be utilized. See Example #2). C. If the desired NCS boron concentration is less than the initial NCS boron concentration (i.e. dilution), a value above the zero line will be read. Ihis value corresponds to the number of gallons of demineralized water which must be made up to the system. D. If the desired NCS boron concentration is greater than the initial N CS boron concentration (i.e. boration), a value below the zero line will be read. Ibis value corresponds to the number of gallons of boric acid which must be made up to the system. E. When diluting or borating in Modes 3, 4 or 5, a correction factor, K, must be applied to the makeup amount obtained from the tables. Ihe appropriate correction factor, K, is obtained from fable 5.2, Makeup Concentration Equations. Example #1 Present NCS boron concentration = 960 ppmB Desired NCS boron concentration 790 ppmB lurn to the proper page and locate 960 across the top. Locate 790 in the left column. Read 13134 gallons of demineralized water. (Above the zero line.) Example #2 Present boron concentration 250 ppmB Desired boron concentration 650 ppmB Iurn to the proper page and locate 250 across the top. Ihe number 650 does not appear in the left hand column. However, the volume of boric acid to change boron from 250 ppmB to 650 ppmB is equal to the volume of boric acid to change boron from 250 ppmB to 500 ppmB plus the volume of boric acid to change from 500 ppmb to 650 ppmB. Volume B.A. (250 to 650) = Volume B.A. (250 to 500) + Volume B.A. (500 to 650) Locate 500 in the left column. Read 2543 gallons of boric acid. Iurn two pages ahead and locate 500 across the top. Locate 650 in the left column. Read 1573 gallons of boric acid. Iheretre, 2543 + 1573, or 4116 gallons of boric acid must be made up to the system. U N11 I
OPII 11100122 EncIosure4 - Section 51 Boration and Dilution Tables Example #3 (Dilution or boration in Modes 3, 4 or 5). Present Conditions: NCS boron concentration: 700 ppmB NCS 1avg: 495 °F NCS Pressure: 1570 psig Pressurizer Level: No-Load Correction Factor, K: 1.10 Desired boron concentration: 900 ppmB Locate 700 across the top. Locate 900 in the left column. Read 2174 gallons of boric acid. Multiply 2174 by K for the given present conditions from fable 5.2 (K = 1.10). Corrected amount will be 2391 gallons of boric acid. IVote: It is also permissible to use the following equation to calculate boration and dilution volumes. 7 he tabular data were calculatedfrom this equation. I-Iowever the correction factor, K, from Jthle 5.2 must be applied when diluting or borating in Modes 3, 4 or 5. G V LnE(C-Bi) [(C Bf) where U = Volume of boric acid or demineralized water required for boration or dilution V = Equivalent System Volume = 67388 Gallons (a constant) C Concentration of boric acid or demineralized water being added. (C = BAl concentration if borating or C = 0.0 if diluting) Bi = Present NCS boron concentration (ppmB) 13f= Desired NCS boron concentration (ppmB) U N[T I
OPI1IA/6100/22 LNIT 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a corre ction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 10 20 30 40 50 60 70 80 90 100 110 10 0 46710 74033 93420 108457 120743 131131 140129 148067 155167 161589 20 96 0 27323 46710 61747 74033 84421 93420 101357 108457 114880 30 193 97 0 19386 34424 46710 57098 66096 74033 81133 87556 40 290 193 97 0 15037 27323 37711 46710 54647 61747 68170 50 387 290 194 97 0 12286 22674 31673 39610 46710 53133 60 484 387 291 194 97 0 10388 19386 27323 34424 40846 70 581 484 388 291 194 97 0 8998 16936 24036 30458 80 678 582 485 388 292 194 97 0 7937 15037 21460 90 776 679 583 486 389 292 195 97 0 7100 13523 100 873 777 680 583 487 390 292 195 98 0 6423 110 971 875 778 681 584 487 390 293 195 98 0 120 1069 972 876 779 682 585 488 391 293 196 98 130 1167 1070 974 877 780 683 586 489 391 294 196 140 1265 1169 1072 975 878 781 684 587 489 392 294 150 1363 1267 1170 1074 977 880 782 685 588 490 392 160 1462 1365 1269 1172 1075 978 881 784 686 589 491 170 1560 1464 1367 1271 1174 1077 979 882 785 687 589 180 1659 1563 1466 1369 1272 1175 1078 981 883 786 688 190 1758 1662 1565 1468 1371 1274 1177 1080 982 885 787 200 1857 1761 1664 1567 1470 1373 1276 1179 1081 984 886 210 1956 1860 1763 1666 1570 1472 1375 1278 1181 1083 985 220 2056 1959 1862 1766 1669 1572 1475 1377 1280 1182 1085 230 2155 2059 1962 1865 1768 1671 1574 1477 1379 1282 1184 240 2255 2158 2062 1965 1868 1771 1674 1576 1479 1381 1284 L) 250 2354 2258 2161 2065 1968 1871 1773 1676 1579 1481 1383 260 2454 2358 2261 2164 2068 1971 1873 1776 1679 1581 1483 270 2554 2458 2361 2265 2168 2071 1973 1876 1779 1681 1583 280 2655 2558 2461 2365 2268 2171 2074 1976 1879 1781 1684 290 2755 2658 2562 2465 2368 2271 2174 2077 1979 1882 1784 300 2855 2759 2662 2566 2469 2372 2274 2177 2080 1982 1884 310 2956 2860 2763 2666 2569 2472 2375 2278 2180 2083 1985 320 3057 2960 2864 2767 2670 2573 2476 2379 2281 2184 2086 330 3158 3061 2965 2868 2771 2674 2577 2480 2382 2285 2187 340 3259 3162 3066 2969 2872 2775 2678 2581 2483 2386 2288 350 3360 3264 3167 3070 2973 2876 2779 2682 2585 2487 2389 360 3462 3365 3269 3172 3075 2978 2881 2783 2686 2588 2491 370 3563 3467 3370 3273 3176 3079 2982 2885 2787 2690 2592 380 3665 3568 3472 3375 3278 3181 3084 2987 2889 2792 2694 390 3767 3670 3574 3477 3380 3283 3186 3089 2991 2893 2796 400 3869 3772 3676 3579 3482 3385 3288 3191 3093 2996 2898 410 3971 3875 3778 3681 3584 3487 3390 3293 3195 3098 3000 420 4073 3977 3880 3783 3687 3590 3492 3395 3298 3200 3102 430 4176 4079 3983 3886 3789 3692 3595 3498 3400 3303 3205 440 4278 4182 4085 3989 3892 3795 3698 3600 3503 3405 3307 450 4381 4285 4188 4091 3995 3898 3800 3703 3606 3508 3410 460 4484 4388 4291 4194 4097 4000 3903 3806 3709 3611 3513 470 4587 4491 4394 4298 4201 4104 4006 3909 3812 3714 3616 480 4691 4594 4498 4401 4304 4207 4110 4012 3915 3817 3720 490 4794 4698 4601 4504 4407 4310 4213 4116 4018 3921 3823 500 4898 4801 4705 4608 4511 4414 4317 4219 4122 4024 3927 LJ11IT 1 Page 5 of 20
OPI1/A16100122 U]N1T 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 100 110 120 130 140 150 160 170 180 190 200 10 155167 161589 167453 172847 177841 182490 186839 190925 194776 198420 201876 20 108457 114880 120743 126137 131131 135780 140129 144215 148067 151710 155167 30 81133 87556 93420 98814 103808 108457 112806 116891 120743 124387 127843 40 61747 68170 74033 79427 84421 89070 93420 97505 101357 105000 108457 50 46710 53133 58996 64390 69384 74033 78382 82468 86320 89963 93420 60 34424 40846 46710 52104 57098 61747 66096 70181 74033 77677 81133 70 24036 30458 36322 41716 46710 51359 55708 59794 63645 67289 70745 80 15037 21460 27323 32717 37711 42361 46710 50795 54647 58290 61747 90 7100 13523 19386 24780 29774 34424 38773 42858 46710 50353 53810 100 0 6423 12286 17680 22674 27323 31673 35758 39610 43253 46710 110 98 0 5864 11257 16251 20901 25250 29335 33187 36830 40287 120 196 98 0 5394 10388 15037 19386 23472 27323 30967 34424 130 294 196 98 0 4994 9643 13992 18078 21930 25573 29030 140 392 294 196 98 0 4649 8998 13084 16936 20579 24036 150 490 392 294 196 98 0 4349 8434 12286 15930 19386 160 589 491 393 295 197 98 0 4085 7937 11581 15037 170 687 589 492 394 295 197 99 0 3852 7495 10952 180 786 688 590 492 394 296 197 99 0 3643 7100 190 885 787 689 591 493 395 296 198 99 0 3457 200 984 886 788 690 592 494 395 297 198 99 0 210 1083 985 887 789 691 593 494 396 297 198 99 220 1182 1085 987 889 790 692 594 495 396 298 198 230 1282 1184 1086 988 890 792 693 595 496 397 298 240 1381 1284 1186 1088 990 891 793 694 595 497 398 L) 250 1481 1383 1286 1187 1089 991 893 794 695 596 497 260 1581 1483 1385 1287 1189 1091 992 894 795 696 597 270 1681 1583 1485 1387 1289 1191 1093 994 895 796 697 280 1781 1684 1586 1488 1389 1291 1193 1094 995 897 798 290 1882 1784 1686 1588 1490 1392 1293 1195 1096 997 898 300 1982 1884 1787 1689 1590 1492 1394 1295 1196 1097 998 310 2083 1985 1887 1789 1691 1593 1494 1396 1297 1198 1099 320 2184 2086 1988 1890 1792 1694 1595 1496 1398 1299 1200 330 2285 2187 2089 1991 1893 1794 1696 1597 1499 1400 1301 340 2386 2288 2190 2092 1994 1896 1797 1699 1600 1501 1402 350 2487 2389 2291 2193 2095 1997 1898 1800 1701 1602 1503 360 2588 2491 2393 2295 2197 2098 2000 1901 1802 1704 1605 370 2690 2592 2494 2396 2298 2200 2101 2003 1904 1805 1706 380 2792 2694 2596 2498 2400 2302 2203 2104 2006 1907 1808 390 2893 2796 2698 2600 2502 2403 2305 2206 2108 2009 1910 400 2996 2898 2800 2702 2604 2505 2407 2308 2210 2111 2012 410 3098 3000 2902 2804 2706 2608 2509 2411 2312 2213 2114 420 3200 3102 3004 2906 2808 2710 2611 2513 2414 2315 2216 430 3303 3205 3107 3009 2911 2812 2714 2615 2517 2418 2319 440 3405 3307 3210 3112 3013 2915 2817 2718 2619 2520 2421 450 3508 3410 3312 3214 3116 3018 2919 2821 2722 2623 2524 460 3611 3513 3415 3317 3219 3121 3022 2924 2825 2726 2627 470 3714 3616 3518 3420 3322 3224 3126 3027 2928 2829 2730 480 3817 3720 3622 3524 3426 3327 3229 3130 3031 2933 2834 490 3921 3823 3725 3627 3529 3431 3332 3234 3135 3036 2937 500 4024 3927 3829 3731 3633 3534 3436 3337 3238 3140 3041 LJ?[I1 1 Page 6 of 20
0P111A16100122 LJINIT 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 200 210 220 230 240 250 260 270 280 290 300 10 201876 205164 208299 211295 214163 216914 219557 222100 224551 226915 229200 20 155167 158454 161589 164585 167453 170204 172847 175390 177841 180206 182490 30 127843 131131 134266 137261 140129 142880 145523 148067 150517 152882 155167 40 108457 111745 114880 117875 120743 123494 126137 128680 131131 133496 135780 50 93420 96707 99842 102838 105706 108457 111100 113643 116094 118459 120743 60 81133 84421 87556 90552 93420 96171 98814 101357 103808 106172 108457 70 70745 74033 77168 80164 83032 85783 88426 90969 93420 95784 98069 80 61747 65035 68170 71165 74033 76784 79427 81970 84421 86786 89070 90 53810 57098 60233 63228 66096 68847 71490 74033 76484 78849 81133 100 46710 49998 53133 56128 58996 61747 64390 66933 69384 71749 74033 110 40287 43575 46710 49705 52573 55324 57967 60510 62961 65326 67611 120 34424 37711 40846 43842 46710 49461 52104 54647 57098 59462 61747 130 29030 32317 35452 38448 41316 44067 46710 49253 51704 54069 56353 140 24036 27323 30458 33454 36322 39073 41716 44259 46710 49075 51359 150 19386 22674 25809 28805 31673 34424 37067 39610 42061 44425 46710 160 15037 18325 21460 24455 27323 30074 32717 35261 37711 40076 42361 170 10952 14240 17375 20370 23238 25989 28632 31175 33626 35991 38275 180 7100 10388 13523 16518 19386 22137 24780 27323 29774 32139 34424 190 3457 6744 9879 12875 15743 18494 21137 23680 26131 28495 30780 200 0 3288 6423 9418 12286 15037 17680 20223 22674 25039 27323 210 99 0 3135 6130 8998 11749 14392 16936 19386 21751 24036 220 198 99 0 2996 5864 8614 11257 13801 16251 18616 20901 230 298 199 99 0 2868 5619 8262 10805 13256 15621 17905 240 398 298 199 100 0 2751 5394 7937 10388 12753 15037 L) 250 497 398 299 199 100 0 2643 5186 7637 10002 12286 260 597 498 399 299 200 100 0 2543 4994 7359 9643 270 697 598 499 399 300 200 100 0 2451 4815 7100 280 798 698 599 500 400 300 200 100 0 2365 4649 290 898 799 699 600 500 401 301 201 100 0 2285 300 998 899 800 700 601 501 401 301 201 101 0 310 1099 1000 901 801 701 602 502 402 302 201 101 320 1200 1101 1001 902 802 702 603 503 402 302 201 330 1301 1202 1102 1003 903 803 704 603 503 403 302 340 1402 1303 1203 1104 1004 905 805 705 604 504 404 350 1503 1404 1305 1205 1106 1006 906 806 706 605 505 360 1605 1505 1406 1307 1207 1107 1007 907 807 707 606 370 1706 1607 1508 1408 1309 1209 1109 1009 909 808 708 380 1808 1709 1609 1510 1410 1311 1211 1111 1010 910 809 390 1910 1811 1711 1612 1512 1412 1312 1212 1112 1012 911 400 2012 1913 1813 1714 1614 1514 1414 1314 1214 1114 1013 410 2114 2015 1915 1816 1716 1617 1517 1417 1316 1216 1116 420 2216 2117 2018 1918 1819 1719 1619 1519 1419 1318 1218 430 2319 2220 2120 2021 1921 1821 1722 1621 1521 1421 1320 440 2421 2322 2223 2123 2024 1924 1824 1724 1624 1524 1423 450 2524 2425 2326 2226 2127 2027 1927 1827 1727 1626 1526 460 2627 2528 2429 2329 2230 2130 2030 1930 1830 1729 1629 470 2730 2631 2532 2432 2333 2233 2133 2033 1933 1832 1732 480 2834 2734 2635 2536 2436 2336 2236 2136 2036 1936 1835 490 2937 2838 2738 2639 2539 2440 2340 2240 2139 2039 1939 500 3041 2941 2842 2743 2643 2543 2443 2343 2243 2143 2042 IJ1NI1 1 Page 7 of 20
0P111A16100122 UNIT 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K,from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 300 310 320 330 340 350 360 370 380 390 400 110 67611 69820 71960 74033 76045 77998 79897 81743 83540 85291 86997 120 61747 63957 66096 68170 70181 72135 74033 75880 77677 79427 81133 130 56353 58563 60702 62776 64788 66741 68639 70486 72283 74033 75739 140 51359 53569 55708 57782 59794 61747 63645 65492 67289 69039 70745 150 46710 48919 51059 53133 55144 57098 58996 60842 62640 64390 66096 160 42361 44570 46710 48783 50795 52749 54647 56493 58290 60041 61747 170 38275 40485 42624 44698 46710 48663 50562 52408 54205 55956 57662 180 34424 36633 38773 40846 42858 44811 46710 48556 50353 52104 53810 190 30780 32990 35129 37203 39215 41168 43066 44913 46710 48460 50166 200 27323 29533 31673 33746 35758 37711 39610 41456 43253 45004 46710 210 24036 26245 28385 30458 32470 34424 36322 38168 39965 41716 43422 220 20901 23110 25250 27323 29335 31289 33187 35033 36830 38581 40287 230 17905 20115 22254 24328 26340 28293 30191 32038 33835 35585 37292 240 15037 17247 19386 21460 23472 25425 27323 29170 30967 32717 34424 250 12286 14496 16635 18709 20721 22674 24573 26419 28216 29966 31673 260 9643 11853 13992 16066 18078 20031 21930 23776 25573 27323 29030 270 7100 9310 11449 13523 15535 17488 19386 21233 23030 24780 26486 280 4649 6859 8998 11072 13084 15037 16936 18782 20579 22329 24036 290 2285 4494 6634 8707 10719 12672 14571 16417 18214 19965 21671 300 0 2210 4349 6423 8434 10388 12286 14133 15930 17680 19386 310 101 0 2139 4213 6225 8178 10077 11923 13720 15471 17177 320 201 101 0 2074 4085 6039 7937 9784 11581 13331 15037 330 302 202 101 0 2012 3965 5864 7710 9507 11257 12964 340 404 303 202 101 0 1953 3852 5698 7495 9246 10952 (-) 350 505 404 303 202 101 0 1898 3745 5542 7292 8998 360 606 506 405 304 203 101 0 1846 3643 5394 7100 370 708 607 506 405 304 203 102 0 1797 3548 5254 380 809 709 608 507 406 305 203 102 0 1750 3457 390 911 811 710 609 508 407 305 204 102 0 1706 400 1013 913 812 711 610 509 407 306 204 102 0 410 1116 1015 914 813 712 611 509 408 306 204 102 420 1218 1117 1016 915 814 713 612 510 408 307 205 430 1320 1220 1119 1018 917 816 714 613 511 409 307 440 1423 1322 1222 1121 1020 918 817 715 614 512 410 450 1526 1425 1324 1223 1122 1021 920 818 716 614 512 460 1629 1528 1427 1326 1225 1124 1023 921 819 717 615 470 1732 1631 1530 1429 1328 1227 1126 1024 922 821 719 480 1835 1735 1634 1533 1432 1330 1229 1127 1026 924 822 490 1939 1838 1737 1636 1535 1434 1332 1231 1129 1027 925 500 2042 1942 1841 1740 1639 1537 1436 1334 1233 1131 1029 510 2146 2045 1945 1844 1742 1641 1540 1438 1336 1235 1133 520 2250 2149 2048 1947 1846 1745 1644 1542 1440 1339 1237 530 2354 2253 2152 2052 1950 1849 1748 1646 1544 1443 1341 540 2458 2358 2257 2156 2055 1953 1852 1750 1649 1547 1445 550 2563 2462 2361 2260 2159 2058 1956 1855 1753 1651 1549 560 2667 2566 2466 2365 2264 2162 2061 1959 1858 1756 1654 570 2772 2671 2570 2469 2368 2267 2166 2064 1962 1861 1758 580 2877 2776 2675 2574 2473 2372 2271 2169 2067 1965 1863 590 2982 2881 2780 2679 2578 2477 2376 2274 2172 2070 1968 600 3087 2986 2886 2785 2683 2582 2481 2379 2278 2176 2074 ijrii 1 Page 8 of 20
0P111A16100122 LINIl 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 400 410 420 430 440 450 460 470 480 490 500 210 43422 45086 46710 48295 49845 51359 52840 54289 55708 57098 58459 220 40287 41951 43575 45161 46710 48224 49705 51155 52573 53963 55324 230 37292 38956 40579 42165 43714 45229 46710 48159 49578 50967 52329 240 34424 36088 37711 39297 40846 42361 43842 45291 46710 48099 49461 250 31673 33337 34960 36546 38095 39610 41091 42540 43959 45348 46710 260 29030 30694 32317 33903 35452 36967 38448 39897 41316 42705 44067 270 26486 28150 29774 31360 32909 34424 35905 37354 38773 40162 41524 280 24036 25700 27323 28909 30458 31973 33454 34903 36322 37711 39073 290 21671 23335 24959 26544 28094 29608 31089 32538 33957 35347 36708 300 19386 21050 22674 24260 25809 27323 28805 30254 31673 33062 34424 310 17177 18841 20465 22050 23599 25114 26595 28044 29463 30852 32214 320 15037 16701 18325 19911 21460 22974 24455 25905 27323 28713 30074 330 12964 14628 16251 17837 19386 20901 22382 23831 25250 26639 28001 340 10952 12616 14240 15825 17375 18889 20370 21819 23238 24628 25989 350 8998 10662 12286 13872 15421 16936 18417 19866 21285 22674 24036 360 7100 8764 10388 11974 13523 15037 16518 17968 19386 20776 22137 370 5254 6918 8542 10127 11676 13191 14672 16121 17540 18929 20291 380 3457 5121 6744 8330 9879 11394 12875 14324 15743 17132 18494 390 1706 3370 4994 6580 8129 9643 11124 12574 13992 15382 16743 400 0 1664 3288 4874 6423 7937 9418 10868 12286 13676 15037 410 102 0 1624 3210 4759 6273 7754 9204 10622 12012 13373 420 205 102 0 1586 3135 4649 6130 7580 8998 10388 11749 430 307 205 102 0 1549 3064 4545 5994 7413 8802 10164 440 410 307 205 103 0 1514 2996 4445 5864 7253 8614 L) 450 512 410 308 205 103 0 1481 2930 4349 5739 7100 460 615 513 411 308 206 103 0 1449 2868 4257 5619 470 719 616 514 412 309 206 103 0 1419 2808 4170 480 822 720 617 515 412 309 206 103 0 1389 2751 490 925 823 721 618 516 413 310 207 103 0 1361 500 1029 927 824 722 619 516 413 310 207 104 0 510 1133 1030 928 826 723 620 517 414 311 207 104 520 1237 1134 1032 930 827 724 621 518 415 311 208 530 1341 1238 1136 1034 931 828 725 622 519 415 312 540 1445 1343 1240 1138 1035 932 829 726 623 520 416 550 1549 1447 1345 1242 1140 1037 934 831 727 624 520 560 1654 1552 1449 1347 1244 1141 1038 935 832 729 625 570 1758 1656 1554 1451 1349 1246 1143 1040 937 833 730 580 1863 1761 1659 1556 1454 1351 1248 1145 1042 938 835 590 1968 1866 1764 1661 1559 1456 1353 1250 1147 1043 940 600 2074 1971 1869 1767 1664 1561 1458 1355 1252 1148 1045 610 2179 2077 1975 1872 1769 1667 1564 1460 1357 1254 1150 620 2285 2182 2080 1978 1875 1772 1669 1566 1463 1359 1256 630 2390 2288 2186 2083 1981 1878 1775 1672 1568 1465 1361 640 2496 2394 2292 2189 2086 1984 1881 1778 1674 1571 1467 650 2602 2500 2398 2295 2193 2090 1987 1884 1780 1677 1573 660 2708 2606 2504 2401 2299 2196 2093 1990 1887 1783 1680 670 2815 2713 2610 2508 2405 2302 2199 2096 1993 1890 1786 680 2921 2819 2717 2614 2512 2409 2306 2203 2099 1996 1892 690 3028 2926 2823 2721 2618 2516 2413 2309 2206 2103 1999 700 3135 3033 2930 2828 2725 2622 2519 2416 2313 2210 2106 LJINIT 1 Page 9 of 20
0P111A16100122 IJNI1 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factoi K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 500 510 520 530 540 550 560 570 580 590 600 310 32214 33548 34857 36141 37400 38637 39851 41044 42216 43368 44500 320 30074 31409 32717 34001 35261 36497 37711 38904 40076 41228 42361 330 28001 29335 30644 31927 33187 34424 35638 36830 38002 39154 40287 340 25989 27323 28632 29916 31175 32412 33626 34819 35991 37143 38275 350 24036 25370 26679 27962 29222 30458 31673 32865 34037 35189 36322 360 22137 23472 24780 26064 27323 28560 29774 30967 32139 33291 34424 370 20291 21625 22934 24217 25477 26714 27928 29121 30293 31445 32577 380 18494 19828 21137 22420 23680 24917 26131 27323 28495 29647 30780 390 16743 18078 19386 20670 21930 23166 24380 25573 26745 27897 29030 400 15037 16372 17680 18964 20223 21460 22674 23867 25039 26191 27323 410 13373 14708 16016 17300 18559 19796 21010 22203 23375 24527 25659 420 11749 13084 14392 15676 16936 18172 19386 20579 21751 22903 24036 430 10164 11498 12807 14090 15350 16586 17801 18993 20165 21317 22450 440 8614 9949 11257 12541 13801 15037 16251 17444 18616 19768 20901 450 7100 8434 9743 11027 12286 13523 14737 15930 17102 18254 19386 460 5619 6953 8262 9546 10805 12042 13256 14449 15621 16773 17905 470 4170 5504 6813 8096 9356 10592 11807 12999 14171 15323 16456 480 2751 4085 5394 6678 7937 9174 10388 11581 12753 13905 15037 490 1361 2696 4004 5288 6548 7784 8998 10191 11363 12515 13648 500 0 1334 2643 3927 5186 6423 7637 8830 10002 11154 12286 510 104 0 1309 2592 3852 5088 6303 7495 8667 9819 10952 520 208 104 0 1284 2543 3780 4994 6187 7359 8511 9643 530 312 208 104 0 1260 2496 3710 4903 6075 7227 8360 540 416 312 208 104 0 1237 2451 3643 4815 5967 7100 L) 550 520 417 313 209 104 0 1214 2407 3579 4731 5864 560 625 521 417 313 209 105 0 1193 2365 3517 4649 570 730 626 522 418 314 209 105 0 1172 2324 3457 0 580 835 731 627 523 419 314 210 105 0 1152 2285 590 940 836 732 628 524 419 315 210 105 0 1133 600 1045 941 837 733 629 524 420 315 210 105 0 610 1150 1046 943 838 734 630 525 421 316 211 105 620 1256 1152 1048 944 840 735 631 526 421 316 211 630 1361 1258 1154 1050 945 841 736 632 527 422 317 640 1467 1364 1260 1156 1051 947 842 738 633 528 422 650 1573 1470 1366 1262 1157 1053 948 844 739 634 529 660 1680 1576 1472 1368 1264 1159 1055 950 845 740 635 670 1786 1682 1578 1474 1370 1266 1161 1056 951 846 741 680 1892 1789 1685 1581 1476 1372 1268 1163 1058 953 848 690 1999 1895 1791 1687 1583 1479 1374 1270 1165 1060 954 700 2106 2002 1898 1794 1690 1586 1481 1376 1272 1166 1061 710 2213 2109 2005 1901 1797 1693 1588 1483 1379 1274 1168 720 2320 2217 2113 2009 1904 1800 1695 1591 1486 1381 1276 730 2428 2324 2220 2116 2012 1907 1803 1698 1593 1488 1383 740 2535 2432 2328 2224 2119 2015 1910 1806 1701 1596 1490 750 2643 2539 2435 2331 2227 2123 2018 1913 1808 1703 1598 760 2751 2647 2543 2439 2335 2231 2126 2021 1916 1811 1706 770 2859 2755 2651 2547 2443 2339 2234 2129 2024 1919 1814 780 2967 2863 2760 2656 2551 2447 2342 2238 2133 2028 1922 790 3076 2972 2868 2764 2660 2555 2451 2346 2241 2136 2031 800 3184 3081 2977 2873 2768 2664 2559 2455 2350 2245 2139 LJNIT 1 Page 10 of 20
%jr[ 1 (J OPI1IAI6100/22 1 - Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 600 610 620 630 640 650 660 670 680 690 700 410 25659 26773 27869 28947 30009 31053 32082 33096 34094 35078 36047 420 24036 25149 26245 27323 28385 29430 30458 31472 32470 33454 34424 430 22450 23564 24660 25738 26799 27844 28873 29886 30884 31868 32838 440 20901 22015 23110 24189 25250 26295 27323 28337 29335 30319 31289 450 19386 20500 21596 22674 23735 24780 25809 26822 27821 28805 29774 460 17905 19019 20115 21193 22254 23299 24328 25341 26340 27323 28293 470 16456 17570 18666 19744 20805 21850 22879 23892 24890 25874 26844 480 15037 16151 17247 18325 19386 20431 21460 22473 23472 24455 25425 490 13648 14762 15857 16936 17997 19042 20070 21084 22082 23066 24036 500 12286 13400 14496 15574 16635 17680 18709 19722 20721 21705 22674 510 10952 12066 13161 14240 15301 16346 17375 18388 19386 20370 21340 520 9643 10757 11853 12931 13992 15037 16066 17079 18078 19062 20031 530 8360 9474 10569 11648 12709 13754 14782 15796 16794 17778 18748 540 7100 8214 9310 10388 11449 12494 13523 14536 15535 16518 17488 550 5864 6977 8073 9151 10213 11257 12286 13300 14298 15282 16251 560 4649 5763 6859 7937 8998 10043 11072 12085 13084 14068 15037 570 3457 4570 5666 6744 7806 8850 9879 10893 11891 12875 13844 580 2285 3398 4494 5572 6634 7678 8707 9721 10719 11703 12672 590 1133 2246 3342 4420 5482 6527 7555 8569 9567 10551 11521 600 0 1114 2210 3288 4349 5394 6423 7436 8434 9418 10388 610 105 0 1096 2174 3235 4280 5309 6322 7321 8304 9274 620 211 106 0 1078 2139 3184 4213 5226 6225 7209 8178 630 317 211 106 0 1061 2106 3135 4148 5147 6130 7100 640 422 317 212 106 0 1045 2074 3087 4085 5069 6039 U 650 529 423 318 212 106 0 1029 2042 3041 4024 4994 660 635 529 424 318 212 106 0 1013 2012 2996 3965 L) 670 741 636 530 424 319 213 106 0 998 1982 2952 680 848 742 637 531 425 319 213 107 0 984 1953 690 954 849 743 638 532 426 320 213 107 0 970 700 1061 956 850 745 639 533 427 320 214 107 0 710 1168 1063 957 852 746 640 534 427 321 214 107 720 1276 1170 1065 959 853 747 641 534 428 321 214 730 1383 1278 1172 1066 960 854 748 642 535 429 322 740 1490 1385 1280 1174 1068 962 856 749 643 536 429 750 1598 1493 1387 1282 1176 1070 963 857 751 644 537 760 1706 1601 1495 1389 1284 1178 1071 965 858 752 645 770 1814 1709 1603 1498 1392 1286 1179 1073 967 860 753 780 1922 1817 1712 1606 1500 1394 1288 1181 1075 968 861 790 2031 1926 1820 1714 1608 1502 1396 1290 1183 1077 970 800 2139 2034 1929 1823 1717 1611 1505 1398 1292 1185 1078 810 2248 2143 2037 1932 1826 1720 1614 1507 1401 1294 1187 820 2357 2252 2146 2041 1935 1829 1722 1616 1510 1403 1296 830 2466 2361 2255 2150 2044 1938 1832 1725 1619 1512 1405 840 2576 2470 2365 2259 2153 2047 1941 1835 1728 1621 1514 850 2685 2580 2474 2369 2263 2157 2050 1944 1837 1731 1624 860 2795 2689 2584 2478 2372 2266 2160 2054 1947 1840 1734 870 2905 2799 2694 2588 2482 2376 2270 2164 2057 1950 1843 880 3015 2909 2804 2698 2592 2486 2380 2274 2167 2060 1953 890 3125 3019 2914 2808 2702 2596 2490 2384 2277 2170 2064 900 3235 3130 3024 2919 2813 2707 2601 2494 2388 2281 2174 LJrTIT 1 Page 11 of 20
0Pl1lAl6100l22 UNIT 1 . Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K; from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 700 710 720 730 740 750 760 770 780 790 800 510 21340 22296 23238 24168 25084 25989 26882 27762 28632 29490 30338 520 20031 20987 21930 22859 23776 24680 25573 26454 27323 28182 29030 530 18748 19703 20646 21575 22492 23397 24289 25170 26040 26898 27746 540 17488 18444 19386 20316 21233 22137 23030 23911 24780 25639 26486 550 16251 17207 18150 19079 19996 20901 21793 22674 23544 24402 25250 560 15037 15993 16936 17865 18782 19686 20579 21460 22329 23188 24036 570 13844 14800 15743 16672 17589 18494 19386 20267 21137 21995 22843 580 12672 13628 14571 15500 16417 17322 18214 19095 19965 20823 21671 590 11521 12476 13419 14348 15265 16170 17062 17943 18813 19671 20519 600 10388 11344 12286 13216 14133 15037 15930 16811 17680 18539 19386 610 9274 10230 11172 12102 13019 13923 14816 15697 16566 17425 18272 620 8178 9134 10077 11006 11923 12828 13720 14601 15471 16329 17177 630 7100 8056 8998 9928 10845 11749 12642 13523 14392 15251 16098 640 6039 6995 7937 8867 9784 10688 11581 12462 13331 14190 15037 650 4994 5950 6892 7822 8739 9643 10536 11417 12286 13145 13992 660 3965 4921 5864 6793 7710 8614 9507 10388 11257 12116 12964 2952 3908 4850 5780 6697 7601 8494 9375 10244 11103 11950 680 1953 2909 3852 4781 5698 6603 7495 8376 9246 10104 10952 690 970 1926 2868 3798 4714 5619 6511 7392 8262 9120 9968 700 0 956 1898 2828 3745 4649 5542 6423 7292 8151 8998 710 107 0 943 1872 2789 3693 4586 5467 6336 7195 8043 720 214 107 0 930 1846 2751 3643 4524 5394 6252 7100 730 322 215 107 0 917 1821 2714 3595 4464 5323 6171 740 429 322 215 108 0 905 1797 2678 3548 4406 5254 C..) 750 537 430 323 215 108 0 893 1773 2643 3501 4349 760 645 538 431 323 216 108 0 881 1750 2609 3457 770 753 646 539 431 324 216 108 0 870 1728 2576 0 780 861 754 647 540 432 324 216 108 0 858 1706 790 970 863 755 648 540 433 325 217 108 0 848 800 1078 971 864 757 649 541 433 325 217 109 0 810 1187 1080 973 865 758 650 542 434 326 217 109 820 1296 1189 1082 974 867 759 651 543 435 326 218 830 1405 1298 1191 1083 976 868 760 652 544 435 327 840 1514 1407 1300 1193 1085 977 870 761 653 545 436 850 1624 1517 1410 1302 1195 1087 979 871 763 654 546 860 1734 1626 1519 1412 1304 1197 1089 981 872 764 655 870 1843 1736 1629 1522 1414 1306 1199 1090 982 874 765 880 1953 1846 1739 1632 1524 1416 1309 1200 1092 984 875 890 2064 1957 1849 1742 1634 1527 1419 1311 1202 1094 985 900 2174 2067 1960 1852 1745 1637 1529 1421 1313 1204 1096 910 2285 2178 2070 1963 1855 1748 1640 1532 1423 1315 1206 920 2395 2288 2181 2074 1966 1858 1750 1642 1534 1426 1317 930 2506 2399 2292 2185 2077 1969 1861 1753 1645 1537 1428 940 2617 2510 2403 2296 2188 2080 1972 1864 1756 1648 1539 950 2729 2622 2514 2407 2299 2192 2084 1976 1867 1759 1650 960 2840 2733 2626 2518 2411 2303 2195 2087 1979 1870 1762 970 2952 2845 2738 2630 2523 2415 2307 2199 2091 1982 1874 980 3064 2957 2849 2742 2634 2527 2419 2311 2202 2094 1985 990 3176 3069 2961 2854 2746 2639 2531 2423 2314 2206 2097 1000 3288 3181 3074 2966 2859 2751 2643 2535 2427 2318 2210 LiNIT 1 Page 12 of 20
0P111A16100122 L.J1NIT 1 - Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 800 810 820 830 840 850 860 870 880 890 900 610 18272 19110 19936 20753 21560 22358 23146 23925 24695 25457 26210 620 17177 18014 18841 19657 20465 21262 22050 22829 23599 24361 25114 630 16098 16936 17762 18579 19386 20184 20972 21751 22521 23283 24036 640 15037 15874 16701 17518 18325 19123 19911 20690 21460 22221 22974 650 13992 14830 15656 16473 17280 18078 18866 19645 20415 21177 21930 660 12964 13801 14628 15444 16251 17049 17837 18616 19386 20148 20901 670 11950 12787 13614 14431 15238 16036 16824 17603 18373 19134 19887 680 10952 11789 12616 13433 14240 15037 15825 16604 17375 18136 18889 690 9968 10805 11632 12449 13256 14053 14842 15621 16391 17152 17905 700 8998 9836 10662 11479 12286 13084 13872 14651 15421 16183 16936 710 8043 8880 9707 10523 11330 12128 12916 13695 14465 15227 15980 720 7100 7937 8764 9581 10388 11185 11974 12753 13523 14284 15037 730 6171 7008 7835 8651 9458 10256 11044 11823 12593 13355 14108 740 5254 6091 6918 7734 8542 9339 10127 10906 11676 12438 13191 750 4349 5186 6013 6830 7637 8434 9223 10002 10772 11533 12286 760 3457 4294 5121 5937 6744 7542 8330 9109 9879 10641 11394 2576 3413 4240 5056 5864 6661 7449 8228 8998 9760 10513 780 1706 2543 3370 4187 4994 5791 6580 7359 8129 8890 9643 790 848 1685 2512 3328 4136 4933 5721 6500 7270 8032 8785 800 0 837 1664 2481 3288 4085 4874 5653 6423 7184 7937 810 109 0 827 1644 2451 3248 4036 4815 5586 6347 7100 820 218 109 0 817 1624 2421 3210 3989 4759 5520 6273 830 327 218 109 0 807 1605 2393 3172 3942 4703 5456 840 436 327 218 109 0 798 1586 2365 3135 3896 4649 C-) 850 546 437 328 219 109 0 788 1567 2337 3099 3852 860 655 547 438 328 219 110 0 779 1549 2311 3064 C..) 870 765 656 547 438 329 220 110 0 770 1532 2285 880 875 766 657 548 439 330 220 110 0 761 1514 890 985 877 768 659 549 440 330 220 110 0 753 900 1096 987 878 769 660 550 440 331 221 110 0 910 1206 1098 989 879 770 661 551 441 331 221 111 920 1317 1208 1099 990 881 771 662 552 442 332 221 930 1428 1319 1210 1101 992 882 773 663 553 443 332 940 1539 1430 1321 1212 1103 993 884 774 664 554 443 950 1650 1542 1433 1324 1214 1105 995 885 775 665 555 960 1762 1653 1544 1435 1326 1216 1107 997 887 776 666 970 1874 1765 1656 1547 1437 1328 1218 1108 998 888 778 980 1985 1877 1768 1659 1549 1440 1330 1220 1110 1000 890 990 2097 1989 1880 1771 1661 1552 1442 1332 1222 1112 1002 1000 2210 2101 1992 1883 1773 1664 1554 1444 1334 1224 1114 1010 2322 2213 2104 1995 1886 1776 1667 1557 1447 1337 1226 1020 2435 2326 2217 2108 1998 1889 1779 1669 1559 1449 1339 1030 2547 2439 2330 2221 2111 2002 1892 1782 1672 1562 1452 1040 2660 2552 2443 2334 2224 2115 2005 1895 1785 1675 1565 1050 2774 2665 2556 2447 2337 2228 2118 2008 1898 1788 1678 1060 2887 2778 2669 2560 2451 2341 2232 2122 2012 1902 1791 1070 3000 2892 2783 2674 2564 2455 2345 2235 2125 2015 1905 1080 3114 3005 2896 2787 2678 2569 2459 2349 2239 2129 2018 1090 3228 3119 3010 2901 2792 2682 2573 2463 2353 2243 2132 1100 3342 3233 3125 3015 2906 2797 2687 2577 2467 2357 2246 LJNIT 1 Page 13 of 20
OPI1IA/6100122 ITNIT 1 Enclosure 4.3
- Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 900 910 920 930 940 950 960 970 980 990 1000 710 15980 16724 17461 18189 18910 19623 20329 21027 21718 22402 23080 720 15037 15782 16518 17247 17968 18681 19386 20085 20776 21460 22137 730 14108 14852 15589 16317 17038 17751 18457 19155 19846 20530 21208 740 13191 13935 14672 15400 16121 16834 17540 18238 18929 19614 20291 750 12286 13031 13767 14496 15217 15930 16635 17334 18025 18709 19386 760 11394 12138 12875 13603 14324 15037 15743 16441 17132 17816 18494 770 10513 11257 11994 12722 13443 14156 14862 15560 16251 16936 17613 780 9643 10388 11124 11853 12574 13287 13992 14691 15382 16066 16743 790 8785 9529 10266 10994 11715 12428 13134 13832 14523 15208 15885 800 7937 8682 9418 10147 10868 11581 12286 12985 13676 14360 15037 810 7100 7845 8581 9310 10030 10744 11449 12147 12839 13523 14200 820 6273 7018 7754 8483 9204 9917 10622 11321 12012 12696 13373 830 5456 6201 6937 7666 8387 9100 9805 10504 11195 11879 12556 840 4649 5394 6130 6859 7580 8293 8998 9697 10388 11072 11749 850 3852 4596 5333 6061 6782 7495 8201 8899 9590 10275 10952 860 3064 3808 4545 5273 5994 6707 7413 8111 8802 9486 10164 870 2285 3029 3766 4494 5215 5928 6634 7332 8023 8707 9385 880 1514 2259 2996 3724 4445 5158 5864 6562 7253 7937 8614 890 753 1498 2234 2963 3683 4396 5102 5800 6492 7176 7853 900 0 745 1481 2210 2930 3643 4349 5047 5739 6423 7100 910 111 0 736 1465 2186 2899 3604 4303 4994 5678 6355 920 221 111 0 729 1449 2162 2868 3566 4257 4942 5619 930 332 222 111 0 721 1434 2139 2838 3529 4213 4890 940 443 333 222 111 0 713 1419 2117 2808 3492 4170 U 950 555 444 333 222 111 0 706 1404 2095 2779 3457 960 666 556 445 334 223 111 0 698 1389 2074 2751 U
970 778 667 556 446 334 223 112 0 691 1375 2053 980 890 779 668 557 446 335 224 112 0 684 1361 990 1002 891 780 669 558 447 336 224 112 0 677 1000 1114 1003 893 782 671 559 448 336 224 112 0 1010 1226 1116 1005 894 783 672 560 449 337 225 112 1020 1339 1228 1118 1007 896 784 673 561 449 337 225 1030 1452 1341 1230 1119 1008 897 786 674 562 450 338 1040 1565 1454 1343 1232 1121 1010 899 787 675 563 451 1050 1678 1567 1456 1346 1234 1123 1012 900 788 676 564 1060 1791 1681 1570 1459 1348 1237 1125 1013 902 789 677 1070 1905 1794 1683 1572 1461 1350 1239 1127 1015 903 791 1080 2018 1908 1797 1686 1575 1464 1352 1241 1129 1017 905 1090 2132 2022 1911 1800 1689 1578 1466 1355 1243 1131 1018 1100 2246 2136 2025 1914 1803 1692 1580 1469 1357 1245 1133 1110 2361 2250 2139 2029 1917 1806 1695 1583 1471 1359 1247 1120 2475 2365 2254 2143 2032 1921 1809 1698 1586 1474 1361 1130 2590 2479 2369 2258 2147 2035 1924 1812 1700 1588 1476 1140 2705 2594 2484 2373 2262 2150 2039 1927 1815 1703 1591 1150 2820 2709 2599 2488 2377 2265 2154 2042 1930 1818 1706 1160 2935 2825 2714 2603 2492 2381 2269 2158 2046 1934 1821 1170 3051 2940 2829 2719 2607 2496 2385 2273 2161 2049 1937 1180 3166 3056 2945 2834 2723 2612 2500 2389 2277 2165 2053 1190 3282 3172 3061 2950 2839 2728 2616 2505 2393 2281 2168 1200 3398 3288 3177 3066 2955 2844 2732 2621 2509 2397 2285 LJrIT 1 Page 14 of 20
OP/l!A16100122 tTNIT 1 -
- Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1000 1010 1020 1030 1040 1050 1060 1070 1080 1090 1100 810 14200 14871 15535 16192 16843 17488 18127 18759 19386 20007 20623 820 13373 14044 14708 15365 16016 16661 17300 17933 18559 19181 19796 830 12556 13227 13891 14548 15199 15844 16483 17116 17743 18364 18979 840 11749 12420 13084 13741 14392 15037 15676 16309 16936 17557 18172 850 10952 11622 12286 12944 13595 14240 14878 15511 16138 16759 17375 860 10164 10834 11498 12156 12807 13452 14090 14723 15350 15971 16586 870 9385 10055 10719 11377 12028 12672 13311 13944 14571 15192 15807 880 8614 9285 9949 10606 11257 11902 12541 13174 13801 14422 15037 890 7853 8524 9187 9845 10496 11141 11780 12412 13039 13660 14276 900 7100 7771 8434 9092 9743 10388 11027 11659 12286 12907 13523 910 6355 7026 7690 8347 8998 9643 10282 10915 11542 12163 12778 920 5619 6289 6953 7611 8262 8907 9546 10178 10805 11426 12042 930 4890 5561 6225 6882 7533 8178 8817 9450 10077 10698 11313 940 4170 4840 5504 6162 6813 7458 8096 8729 9356 9977 10592 950 3457 4127 4791 5448 6100 6744 7383 8016 8643 9264 9879 960 2751 3421 4085 4743 5394 6039 6678 7310 7937 8558 9174 970 2053 2723 3387 4044 4696 5340 5979 6612 7239 7860 8475 980 1361 2032 2696 3353 4004 4649 5288 5921 6548 7169 7784 990 677 1348 2012 2669 3320 3965 4604 5237 5864 6485 7100 1000 0 671 1334 1992 2643 3288 3927 4559 5186 5807 6423 1010 112 0 664 1321 1972 2617 3256 3889 4516 5137 5752 1020 225 113 0 657 1309 1953 2592 3225 3852 4473 5088 1030 338 225 113 0 651 1296 1935 2567 3194 3815 4431 1040 451 338 226 113 0 645 1284 1916 2543 3164 3780 L) 1050 564 452 339 226 113 0 639 1272 1898 2519 3135 1060 677 565 452 339 227 113 0 633 1260 1881 2496 1070 791 678 566 453 340 227 114 0 627 1248 1863 1080 905 792 680 567 454 341 227 114 0 621 1237 1090 1018 906 793 681 568 455 341 228 114 0 615 1100 1133 1020 908 795 682 569 455 342 228 114 0 1110 1247 1135 1022 909 796 683 570 456 342 228 114 1120 1361 1249 1136 1024 911 798 684 571 457 343 229 1130 1476 1364 1251 1138 1025 912 799 685 572 458 344 1140 1591 1479 1366 1253 1140 1027 914 800 686 573 458 1150 1706 1594 1481 1368 1255 1142 1029 915 802 688 574 1160 1821 1709 1596 1484 1371 1257 1144 1031 917 803 689 1170 1937 1824 1712 1599 1486 1373 1260 1146 1032 918 804 1180 2053 1940 1828 1715 1602 1489 1375 1262 1148 1034 920 1190 2168 2056 1943 1831 1718 1605 1491 1378 1264 1150 1036 1200 2285 2172 2060 1947 1834 1721 1607 1494 1380 1266 1152 1210 2401 2288 2176 2063 1950 1837 1724 1610 1496 1382 1268 1220 2517 2405 2292 2180 2067 1953 1840 1727 1613 1499 1385 1230 2634 2522 2409 2296 2183 2070 1957 1843 1729 1616 1501 1240 2751 2639 2526 2413 2300 2187 2074 1960 1846 1732 1618 1250 2868 2756 2643 2530 2417 2304 2191 2077 1963 1850 1735 1260 2985 2873 2760 2648 2535 2421 2308 2194 2081 1967 1853 1270 3103 2990 2878 2765 2652 2539 2426 2312 2198 2084 1970 1280 3221 3108 2996 2883 2770 2657 2543 2430 2316 2202 2088 1290 3338 3226 3113 3001 2888 2775 2661 2548 2434 2320 2206 1300 3457 3344 3232 3119 3006 2893 2779 2666 2552 2438 2324 UNIT 1 Page 15 of 20
0P111A16100122 IJ1NIT 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a corre ction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1100 1110 1120 1130 1140 1150 1160 1170 1180 1190 1200 910 12778 13388 13992 14591 15185 15774 16357 16936 17509 18078 18642 920 12042 12652 13256 13855 14449 15037 15621 16199 16773 17341 17905 930 11313 11923 12527 13126 13720 14309 14892 15471 16044 16613 17177 940 10592 11202 11807 12406 12999 13588 14171 14750 15323 15892 16456 950 9879 10489 11094 11693 12286 12875 13458 14037 14610 15179 15743 960 9174 9784 10388 10987 11581 12169 12753 13331 13905 14473 15037 970 8475 9085 9690 10289 10882 11471 12054 12633 13206 13775 14339 980 7784 8394 8998 9597 10191 10780 11363 11942 12515 13084 13648 990 7100 7710 8314 8913 9507 10096 10679 11257 11831 12400 12964 1000 6423 7033 7637 8236 8830 9418 10002 10580 11154 11722 12286 1010 5752 6362 6966 7565 8159 8748 9331 9910 10483 11052 11616 1020 5088 5698 6303 6902 7495 8084 8667 9246 9819 10388 10952 1030 4431 5041 5645 6244 6838 7426 8010 8588 9162 9730 10294 1040 3780 4390 4994 5593 6187 6775 7359 7937 8511 9079 9643 1050 3135 3745 4349 4948 5542 6130 6714 7292 7866 8434 8998 1060 2496 3106 3710 4309 4903 5492 6075 6654 7227 7796 8360 1070 1863 2473 3078 3677 4270 4859 5442 6021 6594 7163 7727 1080 1237 1846 2451 3050 3643 4232 4815 5394 5967 6536 7100 1090 615 1225 1830 2429 3022 3611 4194 4773 5346 5915 6479 1100 0 610 1214 1813 2407 2996 3579 4157 4731 5300 5864 1110 114 0 604 1203 1797 2386 2969 3548 4121 4690 5254 1120 229 115 0 599 1193 1781 2365 2943 3517 4085 4649 1130 344 229 115 0 594 1182 1766 2344 2918 3486 4050 1140 458 344 230 115 0 589 1172 1750 2324 2893 3457 L) 1150 574 459 345 230 115 0 583 1162 1735 2304 2868 1160 689 574 460 345 230 115 0 578 1152 1721 2285 1170 804 690 575 461 346 231 115 0 574 1142 1706 1180 920 806 691 576 462 346 231 116 0 569 1133 1190 1036 922 807 692 577 462 347 232 116 0 564 1200 1152 1038 923 808 694 578 463 348 232 116 0 1210 1268 1154 1039 925 810 695 579 464 348 232 116 1220 1385 1270 1156 1041 926 811 696 580 465 349 233 1230 1501 1387 1273 1158 1043 928 813 697 581 466 349 1240 1618 1504 1389 1275 1160 1045 930 814 698 582 466 1250 1735 1621 1507 1392 1277 1162 1047 931 815 700 583 1260 1853 1738 1624 1509 1394 1279 1164 1048 933 817 701 1270 1970 1856 1741 1627 1512 1397 1281 1166 1050 934 818 1280 2088 1974 1859 1744 1629 1514 1399 1284 1168 1052 936 1290 2206 2092 1977 1862 1747 1632 1517 1402 1286 1170 1054 1300 2324 2210 2095 1980 1866 1750 1635 1520 1404 1288 1172 1310 2442 2328 2213 2099 1984 1869 1753 1638 1522 1406 1290 1320 2561 2447 2332 2217 2102 1987 1872 1757 1641 1525 1409 1330 2680 2565 2451 2336 2221 2106 1991 1875 1760 1644 1528 1340 2799 2684 2570 2455 2340 2225 2110 1994 1879 1763 1647 1350 2918 2803 2689 2574 2459 2344 2229 2113 1998 1882 1766 1360 3037 2923 2808 2694 2579 2464 2348 2233 2117 2001 1885 1370 3157 3042 2928 2813 2698 2583 2468 2352 2237 2121 2005 1380 3276 3162 3048 2933 2818 2703 2588 2472 2356 2241 2124 1390 3396 3282 3168 3053 2938 2823 2708 2592 2476 2361 2245 1400 3517 3402 3288 3173 3058 2943 2828 2712 2597 2481 2365 uNIT 1 Page 16 of 20
0Pl1lAl6100l22 LJNInI 1 Enclosure 4.3
- Section 5.1 Caution: I/in Mode 3, 4 or 5, a correction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1200 1210 1220 1230 1240 1250 1260 1270 1280 1290 1300 1010 11616 12175 12730 13280 13825 14367 14904 15436 15965 16489 17010 1020 10952 11511 12066 12616 13161 13703 14240 14772 15301 15825 16346 1030 10294 10854 11408 11958 12504 13045 13582 14115 14643 15168 15688 1040 9643 10203 10757 11307 11853 12394 12931 13464 13992 14517 15037 1050 8998 9558 10112 10662 11208 11749 12286 12819 13348 13872 14392 1060 8360 8919 9474 10024 10569 11111 11648 12180 12709 13233 13754 1070 7727 8286 8841 9391 9937 10478 11015 11547 12076 12600 13121 1080 7100 7659 8214 8764 9310 9851 10388 10921 11449 11974 12494 1090 6479 7038 7593 8143 8689 9230 9767 10300 10828 11352 11873 1100 5864 6423 6977 7528 8073 8614 9151 9684 10213 10737 11257 1110 5254 5813 6368 6918 7463 8005 8542 9074 9603 10127 10648 1120 4649 5209 5763 6313 6859 7400 7937 8470 8998 9523 10043 1130 4050 4610 5164 5714 6260 6801 7338 7871 8399 8924 9444 1140 3457 4016 4570 5121 5666 6207 6744 7277 7806 8330 8850 1150 2868 3427 3982 4532 5078 5619 6156 6689 7217 7742 8262 1160 2285 2844 3398 3949 4494 5035 5572 6105 6634 7158 7678 1170 1706 2265 2820 3370 3916 4457 4994 5527 6055 6580 7100 1180 1133 1692 2246 2797 3342 3884 4420 4953 5482 6006 6527 1190 564 1123 1678 2228 2774 3315 3852 4385 4913 5437 5958 1200 0 559 1114 1664 2210 2751 3288 3821 4349 4874 5394 1210 116 0 555 1105 1650 2192 2729 3261 3790 4314 4835 1220 233 116 0 550 1096 1637 2174 2707 3235 3760 4280 1230 349 233 117 0 546 1087 1624 2157 2685 3210 3730 1240 466 350 234 117 0 541 1078 1611 2139 2664 3184 U 1250 583 467 351 234 117 0 537 1070 1598 2123 2643 1260 701 584 468 351 234 117 0 533 1061 1586 2106 1270 818 702 585 469 352 235 118 0 529 1053 1573 o 1280 936 820 703 586 470 353 235 118 0 524 1045 1290 1054 938 821 704 588 470 353 236 118 0 520 1300 1172 1056 939 823 706 589 471 354 236 118 0 1310 1290 1174 1058 941 824 707 590 472 354 236 118 1320 1409 1293 1176 1059 943 825 708 591 473 355 237 1330 1528 1411 1295 1178 1061 944 827 709 592 474 356 1340 1647 1530 1414 1297 1180 1063 946 828 711 593 475 1350 1766 1649 1533 1416 1299 1182 1065 947 830 712 594 1360 1885 1769 1652 1536 1419 1302 1184 1067 949 831 713 1370 2005 1888 1772 1655 1538 1421 1304 1186 1069 951 833 1380 2124 2008 1892 1775 1658 1541 1424 1306 1189 1071 952 1390 2245 2128 2012 1895 1778 1661 1544 1426 1309 1191 1073 1400 2365 2248 2132 2015 1898 1781 1664 1546 1429 1311 1193 1410 2485 2369 2252 2136 2019 1902 1784 1667 1549 1431 1313 1420 2606 2490 2373 2256 2139 2022 1905 1788 1670 1552 1434 1430 2727 2610 2494 2377 2260 2143 2026 1908 1791 1673 1555 1440 2848 2732 2615 2498 2381 2264 2147 2030 1912 1794 1676 1450 2969 2853 2736 2620 2503 2386 2268 2151 2033 1915 1797 1460 3091 2974 2858 2741 2624 2507 2390 2272 2155 2037 1919 1470 3212 3096 2980 2863 2746 2629 2512 2394 2276 2159 2040 1480 3334 3218 3102 2985 2868 2751 2634 2516 2398 2280 2162 1490 3457 3340 3224 3107 2990 2873 2756 2638 2521 2403 2285 1500 3579 3463 3346 3230 3113 2996 2878 2761 2643 2525 2407 IJ1NIT 1 Page 17 of 20
0Pl1lA16100l22 UNIT 1 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1300 1310 1320 1330 1340 1350 1360 1370 1380 1390 1400 1110 10648 11164 11676 12185 12690 13191 13688 14182 14672 15159 15642 1120 10043 10560 11072 11581 12085 12586 13084 13577 14068 14554 15037 1130 9444 9961 10473 10982 11486 11987 12485 12978 13469 13955 14438 1140 8850 9367 9879 10388 10893 11394 11891 12385 12875 13361 13844 1150 8262 8778 9291 9799 10304 10805 11303 11796 12286 12773 13256 1160 7678 8195 8707 9216 9721 10222 10719 11213 11703 12189 12672 1170 7100 7616 8129 8637 9142 9643 10141 10634 11124 11611 12094 1180 6527 7043 7555 8064 8569 9070 9567 10061 10551 11037 11521 1190 5958 6474 6987 7495 8000 8501 8998 9492 9982 10469 10952 1200 5394 5910 6423 6931 7436 7937 8434 8928 9418 9905 10388 1210 4835 5351 5864 6372 6877 7378 7875 8369 8859 9346 9829 1220 4280 4796 5309 5817 6322 6823 7321 7814 8304 8791 9274 1230 3730 4246 4759 5267 5772 6273 6771 7264 7754 8241 8724 1240 3184 3701 4213 4722 5226 5728 6225 6719 7209 7695 8178 1250 2643 3159 3672 4180 4685 5186 5684 6177 6667 7154 7637 1260 2106 2622 3135 3643 4148 4649 5147 5640 6130 6617 7100 ,, 1270 1573 2090 2602 3111 3616 4117 4614 5108 5598 6084 6567 1280 1045 1561 2074 2582 3087 3588 4085 4579 5069 5556 6039 1290 520 1037 1549 2058 2563 3064 3561 4055 4545 5031 5514 1300 0 516 1029 1537 2042 2543 3041 3534 4024 4511 4994 1310 118 0 512 1021 1526 2027 2524 3018 3508 3995 4478 1320 237 119 0 509 1013 1514 2012 2505 2996 3482 3965 1330 356 237 119 0 505 1006 1503 1997 2487 2973 3457 1340 475 356 238 119 0 501 998 1492 1982 2469 2952 U 1350 594 475 357 238 119 0 497 991 1481 1968 2451 1360 713 595 476 357 239 119 0 494 984 1470 1953 L) 1370 833 714 596 477 358 239 120 0 490 977 1460 1380 952 834 716 597 478 359 239 120 0 487 970 1390 1073 954 836 717 598 479 359 240 120 0 483 1400 1193 1074 956 837 718 599 480 360 240 120 0 1410 1313 1195 1076 958 839 719 600 480 361 241 120 1420 1434 1316 1197 1078 959 840 721 601 481 361 241 1430 1555 1436 1318 1199 1080 961 842 722 602 482 362 1440 1676 1557 1439 1320 1201 1082 963 843 723 603 483 1450 1797 1679 1560 1442 1323 1203 1084 964 845 725 604 1460 1919 1800 1682 1563 1444 1325 1206 1086 966 846 726 1470 2040 1922 1804 1685 1566 1447 1327 1208 1088 968 848 1480 2162 2044 1926 1807 1688 1569 1449 1330 1210 1090 970 1490 2285 2166 2048 1929 1810 1691 1571 1452 1332 1212 1092 1500 2407 2289 2170 2051 1932 1813 1694 1574 1454 1334 1214 1510 2530 2411 2293 2174 2055 1936 1816 1697 1577 1457 1337 1520 2652 2534 2416 2297 2178 2059 1939 1820 1700 1580 1460 1530 2776 2657 2539 2420 2301 2182 2062 1943 1823 1703 1583 1540 2899 2781 2662 2543 2424 2305 2186 2066 1946 1826 1706 1550 3022 2904 2786 2667 2548 2429 2309 2190 2070 1950 1830 1560 3146 3028 2909 2791 2672 2552 2433 2313 2194 2074 1953 1570 3270 3152 3033 2915 2796 2676 2557 2437 2318 2198 2077 1580 3394 3276 3157 3039 2920 2801 2681 2562 2442 2322 2202 1590 3519 3400 3282 3163 3044 2925 2806 2686 2566 2446 2326 1600 3643 3525 3407 3288 3169 3050 2930 2811 2691 2571 2451 LJ1NIT 1 Page 18 of 20
{_J]%J]rf OPI1IA/6100122 Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, X from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1400 1410 1420 1430 1440 1450 1460 1470 1480 1490 1500 1210 9829 10308 10785 11257 11727 12193 12657 13117 13573 14027 14478 1220 9274 9754 10230 10703 11172 11639 12102 12562 13019 13473 13923 1230 8724 9204 9680 10153 10622 11089 11552 12012 12469 12922 13373 1240 8178 8658 9134 9607 10077 10543 11006 11466 11923 12377 12828 1250 7637 8117 8593 9066 9535 10002 10465 10925 11382 11836 12286 1260 7100 7580 8056 8529 8998 9465 9928 10388 10845 11299 11749 1270 6567 7047 7523 7996 8466 8932 9395 9855 10312 10766 11217 1280 6039 6518 6995 7468 7937 8404 8867 9327 9784 10237 10688 1290 5514 5994 6470 6943 7413 7879 8342 8802 9259 9713 10164 1300 4994 5474 5950 6423 6892 7359 7822 8282 8739 9193 9643 1310 4478 4957 5433 5906 6376 6842 7305 7765 8222 8676 9127 1320 3965 4445 4921 5394 5864 6330 6793 7253 7710 8164 8614 1330 3457 3936 4412 4885 5355 5821 6284 6744 7201 7655 8106 1340 2952 3431 3908 4381 4850 5317 5780 6240 6697 7150 7601 1350 2451 2930 3407 3880 4349 4815 5279 5739 6195 6649 7100 1360 1953 2433 2909 3382 3852 4318 4781 5241 5698 6152 6603 1370 1460 1939 2416 2888 3358 3824 4288 4748 5204 5658 6109 1380 970 1449 1926 2398 2868 3334 3798 4257 4714 5168 5619 1390 483 963 1439 1912 2381 2848 3311 3771 4228 4682 5132 1400 0 480 956 1429 1898 2365 2828 3288 3745 4199 4649 1410 120 0 476 949 1419 1885 2348 2808 3265 3719 4170 1420 241 121 0 473 943 1409 1872 2332 2789 3243 3693 1430 362 242 121 0 470 936 1399 1859 2316 2770 3221 1440 483 363 242 121 0 466 930 1389 1846 2300 2751 U 1450 604 484 363 242 121 0 463 923 1380 1834 2285 1460 726 605 485 364 243 122 0 460 917 1371 1821 1470 848 727 607 486 365 243 122 0 457 911 1361 1480 970 849 729 608 487 365 244 122 0 454 905 1490 1092 971 851 730 609 487 366 244 122 0 451 1500 1214 1094 973 852 731 610 488 367 245 122 0 1510 1337 1216 1096 975 854 732 611 489 367 245 123 1520 1460 1339 1219 1098 977 855 734 612 490 368 245 1530 1583 1462 1342 1221 1100 978 857 735 613 491 369 1540 1706 1586 1465 1344 1223 1102 980 858 736 614 492 1550 1830 1709 1589 1468 1347 1225 1104 982 860 738 615 1560 1953 1833 1712 1591 1470 1349 1228 1106 984 862 739 1570 2077 1957 1836 1715 1594 1473 1351 1230 1108 986 863 1580 2202 2081 1961 1840 1719 1597 1476 1354 1232 1110 987 1590 2326 2206 2085 1964 1843 1722 1600 1478 1356 1234 1112 1600 2451 2330 2210 2089 1968 1846 1725 1603 1481 1359 1237 1610 2576 2455 2335 2214 2093 1971 1850 1728 1606 1484 1361 1620 2701 2580 2460 2339 2218 2096 1975 1853 1731 1609 1487 1630 2826 2706 2585 2464 2343 2222 2100 1979 1857 1734 1612 1640 2952 2831 2711 2590 2469 2347 2226 2104 1982 1860 1738 1650 3078 2957 2837 2716 2595 2473 2352 2230 2108 1986 1863 1660 3204 3083 2963 2842 2721 2599 2478 2356 2234 2112 1989 1670 3330 3210 3089 2968 2847 2726 2604 2482 2360 2238 2116 1680 3457 3336 3215 3095 2973 2852 2731 2609 2487 2365 2242 1690 3583 3463 3342 3221 3100 2979 2857 2736 2614 2492 2369 1700 3710 3590 3469 3348 3227 3106 2984 2863 2741 2619 2496 LJrIT 1 Page 19 of 20
OPI1/A16100122 IJ1NIT 1 - Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1500 1510 1520 1530 1540 1550 1560 1570 1580 1590 1600 1310 9127 9575 10019 10461 10900 11337 11770 12200 12628 13054 13476 1320 8614 9062 9507 9949 10388 10824 11257 11688 12116 12541 12964 1330 8106 8554 8998 9440 9879 10315 10749 11179 11607 12032 12455 1340 7601 8049 8494 8936 9375 9811 10244 10675 11103 11528 11950 1350 7100 7548 7993 8434 8874 9310 9743 10174 10601 11027 11449 1360 6603 7050 7495 7937 8376 8812 9246 9676 10104 10529 10952 1370 6109 6557 7002 7443 7882 8319 8752 9183 9610 10036 10458 1380 5619 6067 6511 6953 7392 7829 8262 8693 9120 9546 9968 1390 5132 5580 6025 6467 6906 7342 7775 8206 8634 9059 9481 1400 4649 5097 5542 5984 6423 6859 7292 7723 8151 8576 8998 1410 4170 4617 5062 5504 5943 6379 6813 7243 7671 8096 8519 1420 3693 4141 4586 5028 5467 5903 6336 6767 7195 7620 8043 1430 3221 3668 4113 4555 4994 5430 5864 6294 6722 7147 7570 1440 2751 3199 3643 4085 4524 4961 5394 5825 6252 6678 7100 1450 2285 2732 3177 3619 4058 4494 4928 5358 5786 6211 6634 1460 1821 2269 2714 3156 3595 4031 4464 4895 5323 5748 6171
, 1470 1361 1809 2254 2696 3135 3571 4004 4435 4863 5288 5711 1480 905 1352 1797 2239 2678 3114 3548 3978 4406 4831 5254 1490 451 899 1343 1785 2224 2660 3094 3524 3952 4377 4800 1500 0 448 893 1334 1773 2210 2643 3074 3501 3927 4349 1510 123 0 445 887 1326 1762 2195 2626 3054 3479 3901 1520 245 123 0 442 881 1317 1750 2181 2609 3034 3457 1530 369 246 123 0 439 875 1309 1739 2167 2592 3015 1540 492 369 246 123 0 436 870 1300 1728 2153 2576
- c. 1550 615 493 370 247 124 0 433 864 1292 1717 2139 1560 739 617 494 371 247 124 0 431 858 1284 1706 1570 863 741 618 495 371 248 124 0 428 853 1276 1580 987 865 742 619 496 372 248 124 0 425 848 1590 1112 989 866 743 620 496 373 249 124 0 422 1600 1237 1114 991 868 745 621 497 373 249 125 0 1610 1361 1239 1116 993 870 746 622 498 374 250 125 1620 1487 1364 1241 1118 995 871 747 623 499 375 250 1630 1612 1489 1366 1243 1120 997 873 749 625 500 375 1640 1738 1615 1492 1369 1246 1122 998 874 750 626 501 1650 1863 1741 1618 1495 1371 1248 1124 1000 876 752 627 1660 1989 1867 1744 1621 1498 1374 1250 1126 1002 878 753 1670 2116 1993 1870 1747 1624 1500 1377 1253 1128 1004 879 1680 2242 2120 1997 1874 1750 1627 1503 1379 1255 1130 1006 1690 2369 2246 2124 2001 1877 1754 1630 1506 1382 1257 1133 1700 2496 2374 2251 2128 2004 1881 1757 1633 1509 1384 1260 1710 2623 2501 2378 2255 2132 2008 1884 1760 1636 1512 1387 1720 2751 2628 2505 2382 2259 2135 2012 1888 1764 1639 1514 1730 2879 2756 2633 2510 2387 2263 2139 2015 1891 1767 1642 1740 3007 2884 2761 2638 2515 2391 2267 2143 2019 1895 1770 1750 3135 3012 2889 2766 2643 2519 2396 2272 2148 2023 1898 1760 3263 3141 3018 2895 2771 2648 2524 2400 2276 2152 2027 1770 3392 3269 3147 3024 2900 2777 2653 2529 2405 2280 2156 1780 3521 3398 3276 3152 3029 2906 2782 2658 2534 2409 2285 1790 3650 3528 3405 3282 3158 3035 2911 2787 2663 2538 2414 1800 3780 3657 3534 3411 3288 3164 3041 2917 2792 2668 2543 LJrIT 1 Page 20 of 20
0Pl1lAl6100l22 UNIT 1 - Enclosure 43 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor, K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1600 1610 1620 1630 1640 1650 1660 1670 1680 1690 1700 1410 8519 8939 9356 9771 10183 10592 11000 11404 11807 12207 12604 1420 8043 8462 8880 9294 9707 10116 10523 10928 11330 11730 12128 1430 7570 7990 8407 8821 9234 9643 10050 10455 10858 11257 11655 1440 7100 7520 7937 8352 8764 9174 9581 9986 10388 10788 11185 1450 6634 7054 7471 7886 8298 8707 9114 9519 9922 10321 10719 1460 6171 6590 7008 7422 7835 8244 8651 9056 9458 9858 10256 1470 5711 6130 6548 6962 7375 7784 8191 8596 8998 9398 9796 1480 5254 5674 6091 6505 6918 7327 7734 8139 8542 8941 9339 1490 4800 5220 5637 6052 6464 6874 7281 7685 8088 8488 8885 1500 4349 4769 5186 5601 6013 6423 6830 7235 7637 8037 8434 1510 3901 4321 4738 5153 5565 5975 6382 6787 7189 7589 7987 1520 3457 3876 4294 4708 5121 5530 5937 6342 6744 7144 7542 1530 3015 3435 3852 4266 4679 5088 5495 5900 6303 6702 7100 1540 2576 2996 3413 3827 4240 4649 5056 5461 5864 6263 6661 1550 2139 2559 2977 3391 3803 4213 4620 5025 5427 5827 6225 1560 1706 2126 2543 2958 3370 3780 4187 4592 4994 5394 5791 1570 1276 1695 2113 2527 2940 3349 3756 4161 4563 4963 5361 1580 848 1268 1685 2099 2512 2921 3328 3733 4136 4535 4933 1590 422 842 1260 1674 2086 2496 2903 3308 3710 4110 4508 1600 0 420 837 1252 1664 2074 2481 2886 3288 3688 4085 1610 125 0 417 832 1244 1654 2061 2466 2868 3268 3666 1620 250 125 0 415 827 1237 1644 2048 2451 2851 3248 1630 375 251 125 0 412 822 1229 1634 2036 2436 2834 1640 501 376 251 126 0 410 817 1222 1624 2024 2421 L) 1650 627 502 377 251 126 0 407 812 1214 1614 2012 1660 753 628 503 378 252 126 0 405 807 1207 1605 1670 879 754 629 504 378 252 126 0 402 802 1200 1680 1006 881 756 630 505 379 253 127 0 400 798 1690 1133 1008 883 757 632 506 380 253 127 0 398 1700 1260 1135 1010 884 759 633 507 380 254 127 0 1710 1387 1262 1137 1011 886 760 634 508 381 254 127 1720 1514 1389 1264 1139 1013 888 761 635 509 382 255 1730 1642 1517 1392 1267 1141 1015 889 763 636 510 383 1740 1770 1645 1520 1395 1269 1143 1017 891 764 638 511 1750 1898 1773 1648 1523 1397 1272 1145 1019 893 766 639 1760 2027 1902 1777 1651 1526 1400 1274 1148 1021 894 767 1770 2156 2031 1906 1780 1655 1529 1403 1276 1150 1023 896 1780 2285 2160 2035 1909 1784 1658 1532 1405 1279 1152 1025 1790 2414 2289 2164 2038 1913 1787 1661 1535 1408 1281 1154 1800 2543 2418 2293 2168 2042 1916 1790 1664 1537 1411 1284 1810 2673 2548 2423 2298 2172 2046 1920 1794 1667 1540 1413 1820 2803 2678 2553 2428 2302 2176 2050 1924 1797 1670 1543 1830 2933 2808 2683 2558 2432 2306 2180 2054 1927 1801 1674 1840 3064 2939 2814 2688 2563 2437 2311 2184 2058 1931 1804 1850 3194 3069 2944 2819 2693 2567 2441 2315 2189 2062 1935 1860 3325 3200 3075 2950 2824 2698 2572 2446 2320 2193 2066 1870 3457 3332 3207 3081 2956 2830 2704 2577 2451 2324 2197 1880 3588 3463 3338 3213 3087 2961 2835 2709 2582 2455 2328 1890 3720 3595 3470 3344 3219 3093 2967 2841 2714 2587 2460 1900 3852 3727 3602 3476 3351 3225 3099 2973 2846 2719 2592 LJ]NIT 1 Page 21 of 20
OPI1IA/6100122 ijJNIi1 1. .
. Enclosure 4.3 Section 5.1 Caution: If in Mode 3, 4 or 5, a correction factor K, from Table 5.2 must be applied PRESENT BORON CONCENTRATION (ppmB) 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 2700 1700 0 3852 7495 10952 14240 17375 20370 23238 25989 28632 31175 1725 319 2868 6511 9968 13256 16391 19386 22254 25005 27648 30191 1750 639 1898 5542 8998 12286 15421 18417 21285 24036 26679 29222 1775 960 943 4586 8043 11330 14465 17461 20329 23080 25723 28266 1800 1284 0 3643 7100 10388 13523 16518 19386 22137 24780 27323 1825 1608 325 2714 6171 9458 12593 15589 18457 21208 23851 26394 1850 1935 651 1797 5254 8542 11676 14672 17540 20291 22934 25477 1875 2263 979 893 4349 7637 10772 13767 16635 19386 22029 24573 1900 2592 1309 0 3457 6744 9879 12875 15743 18494 21137 23680 1925 2923 1640 331 2576 5864 8998 11994 14862 17613 20256 22799 1950 3256 1972 664 1706 4994 8129 11124 13992 16743 19386 21930 1975 3591 2307 998 848 4136 7270 10266 13134 15885 18528 21071 2000 3927 2643 1334 0 3288 6423 9418 12286 15037 17680 20223 2025 4264 2981 1672 338 2451 5586 8581 11449 14200 16843 19386
& 2050 4604 3320 2012 677 1624 4759 7754 10622 13373 16016 18559 2075 4945 3661 2353 1018 807 3942 6937 9805 12556 15199 17743 2100 5288 4004 2696 1361 0 3135 6130 8998 11749 14392 16936 2125 5633 4349 3041 1706 345 2337 5333 8201 10952 13595 16138 2150 5979 4696 3387 2053 691 1549 4545 7413 10164 12807 15350 2175 6327 5044 3735 2401 1039 770 3766 6634 9385 12028 14571 Z 2200 6678 5394 4085 2751 1389 0 2996 5864 8614 11257 13801 2225 7029 5746 4437 3103 1741 352 2234 5102 7853 10496 13039 Z 2250 7383 6100 4791 3457 2095 706 1481 4349 7100 9743 12286 2275 7739 6455 5147 3812 2451 1061 736 3604 6355 8998 11542 2300 8096 6813 5504 4170 2808 1419 0 2868 5619 8262 10805 2325 8456 7172 5864 4529 3168 1778 359 2139 4890 7533 10077 2350 8817 7533 6225 4890 3529 2139 721 1419 4170 6813 9356 2375 9180 7897 6588 5254 3892 2503 1084 706 3457 6100 8643 2400 9546 8262 6953 5619 4257 2868 1449 0 2751 5394 7937 2425 9913 8629 7321 5986 4625 3235 1816 367 2053 4696 7239 2450 10282 8998 7690 6355 4994 3604 2186 736 1361 4004 6548 2475 10653 9370 8061 6727 5365 3976 2557 1108 677 3320 5864 2500 11027 9743 8434 7100 5739 4349 2930 1481 0 2643 5186 2525 11402 10118 8810 7475 6114 4725 3306 1857 375 1972 4516 2550 11780 10496 9187 7853 6492 5102 3683 2234 753 1309 3852 2575 12159 10876 9567 8233 6871 5482 4063 2614 1133 651 3194 2600 12541 11257 9949 8614 7253 5864 4445 2996 1514 0 2543 2625 12925 11641 10333 8998 7637 6248 4829 3379 1898 384 1898 2650 13311 12028 10719 9385 8023 6634 5215 3766 2285 770 1260 2675 13700 12416 11107 9773 8412 7022 5603 4154 2673 1159 627 2700 14090 12807 11498 10164 8802 7413 5994 4545 3064 1549 0 LJ1NIT 1 Page 22 of 20
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U IN ki!T I 4 I Enclosure 4.3 Table 6.3.3 Integral Rod Worth in Overlap HFP, EqUiHbriumXenon Unit I Cycle 21 4 EFPD 100 EFPD 200 EFPD 300 EFPD 400 EFPD Control Bank Position 0-50 EFPD 51 - 150 EFPD 151 -250 EFPD 251 -350 EFPD 351 - EOW Steps Withdrawn
- IRW IRW IRW IRW IRW Bk A Bk B Bk C Bk D (PCM) (PCM) (PCM) (PCM) (PCM) 226 226 196 80 572 571 591 635 689 226 226 191 75 615 614 636 684 741 226 226 186 70 658 658 681 732 793 226 226 181 65 702 701 726 780 845 226 226 176 60 745 745 772 829 896 226 226 171 55 791 792 820 879 948 226 226 166 50 837 839 868 928 999 226 226 161 45 882 886 917 978 1050 226 226 156 40 928 933 965 1028 1101 226 226 151 35 977 981 1014 1077 1150 226 226 146 30 1025 1029 1062 1126 1199 226 226 141 25 1073 1078 1111 1175 1248 226 226 136 20 1122 1126 1159 1225 1297 226 226 131 15 1166 1168 1201 1266 1338 226 226 126 10 1209 1210 1242 1307 1379 226 226 121 5 1253 1252 1284 1348 1420 226 226 116 0 1297 1295 1325 1389 1461 226 226 110 0 1336 1335 1364 1427 1497 226 221 105 0 1371 1370 1398 1461 1533 226 216 100 0 1405 1405 1433 1495 1568 226 211 95 0 1449 1448 1476 1539 1615 226 206 90 0 1493 1491 1519 1584 1663 226 201 85 0 1538 1534 1563 1629 1711 226 196 80 0 1582 1577 1606 1673 1759 226 191 75 0 1630 1626 1655 1724 1812 226 186 70 0 1678 1675 1705 1775 1865 226 181 65 0 1726 1724 1754 1826 1918 226 176 60 0 1775 1772 1803 1876 1971 226 171 55 0 1827 1825 1856 1930 2025 226 166 50 0 1879 1877 1910 1983 2079
- NOTE: For actual ALL Rods out Overlap Data, see Enclosure 4.3, Section 1.13 of the Data Book UNIT I
OP/I 116100/022 UNIT I Enclosure 4.3 Table 6.3.3 Integral Rod Worth in Overlap HFP, Equilibrium XenOn Unit I Cycle 21 4 EFPD 100 EFPD 200 EFPD 300 EFPD 400 EFPD Control Bank Position 0 -50 EFPD 51 - 150 EFPD 151 250 EFPD 251 -350 EFPD
- 351 - EOW Steps Withdrawn IRW IRW IRW IRW IRW Bk A Bk B Bk C Bk D (PCM) (PCM) (PCM) (PCM) (PCM) 226 161 45 0 1931 1930 1963 2037 2133 226 156 40 0 1983 1983 2016 2090 2187 226 151 35 0 2038 2035 2068 2143 2240 226 146 30 0 2092 2087 2121 2196 2294 226 141 25 0 2147 2140 2173 2249 2347 226 136 20 0 2201 2192 2226 2302 2401 226 131 15 0 2246 2232 2266 2342 2443 226 126 10 0 2290 2273 2305 2383 2484 226 121 5 0 2335 2313 2345 2423 2526 226 116 0 0 2379 2354 2385 2464 2568 226 110 0 0 2407 2383 2415 2493 2598 221 105 0 0 2433 2410 2442 2522 2628 216 100 0 0 2460 2437 2469 2550 2659 211 95 0 0 2495 2473 2506 2589 2701 206 90 0 0 2531 2509 2543 2628 2743 201 85 0 0 2566 2545 2580 2667 2785 196 80 0 0 2602 2581 2617 2706 2827 191 75 0 0 2639 2622 2660 2751 2874 186 70 0 0 2676 2663 2703 2796 2921 181 65 0 0 2714 2704 2746 2841 2967 176 60 0 0 2751 2745 2789 2885 3014 171 55 0 0 2791 2789 2835 2932 3061 166 50 0 0 2831 2833 2881 2978 3108 161 45 0 0 2871 2877 2927 3025 3154 156 40 0 0 2911 2922 2973 3071 3201 151 35 0 0 2952 2965 3017 3116 3246 146 30 0 0 2992 3008 3061 3160 3290 141 25 0 0 3032 3051 3105 3205 3335 136 20 0 0 3073 3094 3149 3249 3380 131 15 0 0 3105 3127 3182 3281 3412
- NOTE: For actual ALL Rods out Overlap Data, see Enclosure 4.3, Section 1.13 of the Data Book UNIT I
OPII 11101022 UNIT I Enclosure 4.3 Table 6.3.3 Integral Rod Worth in Overlap N, Equilibrium Xenon Unit I Cycle 21 4 EFPD 100 EFPD 200 EFPD 300 EFPD 400 EFPD Control Bank Position 0 -50 EFPD 51 - 150 EFPD 151 250 EFPD 251 350 EFPD
- - 351 - EOW Steps Withdrawn
- IRW IRW IRW IRW IRW BkA BkB BkC Bk D (PCM) (PCM) (PCM) (PCM) (PCM) 126 10 0 0 3137 3160 3215 3314 3445 121 5 0 0 3169 3194 3248 3346 3477 116 0 0 0 3202 3227 3281 3379 3510 110 0 0 0 3223 3253 3307 3402 3532 105 0 0 0 3239 3274 3327 3420 3549 100 0 0 0 3255 3294 3347 3439 3565 95 0 0 0 3271 3315 3366 3456 3581 90 0 0 0 3287 3335 3386 3473 3597 85 0 0 0 3303 3355 3405 3490 3613 80 0 0 0 3318 3375 3424 3508 3628 75 0 0 0 3333 3394 3443 3524 3643 70 0 0 0 3348 3413 3461 3540 3657 65 0 0 0 3363 3432 3479 3556 3672 60 0 0 0 3378 3451 3498 3572 3686 55 0 0 0 3393 3469 3515 3588 3700 50 0 0 0 3407 3487 3533 3604 3715 45 0 0 0 3422 3506 3551 3620 3729 40 0 0 0 3437 3524 3569 3636 3743 35 0 0 0 3451 3539 3584 3650 3757 30 0 0 0 3464 3554 3599 3665 3770 25 0 0 0 3478 3569 3614 3679 3784 20 0 0 0 3492 3584 3629 3693 3797 15 0 0 0 3503 3592 3637 3701 3805 10 0 0 0 3513 3600 3644 3709 3813 5 0 0 0 3523 3608 3652 3717 3821 0 0 0 0 3533 3616 3660 3724 3829
- NOTE: For actual ALL Rods out Overlap Data, see Enclosure 4.3, Section 1.13 of the Data Book UNIT I
Appendix C Job Performance Measure Form ES-C-i sheet JPMA2RO 2011 Admin-JPMA2 RO(Rev_041111) NUREG 1021, Revision 9
Appendix C Page 2 of 6 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.: Task
Title:
Use Main Generator Carability JPM No.: 2011 Admin JPM A2 Curve RO K/A
Reference:
GKIA 2.2.2 (4.6) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant 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: Unit #1 is at 74% reactor power with the following conditions:
- Generator load is 840 MWE
- Power factor is 0.85 lagging
- Generator Hydrogen pressure is 75 psig
- Generator voltage is 23.9 Ky Power increase to 100% is imminent.
Task Standard: The operator will select the correct Generator Capability Curve (Curve 3.1.2) and use it to determine the maximum permissible generator load and reactive load. Once completed, the operator will determine the desired voltage per the Generator Voltage Operating Schedule. Required Materials: None. General
References:
OP/i/A16100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.1, Calculated Capability Curve at 95% Voltage (22.8KV) OP/i/A16100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.2, Calculated Capability Curve at 100% Voltage (24KV) OP/i/A16100/022 (Core Data Book), Enclosure 4.3, Table 3.1.3, McGuire Nuclear Station Generator Voltage Operating Schedule (kV) 2011 Admin JPM A2 RO
- NUREG 1021, Revision 9
Appendix C Page 3 of 6 Form ES-C-i
- Job Performance Measure Worksheet OP/11A161001022 (Core Data Book), Enclosure 4.3, Table 3.1.4, McGuire Nuclear Station Generator Capability Curve Application Guidance Handouts: OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.1, Calculated Capability Curve at 95% Voltage (22.8KV)
OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.2, Calculated Capability Curve at 100% Voltage (24KV) OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Table 3.1.3, McGuire Nuclear Station Generator Voltage Operating Schedule (kV) OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Table 3.1.4, McGuire Nuclear Station Generator Capability Curve Application Guidance Initiating Cue: The CRS has directed you to determine the following assuming a power factor of 0.85 is maintained constant during the power increase:
- the maximum permissible generator load
- the maximum reactive load
- the desired voltage per the Generator Voltage Operating Schedule for todays date/time.
Time Critical Task: NO Validation Time: 15 minutes 2011 Admin JPM A2 RO
- NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-i . PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*) Provide Candidate with Initial ConditionslCue, and Handout the Four (4) handouts listed. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*1 Assuming a power factor of The operator selects Curve 0.85 is maintained constant 3.1.1.
during the power increase, determine the maximum permissible generator load. Using 0.85 power factor and 75 psig H2 pressure, the operator determines the maximum permissible generator load to be: 1070 Mw (+/-10 Mw)
*2 Assuming a power factor of The operator selects Curve 0.85 is maintained constant 3.1.1.
during the power increase, determine the maximum Using 0.85 power factor and permissible reactive load. 75 psig H2 pressure, the operator determines the maximum permissible reactive load to be: 670 MVARs (+/-10 MVARs)
*3 Assuming a power factor of The operator selects Table 0.85 is maintained constant 3.1.3.
during the power increase, determine the desired Using todays time and date voltage per the Generator (Summer, Weekday, Max Voltage Operating Schedule Load), the operator determines the Desired Voltage to be 23.3 KV for Unit#1. Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2011 Admin JPM A2 RO
- NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-i VER[FICAT[ON OF COMPLET[ON Job Performance Measure No.: 2010 Admin JPM A2 RO Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2010 Admin JPM A2 RO
- NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMCUESI-{EET INITIAL CONDITIONS: Unit #1 is at 74% reactor power with the following conditions:
- Generator load is 840 MWE
- Power factor is 0.85 lagging
- Generator Hydrogen pressure is 75 psig
- Generator voltage is 23.9 KV Power increase to 100% is imminent.
INITIATING CUE: The CRS has directed you to determine the following assuming a power factor of 0.85 is maintained constant during the power increase:
- the maximum permissible generator load
- the maximum reactive load
- the desired voltage per the Generator Voltage Operating Schedule for todays date/time. per the Generator Voltage Operating Schedule NUREG 1021, Revision 9
Uniti OP/1/A/6100/022 ENCLOSURE 4.3 Curve 3.1.1 Calculated Capability Curves at 95% Voltage (22.8 kV) SIEMENS POWER GENERATION CALCULATED CAPABILITY CURVE AT 96 PERCENT VOLTAGE (22.8kV) HYDROGEN INNER-COOLED TURBINE GENERATOR WITH WATER COOLED STATOR 1264MVA, O.76PF, 46C COLD GAS 1100 1000 900 800 700 600 500 400 300 200 100 U) 0
-100 -200 -300 -400 -500 -600 -700 -800 -900 -1000 -1100 MW
Ufliti OP/1/A/6100/022 ENCLOSURE 4.3 Curve 3.1.2 Calculated Capability Curves at 100% Voltage (24 kV) SIEMENS POWER GENERATION CALCULATED CAPABILITY CURVE AT 100 PERCENT VOLTAGE (24kV) HYDROGEN INNER.COOLED TURBINE GENERATOR WITH WATER COOLED STATOR I33OMVA, 0.83PF, 46C COLD GAS 0 2 MW
VVV V OPII!N61001022 - UNIT I Enclosure 4.3 V Table 3.1.3 V V McGuire Nuclear Station Generator Voltage Operating Schedule (kV)
*Note this Generator Voltage Operating Schedule should be used when two (2) buslines are in service. ** **See Operational Restrictions for additional details.**
V Switchyard Generator Buses (Note: If both red and yellow buses are energized, (Reference) (Control Point) switchyard voltage will refer to the red bus.) V M1A0972 M2A0972 V 230kV 500kV MNSI MNS2 Summer Weekday Peak 0730-2330, Mon-Fri 233.5 530.4 23.3 23.5 Weekday Max Load 0730-2330, Mon-Fri 233.1 531.7 23.3 23.4 V 6/1 - 9120 Weekday Off-Peak V 2330-0730, Sun-Thur 235.0 531.8 23.5 23.5 V V Weekend All Hours 2330 Fri- 2330-Sun 233.4 527.2 23.4 23.3 Fall Weekday Peak 053Q2130, Mon-Fri 234.1 532.2 23.3 23.4 9/21 - 11/30 Weekday Off-peak 2130-0530, Sun-Thur 235.6 532.7 23.6 235 V Weekend All hours 2130 Fri 2130 Sun V 235.6 532.7 23.6 23.5 Winter Weekday Peak 0530-2030, Mon-Fri 239.0 538.7 24.1 23.7 12/1 - 3/20 Weekday Off-Peak 2030-0530, Sun-Thur 236.8 536.3 V 23.7 23.7
/
V V Weekend All_Hours__V 2030 Fri 2030 Sun
- 238.8 539.9 24.0 23.7 Spring Weekday Peak 0530-21 30, Mon-Fri 233.0 V
526.3 23.4 23.4 3/21 -5131 Weekday Off-Peak 2130-0530, Sun-Thur 239.2 539.1 23.9 236 V V Weekend All Hours 2130 Fri - 2130 Sun 239.2 539.1 23.9 23.6 Per agreement with Power Delivery, the nuclear units will follow the generator bus voltage. The switchyard voltage is only [or reference. Weekday Peak schedule to be used during Peak periods unless requested by SOC to use the Weekday Max Load schedule. As required by system conditions, the SOC may request changes to these voltages. Voltages shown are targets for optimal grid operation. Do not exceed stator or field temperature limits, generator capability curve, or plant bus voltage alarm setpoints in complying with this voltage schedule. If conditions approach or exceed a limit or operational restriction, adjust voltage appropriately and then notify the SOC of the situation. Operational Restrictions
- For Normal System Operation, Unit 1 Main Electric Generator output should be greater than 0 MVars.
- For abnormal grid conditions, refer to operational limits in API1IN5500!005.
- Operating limit of 224.77kV for Unit 1 and 503.37kv for Unit 2 for 2 buslines in service is used in development of these schedules.
**Minimum operating limit is 235.25kV for Unit I and 525.63kV for Unit 2 when only one busline is in service and the 4.I6kVbuss(es) is fed from that busliae.** V
- DO NOT EXCEED PLANT BUS VOLTAGE ALARM SETPOINTS Note: 1) Routine Task Calendar will be impacted if the schedule is changed.
- 2) AP/1/A15500/005 might be impacted if operational-restrictions are changed.
UNIT I Power Delivery System Planning 9116/2010
OW IJA/6100!022. Enclosure 4.3 UNIT I Table 3.1.4 MG-üiréNueIearSttIOn Generator Capability Curve ApplicatIon Guidance 22.8kV Capability Curve (Curve 3.1.1 of Enclosur e 4.3) to be used when generator output voltage 22.8kV and 24.0 kV. is between 2 24.0kV Capability Curve (Curve 3.1.2 of Enclosur e 4.3) to be used when generator output voltage higher. is 24.0 kV or NOTE: MVAR limits provided in Enclosure 4.3 are based upon Full Power (1200 MWs) operation. At power MVAR limits should be obtained from generator reduced capability curves. Actual MVAR limits are based operating generator voltage, H2- pressure, MW output, upon etc. 3 When generator MVARs exceed capability curve, refer to AP/ 11 A / 5500 / Q05 (Generator Voltage and Grid Disturbances) Electric UNIT 1
Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA4RO 2011 Admin JPM A4 RO (Rev_041311) NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-i
. Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Independently Verify Spent Fuel JPM No.: Exam 2011 Admin - Pool Level Adjustment JPM A4 RO K/A
Reference:
GKIA 2.4.34 (4.2) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant 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:
- The Emergency Plan has been implemented due to an attack on the Facility 36 hours ago.
- The hostile threat has been eliminated and the plant is now recovering, however heavy damage has been sustained.
- AP/1/A/5500/24 (Loss of Plant Control Due to Fire or Sabotage) has been implemented on Unit 1.
- The Standby Makeup Pump is operating to provide inventory to the NC System.
- The crew is attempting to maintain Spent Fuel Pool Level greater than minus 2 feet in accordance with Enclosure 4.4 (Spent Fuel Pool Level Control) of 0P111A162001005 (Spent Fuel Cooling System).
- An operator has been directed to fill the Spent Fuel Pool from the YM System as needed per Step 3.7 of this Enclosure, and is now completed through Step 3.7.2.
- Chemistry reports that the last Boron Sample of the Spent Fuel Pool was 2898 ppm.
Task Standard: The operator will be expected to review Table 4.4-1 of Enclosure 4.4 of OP/i /A/6200/005 and identify three errors, and make the required corrections. Required Materials: None 2011 Admin - JPM A4 RO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-i . Job Pe rnric Measure Worksheet General
References:
OMP 11-1 (Operations Response to a TSC/OSC Activation), Rev 6 API1/A15500/24 (Loss of Plant Control Due to Fire or Sabotage), Rev 28 OP/1IA/6200/005 (Spent Fuel Cooling System), Rev 90 McGuire Unit 1 Cycle 19 Core Operating Limits Report, Rev 30 McGuire Unit 1/2 Technical Specifications Handouts: Enclosure 4.4 (Spent Fuel Pool Level Control) of OP/1/A/6200/005 (Spent Fuel Cooling System) completed through Step 3.7.2 as follows: Step 3.1 Checkbox is checked. Step 3.2 Initialed/Name of Chemist/Todays Date Step 3.3 NA/Initialed. Step 3.4 OAC Graphic Aligned Checkbox is checked. Step 3.5 Section 3.7 Checkbox is checked. Step 3.7.1 All four Checkboxes checked. Step 3.7.2 initialed/V block BLANK Enclosure 4.4 (Spent Fuel Pool Level Control) of OP/1/A16200/005 (Spent Fuel Cooling System), Table 4.4-1 completed as follows: Check Makeup Water Source: RN Checkbox is checked. (ERROR) Last SFP Boron Sample: 2988 (ERROR) Initial Spent Fuel Pool Level: 1.5 feet Desired Spent Fuel Pool Level: 0.5 feet (ERROR carried forward) Initiating Cue: You have been directed to perform an independent verification (IV) ensuring that the total desired SEP Level change is within the guidance of the NOTE in Step 3.7. Identify any corrections or changes that are needed. Time Critical Task: NO Validation Time: 15 minutes 2011 Admin JPM A4 RO
- NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-i PERFORMANCE 1T1FORAT1O11 - (Denote Critical Steps with an asterisk*) Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout .4 of 0P111A162001005, marked up as described in the Handout Section. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
* (IV for Step 3.7.2) Ensure The operator reviews Table the total desired SFP level 4.4-i and discovers that the change is within the RN Checkbox is checked guidance of note in Step instead of the YM T Checkbox.
The operator makes this correction on Table 4.4-i.
*2 (IV for Step 3.7.2) Ensure The operator reviews Table the total desired SFP level 4.4-1 and discovers that the change is within the Last Boron sample was guidance of note in Step transposed incorrectly 3.7. (should be 2898 ppm rather than 2988 ppm).
The operator makes this correction on Table 4.4-1. 2011 Admin JPM A4 RO
- NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-i PERFORMANCE NFORMAT1O STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*3 (IV for Step 3.7.2) Ensure The operator reviews Table the total desired SFP level 4.4-i and discovers that the change is within the desired change in level is guidance of note in Step 24 inches, which would be T permissible if SEP CB was at the transposed value, but NOT permissible at the actual concentration. (The
. highest level that the SEP can be raised with the present CB at 2898 ppm is 20-23 inches. If this level adjustment is permitted, the SEP Level will drop below the COLR/TS Value of 2675 ppm value).
The operator identifies that the desired SEP level must be changed to a maximum value of 2-5 inches (maximum level of .2 to .4 ft), and records this on Table 4.4-i in the Desired Spent Fuel Pool Level Block. Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 20i i Admin JPM A4 RO
- NUREG 102i, Revision 9
Appendix C Page 6 of 7 Form ES-C-i VERIFiCATION OF COMPLETION Job Performance Measure No.: 2011 Admin JPM A4 RO Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin JPM A4 RO
- NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET - INITIAL CONDITIONS:
- The Emergency Plan has been implemented due to an attack on the Facility 36 hours ago.
- The hostile threat has been eliminated and the plant is now recovering, however heavy damage has been sustained.
- AP111A15500124 (Loss of Plant Control Due to Fire or Sabotage) has been implemented on Unit 1.
- The Standby Makeup Pump is operating to provide inventory to the NC System.
- The crew is attempting to maintain Spent Fuel Pool Level greater than minus 2 feet in accordance with Enclosure 4.4 (Spent Fuel Pool Level Control) of 0P111A162001005 (Spent Fuel Cooling System).
- An operator has been directed to fill the Spent Fuel Pool from the YM System as needed per Step 3.6 of this Enclosure, and is now completed through Step 3.6.2.
- Chemistry reports that the last Boron Sample of the Spent Fuel Pool was 2898 ppm.
INITIATING CUE:
- You have been directed to perform an independent verification (IV) ensuring that the total desired SEP Level change is within the guidance of the NOTE in Step 3.6.
- Identify any corrections or changes that are needed.
NUREG 1021, Revision 9
Duke Energy Procedure No. McGuire Nuclear Station oPIlI62ooIoo5 Spent Fuel Cooling System Revision No. 090 Electronic Reference No. MC00474B Continuous Use PERFORMANCE I
- * * * * * * * * *IJNCONTROLLEDFQRPPJNT* * * * * * * * * *
(ISSUED) PDF Format
Enclosure 4.4 oPIlIAJ6200Ioo5 Spent Fuel Pool Level Control Page 1 of 17
- 1. Limits and Precautions 1.1 Maximum Spent Fuel Pool Purification Prefilter and Postfilter DP is 40 psid.
1.2 COLR specifies minimum Spent Fuel Pool Boron concentration. 1.3 Maximum pooi temperature is 140°F. 1.4 Maximum SFP level is 8 above t1 J 1.5 Maximize VF availability to ensure worker exposure to airborne Tritium concentrations from SFP evaporation is maintained As Low As Reasonably Achievable (ALARA). {PIP G-08-0774}
- 2. Initial Conditions None
- 3. Procedure Evaluate all outstanding R&Rs that may impact performance of this procedure.
4 3.2 ci IF pooi makeup required by EP or AP, notify Chemistry of makeup source. 3 o c Sc\* Person Notified Date T 3.3 IF fuel handling occurring in Spent Fuel Pool, notify Fuel Handling Crew prior to changing Spent Fuel Pool level. Person Notified Date 3.4 Check status of FWST Recirc and Purification alignment per one of the following: {CAPR, PIP M-l0-2312} IVOAC graphic ALIGN OR D IF OAC NOT available, check Control Room status board. Unit 1
Enclosure 4.4 OPI1/A!62o0!0O5. Spent Fuel Pool Level Control Page 2 of 17 NOTE:
- Due to the Tritium concern from the RMWST, YM is the preferred makeup source to the Spent Fuel Pool.
- Pool makeup water source guidelines are as follows:
- Use YM or RMWST for Boron sample greater than 2775 ppm or dilution desired
- Use FW System for Boron sample less than 2775 ppm or boration desired 3.5 Perform the following sections, as applicable:
D,Section 3.6, Makeup Using RMWST E Section 3.7, Makeup Using YM El Section 3.8, Makeup Using B orated Water El Section 3.9, Makeup from RN System El Section 3.10, Lowering Pool Level by Draining to FWST or RHT El Section 3.11, Lowering Pool Level by Draining to WEFT 3.6 Makeup Using RMWST NOTE: The following table should not be used to determine the makeup source for the Spent Fuel Pool. This table provides clarification as to what Spent Fuel Pool Boron would be if non borated water is used as a makeup source. Last SFP Boron Sample SFP Level Change With Resultant Boron greater than 2675 ppm 2700 ppm 2 2725 ppm 5 2750 ppm 7 2775 ppm 10 2800 ppm 12 2825 ppm 15 2850 ppm 18 2875 ppm 20 2900 ppm 23 2925 ppm 25 2950 ppm 28 3.6.1 Record the following on Table 4.4-1 (Pool Makeup Data Record): El Makeup Water Source El Last SFP Boron sample El Initial Spent Fuel Pool Level El Desired Spent Fuel Pool level 3.6.2 Ensure the total desired SFP level change is within the guidance of note in IV Step 3.6. {PIP M-06-5628} Unit 1
Enclosure 4.4 oP/1MJ-2oo/oo5 - Spent Fuel Pool Level Control Page 3 of 17 3.6.3 Ensure closed:
- 1KF-81 (Unit 1 KF Supply From FW Isol)
- 1KF-83 (Unit 1 KF Supply From FW Isol) 3.6.4 Ensure locked closed:
- 1KF-85 (Unit 1 KF Supply From RN Isol)
- 1KF-86 (Unit 1 KF Supply From RN Isol) 3.6.5 Open:
- 1KF-78 (Unit 1 KF Supply From NB Isol)
- 1KF-80 (Unit 1 KF Supply From NB Isol) 3.6.6 Ensure one of the following running:
- 1A Rx M/U Water Pump
- lB Rx MJU Water Pump 3.6.7 AFTER desired level obtained, perform the following:
3.6.7.1 IFRMWST in Recirc, go to Step 3.6.7.3. 3.6.7.2 Ensure off:
- 1 A Rx M/U Water Pump
- lB Rx M!U Water Pump 3.6.7.3 Close:
- 1KF-80 (Unit 1 KF Supply From NB Isol)
- 1KF-78 (Unit 1 KF Supply From NB Isol) 3.6.8 Notify Chemistry to sample Spent Fuel Pool for Boron Concentration greater than or equal to minimum boron concentration per COLR.
/
Person Notified Date Time O 3.6.9 Complete Table 4.4-1 (Pool Makeup Data Record). O 3.6.10 Place routing stamp in remarks section of cover sheet, check (if) Engineering and fill in Table 4.4-1 only t Unit 1
Enclosure 4.4 0P4/A16200/005 Spent Fuel Pool Level Control Page 4 of 17 3.7 Makeup Using YM NOTE: The following table should not be used to determine the makeup source for the Spent Fuel Pool. This table provides clarification as to what Spent Fuel Pool Boron would be if non borated water is used as a makeup source. Last SFP Boron Sample SFP Level Change With Resultant Boron greater than 2675 ppm 2700 ppm 2 2725 ppm 5 2750 ppm 7 2775 ppm 10 2800 ppm 12 2825 ppm 15 2850 ppm 18 2875 ppm 20 2900 ppm 23 2925 ppm 25 2950 ppm 28 3.7.1 Record the following on Table 4.4-1 (Pool Makeup Data Record): Makeup Water Source Last SFP Boron sample EInitial Spent Fuel Pool Cevel 1Desired Spent Fuel Pool level 3.7.2 Ensure the total desired SFP level change is within the guidance of note in IV Step 3.7. {PIP M-06-5628} 3.7.3 Notify Secondary Chemistry that YM will be used to makeup to Unit 1 Spent Fuel Pool.
/
Person Notified Date Time 3.7.4 Request permission from Primary Chemistry to operate chemistry valve 1YM-102 (YM Supply Isol).
/
Person Notified Date Time Unit 1
Enclosure 4.4 OP/1/A/6200/005 Spent Fuel Pool Level Control Page 5 of 17 3.7.5 Notify Radiation Protection of the following:
- YM will be used for Unit 1 Spent Fuel Pool makeup
- Hose will be routed into the RCZ
- Hose will need to be surveyed during removal from the RCZ I
Person Notified Date Time 3.7.6 Ensure special Fuel Pool area FMElPersonnel safety requirements met. [1 3.7.7 Remove rubber hose from wall and attach to 1YM-l02 (YM Supply Isol). (778,QQ-51) NOTE: The floor on the pool side of the guard rail is considered contaminated. D 3.7.8 Route rubber hose to the edge of the Spent Fuel Pool and secure to guard rail. NOTE: Permission from Engineering is NOT required to open 1YM-102 (YM Supply Isol) during performance of this procedure. Completing Table 4.4-1 satisfies the requirement of notification to engineering per the placard on the wall. 3.7.9 Open 1YM-102 (YM Supply Isol). 3.7.10 Notify Control Room that YM is being added to the Spent Fuel Pool. 3.7.11 AFTER Spent Fuel Pool at desired level, perform the following: 3.7.11.1 Close 1YM-102 (YM Supply Isol). 3.7.11.2 Notify Control Room Spent Fuel Pool makeup complete. 3.7.11.3 Notify Radiation Protection of the following:
- Makeup to the Spent Fuel Pool from YM is complete
- The hose needs to be surveyed during removal from the RCZ
/
Person Notified Date Time El 3.7.11.4 Disconnect rubber hose from 1YM-102 (YM Supply Isol) and drain into pool. El 3.7.11.5 IF required, remove and dispose plastic sleeve per RP. 0 3.7.11.6 Replace rubber hose on wall. Unit 1
Enclosure 4.4 oPIl/AI62ooIoo5 Spent Fuel Pool Level Control Page 6 of 17 3.7.12 Notify Secondary Chemistry that makeup to Spent Fuel Pool from YM is complete. I Person Notified Date Time 3.7.13 Notify Primary Chemistry to sample Spent Fuel Pool for Boron Concentration greater than or equal to minimum boron concentration per COLR.
/
Person Notified Date Time LI 3.7.14 Complete Table 4.4-1 (Pool Makeup Data Record). LI 3.7.15 Place routing stamp in remarks section of cover sheet, check (v) Engineering and fill in Table 4.4-1 only. Unit 1
Enclosure 4.4 OPilfAJ6200/005 Spent Fuel Pool Level Control Page 7 of 17 3.8 Makeup Using Borated Water 3.8.1 Record the following on Table 4.4-1 (Pool Makeup Data Record): El Makeup Water Source El Last SFP Boron sample El Initial Spent Fuel Pool Level El Desired Spent Fuel Pool level 3.8.2 Ensure FWST level greater than 115 in. to prevent draining pool to FWST. 3.8.3 any water level in Refueling Cavity OR Unit 1 in outage, ensure FWST to Refueling Cavity alignment is secured by checking the following Locked Closed:
- 1FW-13 (Unit 1 Refueling Cavity To FW Pump Cont Outside Isol
- 1FW-4 (Unit 1 FWST to Refueling Cavity Cont Outside Isol 3.8.4 FWST in recirc or purification with Unit 1 FW pump, perform the following:
3.8.4.1 Stop #1 FWST Pump. 3.8.4.2 Open 1MXJ-05G (Unit 1 Refueling Water Pump Motor). 3.8.4.3 Ensure closed:
- 1FW-2 (Unit 1 FWST To Refueling Cavity Fill & Drn)
- 1FW-23 (Unit 1 FWST To FW Pump Suction Isol)
El 3.8.4.4 GotoStep3.8.6. 3.8.5 Check the following closed: El 1FW-2 (Unit 1 FWST to Refueling Cavity Fill & Drn) El 1FW-23 (Unit 1 FWST to FW Pump Suction Isol) 3.8.6 Ensure closed:
- 1KF-78 (Unit 1 KF Supply From NB Isol)
- 1KF-80 (Unit 1 KF Supply From NB Isol) 3.8.7 Ensure locked closed:
- 1KF-85 (Unit 1 KF Supply From RN Isol)
- 1KF-86 (Unit 1 KE Supply From RN Isol)
Unit 1
Enclosure 4.4 - -
- OPII/A16200/005 Spent Fuel Pool Level Control Page 8 of 17 3.8.8 Ensure open:
- 1KF-81 (Unit 1 KF Supply From FW Isol)
- 1KF-83 (Unit 1 KF Supply From FW Isol)
- 1FW- 1 A (Refueling Water Loop Isol)
- 1FW-32B (Refueling Water Loop Isol) 3.8.9 HOLD until pooi at desired level.
3.8.10 Close:
- 1 FW- 1 A (Refueling Water Loop Isol)
- 1FW-32B (Refueling Water Loop Isol)
- 1KF-83 (Unit 1 KF Supply From FW Isol)
- 1KF-81 (Unit 1 KF Supply From FW Isol) 3.8.11 FWST was in puri,fication using Unit 1 FWST Pump prior to makeup, perform the following:
3.8.11.1 Open 1FW-23 (Unit 1 FWST To FW Pump Suction Isol). 3.8.11.2 Open the following:
- 1 FW- 1 A (Refueling Water Loop Isol)
- 1FW-32B (Refueling Water Loop Isol) 3.8.11.3 Close 1MXJ-050 (Unit 1 Refueling Water Pump Motor).
3.8.11.4 Start #1 FW Pump. 3.8.11.5 Throttle 1 FW- 19 (Unit 1 FW Pump Disch To KF Prefilter Throttle) to maintain 250 -310 gpm per 1FWPG511O (Unit 1 FW Pump Disch Flow). El 3.8.11.6 Go to Step 3.8.13. Unit 1
Enclosure 4.4 oPi1iiooioo5 - Spent Fuel Pool Level Control Page 9 of 17 3.8.12 FWST was in recirc (NOT in purification) using Unit 1 FWST Pump prior to makeup, perform the following: 3.8.12.1 Open 1FW-23 (Unit 1 FWST To FW Pump Suction Isol). 3.8.12.2 Open the following:
- 1 FW- 1 A (Refueling Water Loop Isol)
- 1FW-32B (Refueling Water Loop Isol) 3.8.12.3 Close 1MXJ-05G (Unit 1 Refueling Water Pump Motor).
3.8.12.4 Start #1 FWPump. 3.8.12.5 Throttle 1FW-66 (Unit 1 FW Pump Disch Throttle) to maintain 250 310 gpm per 1FWPG511O (Unit 1 FW Pump Disch Flow). 0 3.8.13 Complete Table 4.4-1 (Pool Makeup Data Record). 0 3.8.14 Place routing stamp in remarks section of cover sheet, check (v) Engineering and fill in Table 4.4-1 only. Unit 1
Enclosure 4.4
- OP/1/A162001005 Spent Fuel Pool Level Control Page 10 of 17 3.9 Makeup from RN System 3.9.1 Emergency condition requires makeup to Spent Fuel Pool from RN System.
SRO 3.9.2 Record the following on Table 4.4-1 (Pool Makeup Data Record): D Makeup Water Source D Last SFP Boron sample D Initial Spent Fuel Pool Level D Desired Spent Fuel Pool level 3.9.3 Ensure closed:
- 1KF-78 (Unit 1 KF Supply From NB Isol)
- 1KF-80 (Unit 1 KF Supply From NB Isol)
- 1KF-81 (Unit 1 KF Supply From FW Isol)
- 1KF-83 (Unit 1 KF Supply From FW Isol) 3.9.4 jJ 1A RN in operation perform the following:
3.9.4.1 Unlock and open lRN-139 (Assured Fuel Pool Makeup 1A Isol). cv 3.9.4.2 Unlock and open 1KF-86 (Unit 1 KF Supply From RN Isol). 3.9.4.3 AFTER pool at desired level, lock closed:
- 1RN-139 (Assured Fuel Pool Makeup lA Isol)
CV
- 1KF-86 (Unit 1 KF Supply From RN Isol) 3.9.5 j lB RN in operation perform the following:
3.9.5.1 Unlock and open 1RN-239 (Assured Fuel Pool Makeup lB Isol). Cv 3.9.5.2 Unlock and open 1KF-85 (Unit 1 KF Supply From RN Isol). 3.9.5.3 AFTER pool at desired level, lock closed:
- lRN-239 (Assured Fuel Pool Makeup lB Isol)
CV
- 1KF-85 (Unit 1 KF Supply From RN Isol)
Unit 1
Euctosure -oP/1I62ooo Spent Fuel Pool Level Control Page 11 of 17 3.9.6 Notify Chemistry to sample Spent Fuel Pool for Boron Concentration greater than or equal to minimum boron concentration per COLR.
/
Person Notified Date Time LI 3.9.7 Complete Table 4.4-1 (Pool Makeup Data Record). 0 3.9.8 Place routing stamp in remarks section of cover sheet, check () t and fill in Table 4.4-1 only. Engineering NOTE: Copy of this table routed to Engineering. Table 4.4-1. Pool Makeup Data Record LI RMWST OYM Check Makeup Water Source LI .Borated Water RN Last SFP Boron Sample 9 ppm Initial Spent Fuel Pool Level t 5- ft Desired Spent Fuel Pool Level 0 5-Final Spent Fuel Pool Level ft Data Recorded By Date/Time Unit 1
Enclosure 4.4 OPIl/A}6200/0G5 Spent Fuel Pool Level Control Page 12 of 17 3.10 Lowering Pool Level by Draining to FWST or RHT 3.10.1 IF desired, remove Spent Fuel Pool Skimmer Loop from service per Enclosure 4.3 (Spent Fuel Pool Skimmer Loop Operation). CAUTION: Due to Silica concerns, Spent Fuel Pool can only be drained to RHT with Radwaste Chemistry permission. 3.10.2 IF desired to drain to RHT, obtain permission from Radwaste Chemistry. I Person Notified Date Time 3.10.3 Ensure NAC-UMS Cask loading is NOT in progress. 3.10.4 Ensure at least one Spent Fuel Cooling Loop in operation. 3.10.5 Ensure FW System purification alignment secured per OPIl/A162001014 (Refueling Water System). 3.10.6 Ensure KY Purification Loop in service per Enclosure 4.2 (Spent Fuel Pool Purification Loop Operation). 0 3.10.7 Monitor 1KFP5 120 (KF Pool Level). 0 3.10.8 Begin recording level on Table 4.4-2 (Spent Fuel Pool Level Data) once per hour until lowering of SFP level is complete. 3.10.9 Notify Control Room to expect M1D1467 (Ui KY Demin Water Flow) Lo Flow alarm. 3.10.10 Close 1KF-157 (Unit 1 KY Purification Loop Outlet Throttle). 3.10.11 j draining to FWST, open:
- 1KF-76 (Unit 1 KY Purification Loop To FW Isol)
- 1FW-24 (Unit 1 FW Pump Disch To FWST Isol) 3.10.12 !J. draining to A RHT only, perform the following:
3.10.12.1 Unlock and close 1NB-84 (NB System Inlet Hdr Relief To B RHT Isol). 3.10.12.2 Open 1KF-73 (Unit 1 KF Purification Loop To NB Isol). Unit 1
Enclosure 4.4 0P111A162001005 - Spent Fuel Pool Level Control Page 13 of 17 3.10.13 IF draining to B RHT only, perform the following: 3.10.13.1 Unlock and close 1NB-66 (NB System Inlet Hdr Relief To A RHT Isol). 3.10.13.2 Open 1KF-73 (Unit 1 KF Purification Loop To NB Isol). 3.10.14 Unlock and throttle 1KF-71 (Unit 1 KF Purification Loop To FW/NB/WL Isol) to desired flow (300 gpm maximum through purification). 3.10.15 AFTER desired level obtained, perform the following: 3.10.15.1 draining to FWST, perform the following: A. Lock 1KF-71 (Unit 1 KF Purification Loop To FW/NB/WL Isol) closed. B. Close 1KF-76 (Unit 1 KF Purification Loop To FW Isol). C. Close 1FW-24 (Unit 1 FW Pump Disch To FWST Isol). 3.10.15.2 IF draining to A RHT, perform the following: A. Lock 1KF-71 (Unit 1 KF Purification Loop To FW/NB/WL Isol) closed. B. Close 1KF-73 (Unit 1 KF Purification Loop To NB Isol). C. Lock 1NB-84 (NB System Inlet Hdr Relief To B RHT Isol) open. 3.10.15.3 j draining to B RHT, perform the following: A. Lock 1KF-71 (Unit 1 KF Purification Loop To FW/NB/WL Isol) closed. B. Close 1KF-73 (Unit 1 KF Purification Loop To NB Isol). C. Lock 1NB-66 (NB System Inlet Hdr Relief To A RHT Isol) open. Unit 1
Enclosure 4.4 OP/1/A162001005 Spent Fuel Pool Level Control Page 14 of 17 3.10.16 Perform one of the following:
- IF desired to place Spent Fuel Purification Loop in service, throttle 1KF-157 (Unit 1 KF Purification Loop Outlet Throttle) to 220 310 gpm (Preferred band 290 310 gpm).
OR
- IF desired to remove Spent Fuel Purification Loop from service, perform Enclosure 4.2 (Spent Fuel Pool Purification Loop Operation).
3.10.17 IF desired, place Spent Fuel Pool Skimmer Loop in service per Enclosure 4.3 (Spent Fuel Pool Skimmer Loop Operation). 3.11 Lowering Pool Level by Draining to WEFT 3.11.1 Notify Maintenance SPOC that drains from Spent Fuel Pool to WEFT will be open and to evaluate any work being performed for potential hydrogen build up. {PIPM-05-1055}
/
Person Notified Date Time 3.11.2 j[ desired, remove Spent Fuel Pool Skimmer Loop from service per Enclosure 4.3 (Spent Fuel Pool Skimmer Loop Operation). 3.11.3 Ensure NAC-UMS Cask loading is NOT in progress. 3.11.4 Ensure at least one Spent Fuel Cooling Loop in operation. 3.11.5 Ensure KF Purification Loop in service per Enclosure 4.2 (Spent Fuel Pool Purification Loop Operation). 3.11.6 Check the following closed: El 1KF-73 (Unit 1 KF Purification Loop Dm To NB Isol) El 1KF-75 (Unit 1 KF Purification Loop Dm To WL Isol) El 1KF-76 (Unit 1 KF Purification Loop Drn To FW Isol) El 1KF-114 (Unit 1 KF Cask Area Isol) LI 1KF-115 (Unit 1 KF Cask Area Isol) LI 3.11.7 Monitor IKFP512O (KF Pool Level). LI 3.11.8 Begin recording level on Table 4.4-2 (Spent Fuel Pool Level Data) once per hour until lowering of SFP level is complete. Unit 1
Enclosure 4.4 OP/1-!A!6200/005 Spent Fuel Pool Level Control Page 15 of 17 3.11.9 Add item to SRO Turnover Sheet that SFP level is being lowered by draining SRO to WEFT and Radwaste Chemistry has Operational Control of 1KF-75 (Unit 1 KF Purification Loop Drn To WL Isol). D 3.11.10 Record KF purification loop flow from 1KFP5 180 (Unit 1 KF Postfilter Outlet Flow): gpm. 3.11.11 Notify Control Room to expect Ml Dl 467 (Ui KF Demin Water Flow)
??Lo Flow?! alarm 3.11.12 Throttle 1KF-157 (Unit 1 KF Purification Loop Outlet Throttle) to decrease KF purification loop flow by 30 gpm. (As indicated on 1KFP5 180 (Unit 1 KF Postfilter Outlet Flow))
3.11.13 Unlock and open 1 KF-7 1 (Unit 1 KF Purification Loop To FW/NB/WL Is 01). NOTE: The following step will initiate flow to the WEFT. 3.11.14 Throttle 1KF-75 (Unit 1 KF Purification Loop Drn To WL Isol) to increase RWC 0P5 KF purification ioop flow by 30 gpm. (To value recorded in Step 3.11.10.) 0 3.11.15 Notify Radwaste Chemistry to perform the following: 0 3.11.15.1 Inform Unit 1 Control Room when 1KF-75 (Unit 1 KF Purification Loop Drn To WL Isol) is operated. 0 3.11.15.2 Maintain WEFT level as desired by operating 1 KF-75 (Unit 1 KF Purification Loop Drn To WL Isol).
/
Person Notified Date Time 3.11.16 AFTER 1KFP512O (KF Pool Level) is +1 above zero, notify Radwaste Chemistry to close 1KF-75 (Unit 1 KF Purification Loop Drn To WL Isol).
/
Person Notified Date Time 3.11.17 Ensure 1 KF-75 (Unit 1 KF Purification Loop Drn To WL Isol) closed. ops 0 3.11.18 Record final Spent Fuel Pool level: ft. Unit 1
Enclosure 4.4
- OW1/AI620OI0o5 Spent Fuel Pool Level Control Page 16 of 17 3.11.19 Throttle 1KF-157 (Unit 1 KF Purification Loop Outlet Throttle) to 220-310 gpm. (Preferred band 290 -310 gpm) 3.11.20 IF desired, place Spent Fuel Pool Skimmer Loop in service per Enclosure 4.3 (Spent Fuel Pool Skimmer Loop Operation).
3.11.21 Remove item from SRO Turnover Sheet that SFP level is being lowered by SRO draining to WEFT and Radwaste Chemistry has Operational Control of 1KF-75 (Unit 1 KF Purification Loop Dm To WL Isol). Unit 1
Enclosure 4.4 Spent Fuel Pool Level Control Page 17 of 17 Table 4.4-2. Spent Fuel Pool Level Data Date / Time [ Level ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft End of Enclosure Unit 1
ES-301 Administrative Topics Outline Form ES-301-l DRAFT (Rev 041311) Facility: McGuire Date of Examination: 6/27/1 1 Examination Level: SRO Operating Test Number: Nil-i Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.7 (4.7) Ability to evaluate plant performance and Conduct of Operations make operational judgments based on operating characteristics, reactor behavior, M, R and instrument interpretation. JPM: Calculate QPTR 2.1.25 (4.2) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc. M,R JPM: Calculate Reactor Vessel Head Venting Time 2.2.18 (3.9) Knowledge of the process for managing Equipment Control maintenance activities during shutdown operations, such as risk assessments, work M, R prioritization, etc. JPM: Perform a Thermal Margin Determination 2.3.4 (3.7) Knowledge of radiation exposure under Radiation Control normal or emergency conditions. D, R JPM: Take On-Site Protective Actions During a General Emergency 2.4.41 (4.6) Knowledge of emergency action level Emergency thresholds and classifications. Procedures/Plan M, R JPM: Classify an Emergency Event NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5)
(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1) (N)ew or (M)odifled from bank ( 1) (4) (P)revious 2 exams ( 1; randomly selected) (0) NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (Rev_041311) SRO Admin JPM Summary Ala This is a modified JPM using bank JPM ADM-NRC-Al -004 as its basis. With the plant at 99% power, the operator will be told that the Unit 1 OAC failed and is not operating, and that the crew has implemented PT/i/A14600/021A (Loss of Operator Aid Computer while in Mode I). The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PTI1IAI4600I21A. The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4 (Quadrant Power Tilt Ratio) has been exceeded, and identify any required Technical Specification ACTION. Aib This is a modified JPM using Bank JPM-ADM-NRC-A1-018 as its basis. The operator will be told that McGuire Unit 1 is in a Post-Accident situation, that they are available for assignment within the Operational Support Center (OSC), and given a set of NC System and Containment conditions, along with a copy of EP/i/A/5000/FR-l.l (Response to Voids in Reactor Vessel). The operator will be directed to calculate maximum head venting time in accordance with Enclosure 1 of FR-i .3, and be required to calculate this time within an allowable band. A2 This is a modified JPM using Bank JPM5 ADM-NRC-A2-06 as its basis. The operator will be told that Unit 1 was shutdown 24 days ago for a mid-cycle outage after 200 days of operation, that Unit 1 is currently in Mode 5 with the NC system is 145 F and A Train ND in service; and that preparations are being made to lower NC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/i IAI6100ISD-20 (Draining the NC System). The operator will be directed to complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 9 inches above Hot Leg Centerline and make the appropriate notifications. The operator will be expected to complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) with a new thermal margin calculated and documented on Attachment 12.7 (Shutdown Assessment Status) and on MC-6, as well as make the required notifications to the CCC and STA. A3 This is a Bank JPM. The operator will be told that a General Emergency has been declared and that, as the OSM, they have initiated and completed the immediate actions of Enclosure 4.1 of RP/0/A15700/004 (General Emergency). Additionally, the operator will be told that On-Site Protective Actions are being considered in accordance with RP/0/A/5700/004, and that there are reports of an injured non-ambulatory person on-site. The operator will be required to select two rescuers, from among seven potential rescuers, and dispatch them to the injured individual by completing Enclosure 4.4, (Request for Emergency Exposure), of RP/0/A/5700/004. A4 This is a modified form of a Bank JPM. The operator will be given a timeline of events that span a few hours, and asked to classify the event at the point where NUREG-1 021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (Rev_041311) each of two procedures identifies a need to address RPIOIAI5700I000, Classification of Emergency. The operator will be expected to recognize that an Unusual Event is declared at the first procedure direction, and that a Site Area Emergency exists upon entry into the EOP network. NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Woheet JPM Ala SRO 2011 Admin JPM Ala SRO (Rev_041111)
- NUREG 1021, Revision 9
Appendix C Page 2 of 13 Form ES-C-i Job Performance Measure Worksheet - Facility: McGuire Task No.: Task
Title:
Calculate QPTR JPM No.: 2011 Admin JPM Al a SRO K/A
Reference:
GK/A 2.1.7 (4.4/4.7) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant 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:
- The Unit I OAC failed and is not operating.
- The vendor is being consulted concerning repairs.
- It is estimated it will take approximately 15 hours to complete repairs.
- The crew has implemented PT/1/A/4600/021A (Loss of Operator Aid Computer while in Mode 1) and completed through step 12.13.
- Unit I is at 99% power and all Power Range Instruments are OPERABLE.
Task Standard: The operator will calculate the QPTR (See Attached Key) and determine that the QPTR Technical Specification has been exceeded; Then identify the required TS ACTION (i.e. Power must be reduced to at least 94%, and ACTIONS a.2 through A.7 must be taken). Required Materials: Calculator McGuire Technical Specifications General
References:
PT/1/A14600/021A (Loss of Operator Aid Computer while in Mode 1), Rev 36 OP/1/A/6100/022 (MNS Unit #1 Data Book) McGuire Technical Specifications (LCO 3.2.4/Amendment 184/166) 2011 Admin-JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 3 of 13 Form ES-C-i JobPefformance MeasurE Worksheet Handouts: PT/i /A/4600/021A (Loss of Operator Aid Computer while in Mode 1) marked up through step 12.13. Detector Currents (Page 12 of 13 of this JPM) OPI1!A/61001022 (MNS Unit #1 Data Book), Enclosure 4.3, Table 2.2 (Excore Currents and Voltages Correlated to 100% Full Power at Various Axial Offsets) McGuire Technical Specifications (Available) Initiating Cue: The CRS has directed you to calculate QPTR in accordance with Step 12.14 of PT/i JA/4600/21A (Loss of Operator Aid Computer while in Mode 1), and identify any applicable Technical Specification required ACTION. Time Critical Task: NO Validation Time: 25 minutes 2011 Admin-JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 4 of 13 Form ES-C-i
. PERFORMANCE [NFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), the Detector Currents (2 to last Page of this JPM), handout PTIIIAI4600IO2IA marked up through step 12.13, and MNS Unit I Data Book Table 2.2 (Cycle 21). START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Step 12.14) The operator determines from initial conditions QPTR IF QPTR Alarm inoperable Alarm is inoperable, Unit I AND greater than 50% is at 100% power and all RTP, perform the following: PR channels are operable. (Step 12.14.1) If all Power Range (PR) Operator proceeds to channel inputs to QPTR Enclosure 13.5 (Calculation operable, calculate QPTR Sheet for Quadrant Power on Enclosurel3.5 Tilt) Part A. (Calculation Sheet for Quadrant Power Tilt) Part A within 12 hours and every 12 hours thereafter until QPTR Alarm operable. 2 (Enclosure 13.5 Part A) The operator enters the current Date and Time at Complete the Form the top of the form. 2011 Admin-JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 5 of 13 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*3 (Enclosure 13.5 Part A) The operator records the Measured Current From- correct amperage reading NI cabinets current meter for each detector (From the (located on respective PRB Handout provided) in the Drawers). Ensure Detector Measured Current row for Milliamp Range Switches each of the eight (8) are in 0.5 position and detectors as follows:
read 0-500 microamp scale. PR-41A = 295 PR-41B = 304 PR-42A = 299 PR-.42B = 327 PR-43A = 299 PR-43B 315 PR-44A = 285 PR-44B = 304
*4 (Enclosure 13.5 Part A) The operator locates Calibration Current From
- OP/1/A16100/022, most recent calibration data Enclosure 4.3, Table 2.2, using 0 Incore Axial Offset Excore Currents and Current in Data Book, Table Voltages Correlated to 2.2 (IT for detector A, 100% Full Power at Various IB for detector B). Axial Offsets.
The operator records the correct amperage reading for each detector (Table 2.2) in the Calibration Current row for each of the eight (8) detectors as follows: PR-41A = 142.0 PR-41B = 155.3 PR-42A = 150.0 PR-42B = 160.3 PR-43A = 145.0 PR-43B = 162.4 PR-44A= 137.5 PR-44B = 158.1 2011 Admin-JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 6 of 13 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*5 (Enclosure 13.5 Part A) The operator correctly Relative Flux (RF) Divide calculates the average RF line I by line 2 to calculate and records the in the Relative Flux (RF) for each Relative Flux (RF) row for upper (A) and lower (B) each of the eight (8) detector. detectors as follows:
PR-41A = 295/1 42.0 = 2.08 PR-41B = 304/1 55.3 = 1.96 PR-42A = 299/1 50.0 = 1.99 PR-42B = 327/1 60.3 = 2.04 PR-43A 299/1 45.0 = 2.06 PR-43B = 315/162.4 = 1.94 PR-44A = 285/1 37.5 = 2.07 PR-44B = 304/1 58.1 = 1.92
*6 (Enclosure 13.5 Part A) The operator records the Quadrant Power Tilts: RF of each of the four (4) A Calculate by dividing each detectors and calculates the upper relative flux by the Avg RF of A Detectors as average upper relative flux follows:
and dividing each lower (2.08+1.99+2.06+2.07)14 = relative flux by the average LV lower relative flux. Avg RF of A Detectors
*7 (Enclosure 13.5 Part A) The operator records the Quadrant Power Tilts: RF of each of the four (4) B Calculate by dividing each detectors and calculates the upper relative flux by the Avg RF of B Detectors as average upper relative flux follows:
and dividing each lower relative flux by the average (1 .96+2.04+1 .94+1 .92)14 = lower relative flux. 1.97 Avg RF of B Detectors 2011 Admin-JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 7 of 13 Form ES-C-i PERFORMANCE INFORMAT1OI\f STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*8 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-4iA Tilt as follows:
Calculate by dividing each upper relative flux by the 0812 05 1 01 + average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-4iA Tilt
*9 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-41 B Tilt as follows:
Calculate by dividing each upper relative flux by the 97 0 + average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-41 B Tilt
*10 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-42A Tilt as follows:
Calculate by dividing each + upper relative flux by the . average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-42A Tilt
*11 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-42B Tilt as follows:
Calculate by dividing each upper relative flux by the 2 04I1 97 04 + 01 average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-42B Tilt 2011 Admin JPM Al a SRO
- NUREG 1021, Revision 9
Appendix C Page 8 of 13 Form ES-C-i PERFORFVTANCEINFORMAT[ON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*12 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-43A Tilt as follows:
Calculate by dividing each upper relative flux by the 2 0612 05 1 00 + 01 average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-43A Tilt
*13 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-43B Tilt as follows:
Calculate by dividing each + upper relative flux by the . average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-43B Tilt
*14 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-44A Tilt as follows:
Calculate by dividing each 0712 + upper relative flux by the average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-44A Tilt
*15 (Enclosure 13.5 Part A) The operator calculates the Quadrant Power Tilts: PR-44B Tilt as follows:
Calculate by dividing each upper relative flux by the 92I1 97 0 97 + average upper relative flux And records this value. and dividing each lower relative flux by the average lower relative flux. PR-44B Tilt 2011 Admin JPM Ala SRO
- NUREG 1021, Revision 9
Appendix C Page 9 of 13 Form ES-C-i PERFORMANCE INFORMATION - STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*16 (Technical Specification The operator determines 3.2.4) The QPTR shall be that a quadrant is >1.02 and
< 1.02.
refers to LCO 3.2.4. The operator determines that power must be reduced (ACTION Al) to at least 94% (Highest QPTR is 1.04 on PR-42B; Reduce 3% from RTP (100%) for each 1% of QPTR> 1.02 (1.04-102
= 002 x 3% RTP xl 00%
QPTR]RTP)). The operator determines that ACTION A.2, A.3, A.4, A.5, A.6 and A.7 must be completed within the required COMPLETION TIME. Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2011 Admin JPM Ala SRO
- NUREG 1021, Revision 9
Appendix C Page 10 of 13 Form ES-C-i
- VERIFICATION OF COMPLETION -
Job Performance Measure No.: 2011 Admin JPM Ala SRO Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin-JPMAIaSRO NUREG 1021, Revision 9
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Appendix C Form ES-C-i
. JPM CUE SHEET The following Detector Currents are observed on the NI cabinet current meters:
N 1-41 detector: A (left) 295 B (right) 304 NI-42 detector: A (left) 299 B (right) 327 NI-43 detector: A (left) 299 B(right) 315 N 1-44 detector: A (left) 285 B (right) 304 NUREG 1021, Revision 9
Appendix C Form ES-C-i
- JPM CUE SHEET Initial Conditions:
- The Unit 1 OAC failed and is not operating.
- The vendor is being consulted concerning repairs.
- It is estimated it will take approximately 15 hours to complete repairs.
- The crew has implemented PTIIIAI4600IO21A (Loss of Operator Aid Computer while in Mode 1) and completed through step 12.13.
- Unit 1 is at 99% power and all Power Range Instruments are OPERABLE.
INITIATING CUE: The CRS has directed you to calculate QPTR in accordance with Step 12.14 of PTI1IAI4600I2IA (Loss of Operator Aid Computer while in Mode 1), and identify any applicable Technical Specification required ACTION. NUREG 1021, Revision 9
UNIT I OPI1/A161001022 ENCLOSURE 4.3 TABLE 2.2 Excore Currents and Voltages Correlated to 100% Full Power at Various Axial Offsets Unit 1 Cycle 21 Full Power Detector Currents (MrnAtm,Q Cnrrpcnnrn1inc To Various Incore Axial Offsets Detector N4 I Detector N42 Detector N43 Detector N44 Incore Axial Offset T B T B T B T B 30 175.2 118.5 185.2 123.3 177.2 124.1 169.8 119.7 20 164.2 130.7 173.4 135.7 166.5 136.9 159.0 132.6 10 153.1 143.0 161.7 147.9 155.7 149.6 148.3 145.3 0 142.0 155.3 150.0 160.3 145.0 162.4 137.5 158.1
-10 130.9 167.5 138.3 172.5 134.3 175.1 126.7 171.0
-20 119.9 179.8 126.5 184.9 123.6 187.9 116.0 183.8
-30 108.7 192.1 114.8 197.1 112.8 200.6 105.1 196.5 Correlation Coef 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Normalized Detector Voltages (Volts) At Various Axial Offsets Detector N4 1 Detector N42 Detector N43 Detector N44 Incore Axial Offset T B T-B T B T-B T B T-B T B I-B 30 10.280 6.357 3.923 10.285 6.413 3.872 10.178 6.366 3.812 10.288 6.307 3.981 20 9.630 7.014 2.616 9.633 7.052 2.581 9.562 7.020 2.542 9.636 6.981 2.655 10 8.980 7.672 1.308 8.982 7.691 1.291 8.946 7.675 1.271 8.983 7.656 1.327 0 8.330 8.330 0.000 8.330 8.330 0.000 8.330 8.330 0.000 8.330 8.330 0.000
-10 7.680 8.988 -1.308 7.678 8.969 -1.291 7.714 8.985 -1.271 7.677 9.004 -1.327
-20 7.030 9.646 -2.616 7.027 9.608 -2.581 7.098 9.640 -2.542 7.024 9.679 -2.655
-30 6.380 10.303 -3.923 6.375 10.247 -3.872 6.482 10.294 -3.812 6.372 10.353 -3.981 AFD Incore/Excore Ratios For Quadrants 1 - 4 Quad 4 Quad 2 Quad 1 Quad 3 N41 N42 N43 N44 M= 1.274 1.291 1.311 1.255 UNIT I
UNIT I Detector N41 Detector N42 - Detector N43 Detector N44 Incore Axial Offset T B T B T B T B 30 198.2 134.0 205.6 136.9 198.2 138.8 189.3 133.5 20 185.7 147.9 192.5 150.6 186.2 153.1 177.3 147.8 10 173.2 161.8 179.5 164.2 174.2 167.3 165.3 162.0 0 160.6 175.7 166.5 177.9 162.2 181.6 153.3 176.3
-10 148.1 189.5 153.5 191.5 150.2 195.9 141.3 190.6 -20 135.6 203.4 140.4 205.2 138.2 210.2 129.3 204.9 -30 123.0 217.3 127.4 218.8 126.2 224.4 117.2 219.1 UNIT I
Duke Energy Procedure No. McGuire Nuclear Station PTIl/A14600/o21 A Loss Of Operator Aid Computer While In Mode 1 Revision No. 036 Electronic Reference No. MC00483T Continuous Use PERFORMANCE UNCONTROLLED FORPRINT * * * * * * * * * * (ISSUED) PDF Format
PT/1/A/4600/021 A Page 2 of 22 Revision History (significant issues, limited to one page) Rev 036 Revised steps pertaining to performance of Daily and Semi-Daily Surveillances to reflect different schedule times for those procedures. Ends. 13.2, 13.3, 13.4, 13.5 & 13.10: Added SRO Review column and footnote to enclosures per PIP M-08-04917, CA# 3. CA# 3 states Revise all Operations procedures that are used to document conditional surveillances multiple times, to ensure a review of the completed surveillance is performed by the SRO prior to updating the conditional surveillance in TSAIL.. Rev 035 Enclosure 13.5, added to NOTE on page 1 that IP/0/A/3207/003 K (NIS Power Range N41 / N42 / N43 and N44 Drawer Calibration) could also be used to provide required data. Rev 034 Added Conditional Statement for action(s) to take if procedure entered due to OAC QPTR Monitor inoperability as a result of Power Range Current Calibration activities by IAE. Revision allows Operator to perform only Enclosure 13.5 for Manual Calculation of QPTR. Revised Section for determination of Lake Level, incorporating necessary changes to support EC-98743 (MD-101869): Remove Auto-Open function from 1CA-161C and 1CA-l62C. As a result, SLC 16.9.7 revised to require Lake Level greater than 746 feet for SSF operability. Rev 033 -Replaced the term APD Inspector with PT Data in Step 12.17.2.2.
-Deleted existing Step 12.16.2.4, Ensure Total NC Loop Flow is logged in TSAIL as a Conditional Surveillance until returned to normal surveillance period with OAC operable. and added step to use a timer.
-Deleted existing Step 12.17.2.5, Ensure Power Range / Heat Balance (Thermal Power) logged in TSAIL as a Conditional Surveillance until returned to normal surveillance period with OAC operable. and added step to use a timer.
-Made Steps 12.16 and 1.17 conditional so if the Semi-Daily PT or Daily PT was already performed prior to loss of OAC, it is not required at this time.
-Step 12.18.7 deleted because cannot trend lake level if the OAC is down.
Rev 032 Section 12.18, changed responses to Lo Level (750.5) and Lo Lo Level (750) lake levels if Unit 1 OAC not available. Rev 031 Added check for lake level determination for situation where Ml A0766 is unavailable. Rev 030 Added checks to sections for evaluation of Acceptance Criteria and notifications if Acceptance Criteria NOT met per PIP M-07-00393. Unit 1
PT!1/A!4600/021 A Page 3 of 22 Loss Of Operator Aid Computer While In Mode 1
- 1. Purpose To document Tech Spec requirements in the event the Operator Aid Computer (OAC) is out of service (completely or partially) while in Mode 1.
- 2. References 2.1 Tech Specs:
- ITS SR 3.1.4.1 (Rod Group Alignment Limits)
- ITS SR 3.1.6.2 (Control Bank Insertion Limits)
- ITS SR 3.2.3.1 (AFD)
- ITS SR 3.2.4.1 (QPTR)
- ITS SR 3.4.1.3 (NC Loop Flow)
- ITS 3.4.15 (NC System Leakage Detection Instrumentation)
- ITS SR 3.6.5.1 (VU Containment Air Temperature)
- ITS SR 3.6.5.2 (VL Containment Air Temperature) 2.2 Core Operating Limits Report (COLR) 2.3 MC-1341-02.00 (Intake Structure Elevation)
- 3. Time Required 3.1 One Operator until OAC restored to service every time OAC out of service (completely or partially).
- 4. Prerequisite Tests None
- 5. Equipment Required 5.1 Instrument capable of converting RTD resistance reading to temperature reading (Platinum 100 ohm).
5.2 Calibrated digital thermometer, capable of reading ambient air temperatures (Examples: Tegan 871, Keithley 871 or comparable instrument). Limits and Precautions An evaluation should be made to determine if information is available elsewhere and effects of operation without this information for any Annunciator or recorder out of service for which OAC was being used as a substitute monitor. Unit 1
PT/1/A/4600/021 A Page4of22 Unit Status Unit 1 in Model. Prerequisite System Conditions Unit 1 OAC out of service (completely or partially).
- 9. Test Method Control Room Operator shall ensure all items listed in attached enclosures are checked while OAC out of service (completely or partially).
- 10. Data Required 10.1 CompletedEnclosures 13.1-13.6, 13.8, 13.9, 13.10 as required.
- 11. Acceptance Criteria 11.1 IF any Unit 1 MWH OAC Point out of service, Enclosure 13.1 (Hourly Dispatcher Report) performed with all MWH readings recorded.
11.2 IF greater than or equal to 50% RTP, Axial Flux Difference (AFD) monitored as follows: 11.2.1 AFD recorded per Enclosure 13.2 (Axial Flux Difference Monitoring) Part A (Using Control Board AFD Meters) within 1 hour and every hour thereafter until OAC AFD Monitor Alarm operable. 11.2.2 IF Main Control Board (MCB) AFD gauges inoperable, Enclosure 13.2 (Axial Flux Difference Monitoring) Part B (Manual AFD Calculations) performed within 1 hour and every hour thereafter until OAC AFD Monitor Alarm or MCB AFD gauges operable. 11.3 For Control Rod Position:
- All full length rods (individual rod positions) have been checked within 4 hours and every 4 hours thereafter to be within 12 steps (indicated position) of their group demand position and operable.
- IF Annunciator 1AD-2, B9 (Control Rod Bank Lo-Lo Limit) out of service, each Control Bank has been checked within 4 hours and every 4 hours thereafter to be above rod insertion limits as specified in COLR.
Unit 1
PT/1/A/4600/021 A Page 5 of 22 NOTE: Containment lower compartment temperature may be between 120 125°F for up to 90 cumulative days per calendar year provided lower compartment temperature average over previous 365 days is less than 120°F. Within this 90 cumulative day period, lower compartment temperature may be between 125 13 5°F for 72 cumulative hours. 11.4 Containment air temperatures have been checked once per hour after OAC has been out of service for 4 hours. Tech Spec containment average air temperature shall be 75 100°F for containment upper compartment and 100 120°F for containment lower compartment (See NOTE). 11.5 IF a Containment fire watch in effect AND containment air temperatures are being used to satisfy requirements, temperatures have been checked once per hour. (SLC 16.9.6) 11.6 WHEN above 50% RTP, Enclosure 13.5 (Calculation Sheet For Quadrant Power Tilt) has been calculated once within 12 hours and every 12 hours thereafter and Quadrant Power Tilt Ratio (QPTR) checked less than or equal to 1.02. 11.7 IF outside temperature less than 32°F, within 2 hours FWST Level Instrument Room heaters are checked energized and every 12 hours temperature checked greater than 40°F. 11.8 Required data recorded in PT/1/A/4200!040 (Reactor Coolant Leakage Detection) to determine if reactor coolant leakage into Reactor Building has increased. 11.9 CA Storage Tank temperature 32 138°F.
- 12. Procedure NOTE: A magenta OAC point indicates 11 Failed or Bad Quality. Some of these also indicate a partial loss of OAC.
Turn On Code GD OAC may be used to find OAC points in Enclosure 13.7 (OAC Point List For Partial Loss Of OAC). j this procedure entered due to OAC QPTR Monitor inoperability as a result of Power Range Current Calibration activities by LkE AND manual calculation of QPTR required prior to returning OAC Monitor to service, perform the following: 12.1.1 Perform Enclosure 13.5 (Calculation Sheet For Quadrant Power Tilt) only. 12.1.2 Exit this procedure. Unit 1
PT/1/A!4600/021 A I Page6of22 IF this procedure is entered due to a Failed OR Bad Quality OAC point, go to L Enclosure 13.7 (OAC Point List For Partial Loss Of OAC) to determine applicable sections of procedure to perform. All other sections of procedure may be marked NA. 3 Noti Eng OAC Group that OAC is out of service (completely or partially) and needs to be returned to service as soon as possible. h 0
) f\J) Lt_
Person Notified Date Time Noti RP Shift that OAC is out of service and PT Data collection is unavailable. Person Noied Date Time (pTj 3 OAC alarm responses associated with Unit 1 and Unit 2 buslines and bus voltages are ,/ only available on Unit 1 OAC. Nof TCC of the following: {PIP 04-2818} 12.5. Unit 1 OAC is out of service and the following OAC points will NOT alarm: M1P2835 (lB 230 KV Busline In Service Only) M1P2836 (1A 230 KV Busline In Service Only) M1E0835 (230 KV Y Bus Volts) M1E0850 (230 KV R Bus Volts) M1P2837 (2B 525 KV Busline In Service Only) M1P2838 (2A 525 KV Busline In Service Only) M1E0905 (525 KV Y Bus Volts) 72M1E0921 (525 KV R Bus Volts) McGuire Control Room is unable to monitor grid conditions for either Unit. Have TCC monitor RTCA (Real Time Contingency Analysis) for both Units and advise Control Room if either switchyard voltage would NOT be adequate should affected unit trip. ht1 Person Ntified Date Time Unit 1
PT/1/Af4600/021 A Page 7 of 22 IF TCC advises that Unit 1 switchyard voltage would NOT be adequate should Unit 1 trip, go to AP/1/A/5500/005 (Generator Voltage and Electric Grid Disturbances). IF TCC advises that Unit 2 switchyard voltage would NOT be adequate should Unit 2 trip, go to AP/2/A15500/005 (Generator Voltage and Electric Grid Disturbances). 12.6 Perform the following: 1 . . Enter the following in TSAIL for tracking increased surveillance frequency:
- Rod Position Deviation Monitor (ITS SR 3.1.4.1)
AFD Monitor Alarm (ITS SR 3.2.3.1)
)QPTR Alarm (ITS SR 3.2.4.1)
IF Annunciator 1AD-2, B9 (Control Rod Bank Lo-Lo Limit) unavailable, enter Rod Insertion Limit Monitor (ITS SR 3.1.6.2) in TSAIL for tracking increased surveillance frequency. 2.7 Reduce turbine generator load as required to maintain indicated Reactor Power level less than 100% as indicated on NI Power Range Meters. {PIP-l-M99-0578} Record Unit 1 Electrical Surveillance Items as follows: Check the following Unit 1 MWH OAC Points by entering Turn-on Code GD MWH: M1P1 103 (Unit 1 Gross MWH Counter) M1P1 109 (1A D/G Compensated MWH Hours) M1P1 111 (lB D/G Compensated MWH Hours) M1P1 104 (1ATA Auxiliary MWH Counter) M1P1 105 (1ATB Auxiliary MWH Counter) 1P0407 (Ui Net MWH) 2.8. IF all Unit 1 MWH OAC Points in service AND M1L12O1 (Ui SOC External Gateway Link Status) in service, go to Step 12.9. Unit 1
PTJ1/A74600/021 A Page 8 of 22 NOTE: Unit 2 OAC in service, Unit 1 MWH data is available on Unit 2 Switchboard Log. System Operating Center (SOC) can be contacted using old Dispatcher Red Phone or 704-3 82-4413. 12.8.3 IF all Unit 1 MWH OAC Points in service AND M1L12O1 (Ui SOC External ( Gateway Link Status) out of service, perform the following: 12.8.3.1 Unit 2 OAC Point M2L1201 (U2 SOC External Gateway Link Status) in service, notify SOC that Unit 1 MWH data must be obtained via Unit 2 OAC Switchboard Log.
/
Person Notified Date Time 12.8.3.2 j[ Unit 2 OAC Point M2L1201 (U2 SOC External Gateway Link Status) out of service, perform the following: A. Notify SOC that Unit 1 MWH data unavailable.
/
Person Notified Date Time B. IF Unit 2 OAC Switchboard Log unavailable, record Unit 1 MWH readings on Enclosure 13.1 (Hourly Dispatcher Report) every hour on the hour using Digital Counters located in Control Room behind control board. C. AFTER Enclosure 13.1 (Hourly Dispatcher Report) completed, place routing stamp in remarks section of cover sheet and check (V) Other and fill in Ops Test Group t (MGO1OP) (Enclosure 13.1 only). Unit 1
PTTI/A/4600/021 A Page 9 of 22 12.8 jj any Unit 1 MWH OAC Point out of service, perform the following: Noti Soc that Unit 1 MWH data unavailable. Person Notified Date Time D4.2 Record Unit 1 MWH readings on Enclosure 13.1 (Hourly Dispatcher Report) every hour on the hour using Digital Counters located in Control Room behind control board. 12.8.4. AFTER Enclosure 13.1 (Hourly Dispatcher Report) completed, place routing stamp in remarks section of cover sheet and check (V) Other and fill in Ops Test Group (MGO lOP) (Enclosure 13.1 only) t OAC will be out of service for greater than 48 hours, perform Manual Trigger of Analog Fault Recorder as follows: 12.9.1 WHEN OAC has been out of service for 48 hours, notify System Engineering.
/
Person Notified Date Time 12.9.2 Depress Manual Trigger on Analog Fault Recorder (located on EB7) every hour until OAC is returned to service. 0 12.9.3 Record manual trigger of Analog Fault Recorder on Enclosure 13.9 (Manual Trigger of Analog Fault Recorder) every hour. 2.10 IF AFD Monitor Alarm inoperable AND greater than or equal to 50% RTP, perform the following: IF MCB AFD gauges operable, record AFD within 1 hour and every hour thereafter on Enclosure 13.2 (Axial Flux Difference Monitoring) Part A until OAC AFD Monitor Alarm operable. MCB AFD gauges inoperable, perform the following: 0 12.10.2.1 Check AFD by performing Enclosure 13.2 (Axial Flux Difference Monitoring) Part B within 1 hour and every hour thereafter until OAC AFD Monitor Alarm or MCB AFD gauges operable. 12.10.2.2 IF MCB AFD gauges restored operable AND AFD Monitor Alarm remains inoperable, perform Step 12.10.1. Unit 1
PT/1/A/4600/021 A Page 10 of22 Control Rods, perform the following:
- 12. 1 Record within 4 hours and every 4 hours thereafter that the position of each full length rod to be within 12 steps of its group demand position and operable on Enclosure 13.3 (Full Length Rod Verification Data) Part A.
IF munciator 1AD-2, B9 (Control Rod Bank Lo-Lo Limit) unavailable, record within 4 hours and every 4 hours thereafter that each Control Bank of rods are above Rod Insertion Limit on Enclosure 13.3 (Full Length Rod Verification Data) Part B. 12.12 IF a Containment Fire watch in affect OAC has been out of service for greater than f,éhours, perform the following for Containment Air Temperatures: Write an El Work Request for IAE to obtain Containment Air Temperature readings. Noti E to perform the following: Person Notified Date Time Obtain applicable E procedure to record opening of terminal links. l2.2 Obtain an instrument capable of converting RTD resistance readings (Platinum 100 ohm) to temperature readings.
.12.2. Using Table 12.11-1 (Containment Air Temperatures), obtain temperature readings.
D 1 .12.3 ecord temperature readings obtained per Table 12.11-1 (Containment Air Temperatures) on Enclosure 13.4 (Containment Air Temperatures) every hour. Unit 1
PT/1/A14600/021 A Page 11 of22 NOTE: nstrument connection can be made to computer cabinet 1AT5, Terminal Block Location Ri (See MC-1790-17.01 for terminal location.) or to applicable terminals in computer room, as desired. Terminals used for instrument connections are required to have open terminal links. 7 using a Fluke 743, set it to read RTD (Pt 100 (3916)) and 3 wire hook up. Table 12.11-1 Containment Air Temperatures Ventilation 1AT5 Terminals Serial Number Analog Number Unit TB1 (Ri) VU 1A 13, 14, 15 M1AVUOO1 M1A1204 VU lB 16, 17, 18 M1AVUOO3 M1A121O VU1C 19,20,21 M1AVUOO5 M1A1216 VU 1D 22, 23, 24 M1AVUOO7 M1A1222 VL1A 25,26, 27 M1AVLOO1 M1A1228 VL lB 28, 29, 30 M1AVLOO3 M1A1234 VL1C 31,32,33 M1AVLOO5 M1A1240 VL 1D 34, 35, 36 M1AVLOO7 M1A1246 Unit 1
PTI1/A/4600/021 A Page 12 of22 OAC has been out of seice for greater than four hours, perform the following for CA Storage Tank Temperature: Vl Write an El Work Request for IAE to obtain CA Storage Tank Temperature readings. Noti E to perform the following:
/h Person Notifi Date Time Q2. applicable E procedure to record opening of terminal
- in Obtain an instrument capable of converting RTD resistance readings (Platinum 100 ohm) to temperature readings.
Using Table 12.12 1 (CA Storage Tank Temperature), obtain temperature readings. C 2.13.3 Record temperature readings obtained per Table 12.12-1 (CA Storage Tank Temperature) on Enclosure 13.8 (CA Storage Tank Temperatures) every hour. NOTE: Instrument connection can be made to computer cabinet 1AT4, Terminal Block Location Rl (See MC-1790-17.02 for terminal location.) or to applicable terminals in computer room, as desired.
,Terminals used for instrument connections are required to have open terminal links.
using a Fluke 743, set it to read RTD (Pt 100 (3916)) and 3 wire hook up. Table 12.12-1 CA Storage Tank Temperature Description 1AT4 Terminals TB1 Analog Number (Ri) Upper CAST Temp 64, 65, 66 M1A1377 Middle CAST Temp 67, 68, 69 M1A1371 Lower CAST Temp 70, 71, 72 M1A1342 Unit 1
- PT/1/AJ4600/021 A Page 13 of22 12.14 IF QPTR Alarm inoperable AND greater than 50% RTP, perform the following:
12.14.1 all Power Range (PR) channel inputs to QPTR operable, calculate QPTR on Enclosure 13.5 (Calculation Sheet For Quadrant Power Tilt) Part A within 12 hours and every 12 hours thereafter until QPTR Alarm operable. 12.14.2 IF input from one PR channel is inoperable, perform the following: 12.14.2.1 IF less than 75% RTP, perform the following: Q A. Calculate QPTR on Enclosure 13.5 (Calculation Sheet For Quadrant Power Tilt) Part B using other 3 PR channels. 0 B. Record PR channels used within 12 hours and every 12 hours thereafter until QPTR Alarm operable or inoperable PR input operable. 12.14.2.2 IF greater than or equal to 75% RTP, have Reactor Engineering perform PT/O/A!4150/007 (Verification of QPTR Using Incore Detectors) every 12 hours until QPTR Alarm operable or the inoperable PR input operable. 12.14.2.3 AFTER PR channel restored, monitor QPTR per Step 12.14.1. 12.14.3 QPTR is greater than 1.02, refer to ITS 3.2.4 for subsequent action. Unit 1
- PT/IIA/460tJ/021 A Page 14 of 22 12.15 IF outside air temperature is less than 32°F, perform the following:
NOTE:
- FWST Level Instrument Room located within FWST concrete enclosure.
- RWP, dosimetry and Security are required for access to FWST enclosure.
12.15.1 Within 2 hours, check power to FWST Level Instrument Room heaters by ensuring closed:
- Normal heater Panel board 1KG, Bkr 17
- Backup heater Panel board 1KC, Bkr 13 D 12.15.2 Obtain a calibrated digital thermometer, capable of reading ambient air temperatures (Examples: Tegan 871, Keithley 871, or comparable instrument). Instrument can be obtained at tool issue point in Service Building truck corridor.
12.15.3 Every 12 hours, perform the following: D 12.15.3.1 Check Unit 1 FWST Level Instrument Room area temperature (in vicinity of FWST Level Instruments) greater than 40°F. Q 12.15.3.2 Record on Enclosure 13.6 (FWST Level Instrument Room Temperature). 12.16 IF any of the following are out of service, perform PT/1/A/4200/040 (Reactor Coolant Leakage Detection) until all are returned to service:
*OAC
- Mi P0592 (1 EMF3 8(L) Containment Leakage Alarm)
- M1P 1069 (Ui Total Cont Floor & Equip Sump Lvl Rate)
- MiD34Oi (Ui Incore Instrument Room Sump)
Unit 1
PT/l/A14600/021A Page 15 of22 NOTE: Tech Spec Total NC Loop Flow calculation must be performed prior to 1000 or 2200 to comply with ITS 3.4.1. Data collection and manual calculations require 4 hours to complete for surveillance item. 12.17 IF AT ANY TIME there is a possibility that the OAC will be out of service for greater than 12 hours, be prepared to perform a manual calculation as follows: 12.17.1 Notify Work Control SPOC to be prepared to obtain 7300 voltage readings for NC Loop THO, TcOId, and NC Loop Flow transmitters per PT/1/A/4150/013 B (Manual NC Flow Calculation).
/
Person Notified Date Time 12.17.2 Notify NC System Engineer or designee to be prepared to perform PT/i /A/4 150/013 B (Manual NC Flow Calculation).
/
Person Notified Date Time 12.18 IF between hours of 0700 1000 OR 1900 2200 AND PT/1/A/4600/003 A (Semi-Daily Surveillance Items) has NOT yet been performed, perform surveillance of Total NC Loop Flow as follows: 12.18.1 IF valid P1 Data available, use PT Data to meet surveillance requirement for Total NC Loop Flow as follows: 12.18.1.1 Obtain PT Data for point M1P1085 and record Total NC Loop Flow: gpm. 12.18.1.2 Record Date / Time for valid Total NC Loop Flow data used from PT Data (prior to OAC being out of service).
/
Date Time Unit 1
PT/1/A14600/021 A Page 16 of22 NOTE: IF surveillance of Total NC Loop Flow performed prior to normal surveillance time period, surveillance must be performed an additional time to return surveillance period to the normal surveillance period of 0700 1000 or 1900 2200.
- 12. 18.1.3 Ensure Total NC Loop Flow surveillance is performed within 12 hours from Date / Time surveillance was performed in Step 12.18.1.2.
Q 12.18.1.4 Set a timer to track the next time the surveillance is required. LI 12.18.1.5 Repeat Step 12.18.1.4 every 12 hours until OAC is returned to service. 12.18.2 IF valid PT Data unavailable, perform manual calculation as follows: 12.18.2.1 Notify Work Control SPOC to obtain 7300 voltage readings for NC Loop TH I, Tc 0 1d, and NC Loop Flow transmitters per 0 PT/1/A!4l50/013 B (Manual NC Flow Calculation).
/
Person Notified Date Time 12.18.2.2 Notify NC System Engineer or designee to perform PT/1/A/4150/013 B (Manual NC Flow Calculation).
/
Person Notified Date Time Record Total NC Flow: gpm Calculations Performed By Date Time Unit 1
PT[1IA/4600/021 A Page 17 of22 NOTE: Tech Spec Power Range / Heat Balance (Thermal Power) calculation must be performed prior to 0100. Data used for Manual NC Flow Calculation is required for calculation of Power Range / Heat Balance (Thermal Power) for PT/1/A/4600/003 B (Daily Surveillance Items). 12.19 IF AT ANY TIME there is a possibility that the OAC will be out of service for greater than 24 hours, notify Reactor Group Engineer or designee to be prepared to perform PT/0/A141 50/03 9 (Manual Calculation of Thermal Power).
/
Person Notified Date Time 12.20 IF between hours of 1900 0100 AND PT/1/A/4600/003 B (Daily Surveillance Items) has NOT yet been performed, perform surveillance of Power Range / Heat Balance (Thermal Power) calculation as follows: 12.20.1 IF valid PT Data available, use P1 Data to meet surveillance requirement for Power Range / Heat Balance (Thermal Power) as follows: 12.20.1.1 Obtain the following PT Data: Point Description Data (%) M1P1385 Ui Reactor Thermal Power, Best (Estimate) MiPi4O7 Ui Quad 1 (PR43) Excore / Thermal Power Mismatch M1P 1408 Ui Quad 2 (PR42) Excore / Thermal Power Mismatch M1P 1409 Ui Quad 3 (PR44) Excore / Thermal Power Mismatch MiPi4iO Ui Quad 4 (PR41) Excore / Thermal Power Mismatch Unit 1
PT/1IA/4600/O2rA Page 18 of22 12.20.1.2 Record Date / Time for valid Power Range / Heat Balance (Thermal Power) data used from P1 Data (prior to OAC being out of service):
/
Date Time 12.20.1.3 Determine power mismatch as follows:
- Use M1P1407, M1P1408, M1P1409, and M1P141O of Step 12.20.1.1.
OR
- Compare M1P1385 (Ui Reactor Thermal Power, Best) to Control Board Power Range gauges NOTE: IF surveillance of Power Range / Heat Balance (Thermal Power) performed prior to normal surveillance time period, surveillance must be performed an additional time to return surveillance period to normal surveillance period of 1900 0100.
12.20.1.4 Ensure Reactor Power / Heat Balance (Thermal Power) surveillance is performed within 24 hours from Date / Time surveillance was performed in Step 12.20.1.2. LI 12.20.1.5 Set a timer to track the next time the surveillance is required. LI 12.20.1.6 Repeat Step 12.20.1.5 every 12 hours until OAC is returned to service. 12.20.2 valid PT Data is unavailable, notify Reactor Group Engineer or designee to perform PT/0/A/4 150/039 (Manual Calculation of Thermal Power).
/
Person Notified Date Time
/
Calculation Performed By Date Time Unit 1
PT!1IA!4600/021 A Page 19 of22 12.21 IF OAC has been out of service for greater than four hours, perform the following to determine lake level at the Main Intake Structure: O 12.21.1 Obtain the following:
- A 25 foot (minimum) extension tape measure
- Lanyard for tape measure
- Flashlight (as necessary)
NOTE:
- The deck (walking surface) of the Main Intake Structure is at 770 ft.
Measuring lake level can be performed from any point on the Main Intake Structure. O 12.21.2 Using the extension tape, measure from the top of the water surface to the deck (walking surface) of the Main Intake Structure and record below. Distance between Deck (walking surface) of the Main Intake Structure and top of the water surface: ft 0 12.21.3 Subtract measurement obtained in Step 12.21.2 from 770 ft to obtain actual lake level. 0 12.21.4 Record lake level reading on Enclosure 13.10 (Lake Level). NOTE: Bases for actions taken in Step 12.21.5 maybe referenced in UFSAR Section 9.2.2, SLC 16.9.7 and Engineering Calculation MCC-1223.42-00-0055. Actions taken are based on Engineering judgment, to allow adequate time to prepare for possible Unit shutdown. Entry into SLC 16.9.7, Condition D at 747 ft based on 12 inches of lake level uncertainty as documented in Engineering Calculation MCC-l223.42-00-0055. 12.2 1.5 lake level decreases to 747 ft, perform the following: 12.21 .5.1 Notify CRS. 12.21.5.2 Enter SLC 16.9.7, Condition D for lake level. SRO 12.21.5.3 IF lake level decreases to 746 ft, notify Duty Station Manager to initiate formation of Unit Threat Team.
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Person Notified Date Time 12.21.5.4 Evaluate Unit 1 and Unit 2 shutdown to Mode 5 prior to lake SRO level less than 745 ft. Unit 1
PT/1/A/4600/021 A Page 20 of 22 12.2 1.6 j lake level is decreasing AND loss of lake level due to unexpected or rapid lake depletion condition, perform the following: 12.21.6.1 Implement the following: A. AP/1/A/5500/020 (Loss of RN), Case II (Loss of LLI or RC Supply Crossover) B. AP!2/A/5500/020 (Loss of RN), Case II (Loss of LLI or RC Supply Crossover) 12.2 1.6.2 j appropriate, implement RP/0/A15700/006 (Natural Disasters). 12.21.6.3 IF appropriate, implement RP/0/A/5700/007 (Earthquake). 12.21.7 Repeat Steps 12.21.1 - 12.21.6 every 12 hours until OAC returned to service. Unit 1
PT/1/Af4600/021 A Page 21 of22 NOTE: The following values must be updated prior to returning OAC to service to prevent potential Reactivity Management Event due to incorrect data. 12.22 Prior to returning OAC to service, perform the following: {PIP 05-0212} 12.22.1 Notify Reactor Group Duty Engineer to update the following: El Xenon Data El Burnup El Thermal Outputs El 100% Target AFD Values I Person Notified Date Time 12.22.2 HOLD until Reactor Group Duty Engineer has validated the above values. 12.23 AFTER OAC returned to service, perform the following: 12.23.1 Notify RP Shift that P1 Data collection is available. I Person Notified Date Time NOTE: OAC points which have been locked out or have inserted values may unlock during a loss of OAC. IF used in calculations (i.e., TPBE), the calculated values may NOT be accurate. 12.23 .2 Using SRO Turnover printout (PPLOG) of inserted and locked out points, ensure the following are in the same status as before the OAC went out of service: El OAC points that have inserted values El OAC points that are locked out El OAC points deleted from processing El OAC points deleted from alarm Yes No 12.23.3 Acceptance Criteria met. 12.23 .4 Acceptance Criteria NOT met, log applicable Tech Spec or SLC. SRO {PIP M-07-00393} Unit 1
PTtItA!4600/021 A Page 22 of 22
- 13. Enclosures 13.1 Hourly Dispatcher Report 13.2 Axial Flux Difference Monitoring 13.3 Full Length Rod Verification Data 13.4 Containment Air Temperatures 13.5 Calculation Sheet For Quadrant Power Tilt 13.6 FWST Level Instrument Room Temperature 13.7 OAC Point List For Partial Loss Of OAC 13.8 CA Storage Tank Temperatures 13.9 Manual Trigger of Analog Fault Recorder 13.10 Lake Level End of Body Unit 1
Enclosure 13.1 PT/1/A!46D0/021 A Hourly Dispatcher Report Page 1 of 1 Obtain data from Digital Counters Sheet of 2 Unit 1 Gross DIG 1A DIG lB Transf 1ATA Transf 1ATB Net MWHs M1P1103 M1PI 109 M1P1II1 M1P11O4 M1PI 105 M1P0407 Date I Time Initials (MWH) (MWH) (MWH) (MWH) (MWH) (MWH) (+) (_) (_) (_) (_) = I (_) (_) (_) (_) I I (+) () () (_) (_) = (+) (-) (-) (_) (-) = (_) (_) (_) (_) I I (+) () () (_) (_) = I (+) () () (_) (_) = I (+) (_) (_) (_) (_) = I (+) () () (_) (_) = (+/-) (-) (-) (_) (_) = () () (_) () = I I (+) () () (_) () = (_) () (_) (_) = I I (+) (-) (-) (-) (-) = I I () (-) (_) (-) = End of Enclosure Last two digits on Digital Counters for D/G IA and lB are decimal places. Do I use when recording MWHs. 2 For each item, subtract previous hour reading from present hour reading and record in (+) and () area. Then subtract DIG and Transf readings from Unit 1 Gross reading to obtain Net MWHs. Unit 1
Encloure.132-PT/1/A!4600/021 A Axial Flux Difference Monitoring Page 1 of 2 Part A Sheet of 1 Date Time Initials SRO Review 2 PR-41 AFD PR-42 AFD_}_PR-43 AFD PR-44 AFD WHEN greater than or equal to 50% RTP, performed within 1 hour and every hour thereafter until OAC AFD Monitor Alarm operable. 2 Review of the completed surveillance shall be performed by the SRO prior to updating the conditional surveillance in TSAIL. {PIP M-08-04917} Unit 1
Enlosur 13.2 PTII/A/4600/021 A Axial Flux Difference Monitoring Page 2 of 2 Part B Sheet of Date: : 3 Time NOTE:
- Manual AFD calculations using PR detector currents will provide a means to check AFD is within limits as specified in COLR. A difference may exist between manual AFD calculations and functioning OAC calculated values and functioning Control Board AFD gauges due to accuracy of readings and calibration of PR current meters.
- IF more accurate Power Range (PR) detector current readings are desired or required, SPOC should be contacted to obtain PR detector current readings with a digital voltmeter (DVM) per Reactor Engineering procedure PT/O/A!4600/002 G (Incore and NIS Recalibration).
. (A) (B) (C) (D) (E) (F) Detectors 0% Axial Measured (Col B I Col A) (Bet A Det B) M Factor AFD . Offset Currents Currents x 100 2 (Col D x Col E)
- PR-41A PR-41 B PR-42 A PR-42 B PR-43 A PR-43 B PR-44 A PR-44 B (A) From most recent calibration data using 0 Incore Axial Offset current in Data Book, Table 2.2 (T for Detector A and B for Detector B).
(B) From NI cabinets current meters (located on respective PR A and B Drawers). Ensure Detector Milliamp range switches are in 0.5 position and read from 0 500 microamp scale. Readings should be to nearest microamp for accuracy. (C) Column B Measured Current divided by Column A Axial Offset Current for each detector multiplied by 100. (D) Column C Detector A minus Column C Detector B for each PR channel divided by 2. (E) M Factor from Data Book Table 2.2 AFD Incore I Excore Ratios for Quadrants 1 4. - (F) Column D multiplied by Column B will provide AFD value for each PR channel. End of Enclosure WHEN greater than or equal to 50% RTP jQ MCB AFD gauges inoperable, within 1 hour and every hour thereafter until MCB AFD gauges or OAC AFD Monitor Alarm operable. Unit 1
Enclosure 133-PT/1/A/4600/o21 A Full Length Rod Verification Data Page 1 of2 Part A Sheet of All full length rods are positioned within 12 steps (indicated position) of their group demand position and operable. (ITS SR 3.1.4.1) Date Time 1 Initials SRO Review 2 Date Time 1 [ Initials SRO Review 2 Performed within 4 hours and every 4 hours thereafter until OAC Rod Position Deviation Monitor operable. 2 Review of the completed surveillance shall be performed by the SRO prior to updating the conditional surveillance in TSAIL. {PIP M-08-04917} Unit 1
Euclosure 13.3 PTI1/A!4600/021 A Full Length Rod Verification Data Page 2 of 2 Part B Sheet of All Control Banks are above the rod insertion limit as specified in the COLR. (ITS SR 3.1.6.2) Control Control Control Control 3 . SRO Date Time Initials Bank A Bank B Bank C Bank D Review 4 Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position Insertion Limit Bank Position End of Enclosure Performed within 4 hours and every 4 hours thereafter until OAC Rod Insertion Limit Monitor or Annunciator 1AD-2, B9 (Control Rod Bank Lo-Lo Limit) operable. Review of the completed surveillance shall be performed by the SRO prior to updating the conditional surveillance in TSAIL. {PIP M-08-04917} Unit 1
Enc1sure- 13.4
- PT/11A14600/021 A Containment Air Temperatures Page 1 of 1 Sheet of Upper Containment Temperature (°F) Lower Containment Temperature (°F) SRO 2
Date Time Initials Review 1A lB 1C { 1D 3 Average 1A lB 1C 1D 4 Average End of Enclosure Performed every hour while OAC is out of service beginning four hours after OAC out of service. 2 Review of the completed surveillance shall be performed by the SRO. {PIP M-08-04917} Upper Containment average air temperature shall be computed using temperature points corresponding to A}{Us with operable sensors, regardless of AHU running or not running (based on large air volume (mass) in upper containment). {PIP-O-MOO-0552 } Lower Containment average air temperature shall be computed using temperature points corresponding to running AHUs with operable sensors. {Pll-O-MOO-O552} Unit 1
Enclosure 13.5 PT/1/A14600/021 A Calculation Sheet For Quadrant Power Tilt Page 1 of 4 Part A Sheet of NOTE:
- more accurate Power Range (PR) detector current readings are desired or required, SPOC should be contacted to obtain PR detector current readings with a digital voltmeter (DVM) per Reactor Engineering procedure PT/O/A14600/002 G (Incore and NIS Recalibration).
- Data can also be provided by IP/O/A!3207/003 K (NIS Power Range N41 / N42 / N43 and N44 Drawer Calibration).
Date Time Initials PR-41 PR-42 PR-43 PR-44 SRO Review 2 A B A B A B A B
- 1) Measured Current
- 2) Calibration Current
- 3) Relative Flux (RF)
- 1) From NI cabinets current meter (located on respective PR B Drawers). Ensure Detector Milliamp Range Switches are in 0.5 position and read 0 500 microamp scale.
- 2) From most recent calibration data using 0 Incore Axial Offset Current in Data Book, Table 2.2 (IT for detector A, Is for detector B).
- 3) Divide line 1 by line 2 to calculate Relative Flux (RF) for each upper (A) and lower (B) detector.
WHEN above 50% RTP, calculation performed within 12 hours and every 12 hours thereafter until QPTR Alarm operable. 2 Review of the completed surveillance shall be performed by the SRO prior to updating the conditional surveillance in TSAIL. {PIP M-08-04917} Unit 1
Enciosurel3S PT/l/A!460G/021A Calculation Sheet For Quadrant Power Tilt Page 2 of 4 Part A (continued) Quadrant Power Tilts: Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux Avg RF of A Detectors + + + x1/4 = (RFA) RF of PR-41A RF of PR-42A RF of PR-43A RF of PR-44A Avg RF of B Detectors + + + x1/4 = (RFB) RF ofPR-41B RF of PR-42B RF of PR-43B RF of PR-44B PR-41A Tilt = RF of PR-41A = PR-41B Tilt RF of PR41B RFA RFB PR-42A Tilt = RF of PR-42A = PR-42B Tilt = RF of PR-42B = RFA RFB PR-43A Tilt = RF of PR-43A = PR-43B Tilt = RF of PR-43B = RFA RFB PR-44A Tilt = RF of PR-44A = PR-44B Tilt = RF of PR-44B = RFA RFB Unit 1
Enlos.ure 13.5 PT/1/A74600/021 A Calculation Sheet For Quadrant Power Tilt Page 3 of 4 Part B Sheet of NOTE:
- j more accurate Power Range (PR) detector current readings are desired or required, SPOC should be contacted to obtain PR detector current readings with a digital voltmeter (DVM) per Reactor Engineering procedure PT/O/A!4600/002 G (Incore and NIS Recalibration).
- Data can also be provided by IP/O/A13207/003 K (NIS Power Range N41 / N42 / N43 and N44 Drawer Calibration).
Date 3 Time Initials PR-4 PR-4 PR-4 SRO 4 Review A B A B A B
- 1) Measured Current
- 2) Calibration Current
- 3) Relative Flux (RE)
- 1) From NI cabinets current meter (located on respective PR B Drawers). Ensure Detector Milliamp Range Switches are in 0.5 position and read 0 500 microamp scale.
- 2) From most recent calibration data using 0 Incore Axial Offset Current in Data Book, Table 2.2 (IT for detector A, 1B for detector B).
- 3) Divide line 1 by line 2 to calculate Relative Flux (RE) for each upper (A) and lower (B) detector.
WHEN greater than 50% RTP but less than 75% RTP, calculation performed within 12 hours and every 12 hours thereafter while QPTR Alarm inoperable and one PR channel input inoperable. of the completed surveillance shall be performed by the SRO prior to updating the conditional surveillance in TSAIL. {PIP M-08-049l7} Unit 1
Enclosure 13.5 PT/1/A/4600/021 A Calculation Sheet For Quadrant Power Tilt Page 4 of 4 Part B (continued) Quadrant Power Tilts: Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux Avg RF of A Detectors + + x (RFA) RF of PR-4_A RF ofPR-4A RF of PR-4_A Avg RF of B Detectors + + x (RFB) RF of PR-4_B RF of PR-4_B RF ofPR-4B PR-4A Tilt = RE of PR-4 A PR-4B Tilt = RF of PR-4 B RFA RFB PR-4A Tilt = RE of PR4 A PR-4B Tilt = RF of PR-4_B = RFA RFB PR-4A Tilt RF of PR-4 A = PR-4B Tilt = RF of PR-4_B = RFA RFB End of Enclosure Unit 1
En1oure [ PY/1/A/4600/021 A FWST Level Instrument Room Temperature Page 1 of 1 Sheet of Digital Thermometer Date Time 1 J Initials Area Temperature (°F) Manufacturer Model # Instrument # Cal Due Date End of Enclosure Performed every 12 hours while outside temperature less than 32°F. Unit 1
Enclosure 137 PT/11A14600/021 A OAC Point List For Partial Loss Of OAC Page 1 of 2 OAC Point Title Procedure Sections To Be Performed M1L4375 Tech Spec AFD Monitor Inoperable M1P1385 Reactor Thermal Power, Best 12.3, 12.6, 12.7, 12.8, 12.10, 12.14, 12.17, 12.18, 12.19, 12.20, 12.23 Ml L236 1 Therm Pwr Limit Change Program Status Mi L26 11 Thermal Power Caics Program Status Mi Li 200 Jems External Gateway Link Status M1L1201 SOC External Gateway Link Status 12.3, 12.8, 12.9 M1L2303 SWBD Application Active Flag M1L2221 Upper / Lower Contmnt Temp Program Status M1P15O1 Upper Cont Avg Temp M1P0755 Lower Containment Weighted Average Temp MiAi 228 Lower Cont Ambient Air Temp A 12.3, 12.12 M1A1234 Lower Cont Ambient Air Temp B M1A1240 Lower Cont Ambient Air Temp C M1A1 246 Lower Cont Ambient Air Temp D M1L221 1 Equipment Runtime Program Status M1A1074 FWST Instrument Room Temperature 12.3, 12.15 M1L2050 NC Flow Monitoring Status 12.3, 12.17, 12.18, 12.23 M1P1O85 Ui NC Flow Best (10 mm avg) M1L1202 EMF External Gateway Link Status M1D34O1 Ui IncoreinstrumentRoomSump 12.3, 12.16 M1EO 190 EMF38L Containment Part Lo Range M1P1O69 Ui Total Cont Floor & Equip sump Lvl Rate M1E0178 EMF36L Unit Vent Gas Lo Range M1P2535 Average Unit Vent Stack Flow 12.3, 12.4, 12.23 M1A0766 Lake Level 12.21 Unit 1
Encloure 137. PT/1/A14600/021 A OAC Point List For Partial Loss Of OAC Page 2 of 2 OAC Point Title
] Procedure Sections To Be Performed M1L2391 Control Rod Posit Monitor Prgm Status M1L4051 Rod Bank Position Hardware Malfunction M1L4052 Control Rod Position Hardware Malfunct M1L4464 Control Rod Insert Limits-Invalid Data M1P1551 Max Rod Deviation Shutdown Bank A M1P1552 Max Rod Deviation Shutdown Bank B 12.3, 12.6, 12.11, 12.23 M1P 1553 Max Rod Deviation Shutdown Bank C M1P 1554 Max Rod Deviation Shutdown Bank D M1P 1555 Max Rod Deviation Shutdown Bank E M1P 1556 Max Rod Deviation Control Bank A M 1P 1557 Max Rod Deviation Control Bank B M1P1558 Max Rod Deviation Control Bank C M1P 1559 Max Rod Deviation Control Bank D M1L4409 Ctrl Bank Tech Spec Insert Lmt Reached M1L4410 Shutdown Bank Withdrawn Per Tech Specs M1L441 1 Improper Bank Sequence Or Bank Overlap Ml P1448 Low Bank Insertion Limit Margin M1L1470 Xenon I Samarium Calcs Program Status 12.3, 12.23 M1L261 1 Thermal Power Calcs Program Status M1A1342 Lower CA Storage Tank Temperature M1A1371 Middle CA Storage Tank Temperature 12.3, 12.13 M1A1377 Upper CA Storage Tank Temperature M1P2835 lB 230 KV Busline In Service Only M1P2836 1A 230 KV Busline In Service Only 12.3, 12.5 M1E0835 230 KV Y Bus Volts M1E0850 230 KV R Bus Volts M1P2837 2B 525 KV Busline In Service Only M1P2838 2A 525 KV Busline In Service Only M1E0905 525 KV Y Bus Volts M1E0921 525 KV R Bus Volts End of Enclosure Unit 1
EncLosure 13.8 PTII/A!46001021 A CA Storage Tank Temperatures Page 1 of 1 Sheet of 1 Upper °F Middle °F Lower °F Date Time Intitials End of Enclosure Performed every hour while OAC is out of service beginning 4 hours after OAC out of service. Unit 1
Enclosure 13.9
/1/,46OO/O21 A Manual Trigger of Analog Fault Recorder Page 1 of 1 Sheet of Manual Trigger Depressed Date Time Initial End of Enclosure Unit 1
Enclosure hu1 PT/1/A/4600/021 A Lake Level Page 1 of 1 Sheet of 2 Lake Level Date Time Initials SRO Review End of Enclosure Performed every 12 hours while OAC is out of service; beginning 4 hours after OAC out of service. 2 of the completed surveillance shall be performed by the SRO. {PIP M-08-04917} Unit 1
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Aib SRO 2011 Admin JPM Aib SRO (Rev_04111)
- NUREG 1021, Revision 9
Appendix C Page 2 of 8 Form ES-C-I
- Job PerforrnanceMeasure Worksheet Facility: McGuire Task No.:
Task
Title:
Calculate Reactor Vessel Head JPM No.: 2011 Admin JPM Al b Venting Time SRO K/A
Reference:
GKIA2.1.25 (3.9/4.2) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant 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: McGuire Unit I is in a Post-Accident situation. You are a Licensed Operator available in the Operational Support Center (OSC). EP/1/A15000/FR-l.3 (Response to Voids in Reactor Vessel) has been implemented and completed through step 20.a. The following conditions exist: Containment Pressure 7.2 psig Lower Containment Temperature 190°F Containment H 2 Concentration 2.9 % NC Pressure 550 psig Task Standard: The Reactor Vessel Head venting time calculated to fall between 1.74 and 1.85 minutes. Required Materials: Calculator General
References:
EP/1/A/5000/FR-l.3 (Response to Voids in the Reactor Vessel), Rev 9 Handouts: EP/1/A15000/FR-l.3 (Response to Voids in the Reactor Vessel) Enclosure 1 (Allowable H2 Venting Time) 2011 Admin-JPMAIbSRO NUREG 1021, Revision 9
Appendix C Page 3 of 8 Form ES-C-i Job Performance Measure Worksheet - Initiating Cue: You have been directed to calculate maximum venting time per Enclosure 1, (Allowable H2 Venting Time) of EPIIIA/5000/FR-I.3, (Response to Voids in Reactor Vessel). Time Critical Task: NO Validation Time: 8 minutes 2011 Admin JPM Al b SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*) Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout EPIIIAI5000IFR-I.3, Enclosure 1. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Step 1) Calculate A The operator calculates A A = 9,500 (x) (P+14.7) (x) 492 9,500 (x) (7.2+14.7) (x) 492 14.7 (T+460) 14.7 (190+460) Where: P = 7.2 as stated in Initial Conditions. P = Containment T = 190 as stated in Initial pressure (PSI G) Conditions. T = Lower containment This equals ave. temp (F) 9,500 x 1.49 x 0.76 and this equals: A= A= 10757.80 2 (Step 2) Calculate B The operator calculates B B=(3-H)(x)A (32.9)x10757.80= where H = 2.9 as stated in Initial Conditions. H = Containment H-2 A = Calculated Value in Concentration (%). Step 1. B = (0.1) x (10757.80) = B = 1075.78 2011 Admin-JPMA1bSRO NUREG 1021, Revision 9
Appendix C Page 5 of 8 Form ES-C-i
- PERFORMANCE tNFORMAT1N STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*3 (Step 3) Determine C from The operator uses Curve on the curve for the current NC Page 2 of 2 of Enclosure 1, system pressure and determines C to equal 600 +/-20 using curve *4 (Step 4) Calculate T The operator calculates T T = B/C = Venting Time 1075.78 =
in minutes 600 T = I B = Calculated Value in Step 2. T = minutes C = Value obtained from Curve in Step 3. 1.79 minutes (Acceptable range of t74 1.85 minutes) Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2011 Admin-JPMA1bSRO NUREG 1021, Revisiong
Appendix C Page 6 of 8 Form ES-C-I VERIFICATIONOF COMPLETION Job Performance Measure No.: 2011 Admin JPM Al b SRO Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin JPM Alb SRO
- NUREG 1021, Revision 9
Appendix C Page 7 of 8 Form ES-C-i
- VER1FlCATFOttORCOMPLETlOtI KEY:
A= 9,500(x)(P+14.7) (x) 492 14.7 (T+460) A=9,500(x) (7.2+14.7)(x) 492 14.7 (190+460) A = 9,500 x 1.49 x 0.76 = 10757.80 B = (3 H)
- (x) A B = (32.9) x 10,757.80 B (0.1) x (10,757.80) 1075.78 C = Using Enclosure 1 Graph for NC System Pressure of 350 psig = 600+/-20 SCFM Venting Time in minutes (T) = B/C =1075.78 1.74-1.85 minutes 600+/-20 (Acceptable range of 1.74 1.85 minutes) 2011 Admin-JPMAIbSRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM-CUE SHEET - INITIAL CONDITIONS: McGuire Unit 1 is in a Post-Accident situation. You are a Licensed Operator available in the Operational Support Center (OSC). EPI1IAI5000IFR-l.3 (Response to Voids in Reactor Vessel) has been implemented and completed through step 20.a. The following conditions exist: Containment Pressure 7.2 psig Lower Containment Temperature 190°F Containment H 2 Concentration 2.9 % NC Pressure 550 psig INITIATING CUE: You have been directed to calculate maximum venting time per Enclosure 1, (Allowable H2 Venting Time) of EP/1/A15000/FR-I.3, (Response to Voids in Reactor Vessel). NUREG 1021, Revision 9
I MNS I RESPONSE TO VOIDS IN REACTOR VESSEL I PAGE NO. F EPtIIN5000IFR-L3 I Enclosure I Page 1 of 2 24 of 27 Rev. 10 UNIT 1 Allowable H2 Venting Time f CALCULATION OF MAXIMUM ALLOWABLE VENTING TIME STEP 1: Calculate A (P + 14.7) 492 A=9,500x x 14.7 (t + 460) Where: P = Containment pressure (PSIG) t = Lower containment avg temp (°F) (____ + 14.7) 492 A=9,500x x 14.7 C +460) A=9,500x x STEP 2: Calculate B B = (3 - H) x A where: H = Containment H2 Concentration (%) STEP 3: Determine C from the curve (on page 2) for the current NC system pressure. STEP 4: Calculate T T = B/C = Venting Time in minutes
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Appendix C Job Performance Measure Form ES-C-i
- Worksheet JPMA2SRO 2011 Admin JPM A2 SRO (Rev_041111)
- NUREG 1021, Revision 9
Appendix C Page 2 of 10 Form ES-C-i
- Jab Performariae Measure Warkshet Facility: McGuire Task No.:
Task
Title:
Perform a Thermal Margin JPM No.: 2011 Admin JPM A2 Determination SRO K/A
Reference:
GK/A 2.2.12 (3.9) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant 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:
- Unit I was shutdown 24 days ago for a mid-cycle outage after 200 days of operation.
- Unit I is currently in Mode 5.
- No Core Offload will occur.
- The NC system is 145°F with A Train ND in service.
- Preparations are being made to lower NC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/IIA/61 00/SD-20 (Draining the NC System).
Task Standard: The operator will complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) with a new thermal margin calculated and documented on Attachment 12.7 (Shutdown Assessment Status) and on MC-6/MLOG, as well as make the required notifications to the CCC and STA. Required Materials: None General
References:
OP/1/A/6100/SD-20 (Draining the NC System), Rev 40 OMP 5-8 (Shift Supervision Turnovers), Rev 44 OP/1/A/6100/22 (Core Data Book), Cycle 21 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Page 3 of 10 Form ES-C-i JOb P rrinoe teure Werkheef Handouts: Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) Attachment 12.7 (Shutdown Assessment/Status) of OMP 5-8 (Shift Supervision Turnovers) 0P111A16100122 (Core Data Book), Cycle 21, Enclosure 4.3, Section 2.10 (Thermal Margin Curves at Various Reactor Vessel Levels). Initiating Cue: Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 9 inches above Hot Leg Centerline and make the appropriate notifications. Time Critical Task: NO Validation Time: 15 minutes 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of 10 Form ESC-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*) Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and the three (3) identified Handouts. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Attachment 12.6) The operator places a Applicable to: check in the Unit 1 checkbox. Unit 1 Unit 2 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Page 5 of 10 Form ES-C-i PERFORMANCE lfWORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Attachment 12.6, Step 1) The operator obtains the Refer to OP/I (2)/A/61 00/22, Core Data Book and locates Unit 1 (2) Databook, Section 2.10. Enclosure 4.3, Section 2.10 Thermal Margin Curves, to The operator recognizes determine appropriate that since the Loops are section and/or curve to use. drained and the Vessel Head has NOT been removed, the Curves of Section 2.10.1 are SECTION/CURVE applicable. USED The operator determines that from the Initial INITIAL________ conditions given, Enclosure 4.3 Section 2.10.1 A is to be used, and records this, placing their initial in the appropriate Block. Using 2.10.1 A Curve, the operator intersects the point of 24 days after shutdown and the 160°F temperature Curve, and determines that the new Thermal Margin is
.36+/-02 hours, or 21.6 +/-1.2 minutes.
NOTE: The operator may use 2.10.1 A (I) Curve. If so, the operator intersects the point of 24 days after shutdown and the 160°F temperature Curve, and determines that the new Thermal Margin is 22 +/-1 minutes. 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Page 6 of 10 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 3 (Attachment 12.6, Step 2) The operator records the Document thermal margin date in the chart on time and maximum NC Attachment 12.6. Temperature allowed (for curve used) in the table The operator records the below and initial, time in the chart on Attachment 12.6. The operator records 21.6
+/-1.2 minutes in the Thermal Margin MIN block on the chart on Attachment 12.6.
The operator records 160°F in the Max NC Temp °F block on the chart on Attachment 12.6. 4 (Attachment 12.6, Step 3) Communicate Thermal Margin as follows: The operator records JA
+/-1.2 minutes in the (Attachment 12.6, Step 3.a) Thermal Margin Column Write thermal margin time TM Minutes block on and max NC Temp on the Attachment 12.7.
Shutdown Assessment/Status The operator records 160°F (Attachment 12.7). Include in the Thermal Margin any data Book 4.3 Section Column Max NC Temp 2.10 support parameters block on Attachment 12.7. (S/G Lvls, Pzr Lvi, etc.) Initial in Table below. The operator records 9 in the Thermal Margin Column N CS Level block on Attachment 12.7. The operator places their initial in the Thermal Margin Data Written on Shutdown Assessment/Status (Attachment 12.7) block on the chart on Attachment 12.6. 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Page 7 of 10 Form ES-C-i PERFORMANCE [NFORMAT1Of4 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*5 (Attachment 12.6, Step 3.b) The operator contacts the Notify the Containment CCC and notifies that TM is Closure Coordinator (CCC) 21.6 +/-1.2 minutes.
of the thermal margin time determined. Initial in the Cue: table below. The Containment Closure Coordinator has been notified. The operator places their initial in the CCC Notified block on the chart on Attachment 12.6.
*6 (Attachment 12.6, Step 3.c)
Notify the Shift Technical The operator contacts the Advisor (STA) of the STA and notifies that TM is thermal margin time 21.6 +/-1.2 minutes. determined. Initial in the table below. I Cue: TheSTA has been notified. The operator places their initial in the STA Notified block on the chart on Attachment 12.6. 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Page 8 of 10 Form ES-C-i PERFORMANCE [NFORMAT[ON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 7 (Attachment 12.6, Step 3.d) The operator directs the Write thermal margin time OATC to write 21.6 +/-1.2 on MC-6 and update minutes in the TM Block on MLOG. Initial in the table MC-6, and enter into below. MLOG. Cue: MC-6IMLOG has been updated. The operator places their initial in the Thermal Margin Time Written on MC-6 and MLOG block on the chart on Attachment 12.6. Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Page 9 of 10 Form ES-C-i VER[flCAON OF COMPLON Job Performance Measure No.: 2011 Admin JPM A2 SRO Examinees Name: Date Performed: Facility Evaluator: Numberof Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin JPM A2 SRO
- NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMGUE SHEET INITIAL CONDITIONS:
- Unit 1 was shutdown 24 days ago for a mid-cycle outage after 200 days of operation.
- Unit I is currently in Mode 5.
- No Core Offload will occur.
- The NC system is 145°F with A Train ND in service.
- Preparations are being made to lower NC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OPI1/AI6100ISD-20 (Draining the NC System).
INITIATING CUE: Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 9 inches above Hot Leg Centerline and make the appropriate notifications. NUREG 1021, Revision 9
Attachment 12.6 OMP 5$ Thermal Margin Determination Page 1 of 1 Applicable to: D Unit 1 D Unit 2 PT/i (2)/A14200/002 C (Containment Closure) is required during outages to ensure any breached penetrations are closed within the time constraints of thermal margin. The purpose of this attachment is to provide guidance in determining the thermal margin time constraint and the communication of thermal margin time. NOTE: IF plant conditions are to be changed such that thermal margin will become less (i.e., decreasing NCS inventory), thermal margin shall be determined and communicated ahead of time (prior to decrease in thermal margin) to ensure containment closure requirements can be or will continue to be met. WHEN containment closure is required (or thennal margin will change), determine and communicate thermal margin as follows: i) Refer to OP/1(2)/A16100/022, Unit 1(2) Databook, Enclosure 4.3, Section 2.10 Thermal Margin Curves, to determine appropriate section and/or curve to use. SECTION/CURVE USED INITIAL
- 2) Document thermal margin time and maximum NC temperature allowed (for curve used) in the table below and initial.
- 3) Communicate thermal margin as follows:
a) Write thermal margin time and max NC Temp on the Shutdown Assessment/Status (Attachment 12.7). Include any Data Book Enclosure 4.3 Section 2.10 support parameters (S/G Lvls, Pzr Lvl, etc.). Initial in table below. b) Notif the Containment Closure Coordinator (CCC) of the thermal margin time determined. Initial in table below. c) Notif the Shift Technical Advisor (STA) of the thermal margin determined. Initial in table below. d) Write thermal margin time on MC-6 and update MLOG on SDS (OAC). Initial in table below. INITIAL COMPLETION OF ITEMS BELOW Date Time Thermal Max Thermal Margin Thermal Margin CCC STA Notified Margin NC Data Written on Time Updated Notified MIN. Temp Shutdown on MC-6 and
°F Assessment/Status MLOG (Attachment_12.7)
Attacliiiieflt 12.7 OMP 5-8 Shutdown Assessment/Status Page 1 of 3 2.7 is intended to help the CRS on the outage unit keep track of important plant configurations and status in the event of a loss of decay heat removal. The Restoration of Available Systems, Structures, Components (SSCs), table is intended to track the individual andlor position responsible for supporting the in the field restoration of the SSCs during a loss of decay heat removal as directed by AP-19. SSC column document particular SSC to be restored; example could be lA NV Pump Action column document what manual action must be taken to restore the SSC function, example would be remove white tag and rack in breaker for 1A NV Pump Responsibility column document the responsible position or individual who will perform the action: example would be Unit 1 Aux Building Rounds Communication column document the primary means to be used to contact the individual; example would be t Radio The individual(s) responsible for performing these task(s) must be determined in such a manner as to ensure continuous coverage during shift turnovers. The Large Vent Path status tracker is to be used anytime there is fuel in the core and the S/G nozzle dams or incore instrument guide tube low pressure seals are in place. The required size of the Large Vent Path is such that the pressure limits of the nozzle dams and low pressure seals are NOT challenged by any credible outage accident or combination of pumps injecting into the reactor coolant system as a response to an accident. The definition of a Large Vent path is from NSD 403 (Shutdown Risk Management (Modes 4, 5, 6, and No-Mode) per 10 CFR 50.65(a)(4)) and located on the status tracker. To verify the path, check off the status of each S/Gs hot and cold legs nozzle dams and manways/diaphragms. WHEN the Large Vent Path has been determined, check off which S/G is being used for credit at that time. Update the status tracker each time that Maintenance changes the location of the Large Vent Path.
Attachment 12.7 OMP 5-8 Shutdown Assessment/Status Page2of3 SHUTDOWN ASSESSMENT/STATUS Boron Injection Flowpath Protected Train Thermal Margin LTOP Vent Path (Select 1) Gravity Fill Vent Path (Select 1) Mode 4, 5. and 6 Mode 4, 5. and 6 (Notify CCC / STA when 1 NC-32 / 34 operable D Same as Large Vent Path changed) D Boron Injection Flowpath (Should include DIG, NV Pump, D Pzr Safety out D Other per NSD 403 (specify) (Initial) BAT Pump, NI Pump, ND TM Minutes D Additional (DID) Boron Pump, KC Pumps, RN Pump, D Pzr PORV Gagged Injection Flowpath KF Pump) (Initial) Support Conditions D Boron Injection Flowpath(s) Correctly Identified On D Pzr PORV out No Mode Max NC Temp_____________ Control Boards D Other (specify): (Initial) (Should include DIG, KC S/G Level(s) Pumps, RN Pump, KF Pump) NCS Level Desire NC Level Refuel Cavity Level Desired NC Temp Check () selected Train: Date D A 0 B SFP Time to Boil OWPG Staff____________ Restoration of Available SSCs SSC Action Responsibility Communication
Attachment 12.7 OMP 5-8 Shutdown Assessment/Status Page 3 of 3 A LARGE VENT PATH is:
- Required to exist at all times that either nozzle dams or low pressure incore seals are installed.
- Provided by the following examples:
U Large Vent Path Credit o Removal of a hot leg diaphragm and manway with hot leg nozzle dam I installed EJ Large Vent Path Credit o Removal of cold leg diaphragm and ntanway in a loop with hot leg nozzle dam NOT installed. Associated cold 1 eg nozzle darn must he itt-service. (AUlLON: SJG C Cpld o Removal of the reactor vessel head for both High Decay Heat and Low Decay Heat. Leg \ianwav shall NOT A fully detensioned reactor vessel head which can move upward when sufficiently pressurized will be used as I lot Leg vent seme ma pressure relief path for the Low Pressure Seals, provided nozzle dams are NOT installed. path because olhuhhlc With the reactor vessel head removed and the reactor upper tnternals in place, adequate pressure relief wilt occur through the internals to prevent any adverse effect on the nozzle dam or mv pressure incore induced siphon potential. instrumentation seats if boiling were to occur under the internals. With the head off there exists an PIE M-93-00527} acceptable large vent path in both high and low decay heat. Cold Leg Hot Leg Cold Leg Hot Leg Manway ! Diaphragm: Manway! Diaphragm: Manway! Diaphragm: Manway ! Diaphragm: U Installed U Installed U Installed U Installed U Removed U Removed U Removed U Removed Nozzle Dam: Nozzle Dam: Nozzle Dam: Nozzle Dam: U Installed O Installed U Installed U Installed U Removed O Removed Head U Removed U Removed U Large Vent Path Credit U Large Vent Path Credit U::.Ji Hot Leg Cold Leg Cold Leg Hot Leg U Head is Removed Cold Leg Hot Leg Manway! Diaphragm: Manway ! Diaphragm: U Head is Set! Manway ! Diaphragm: Manway ! Diaphragm: Detensioned U Installed U Installed U Installed U Installed U Head is Set! U Removed U Removed U Removed U Removed Tensioned Nozzle Dam: Nozzle Dam: U Low Pressure Nozzle Dam: Nozzle Dam: U Installed U Installed Incore Seals U Installed U Installed Installed U Removed U Removed U Removed U Removed
UNIT 1 Page 1 of 3 OP/l/N6100122 ENCLOSUE 4. SECTION 2.10.1 THERMAL MARGIN CURVES AT VARIOUS REACTOR VESSEL LEVELS
Purpose:
The thermal margin curves presented in section 2.10.1 are to be used in assessing time to core boiling for loss of decay heat removal capabilities. This information is used in assessing the need for containment closure for periods when either the Reac tor Coolant system is not intact (not capable of being pressurized), the Reactor Coolant syste m level is below 20% Pressurizer cold calibration level (or Corrected Pressurizer Level, P030
- 1) or the decay heat removal function is compromised or degraded.
Use of the Curves: These curves are documented in DPC-1552.08-00-0014, Rev. 6, Loss of Decay Heat Removal. This calculation is based upon the decay heat generated by cores operated at 100% power for nominally 505 continuous days. The decay heat values used should be reevaluated for continuous 100% power operation extending beyond 525 days. The user should be aware that the information presented in these curves should be used in conjunction with the information in Section 2.10.4 to ensu re adequate contingency planning to mitigate core boiling (particularly for reduced inventory coupled with high decay heat conditions). For times when the upper internals are in place (prior to reload), care should be taken to ensure appropriate flow paths are aligned to ensu re adequate forced flow through the core upon a loss of decay heat removal capacity. With internals in place and a loss of decay heat removal, resistance across the nozzles would restrict circu lation I replenishment flow and could lead to voiding in the top of the core even with Reactor Coolant level above the upper internals. This voiding phenomena will not occur if forced flow is initiated prior to the onset of boiling at a flow rate defined in Section2.10.4 or if the internals are removed. Therefore, when the RCS is no longer intact and the upper internals are installed, Ther mal Margin should be determined using the 84 curves as a maximum. The curves contained in this section contain informati on on time to core boiling following a complete loss of decay heat removal capability base d on various Reactor Coolant system volumes and initial temperatures. To ensure conserva tism, for any initial temperature in between the given range, the user should default to the curve with the higher initial temperature in calculation of thermal margin. Likewise, for any initia l level in between the given range, the user should default to the curve with the lower level in calcu lation of thermal margin. UNIT 1
UNIT 1 Page 2of 3 OPI1IN6IOO/22 ENGLOSURE4.3 SECTION. 2.10.1 Detailed Discussion of Development and Application of Section 2.10.1 Section 2.10.1 contains thermal margin curves for various Reactor Vessel Levels (9, 60 and 84 above Hot Leg Centerline) based on time to boil verses time after shutdown for pre-refue and post refueling configurations. ling In the Initial Conditions section of 2.10.1, the prov ision is included stating that prior to shutdown, 100% power operation was achieved for a minimum of one week. In the event a is shutdown after operating for a period less than unit one week and a less conservative thermal margin determination is required, Primary System Engineering should be contacted to determine the changes in the heat load assumptions for the thermal margin determination. UNIT 1
UNIT 1 Page 3of 3 OP/I!A/6i00122 - ENCLOSURE4.3* SECTION 2. 10.1 I. Initial Conditions A. 100% power operation (for a minimum of one week) prior to shutdown. B. Complete Loss of Decay Heat Removal Capability. C. No mitigative actions are taken. II. Assumptions and Conservatisms A. The RCS is depressurized and open to the Reactor Buildi ng atmosphere. B. Water in the lower plenum, the downcomer, the barrel-baffle region, the hot legs, and the cold legs are assumed to be thermally isolated from the core region during the heatup to saturation. Therefore, the volume of water used to determ ine when the core region reaches saturation consists of the water in and above the active fuel (inide the core barrel but excluding the barrel-baffle region) up to elevation 740.96 feet. D. Perfect mixing is assumed to occur in the regions being heated to saturation. Therefore, all of the heated water is assumed to reach saturation at the same time. E. Water volumes in geometrically complex regions are minim ized for conservative results. F. The heating of the reactor vessel internal structures is neglec ted as an additional conservatism. G. The effect of the elevation head in the RCS in raising the saturation temperature is considered. H. Decay heat and core volumes are referenced from the applica ble revision of DPC- 1552.08-00-0014. ifi. References A. DPC-1552.08-00-0014, Loss of Decay Heat Removal B. DPC-1552.08-00-0051, Decay Heat for Mark-BW and OFA Fuel Types C. DPC-l552.08-00-0089, Time Required After Shutdown Before Entering Mid-Loop Operation UNIT 1
IT1 Enclos. ,b - Section 2.1O,1,A Loss of Decay Heat Removal with Water Level 9 Above Hot Leg Centerline (Prior to Offload) 15 ________ CI-) -c P I 0 - m .- 0 0
- 0 H
0.5 1 - - -
- NOTE: For expanded resolution of these - 140 deg F curves refer to 210 1 A(1) 160 degF 0
0 10 20 30 40 50 60 70 Time after Shutdown (days) UNIT 1
UNtT1 OP/i I 1 0.01022 EncIo ctfon 2.1O.1,A(1) Loss of Decay Heat Removal with Water Level 9 Above Hot Leg Centerline (Prior to Offload) 50
-I-L_L_
40 H 1 a) C 30 . hL. ] L L rEZZE* - . - 0 I_-___ I 0 S l---
= ---
F- _r lOOdegF 10 77f l2Ode.gF 1/7/ l4Ode.gF I:
- l6OdegF 0
0 1 2 j j 3 4 I 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Time after Shutdown (days) UNIT1
IT 1 QPu1 1OJIO22 Enclos Section 2.1O.1.B Loss of Decay Heat Removal with Water Level 6Ot Above Hot Leg Centerline (Prior to Offload) 2 -__ lOOdegF 1 - l2OdegF NOTE: For - l4OdegF 1 - resoIuon of these
- 160 deg F 0*
0 10 20 30 40 50 60 70 Time after Shutdown (days) UNIT I
NIT 1 ei O0A022 Ericic 3ecton 2.10.1.B(1) Loss of Decay Heat Removal with Water Level 60 Above Hot Leg Centerline (Prior to Offload) 60 50 40 z::;::zzEzEz: C S Dl C 0 30 0 ci) 20 - j;jtJ+HZZ
/jZ - - -
100 degF 7,/I, - - 10 -------- 120 deg F
$Q
- l4Ode.gF
/ - -
- 1.6OdegF 0
.84
-r r -r m -r m -r -
0 2 3 4 5 6 7 8 9 10 11 12 13 14.15 16 17 18 19 20 21 2.2 as Time after Shutdown (days) UNIT 1
T 1 or I ØC!022 EncIosL , - Section 2.10.1.0 Loss of Decay Heat Removal with Water Level 84 Above Hot Leg Centerl ine (Prior to Offload) 2 NOTE: IF upper internals are installed and level is >1= 84, these cues apply. I 1.5 U) -c C) C C - 0 - - a -
- 0)
- [
0,5 100 degF 17/ l2OdegF NOTE: For expanded resolution of these - l4OdegF curves, refer to 2,10.1.C(1). - - - l6OdegF 0 0 10 20 30 40 50 6.0 70 Time after Shutdown (days) UNIT 1
1T 1 C 100/022 EncIo ection 2.1O,1,C(1) Loss of Decay Heat Removal with Water Level 84 Above Hot Leg Cen terline (Prior to Offload) 70 I I NOTE: IF upper internals are instaHed and level is >1= 84, these cues apply. 60 m 2 2 CD C 0 0 F-50 40 30 LEEEEEE
- 100 degF 10 120 deg F
- l4OdegF
- l6OdegF r r---- r------ r--- r---
---7----- r- r- r -r r -r r --i - r-- -r- I I r r r 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 2S Time alter Shutdown (days)
UNIT 1
(_ 100/022 Encos, - - Section 2.1O.tD Loss of Decay Heat Removal with Water Level 9?t Above Hot Leg Centerline (After Reload) 2 -c 0 0 C) C C) S 1.5 H___ H 0.5 lOOdegF
//__-_ -- l2OdegF
-7/ - -
NOTE: For expanded resolution of these 160 deg F curves, refer to 2.10.1.D(1). 0 n 10 20 30 40 50 60 Time after Shutdown (days) UNIT 1
1T1 C 1VO/O2 Enclos ection2.10,1,D(1) Loss of Decay Heat Removal with Water Level 9 Above Hot Leg Centerline (After Reload) 70 60 -- t------ 50 C 1 I 40 C) C I I 0 i_t 0 a-) 30 1____ 20
/7 - - -
120 deg F 10 J/7/* t! - - - l6OdegF 0 T____ 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 Time after Shutdown (days) UNIT 1
IT1 EnclosL 3-Section2.1O,1.E Loss of Decay Heat Removal with Water Level 60 Above Hot Leg Centerline (After Reload) 2.5
.i 2
(I) C) C 0 0 a) 1 zZ 0.5 lOOdegF l2OdegF
/ .
- NOTE: For expanded resoution of these curves, refer to 2,1O.1.E(1).
l4OdegF 160 degF 0 0 10 20 30 40 50 60 70 Time after Shutdown (days) UNIT 1
91T I (%Jd 1GO/ø22. Ericic dction 2.1O.1.E(1) Loss of Decay Heat Removal with Water Level 60 Above Hot Leg Centerline (After Reload) 90 I* 4 80 -- L_ 1 70 --------- f___ - 60 I I I [ E 50 C 0 _-_t_i---i 2 40 H 30 El IZEZ EZ I 20 I _ZJ___._ lOOdegF I 1I
,.-- 120deF j /
l4OdegF 10
- .H 160degF 0 .
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 2.3 24 25 Time after Shutdown (days) UMT I
Ti op. Enclosure +.3 Section 2.1O,1.F Loss of Decay Heat Removal with Water Level 84 Above Hot Leg Centerline (After Reload) 3 NOTE: IF upper internals are instaed and level is >1= 84, these curves apply. 2.5 (I) 2 .L_____
- 0) I C
0 1 .5 L J-0 a ci) 2 ft 0 0 0 I 10Odeg l2OdegF 0.5 - l4OdegF NOTE: For expanded resolution of these
- - - l6OdegF curves, refer to 2.10.1.F(1).
I 0 10 20 30 40 50 60 70 Time after Shutdown (days) UNIT 1
Op IO22 Enclosure Section 2.1O.1.F(1) Loss of Decay Heat Removal with Water Level 84 Above Hot Leg Centerline (After Reload) 100 90 NOTE: IF upper internals are installed and level is >1= 84, these cues apply. 80 Eiz::::::p::r:z: z 70 I C S 60 C 0 50 0 G) S 40 I-30 f 120 deg F 20 . -
- /
l4OdegF I
, - l6OdegF zz 10 0
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 2324 25 Time after Shutdown (days) UNIT 1
UNIT 1* Page 1 of 3 OPI1IAI6I 00122 ENCLOSURE 4.3 SECTION 2.10.2 THERMAL MARGIN CURVES WITH UPPER INTERNALS REMOVED AND FULL REFUELING CAVITY LEVEL
Purpose:
The thermal margin curves presented in section 2.10.2 are to be used in assessing time to core boiling for loss of decay heat removal capabilities with the refueling cavity filled and upper internals removed. The requirements of Refueling Integrity do not necessarily meet the requirements of Containment Closure as a functional barrier against effluent release (as required per NSD 403, NUMARC 9 1-06 and NTJREG 1447). Use of the Curves: These curves are documented in DPC-1552.08-00-0014, Rev. 6, Loss of Decay Heat Removal. This calculation is based upon the decay heat generated by cores operated at 100% power for nominally 505 continuous days. The decay heat values used should be reevaluated for continuous 100% power operation extending beyond 525 days. The user should he aware that the information presented in these curves should be used in conjunction with the information in Section 2.10.4 to ensure adequate contingency planning to mitigate core boiling. With the upper internals removed, any loss of decay heat removal will result in establishing a natural convective heat transfer circuit in the cavity with hours to core boiling (if shutdown a minimum of 2 days). The curves contained in this section contain information on time to core boiling following a complete loss of decay heat removal capability based on a full refueling cavity and the assumption of full convective heat transfer (i.e., upper internals removed). UNIT 1
UNIT 1 Page 2of 3 OPFIIN6100/22 ENCLOSURE 4.3 SECTION 2.10.2 Detailed Discussion of Development and Application of Section 2.10.2 Section 2.10.2 contains thermal margin curves for full refueling cavity level based on time to boil verses time after shutdown for pre-refueling and post refueling config urations. This section has been reformatted to include the purpose of the curves and guidance on the use of the curves. In the Purpose section, this set of curves is defined to be applicable at times the Reactor Coolant system is not intact, the upper internals are removed, and the refueling cavity is at full level. In the Initial Conditions section of 2.10.2, the provision is included stating that prior to shutdown, 100% power operation was achieved for a minimum of one week. In the event a unit is shutdown after operating for a period less than one week and a less conser vative thermal margin determination is required, Primary System Engineering should be contacted to determine the changes in the heat load assumptions for the thermal margin determination UNIT1
UNIT 1
- Paga3.of 3 OP1IIA16 100/22 ENCLOSURE 4.3 SECTION 2J0.2 I. Initial Conditions A. 100% power operation (for a minimum of one week
) prior to shutdown.
B. Complete Loss of Decay Heat Removal Capability C. No mitigative actions are taken. II. Assumptions and Conservatisms A. The RCS is depressurized and open to the Reactor Building atmosphere. B. Water in the lower plenum, the downcomer, the barre l-baffle region, the hot legs, and the cold legs are assumed to be thermally isolated from the core region during the heatup to saturation. Therefore, the volume of water used to deter mine when the core region reaches saturation consists of the water in and above the active fuel (inside the core barrel but excluding the barrel-baffle region) up to full cavit y level. D. Perfect mixing is assumed to occur in the regions bein g heated to saturation. Therefore, all of the heated water is assumed to reach saturation at the same time. E. Water volumes in geometrically complex regions are minimized for conservative results. F. The heating of the reactor vessel internal structures is neglected as an additional conservatism. G. The effect of the elevation head in the RCS in raising the saturation temperature is considered. H. Decay heat and core volumes are referenced from the applicable revison of DPC- 1552.08-00-0014. Ill. References A. DPC-1552.08-00-0014, Loss of Decay Heat Removal B. DPC-1552.08-00-0051, Decay Heat for Mark-EW and OFA Fuel Types C. DPC-155208-00-0089, Time Required After Shut down Before Entering Mid-Loop Operation UNIT 1
4 Enclosure p.3 Section 2,1O.2.A Loss of Decay Heat Removal with Refueling Canal Filled and Upper Internals Removed (Prior to Offload) 25 20 U, 15 0 0 io Z -- 5 ZZJ l6OdegF 0 0 10 20 30 40 50 60 70 Time after Shutdown (days) UNIT I
-I Enclosure -3 Section 2,1O.2.B Loss of Decay Heat Removal with Refueling Cavity Filled and Upper Internals Removed (After Reload) 40 35 30 1.
25 3 20 0 4-a C) 2 15 F-10 5 0 0 10 20 30 40 50 60 70 Time after Shutdown (days) UNIT I
UNIT I
- Page.lof 3.
OP/i /N61 00/22 ENCLOSURE 4.3 SECTION 2.10.3 THERMAL MARGIN DETERMINATION NORMAL CONDITIONS FOR LOSS OF DECAY HEAT The following special conditions ensure that thermal margin can be determined for most conditions encountered during normal outage evolutions. These conditions assume a Loops Filled Condition, utilizing the water on the secondary side of the steam generators as a heat sink to establish natural circulation. A given for these cases is that the NC System [NCSJ is filled and vented and either intact or capable of being made intact by remote means. The expected conditions are as follows: Section Time Since Entry into Steam Generators Steam Generator Level Mode 3 Available 2.10.3.A 3 hours 4 42% NR 2.1O.3.B 18 hours 2 68% WR 2.10.3.C 40 hours > I () 42% NR (*) Note: A single SG does not meet the Tech Spec requirements for redundancy; this information is presented to aid in contingency planning. When it is desired to take credit for thermal margin provided by the secondary heat sink capability of the Steam Generators and all four NC Pumps are off, the A, B and/or D Steam Generators must be used in lieu of the C Steam Generator (if an NC Pump is on, there is sufficient flow to prevent void formation in the C Steam Generator U-tubes). The residual heat removal system takes suction off the C hot leg. Nitrogen tends to come out of solution, due to solubility changes as flow passes upwards through the core. The pressure drop across the core coupled with temperature increases can lead to significant changes in the solubility of Nitrogen in the NCS. During shutdown conditions (with fuel in the vessel) the C hot leg is the flow path for all core flow exiting the outlet plenum. This flow path, coupled with the solubility changes for the NCS may sweep non-condensable gases (Nitrogen) into the C leg, leading to voiding in the C Steam Generator U-tubes. Refer to PIP M-04-05 113. UNIT I
UNIT I Page2of3 OP/i 1N6 100/22 ENCLOSURE 4.3 SECTION 2.10.3 Discussion of Loops Filled and Loops Not Filled Conditions The inability to make the NCS intact remotely (ie. closing the PORVs or the associated block valves from the control room) or the NCS level less than 20% Pressurizer Cold Calibration level defines the condition known as Loops Not Filled. For a refueling outage, Operations usually begins draindown of the reactor coolant system by pulling a code safety from the Pressurizer, draining the NCS while opening head vent valves and pulling the head spool piece to vent the NCS to atmosphere to assist in the drain. Once the safety is pulled, the NCS is no longer intact and NCS is considered Loops Not Filled due to the inability to pressurize the NCS. If the safety is not pulled, however, the head vents andlor the spool piece are pulled, the NCS is also considered Loops Not Filled due to the presence of non-condensable gases in the NCS. In this case, the NCS may be capable of some pressurization, however the presence of non-condensable gases may lead to voids in the Steam Generator U-tubes such that natural circulation cannot be established. In order to meet the Loops Filled condition, the U-tubes of the Steam Generators must be filled with liquid or condensable gases (steam) and the NCS must be capable of pressurization (to the LTOP setpoint). This ensures that proper conditions are in place to establish natural circulation in the NCS, using the heat transfer to the secondary side of the Steam Generators for decay heat removal. If the unit has existed in a Loops Not Filled condition such that non-condensable gases are present in the NCS, it is essential that the NCS be filled and vented (with water available to the secondary side of the Steam Generators) prior to taking credit for decay heat removal capability (thermal margin) via the secondary heat sink. This ensures that the U-tubes of the Steam Generators are filled and capable of establishing a natural convective circuit with the heat source (core) at a lower elevation than the heat sink (the Steam Generators). The level requirements referenced in this procedure for maintaining the Loops Filled condition is 20% Pressurizer Cold Calibration level or OAC Corrected Pressurizer Level (this is in addition to the requirement to make the NCS intact remotely). It is recognized that during an initial drain, with the NCS able to be made intact, that the Steam Generator U-tubes will remain filled even with partial draining of the Reactor Vessel due to siphoning at the lower pressure, higher elevation of the U-tubes. However, it is extremely unlikely that the NCS would be drained to below 20% Pressurizer Cold Calibration Level without opening a large vent path that cannot readily be isolated. Since these curves have been developed to support normal evolutions, a requirement of 20% Pressurizer Cold Calibration level is acceptable. UNIT I
UNIT I Page3-of3 OPI1/A161 00/22 ENCLOSURE 4.3 SECTION 2.10.3 During a normal outage evolution, fill and vent includes filling to 80% Pressurizer Level followed by system heatup and pressurization. During these evolutions, the Loops Filled condition will not be applied until the NCS is at 80% Pressurizer Level, filled and vented. Detailed Discussion of Development and Application of Section 2.10.3 Section 2.10.3 .A provides information on thermal margin available for the condition of Loops Filled with four Steam Generators available at > 42% narrow ranges level. Meeting the conditions of section 2.l0.3.B is preferred over 2.10.3.A due to the higher probability of non-condensable gases (steam) in the C Steam Generator (see previous discussion). The NCS initial temperature of 350*F is supported by DPC-1552.08 0014, Loss ofDecay I-feat Removal, Attachment 1. The elimination of the requirement to have the safeties installed was replaced with a requirement to have the NCS intact or capable of being made intact to ensure that any work to the PORV block valves, Reactor Vessel Head vent valves or pulling of the spool piece are also evaluated as having an impact on NCS pressurization capabilities. The time requirements since entering Mode 3 of three hours is supported by DPC-1552.08-00-0014, Loss ofDecay Heat Removal, . As referenced in the previous paragraph, the references to a minimum of 2 hours of thermal margin is due to Work Control administrative requirements. The actual thermal margin available is directly proportional to the makeup capability to the Steam Generators. Section 2.10.3.B provides information on thermal margin available for the condition of Loops Filled with two Steam Generators available at> 68% wide range level. The A, B and/or D Steam Generators must be used in lieu of the C Steam Generator (see previous). In this condition, thermal margin can be sustained for a minimum of 2 hours. Therefore, the thermal margin is recorded as greater than or equal to 2 hours via Work Control procedures defining thermal margin. The actual thermal margin available is directly proportional to the makeup capability to the Steam Generators. If there is no makeup capability to the generators, the thermal margin is > 2 hours. If there are redundant means of makeup capability to the generators (this includes redundant sources and available power and equipment) then the thermal margin is>> 2 hours. Section 2.l0.3.C addresses information on thermal margin available for the condition of Loops Filled with one Steam Generator available at> 42% narrow ranges level. This information is presented to aid in contingency planning, but does NOT meet the Tech Spec requirements for redundancy. UNIT I
uI111 -I OP/i /A/6i 00/22 EQLOSURE 43 SECTION: 2.10.3.A THERMAL MARGIN FOR LOOPS FILLED CONDITION WITH 4 STEAM GENERATORS The minimum time to boiling is at least 2 hours, provided:
- 1) Greater than 3 hours have elapsed since entry into Mode 3.
- 2) NC System temperature is less than 350°F.
- 3) A maximum of 4 NC pumps are in operation.
I) NC System level is greater than or equal to 20% pressurizer cold cal level or greater than or equal to 20% corrected pressurizer level.
- 3) The NCS is intact or capable of being made intact.
- 4) Capability to steam through four Steam Generator PORVs, with all S/G levels at 42% narrow range.
- 5) Pressurizer PORVs or block valves closed (or ability to close remote ly from the control room) and at least one PORV capable of LTOP Mode of Operation.
Discussion: The NC System is capable of natural circulation due to the heat source (the core) being physically lower than the heat sink (the steam generators), assuming that the NC system is intact. Natural circulation is that flow generated by the density differe nce between the NC hot leg and cooled cold return leg from the steam generator, which provides the motive force for NC flow. For the conditions presented here, the heat generated by the core can be dissipated by the conversion of secondary fluid from fluid to vapor at a rate of 870 BTU/lbm. Given an intact NC System with the ability to pressurize, and a secondary system volum e of 4 Steam Generators at 42% narrow range level, the core heat can be dissipated for greater than 2.5 hours prior to boiling the generators dry. Ref: 1. DPC-1552.08-00-0014, Loss of Decay Heat Removal, Attachment 1.
- 2. EPRI TR-l02969, Contingency Strategies for Diablo Canyon During Potential Shutdown Operation Events.
- 3. MCC-1210.04-00-0066, Replacement Steam Generators Wide Range Level indication Uncertainty (1 and 2 CPLP561O, 5620, 5630 and 5640)
UNIT 1
UNIT 1. OPI1/A/61 00/22 ENCLOSURE 4.3 SECTION 2.iO.3.B THERMAL MARGIN FOR LOOPS FILLED CONDITI ON WITH 2 STEAM GENERATORS The minimum time to boiling is at least 2 hours, provid ed:
- 1) Greater than 18 hours have elapsed since entry into Mode 3.
- 2) NC System temperature is less than 250°F.
- 3) A maximum of 2 NC pumps are in operation.
- 4) NC System level is greater than or equal to 20% pressurizer cold cal level or greater than or equal to 20% corrected pressurizer level.
- 5) The NC System is intact or capable of being made intact.
- 6) Capability to steam through at least two Steam Generator PORVs, with both S/G levels at 68% wide range. (A, B andlor D Steam Generator preferred)
- 7) Pressurizer PORVs or block valves closed (or ability to close remotely fromthe control room) and at least one PORV capable of LTOP Mode of Operation.
Discussion: The NC System is capable of natural circulation due to the heat source (the core) being physically lower than the heat sink (the steam generators), assuming that the NC system is intact. Natural circulation is that flow generated by the density difference between the NC hot leg and cooled cold return leg from the steam generator, which provid es the motive force for NC flow. See Section 2.10.3 for discussion of C Steam Generator voidin g concerns. UNIT 1
UNIT I OPttfA/61OO/22 ENCLOSURE 4.3 SECTION 2.1O.3.C TI-IERMAL MARGiN FOR LOOPS FILLED CONDITION WITH 1 STEAM GENERATORS Note: A single SG does not meet the Tech Spec requirements for redundancy; this information is presented to aid in contingency planning. The minimum time to boiling is at least 2 hours, provided:
- 1) Greater than 40 hours have elapsed since entry into Mode 3.
- 2) NC System temperature is less than 200°F.
- 3) A maximum of 1 NC pump is in operation.
- 4) NC System level is greater than or equal to 20% pressurizer cold cal level or greater than or equal to 20% corrected pressurizer level.
- 5) The NC System is intact or capable of being made intact.
- 6) Capability to steam through at least one Steam Generator PORVs, with S/G level at
? 42% narrow range. (A, B or D Steam Generator required)
- 7) Pressurizer PORVs or block valves closed (or ability to close remotely from the control room) and at least one PORV capable of LTOP Mode of Operation.
- 8) Redundant means of makeup inventory available to the Steam Generators (including redundant power supply).
Discussion: The NC system is capable of natural circulation due to the heat source (the core) being physically lower than the heat sink (the steam generators), assuming that the NC system be intact. Natural circulation is that flow generated by the density difference between the NC hot leg and cooled cold return leg from the steam generator, which provides the motive force for NC flow. For the conditions presented here, greater than 2 hours of thermal margin is available via the secondary heat sink provided makeup capability is maintained to the Steam Generators. See Section 2.103 for discussion ofC Steam Generator voiding concerns. Ref: I. EPRI TR-102969, Contingency Strategies for Diablo Canyon During Potential Shutdown Operation Events. UNIT I
I lof2 Aio100122 ENLOSURE4.3 SECTION 2.10,4 Core Flow Required to Prevent Boiling for Loss of Decay Heat Removal 1800 1600 1400 2 1200 800 600 400 200 0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65,0 70.0 75.0 Time After Shutdown (days) UNIT I
UNIT I Page 2 of 2
- OP/11N610Q122.
ENCLOSURE 4.3 SECTION 2.10.4 Detailed Discussion of Development and Application of Section 2.10.4 Section 2.10.4 contains a graph of Core Flow Required tu Prevent Boiling for Loss of Decay Heat Removal. The supporting calculations for this graph are in DPC- 1552.08 0143, Upper Internals Spray Nozzle Flow Capability During A Loss ofDecay Heat Removal Event. Detailed calculations to determine the point at which required core flow to prevent boiling can be met by the circulation available through the upper internal nozzles have not been developed. Therefore, the thermal margin values in 2.10.2 are non-conservative when the upper internals are installed, and thus do not apply. For conservatism, anytime upper internals are installed, no credit can be taken for water level greater than 84, and the appropriate curves from Section 2.10.1 should be used. The results presented in the thermal margin curves for section 2.10.1 are not affected by this analysis. However, the presence of the upper internals coupled with the heat loads at times near shutdown may lead to localized core voiding. If decay heat removal capability (forced flow) were lost, the limited flow past the upper internals nozzles (with the normal configuration of a vented RCS) could lead to rapid voiding in the top of the core even with water level above the upper internals. In addition, the core flow requirements for mitigation of core boiling are based on forced flow required to dissipate decay heat with no allowances for recovery of core volume. The flow requirement presented in the graph are valid for mitigation of boiling for a pre-refueling core. This information should be used in conjunction with 2.10.1 and 2.10.2 to ensure appropriate contingencies are planned to mitigate core boiling in the event of a loss of decay heat removal capability. For AP/EP use: I. This curve specfically addresses the condition of a vented reactor coolant system.
- 2. The makeup flow to the NC system is assumed to be at 140 °F
- 3. To ensure adequate makeup flowfor inlet temperatures approaching saturation, multiply the flow requirements of this graph by 1.10.
- 4. This curve assumes atmospheric pressure, any application for RCS pressures> 14. 7psig could result in a non-conservative flowrate.
- 5. SAMG Calculation Aids requirements for makeup flow may also be helpfuL
References:
- 1. DPC-1552.08-0O-0143, Uppei-fnternals Spray Nozzle Flow Capabiliy DuringA Loss of Decay Heat Removal Event
- 2. WOG DW-95-23 UNIT I
(P/1 61OO/22 URE 4.3
..TION2.1O.5 Time Required after Shutdown before Entering Midloop Operations to Ensure 2.5 Hours to Fuel Damage for Loss of Decay Heat Removal 7
6 5 S 2 0 0 50 100 150 200 250 300 350 400 450 Operating Days UNIT 1
1of5 I 0 ENCLOSURE 4.3 SECTION 2.10.6 Boiloff Makeup Rate for Vented RCS at Nominal FWST Temp 350 300 250 E 0 200 0 150 C 0 100 50 0 0 0.2 0.4 0,6 0.8 1 1.2 1.4 1,6 1.8 2 Days Shutdown UNIT I
ITI e2of5 r/1 iAJ6l 00/022 ENCLOSURE 4.3 SECTION 2.10.6 Boiloff Makeup Rate for Vented RCS at Nominal FWST Temp 200 180 160 140 zz:zz:zz:z:,., E 120 SEe iscus lo SE cti )n or Cu ie ba s D 100 4-9 0 0 60 --- ew490 40 20 0 0 4 8 12 16 I 20 I 24 i [ i I - I I 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 9.6 101 Days Shutdown UNIT I
I 30f5 C A.,00/022 ENCLOSURE 4.3 SECTION 2.10,6 Boiloff Makeup Rate for RCS at 200 psig assuming Makeup Flow at 350 deg F 450 400 350 \ 300 S di cussior sectio for curve basi; 250 200 0 150 100 ______ 50 a Pre OffIod w (200psig at 35OdegF) Post Reload w (200psig at 35OdegF) 1 I I J I 0 , 0 0.2 0.4 0.6 0.8 1 1.2 1.4 1.6 1.8 2 Days Shutdown UNIT I
I 4of5 ( Ai0OIO22 ENCLOSURE 4,3 SECTION 2.10.6 Boiloff Makeup Rate for Vented RCS assuming Makeup Flow at 200 deg F 200 180 160 140 S 80 60 40 20 0 0 4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 Days Shutdown UNIT I
UNIT I Page5of5 OPI-t/N6100f022 ENCLOSURE 4.3 SECTION 2.10.6 Detailed Discussion of Development and Application of Section 2.10.6 Section 2.10.6 contains a graph of Boiloff Makeup Rate Requirements for varied Reactor Coolant System pressures and inlet flow temperatures. These graphs were developed to provide a minimum flow rate requirement to ensure that the core remains covered and the fuel protected from damage if the core conditions reach saturation. The supporting calculations for these graphs are in DPC-1552.08-00-0023, Loss of Decay Heat Removal (GL. 88-17). These curves show the boiloff makeup flow requirements for pre and post refueling. This calculation was issued in response to Generic Letter 88-17 which required containment closure in the form of a functional fission product barrier for shutdown risk evolutions prior to the onset of core boiling. The original calculation methodology has been used for the current limiting core heat loads (see Section 2.10.1) to generate these curves. This analysis is conservative in that it assumes a constant heat generation rate, and water volumes in geometrically complex regions are minimized. For AP/EP use:
- 1. The makeup flow temperature to the NC system is stated on the graph.
- 2. The NCS is assumed to be at a pressure as defined on the graph.
- 3. WOG D W-95-23 discusses possible non-conservatism associated with assuming atmospheric pressure for the NCS. The graphs presented here are maximum and nominal shutdown requirements. The maximum requirements should be used if the scenario in question is between the nominal and maximum flow requirements.
- 4. If the NCS is pressurized beyond the predictions of these curves, the flow requirements may be non-conservative by a factor of 2.
- 5. SAMG Calculation Aids for make up flow may also be helpful.
References:
- 1. DPC-1552.08-00-0023, Loss of Decay Heat Removal (G.L. 88-17)
- 2. WOG DW-95-23
- 3. MCC-1223.03-00-0045, Reactor Coolant System Boiloff Makeup UNIT 1
.T
,AIbl 00/22 Enclosure 4.3 Section 2,10.7 Time to Core Uncovery for Loss of Decay Heat Removal 10.00 9.00 8.00 7 00 6.00 0
5.00 U) 4.00 E I- 3.00 2.00 1.00 0.00 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 Time to Core Uncovery (hrs) UNIT I
UNrE 1 0P121A16 100/22 ENCLOSURE 4.3 SECTION 2.10.8 Detailed Discussion of Development and Application of Section 2.10.8 Section 2.10.8 contains a graph displaying the Time for the Spent Fuel Pool to Boil following Complete Loss of KF Cooling for various times after shutdown and initial Spent Fuel Pool Temperatures. This graph was developed to enable operators to quickly determine an approximate and conservative Spent Fuel Pool time to boil based on real time SEP temperatures. The supporting calculation for this graph is MCC-1223.20 0017, Spent Fuel Pool Time to Boil Following Complete Loss of Cooling. This graph shows the time to boil following a full core offload with respect to time after reactor shutdown assuming no makeup to the Spent Fuel Pool occurs. The calculation was issued in order to give Operations a nominal time to boil following a complete loss of cooling. The calculation for the curve was conservatively created such that it is non-unit and non outage specific. A 3% conservatism factor was added to maximum fuel pool heat load such that the heat load for the first 5.1 days following subcritical was assumed to be greater than the UFSAR requirement of 42.2 x 106 BTU/hr.
References:
- 1. MCC-1223.20-00-0017, Spent Fuel Pool Time to Boil Following Complete Loss of Cooling
- 2. UFSAR Table 9-5, Peak Heat Loads and Pool Temperature for the McGuire Units I & 2 Spent Fuel Pools
- 3. MCC-1201.30-0O-0009, Two Region Storage Rack Expanded Heat Load UNIT 1
IT 1
/iiAJ6100/022 Enclosure 4.3 Section 2.10.8 Time for Spent Fuel Pool to Boil following Complete Loss of KF Cooling 18.0 16.0 14.0 z
0 12.0 0 0 .1 10.0 E 8.0 6.0 4.0 4 7 10 13 16 19 22 25 28 Time Since Shutdown (Days) UNIT 1
UNIT 1 OP/11N6100/22 ENCLOSURE 4:3 SECTION 2.10.9 SINGLE TRAIN RHR HEAT REJECTION CAPABIIJTY PROJECTIONS Note: The following information is provided to aid in evaluating shutdown risk (primarily of a regulatory nature). If Mode 5 is entered prior to allowing time for decay heat load to reduce to a level that can be rejected by a single RI-ER train, then loss of heat rejection may result in an inadvertent heatup and return to Mode 4. Discussion: The following graph was derived by matching the projected time-dependent decay heat load (from a core having operated continuously for nominally 505 EFPDs) to the heat rejection capability of an NDHX being cooled by varying support sytem flowrates and lake tempertures. No heat input from reactor coolant pumps was reflected in the curves, and no heat rejection via condenser dumps was credited. By evaluating current (or projected) lake temperatures as given by suction header temps for in-service RN trains, the corresponding time after shutdown at which a single ND train will be capable of maintining Mode 5 conditions can be determined. Three sets of conditions are displayed by the capability projection curves:
- 1) Limiting Case analysis used system operating conditions:
RN Flowrate to KC Heat Exchanger: 5500 gpm KC Flowrate to ND Heat Exchanger: 4800 gpm ND Tubeside Flowrate: 3800 gpm
- 2) Nominal Case analysis used system operating conditions:
RN Flowrate to KC Heat Exchanger: 6500 gpm KC Flowrate to ND Heat Exchanger: 5000 gpm ND Tubeside Flowrate: 3800 gpm
- 3) Enhanced Case analysis used system operating conditions:
RN Flowrate to KC Heat Exchanger: 7000 gpm KC Flowrate to ND Heat Exchanger: 6000 gpm ND Tubeside Flowrate: 4000 gpm All three cases used the following inputs: RN Fouling: 0.004 hr-ft
-°F/BTU; KC Fouling: 0.001 hr-ft 2 -°FIBTU 2
ND Fouling: 0.0003 hr-ft
-°F/BTU; Tubes Plugged: KCHX 200, NDHX 0 2 -
NC inlet temperature: 200°F (Mode 4 transition definition) In order to ensure NC subcooling margin and RHR redundancy, depressurizing the NC system should NOT be considered prior to ensuring that sufficient time has passed so that decay heat load can be rejected by operation of a single RHR train. Ref: MCC-l223.l 1-00-0037, Mode 5 Entry Time versus Heat Rejection Capability with a Single Operable Train of ND UNIT 1
OP/i /A61 00/22 Encbsure 4.3; Section 2.10.9 ND Heat Transfer Capability Performance Projections 24.00 23.00 22,00 21.00 20.00 19.00 I 18.00 C 17.00 0 16.00 .C 15.00 (.1) 14.00 C.) C 13.00 12.00 11.00 10.00 9.00 8.00 7.00 6,00 45 50 55 60 65 70 75 80 Lake Temp [deg F] Limiting Case System Conditions: RN-to-KC = 5500 gpm; KC-toND = 4800 gpm; ND flow = 3800 gpm Nominal Case System Conditions: RN-to-KC = 6500 gpm; KC-to-ND = 5000 gpm; ND flow = 3800 gpm Enhanced Case System Conditions: RN-to-KC = 7000 gpm; KC-to-ND = 6000 gpm; ND flow = 4000 gpm UNIT 1
5 cj gL Uniti OP/i 11100/022 ENCLOSURE 4.3 TABLE 2.11 REVISED T-HOT AVERAGE SCALING (RTAS) AND CURRENT 100% POWER DELTA-Ts REVISED T-HOT AVERAGE SCALING WEIGHTING CONFIGURATION LOOP A LOOP B LOOP C LOOP D T-HOTA1 WEIGHT 0.20 0.20 0.30 0.20 T-HOT A2 WEIGHT 0.20 0.60 0.20 0.60 T-HOT A3 WEIGHT 0.60 0.20 0.50 0.20 DELTA-Ts wi ja WIIItL LOOP A LOOP B LOOP C LOOP D CURRENT 100% POWER UN-WEIGHTED DELTA-Ts 58.22 °F 58.18 °F 58.21 °F 57.44 °F CURRENT 100% POWER WEIGHTED DELTA-is 59.59 °F 58.93 °F 58.94 °F 58.73 °F CURRENT 7300 DELT-T GAINS* 1.343 VN 1.358 VN 1.357 V/V 1 .362VN 7300 Delt-T Gains are derived from weighted 100% Power Delta-Ts if weighting is applicable. Recorded by) 1/1.1)11
Appendix C Job Performance Measure Form ES-C-i WrkMeet JPMA3SRO 2011 Admin JPM A3 SRO (Rev_041111)
- NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-i
- Job Performance Measure Worksheet -
Facility: McGuire Task No.: Task
Title:
Take On-Site Protective Actions JPM No.: Exam 2011 Admin - During a General Emergency JPM A3 SRO K/A
Reference:
GK/A 2.3.4 (3.7) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant 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:
- With Unit I shutting down due to failed fuel causing high NC System Activity, a LOCA Outside of Containment occurred.
- A Site Assembly is in progress in accordance with Enclosure 4.3 of RP/0/A15700/01 i (Conducting a Site Assembly, Site Evacuation or Containment Evacuation), and all personnel have NOT been accounted for.
- An RP Technician reports that an operator working with him in the 695 pipe chase has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.
- The OSM has initiated and completed the immediate and subsequent actions of Enclosure 4.1 of RP/0/A15700/004 (General Emergency).
- RP has been contacted and estimates it will take at least ten minutes to retrieve the victim. Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.
- Dose rates at the area needing access are greater than 500 Rem/Hr.
Task Standard: Select and dispatch two rescuers (Smith and Shelly) by completing Enclosure 4.4 of RP/0/A/5700/004 (General Emergency). 2011 Admin-JPMA3SRO NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-i Jb rfrmarie Measure Worksheet Required Materials: Calculator General
References:
RP101A157001004 (General Emergency), Rev 25 RPIOIAI5700IO1 1 (Conducting a Site Assembly, Site Evacuation or Containment Evacuation), Rev 14 RP101A15700129, RPIO/A15700129 (Notification of Off-Site Agencies From the Control Room), Rev 10 OMP 2-2 (Conduct of Operations), Rev 54 Handouts: RP101A157001004, General Emergency, marked up as follows:
- Section 2 immediate actions are complete.
- Enclosure 4.1 actions are complete.
- Section 3 subsequent actions complete through Step 3.8.1.
List of Available Rescuers Initiating Cue: As the OSM, evaluate, and take on-site Protective Actions in accordance with Step 3.8.2 and 3.8.3 of RP/0/A15700/004 (General Emergency). Time Critical Task: NO Validation Time: 15 minutes 2011 Admin JPM A3 SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE1NFORMATION (Denote Critical Steps with an asterisk*) Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout: RP101A157001004 marked up as described, and the List of Available Rescuers. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (RPO4/Step 3.8.2) IF a The operator recognizes situation is immediately from initial conditions that hazardous to life or valuable Dose rates at the area property exists, evaluate needing access is greater potential dose rates by one than 500 Rem/Hr. of the following methods: (Step 3.8.2.a) Contact RP Shift at Ext. 4282. 2 (Step 3.8.2.b) Assess area The operator recognizes monitors. from initial conditions that Dose rates at the area needing access is greater than 500 Rem/Hr. The operator determines that rescuers will need to be authorized to receive Emergency Exposure Dose Limits. 3 (Step 3.8.3) Complete The operator reviews List of Enclosure 4.4 (Request for Available Rescuers in Emergency Exposure), prior Control Room and to dispatch of emergency determines qualification of workers if emergency potential rescuers. situation precludes documentation. 4 (Enclosure 4.4.a) The operator determines Request for Emergency that Casey cannot be Exposure dispatched as a rescuer (Declared pregnancy) 2011 Admin JPM A3 SRO
- NUREG 1021, Revision 9
Appendix C Page 5 of 9 Form ES-C-I PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 (Enclosure 4.4.c) Only on a Operator determines that volunteer basis to persons Blade cannot be dispatched fully aware of the risks as a rescuer (Does NOT involved. All factors being Volunteer). equal, select volunteers above the age of 45 and Operator determines that those who normally receive Mack cannot be dispatched little exposure. as a rescuer (Has too much Lifetime Exposure). Operator determines that Leavy cannot be dispatched as a rescuer (Only STA OMP 2-2 requires her in Control Room). Operator determines that Baylor cannot be dispatched as a rescuer (< 45 years Old). 6 (Enclosure 4.4) Request for Emergency Exposure The operator selects Smith and Shelly as rescuers, and completes Enclosure 4.4. The operator enters the following information on Enclosure 4.4 for Smith:
. RPBadge#-12579
. Name Smith
. Age52
. Employer Duke The operator enters the following information on Enclosure 4.4 for Shelly:
. RPBadge#-12456
. Name Shelly
. Age48
. Employer Duke 2011 Admin JPM A3 SRO
- NUREG 1021, Revision 9
Appendix C Page 6 of 9 Form ES-C-i PERFORMANCE INFORMATiON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT The operator has Smith (Contd) and Shelly Read and Sign Enclosure 4.4. Cue: After having selected rescuers sign Enclosure 4.4, indicate that each has signed. Cue: If Operator seeks concurrence from RPM for authorization of Emergency Exposure Limits, indicate RPM Bob Smith has concurred. The operator signs Enclosure 4.4 indicating that they approve the Emergency Exposure Authorization. Terminating Cue: Evaluation on this JPM is complete. STOP TIME: 2011 Admin JPM A3 SRO
- NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-i VERIFICATION OF COMPLETiON Job Performance Measure No.: 2011 Admin JPM A3 SRO Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin-JPMA3SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMCUESHEET - List of Available Rescuers in Control Room: RP Name Gender! Job Employer Current Lifetime Special Status Badge Age Assignment Exposure Exposure
# (yr)
Would prefer not to 12345 Blade Male! Maintenance Duke 1800 mr 5.2 R go! Reports good 49 physical health 12456 Shelly Female! Engineer Duke 45 mr 400 mr Volunteers! Reports 48 good physical health 12567 Mack Male NEC Duke 125 mr 35.4 R Volunteers! Reports
/45 good physical health 12579 Smith Male! Training Duke 6 mr 1400 mr Volunteers!Reports 52 Supervisor good physical health 12110 Casey Female! Security Duke 10 mr 65 mr Declared 32 Supervisor PregnantNolunteers!
Reports good physical health 12238 Leavy Female! STA Duke 4 mr 120 mr Volunteers!Only STA 46 qualified individual in Control Room! Reports good physical health. 12198 Baylor Male! U2 BOP Duke 78 mr 1.7 R Volunteers! Reports 34 good physical health NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMCUE SHEET INITIAL CONDITIONS:
- With Unit I shutting down due to failed fuel causing high NC System Activity, a LOCA Outside of Containment occurred.
- A Site Assembly is in progress in accordance with Enclosure 4.3 of RPIOIAI5700IO1 I (Conducting a Site Assembly, Site Evacuation or Containment Evacuation), and all personnel have NOT been accounted for.
- An RP Technician reports that an operator working with him in the 695 pipe chase has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.
- The OSM has initiated and completed the immediate and subsequent actions of Enclosure 4.1 of RPIOIA/57001004 (General Emergency).
- RP has been contacted and estimates it will take at least ten minutes to retrieve the victim. Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.
- Dose rates at the area needing access are greater than 500 Rem/Hr.
INITIATING CUE: As the OSM, evaluate, and take on-site Protective Actions in accordance with Step 3.8.2 and 3.8.3 of RP/0/A/5700/004 (General Emergency). NUREG 1021, Revision 9
Duke Energy Procedure No. McGuire Nuclear Station Rp/OIAIs700Ioo4 General Emergency Revision No. 025 Electronic Reference No. MC0048M7 Reference Use PERFORMANCE I UNCONTROLLED FOR PRINT * * * * * * * * * * (ISSUED) PDF Format
RPJOIA/s7QoIoo4 Page 2 of 5 General Emergency
- 1. Symptoms Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.
Immediate Actions NOTE: The Immediate Actions and part of the Subsequent Actions have been separated into position specific enclosures to enhance timely completion and consistent execution. The following Enclosures should be given to the appropriate personnel: The OSM should execute Enclosure 4.1 (OSM ediate and Subsequent Actions) in a timely maimer. The STA should execute Enclosure 4.2 (STA Immediate and Subsequent Actions) in a timely manner. 2.2 Have an SRO make offsite notifications PER RP/O/B/5700/029 (Notifications to Offsite Agencies from the Control Room).
RP/OJA/57U0J004 Page 3 of 5 Subsequent Actions r/ j7 Make initial and follow-up notifications according to the following criteria: Initial Notifications {G-07-0127}
- 1. Initial notifications to the State(s) and counties must be made within 15 minutes of the event declaration using the Emergency Notification form (ENF).
- 2. For an upgrade in classification prior to or while transmitting an initial message:
-The notification for the lesser emergency classification must be made within 15 minutes of the lesser classification declaration time.
-The agencies must be informed that an upgrade in classification will be coming.
-The upgraded classification message must be transmitted within 15 minutes of the upgraded classification declaration time.
Follow-up Notifications Follow-up notifications to the State(s) and Counties must be made according to the following schedule:
-For GE, every hour until the emergency is terminated.
OR
-If there is any significant change to the situation (make notification as soon as possible).
OR
-As agreed upon with an Emergency Management official from each individual agency. Documentation shall be maintained for any agreed upon schedule change. The interval for GE shall not be greater than 2 hours to any agency.
Follow-up messages in the General Emergency classification that involve an upgrade in PARs must be communicated to the offsite agencies as soon as possible and within 15 minutes. Ensure completion of Enclosure 4.3 (Emergency Coordinator Turnover Checklist) prior to turnover of Emergency Coordinator responsibilities.
p/O/i57oo/oo1. Page 4 of 5 NOTE: . An EOF Director preprogrammed fax button is available on the control room fax machine. TSC preprogrammed fax button is available on the Control Room fax machine. IF changes to the initial Protective Action Recommendations are recognized during the turnover, the turnover should not be completed until the Control Room transmits this notification to the offsite agencies. {PIP-M-0-00541 } IF the emergency situation prevents activating the TSC within 75 minutes of declaration, then turn over responsibility for classification and notification (state and county) to the EOF as follows:
- Fax a completed copy of Enclosure 4.3 to the EOF Director.
- Contact the EOF Director at 9-704-382-0760.
- Perform a turnover to the EOF Director using completed Enclosure 4.3.
AND Maintain responsibility for NRC Event Notification until relieved by the NRC Communicator in the TSC, AND Maintain responsibility for continuous phone communications to the NRC Operations Center until relieved by the NRC Communicator in the TSC. IF the TSC remains unavailable and the EOF cannot take responsibility for classification and notification (state and county), maintain these responsibilities until one of the facilities is capable of accepting turnover. WHEN TSC Emergency Coordinator is ready to receive turnover, perform one of the following to facilitate turnover: Hand deliver turnover sheet to the TSC Emergency Coordinator. OR Fax turnover sheet to the TSC. In the event that a workers behavior or actions contributed to an actual or potential substantial degradation of the level of safety of the plant (incidents resulting in an Alert or higher emergency declaration), the supervisor must consider and establish whether or not a for cause drug/alcohol screen is required. The FFD Program Administrator or designee is available to discuss/assist with the incident.
Ip/O/AI57ooIoo4 Page 5 of 5 Protective Actions Onsite Evacuate non-essential personnel from the site after all personnel have been accounted for via Site Assembly. REFER TO RPIO/A15700/O 11 (Conducting a Site Assembly, Site Evacuation or Containment Evacuation). 3.8.2 a situation which is immediately hazardous to life or valuable property exists, evaluate potential dose rates by one of the following methods:
- a. Contact RP Shift at Ext. 4282
- b. Assess area monitors 3.8.3 Complete Enclosure 4.4 (Request for Emergency Exposure), prior to dispatch of emergency workers if emergency situation precludes documentation.
3.9 Using Section D of the Emergency Plan (EAL Basis), assess the emergency condition: 3.9.1 Remain in a General Emergency, OR 3.9.2 Terminate the emergency, PER one of the following:
- RP/O/A15700/012 (Activation of the Technical Support Center {TSC}),
Enclosure 4.18, for termination criteria. OR
- SR/O/B/2000/003 (Activation of the Emergency Operations Facility),
Enclosure 4.5. 3.9.3 Termination Notifications Emergency Operations Facilities).
- 4. Enclosures 4.1 OSM Immediate and Subsequent Actions {PTP O-M97-4638}
4.2 STA Immediate and Subsequent Actions {PIP O-M97-40638} 4.3 Emergency Coordinator Turnover Checklist {PIP M-02-6113, C. A. 13} 4.4 Request for Emergency Exposure
Enclosure 4.1 /O/57oo/oo4 OSM Immediate and Subsequent Actions Page 1 of 2
- i. Immediate Actions 1.1 The Operations Shift Manager or designee shall announce the event over the plant P.A. system by performing the following:
LI 1.1.1 Turn on the outside page speakers. NOTE:
- For drill purposes, state This is a drill. This is a drill.
- Any plant phone in the Control Room horse shoe area or extension 4021 is programmed to access 710, site all call. {PIP 0-M98-2545}
1.1.2 IF a Security event is in progress and directed by Security that no movement on site is allowed, dial 710, pause, dial 80, and following the beep make the following announcement a General Emergency has been declared due to No movement on site is allowed. Remain in your assigned work locations. GO TO Step 1.1.4. LI 1.1.3 For all other events, Dial 710; pause, dial 80. Following the beep, announce a General Emergency has been declared due to Activate the TSC, OSC and EOF. El 1.1.4 Repeat the preceding announcement(s) one time. LI 1.1.5 Turn off the outside page speakers. 1.2 Ensure Protective Action Recommendations to the Offsite Agencies are made and transmitted within 15 minutes jj RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room), Enclosure 4.4 (Protective Action Recommendations). 1.3 changes to the initial Protective Action Recommendations are recognized and approved by the Emergency Coordinator, these changes shall be transmitted to the offsite agencies within 15 minutes. {PIP M-00-02l38} 1.4 valid trip II alarm occurs on any one of the following: 1 OR 2 EMF36(L) 1 EMF24, 25, 26, 27 2EMF1O, 11,12,13 Immediately contact RP shift at 4282 to perform HP/0/B/1009/029 (Initial Response On-Shift Dose Assessment). 1.5 IF B (IS OCCURRING) or C (HAS OCCURRED) on Line 6 (EMERGENCY RELEASE) of the Emergency Notification Form is checked, immediately contact RP shift at 4282 to perform HP/0/B/l 009/029 (Initial Response On-Shift Dose Assessment).
Enclosure 4.1 /O/A,57ooIoo4 OSM Immediate and Subsequent Actions Page 2 of 2
- 2. Subsequent Actions 2.1 WHEN the movement on site is allowed:
El 2.1.1 Turn on the outside page speakers. NOTE:
- For drill purposes, state This is a drill. This is a drill.
Any plant phone in the Control Room horse shoe area or extension 4021 is programmed to access 710, site all call. {PIP 0-M98-2545} El 2.1.2 Dial 710, pause, dial 80, and following the beep make the following announcement The Security Threat no longer exists, Activate the TSC, OSC and EOF. El 2.1.3 Repeat the preceding announcement one time. El 2.1.4 Turn off the outside page speakers. NOTE: Site Assembly is a required on-site protective action in response to an Alert or higher declaration. Site assembly for a Notification of Unusual Event is optional due to conditions and not expected as for an Alert or higher classification. 2.2 REFER TO RP/0/A!5700/01 1, (Conducting a Site Assembly, Site Evacuation or Containment Evacuation) to evaluate and initiate a site assembly. 2.3 Augment shifi resources to assess and respond to the emergency situation as needed. 2.4 GO TO Step 3.1 in the body of this procedure and continue with the prescribed subsequent actions.
Enclosure 4.2 /O/570o/o04 STA Immediate and Subsequent Actions Page 1 of 4 Immediate Actions None
- 2. Subsequent Actions NOTE:
- For a Drill the Nuclear Callout System is not activated
- The Security Pager Message is only used when no movement on site is required 2.1 IF a Security Event exists, AND no movement on site is allowed, activate the Emergency Response Origination (ERO) by contacting Security via the ring down phone to the CAS/SAS, or at extension 2688 or 4900 and issue the following message {PIP-M-05-758}:
2.1.1 For a Drill Activate the TSC/OSC/EOF pagers according to the Emergency Response Pager Instructions for a McGuire Security Event drill. General Emergency declared at (time). 2.1.2 For an Emergency Activate the TSC/OSC/EOF pagers according to the Emergency Response Pager Instructions for a McGuire Security Event emergency. General Emergency declared at (time). AND Activate the Nuclear Callout System.
Enclosure 4.2 RP/O/A!5700/oo4 STA Immediate and Subsequent Actions Page 2 of 4 NOTE:
- For a Drill, the Emergency Response Data System (ERDS) is not activated.
- ERDS can only be activated / deactivated from designated computer terminals with SDS access.
These are located in the STAs office, the Data Coordinators room in the TSC and all within the Control Room horseshoe area. 2.1.3 For an Emergency, activate the Emergency Response Data System (ERDS) as soon as possible, but not later than one hour after the emergency declaration per the following: U A. Ensure SDS is running on the selected terminal. U B. Click on MAIN. U C. Click on GENERAL. U D. Click on ERDS. U E. Click on ACTiVATE. O F. Record the time and date ERDS was activated. TIME/DATE / / Eastern mm dd yy U G. Inform the OSM that ERDS was activated. H. IF ERDS failed to activate after five (5) attempts, have an Offsite Agency Communicator notify the NRC via ENS or other available means. U 2.1.4 Notify one of the NRC Resident Inspectors using RP/O/A15700/014, Enclosure 4.2. U 2.1.5 Contact Duke Management using RP/O/A/5700/014, Enclosure 4.3 as soon as possible following event declaration. O 2.1.6 Inform the OSM/EC when steps 2.1.1 thru 2.1.5 have been completed reporting any deficiencies or problems. 2.1.7 WHEN the security event is stabilized to the point that ERO members can come on site, activate the ERO pagers PER Step 2.2.
Enclosure 4.2 /O/5700/004 STA Immediate and Subsequent Actions Page 3 of 4 2.2 Activate the Emergency Response Organization contacting Security via the ring down phone to the CAS/SAS, or at extension 2688 or 4900 and issue the following message {PIP-M-04-754}: 2.2.1 For a Drill Activate the TSC/OSC/EOF pagers, McGuire Drill, General Emergency declared at (time). 2.2.2 For an Emergency Activate the TSC/OSC!EOF pagers, McGuire Emergency, General Emergency declared at (time). AND Activate the Nuclear Callout System. NOTE:
- For a Drill, the Emergency Response Data System (ERDS) is not activated.
- ERDS can only be activated / deactivated from designated computer terminals with SDS access.
These are located in the STAs office, the Data Coordinators room in the TSC and all within the Control Room horseshoe area. 2.2.3 For an Emergency, activate the Emergency Response Data System (ERDS) as soon as possible, but not later than one hour after the emergency declaration per the following: U A. Ensure SDS is running on the selected terminal. U B. Click on MAIN. U C. Click on GENERAL. U D. Click on ERDS. U E. Click on ACTIVATE. U F. Record the time and date ERDS was activated. TIME/DATE / / Eastern mm dd yy U G. Inform the OSM/EC that ERDS was activated. H. IF ERDS failed to activate after five (5) attempts, have an Offsite Agency Communicator notify the NRC via ENS or other available means.
Enclosure 4.2 RP/O/A15700!Q04 STA Immediate and Subsequent Actions Page 4 of 4 El 2.2.4 Notify one of the NRC Resident Inspectors using RP/O/A]5700/014, Enclosure 4.2. El 2.2.5 Contact Duke Management using RPIO/A15700/014, Enclosure 4.3 as soon as possible following event declaration. LI 2.2.6 Inform the OSM/EC when this enclosure has been completed, reporting any deficiencies or problems.
Enclosure 4.3 p.pIO!A!5700!oo4 Emergency CoordfrLatrr Turnovur Checklist Page 1 of I UNIT(S) AFFECTED: Ui U2 {8} POWER LEVEL NCS TEMP NCS PRESS DATE:_________ U-i___________ TIME:_________ Ci U-2__________ NOUE DECLARED AT: TSC ACTIVATED AT:_______________ ALERT DECLARED AT: EOF ACTIVATED AT:_______________ SAE DECLARED AT: c G.E. DECLARED AT: REASON FOR EMER CLASS: YES NO TIME LOCATION OR COMMENTS SITE ASSEMBLY SITE EVAC. (NON-ESSEN.) >e7 SITE EVAC. (ESSENTIAL) L)
. OTHER OFFSITE AGENCY INVOLVEMENT MEDICAL FIRE POLICE NUMBER NUMBER ASSEM. DEPLOYED FIELD MON. TEAMS ZONES ZONES KI (General Public)
EVACUATED SHELTERED Yes( ) No( ) OFFSITE PARS RELEASE IN PROGRESS YES ( ) NO ( 1 RELEASE PATHWAY CONTAINMENT PRESSURE PSIG WIND DIRECTION WIND SPEED NUMBER TIME 7 C LAST MESSAGE SENT: NEXT MESSAGE DUE: C NOTE: EOF COMMUNICATION CHECKS SHOULD BE COMPLETED PRIOR TO ACTIVATING THE EOF. C U OTHER NOTES RELATED TO THE ACCIDENT/EVENT/PLANT EQUIPMENT FAILED OR OUT OF SERVICE
Enclosure 4.4 1.P/O/A!57oo/oo4 Requestfor Emergency Exposure (a) Page 1 of 1 Total Effective Dose Lens of Eye Other Organs (b) Activity Equivalent (TEDE) All 5 rem 15 rem 50 rem Protecting Valuable 10 rem 30 rem 100 rem Property Life saving or 25 rem 75 rem 250 rem Protection of Large Populations Life saving or > 25 rem > 75 rem > 250 rem Protection of Large Populations (c) (a) Excludes declared pregnant women. (b) Includes skin and body extremities. (c) Only on a volunteer basis to persons fully aware of the risks involved. All factors being equal, select volunteers above the age of 45 and those who normally encounter little exposure. RP Badge No. Name Age Employer Signature of Individual My signature indicates my acknowledgement that I have been informed that I may be exposed to the levels of radiation indicated above. I have been fully briefed on the task to be accomplished and on the risks of this exposure. I, acknowledge this planned Emergency Exposure (RPM or designee, signature or note of verbal authorization) Date/Time I, approve this planned Emergency Exposure at (Emergency Coordinator or EOF Director, signature or note of verbal authorization) Date/Time Subsequent Radiation Protection Action: - Determine need for medical evaluation - Initiate reporting requirements per 1 OCFR2O - Copy to Individuals Exposure History File
Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA4SRO 2011 Admin JPMA4 SRO (Rev_041211)
- NUREG 1021, Revision 9
Appendix C Page 2 of 8 Form ES-C-i
- JobPerformance Measure-Worksheet -
Facility: McGuire Task No.: Task
Title:
Classify an Emergency Event JPM No.: 2011 Admin JPM A4 SRO K/A
Reference:
GK/A2.4.41 (2.9/4.6) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: X Classroom X Simulator Plant EXAMINER NOTE: The operator will be given a timeline of events that span a few hours, and asked to classify the event per RPIOIAI5700I000, Classification of Emergency, at two (2) different times during the event. 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: A plant event is in progress on Unit 1. Task Standard: The operator will declare an Unusual Event at T=0302, and declare a Site Area Emergency at T=0349. Required Materials: Blank Copies of RP/0/A/5700/000, Enclosure 4.1, Fission Product Barrier Matrix. General
References:
RP/0/A15700/000 (Classification of Emergency) Rev 16 AP/1/A/5500/i 8 (High Activity in Reactor Coolant), Rev 4 AP/i/A/5500/iO (NC System Leakage Within the Capacity of Both NV Pumps), Rev 22 EP/i/A/5000/E-0 (Reactor Trip or Safety Injection), Rev 31 EP/i/A/5000/E-2 (Faulted Steam Generator Isolation), Rev 9 2011 Admin JPM A4 SRO
- NUREG 1021, Revision 9
Appendix C Page 3 of 8 Form ES-C-i Job Performance Me sure Worksheet EPI1IAI5000IE-3 (Steam Generator Tube Rupture), Rev i 9 OMP 4-3 (Use of Abnormal and Emergency Procedures), Rev 32 McGuire Technical Specifications Handouts: RPIOIAI5700/000 (Classification of Emergency) McGuire Technical Specifications Initiating Cue: Classify the Event in accordance with RPIOIAI5700I000 (Classification of Emergency). Time Critical Task: YES Each Classification is 15 minute Time Critical Validation Time: 25 minutes 2011 Admin JPM A4 SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-i
- PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with 1 s t Timeline Cue 0302 (Last Page of this JPM) and Handout RPIOIAI5700I000. START TIME: STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
*1 (AP/1/A15500/10, Case I The operator enters Step 5) REFER TO RP/0/A/5700/000, Step 2.1 RP/OIA/57001000 and determines that the (Classification of plant was in Mode 1 at the Emergency). start of the event.
The operator reviews Time = 0302 Enclosure 4.1, and determines a Loss of Containment exists, based on 4.1.C.4, SG Secondary Side Release With Primary-to-Secondary Leakage. The operator records 3 points for the loss of the Containment Barrier in Table on Page 2 of 5 of Enclosure 4.1. With a total of 3 points, the operator determines that an Unusual Event exists, NOTE: The operator based on 4.1.U.2, Loss of declaring an Unusual Containment. Event is Critical. The operator reviews Enclosures 4.2 through 4.7. The operator determines that EAL 4.2.U.3, DEl-I 31
> TS allowed Limit, is exceeded, and Declares an Unusual Event.
TIME CRITICAL STOP TIME: 2011 Admin JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 5 of 8 Form ES-C-i
-- PERFORMANCEfNORMkTION - - -
ND 2 Provide Candidate with Timeline Cue 0349 (Now Last Page of this JPM). START TIME:
*2 (OMP 4-3, Steps The operator enters 7.20.1/7.20.1.1-2) OSM RP/0/A/5700/000, Step 2.1 Responsibilities and determines that the plant was in Mode I at the start of Assume role of Emergency the event.
Coordinator upon activation of the Emergency Plan until The operator reviews properly relieved by the Enclosure 4.1, and Station Manager. determines a Loss of Containment exists, based on 4.1.C.4, SG Secondary Emergency Classification is Side Release With Primary-done properly and in a to-Secondary Leakage. timely manner. The operator records 3 points for the loss of the Time = 0349 Containment Barrier in Table on Page 2 of 5 of Enclosure 4.1. The operator reviews Enclosure 4.1, and determines a Loss of NCS exists, based on 4.1.N.3, SG Tube Rupture. The operator records 5 points for the Loss of the NCS barrier in Table on Page 2 of 5 of Enclosure 4.1. NOTE: The operator With a total of 8 points, the operator determines that a declaring an SAE is Site Area Emergency Critical. exists, based on 4.1.S.3, Loss of Containment AND Loss or Potential Loss of Any other Barrier. The operator reviews Enclosures 4.2 through 4.7. Terminating Cue: Evaluation on this JPM is complete. TIME CRITICAL STOP TIME: 2011 Admin -JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 6 of 8 Form ES-C-i
- VERiFICATiON OF COMPtETION Job Performance Measure No.: 2011 Admin JPM A4 SRO Examinees Name:
Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Result: SAT UNSAT Examiners Signature: Date: 2011 Admin-JPMA4SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Event Timeline to 0349 Initial Conditions: A plant event s in progress on Unit 1. 0334 The B MSIV inadvertently closes and the reactor trips. The crew enters EPI1IAI5000IE-0 (Reactor Trip or Safety Injection). 0335 Based on slowly decreasing Pzr pressure, the crew manually actuates Safety Injection. 0340 The crew receives a report that a Steam Generator Safety valve on the B Steam Generator has lifted and stuck partially open causing steam to issue into the sky. 0344 The crew transitions to EPI1IAI5000IE-2 (Faulted Steam Generator Isolation). 0348 The crew observes SI flow at 400 gpm, Pzr level stable at 12%, and the B Steam Generator Narrow Range Level increasing with CA flow shutoff. 0349 The crew isolates the B Steam Generator and transitions to EP/1/A15000/E-3 (Steam Generator Tube Rupture). The Safety valve on the B Steam Generator is still stuck partially open. INITIATING CUE: Classify the Event in accordance with RP/0/A15700/000 (Classification of Emergency). This is a Time Critical JPM NUREG 1021, Revision 9
Appendix C Form ES-C-i
. JPMCLJESF4EET Event Timeline to 0302 Initial Conditions: A plant event is in progress on Unit 1 0100 Unit 1 and Unit 2 are in Mode I at 100% power.
0100 The following Radiation Monitors come into alarm simultaneously:
- 1 EMF-48, Reactor Coolant Rad Hi
- 1EMF-i8, Reactor Coolant Filter iA
- 1 EMF-1 9, Reactor Coolant Filter lB 0101 The crew entered and completed AP/1/A15500118 (High Activity in Reactor Coolant).
0156 Chemistry has determined that the increased radiation levels are due to fuel failure, and report that the Dose Equivalent Iodine levels have stabilized at 70 pc/gm. 0215 Station management has directed that Unit 1 be brought to Hot Standby within the next 6 hours. 0302 During the shutdown, a 20 gpm tube leak develops on the B Steam Generator, and the crew enters AP/1/A/5500/i0 (NC System Leakage Within the Capacity of Both NV Pumps). INITIATING CUE: Classify the Event in accordance with RP/0/A/5700/000 (Classification of Emergency). This is a Time Critical JPM NUREG 1021, Revision 9
Duke Energy Procedure No. McGuire Nuclear Station RPIO!AI5700I000 Classification Of Emergency Revision No. 017 Electronic Reference No. MCOO4SM3 Reference Use PERFORMANCE UNCONTROLLED FOR PRINT * * * * * * * * * * (ISSUED) PDF Format
* -. RPIOJA!5zooJooo Page 2 of 3 Classification of Emergency
- 1. Symptoms 1.1 Notification of Unusual Event 1.1.1 Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. 1.2 Alert 1.2.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. 1.2.2 Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. 1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. 1.3.2 Any releases are not expected to exceed EPA Protective Action Guideline exposure levels beyond the site boundary. 1.4 General Emergency 1.4.1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. 1.4.2 Releases can be reasonably expected to exceed EPA Protective Action Guidelines exposure levels offsite for more than the immediate site area.
- 2. Immediate Actions 2.1 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.
p,p/O/57oo/ooo-Page 3 of3 2.2 Ii the plant was in Mode 1-4 and a valid condition affects fission product barriers, THEN proceed to Enclosure 4.1 (Fission Product Barrier Matrix). 2.3 Wa General Emergency is NOT declared in Step 2.2, OR the condition does not affect fission product barriers, THEN review the listing of enclosures to determine if the event is applicable to one of the categories shown. 2.4 Compare actual plant conditions to the Emergency Action Levels evaluated in 2.2 and/or 2.3, then declare the appropriate Emergency Class as indicated. 2.4.1 Event Declaration time 2.5 Implement the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure. Notification of Unusual Event RP/0/A/5700/00 1 Alert RP/0/A/5700/002 Site Area Emergency RP/0/A/5700/003 General Emergency RP/0/A/5700/004.
- 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures 4.1 through 4.7.
3.2 Refer to enclosure 4.9, Emergency Declaration Guidelines, as needed. 3.3 Refer to section D of the McGuire EPLAN as the basis document for classification of emergencies as needed. 4.0 Enclosures 4.1 Fission Product Barrier Matrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radiological Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fire/Explosion and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.10 Radiation Monitor Readings for Enclosure 4.3 EALs 4.11 Commitment Reference for Emergency Action Levels
re 4.1 RP/O/A/57 dO Fission Product Barrier Matrix Page 1 of5 Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all 3 barriers. Classify according to the table on page 2 of 5 of this enclosure. Note 1: This table is only applicable in Modes 1-4. Note 2: Also, an event (or multiple events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is imminent (i.e., within 1-3 hours). In this imminent loss situation, use judgement and classify as if the thresholds are exceeded. Note 3: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously (validated and sustained) during the event, even if the conditions do not currently exist. Note 4: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the start-up of engineered safeguards equipment. A CSF condition is satisfied when the alarmed state is valid and sustained. The STA should be consulted to affirm if any CSF has been validated prior to that CSF being used as the basis to classify an emergency. { 1 } Example: If ECA-O.O, Loss of All AC Power, is implemented with an appropriate CSF alarm condition valid and sustained, that CSF should be used as the basis to classify an emergency prior to any function restoration nrocedure being implemented within the confines of ECA-O.O. EAL # Unusual Event EAL # Alert EAL # Site Area Emergency EAL # General Emergency 4.1.U.1 Potential Loss of 4.1 .A. 1 Loss OR Potential Loss 4.l.S.1 Loss OR Potential Loss 4.l.G.1 Loss of All Three Barriers Containment of of Both Nuclear Coolant System Nuclear Coolant System AND Fuel Clad 4.1.U.2 Loss of Containment 4.1 .A.2 Loss OR Potential Loss 4.l.S.2 Loss 4.1.G.2 Loss of Any Two Barriers of AND AND Fuel Clad Potential Loss Potential Loss of the Third Combinations of Both Nuclear Coolant System AND Fuel Clad 4.1.A.3 Potential Loss of 4.1.S.3 Loss of Containment Containment AND AND Loss OR Potential Loss Loss OR Potential Loss of Any Other Barrier of Any Other Banier
Ei 4re 4.1 RP/O/A/57u J0 Fission Product Barrier Matrix Page 2 of 5 NOTE: If a barrier is affected, it has a single point value based on a potential loss or a loss. Not Applicable is included in the matrix as a place holder only, and has no point value assigned. Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containment 1 3 1 3 Unusual Event NCS 4 5 46 Alert Fuel Clad 4 5 710 SiteArea Emergency Total Points 11 - 13 General Emergency
- 1. Compare plant conditions against the Fission Product Barrier Matrix on pages 3 through 5 of 5.
- 2. Determine the potential loss or loss status for each balTier (Containment, NCS and Fuel Clad) based on the EAL symptom description.
- 3. For each barrier, write the highest single point value applicable for the barrier in the Points column and mark the appropriate potential loss OR loss column.
- 4. Add the points in the Points column and record the sum as Total Points.
- 5. Determine the classification level based on the number of Total Points.
- 6. In the table on page 1 of this enclosure, under one of the four classification columns, select the event (e.g. 4.1 .A. 1 for Loss of Nuclear Coolant System) that best fits the loss of barrier description.
- 7. Using that EAL number (e.g. 4.1 .A. 1) select the preprinted notification form Qj3 a blank form and complete the required information for Emergency Coordinator/EOF Director approval and transmittal.
Et ire 4.1 RP/O/A/57 .JO Fission Product Barrier Matrix Page 3 of 5 4.l.C CONTAINMENT BARRIER 4.1.N NCS BARRIER 4.1.F FUEL CLAD BARRIER POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS - (1 Point) (3 Points) (4 Points) (5 Points) (4 Points) (5 Points)
- 1. Critical Safety Function Status 1. Critical Safety Function Status 1. Critical Safety Function Status
- Containment-RED. Not applicable.
- NCS Integrity- Not applicable.
- Core Cooling- Core Cooling-RED.
RED. ORANGE.
- Core Cooling -
RED Path is
- Heat Sink-RED.
- Heat Sink-RED.
indicated for >15 minutes.
- 2. Containment Conditions 2. NCS Leak Rate 2. Primary Coolant Activity Level
- Containment
- Rapid unexplained Unisolable leak
- GREATER THAN
- Not applicable.
- Coolant Activity Pressure> 15 decrease in exceeding the available makeup GREATER THAN PSIG. containment capacity of one capacity as 300 tCi/cc Dose pressure following charging pump in indicated by a loss Equivalent Iodine
- H2 concentration initial increase. the normal of NCS subcooling. (DEl) 1-131.
>9%. charging mode
- Containment with letdown
- Contaimnent pressure or sump isolated.
pressure greater than level response not 3 psig with less than consistent with one full train of NS LOCA conditions. and a VX-CARF operating. CONTINUED CONTINUED CONTINUED
ire 4.1 RP/O/A/57. Fission Product Barrier Matrix Page 4 of 5 4.1.C CONTAINMENT BARRIER 4.1.N NCS BARRIER 4.1.F FUEL CLAD BARRIER POTENTIALLOSS- LOSS- POTENTIAL LOSS- LOSS- POTENTIALLOSS- LOSS-(1 Point) (3 Points) (4 Points) (5 Points) (4 Points) (5 Points)
- 3. Containment Isolation Valves Status After 3. SG Tube Rupture 3. Containment Radiation Monitoring Containment Isolation Actuation Not applicable. . Containment . Primary-to- . Indication that a
- Not applicable.
- Containment isolation is Secondary leak SG is Ruptured and radiation monitor incomplete and a rate exceeds the has a Non-Isolable EMF 51 A or 51 B release path from capacity of one secondary line Reading at time containment exists, charging pump in fault. since shutdown the normal charging mode
- Indication that a 0-0.5 hrs > 99 R/hr with letdown SG is ruptured and 0.5-2 hrs> 43 RIhr isolated. a prolonged release 2-4 hrs> 31 R/hr of contaminated 4-8 hrs > 22 R/hr secondary coolant >8 hrs> 13 RJhr is occurring from the affected SG to the environment.
- 4. SG Secondary Side Release With Primary-to- 4. Containment Radiation Monitoring 4. Emergency Coordinator/EOF Director Secondary Leakage Judgement Not applicable.
- Release of
- Not applicable.
- Not applicable.
- Any condition, including inability to monitor secondary side to the barrier, that in the opinion of the the environment Emergency Coordinator/EOF Director with primary-to- indicates LOSS or POTENTIAL LOSS of secondary leakage the fuel clad barrier.
GREATER THAN Tech Spec allowable. END CONTINUED CONTINUED
re 4.1 RP/O/A/57., JO Fission Product Barrier Matrix Page 5 of5 4.1.C CONTAINMENT BARRIER 4.1.N NCS BARRIER 4.1.F FUEL CLAD BARRIER POTENTIAL LOSS LOSS - POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS - (1 Point) (3 Points) (4 Points) (5 Points) (4 Points) (5 Points)
- 5. Significant Radioactive Inventory In 5. Emereency Coordinator/EOF Director Containment Ju&ement
- Containment Rad.
- Not applicable. Any condition, including inability to monitor Monitor EMF5 1 A the barrier, that in the opinion of the or 51B Emergency Coordinator/EOF Director Reading time indicates LOSS or POTENTIAL LOSS of since shutdown: the NCS barrier.
> 390 R!hr 0 0.5 hr
> 170 R!hr(l 0.5 2 hr
- END
> 125 R!hr 2 4 hr
> 9ORJhr @
4 8 hr
> 53 PJhr @
> 8 hr.
- 6. Emergency Coordinator /EOF Director Judgement Any condition, including inability to monitor the barrier, that in the opinion of the Emergency Coordinator/EOF Director indicates LOSS or POTENTIAL LOSS of the containment barrier.
END
Enclosure 4.2 RP/O/A/5700/000 System Malfunctions Page 1 of2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.2.U.1 Inability to Reach Required 4.2.A.1 Unplanned Loss of Most or All 4.2.S.1 Inability to Monitor a Shutdown Within Technical Safety System Annunciation or Significant Transient in Specification Limits. Indication in Control Room Progress. With Either (1) a Significant OPERATING MODE: 1,2,3,4 Transient in Progress, or (2) Compensatory Non-Alarming OPERATING MODE: 1,2,3,4 4.2.U.1-1 Plant is not brought to required Indicators Unavailable. operating mode within Technical 4.2.S.1-1 The following conditions Specifications LCO Action Statement OPERATING MODE: 1, 2, 3, 4 exist: Time. 4.2.A.1.-1 The following conditions exist: Loss of most (>50%) 4.2.U.2 Unplanned Loss of Most or All Safety annunciators associated with System Annunciation or Indication in Unplanned loss of most (>50%) safety systems. the Control Room for Greater Than annunciators associated with safety 15 Minutes. systems for greater than 15 minutes. AND OPERATING MODE: 1,2, 3, 4 AND A significant plant transient is in progress. 4.2.U.2-l The following conditions exist: In the opinion of the Operations Shift Manager/Emergency AND Unplanned loss of most (>50%) Coordinator/EOF Director, the annunciators associated with safety loss of the annunciators or Loss of the OAC. systems for greater than 15 minutes. indicators requires additional personnel (beyond normal shift AND AND compliment) to safely operate the unit. Inability to provide manual AND monitoring of any of the In the opinion of the Operations Shift following Critical Safety Manager/Emergency Coordinator/EOF EITHER of the following: Functions: Director, the loss of the annunciators
- A significant plant transient is or indicators requires additional in progress.
- subcriticality personnel (beyond normal shift
- core cooling compliment) to safely operate the unit. OR
- heat sink
- containment.
CONTINUED
- Loss of the OAC.
END END
Enclosure 4.2 System Malfunctions Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.2.U.3 Fuel Clad Degradation. OPERATING MODE: 1,2,3* 4.2.U.3-1 Dose Equivalent 1-131 greater than the Technical Specification allowable limit. (*mode 3 with Tavg 500°F) 4.2.U.4 Reactor Coolant System (NCS) Leakage. OPERATING MODE: 1,2,3,4 4.2.U.4-1 Unidentified leakage> 10 gprn. 4.2.U.4-2 Pressure boundary leakage> 10 gprn. 4.2.U.4-3 Identified leakage> 25 gpm. 4.2.U.5 Unplanned Loss of All Onsite or Offsite Communications. OPERATING MODE: ALL 4.2.U.5-I Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perform routine operations. 4.2.U.5-2 Loss of all offsite communications capability (Selective Signaling, NRC ETS lines, offsite radio system, commercial phone system) affecting the ability to communicate with offsite authorities. END
Enclosure 4.3 1Y/O/A/57oo/ooo Abnormal Rad Levels/Radiological Effluent Page 1 of5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.U.1 Any Unplanned Release of Gaseous or 4.3.A.l Any Unplanned Release of 4.3.S.1 Boundary Dose 4.3.G.l Boundary Dose Liquid Radioactivity to the Gaseous or Liquid Resulting from an Resulting from an Environment that Exceeds Two Times Radioactivity to the Actual or Imminent Actual or Imminent the SLC Limits for 60 Minutes or Environment that Exceeds Release of Release of Longer. 200 Times the SLC limits Radioactivity that Radioactivity that. for 15 Minutes or Longer. Exceeds 100 mRem Exceeds 1000 OPERATING MODE: ALL TEDE or 500 mRem mRem TEDE or OPERATING MODE: ALL CDE Adult Thyroid 5000 mRem CDE Note: (This applies to all EALs in the 4.3.U.1 for the Actual or Adult Thyroid for IC). If the monitor reading is sustained Note: (This applies to all EALs in the Projected Duration the Actual or for the time period indicated in the EAt. 4.3.A.1 IC). If the monitor of the Release. Projected Duration AND the required assessments reading is sustained for the time of the Release. (procedure calculations) cannot be period indicated in the EAL OPERATING MODE: ALL completed within this time period, AND the required assessments OPERATING MODE: ALL declaration must be made based on the (procedure calculations) cannot Note 1: These EMF readings are valid radiation monitor reading. be completed within this time calculated based on Note 1: These EMF readings are period, declaration must be made average annual alculated based on 4.3.U.l-1 A valid indication on radiation monitor based on the valid radiation meteorology, site average annual EMF- 49L, EMF-44L or EMF-3 1 monitor reading. boundary dose rate, and meteorology, site (when aligned to RC) of design unit vent flow rate. boundary dose rate, and 5.45E+06 cpm for 60 minutes or will 4.3.A.1-l A valid indication on Calculations by the dose design unit vent flow likely continue for 60 minutes, which radiation monitor EMF- 49H assessment team use rate. Calculations b the indicates that the release may have of 1. 56E+03 cpmfor actual meteorology, dose assessment team use exceeded the initiating condition and 15 minutes or will likely release duration, and unit actual meteorology, indicates the need to assess the release continue for 1 5 minutes, which vent flow rate. Therefore, release duration, an unit with procedure HP/0/B/l 009/010, indicates that the release may these EMF readings vent flow rate. HP/0/B/1 009/029, or SH/0/B/2005/00 1. have exceeded the initiating should not be used if dose Therefore, these EMF condition and indicates the need assessment team readings should not be to assess the release with calculations are available. used if dose assessnent (Continued) procedure HP/0/B/l 009/010, team calculations ar HP/0/B/l 009/02 9, or (Continued) available. SH/0/B/2005/00 I. (Continued) (Continued)
Enclosure 4.3 1u/O/A/s700/000 Abnormal Rad Levels/Radiological Effluent Page 2 of 5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.U.1-2 A valid indication on radiation monitor 4.3.A.1-2 A valid indication on Note 2: If dose assessment team Note 2: If dose assessment tram EMF- 36L of 2.05E+04 cpm for radiation monitor EMF- 36L calculations cannot be calculations cannot le
> 60 minutes or will likely continue for of 2.05E+06 cpm for completed in 15 minutes, completed in 15 miilutes, 60 minutes, which indicates that the 15 minutes or will likely then valid monitor reading then valid monitor release may have exceeded the initiating continue for 15 minutes, should be used for reading should be used condition and indicates the need to assess which indicates that the release emergency classification. for emergency the release with procedure may have exceeded the initiating classification.
HP/0/B/1 009/010, HP/0/B/1 009/029, or condition and indicates the need 4.3.S.1-1 A valid indication SH/0/B/2005/00 1. to assess the release with on radiation monitor 4.3.G.I-1 A valid indication procedure HP/0/B/1 009/010, EMF-36H of on radiation monitor 4.3.U.1-3 A valid indication on radiation monitor HP/0/B/1 009/029, or >3.4 E + 03 cpm EMF-36H of EMF-3 I (when aligned to WC or SHIO/B/2005/001. sustained for >3.4E+O4cpm WWCB) of 9.174 E+03 cpm for > 15 minutes. sustained for 60 minutes or will likely continue for 4.3.A.1-3 Gaseous effluent being released >15 minutes. 60 minutes which indicates that the exceeds 200 times the level of 4.3.S.1-2 Dose assessment team release may have exceeded the initiating SEC 16.11-6 for>15 minutes as calculations indicate 4.3.G.1-2 Dose assessment condition and indicates the need to assess determined by Radiation dose consequences team calculations the release with procedure Protection (RP) procedure. greater than 100 indicate dose HP/0/B/1 009/010, HP/0/B/1 009/029, or mRem TEDE or 500 consequences SH/0/B/2005/001. 4.3.A.1-4 Liquid effluent being released mRem CDE Adult greater than 1000 exceeds 200 times the level of Thyroid at the site mRem TEDE or 4.3.U.1-4 Gaseous effluent being released exceeds SLC 16.11-1 for> 15 minutesas boundary. 5000 mRem CDE two times SLC 16.11-6 for determined by Radiation Adult Thyroid at th 60 minutes as determined by Radiation Protection (RP) procedure. 4.3.S.1-3 Analysis of field site boundary. Protection (RP) procedure. survey results or field (Continued) survey samples 4.3.G.1-3 Analysis of field 4.3.U.1-5 Liquid effluent being released exceeds indicates dose survey results or twotimesSLC 16.11-1 for consequences greater field survey samples
> 60 minutes as determined by Radiation than 100 mRem indicates dose Protection (RP) procedure. TEDE or 500 mRem consequences (Continued) CDE Adult Thyroid greater than 1000 at the site boundary. mRem TEDE or END 5000 mRem CDE Adult Thyroid at the site boundary.
END
Enclosure 4.3 1u/O/A/5700/000 Abnormal Rad Levels/Radiological Effluent Page 3 of5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.U.2 Unexpected Increase in Plant 4.3.A.2 Major Damage to Radiation or Airborne Concentration. Irradiated Fuel or Loss of Water Level that Has or OPERATING MODE: ALL Will Result in the Uncovering of Irradiated 4.3.U.2-1 Indication of uncontrolled water level Fuel Outside the Reactor decrease of greater than 6 inches in the Vessel. reactor refueling cavity with all Does not apply to spent fuel in dry irradiated fuel assemblies remaining cask storage. Refer to EPLAN covered by water. section D basis document. 4.3.U.2-2 Uncontrolled water level decrease of OPERATING MODE: ALL greater than 6 inches in the spent fuel pooi and fuel transfer canal with all 4.3.A.2-l An unplanned valid trip II irradiated fuel assemblies remaining alarm on any of the covered by water. following radiation monitors: 4.3.U.23 Unplanned valid area EMF reading exceeds the levels shown in Enclosure Spent Fuel Building 4.10. Refueling Bridge 1 EMF-l 7 2EMF-4 END Spent Fuel Pool Ventilation 1EMF-42 2EMF-42 Reactor Building Refueling Bridge lEMFl6* 2EMF-3
- Containment Noble Gas 1EMF39*
2EMF39*
*Applies to Mode 6 and No Mode Only.
(Continued)
Enclosure 4.3 RP/O/A/5700/000 Abnormal Rad Levels/Radiological Effluent Page 4 of 5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fuel will become uncovered. 4.3.A.2-3 NC system wide range level
<358 inches after initiation of NC system make-up.
AND Any irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel. 4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup. AND Any irradiated fuel assembly not capable of being fully lowered into the spent fuel pool racks or transfer canal fuel transfer system basket. (Continued)
Enclosure 4.3 RP/O/A/5700/000 Abnormal Rad Levels/Radiological Effluent Page 5 of 5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive Material or Increases in Radiation Levels Within the Facility That Impedes Operation of Systems Required to Maintain Safe Operations or to Establish or Maintain Cold Shutdown. OPERATING MODE: ALL 4.3.A.3-1 Valid reading on EMF-12 greater than 15 mRlhr in the Control Room. 4.3.A.3-2 Valid indication of radiation levels greater than 15 mRlhr in the Central Alarm Station (CAS) or Secondary Alarm Station (SAS). 4.3.A.3-3 Valid area EMF reading exceeds the levels shown in Enclosure 4.10. END
Enclosure 4.4 1u/O/A/5700/000 Loss of Shutdown Functions Page 1 of3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY END 4.4.A.1 Failure of Reactor 4.4.S.1 Failure of Reactor 4.4.G.1 Failure of the Reactor Protection System Protection System Protection System to Instrumentation to Complete Instrumentation to Complete Complete an Automatic Trip or Initiate an Automatic or Initiate an Automatic and Manual Trip WAS NOT Reactor Trip Once a Reactor Trip Once a Successful and There is Reactor Protection System Reactor Protection System Indication of an Extreme Setpoint Has Been Exceeded Setpoint Has Been Exceeded Challenge to the Ability to and Manual Trip 3i and Manual Trip WAS J2 Cool the Core. Successful. Successful. OPERATING MODE: 1 OPERATING MODE: 1,2,3 OPERATING MODE: 1 4.4.G.1-1 The following conditions exist: 4.4.A.1-1 The following conditions exist: 4.4.S.1-1 The following conditions exist: Valid reactor trip signal Valid reactor trip signal Valid reactor trip signal received or required and received or required and received or required and automatic reactor trip automatic reactor trip automatic reactor trip was not successful. was not successful. was not successful. AND AND AND Manual reactor trip from the Manual reactor trip from the Manual reactor trip from the control room was not control room is successful and control room was not successful in reducing reactor reactor power is less than 5% successful in reducing reactor power to less than 5% and and decreasing. power to less than 5% and decreasing. decreasing. (Continued) AND (Continued) EITHER of the following conditions exist:
- Core Cooling CSF-RED
- Heat Sink CSF-RED.
END
Enclosure 4.4 RPIO/A/5700/000 Loss of Shutdown Functions Page 2 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.A.2 Inability to Maintain Plant 4.4.S.2 Complete Loss of Function in Cold Shutdown. Needed to Achieve or Maintain Hot Shutdown. OPERATING MODE: 5,6 OPERATING MODE: 1,2,3,4 4.4.A.2..1 Total loss of ND and/or RN and/or KC. 4.4.S.2-1 Subcriticality CSF-RED. AND 4.4.S.2-2 Heat Sink CSF-RED. One of the following: 4.4.S.3 Loss of Water Level in the Reactor Vessel That Has or
- Inability to maintain Will Uncover Fuel in the reactor coolant temperature Reactor Vessel.
below 200°F OPERATING MODE: 5,6 OR 4.4.S.3-1 Failure of heat sink causes loss of cold shutdown conditions.
- Uncontrolled reactor coolant temperature rise to AND
>180°F.
Lower range Reactor Vessel Level Indication System (RVLIS) decreasing after initiation of NC system makeup. (Continued)
Enclosure 4.4 RP/O/A/5700/000 Loss of Shutdown Functions Page 3 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.S.3-2 Failure of heat sink causes loss of cold shutdown conditions. AND Reactor Coolant (NC) system narrow range level less than 6 inches and decreasing after initiation of NC system makeup. 4.4.S.3-3 Failure of heat sink causes loss of cold shutdown conditions. AND Either train ultrasonic level indication less than 6 inches and decreasing after initiation of NC system makeup. END
Enclosure 4.5 iu/O/A/5700/000 Loss of Power Page 1 of3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.5.U.1 Loss of All Offsite 4.5.A.1 Loss of All Offsite 4.5.S.1 Loss of All Offsite 4.5.G.1 Prolonged Loss of All Power to Essential Power and Loss of All Power and Loss of All (Offsite and Onsite) AC Busses for Greater Than Onsite AC Power to Onsite AC Power to Power. 15 Minutes. Essential Busses During Essential Busses. Cold Shutdown Or OPERATING MODE: 1,2,3,4 OPERATING MODE: 1,2,3,4 Refueling Mode. OPERATING MODE: 1,2,3,4 4.5.G.1-1 Prolonged loss of all 4.5.U.1-1 The following conditions OPERATING MODE: 5,6, No 4.5.S.1-1 Loss of all offsite and offsite and onsite AC exist: Mode onsite AC power as power as indicated by: indicated by: Loss of offsite power to 4.5.A.1-1 Loss of all offsite and Loss of power on essential essential buses ETA and onsite AC power as Loss of power on essential buses ETA and ETB for ETB for greater than indicated by: buses ETA and ETB. greater than 15 minutes. 15 minutes. Loss of power on essential AND AND AND buses ETA and ETB. Failure to restore power to Standby Shutdown Both emergency diesel AND at least one essential bus Facility (S SF) fails to generators are supplying within 15 minutes. supply NC pump seal power to their respective Failure to restore power to injection OR CA supply essential busses. at least one essential bus to Steam Generators. within 15 minutes. (Continued) AND (Continued) (Continued) (Continued)
Enclosure 4.5 RPIO/A/5700/000 Loss of Power Page 2 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY OPERATING MODE: 5,6, No 4.5.A.2 AC Power to Essential 4.5.S.2 Loss of All VitaL DC At least one of the Mode Busses Reduced to a Power. following conditions Single Power Source for exist: 4.5.U.1-2 The following conditions Greater Than 15 OPERATING MODE: 1,2,3,4 exist: Minutes Such That An
- Restoration of at least Loss of offsite power to Additional Single 4.5.S.2-1 The following conditions one essential bus essential buses ETA and Failure Could Result in exist: within 4 hours is ETB for greater than Station Blackout. NOT likely 15 minutes. Loss of both unit related OPERATING MODE: 1,2,3,4 EVDA and EVDD busses
- Indication of AND as indicated by bus continuing 4.5.A.2-1 The following condition voltage less than degradation of core One emergency diesel exists: 110 VDC. cooling based on generator is supplying Fission Product power to its respective AC power capability has AND Barrier monitoring.
essential bus. been degraded to one essential bus powered Failure to restore power to END from a single power at least one required DC source for> 15 mm. due bus within 15 minutes Continued to the loss of all but one from the time of loss. of: END SATA SATB ATC ATD DIG A DIG B. END
Enclosure 4.5 RP/O/A/5700/000 Loss of Power Page 3 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.5.U.2 Unplanned Loss of Required DC Power During Cold Shutdown or Refueling Mode for Greater than 15 Minutes. OPERATING MODE: 5,6 4.5.U.2-1 The following conditions exist: Unplanned loss of both unit related EVDA and EVDD busses as indicated by bus voltage less than 110 VDC. AND Failure to restore power to at least one required DC bus within 15 minutes from the time of loss. END
Enclosure 4.6 RP/O/A/5 7 00/000 Fire/Explosion and Security Events Page 1 of4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6.U.1 Fire Within Protected Area 4.6.A.1 Fire or Explosion Affecting 4.6.S.1 HOSTILE ACTION within 4.6.G.1 HOSTILE ACTION Boundary NOT the Operability of Plant the PROTECTED AREA Resulting in Loss of Physical Extinguished Within Safety Systems Required to Control of the Facility. 15 Minutes of Detection OR Establish or Maintain Safe OPERATING MODE: ALL Explosion Within the Shutdown. OPERATING MODE: ALL Protected Area Boundary. 4.6.S.1-1 A HOSTILE ACTION is OPERATING MODE: 1, 2, 3,4, 5, 6 occurring or has occurred within the 4.6.G.1-1 A HOSTILE ACTION has OPERATING MODE: ALL PROTECTED AREA as reported by the occurred such that plant 4.6.A.1-I The following conditions exist: MNS Security Shift Supervision. personnel are unable to operate 4.6.U.1-1 Fire in any of the following (includes non-security events) equipment required to areas NOT extinguished Fire or explosion in any of the maintain safety functions. within 1 5 minutes of control following areas: END room notification or
- Reactor Building 4.6.G.1-2 A HOSTILE ACTION has verification of a control room
- Auxiliary Building caused failure of Spent Fuel fire alarm.
- Diesel Generator Rooms Cooling Systems and
- Control Room IMMINENT fuel damage is Reactor Building
- Standby Shutdown Facility likely for a freshly off-loaded
- Auxiliary Building
- CAS reactor core in pool.
- Diesel Generator Rooms SAS
- ControlRoom
- FWST END
- Standby Shutdown Facility S Doghouses (Applies in
- CAS Mode 1, 2, 3,4 only).
- SAS
- Doghouses AND
- FWST
- Turbine Building
- Service Building (Continued)
- Interim Radwaste Building
- Equipment Staging Building
- ISFSI.
(Continued)
Enclosure 4.6 1P/O!A/57oo/ooo Fire/Explosion and Security Events Page 2 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6.U.12 Report by plant personnel of One of the following: an unanticipated explosion within the protected area Note: Only one train of a system boundary resulting in visible needs to be affected or damaged in order to satisfy damage to permanent this condition. structures or equipment or a loaded cask in the ISFSI.
- Affected safety system parameter indications show 4.6.U.2 Confirmed SECURITY degraded performance CONDITION or Threat
- Plant personnel report Which Indicates a Potential visible damage to Degradation in the Level of permanent structures or Safety of the Plant. equipment within the specified area.
OPERATING MODE: All 4.6.A.2 Fire or Explosion Affecting 4.6.U.2-1 A SECURITY CONDITION the Operability of Plant that does NOT involve a Safety Systems Required to HOSTILE ACTION as Establish or Maintain Safe reported by the MNS Security Shutdown. Shift Supervision. OPERATING MODE: No Mode 4.6.U.2-2 A credible site specific security threat notification. 4.6.A.2-1 The following conditions exist: (includes non-security events) 4.6.U.2-3 A validated notification from Fire or explosion in any of the NRC providing information of following areas: an aircraft threat.
- Spent Fuel Pool Auxiliary Building.
END AND (Continued)
Enclosure 4.6 RP/O/A/5700/000 Fire/Explosion and Security Events Page 3 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY One of the following: Note: Oniy one train of a system needs to be affected or damaged in order to satisfy this condition.
- Spent Fuel Pool level and/or temperature show degraded performance
- Plant personnel report visible damage to permanent structures or equipment supporting Spent Fuel Pool Cooling.
4.6.A.3 HOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat. OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the MNS Security Shift Supervision. (Continued)
Enclosure 4.6 1u/O/A/5700/000 Fire/Explosion and Security Events Page 4 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6.A.3-2 A validated notification from NRC of an airliner attack threat within 30 minutes of the site. END
Enclosure 4.7 RP/O/A/5700/000 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 1 of4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.U.1 Natural and Destructive 4.7.A.1 Natural and Destructive 4.7.S.1 Control Room Evacuation 4.7.G.1 Other Conditions Existing Phenomena Affecting the Phenomena Affecting the Has Been Initiated and Plant Which in the Judgement of Protected Area. Plant Vital Area. Control Cannot Be the Emergency Established. Coordinator/EOF Director OPERATING MODE: ALL OPERATING MODE: ALL Warrant Declaration of OPERATING MODE: ALL General Emergency. 4.7.U.l-1 Tremor felt and valid alarm on 4.7.A.1-1 Valid OBE Exceeded Alarm the Syscom Seismic on 1AD-l3, E-7 4.7.S.1-1 The following conditions OPERATING MODE: ALL Monitoring System (OAC exist: Ml D2422). 4.7.A.12 Tornado or high winds: 4.7.G.1-1 Other conditions exist which Control Room evacuation has in the Judgement of the 4.7.U.1-2 Report by plant personnel of Tornado striking plant been initiated per Emergency tornado striking within structures within the vital APII(2)/A15500/017, or Coordinator/EOF Director protected area area: AP/l (2)IA!5500!024. {3] indicate: boundary/ISFSI.
- Reactor Building AND (1) actual or imminent 4.7.U.1-3 Vehicle crash into plant
- Auxiliary Building substantial core degradation structures or systems within
- FWST Control of the plant cannot be with potential for loss of protected area
- Diesel Generator Rooms established from the Auxiliary containment, boundary/ISFSI.
- Control Room Shutdown Panel or the
- Standby Shutdown Standby Shutdown Facility OR 4.7.U.l-4 Report of turbine failure Facility within 15 minutes.
resulting in casing penetration
- Doghouses (2) potential for or damage to turbine or
- CAS uncontrolled radionuclide generator seals. SAS. (Continued) releases. These releases can reasonably be expected to (Continued) OR exceed Environmental Protection Agency Sustained winds 74 mph for Protective Action Guideline
> 15 minutes. {4} levels outside the site boundary.
(Continued) END
Enclosure 4.7 RP/O/A/5700/000 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 2 of4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.U.1-5 Independent Spent Fuel Cask 4.7.A.1-3 Visible structural damage 4.7.S.2 Other Conditions Existing tipped over or dropped greater caused by either: Which in the Judgement of than 12 inches.
- Vehicle crashes, OR the Emergency
- Turbine failure generated Coordinator/EOF Director 4.7.U.1-6 Uncontrolled flooding in the missiles, OR Warrant Declaration of Site ISFSI area.
- Other catastrophic events Area Emergency.
4.7.U.1-7 Tornado generated missile(s) on any of the following plant OPERATING MODE: ALL impacting the ISFSI. structures: 4.7.S.24 Other conditions exist which
- Reactor Building in the Judgement of the 4.7.U.2 Release of Toxic or
- Auxiliary Building Emergency Coordinator/EOF Flammable Gases Deemed
- FWST Director indicate actual or Detrimental to Safe
- Diesel Generator Rooms likely major failures of plant Operation of the Plant.
- Control Room functions needed for
- Standby Shutdown protection of the public.
OPERATING MODE: ALL Facility END
- Doghouses 4.7.U.2-1 Report or detection of toxic or
- CAS flammable gases that could
- SAS enter within the site boundary
- Ultimate heat sink in amounts that can affect safe (Standby Nuclear Service operation of the plant. Water Pond Dam and Dikes).
4.7.U.2-2 Report by Local, County or State Officials for potential evacuation of site personnel based on offsite event. (Continued) (Continued)
Enclosure 4.7 1u/O/A/5700/000 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 3 of4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.U.3 Other Conditions Existing 4.7.A.2 Release of Toxic or Which in the Judgement of Flammable Gases Within a the Emergency Facility Structure Which Coordinator/EOF Director Jeopardizes Operation of Warrant Declaration of an Systems Required to Unusual Event. Maintain Safe Operations or to Establish or Maintain OPERATING MODE: ALL Cold Shutdown. 4.7.U.3-l Other conditions exist which OPERATING MODE: ALL in the judgement of the Emergency Coordinator/EOF Note: Structures for the below EALs: Director indicate a potential
- Reactor Building degradation of the level of
- Auxiliary Building safety of the plant.
- Diesel Generator Rooms
- Control Room END
- Standby Shutdown Facility
- Doghouses
- CAS SAS.
4.7.A.2-1 Report or detection of toxic gases within a Facility Structure in concentrations that will be life threatening to plant personnel. 4.7.A.2-2 Report or detection of flanmiable gases within a Facility Structure in concentra tions that will affect the safe operation of the plant. (Continued)
Enclosure 4.7 RP/O/A/5700/000 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 4 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.3 Control Room Evacuation Has Been Initiated. OPERATING MODE: ALL 4.7.A.3-l Control Room evacuation has been initiated per AP/1(2)/A/5500/017, or AP/1 (2)/A15500/024. {3} 4.7.A.4 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of an Alert. OPERATING MODE: ALL 4.7.A.4-1 Other conditions exist which in the Judgernent of the Emergency Coordinator/EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant ftinctions is warranted. END
Enc1oure4.8 RP/O[A/5700/000 Definitions/Acronyms Page 1 of 4 ALERT Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of hostile action. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels ALL (As relates to Operating Mode Applicability)
- At all times.
BOMB Refers to an explosive device suspected of having sufficient force to damage plant systems or structures. C1VIL DISTURBANCE A group of persons violently protesting station operations or activities at the site. CONFINEMENT BOUNDARY The barrier(s) between areas containing radioactive substances and the environment. EXPLOSION A rapid, violent unconfined combustion, or a catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems or components. EXTORTION An attempt to cause an action at the site by threat of force. FIRE Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed. An electrical breaker flash that creates high temperatures for a short duration and merely localized scorching to that breaker and its compartment should not be considered a fire. GENERAL EMERGENCY Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guidelines exposure levels offsite for more than the immediate site area. HOSTAGE A person(s) held as leverage against the station to ensure demands will be met by the station. HOSTILE ACTION An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and / or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities, (i.e., this may include violent acts between individuals in the owner controlled area).
Encksure 4.8 RP/O/A/5700/000 Definitions/Acronyms Page 2 of 4 HOSTILE FORCE One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction. IMMINENT Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur. Where IMMINENT time frames are specified, they shall apply. INABILITY TO DIRECTLY MONITOR Operational Aid Computer data points are unavailable or gauges/panel indications are not readily available to the operator. INTRUSION A person(s) present in a specified area without authorization. Discovery of a BOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE. ISFSI Independent Spent Fuel Storage Installation. NO MODE Defueled. PROJECTILE An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety. PROLONGED A duration beyond normal limits, defined as greater than 15 minutes or as determined by the judgement of the Emergency Coordinator. PROTECTED AREA Typically the site specific area which normally encompasses all controlled areas within the security PROTECTED AREA fence. REACTOR COOLANT SYSTEM (RCS/NCS) LEAKAGE - RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13. RUPTURED (As relates to Steam Generator) Existence of primary to secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection. SABOTAGE Deliberate damage, misalignment, or mis-operation of plant equipment with the intent to render the equipment inoperable. Equipment found tampered with or damaged due to malicious mischief may not meet the definition of SABOTAGE until this determination is made by security supervision. SECURITY CONDITION Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threatlrisk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION. SIGNIFICANT TRANSIENT- An unplanned event involving one or more of the following: (1) automatic turbine runback >25% thermal reactor power, (2) electrical load rejection >25% full electrical load; (3) reactor trip, (4) safety injection, (5) thermal power oscillations 10%.
Enc1our& 48 RP/O/A/5700/000 Definitions/Acronyms Page 3 of 4 SITE AREA EMERGENCY Events are in process or have occurred which involve actual or likely maj or failures of plant functions needed for protection of the public or hostile action that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels beyond the site boundary. SITE BOUNDARY That area, including the protected area, in which Duke Power Company has the authority to control all activities, including exclusion or removal of personnel and property. SLC Selected Licensee Commitments. SUSTAiNED A duration of time long enough to confirm that the CSF is valid (not momentary). TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) The sum of external dose exposure to a radioactive plume, to radionuclides deposited on the ground by the plume, and the internal exposure from inhaled radionuclides deposited in the body. TOXIC GAS A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g. chlorine). UNCONTROLLED Event is not the result of planned actions by the plant staff. UNPLANNED An event or action is UNPLANNED if it is not the expected result of normal operations, testing, or maintenance. Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED. UNUSUAL EVENT Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. VALID An indication or report or condition is considered to be VALID when it is conclusively verified by: (1) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) by direct observation by plant personnel such that doubt related to the instruments operability, the conditions existence or the reports accuracy is removed. Implicit in this definition is the need for timely assessment. VIOLENT Force has been used in an attempt to injure site personnel or damage plant property. VISIBLE DAMAGE Damage to equipment or structure that is readily observable without measurements, testing, or analyses. Damage is sufficient to cause concern regarding the continued operability or reliability of affected safety structure, system, or component. Example damage: deformation due to heat or impact, denting, penetration, rupture, cracking, paint blistering.
Enelosure 4.8
- 1/O/A/57oo/ooo Definitions/Acronyms Page 4 of 4 VITAL AREA Areas within the PROTECTED AREA that house equipment important for nuclear safety. Access to a VITAL AREA is allowed only if an individual has been authorized to be in that area per the Security plan, therefore VITAL AREA is a Security term.
Eiw1oure 4.9 RF/OIA/57001000 - - Emergency Declaration Guidelines Page 1 of 2 THE FOLLOWING GUII)ANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESSING EMERGENCY CONDITIONS.
- The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.
- The BASIS Document (located in Section D of the McGuire Nuclear Site Emergency Plan) is available for review if any questions arise over proper classification.
- If an event occurs on more than one unit concurrently, the event with the higher classification will be classified on the emergency notification form. Information relating to the problem on the other unit will be captured on the emergency notification form line 13 remarks section.
- The Affected Unit(s) on Line 11 is tied to the EAL (IC) Number and EAL (IC) Description on Line
- 4. Certain events could occur at the plant site such that multiple units are affected. These may include Abnormal Rad Levels/Radiological Effluents; Fire/Explosion and Security Events; and Natural Disasters, Hazards, and Other Conditions Affecting Plant Safety. This shall be considered when evaluating the accuracy of the Unit designation. {PIP 0-M97-463 8 } If the initiating event puts more than one unit in the same Emergency Classification (example Alert), then the unit designation may be either the Affected Unit numbers or All. If the initiating event drives one unit to a higher classification, then the unit with the higher classification should be listed as Affected Unit. {PIPs M 03-3294 and C-04-2586}
- The EAL (IC) Number and EAL (IC) Description provided on Line 4 of the emergency notification form should be based on the highest emergency classification that applies. Other classifiable events should be included on Line 13, Remarks, on the emergency notification form, but not given an EAL number. {PIPs M-03-3294 and C-04-2586}
- If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed at the time the event occurred.
- The fission product barrier matrix is applicable only to those events that occur at hot shutdown or higher. An event that is recognized at cold shutdown or lower shall not be classified using the fission product barrier matrix. Reference would be made to the additional enclosures that provide emergency action levels for specific events (e.g. severe weather, fire, security).
- If a transient event should occur, the following guidance is provided.
- 1. Some emergency action levels specify a specific duration. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses), whichever is sooner.
Enc1oure4. 1P/O/A/57oo/ooo Emergency Declaration Guidelines Page 2 of 2
- 2. If a plant condition exceeding EAL criteria is corrected before the specified duration time is exceeded, the event is NOT classified by that EAL. Lower Severity EALs, if any, shall be reviewed for possible applicability in these cases.
- 3. If a plant condition exceeding EAL criteria is not recognized at the time of occurrence, but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared. Reporting under 10CFR5O.72 may be required. Such a condition could occur, for example, if a follow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.
- 4. If an emergency classification was warranted, but the plant condition has been corrected prior to declaration and notification, the following are applicable: {2}
- a. For UNUSUAL EVENT, the emergency shall be declared and the condition shall be reported. The event should be terminated in a follow-up notification as soon as time permits, but within one hour.
- b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY, the emergency shall be declared and the Emergency Response Organization shall be activated. The TSC Emergency Coordinator shall be responsible for terminating the emergency as soon as time permits when appropriate.
- c. The Control Room Emergency Coordinator (Operations Shift Manager) shall ensure that any required follow-up notifications are conducted as required prior to activation of the TSC.
DETERMINATION OF EVENT TIME (TIME THE 15 MINUTE CLOCK STARTS) Event Time is the time at which indications become available that an EAL has been exceeded.
- 2. Event Time is the time the 15 minute clock starts for classification.
- 3. The event classification time shall be entered on the emergency notification form.
MOMENTARY ENTRY INTO A HIGHER CLASSIFICATION If, while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged. Acknowledgment is performed as follows: If this condition occurs prior to the initial notification to the emergency response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria for the higher classification. It should also be noted that plant conditions have improved and stabilized to the point that the criteria for the higher classification are not expected to be repeated.
Enclosure 4.10 1u/O/A/5700/000 Radiation Monitor Readings for Enclosure 4.3 EALs Page 1 of 1 Note: These values are not intended to apply to anticipated temporary increases due to planned events (e.g. incore detector movement, radwaste container movement, depleted resin transfers, etc.) Detector Elevation Column Identifier Unusual Alert Event mRlhr mR/hr 1EMF-1 695 FF, GG-56 Aux. Bldg. Corridor 500 5000 1EMF-5 716 FF-54 Unit 1 NM Sample Room 600 5000 1EMF-8 733 HH-56 Aux. Bldg. Corridor 100 5000 1EMF-10 750 LL-56 Aux. Bldg. Corridor 100 5000 1EMF-13 775 QQ-56 Shift Lab/Count Room 100 5000 1EMF-17 786 N/A Unit 1 Spent Fuel Pool Refueling Bridge 100 5000 2EMF-1 716 BE, FF-58 Unit 2 NM Sample Room 300 5000 2EMF-4 786 N/A Unit 2 Spent Fuel Pool Refueling Bridge 100 5000 2EMF-9 767 JJ-59 Aux. Bldg. Corridor 100 5000
Eiwlosure--4d1 RP/O/A15700/OOO Commitment Reference for Emergency Action Levels Page 1 of 1 {1} PIP-M-OO-2138, CA# 18 {2} PIP-M-02-O 187, CA # 6 {3} PIP-M-Ol-2860, CA #2 {4} PIP-M-03 -4281, CA #3 {5} PIP-M-05-3403, CA#3, multiple changes in enclosure 4.6}}