Text

Initial Exam 2010-301 Draft Administrative JPMs
	ML102640745
Person / Time
Site:	Mcguire, McGuire
Issue date:	08/02/2010
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas, Duke Power Co
References
	50-369/10-301, 50-370/10-301, ES-301, ES-301-1 50-369/10-301, 50-370/10-301
	Download: ML102640745 (207)
	v • d • e

ES-301 Administrative Topics Outline Form ES3O1-1 Draft Facility: McGuire Date of Examination: 8/2/10 Examination Level: RO Operating Test Number: Nb-i Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.37 (4.3) Knowledge of procedures, guidelines or Conduct of Operations limitations associated with reactivity M, R management JPM: Perform an ECP 2.1.25 (3.9) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

D, P, R JPM: Determine Boric Acid Addition to FWST 2.2.12 (3.7) Knowledge of Surveillance Procedures.

Equipment Control M, R JPM: Perform a Manual NC Leakage Calculation 2.3.11 (3.8) Ability to control radiation releases Radiation Control MR JPM: Perform a Unit Vent Flow Calculation of a Containment Air Release 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 (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) (1)

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-3d-i Draft RO Admin JPM Summary Ala This is a modified JPM using Bank JPM-RT-RB:073 as its basis. The operator will be told that Reactor Startup is an hour away, and provided with a set of initial conditions.

The operator will be asked to perform an Estimated Critical Position (ECP) in accordance with OPIOIA61 00/06 (Reactivity Balance Calculation), Enclosure 4.2 (Estimated Critical Rod Position). During the course of the ECP, the operator will be given a set of power history conditions, and asked to perform a Shutdown Fission Product Correction calculation in accordance with OP/0/A/6100/06 (Reactivity Balance Calculation), Enclosure 4.8 (Shutdown Fission Product Correction Calculation) in support of the ECP. This is the same JPM as the SRO Exam.

Aib This is a bank JPM, and previously used on the 2009 NRC Operating Test. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, (FWST Makeup Using the RHT), of OP/1/A16200/014 (Refueling Water System) is in progress and completed through Step 3.9, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480 using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/l/A16200/014 (Refueling Water System). The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST.

A2 This is a modified JPM using Bank JPMs ADM-NRC-A2-05 and 12 as its basis. The operator will be told that Unit 1 is at 100% power, the Unit 1 OAC point M1L4554 is out of service, and that PT/l/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm. The operator will be given Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/OO1B (Reactor Coolant Leakage Calculation) with the necessary raw data compiled on a Data Sheet; and directed to complete the calculations within the Enclosure. The operator will be expected to complete all calculations, and identify any Technical Specification Limits that have been exceeded.

A3 This is a modified JPM using Bank JPM ADM-NRC-A3-0i0 as its basis. The operator will be told that GWR Package # 2010013 for Unit 1 Containment Air Release is currently in use to conduct a series of Containment air releases, and that during the first release, conducted using Enclosure 4.2 (Air Release Mode With VQ Flow Monitor Operable) of OP/l/A/6450/017 (Containment Air Addition and Release), the Unit I VQ Monitor became inoperable. The operator will be told that the crew stopped the release and continued the air release using Enclosure 4.3 (Air Release Mode with VQ Flow Monitor Inoperable) of OP/l/A16450/0i7 (Containment Air Addition and Release), and that three previous releases have been made; including the one which was made with the Unit 1 VQ Flow Monitor in operation. Finally, the operator will be provided with the pertinent data for the current release, and then be directed to calculate the volume released for the current release and to determine the total volume released from the Containment during all releases. The operator will be expected to calculate the volume of air released from the Containment during the final release, and determine the total volume of air released in the series of four releases.

NUREG-i 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Draft Facility: McGuire Date of Examination: 8/2/10 Examination Level: SRO Operating Test Number: Nb-i Administrative Topic Type Code* Describe activity to be performed (see_Note) 2.1.37 (4.6) Knowledge of procedures, guidelines or Conduct of Operations limitations associated with reactivity M, R management JPM: Perform an ECP 2.1.25 (4.2) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

D, P, R JPM: Determine Boric Acid Addition to FWST 2.2.12 (4.1) Knowledge of Surveillance Procedures.

Equipment Control M,R JPM: Perform/Review a Manual NC leakage Calculation 2.3.1 1 (3.8) Ability to control radiation releases Radiation Control M,R JPM: Perform a Unit Vent Flow Calculation of a Containment Air Release 2.4.44 (4.4) Knowledge of emergency plan protective Emergency action recommendations.

Procedures/Plan N, R JPM: Provide an updated PAR 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 (5)

(D)irect from bank ( 3 for ROs; 4 for SROs & RD retakes) (1)

(N)ew or (M)odified from bank ( 1) (4)

(P)revious 2 exams ( 1; randomly selected) (1)

NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES30l-l Draft SRO Admin JPM Summary Ala This is a modified JPM using Bank JPM-RT-RB:073 as its basis. The operator will be told that Reactor Startup is an hour away, and provided with a set of initial conditions. The operator will be asked to perform an Estimated Critical Position (ECP) in accordance with OPIOIA/6100/06 (Reactivity Balance Calculation),

Enclosure 4.2 (Estimated Critical Rod Position). During the course of the ECP, the operator will be given a set of power history conditions, and asked to perform a Shutdown Fission Product Correction calculation in accordance with OP/01A161 00/06 (Reactivity Balance Calculation), Enclosure 4.8 (Shutdown Fission Product Correction Calculation) in support of the ECP. This is the same JPM as the RD Exam.

Alb This is a bank JPM, and previously used on the 2009 Operating Test. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4 (FWST Makeup Using the RHT), of OP/l/A/6200/014 (Refueling Water System) is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Independent Verification (SRO aspect) of the calculation in Step 3.10 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480 using the RHT. The operator will discover two errors within the previous calculation, and determine the correct volume of Boric Acid to add. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION.

The operator will be required to identify that ACTION C is applicable after one hour.

A2 This is a modified JPM using Bank JPMs ADM-NRC-A2-05 and 12 as its basis.

The operator will be told that Unit I is at 100% power, the Unit 1 OAC point Ml L4554 is out of service, and that PT/1/A14200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm. The operator will be given Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A14150/OOIB (Reactor Coolant Leakage Calculation) with the necessary raw data compiled on a Data Sheet; and directed to complete the calculations within the Enclosure. The operator will be expected to complete all calculations in accordance with the provided Key, identify any Technical Specification Limits that have been exceeded, and (SRO aspect) identify with all Technical Specification ACTION.

A3 This is a modified JPM using Bank JPM ADM-NRC-A3-0l0 as its basis. The operator will be told that GWR Package # 2010013 for Unit 1 Containment Air Release is currently in use to conduct a series of Containment air releases, and that during the first release, conducted using Enclosure 4.2 (Air Release Mode NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Draft With VQ Flow Monitor Operable) of 0P111A164501017 (Containment Air Addition and Release), the Unit 1 VQ Monitor became inoperable. The operator will be told that the crew stopped the release and continued the air release using Enclosure 4.3 (Air Release Mode with VQ Flow Monitor Inoperable) of 0P111A16450/017 (Containment Air Addition and Release), and that three previous releases have been made; including the one which was made with the Unit 1 VQ Flow Monitor in operation. Finally, the operator will be provided with the pertinent data for the current release, and then be directed to calculate the volume released for the current release and to determine the total volume released from the Containment during all releases. The operator will be expected to calculate the volume of air released from the Containment during the final release, and determine the total volume of air released in the series of four releases. This is the same JPM as the RD Exam.

A4 This is a new JPM. The operator will be placed in a post-accident condition with a Large Break LOCA with a release from the Containment. The operator will be told that a General Emergency has been declared, and provided with the initial Protective Action Recommendation (PAR). The operator will be given a subsequent set of plant conditions and meteorological data, and asked to provide an updated PAR in accordance with Enclosure 4.4 (Offsite Protective Recommendations) of RP101B157001029 (Notifications to Offsite Agencies from the Control Room). The operator will be expected to determine the Updated PAR for the subsequent conditions.

NUREG-1 021, Revision 9

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Ala ROISRO 2010 Admin JPM Ala ROISRO NUREG 1021, Revision 9

Appendix C Page 2 of 17 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.: 2140P_010 Task

Title:

Perform an ECP JPM No.: 2010 Admin JPM Ala ROISRO K/A

Reference:

GKIA 2.1.37 (4.3/4.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

V 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 startup in progress per OP/1/A16100/001 (Controlling Procedure for Unit Startup).

All steps are complete up to determining the desired estimated critical rod height.

The Unit tripped from 30% power, 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months ago.

Prior to that the Unit had operated at 2 EFPD since the previous plant trip, which resulted in a shutdown lasting 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The following Cycle 21 conditions exist:

EFPD=125

NCBoron=1577PPM

Xenon Worth = 0

Samarium = 150 PCM greater than equilibrium It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Reactor Engineer Chad Adams has been contacted earlier today and has reported that there have been no unusual trends on ECPs.

The QAC and REACT Program are unavailable.

Task Standard: The Actual Estimated Critical Rod Position Bank for Xenon at time of Criticality agrees with the evaluator calculated ECP +/- 10 steps.

2010 Admin JPM Al a RO/SRO NUREG 1021, Revision 9

Appendix C Page 3 of 17 Form ES-C-i Job Performance Measure Worksheet Required Materials: Calculator General

References:

OPI1IAJ6100IOO1 (Controlling Procedure for Unit Startup)

OP/0/A/6 100/006 (Reactivity Balance Calculation)

OP/1/A6100/022 (Unit 1 Data Book Cycle 21)

SOMP 01-02 (Reactivity Management)

Handouts: OP/0/A/6i00/006 (Reactivity Balance Calculation) Enclosure 4.2 (Estimated Critical Rod Position (ECP))

OP/0/A16100/006 (Reactivity Balance Calculation) Enclosure 4.8 (Fission Product Correction Calculation)

OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.7, Shutdown Fission Product Correction OP/1/A16100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.1, Critical Boron Concentration HZP, ARC, NO XENON, EQ Sm.

OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.8, Differential Boron Worth, HZP, ARC, NO XENON, EQ Sm.

OP/i/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.9, Xenon and Samarium Worths.

OP/1/A16100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.3.A, Integral Rod Worth in Overlap, HZP, NO XENON.

OP/1/A16100/022 (Unit I Data Book), Enclosure 4.3, Table 6.3.B, Integral Rod Worth in Overlap, HZP, PEAK XENON.

OP/1/A/6100/022 (Unit I Data Book), Enclosure 4.3, Graph 1.2, Control Rod Insertion Limit as a Function of Power.

OP/1/A/6100/022 (Unit I Data Book), Enclosure 4.3, Table 2.8, Rod Withdrawal Limits.

Initiating Cue: The CRS has directed you to perform an ECP per Enclosure 4.2 (Estimated Critical Rod Position (ECP)) of OP/0/A/61 00/006 (Reactivity Balance Calculation).

Time Critical Task: NO Validation Time: 40 minutes 2010 Admin JPM Al a RO/SRO

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Appendix C Page 4 of 17 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout all documents identified in the Handout section.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Note prior to Step 3.1) All The operator reads the curves/tables used in this Note and proceeds.

procedure are found in OP/i (2)/A/61 00/022 (Unit One (Two) Core Data Book). These procedures will be referred to as the Data Book.

2 (Step 3.1) Record the following:

The operator records Unit 1.

(Step 3.1 .1)

Unit_____ Cycle The operator records Cycle 21.

3 (Step 3.1.2) Recent trends The operator recognizes on ECP .

that Chad Adams has been

. contacted.

Reactor Engineer contacted Date_______ The operator records RE name as Chad Adams and todays date.

4 (Step 3.1.3) Date/Time of The operator records Shutdown. DateITime (70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months ago) from current Date/Time.

5 (Step 3.1.4) Anticipated The operator records Date/Time of Criticality todays date and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from the time calculation

/ is started as the time of criticality.

2010 Admin JPM Ala RO/SRO

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Appendix C Page 5 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Step 3.1.5) Burnup:

(P1457) The operator records 125 EFPD.

7 (Step 3.1.6) NC System Boron Concentration:

(Step 3.1.6.1) If pulling rods The operator recognizes to Criticality: from initial conditions that (Step 3.1.6.1A) If OAC is OAC is unavailable and it is unavailable, record the intended to pull rods to current NC System boron criticality. The operator concentration. records 1577 in Step 3.1 .6.1A.

OR (Step 3.1 .6.1 B) If OAC is The operator places NA in available Step 3.i.6.1B.

8 (Step 3.1.6.2) If dilution to The operator places NA in Criticality Step 3.1.6.2.

9 (Step 3.1.6.3) Record the Effective Boron Concentration:

(Step 3.l.6.IA or Step 3.1.6.1B3 or 3.1.6.2) The operator records 1577 ppm from Step 3.i.6.1A.

10 (Step 3.1.7) Xenon worth at The operator records 0 from anticipated time of Criticality initial conditions.

(From OAC program Xenon Samarium XESM or REACT Program).

11 (Step 3.1.8) If burnup from The operator recognizes Step 3.1.5 is> 0 EFPD, that burnup is> 0 EFPD record the difference and records 150 from initial between equilibrium and conditions.

present samarium worth (P1475, Samarium program on OAC or REACT).

2010 Admin JPM Al a RO/SRO

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Appendix C Page 6 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 12 (Step 3.1.9) If burnup from The operator recognizes Step 3.1.5 is> 12 EFPD, that burnup is> 12 EFPD perform Enclosure 4.8 to and that fission product determine the fission correction is needed, and product correction. proceeds to Enclosure 4.8.

13 (Enclosure 4.8/Notes prior The operator reads Notes, to Step 3.1) All curves and proceeds.

/tables used in this procedure are found in OP/i (2)1A161001022 (Unit One (Two) Core Data Book). These procedures will be referred to as the Data Book.

Number of hours shutdown is the difference in time between the time the reactor went subcritical and the expected time of criticality.

14 (Step 3.1) Shutdown The operator reviews power Fission Product Correction history and recognizes that Calculation: the Unit did NOT operate>

3 EFPD from previous (Step 3.1.1) If Unit operated shutdown to current

> 3 EFPD from previous shutdown.

shutdown to current shutdown The operator records an NA in Step 3.1 .1, and proceeds to Step 3.1.2.

2010 Admin JPM Ala RO/SRO NUREG 1021, Revision 9

Appendix C Page 7 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 15 (Step 3.1.2) If Unit operated The operator reviews power

<1 EFPD from previous history and recognizes that shutdown to current the Unit operated> 1 EFPD shutdown from previous shutdown to current shutdown.

Operator records an NA in Step 3.1.2, and proceeds to Step 3.1.3.

16 (Step 3.1.3) If Unit operated The operator reviews power between 1 EFPD and 3 history and recognizes that EFPD from previous the Unit operated between shutdown to current 1 EFPD and 3 EFPD from shutdown and current previous shutdown to shutdown <72 hours use current shutdown, and the Data Book Table 6.7 to current shutdown is <72 determine the shutdown hours.

fission product correction based on the following: Operator proceeds to Step 3.1.3.1.

17 (Step 3.1.3.1) Previous The operator recognizes Shutdown: from initial conditions that the number of hours during (A) Number of hours during the previous shutdown is previous shutdown: 24, and records 24.

h rs The operator addresses Data Book Table 6.7 and determines the Shutdown (B) Shutdown Fission Fission Product Correction Product Correction:

to be 10, and records 10.

ppm 2010 Admin JPM Ala RO/SRO NUREG 1021, Revision 9

Appendix C Page 8 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 18 (Step 3.1.3.2) Current The operator recognizes Shutdown: from initial conditions that the number of hours during (A) Number of hours since the current shutdown to the current shutdown: time of the ECP is 71, and records 71.

hrs The operator addresses (B) Shutdown fission Data Book Table 6.7 and product correction: determines the shutdown fission product correction is ppm 35, and records 34.5.

19 (Step 3.1.3.3) Shutdown The operator uses value Fission product Correction: determined in Step 3.1.3.1B and 3.1.3.2 and determines (Step 3.i.3.1B x 0.5)

+ the Shutdown Fission (Step 3.1.3.2B) =

Product Correction is 39.5 ppm.

Operator records 39.5

(+/-0.5).

(10 x 0.5) + (34.5) = 40 ppm 2010 Admin JPM Ala RO/SRO NUREG 1021, Revision 9

Appendix C Page 9 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 20 (Step 3.1.4) If Unit The operator reviews power operated between 1 EFPD history and recognizes that and 3 EFPD from previous the Unit operated between shutdown to current 1 EFPD and 3 EFPD from shutdown and current previous shutdown to shutdown > 72: current shutdown, however, the current shutdown is <

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Operator records an NA in Step 3.1.4.

Operator reports that the Shutdown Fission Product Correction factor is 39.5

(+/-0.5).

21 (Enclosure 4.2/Step 3.2) If The operator recognizes desired, perform automated from initial conditions that calculations using REACT is NOT available REACT and proceeds to Step 3.3.

22 (Step 3.3) Manual Calculations:

(Step 3.3.1) Boron Concentration:

(Step 3.3.1 .1) Determine The operator addresses the all rods out (ARO), hot Data Book Graph 6.1.

zero power (HZP), no (NOTE: The operator xenon, equilibrium should use chart at bottom, samarium, boron and NO interpolation is concentration for present needed).

burnup from Step 3.1.5 (Data Book Graph 6.1)

(Step 3.3.1.2) Record value The operator records 1818 in Table 4.2.1 Line A. in Table 4.2.1 Line A.

2010 Admin JPM Ala RO/SRO

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Appendix C Page 10 of 17 Form ES-C-I PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 23 (Step 3.3.2) Differential The operator addresses Boron Worth: Data Book Graph 6.8.

(Step 3.3.2.1) Determine (NOTE: Operator should the ARO differential boron use chart at bottom, and worth for present burnup of NO interpolation is needed).

step 3.1.5 (Data Book Graph 6.8)

(Step 3.3.2.2) Record value The operator records -6.35 in Table 4.2.1 Line B in Table 4.2.1 Line B.

24 (Step 3.3.3) Determine the The operator records values Rod Inserted Worth: from steps 3.1.6 3.1.9 in Step (3.3.3.1) Record Table 4.2.1 as follows:

values from Steps 3.1.6 - C. Present Effective Boron 3.1.9 in Table 4.2.1. Concentration: 1577 D. Xenon Worth: 0 E. Duff from Eq Sm Worth:

150 F. Fission Product Correction: 39.5 (+/-0.5) 25 (Step 3.3.3.2) Complete The operator records Table 4.2.1, recording 0 for remaining values in Table any N/Ad Reference Steps. 4.2.1, as follows:

G. Reactivity Equivalent of Boron Difference (C A) x B -

= 1530.

(1577 -1818)x-6.351530pcm H. Reactivity Equivalent of Fission Product Correction F x B = 250.83 39.5 x -6.35 -250.83 Reactivity of Inserted Rods:

(D ÷ E + G) H = 1931 (0 + 150 + 1530)- (-)250.83 1931 2010 Admin JPM Ala RO/SRO

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Appendix C Page ii of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 26 (Step 3.3.4) If result from The operator recognizes Table 4.2.1 < 0 result from Table 4.2.1 > 0 and records NA in Step 3.3.4.

27 (Step 3.3.5) Peak xenon The operator addresses worth:

Data Book Table 6.9.

(Step 3.3.5.1) Determine the peak xenon worth for present burnup from step 3.1.5 (Data Book Table 6.9)

(Step 3.3.5.2) Record value The operator records 3913 in Table 4.2.2 Line C. in Table 4.2.2 Line C.

28 (Step 3.3.6) Calculate the The operator records values Estimated Critical Rod in Table 4.2.2 as follows:

Positions: A. Xenon Worth: 0 (Step 3.3.6.1) Record B. Reactivity of inserted values from Step 3.1.7 and rods: 1931 Table 4.2.1 in Table 4.2.2.

C. Peak Xenon Worth: 3913 D. Lower Band Reactivity Worth: 2681 E. Upper Band Reactivity Worth: 1181 2010 Admin JPM Al a RO/SRO NUREG 1021, Revision 9

Appendix C Page 12 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 29 (Step 3.3.6.2) Complete The operator completes Table 4.2.2. Table 4.2.2 as follows:

The operator addresses Table 6.3.A of the Data Book and determines:

F. No Xenon Rod Position for Reactivity of B Bank C (35 steps, +21-3 steps.

G. No Xenon Rod Position for Reactivity of D Bank B

( 39 steps, +21-3 steps.

H. No Xenon Rod Position for Reactivity of E Bank D c 3 steps, +21-3 steps.

The operator addresses Table 6.3.B of the Data Book and determines:

I. Peak Xenon Rod Position for Reactivity of B Bank C

( 49 steps, +21-3 steps.

J. Peak Xenon Rod Position fro Reactivity of D Bank B

( 68 steps, +21-3 steps.

K. Peak Xenon Rod Position for Reactivity of E -

Bank D ( 26 steps, +21-3 steps.

3Q (Table 4.2.2) Estimated The operator records Bank Critical Position C 35 steps, +21-3 steps.

[(I F) x (A ÷ C)] + F.

31 (Table 4.2.2) Lower Limit of The operator records Bank Band B ( 39 steps, +2I-3 steps.

[(J G) x (A ÷ C)] + G 2010 Admin JPM Al a RO/SRO NUREG 1021, Revision 9

Appendix C Page 13 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

32 (Table 4.2.2) Upper Limit of The operator records Bank Band D (. 3 steps, +21-3 steps.

[(K-H)x(AC))+H

33 (Step 3.4) Check the The operator addresses following: Graph 1.2 and determines (Step 3.4.1) Rod Positions rod positions are NOT of Table 4.2.2 or REACT greater than insertion limits.

output are greater than insertion limits per Data Book Graph 1.2.

(Step 3.4.2) Rod positions The operator addresses of Table 4.2.2 or REACT Table 2.8 and determines Output are less than rod no withdrawal limits exist.

withdrawal limits per Data Book Table 2.8.

34 (Step 3.5) If Step 3.4 The operator contacts CANNOT be met, contact Reactor Engineering.

reactor Engineering.

Cue:

Reactor Engineering acknowledges.

35 Calculations performed By: The operator records Name RO and date.

Date Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2010 Admin JPM Al a RO/SRO NUREG 1021, Revision 9

Appendix C Page 14 of 17 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 Admin JPM Al a RO/SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2010 Admin JPM Al a RO/SRO NUREG 1021, Revision 9

Appendix C Page 15 of 17 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Table 4.2.1: Rod Inserted Worth Calculation Description Reference Value A. ARO, HZP, No Xenon, Eq. Step 3.3.1 i8i8ppm Samarium Boron B. ARO!DBW Step 3.3.2 -6.35pcm!ppm C. Present Effective Boron Step 3.1.6.3 1577ppm Concentration D. Xenon Worth Step 3.1.7 Opcm E. Diff from Eq Sm Worth Step 3.1.8 l5Opcm F. Fission Product Correction Step 3.1.9 39.5(+/-O.5)ppm G. Reactivity Equivalent of (C-A) x B l53Opcm Boron Difference (1577- 1818) x -6.35 H. Reactivity Equivalent of FxB -250.83pcm Fission Product Correction 39.5 x -6.35 (-247.65 (-) 254)

Reactivity of Inserted Rods ( D + E + G) H 1930.83pcm (0+150 (1927.65-1934)

+ 1530) (-250.83) 2010 Admin JPM Ala RO/SRO NUREG 1021, Revision 9

Appendix C Page 16 of 17 Form ES-C-i VERIFICATION OF COMPLETION KEY0nt:

Table 4.2.2: Estimated Critical Rod Positions Description Reference Value A. Xenon Worth Step 3.1.7 Opcm B. Reactivity of inserted rods Table 4.2.1 l93lpcm C. PeakXenon Worth Step 3.3.5 - 3913pcm D. Lower Band Reactivity B + 750 2681 pcm Worth E. Upper Band Reactivity B - 750 1 181 pcm Worth F. No Xenon Rod Position for Data Book Table 6.3.A BankC 35+2/-3steps wld Reactivity of B G. No Xenon Rod Position for Data Book Table 6.3.A BankB 39+2/-3steps wld Reactivity of D H. No Xenon Rod Position for Data Book Table 6.3.A BankD 3+2/-3steps w/d Reactivity of E I. Peak Xenon Rod Position Data Book Table 6.3.B BankC 48+2/-3steps wld for Reactivity of B J. Peak Xenon Rod Position Data Book Table 6.3.B BankB 68+2/-3steps wld for Reactivity of D K. Peak Xenon Rod Position Data Book Table 6.3.B BankD 26+2/-3steps w/d for Reactivity of E Estimated Critical Position [(I - F) x (NC)] + F BankC 35 +2/-3steps wld

[(C48 C35) x (0/3913)]

+ C35 Lower Limit of Band [(J - G) x (NC)] + G BankB 39+2/-3steps w/d

[(B68 B39) x (0/3913)]

+ B39 Upper Limit of Band [(K H) x (NC))

- + H BankD 3 +2/-3steps wid

[(D26 D3) x (0/391 3)]

+_D3 2010 Admin - JPM Ala RO/SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions: Unit 1 startup in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup).

All steps are complete up to determining the desired estimated critical rod height.

The Unit tripped from 30% power, 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months ago.

Prior to that the Unit had operated at 2 EFPD since the previous plant trip, which resulted in a shutdown lasting 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The following Cycle 21 conditions exist:

EFPD=i25

NC Boron = 1577 PPM

Xenon Worth 0

Samarium = 150 PCM greater than equilibrium It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Reactor Engineer Chad Adams has been contacted earlier today and has reported that there have been no unusual trends on ECPs.

The QAC and REACT Program are unavailable.

INITIATING CUE: The CRS has directed you to perform an ECP per Enclosure 4.2 (Estimated Critical Rod Position (ECP)) of OPIOIAI61 00/006 (Reactivity Balance Calculation).

NUREG 1021, Revision 9

Enclosure 4.2 oP/O/A/6 100/006 Estimated Critical Rod Position (ECP) Page 1 of 6

1. Limits and Precautions 1.1 The calculation shall be performed twice. A Licensed Reactor Operator performs the calculation. The second, independent calculation shall be performed by a Qualified Reactor Engineer as a separate verification of the original calculation (NSD 304).

1.2 Criticality should not be obtained outside the maximum window (+/- 750 pcm) of estimated critical control bank position.

1.3 Estimated critical rod position must be recalculated if criticality will not be achieved within +/- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months from previously anticipated time of criticality.

1.4 For Dilution to Criticality (Initial Startup for Cycle): The ECP shall be performed using the All Rods Out, HZP, 0 EFPD Critical Boron Concentration provided in the Data Book.

1.5 Rod Worths listed in Data Book Tables 6.3.A, 6.3.B and 6.3.3 do not need to be interpolated over EFPD. The worths are valid over the range given in each column.

1.6 The maximum allowable rod position is ARO and the minimum allowable rod position isO.

2. Initial Conditions 2.1 None

3. Procedure NOTE: All curves/tables used in this procedure are found in OP/1(2)/AJ6100/022 (Unit One (Two) Data Book). These procedures will be referred to as the Data Book.

3.1 Record the following:

O 3.1.1 Unit Cycle O 3.1.2 Recent trends on ECP Reactor Engineer contacted: Date O 3.1.3 Date/Time of Shutdown:

O 3.1.4 Anticipated Date/Time of Criticality:

0 3.1.5 Burnup: (P1457) EFPD

Enclosure 4.2 v6100/oo6 1

oPIO/

Estimated Critical Rod Position (ECP) Page 2 of 6 3.1.6 NC System Effective Boron Concentration:

3.1.6.1 Pulling Rods to Criticality:

A. IF OAC is unavailable, record the current NC Boron Concentration ppm B. IF OAC is available:

LI 1. Record B- 10 Atom Percent, Best Estimate (P56 13)

LI 2. Record the current NC Boron Concentration ppm LI 3. Calculate the Effective Boron Concentration (Step 3.1.6.1B.2 x Step 3.1.6.1B.1)+/-19.8 x ppm 3.1.6.2 IF Dilution to Criticality, record All Rods Out, HZP, Critical Boron Concentration for 0 EFPD. (Databook Graph 6.1) ppm LI 3.1.6.3 Record the Effective Boron Concentration:

(Step 3.l.6.IA or Step 3.1.6.IB.3 or 3.1.6.2) = ppm LI 3.1.7 Xenon worth at anticipated time of criticality pcm (from OAC program Xenon Samarium XESM -

or REACT program).

3.1.8 jj burnup from step 3.1.5 is> 0 EFPD, record the pcm difference between equilibrium and present samarium worth (P 1475, Samarium program on OAC or REACT). {MCEI-0400-150}

3.1.9 bumup from step 3.1.5 is> 12 EFPD, perform ppmb Enclosure 4.8 to determine the fission product correction.

Enclosure 4.2 oP/O/Al6loo/oo6 Estimated Critical Rod Position (ECP) Page 3 of 6 3.2 IF desired, perform automated calculations using REACT (Reactivity Balance ECP-module) by performing the following:

El 3.2.1 Enter data from Section 3.1 into REACT and calculate, ensuring effective boron concentration from 3.1.6.3 is used as NC System Boron concentration.

El 3.2.2 Attach REACT output to this enclosure.

El 3.2.3 N/A section 3.3 arid go to step 3.4.

3.3 Manual Calculations:

3.3.1 Boron Concentration:

El 3.3.1.1 Determine the all rods out (ARO), hot zero power (HZP), no xenon, equilibrium samarium, boron concentration for present burnup from Step 3.1.5 (Data Book Graph 6.1).

El 3.3.1.2 Record value in Table 4.2.1 Line A.

3.3.2 Differential Boron Worth:

El 3.3.2.1 Determine the ARO differential boron worth for present burnup of step 3.1.5 (Data Book Graph 6.8)

El 3.3.2.2 Recordvalue in Table 4.2.1 Line B.

Enclosure 4.2 oPIOIAJ6loo/oo6 Estimated Critical Rod Position (ECP) Page 4 of 6 3.3.3 Determine the Rod Inserted Worth:

Q 3.3.3.1 RecordvaluesfromSteps3.1.6-3.1.9inTable4.2.1.

0 3.3.3.2 Complete Table 4.2.1, recording 0 for any N/Ad Reference Steps.

Table 4.2.1 Rod Inserted Worth Calculation Description Reference Value A. ARO, HZP, No Xenon, Eq.

Samarium Boron Step 3.3.1 ppm B. ARO DBW Step 3.3.2 pcm!ppm C. Present Effective Boron Step 3.1.6.3 ppm Concentration D. Xenon Worth Step 3.1.7 pcm E. Diff from Eq Sm Worth Step 3.1.8 pcm F. Fission Product Correction Step 3.1.9 ppm G. Reactivity Equivalent of (C A) x B Boron Difference -

X pcm H. Reactivity Equivalent of FxB Fission Product Correction.

X pcm Reactivity of Inserted Rods (D + E + G) - H

(___ +

+ pcm 3.3.4 IF result from Table 4.2.1 <0 perform the following:

0 3.3.4.1 Perform Enclosure 4.1 for an ECB.

0 3.3.4.2 Exit this Enclosure.

3.3.5 Peak xenon worth:

0 3.3.5.1 Determine the peak xenon worth for present burnup from step 3.1.5 (Data Book Table 6.9).

0 3.3.5.2 Record value in Table 4.2.2 Line C.

Enclosure 4.2 oP/O/A/6 100/006 Estimated Critical Rod Position (ECP) Page 5 of 6 3.3.6 Calculate the Estimated Critical Rod Positions:

EJ 3.3.6.1 Record values from Step 3.1.7 and Table 4.2.1 in Table 4.2.2.

LI 3.3.6.2 Complete Table 4.2.2.

Table 4.2.2: Estimated Critical Rod Positions Description Reference Value A. Xenon Worth Step 3.1.7 porn B. Reactivity of inserted rods Table 4.2.1 pcm C. Peak Xenon Worth Step 3.3.5 - porn D. Lower Band Reactivity Worth B + 750 pcm E. Upper Band Reactivity Worth B 750 pcm F. No Xenon Rod Position for Reactivity of B Data Book Table 6.3.A Bank steps w/d G. No Xenon Rod Position for Reactivity of D Data Book Table 6.3.A Bank steps w/d H. No Xenon Rod Position for Reactivity of E Data Book Table 6.3.A Bank steps w/d I. Peak Xenon Rod Position for Reactivity of B Data Book Table 6.3.B Bank steps w/d J. Peak Xenon Rod Position for Reactivity of D Data Book Table 6.3.B Bank steps w/d K. Peak Xenon Rod Position for Reactivity of E Data Book Table 6.3.B Bank steps w/d Estimated Critical Position [(I F)

- (A÷C)] + F

[L -____

x( ÷____

+

Bank steps w/d Lower Limit of Band [(J - G) x (A÷C)] + G

[( -____

x( ÷

)J

+ Bank steps w/d Upper Limit of Band [(K- H) x (A÷C)J + H

[C -____

x( ÷ jJ

+

Bank steps w/d

Enclosure 4.2 oP/O/A/6loo/oo6 Estimated Critical Rod Position (ECP) Page 6 of 6 3.4 Check the following:

LI 3.4.1 Rod Positions of Table 4.2.2 or REACT output are greater than insertion limits per Data Book Graph 1.2.

0 3.4.2 Rod Positions of Table 4.2.2 or REACT output are less than rod withdrawal limits per Data Book Table 2.8.

3.5 IF Step 3.4 CANNOT be met, contact Reactor Engineering.

/

Reactor Engineer Contacted Date Time Calculations Performed By: (RO) Date:

Separate Verification By: (QRE) Date:

3.6 WHEN criticality is achieved, record the following Actual Critical Data (with power leveled off at 108 amps on JJR):

0 3.6.1 Critical Time O 3.6.2 Tavg at Time of Criticality 0 3.6.3 Critical Rod Position: Bank at steps w/d O 3.6.4 Critical Boron Concentration ppm El 3.7 Request that Primary Chemistry obtain an NC system boron sample for B 10 analysis.

3.8 criticality is achieved outside the upper or lower band rod position, generate a N coded Reactivity Management PIP.

PIP Number:

0 3.9 Forward a copy of this Enclosure to Reactor Engineering.

End of Enclosure

Enclosure 4.8 oP/O/A/6 100/006 Fission Product Correction Calculation Page 1 of 2

1. Limits and Precautions None

2. Initial Conditions None

3. Procedure NOTE: 1. All curves/tables used in this procedure are found in OP/1(2)/A/6100/022 (Unit One (Two) Data Book). These procedures will be referred to as the Data Book.

2. Number of hours shutdown is the difference in time between the time the reactor went subcritical and the expected time of criticality.

3.1 Shutdown Fission Product Correction Calculation:

3.1.1 Unit operated> 3 EFPD from previous shutdown to current shutdown:

LI 3.1.1.1 Use Data Book Table 6.7 to determine the shutdown fission product correction:

LI 3.1.1.2 Number of hours shutdown hrs LI 3.1.1.3 Shutdown Fission Product Correction: ppm 3.1.2 IF Unit operated < 1 EFPD from previous shutdown to current shutdown:

LI 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:

LI 3.1.2.2 Number of hours since shutdown hrs LI 3.1.2.3 Shutdown Fission Product Correction: ppm

Enclosure 4.8 oP/O/A16 100/006 Fission Product Correction Calculation Page 2 of 2 3.1.3 IF Unit operated between 1 EFPD and 3 EFPD from previous shutdown to current shutdown and current shutdown < 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months use Data Book Table 6.7 to determine the shutdown fission product correction based on the following:

3.1.3.1 Previous Shutdown:

El A. Number of hours during previous shutdown: hrs El B. Shutdown fission product correction: ppm 3.1.3.2 Current Shutdown:

El A. Number of hours since current shutdown: hrs El B. Shutdown fission product correction: ppm El 3.1.3.3 Shutdown Fission Product Correction:

(Step 3.l.3.1B x 0.5) + Step 3.1.3.2B ppm 3.1.4 IF Unit operated between 1 EFPD and 3 EFPD from previous shutdown to current shutdown and current shutdown> 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s:

El 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.

El 3.1.4.2 Number of hours shutdown hrs El 3.1.4.3 Shutdown Fission Product Correction: ppm

UNiTI OPIIIAI6I 001022 ENCLOSURE 4.3 GRAPH 1.2 CONTROL ROD INSERTION LIMITS AS A FUNCTION OF POWER (Fully Withdrawn UNIT I CYCLE 21 rn/ne 222 max 231) 220 tj60/)

20 EEjANK B

18O 160 140 BANK C 120 100 080 BANK 60 40 (0%,47) 20 10 20 30 40 50 60 70 80 90 100 (Fully Inserted) Relative Power (Percent)

I ()

Note: (1) Compliance with Tech Spec 3.1.3 may require rod withdrawal limits. Referto Unit Data Book Table 2.8.

c)

This data is also available on the QAC U N IT I

UNIT I OPI1IAI6IOO/022 TABLE 2.8 ROD WITHDRAWAL LIMITS McGUIRE UNIT 1 CYCLE 21 McGuire Unit 1 is required to operate with aModerator Temperature Coefficient within the limits of Tech Spec 3.1.3 and as shown in the McGuire Unit I Cycle 21 Core Operating Limits Report, MCEI-0400-232, Revision 0.

For McGuire Unit I Cycle 21, there are NO ROD WITHDRAWAL LIMITS.

UNIT I

Ui 1 OP/it! 00/022 Enclosure 4,3 Graph 6.1 CRITICAL BORON CONCENTRATION HZP, ARO, No Xe, EQ Sm Unit 1 Cycle 21 1791 1591 S

a a

1391 0

ct I

C 1191 C

0 C-)

C 0

0 791 591 0 100 200 300 400 5.00 EFPD n

EFPD 0 4 12 25 50 75 100 125 150 200 250 300 350 400 450 485 509 524 J PPMB 1850 1839 1832 1839 1860 1862 1847 1818 1778 1672 1540 1392 1230 1058 879 753 666 611 Note: Peak Sm at 0 EFPD This data is avaUable on the QAC UNITI

z m 9

71 0

aC a

r r

0 a

0 C

9 CD I a

0 C

5 rn z

C, 0

0 C.

CD H I C, H a C i NZC C) x CD Cz

<9)

Sc,

1

-C

1 A S

C .

I cz z

UNIT 1 Enclosure 4.3 Table 6.3.A ct ,.

Integral Rod Worth in Overlap HZP, No Xenon Unit I Cycle 21 4 EFPD 100 EFPD 200 EFPD 300 EFPD 400 EFPD Control Bank Position 0-5OEFPD 51-15OEFPD 151-25OEFPD 251

350 EFPD 351 - EOW Steps Withdrawn tRW tRW tRW tRW tRW BkA 8kB BkC Bk D (PCM) (PCM) (PCM) (PCM) (PCM) 226 226 196 80 632 589 631 712 801 226 226 191 75 670 626 672 762 862 226 226 186 V 70 707 664 713 812 923 226 226 181 65 745 701 754 862 984 226 226 176 60 782 V 739 795 911 1045 957V 226 226 171 55 V 819 777 836 1097 226 226 166 50 856 816 878 1004 1148 226 226 161 45 893 855 919 1050 1200 226 226 156 40 930 V 894 961 1096 1251 226 226 151 35 969 934 1002 1138 1295 226 226 146 30 1008 974 1043 1181 1338 226 226 141 25 1047 1014 1084 1224 1381 226 V 226 136 20 1086 1054 1125 1266 1425 7 226 131 15 1124 V 1091 1162 1302 1457 226 126 10 1161 1129 1199 1338 1489 26 226 226 226 121 116 5

0 V

1198 1235 1167 1205 1236 1273 V 1374 1410 1522 1554 226 226 110 0 1269 1246 1312 1446 1583 226 221 105 0 1300 1282 1346 1477 1611 226 216 100 0 1330 1318 1380 1508 1639 226 211 95 0 1367 1360 1420 1547 1682 226 206 90 0 1404 1402 1461 1587 1725 226 201 85 V 0 1441 1444 1501 1627 1769 V

226 196 80 0 1477 1486 1541 1666 1812 226 191 75 0 1523 1534 V

1589 1712 1859

. 226 186 70 0 1569 1583 1636 1758 1907 226 181 65 0 1614 V 1632 1683 1804 1954 226 176 60 0 1660 1680 1730 1850 2002 226 171 55 0 1719 1732 1781 1897 2044 226 166 50 0 1778 1784 1831 1944 2087 NOTE: For actual ALL Rods out Overlap Data, see Enclosure 4.3, Section 1.13 of the Data Book UNIT

UNIT I s_is I,,Ss, I Enclosure 4.3 Table 6.3.A Integral Rod Worth in Overlap HZP, No 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 0 (PCM) (PCM) (PCM) (PCM) (PCM) 226 161 45 0 1836 1837 1881 1991 2130 226 156 40 0 1895 1889 1932 2038 2172 226 151 35 0 1954 1933. 1974 2076 2203 226 146 30 0 2013 1978 2016 2114 -

2234 226 141 25 0 2072 2022 2058 2151 2265 226 136 20 0 . 2131 2066 2100 2189 2295 226 131 15 0 2168 2097 2127 . 2212 2312 226 126 10 0 2205 2127 2155 2235 2329 226 121 5 0 2241 2158 2183 2257 2346 226 116 0 0 2278 2188 2210 2280 2363 226 110 0 0 2300 2213 2233 2297 2375 221 105 0 0 2323 2236 2255 2317 2396 216 100 0 0 2347 2260 2276 2337 2416 211 95 0 0 2379 2291 2309 2374 2460 90 0 0 2412 2323 2342 2411 2504 0 0 2445 2355 2375 2448 2548 196 80 0 0 2477 2387 2407 2485 2592 191 75 0 0 2510 2422 2445 2527 2639 186 70 0 0 2542 2457 2483 2569 2686 181 65 0 0 2574 2493 2521 2611 2732 176 60 0 0 2606 2528 2558 2653 2779 171 55 0 0 2640 2565 2596 2691 2816 166 50 0 0 2674 2601 2634 2730 2853 161 45 0 0 2708 2638 2673 2768 2890 156 40 0 0 2742 267-5 2711 2806 2928 35 151 0 0 2774 2710 2746 2839 2955 146 30 0 0 2807 2746 2781 2871 2982 141 25 0 0 2839 2782 2816 2903 3008 136 20 0 0 2871 2817 2852 2936 3035 131 15 0 0 2895 2848 2880 2959 . 3051 NOTE: For actual At.L Rods out Overlap Data, see Enclosure 4.3, Section 1.13 of the Data Book UNIT

UNII 1 Enclosure 4.3 Table 6.3.A Integral Rod Worth in Overlap ck G HZP, No Xenon Unit I Cycle 21 4EFPD 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 8kB BkC BkD (PCM) (PCM) (PCM) (PCM) (PCM) 126 10 0 0 2920 2878 2908 2981 3067 121 5 0 0 2944 2909 2937 3004 3083 116 0 0 0 2969 2939 2965 3027 3098 110 0 0 0 2988 2970 2993 3047 3110 105 0 0 0 3003 2994 3014 3060 3118

. 100 0 0 0 3018 3018 3035 3074 3126 95 0 0 0 3030 3039 3052 3084 3130 90 0 0 0 3042 3060 3069 3093 3134 85 0 0 0 3054 3081 3087 3103 3139 80 0 0 - 0 3066 3102 3104 3112 3143 75 0 0 0 3074 3117 3115 --3117 3145 70 0 0 0 3082 3131 3126 3123 3147 65 0 0 - 0 3090 3145 3137 3128 3149 60 0 0 0 3099 3160 3148 3133 3151

-- 0 0 0 3103 3167 3153 3135 3152 0 0 0 3108 3174 3159 3138 3153 5 0 0 0 3112 3182 3164 3140 3154 40 0 0 0 3117 3189 3170 3143 3155 35 0 0 0 3119 3192 3172 3144 3155 30 0 - 0 0 3121 3195 3174 3145 3156 25 0 0 0 3124 3198 3176 3146 3156 20 0 0 0 3126 3201 3179 3147 3156 -

15 0 0 0 3127 3202 3179 3147 3156 10 0 0 0 3128 3203 3180 3147 3157 5 0 0 0 3129 3204 3180 3148 3Th7 0 0 0 0 3130 3205 3181 3148 3157 NOTE: For actual ALL Rods out Overlap Data, see Endosure 4.3, Section 1.13 of the Data Book UNIT

UNIT I ..ll IftVU II.$tVL..

Enclosure 4.3 Table 6.3.A c1 4Gm Integral Rod Worth in Overlap HZP, No Xenon Unit 1 Cycle 21 4 EFPO 100 EFPO 200 EFPO 300 EFPO 400 EFPO Control Shutdown Bank Position 0-50 EFPO 51 - 150 EFPO 151 - 250 EFPD 251 - 350 EFPD 351 - EOW Bank Steps Withdrawn IRW tRW IRW tRW - tRW -

Position SO E SOD soc so s SD A (PCM) (PCM) (PCM) (PCM) (PCM) 226 226 226 226 226 226 0 -0 0 0 0 0 226 226 226 226 226 3130 3205 3181 3148 3157 0 0 226 226 226 226 3985 4047 3973 3911 3907 0 0 0 226 226 226 4497 4671 4658 4614 4623 0 0 0 0 226 226 5047 5361 5438 5429 5-463 0 0 0 0 0 226 6289 6430 6420 6370 6394 0 0 0 0 0 0 6402 6563 6568 6525 6562

NOTE: For actual ALL Rods out Overlap Oata. see Enclsure 4.3, Section 1.13 of the Data Book UNIT

0 N)N)N)N)N)N)N)N)N3N)N)N)N) C) r3rN)N)rrN),N)N)N)N)N)N) ,N)N)N)N)N)N)CiN)N)N)N)N)N)

C)C)C)C)C)C)C)C)C)C)C)C)C)J)C)C)C)C)C)C)C)C)C)C)C)C)C)>cfg m . CD

a N)N) N) N) N) N)N)N)N) N)N) N)N) N)N) N)N)N) )N)N) MN)N)N) N)N) N)N)N) C N) N) r N) N) r N) N) N) r N) N) N) N) N) N) N)

C)C) C)C)C)C)C)C)C)C)C)C)C)C)C)C)C)C) C)C)C)

0) 0

ø I N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N)

CO - -. N) N) N) N) N) N) N) N)N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N) N)

-)-C) C)C)C)C) 0 0

0) 0 0 C ...A .h N) N) N) N) N) N) N)

O C) 0)

0 0

.D.

0)

0) (D CO C.300

. 40 N)O 4 C) C.) 0 C.) -J 0 C.) N) 0 C) C) CO C.) C) C.) rn -c 0)

CD CD C rn 1

0 0)

C N)OO orn C.) Q.)C.C)C.)CDON)OC)N)C)C)C)C)CDCOCD C,

!rn L:r)

CD C C 0

CT C.) o 0

CD rn-c Q

C . C 0 CD 0>

0) N) O)

CT CD 0 -

8 N)N)N)

C.)O0T m CD rnc C

. C.)

C)C)C)(N)N) -c m

C C

z

UNIT I Enclosure 4.3 Table 6.3.B Integral Rod Worth in Overlap AC HZP, Peak Xenon Unit I Cycle2I 4 EFPD 100 EFPD 200 EFPD 300 EFPD 400 EFPD Control Bank Position 0-5OEFPD 51 -150 EFPD 151 -250 EFPD 251-35OEFPD 351 -EOW Steps Withdrawn

IRW tRW tRW IRW IRW BkA 8kB BkC Bk 0 (PCM) (PCM) (PCM) (PCM) (PCM) 226 226 196 80 720 718 773 830 887 226 226 191 - 75 761 763 827 894 958 226 226 186 70 802 808 881 957 1028 226 226 181 65 843 854 935 1021 1099 226 226 176 60 884 899 990 1084 1169 226 226 171 55 923 942 1038 1137 1225 226 226 166 50 961 984 1085 1189 1280 226 226 161 45 1000 1027 1133 1242 1336 226 226 156 40 1039 1070 1181 1295 1392 226 226 151 35 1079 1111 1224 1338 1433 226 226 146 30 1119 1153 1267 1381 1475 226 226 141 25 1159 1194 1310 1424 1516 226 226 136 20 1200 1236 1354 1467 1558 S 226 131 15 1236 1271 1388 1498 1584 j 226 126 10 1272 1307 1423 1529 1610 226 226 121 5 1308 1342 1457 1561 1636 226 226 116 0 1344 1377 1492 1592 1662 226 V 226 110 0 1375 1410 1524 1618 1682 226 221 105 0 1403 1439 1553 V 1645 1709 V

226 216 100 0 1431 1468 1582 1673 1736 226 211 95 0 V 1467 1506 1624 1721 1792 V 226 206 90 0 1502 1544 1666 1769 1847 226 201 85 0 1537 1582 1708 1817 1903 226 196 80 0 1572 1620 V 1750 1866 1958 226 191 75 0 1616 1666 1799 1918 2015 226 186 70 0 1660 1713 1847 1970 2072 226 181 65 0 1703 1759 1895 2022 2129 226 176 60 0 1747 1806 1944 2074 2186 226 V 171 55 0 1805 1862 1996 2121 2230 226 166 50 0 1863 1919 2047 2168 2275

NOTE: For actual ALL Rods out Overlap Data, see Endosure 4.3, Section 1.13 of the Data Book UNIT

UNIT I %sI I I#rvsI *IVI%I Enclosure 4.3 Table 6.3.8

- 5 cJ AG Integral Rod Worth in Overlap HZP, Peak Xenon Unit I Cycle2I 4 EFPO 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 tRW tRW tRW IRW Bk A Bk B Bk C Bk 0 (PCM) (PCM) (PCM) (PCM) (PCM) 226 161 45 0 1921 1975 2099 2215 2320 226 156 40 0 1979 2032 2151 2262 2364 226 151 35 0 2043 2085 2195 2298 2395 226 146 30 0 2106 2139 2239 2333 2425 226 141 25 0 2170 2193 2282 2368 2455 226 136 20 0 2233 2246 2326 2404 2485 226 131 15 0 2275 2279 2352 2423 2501 226 126 10 0 2316 2313 2378 2443 2516 226 121 5 0 2357 2346 2404 2463 2532 226 116 0 0 2398 2379 2430 2482 2548 226 110 0 0 2421 2401 2448 2496 2558 221 105 0 0 2445 2424 2469 2516 2579 216 100 0 0 2469 2447 2490 2536 2601 211 95 0 0 2503 2483 2529 2578 2646 90 0 0 2536 2518 2567 2620 2692 85 0 0 2570 2553 2606 2662 2738 196 80 0 0 2603 2588 2644 2704 2783 191 75 0 0 2637 2626 2685 2748 - 2828 186 70 0 0 2670 2664 2727 2791 2873 181 65 0 0 2704 2702 2768 2835 2917 176 60 0 0 2738 2740 2809 2878 2962 171 55 0 0 2773 2778 2846 2913 2993 166 50 0 0 2808 2816 2882 2947 3025 161 45 0 0 2843 2854 2918 2981 3056 156 40 0 0 2878 2892 2955 3015 3088 151 35 0 0 2908 2923 2983 3038 3107 146 30 0 0 2938 2955 3010 3061 3126 141 25 0 0 2968 2987 3038 3084 3145 136 V

20 0 0 2998 3019 3066 3107 3164 V V

131 15 0- 0- 3Q17 3039 3083 3120 3174 NOTE: For actual ALL Rods out Overlap Data, see Enclosure 4.3, Section 1.13 of the Data Book UNIT

UNIT I Enclosure 4.3 Table 6.3.B Integral Rod Worth in Overlap HZP, Peak Xenon Unit I Cycle2I 4 EFPD 100 EFPO 200 EFPD 300 EFPO 400 EFPD Control Bank Position 0-50 EFPD 51 - 150 EFPD 151 - 250-EFPD 251 - 350 EFPO 351 - EOW Steps Withdrawn IRW IRW IRW IRW IRW Bk A Bk B Bk C Bk D (PCM) (PCM) (PCM) (PCM) (PCM) 126 10 0 0 3035 3060 3100 3132 3184 121 5 0 0 3054 3081 3117 3145 3193 Tii 0 0 0 3072 3101 3134 3158 3203 110 0 0 0 3085 3118 3147 3167 3210 105 0

0 0 3094 3129 3156 3173 3213 100 0 0 0 3103 3140 3165 3179 3217 95 0 0 0 3110 3149 3170 3182 3219 90 0 0 0 3117 3157 3176 3185 3221 85 0 0 0 3123 3165 3181

3189 3224 80 0 0 0 3130 3174 3187 3192 3226 75 0 0 - 0 3134 3179 3190 3194

3226 70 0 0 0 3138 3183 3193 3195 .3227 65 0 0 0 3142 3188 3196 3196 3228 60 0 0 0 3146

3193 3198 3198 3229

-. 0 0 0 3149 3196 3200 3199 3229 0 0 0 3151 3199 3201 3199 3229 5 & 0 0 3153 *

3201

3203 3200 3230 0 0 0 - 3156 3204 3204 3201 3230 35 . 0 0 0 3157 3205 3205 3201 3230 30

0 0 0 3158 3206 3205 3201 3230 25 0 0 0 3160 3208 -3206 3201

3230 20 & 0 0 3161 3209 3207 3202 3230 15 0 0 0 3161 3209 - 3207 3202 3230 10

0 0 0 3162 3210 3207 3202 3230 5 0 0 0 3162 3210 3207 3202 3231 0 0 0 0 3163 3211 3208 3202

3231 1OTE: For actual ALL Rods out Overlap Data, see Enclosure 4.3. Section 1.13 of the Data Book UNIT

.sr. .,ru,s .,,s,,.st.

JNIT I Enclosure 4.3 Table 6.3.B Ckr A Integral Rod Worth in Overlap HZP, Peak Xenon Unit I Cycle2I 4 EFPD 100 EFPD 200 EFPD 300 EFPD 400 EFPD Control Shutdown Bank Position 0 -50 EFPO 51 -150 EFPD 151 - 250 EFPD 251 - 350 EFPI) 351 - EOW Bank Steps Withdrawn IRW IRW RW IRW IRW Position SD E SD 0 SD C SD B SD A (PCM) (PCM) (PCM) (PCM) (PCM) 226 226 226 226 226 226 0 0 0 0 0 226 226 226 226 226 3163 3211 3208 3202 3231 0 0 226 226 226 226 3925 3955 3916 3890 3906 0 0 0 226 226 226 4506 4639 4652 4643 4674 0 0 0 0 226 226 5152 5424 5515 5539 5598 0 0 0 0 0 226 6427 6542 6544 6523 6567 0 0 0 0 0 0 6612 6749 6762 6749 6813 NOTE: For actual ALL Rods out Oveilap Data, see Enclosure 4.3, Section 1.13 olthe Data Book UNIT

C a)oa) 0 z 3

I

-CD C) 0 C.) - CD a) 0)

, 0 z

ci, N)t%)

0) 0)0 .

3 .

CD 0 0.

-U 0

a t

C.,

0 g g C,

3.

(0 -.J . N) N) N) N) N) N) - 0

0) N) Co .1 C.) N) C) 0 (0 0

0 Q00N).0)0)0N)

SCD pcop NC CD 0

z a)0a)C.)0(0D I 3

UNii1 OP/1/Ai OO/O22 Enclosure 4.3 Graph 6.8 DIFFERENTIAL BORON WORTH HZP, ARO, No Xe, EQSm Unit 1 Cycle 21

-5.78

-5.98

-6.18

-6.38

-6.58

-6.78 N

I

-6.98

-7.18

-7.38

-7.58

-7.78 0 100 200 300 400 50Q EFPD EFPD 0 4 12 25 50 75 100 125 150 200 250 300 350 400 450 4851 509 5241 DBW -6.28 -6.33 -6.33 -6.32 -6.30 -6.30 -6.32 -6.35 -6.39 -6.50 -663 -6.78 -6.96 -7.17 -7.40 -7.57 -7.70 -7,781 This data is also available on the QAC UNIT I

OPII!A161001022 4G Page 1 off U N IT I ENCLOSURE 4.3 TABLE 6.9 McGuire I Cycle 21 Xenon and Samarium Wóh HFP Equilibrium HZP Peak HFP Equilibrium Bumup Xenon Xenon Samarium (EFPD) (pcm) (pcm) (pcm) 0 748 4 2523 3860 564 12 219 3850 654 25 2523 3853 753 50 2534 3865 792 75 2548 3880 809 100 2564 3896 825 125 2580 3913 841 150 2597 3932 857 200 2632 3983 887 250 2668 4052 914 300 2706 4144 940 350 2744 4253 963 400 2783 4372 985 450 2822. 4499 1O06 485 2849 4603 1019 509 2868 4691 1028 524 2879 4738 1033 UNIT I

Appendix C Job Performance Measure Form ES-C-i Worksheet JPMAIbRO 2010 Admin JPM Aib RO

- NUREG 1021, Revision 9

Appendix C Page 2 of 8 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.: 217MFW002 Task

Title:

Determine Boric Acid Addition to JPM No.: 2010 Admin JPM Aib FWST 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 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 plant was at 100% power when a leak developed on the FWST.

FWST Level dropped to 440 inches before leak was isolated.

Enclosure 4.4, FWST Makeup Using the RHT, of OP/i/A/6200/014, Refueling Water System is in progress and completed through Step 3.9.

LCO 3.5.4, Refueling Water Storage Tank (RWST), was entered 10 minutes ago.

Chemistry has provided the following information.

BAT Boron Conc. 7234 ppm

RHT Boron Conc.= 1076 ppm

FWST Make up Boron Concentration: Use COLR Minimum Task Standard: The operator will calculate the amount of Boric Acid that must be added from the BAT to refill the FWST is 7,912 gallons +300/-75 gallons.

Required Materials: Calculator General

References:

OP/i/A16200/014, Refueling Water System 2OlOAdmin-JPMA1bRO NUREG 1021, Revision 9

Appendix C Page 3 of 8 Form ES-C-i Job Performance Measure Worksheet McGuire Core Operating Limits Report (Cycle 21)

McGuire U-i Data Book OMP 8-2, Component Verification Techniques Handouts: Enclosure 4.4 of 0P111A162001014, Refueling Water System, marked up for place-keeping through Step 3.9 as follows:

Initial Conditions 2.1 -2.3 are initialed.

Procedure Step 3.1 Checkbox is checked.

Procedure Step 3.2 Left blank (Conditional step).

Procedure Step 3.3 initialed, Person Notified: CHEMIST, date/time:

present.

Procedure Step 3.4 NA, initialed.

Procedure Step 3.5 initialed.

Procedure Step 3.6 NA, initialed.

Procedure Step 3.7 NA, initialed.

Procedure Step 3.8 NA, initialed.

Procedure Step 3.9 initialed, Person Notified: R.P. TECH, date/time: present.

McGuire 1 Cycle 21 Core Operating Limits Report (Page 26 of 32)

OP/i/A16100/22, Enclosure 4.3, Curve 7.7, Refueling Water Storage Tank Level (Volume vs. Tank Level)

Initiating Cue: Determine the amount of Boric Acid needed to raise the FWST level to 480 using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/i /A/6200/0 14, Refueling Water System.

Time Critical Task: NO Validation Time: 20 minutes 2010 Admin JPM Aib RO NUREG 1021, Revision 9

Appendix C Page 4 of 8 Form ES-C1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout all three (3) identified Handout documents, marked up as described.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

1 (Step 3.10) Determine the The operator refers to the amount of Boric Acid COLR, Section 2.13.1 on needed to raise makeup Page 26 of 32 and water to the limits specified determines that the in the Core Operating Limits minimum boron Report (COLR). concentration to be used in the calculation is 2675 ppm.

The operator records 2675 ppm in the first line (Desired Boron Concentration of Addition from COLR) of the Doer Calculation in Step 3.10 of Enclosure 4.4.

2 (lst Bullet) Desired Boron The operator adds an Concentration of Addition additional 25 ppm and from COLR + 25 ppmB determines Desired Boron margin = Desired Boron Concentration to be 2700 Concentration ppm.

The operator records 2700 ppm in the 2nd line (Desired Boron Conc) of the Doer Calculation in Step 3.10 of Enclosure 4.4.

3 (2 Bullet) The operator identifies Desired Cb = 2700 from

{(Desired Cb) (RHT Cb)}

previous Step and records.

(BATCb)-(RHTCb)

The operator recognizes x {Desired Total that RHT Cb = 1076 ppm Makeup Volume to and records (Initial FWST} Conditions).

= Desired BAT Volume 2010 Admin JPM Al b RO

- NUREG 1021, Revision 9

Appendix C Page 5 of 8 Form ES-C-I PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 The operator recognizes (CONTD) that BAT Cb = 7234 ppm and records (Initial Conditions).

The operator addresses OP/1/A16100122, Enclosure 4.3, Curve 7.7, and determines from graph that total makeup volume is 30,000 by comparing 480 volume of 390,000 gallons to the 440 volume of 360,000 gallons.

The operator records 30,000 (+1300#) gallons.

The operator calculates the Desired BAT Volume to be added to be 7,912 gallons

+3001-75 gallons.

The operator records 7,912 gallons ÷3001-75 gallons as the Desired BAT Volume in the Doer Calculation.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2010 Admin JPM Aib RO

- NUREG 1021, Revision 9

Appendix C Page 6 of 8 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2009 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:

2010 Admin JPM Al b RO

- NUREG 1021, Revision 9

Appendix C Page 7 of 8 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Desired Boron Concentration from COLR + 25 ppmB Desired Boron Concentration 2675 ppm (From COLR) + 25 ppmB = 2700 ppm

{(Desired Cb) (RHT Cb)} x {Desired Total Makeup Volume to FWST}

- = Desired BAT Volume (BAT Cb) (RHT Cb)

Given:

RHT Cb = 1076 ppm BAT Cb = 7234 ppm Desired Total Makeup Volume to FWST = Overflow volume Present volume (From Enclosure 4.3, Curve 7.7 of Unit I Core Data Book:)

390,000 gallons 360,000 gallons (440) = 30,000 gallons#

If the operator uses develops a gallonslinch volume from the information block on Curve 7.7, the operator will determine the makeup volume to be 31,277 gallons.

Volume at 484 inches 394,089 gallons Volume at 0 inches 15,638 gallons (394,089 gallons 15,638 gallons)1484 inches 781.92 gallonslinch OR Volume at 455.88 inches = 372,100 gallons Volume at 0 inches = 15,638 gallons (372,100 gallons 16, 638 gallons)/455.88 inches = 781.92 gallonslinch Therefore, 781.92 gallonslinch x 40 inches 31,276.80 gallons (This may be used as the makeup volume instead of 30,000 gallons).

If this volume is used, the calculation will result in a Desired BAT Volume below of 8132 gallons So:

{(Desired Cb)-(RHT Cb)} x {Desired Total Makeup Volume to FWST} = Desired BAT Volume (BAT Cb)-(RHT Cb)

{(2700)-(1076)} x {30000} = Desired BAT Volume (7234)-(i 076)

{i624} x {30000} = Desired BAT Volume 6158

.26 x {30000} = Desired BAT Volume or 7,912 gallons +300/-75 gallons OR between 7,837 and 8212 gallons 2010 Admin JPM Al b RO

- NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

The plant was at 100% power when a leak developed on the FWST.

FWST Level dropped to 440 inches before leak was isolated.

Enclosure 4.4, FWST Makeup Using the RHT, of OP111A162001014, Refueling Water System is in progress and completed through Step 3.9.

LCO 3.5.4, Refueling Water Storage Tank (RWST), was entered 10 minutes ago.

Chemistry has provided the following information:

BAT Boron Conc. = 7234 ppm

RHT Boron Conc.= 1076 ppm

FWST Make up Boron Concentration: Use COLR Minimum INflATING CUE: Determine the amount of Boric Acid needed to raise the FWST level to 480 using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/1/A16200/0i4, Refueling Water System.

NUREG 1021, Revision 9

Enclosure 4.4 OP/l/A/6200/o14 FWST Makeup Using RHT Page 1 of 9

1. Limits and Precautions

/ 1.1 Maximum FWST Tech Spec temperature limit is 100°F.

J1.2 Minimum FWST Tech Spec temperature limit is 70°F.

./i .3 All electrically operated engineered safeguard valves must be operated electrically after any manual operation.

/1.4 Maximum FWST level is 483 inches unless FWST overflow is required. (Overflows to SFP at 484 inches)

-Ji .5 NC System sampling during makeup to the FWST is prohibited.

2. Initial Conditions 6Li 2.1 Boron concentration control systems available per OP/1/A16 150/009 (Boron Concentration Control).

L-M 2.2 NB System aligned per OP/0/A/6200/003 (Boron Recycle System).

L-g 2.3 NI check valve test header alignment to FWST secured.

3. Procedure I21 3.1 Evaluate all outstanding R&Rs that may impact performance of this procedure.

3.2 Emergency Boration Flow is needed, secure makeup to FWST.

3.3 Notify Chemistry to sample RHT.

h 1

Kr /

Person Notified Date Time j A-3 .4 IF RHT is unacceptable for use, exit this enclosure.

SLi%1 3.5 Ensure that a pre-job briefing has been performed that includes discussion of reactivity SRO management concerns with this procedure.

3.6 j FWST in Recirculation per Enclosure 4.1 (FWST Recirculation Using 1A (1B)

FWST Recirc Pump), stop the following:

1A FWST Recirc Pump

lB FWST Recirc Pump 3.7 IF FWST in Recirculation with #1 FWST Pump, secure per Enclosure 4.6 (FWST Recirculation Using Unit 1 FWST Pump).

Unit 1

Enclosure 4.4 oP/1/A16200/o14 FWST Makeup Using RHT Page 2 of 9 IF FWST in Purification, secure per Enclosure 4.5 (FWST Purification).

3.9 Notify RP of change in FW System alignment. {PIP M97-0680}

Cl)fl i Person Notified Date Time 3.10 Determine amount of Boric Acid needed to raise makeup water to limits specified per IV Core Operating Limits Report (COLR): {PIP 2-M98-0017}

Desired Boron Concentration of Addition from COLR +25 ppmB margin = Desired Boron Cone

((Desired Boron Cone) (RHT Boron Conc) (Desired Total Makeup I I I = Desired BAT Volume (BAT Boron Cone) (Ri-IT Boron Cone) } Volume To FWST )

( ppmB) + 25 ppmB = ppmB Doer ppmB)( ppmB)(

Calculation I _gal ppmB,,)ii

=

ppmBj gal)

IV Calculation ppmB)( ppmB)( 1=

ppmB)( ppmB),iI gal)

U 3.11 Record initial FWST level on Attachment 1.

3.12 IF amount of boric acid to be added from Step 3.10 is zero, perform the following:

3.12.1 Ensure NC System Makeup aligned for auto makeup per OP/i /A/6 150/009 (Boron Concentration Control).

3.12.2 Go to Step 3.29.

Unit 1

Enclosure 4.4 oPIl/A162001014 FWST Makeup Using RHT Page 3 of 9 3.13 Add amount of Boric Acid calculated in Step 3.10 to FWST from Blender as follows:

3.13.1 Ensure closed one of the following:

1NI-96B (NI Chk Test Hdr C/I Outside)

OR

1NI-99 (Unit 1 NI Check Valve Test Hdr To FWST Isol) 3.13.2 Ensure locked closed, either:

3.13.2.1 1NS-70 (1A & lB NS HX Outlet To FWST Throttle)

OR 3.13.2.2 Both of the following:

1NS-8 (lB NS HX Outlet To FWST Isol) cv

*1NS-25 (1A NS HX Outlet To FWST Isol) cv D 3.13.3 Ensure closed 1NB-5 (Unit 1 Boric Acid Blender To NB System Isol).

(AB 733+6, KK-51, S End Ui VCT Hallway) 3.13.4 Open:

INV-172 (Unit 1 Boric Acid Blender To NB & FW Isol)

1NV-174 (Unit 1 Boric Acid Blender To FWST Isol) 3.13.5 Select MANUAL on NC Sys M/U Controller.

3.13.6 Ensure in STOP:

1A Rx M/U Water Pump

lB Rx M/U Water Pump 3.13.7 both BA Trans Pumps off, ensure in AUTO one of the following:

IA BA Trans Pump OR

lB BA Trans Pump Unit 1

Enclosure 4.4 oP/l/A16200/o14 FWST Makeup Using RUT Page 4 of 9 3.13.8 IF VCT is set up for automatic makeup, record current Setpoint(s) (SP) for the following:

Rx M/U Water Flow Control: gpm

BA Flow Control: gpm 3.13.9 Place Rx M/U Water Flow Control in manual and close.

NOTE: Total Makeup Flow and Boric Acid Flow Counters must be reset for NC Makeup System to operate.

3.14 Ensure the following reset to zero:

U Total Make Up Flow Counter U Boric Acid Flow Counter 3.15 Set Total Makeup Flow Counter to desired value.

3.16 Set Boric Acid Flow Counter to desired value.

NOTE: Valve leakage may occur causing input to the VCT.

U 3.17 Monitor the following parameters:

SM Pressure

Reactor Power

Tavg

Rod Motion 3.18 plant parameters indicate other than expected response, notify CRS.

NOTE: FWST level should be maintained less than 481 inches unless FWST overflow is required. (OAC Hi level alarm) 3.19 Momentarily select START on NC System Make Up.

U 3.20 Check lit NC System Makeup red light.

3.21 IF in AUTO, ensure BA Trans Pump starts.

3.22 Place BA Flow Control in manual and adjust to desired flow rate.

Unit 1

Enclosure 4.4 oP/1/AJ6200/o14 FWST Makeup Using RUT Page 5 of 9 3.23 HOLD until desired amount of boric acid added then perform the following:

3.23.1 IF in AUTO, ensure off:

1A BA Trans Pump

lB BA Trans Pump 3.23.2 Flush flow path for 5 minutes as follows:

3.23.2.1 Select OFF on NC Sys M/U Controller.

3.23.2.2 Close BA Flow Control.

3.23.2.3 Open Rx M/LJ Water Flow Control.

3.23.2.4 Select STOP on the following:

1A BA Trans Pump

lB BA Trans Pump 3.23.2.5 Select AUTO on one of the following:

lA Rx M/U Water Pump OR

lB Rx M/U Water Pump 3.23.2.6 Select MANUAL on NC System MIU Controller.

3.23 .2.7 Momentarily select START on NC System Make Up.

Q 3.23.2.8 Check lit NC System Makeup red light.

3.23.2.9 Ensure Rx M/U Water Pump starts.

3.23.2.10 HOLD until flush complete then select OFF on NC System Makeup.

3.24 Placeinauto:

BA Flow Control

Rx M/U Water Flow control 3.25 Close:

1NV-172 (Unit 1 Boric Acid Blender To NB & FW Isol)

1NV-174 (Unit I Boric Acid Blender To FWST Isol)

Unit 1

Enclosure 4.4 oP/1/A/6200/o14 FWST Makeup Using RHT Page 6 of 9 3.26 IF BAT to be in recirc, perform the following:

3.26.1 Select START on one of the following:

1A BA Trans Pump OR

lB BA Trans Pump LI 3.26.2 GotoStep3.28.

3.27 Select AUTO on one of the following:

1A BA Trans Pump OR

lB BA Trans Pump 3.28 Return the following controllers to values recorded in Step 3.13.8:

BA Flow Control (+1- 0.2 gpm)

Rx M/U Water Flow Control (+1- 0.2 gpm) 3.29 Select AUTO on NC Sys M/U Controller.

3.30 Momentarily select START on NC System Make Up.

LI 3.31 Check lit NC System Makeup red light.

3.32 Open:

1FW-22 (NB To Unit 1 FW Pump Disch Hdr Isol)

1FW-24 (Unit 1 FW Pump Disch To FWST Isol)

LI 3.33 Check closed 1FW-2 (Unit 1 FWST To Refueling Cavity Fill & Drn).

Unit 1

Enclosure 4.4 oP/1/A/6200/o14 FWST Makeup Using RUT Page 7 of 9 3.34 Notify Radwaste Chemistry to perform the following:

I Person Notified Date Time 3.34.1 Operate the following as required:

LI 1NB-126 (NB Evap Feed Pumps RHT Contents Transfer Isol)

LI 1NB-127 (NB Evap Feed Pumps Disch Isol To Ui & U2 FWST)

LI 3.34.2 Operate both Recycle Evaporator Feed Pumps to complete makeup from RHT.

3.35 HOLD until FWST is at desired level.

3.36 Notify Radwaste Chemistry to operate Recycle Evaporator Feed Pumps as desired.

/

Person Notified Date Time 3.37 Close:

1 FW-22 (NB To Unit 1 FW Pump Disch Hdr Isol)

1FW-24 (Unit 1 FW Pump Disch To FWST Isol) 3.38 Notify Radwaste Chemistry to close:

/

Person Notified Date Time LI 1NB-126 (NB Evap Feed Pumps RHT Contents Transfer Isol)

LI 1NB-127 (NB Evap Feed Pumps Disch Isol To Ui & U2 FWST)

LI 3.39 Record final FWST level on Attachment 1.

LI 3.40 Record in Auto Log final blender contents, either:

LI Rx Makeup Water OR LI Blend OR

LI Boric Acid Unit 1

Enclosure 4.4 IAJ6200/014 1

OPI FWST Makeup Using RUT Page 8 of 9 D 3.41 Place routing stamp in remarks section of cover sheet, check (V) Engineering and fill in Attachment 1 only.

3.42 IF desired to align for automatic NC System Makeup, align per OP/l/A161501009 (Boron Concentration Control).

3.43 IF FWST Recirc Pump stopped in Step 3.6, start one of the following:

IA FWST Recirc Pump OR

I B FWST Recirc Pump 3.44 IF FWST Recirculation with #1 FWST Pump is desired, place FWST in Recirculation per Enclosure 4.6 (FWST Recirculation Using Unit 1 FWST Pump).

3.45 IF FWST Purification is desired, place FWST in Purification per Enclosure 4.5 (FWST Purification).

Unit 1

Enclosure 4.4 OPI1/A16200/014 FWST Makeup Using RuT Page 9 of 9 Attachment 1 FWST Makeup Data Initial FWST Level inches Date Time Final FWST Level inches Date Time Data Collected By End of Enclosure Unit 1

MCEI-0400-232 Page 26 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.11 RCS Pressure, Temperature and Flow Limits for DNB (1S 3.4.1) 2.11.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.

2.12 Accumulators TS 3.5.1) 2.12.1 Boron concentration limits during MODES I and 2, and MODE 3 with RCS pressure >1000 psi:

Parameter Limit Accumulator minim irn boron concentration. *2,475. ppm Accumulator maximum boron concentration. 2,875 ppm 2.13 Refueling.Water Storage Tank RWST TS 3.5.4) 2.13.1 Boron concentration limits during MODES 1,2, 3, and 4:

Parameter Limit RWST minimum boron concentration. 2,675 ppm RWST maximum boron concentration. 2,875 ppm

MCEI-0400-232 Page 26 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.11 RCS Pressure, Temperature and Flow Limits for DNB (TS 3.4.1) 2.11.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.

2.12 Accumulators (IS 3.5.1) 2.12.1 Boron concentration limits during MODES I and 2, and MODE 3 with RCS pressure >1000 psi:

Parameter Limit Accumulator minimum boron concentration. V 2,475. ppm

- Accumulator maximum boron concentration. 2,875 ppm 2.1.3 RefuelingWater Storage Tank RWST tS 3.5.4) 2.13.1 Boron concentration limits during MODES 1,2, 3, and 4:

Parameter Limit RWST minimum boron concentration. 2,675 ppm RWST maximum boron concentration. 2,875 ppm

NIT1 IAI6100/22 E. OSURE 4.3 CURVE 7.7 REFUELING WATER STORAGE TANK LEVEL (VOLUME vs. TANK LEVEL) 00000

= I I-350000 484 inches = 394,089 gallons (overflow) 455.88 inches = 372,100 gallons 300000 0 inches = 15,638 gallons 250000 0

-J

-4

2. 200000 -

LU 150000 100000*

50000*

zzr zE 0.

0 100 200 300 400 500 INSTRUMENT INDICATION (INCHES WATER)

This data is also available on the OAC, UNIT 1

IA/6100/22

\IIT1 L OSURE 4.3 CURVE 7.7 REFUELING WATER STORAGE TANK LEVEL (VOLUME vs. TANK LEVEL) 400000 I ==z:i_-_:

zzzEpz I 350000 484 inches 394,089 gallons (overflow) 455.88 inches = 372,100 gallons ZZE 300000 0 inches = 15,638 gallons 250000 0

A

-J 200000

=========

-1J

= zzz:zz :zzz zz 150000 74 -

LZEEZZEEZZZEZ ZZEE EE 100000 !

JZ EE ZZZZ ZZ ZZ 50000 0

0 100 200 300 400 500.

INSTRUMENT INDICATION (INCHES WATER)

This data is also available on the OAC. UNIT 1

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Aib SRO 2010 Admin JPM Al b SRO

- NUREG 1021 Revision 9

Appendix C Page 2 of 10 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.: 217MFW002 Task

Title:

Determine Boric Acid Addition to JPM No.: 2010 Admin JPM Al b FWST SRO K/A

Reference:

GK/A 2.1.25 (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:

The plant was at 100% power when a leak developed on the FWST.

FWST Level dropped to 440 inches before leak was isolated.

Enclosure 4.4, FWST Makeup Using the RHT, of OP/i/A16200/014, Refueling Water System is in progress and completed through Step 3.9.

LCO 3.5.4, Refueling Water Storage Tank (RWST), was entered 10 minutes ago.

Chemistry has provided the following information:

BAT Boron Conc. = 7234 ppm

RHT Boron Conc.= 1076 ppm

FWST Make up Boron Concentration: Use COLR Minimum

The BOP has just completed the Doer Calculation of Step 3.10 of Enclosure 4.4, FWST Makeup Using the RHT, and has asked you to perform an Independent Verification on the calculation.

2010 Admin JPM Aib SRO

- NUREG 1021, Revision 9

Appendix C Page 3 of 10 Form ES-C-i Job Performance Measure Worksheet Task Standard: The operator will calculate the amount of Boric Acid that must be added from the BAT to refill the FWST is 7,912 gallons +300/-75 gallons, determine that the BOP made two errors in the original calculation, and identify that Technical Specification ACTION C is now applicable.

Required Materials: Calculator Reference Cart with all identified General References.

General

References:

OP/I /A/620010 14, Refueling Water System McGuire Core Operating Limits Report (Cycle 21)

McGuire U-i Data Book McGuire Technical Specifications McGuire Selected Licensee Commitment Manual OMP 8-2, Component Verification Techniques Handouts: Enclosure 4.4 of OP/1/A/6200/014, Refueling Water System, marked up for place-keeping and the Doer Calculation of Step 3.10 as follows:

Initial Conditions 2.1 -2.3 are initialed.

Procedure Step 3.1 Box checked.

Procedure Step 3.2 Left blank (Conditional step).

Procedure Step 3.3 initialed, Person Notified: CHEMIST, date/time:

present.

Procedure Step 3.4 NA, initialed.

Procedure Step 3.5 initialed.

Procedure Step 3.6 NA, initialed.

Procedure Step 3.7 NA, initialed.

Procedure Step 3.8 NA, initialed.

Procedure Step 3.9 initialed, Person Notified: R.P. TECH, date/time: present.

Procedure Step 3.10 initialed.

Doer Calculation:

(2875 ppmB + 25 ppmB = 2900 ppmB

{ (2900 ppmB) (1076 ppmB) }{15,000}

4443 gal (7234 ppm B) (1076 ppm B)

McGuire 1 Cycle 21 Core Operating Limits Report (Page 26 of 32)

McGuire Technical Specifications OP/1/A16100/22, Enclosure 4.3, Curve 7.7, Refueling Water Storage Tank Level (Volume vs. Tank Level) 2010 Admin JPM Aib SRO

- NUREG 1021, Revision 9

Appendix C Page 4 of 10 Form ES-C-I Job Performance Measure Worksheet Initiating Cue: Perform the Independent Verification (IV) of the calculation in Step 3.10 of Enclosure 4.4 to confirm the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480 using the RHT.

AFTER the calculations have been completed and verified in the FWST make up procedure, an 80 gpm Makeup is started to the FWST, and continues for I hour.

At the end of this 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period:

What is the status of compliance with LCO 3.54?

FWST Temperature = 85 Deg FWST [B] = 2775 ppm Time Critical Task: NO Validation Time: 15 minutes 2010 Admin JPM AIb SRO

- NUREG 1021, Revision 9

Appendix C Page 5 of 10 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout all four (4) identified Handout documents, marked up as described.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

1 (Step 3.10) Determine the The operator refers to the amount of Boric Acid COLR, Section 2.13.1 on needed to raise makeup Page 26 of 32 and water to the limits specified determines that the in the Core Operating Limits minimum boron Report (COLR). concentration to be used in the calculation is 2675 ppm, and NOT 2875 ppm used by BOP ( St 1

Error).

The operator records 2675 ppm in the first line (Desired Boron Concentration of Addition from COLR) of the IV calculation in Step 3.10 of Enclosure 4.4.

2 (Ist Bullet) Desired Boron The operator adds an Concentration of Addition additional 25 ppm and from COLR ÷ 25 ppmB determines Desired Boron margin = Desired Boron Concentration to be 2700 Concentration ppm.

The operator records 2700 ppm in the 2nd line (Desired Boron Conc) of the IV calculation in Step 3.10 of Enclosure 4.4.

3 d 2

(

Bullet) The operator identifies

{(Desired Cb) (RHT Cb)}

Desired Cb = 2700 from (BAT Cb) (RHT Cb) previous Step and records.

x {Desired Total The operator recognizes Makeup Volume to that RHT Cb = 1076 ppm FWST} and records Initial Conditions).

= Desired BAT Volume 2010 Admin JPM Alb 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 The operator recognizes (CONTD) that BAT Cb = 7234 ppm and records (Initial Conditions).

The operator addresses 0P111A16100122, Enclosure 4.3, Curve 7.7, and determines from graph that total makeup volume is 30,000 by comparing 480 volume of 390,000 gallons to the 440 volume of 360,000 gallons.

The operator records 30,000 (+1300#) gallons; and NOT 15,000 gallons used by the BOP (2 Error).

The operator records 30,000 (+1300#) gallons in the IV Calculation.

The operator calculates the Desired BAT Volume to be added to be 7,912 gallons

+3001-75 gallons.

The operator records 7,912 gallons +3001-75 gallons as the Desired BAT Volume in the IV Calculation.

2OlOAdmin-JPMA1bSRO NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

4 (Technical Specification The operator observes TS LCO 3.5.4) The RWST shall LCO 3.5.4 and determines be OPERABLE. that ACTION B was entered at the start of the JPM action was necessary within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to restore volume.

The operator determines that the FWST Volume TS Limit is 372,100 gallons.

The operator determines that 12,100 gallons must be added to the FWST to comply with this ACTION Statement, and that in one hour 4800 gallons will be added.

The operator identifies that ACTION C is now applicable.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2010 Admin JPM Al b SRO

- NUREG 1021, Revision 9

Appendix C Page 8 of 10 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 Admin JPM Aib SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2010 Admin JPM Aib SRO

- NUREG 1021, Revision 9

Appendix C Page 9 of 10 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Desired Boron Concentration from COLR + 25 ppmB = Desired Boron Concentration 2675 ppm (From COLR) + 25 ppmB = 2700 ppm

{(Desired Cb) (RHT Cb)} x {Desired Total Makeup Volume to FWST}

= Desired BAT Volume (BAT Cb) (RHT Cb)

Given:

RHT Cb = 1076 ppm BAT Cb = 7234 ppm Desired Total Makeup Volume to FWST Overflow volume Present volume (From Enclosure 4.3, Curve 7.7 of Unit 1 Core Data Book:)

390,000 gallons 360,000 gallons (440) = 30,000 gallons#

If the operator uses develops a gallonslinch volume from the information block on Curve 7.7, the operator will determine the makeup volume to be 31,277 gallons.

Volume at 484 inches = 394,089 gallons Volume at 0 inches = 15,638 gallons (394,089 gallons 15,638 gallons)/484 inches 781.92 gallons/inch OR Volume at 455.88 inches = 372,100 gallons Volume at 0 inches = 15,638 gallons (372,100 gallons 15, 638 gallons)/455.88 inches = 781.92 gallons/inch Therefore, 781.92 gallonslinch x 40 inches 31,276.80 gallons (This may be used as the makeup volume instead of 30,000 gallons).

If this volume is used, the calculation will result in a Desired BAT Volume below of 8132 gallons So:

{(Desired Cb)-(RHT Cb)} x {Desired Total Makeup Volume to FWST} = Desired BAT Volume (BAT Cb)-(RHT Cb)

{(2700)-(1 076)} x {30000} Desired BAT Volume (7234)-(1 076)

{1624} x {30000} = Desired BAT Volume 6158

.26 x {30000} = Desired BAT Volume or 7,912 gallons +3001-75 gallons OR between 7,837 and 8212 gallons 2010 Admin JPM Al b SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

The plant was at 100% power when a leak developed on the FVVST.

FWST Level dropped to 440 inches before leak was isolated.

Enclosure 4.4, FWST Makeup Using the RHT, of 0P111A162001014, Refueling Water System is in progress and completed through Step 3.9.

LCO 3.5.4, Refueling Water Storage Tank (RWST), was entered 10 minutes ago.

Chemistry has provided the following information:

BAT Boron Conc. 7234 ppm

RHT Boron Conc.= 1076 ppm

FWST Make up Boron Concentration: Use COLR Minimum

The BOP has just completed the Doer Calculation of Step 3.10 of Enclosure 4.4, FWST Makeup Using the RHT, and has asked you to perform an Independent Verification on the calculation.

INITIATING CUE: Perform the Independent Verification (IV) of the calculation in Step 3.10 of Enclosure 4.4 to confirm the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480 using the RHT.

AFTER the calculations have been completed and verified in the FWST make up procedure, an 80 gpm Makeup is started to the FWST, and continues for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

At the end of this 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period:

What is the status of compliance with LCO 3.5.4?

FWST Temperature = 85 Deg FWST [B] = 2775 ppm NUREG 1021, Revision 9

Enclosure 4.4 oPIl/A!6200/o14 FWST Makeup Using RHT Page 1 of 9

1. Limits and Precautions

/1.1 Maximum FWST Tech Spec temperature limit is 100°F.

J 1.2 Minimum FWST Tech Spec temperature limit is 70°F.

/1.3 All electrically operated engineered safeguard valves must be operated electrically after any manual operation.

11.4 Maximum FWST level is 483 inches unless FWST overflow is required. (Overflows to SFP at 484 inches)

J1 .5 NC System sampling during makeup to the FWST is prohibited.

2. Initial Conditions 2.1 Boron concentration control systems available per OP/l/AI6150/009 (Boron Concentration Control).

2.2 NB System aligned per OP/0/A16200/003 (Boron Recycle System).

2.3 NI check valve test header alignment to FWST secured.

3. Procedure 3.1 Evaluate all outstanding R&Rs that may impact performance of this procedure.

3.2 IF Emergency Boration Flow is needed, secure makeup to FWST.

3.3 Notif Chemistry to sample RHT.

Icinr flci /

Person Notifiect Date Time

.4 IF RHT is unacceptable for use, exit this enclosure.

3.5 Ensure that a pre-job briefing has been performed that includes discussion of reactivity SRO management concerns with this procedure.

IF FWST in Recirculation per Enclosure 4.1 (FWST Recirculation Using 1A (1B)

FWST Recirc Pump), stop the following:

1A FWST Recirc Pump

lB FWST Recirc Pump 3.7 FWST in Recirculation with #1 FWST Pump, secure per Enclosure 4.6 (FWST Recirculation Using Unit 1 FWST Pump).

Unit 1

Enclosure 4.4 oP/lIAJ6200/o14 FWST Makeup Using RHT Page 2 of 9 IF FWST in Purification, secure per Enclosure 4.5 (FWST Purification).

LM 3.9 Notif RP of change in FW System alignment. {PIP M97-0680}

/

Person Notified Date Time 9-M 3.10 Determine amount of Boric Acid needed to raise makeup water to limits specified per IV Core Operating Limits Report (COLR): {PIP 2-M98-0017}

Desired Boron Concentration of Addition from COLR + 25 ppmB margin = Desired Boron Conc

((Desired Boron Conc) (RHT Boron Concfl (Desired Total Makeup (BAT Boron Conc) (RHT Boron Conc) )I I Desired BAT Volume Volume To FWST )

P75

( ppmB) +25 ppmB 9oc ppmB Doer Calculation (( ppmB)( /o7(p ppmB)(

rn V3 gal 73 ppmB)( ji,çi, ppmB)JL\ 15,ooo gal,)

IV + 25 ppmB = ppmB Calculation ppmB) ( ppmB)

(

ppmB) ( ppmB)) gal)

=

Q 3.11 Record initial FWST level on Attachment 1.

3.12 IF amount of boric acid to be added from Step 3.10 is zero, perform the following:

3.12.1 Ensure NC System Makeup aligned for auto makeup per OP/1/A16150/009 (Boron Concentration Control).

3.12.2 Go to Step 3.29.

Unit 1

Enclosure 4.4 oP/1/A162001014 FWST Makeup Using RUT Page 3 of 9 3.13 Add amount of Boric Acid calculated in Step 3.10 to FWST from Blender as follows:

3.13.1 Ensure closed one of the following:

1NI-96B (NI Chk Test Hdr C/I Outside)

OR

1NI-99 (Unit 1 NI Check Valve Test Hdr To FWST Isol) 3.13.2 Ensure locked closed, either:

3.13.2.1 1NS-70 (1A & lB NS HX Outlet To FWST Throttle)

OR 3.13.2.2 Both of the following:

1NS-8 (lB NS HX Outlet To FWST Isol) cv

1NS-25 (1A NS HX Outlet To FWST Isol) cv LI 3.13.3 Ensure closed 1NB-5 (Unit 1 Boric Acid Blender To NB System Isol).

(AB 733+6, KK-51, S End Ui VCT Hallway) 3.13.4 Open:

1NV-172 (Unit 1 Boric Acid Blender To NB & FW Isol)

1NV-174 (Unit 1 Boric Acid Blender To FWST Isol) 3.13.5 Select MANUAL on NC Sys M/U Controller.

3.13.6 Ensure in STOP:

1A Rx M/U Water Pump

lB Rx M/U Water Pump 3.13.7 j both BA Trans Pumps off, ensure in AUTO one of the following:

1A BA Trans Pump OR

lB BA Trans Pump Unit 1

Enclosure 4.4 0P111A16200/014 FWST Makeup Using RUT Page 4 of 9 3.13.8 VCT is set up for automatic makeup, record cunent Setpoint(s) (SP) for the following:

Rx M/U Water Flow ControlH: gpm

BA Flow ControP:

t gpm 3.13.9 Place Rx M/U Water Flow Control in manual and close.

NOTE: Total Makeup Flow and Boric Acid Flow Counters must be reset for NC Makeup System to operate.

3.14 Ensure the following reset to zero:

O Total Make Up Flow Counter U Boric Acid Flow Counter 3.15 Set Total Makeup Flow Counter to desired value.

3.16 Set Boric Acid Flow Counter to desired value.

NOTE: Valve leakage may occur causing input to the VCT.

U 3.17 Monitor the following parameters:

SM Pressure

Reactor Power

Tavg

Rod Motion 3.18 IF plant parameters indicate other than expected response, notify CRS.

NOTE: FWST level should be maintained less than 481 inches unless FWST overflow is required. (OAC Hi level alarm) 3.19 Momentarily select STARV on NC System Make Up.

U 3.20 Check lit NC System Makeup red light.

3.21 IF in AUTO

, ensure BA Trans Pump starts.

T 3.22 Place BA Flow Control in manual and adjust to desired flow rate.

Unit 1

Enclosure 4.4 oP/l/AI6200Iol4 FWST Makeup Using RHT Page 5 of 9 3.23 HOLD until desired amount of boric acid added then perform the following:

3.23.1 IF in AUTO, ensure off:

1A BA Trans Pump

lB BA Trans Pump 3.23.2 Flush flow path for 5 minutes as follows:

3.23.2.1 Select OFF on NC Sys M/U Controller.

3.23.2.2 Close BA Flow Control??.

3.23.2.3 Open Rx M!U Water Flow Control.

3.23.2.4 Select STOP on the following:

1A BA Trans Pump

lB BA Trans Pump 3.23.2.5 Select AUTO on one of the following:

1A Rx M/U Water Pump OR

1BRxM/UWaterPump 3.23.2.6 Select MANUAL on NC System M/LT Controller.

3.23 .2.7 Momentarily select START on NC System Make Up.

U 3.23.2.8 Check lit NC System Makeup red light.

3.23.2.9 Ensure Rx M!U Water Pump starts.

3.23.2.10 HOLD until flush complete then select OFF on NC System Makeup.

3.24 Placeinauto:

BA Flow Control

Rx M/U Water Flow control 3.25 Close:

1NV-172 (Unit 1 Boric Acid Blender To NB & FW Isol)

1NV-174 (Unit 1 Boric Acid Blender To FWST Isol)

Unit 1

Enclosure 4.4 OPI1/A16200/014 FWST Makeup Using RHT Page 6 of 9 3.26 IF BAT to be in recirc, perform the following:

3.26.1 Select START on one of the following:

1A BA Trans Pump OR

lB BA Trans Pump 0 3.26.2 Go to Step 3.28.

3.27 Select AUTO on one of the following:

1A BA Trans Pump OR

lB BA Trans Pump 3.28 Return the following controllers to values recorded in Step 3.13.8:

BA Flow Control (+1- 0.2 gpm)

Rx M!U Water Flow Control (+1- 0.2 gpm) 3.29 Select AUTO on NC Sys MIU Controller.

3.30 Momentarily select START on NC System Make Up.

0 3.31 Check lit NC System Makeup red light.

3.32 Open:

1FW-22 (NB To Unit 1 FW Pump Disch Hdr Isol)

1FW-24 (Unit 1 FW Pump Disch To FWST Isol) 0 3.33 Check closed IFW-2 (Unit 1 FWST To Refueling Cavity Fill & Drn).

Unit 1

Enclosure 4.4 OP/l/A16200/014 FWST Makeup Using RHT Page 7 of 9 3.34 Notify Radwaste Chemistry to perform the following:

/

Person Notified Date Time 3.34.1 Operate the following as required:

LI 1NB-126 (NB Evap Feed Pumps RHT Contents Transfer Isol)

LI 1NB-127 (NB Evap Feed Pumps Disch Isol To Ui & U2 FWST)

LI 3.34.2 Operate both Recycle Evaporator Feed Pumps to complete makeup from RHT.

3.35 HOLD until FWST is at desired level.

3.36 Notify Radwaste Chemistry to operate Recycle Evaporator Feed Pumps as desired.

/

Person Notified Date Time 3.37 Close:

1FW-22 (NB To Unit 1 FW Pump Disch Hdr Isol)

1FW-24 (Unit 1 FW Pump Disch To FWST Isol) 3.38 Notify Radwaste Chemistry to close:

/

Person Notified Date Time O 1NB-126 (NB Evap Feed Pumps RHT Contents Transfer Isol) 0 1NB-127 (NB Evap Feed Pumps Disch Isol To Ui & U2 FWST) 0 3.39 Record final FWST level on Attachment 1.

LI 3.40 Record in Auto Log final blender contents, either:

O Rx Makeup Water OR LI Blend OR 0 Boric Acid Unit 1

Enclosure 4.4 0P111A16200/o14 FWST Makeup Using RuT Page 8 of 9 El 3.41 Place routing stamp in remarks section of cover sheet, check (v) Engineering and fill in Attachment 1 only.

3.42 IF desired to align for automatic NC System Makeup, align per OP/1/A16150/009 (Boron Concentration Control).

3.43 jj FWST Recirc Pump stopped in Step 3.6, start one of the following:

1A FWST Recirc Pump OR

lB FWST Recirc Pump 3.44 IF FWST Recirculation with #1 FWST Pump is desired, place FWST in Recirculation per Enclosure 4.6 (FWST Recirculation Using Unit 1 FWST Pump).

3.45 IF FWST Purification is desired, place FWST in Purification per Enclosure 4.5 (FWST Purification).

Unit 1

Enclosure 4.4 OPI1/A16200/014 FWST Makeup Using RHT Page 9 of 9 Attachment 1 FWST Makeup Data Initial FWST Level inches Date Time Final FWST Level inches Date Time Data Collected By End of Enclosure Unit 1

MCEI-0400-232 Page 26 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.11 RCS Pressure, Temperature and Flow Limits for DNB (TS 3.4.1) 2.11.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.

2.12 Accumulators (TS 3.5.1) 2.12.1 Boron concentration limits during MODES 1 and 2, and MODE 3 with RCS pressure >1000 psi:

Parameter Limit Accumulator minimum boron concentration. *2,475. ppm Accumulator maximum boron concentration. 2,875 ppm 2.13 Refueling.Water Storage Tank RWST çrs 3.5.4) 2.13.1 Boron concentration limits during MODES 1,2, 3, and 4:

Parameter Limit RWST minimum boron concentration. 2,675 ppm RWST maximum boron concentration. 2,875 ppm

MCEI-0400-232 Page 26 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.11 RCS Pressure, Temperature and Flow Limits for DNB (ES 3.4.1) 2.11.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.

2.12 Accumulators (TS 3.5.1) 2.12.1 Boron concentration limits during MODES 1 and 2, and MODE 3 with RCS pressure >1000 psi:

Parameter Limit Accumulator minim tim boron concentration.

2,475 ppm Accumulator maximum boron concentration.

2,875 ppm 2.13 Refueling.Water Storage Tank RWST (TS 3.5.4) 2.13.1 Boron concentration limits during MODES 1,2, 3, and 4:

Parameter Limit RWST minimum boron concentration. 2,675 ppm RWST maximum boron concentration. 2,875 ppm

\1IT1 C /A/6100/22

1. OSURE 4.3 CURVE 7.7 REFUELING WATER STORAGE TANK LEVEL (VOLUME vs. TANK LEVEL)

L100000

===_i_===-_j-_ -

350000 484 inches = 394,089 gallons (overflow) 455.88 inches = 372,100 gallons 300000 0 inches = 15,638 gallons U,

z 250000 0

.1

= = === .

ZrZrZrZEE :rzzz z

-J Zr 200000 zrz UJ zzrzzzz-zz

-J Zr Zr Zr Zr 0 150000 -

ZrErEZZZrZrZrZrZrZrZrzZrZr_

z.zzr:z:z:.r 100000 Zr ZrZrJ Zr Zr Zr Zr Zr Zr Zr Zr Zr Zr Zr Zr Zr Zr Zr 50000 -

Z Zr Zr Zr -

0 0 100 200 300 400 500 INSTRUMENT INDICATION (INCHES WATER)

This data is also available on the GAO. UNiT 1

NIT1 IA/6100/22 L 0SURE 4.3 CURVE 7.7 REFU ELING WATER STORAGE TANK LEVEL (VOLUME vs. TANK LEVEL) 400000 -

350000 484 inches = 394,089 gallons (overflow) 455.88 inches = 372,100 gallons 300000 0 inches = 15,638 gallons Cr) z 250000 0

-J F

)

(D 200000

= ..zz.zzzzzz JEJZ.ZE

-J 0 150000 Z.Z ZZZZZEZZ_ ZZZEZZZZ 100000 .

Z 50000 0-0 100 200 300 400 500.

INSTRUMENT INDICATION (INCHES WATER)

This data is also available on the GAG.

UNIT 1

Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA2RO 2010 Admin JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 2 of 12 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Perform a Manual NC Leakage JPM No.: 2010 Admin JPM A2 Calculation RO K/A

Reference:

GK/A 2.2.12 (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: Unit 1 is at 100% power.

The Unit 1 QAC point Ml L4554 is out of service.

PT/i/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.

A manual NC System leakage calculation is in progress in accordance with PT/i /A/41 50/OOIB (Reactor Coolant Leakage Calculation)

Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/i/A/4i50/OOiB (Reactor Coolant Leakage Calculation) has been completed through Step 1.9.

Task Standard: The operator will complete all calculations in accordance with the attached Key, and identify that the Unidentified RCS Leakage Technical Specification has been exceeded.

Required Materials: None.

General

References:

PT/i/A/4200/040 (Reactor Coolant Leakage Detection)

PT/i/A/4i 50/001 B (Reactor Coolant Leakage Calculation)

McGuire Unit I Technical Specifications 2010 Admin JPM A2 RO

- NUREG 1021, Revision 9

Appendix C Page 3 of 12 Form ES-C-i Job Performance Measure Worksheet Handouts: PTIIIAI4I5OIOO1B (Reactor Coolant Leakage Calculation) marked up as follows:

Step 7.1 Initialed Steps 8.1 through 8.5 Initialed.

Step 12.1 Enclosure 13.2 Checkbox is checked.

PT/i IAI4i 50/001 B (Reactor Coolant Leakage Calculation) Enclosure 13.2 (NC Leakage Determinations Using Manual Calculations) marked up as follows:

Step 1.1 Checkbox is checked/Initialed.

Step 1.2 Initialed.

Step 1.3 Initialed.

Determine VCT Purge Status Checkbox is checked.

Secured Checkbox is checked.

NC System leakage calculation is in progress Checkbox is checked.

To refrain from sampling Checkbox is checked.

Person Notified Mike Smith Todays Date/Time Step 1.4 Initialed.

NC System leakage calculation is in progress Checkbox is checked.

To check that NC sample Checkbox is checked.

NC System sampling Checkbox is checked.

Person Notified Melvin Smith Todays Date/Time Step 1.5Initialed.

Step 1.6 All Checkboxes checked/Initialed.

Step 1.7 Initialed.

Step 1.7.1 Initialed.

Step 1.7.2 Initialed.

Step 1.8 Initialed.

Step 1.9 Initialed.

Enclosure 13.3 (NCDT Volume) of PT/1/A4150/OO1B (Reactor Coolant Leakage Calculation)

Enclosure 13.4 (PRT Volume) of PT/1/A/4150/OOIB (Reactor Coolant Leakage Calculation)

Time Critical Task: NO 2010 Admin JPM A2 RO

- NUREG 1021, Revision 9

Appendix C Page 4 of 12 Form ES-C-i Job Performance Measure Worksheet Validation Time: 20 minutes 2010 Admin JPM A2 RO

- NUREG 1021, Revision 9

Appendix C Page 5 of 12 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial ConditionslCue, and associated Datasheet (Last two (2)

Pages of this JPM); and Handout PTIIIAI4I5O!OOIB procedure body marked up as described, Enclosure 13.2 marked up as described, Enclosure 13.3 and Enclosure 13.4.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT I (Enclosure 13.2, Steps The operator transposes 1.10.1 through 13,22,26 raw data from the Data and 1.11.1) Sheet provided.

Record raw data.

2 (Enclosure 13.2, Step The operator calculates the 1.10.14) Calculate change change in NC System Tave in NC System Tave: to be 0°F, and records.

3 (Enclosure 13.2, Step The operator calculates the 1.10.15) Calculate VCT VCT Leakage Rate to be Leakage Rate: 1.55 qpm, and records.

4 (Enclosure 13.2, Step The operator calculates the 1 .10.16) Calculate PZR PZR Leakage Rate to be Leakage Rate: 0.02 gpm, and records.

5 (Enclosure 13.2, Step The operator calculates the 1 .10.17) Calculate Total Total Leakage to be 1.57 Leakage: nrn and records.

2010 Admin JPM A2 RO

- NUREG 1021, Revision 9

Appendix C Page 6 of 12 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Enclosure 13.2 Step The operator uses 1.10.18) Using Enclosure Enclosure 13.4 and an 13.4 (PRT Volume) record initial PRT Level of 76.0 %,

the following: and determines that initial PRT Volume is 10636.1 Initial PRT Volume j, and records.

Final PRT Volume The operator uses Enclosure 13.4 and interpolates a PRT Volume for 76.1% to be 10649.5 j, and records.

7 (Enclosure 13.2, Step The operator calculates the 1.10.19) Calculate PRT PRT Leakage Rate to be Leakage Rate: 19 gpm, and records.

8 (Enclosure 13.2, Step 1.10. The operator uses

20) Using Enclosure 13.3 Enclosure 13.3 and an (NCDT Volume), record the initial NCDT Level of 30.0%,

following: and determines that initial Initial NCDT Volume NCDT Volume is 105.9 gal,

. and records.

Final NCDT Volume The operator uses Enclosure 13.3 and a final NCDT Level of 33.0%, and determines that final NCDT Volume is 116.2 gal, and records.

9 (Enclosure 13.2, Step The operator calculates the 1.10.21) Calculate NCDT NCDT Leakage Rate to be Leakage Rate: 14 gpm, and records.

10 (Enclosure 13.2, Step The operator calculates the 1.10.23) Calculate Total Total Background Leakage Background Leakage: to be 0 gpm, and records.

2010 Admin JPM A2 RO

- NUREG 1021, Revision 9

Appendix C Page 7 of 12 Form ES-C-i

. PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

1 1 (Enclosure 13.2, Step The operator calculates the 1.10.24) Calculate Identified Identified Leakage to be Leakage: 0.33 (+/-10%) qpm, and records.

12 (Enclosure 13.2, Step The operator calculates the 1.10.25) Calculate Unidentified Leakage to be Unidentified Leakage: 1.24 (+/-10%) gpm, and records.

13 (Enclosure 13.2, Step The operator calculates the 1.10.26) Determine Total Total NC Pumps #1 Seal NC Pump #1 Seal Leakoff: Leakoff to be 12.8 (+/-10%)

nrn and records.

14 (Enclosure 13.2, Step The operator calculates the 1.10.27) Calculate Total Total Accumulative Accumulative Leakage: Leakage to be 14.37

(+/-10%) qpm, and records.

15 (Enclosure 13.2) Calculated The operator places their By? Date?Time: name in the Calculated by BLOCK, and signs.

The operator enters the Date and Time.

2010 Admin JPM A2 RO

- NUREG 1021, Revision 9

Appendix C Page 8 of 12 Form ES-C-I PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

16 Technical Specification The operator returns the LCO 3.4.13: completed Enclosure 13.2 and reports that LCO 3.4.13 RCS operational LEAKAGE has been exceeded shall be limited to: because there is greater than 1 gpm unidentified

a. No pressure boundary LEAKAGE.

LEAKAGE;

b. 1 gpm unidentified Examiner NOTE LEAKAGE See KEY on Page 9 of this c 10 gpm identified JPM LEAKAGE

d. 389 gallons per day total primary to secondary LEAKAGE through all steam generators (SGs); and

e. 135 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY:

MODES 1, 2, 3, and 4.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2010 Admin JPM A2 RO

- NUREG 1021, Revision 9

Appendix C Page 9 of 12 Form ES-C-i VERIFICATION OF COMPLETION 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 Page 10 of 12 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Enclosure 13.2, Step 1.10.14 (JPM Step 2): Change in NC System Tave:

584.8°F 584.8°F = 0°F Enclosure 13.2, Step 1.10.15 (JPM Step 3): VCT Leakage Rate:

(53.4% 47.6%) xl 9.3 gallons/%/72 minutes = 1.55 gallons per minute (gpm)

Enclosure 13.2, Step 1.10.16 (JPM Step 4): PZR Leakage Rate:

(54.9% 54.1%) x 132.5 gallons/% x .01613 /72 minutes = 0.02 gallons per minute (gpm)

Enclosure 13.2, Step 1.10.17 (JPM Step 5): Total Leakage:

1.55 gpm + 0.02 gpm 1.57 gpm Enclosure 13.2, Step 1.10.18 (JPM Step 6): PRT Final Volume:

(10770.4-10636.1)/10 = 13.43/.1% PRT Level, 10636.1 + 13.43 = 10649.53 (gal)

Enclosure 13.2, Step 1.10.19 (JPM Step 7): Total PRT Leakage:

(10649.5 gallons 10636.1 gallons)/72 minutes 0.19 gallons per minute (gpm)

Enclosure 13.2, Step 1.10.21 (JPM Step 9): Total NCDT Leakage:

(116.2 gallons 105.9 gallons)/72 minutes = 0.14 gallons per minute (gpm) 3.2, Step 1.10.23 (JPM Step 10): Total Background Leakage:

(0 gpm + 0 gpm) 0 gpm 3.2, Step 1.10.24 (JPM Step 11): Identified Leakage:

(.19 gpm + .14 gpm + 0 gpm) = 0.33 gpm 3.2, Step 1.10.25 (JPM Step 12): Unidentified Leakage:

(1.57 gpm .33 gpm) = 1.24 gpm

- 3.2, Step 1.10.26 (JPM Step 13): Total NC Pumps #1 Seal Leakoff:

(2.8 gpm + 3.6 gpm + 3.1 gpm + 3.3 gpm) = 12.8 gpm 3.2, Step 1.10.27 (JPM Step 14): Total Accumulative Leakage:

(.33 gpm + 1.24 gpm + 12.8 gpm) = 14.37 gpm LCO 3.4.13 (1 gpm unidentified LEAKAGE) has been exceeded.

2010 Admin JPM A2 RO NUREG 1021, Revision 9

Appendix C Form ES-C1 JPM CUE SHEET INITIAL CONDITIONS: Unit 1 is at 100% power.

The Unit 1 OAC point Ml L4554 is out of service.

PT/11A14200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.

A manual NC System leakage calculation is in progress in accordance with PT/11A141501001B (Reactor Coolant Leakage Calculation)

Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/i /A141 50/001 B (Reactor Coolant Leakage Calculation) has been completed through Step 1.9.

INITIATING CUE: Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, by performing Steps 1.10 and 1.11.

Indicate whether or not a Technical Specification has been exceeded.

NUREG 1021, Revision 9

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Duke Energy Procedure No.

McGuire Nuclear Station PT/l/A/4150/oo1 B Reactor Coolant Leakage Calculation Revision No.

067 Electronic Reference No.

MCOO47QI Continuous Use PERFORMANCE

* * * * * * * * *JJNCQNTROLLEDFORpRfl.4T* * * * * * * * * *

(ISSUED) PDF Format

PT/l/A/4150/001 B Page 2 of 7 Revision History (significant issues, limited to one page)

Rev 067 Changed format of procedure to split out calculation performed by OAC and performed by manual calculation. Combined leakage calculation using the OAC steps with current Enclosure 13.1 and renamed enclosure NC Leakage Calculation Using OAC.

Combined manual leakage calculation steps with Enclosure 13.2 and renamed enclosure NC Leakage Determination Using Manual Calculation.

Changed all references throughout procedure to include these format changes.

End. 13.5. Added Independent Verification sign offs for calculation of seven day rolling average of Unidentified Leakage. {PIP M-09-.1307}

Revised current steps for determining if Tier Two or Tier Three Action levels exceeded to reference step numbers associated with determination. Intent is to clarify steps.

Reworded steps that state IF directed by engineering to IF advised by engineering.

Definition of directed changed with new fatigue rule.

Added PIP M-09-1857 as an additional reference to NCP seal leakage basis.

Modified steps that begin with WHEN to reflect NSD 704 Rev 016 requirements.

Rev 066 Body of procedure.

Added a limit and precaution about manipulation of VA System during leakage calculation has an affect on VCT level.

Re-worded Step 12.6.17. The leakage calculation is considered valid after 60 minutes but is preferred to run up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The step as written requires the operator to print calculation after 60 minutes when 1 of 3 conditions met. This is procedure use and adherence issue. Re-worded step to give operator flexibility to print calculation summary between 60 minutes and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Re-worded Step 12.6.35. If operator performs section 12.6.16 to abort leakage calculation early, enclosure 13.1 is not performed. 12.6.35 directs operator to perform End. 13.5, however, this enclosure requires data from enclosure 13.1. Re-worded step to stipulate if unit at 100% RTP AND End. 13.1 completed, then perform End. 13.5.

Procedure use and adherence issue.

Rev 065

Added step to make operator aware that if leakage calc ran for greater than 30 minutes but less than 60 minutes, the data can still be valid if it meets certain conditions.

Added step to record status of VCT purge at beginning of procedure.

Added steps to take NV-137A hard to VCT and back to AUTO prior to starting leakage calculation.

End. 13.5. Reworded section if any Tier One, Two, or Three Action level is exceeded to make it easier to understand.

Unit 1

PT/1/A/4150/OO1 B Page 3 of 7 Reactor Coolant Leakage Calculation

1. Purpose To determine NC System Leakage using the Operator Aid Computer (OAC) or manual calculations to ensure Tech Spec requirements met.

2. References 2.1 Tech Spec TS SR 3.4.13.1, 3.4.13.2, TS 3.4.15 2.2 SLC 16.9.7 Standby Shutdown System 2.3 MCS-1274.OO-OO-0016 (License Renewal Basis Spec), Section 4.29 2.4 UFSAR Chapter 18 (Aging Management Program and Activities), Table 18-1, Reactor Coolant Operational Leakage Monitoring Program 2.5 SLC 16.7.6 Radiation Monitoring for Plant Operation 2.6 WCAP-16423-NP (Methodology for calculating Unidentified NC System leakage) 2.7 WCAP-16465-NP (Action levels and response guidelines for increasing Unidentifed NC System leakage less than Tech Spec limits) 2.8 MCC-1201.O1-OO-0053 (MNS Unit 1 & 2 NC Pump Response to Loss of Seal Cooling)

3. Time Required 3.1 One operator for three hours every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4. Prerequisite Test None

5. Test Equipment None Unit 1

PT/1/AJ4150/00l B Page4of7

6. Limits and Precautions 1 NC System Tave, Reactor Power, Containment Temperature, and SM Pressure should remain constant during calculation.

Positioning valves during calculation which could adversely affect results will invalidate the calculation.

Performing Leakage Calculation between 3 am and 8 am on Wednesdays may cause calculation to fail due to OAC weekly backup routine.

Performing PT/l/A/4200/019 (ECCS Pump and Piping Vent) during calculation could adversely affect results and will invalidate the calculation.

d Manipulation of VA System should be avoided while performing Leakage Calculation due to affect on VCT level.

7. Required Unit Status 7.1 NC System filled and vented with a steam bubble in the Pzr.

8. Prerequisite System Conditions 8.1 NC System Tave at steady state condition. (+/- 0.5°F) 8.2 Reactor Power at steady state condition. (+/- 0.2%)

8.3 Main Steam pressure at steady state condition. (+/- 1%)

8.4 NCDT and PRT will NOT need to be pumped down during calculation.

NOTE: Background leakage consists of known valve stem leakage and NC Sample Purge Flow.

8.5 iJ. background leakage provided, data meets the following requirements:

Measured within last 7 days

Associated system conditions unchanged since calculated Unit 1

PT/1/A/4150/001 B Page 5 of 7

9. Test Method OAC available for leakage calculation, NC System leakage is calculated using a water Vinventory balance around the NC System based on input data from the OAC. OAC NC System Leakage Calculation will be initiated once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and will then run automatically for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . During the first 15 minutes of calculation, no correlation coefficient will be displayed.

,ii elapsed time greater than 60 minutes, program data may be used for leakage calculation when one of the following sets of criteria met:

TOTAL LEAKAGE BEST NOT between +/-0.15 gpm and TOTAL LEAKAGE CORRELATION COEFF greater than 0.6 OR y greater TOTAL LEAKAGE BEST less than 0.15 gpm and IDENTIFIED LEAKAGE BEST than or equal to BACKGROUND LEAKAGE.

OR

/TOTAL LEAKAGE BEST less than 0.1 gpm IF plant stability can NOT be maintained AND elapsed time greater than 30 minutes, leakage

/alculation data may be used when absolute value for Total Leakage Correlation Coefficient greater than or equal to 0.50 and Identified Leakage Best greater than or equal to Background Leakage.

LOAC is partially or wholly unavailable, NC System leakage will be calculated manually.

.Ifiitial data will be recorded followed by final data after 60 75 minute wait. Tank volume /

gallon conversion and water densities are used in equations to determine NC System leakage.

Ipdividual NC Pump #1 Seal Leakoff flows will be recorded and compared to the maximum 6llowable limit of 4.0 gpm.

P;imary to Secondary Leakage will be recorded from EMF indication(s) or Chemistry sample 6nd compared to a maximum of 135 gpd through any one steam generator or a maximum of 389 gpd through all steam generators.

OTAL ACCUMULATIVE LEAKAGE will be calculated using IDENTIFIED LEAKAGE EST, UNIDENTIFIED LEAKAGE BEST and TOTAL NC PUMP SEAL LEAKOFF FLOWS.

Unit 1

PT/1/A/4150/OO1 B Page 6 of 7

10. Data Required jhY. 1 Enclosure 13.1 (NC Leakage Calculation Using OAC) or Enclosure 13.2 (NC Leakage Determination Using Manual Calculations).

I62 IF Unit 1 at 100% RTP, Enclosure 13.5 (Evaluation of NC System Unidentified Leakage Results)

Indicate on cover sheet of this procedure under Remarks Section any special system alignments made for this calculation.

11. Acceptance Criteria 34.l NC System Identified Leakage shall be limited to 10 gpm. (Reference TS 3.4.13) j4.2 NC System Unidentified Leakage shall be limited to 1 gpm. (Reference TS 3.4.13) 14.3 Total NC Pumps #1 Seal Leakoff shall be limited to 16.3 gpm. (Reference SLC 16.9.7)

{PIP 04-3317}

Total Accumulative Leakage (sum of Identified Leakage, Unidentified Leakage, and NC Pumps #1 Seal Leakoff) shall be limited to 20 gpm. (Reference SLC 16.9.7)

{PIP M99-3926}

I .5 Each NC Pump #1 Seal Leakoff flow shall be limited to a sustained value of less than 4.0 gpm. (Reference SLC 16.9.7, MCC-1201.01-00-0053) {PIP 05-779, M-09-1857}

V6 Primary to Secondary Leakage shall be limited to 135 gpd through any one steam generator and 389 gpd through all steam generators. (Reference TS 3.4.13)

12. Procedure 12.1 Perform one of the following:

D Enclosure 13.1, NC Leakage Calculation Using OAC OR Enclosure 13.2, NC Leakage Determination Using Manual Calculations Unit 1

PT/1/A14150/OO1 B Page 7 of 7

13. Enclosures 13.1 NC Leakage Calculation Using OAC 13.2 NC Leakage Determination Using Manual Calculations 13.3 NCDT Volume 13.4 PRT Volume 13.5 Evaluation of NC System Unidentified Leakage Results End of Body Unit 1

Enclosure 13.2 PT/1/A1415o/ool B NC Leakage Determination Using Manual Page 1 of 10 Calculations

1. Procedure Evaluate all outstanding R&Rs that may impact performance of this procedure.

NOTE: A IF Unit 1 in Mode 3 or 4, this procedure is NOT required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation have elapsed.

The first calculation is considered the first calculation after 18:00 hrs for normal operation.

1.2 more than one leakage calculation performed per shift, a brief explanation should be entered on Autolog indicating reason for repeating calculation.

NOTE: / VCT A continuous vent is maintained on the PRT and a continuous purge is maintained on the by Radwaste Chemistry.

1.3 Notify Radwaste Chemistry of the following:

Determine VCT purge status:

D Active Secured NC System leakage calculation is in progress LVTo refrain from sampling PRT, NCDT and VCT or changing vent (purge) status of PRT, NCDT and VCT {PIPM-00-0615}

Person Notified Date Time 1.4 Notify Primary Chemistry of the following:

NC System leakage calculation is in progress To check that NC Sample Purge Flow value is unchanged from the current Autolog entry (Prerequisite System Condition 8.5) 134 NC System sampling shall only be performed with permission from the Control Room

/

Person Notified Date Time

.5 Ensure adequate VCT level to prevent auto makeup during calculation.

Unit 1

Enclosure 13.2 PT/1/A/415o/ool B NC Leakage Determination Using Manual Page 2 of 10 Calculations NOTE: frLeakage Calculation will be invalid if any valve in Step 1.6 or 1.7 is repositioned during calculation.

1.6 Check closed:

INC-58A (PRT Spray Supply Block) 1NI-9A (NC Cold Leg Inj From NV) 2 1NI-1OB (NC Cold Leg Inj From NV) 2 1NV-39A (A NC Pump Standpipe Fill) 1NV-55B (B NC Pump Standpipe Fill) 1NV-71A (C NC Pump Standpipe Fill)

M 1NV-87B (D NC Pump Standpipe Fill) 1NV-171A (BA Blender To VCT Inlet)

L4 1NV-175A (BA Blender To VCT Outlet)

L!f 1NV-221A (NV Pumps Suct From FWST) 1NV-222B (NV Pumps Suct From FWST) 1.7 jj 1NV-137A (NC Filters Otlt 3-Way Cntrl) in AuTO perform the following:

1.7.1 Place 1NV-137A to VCT position.

1.7.2 HOLD until 1NV-137A indicates VCT, THEN place 1NV-137A to AUTO 1.8 Place 1WL-23 Mode Select in MAN.

94 1.9 Close 1WL-23 (NCDT Pump Level Control).

Unit 1

Enclosure 13.2 PT/1/A14150/001 B NC Leakage Determination Using Manual Page 3 of 10 Calculations U 1.10 Perform the following:

NOTE: IF available, the OAC should be used to obtain data required for calculation.

U 1.10.1 Record Start Time:

U 1.10.2 Record initial VCT Level (M1PO2O1): %

U 1.10.3 Record initial PZR Level (Ml P0200): %

NOTE: IF Tave less than 530°F AND OAC unavailable, Tave must be calculated using WR TH and Tc.

D 1.10.4 Record initial NC System Tave (M1P1479):

Q 1.10.5 Record initial PRT Level (M1P0202): %

U 1.10.6 Record initial NCDT Level (M1P0203): %

1.10.7 HOLD until 60 75 minutes elapsed.

U 1.10.8 Record Stop Time:

U 1.10.9 Record final VCT Level (M1PO2O1):

U 1.10.10 Record final PZR Level (M1PO200): %

NOTE: IF Tave less than 5 30°F AND OAC unavailable, Tave must be calculated using WR TH andTc.

U 1.10.11 Record final NC System Tave (M1P1479): °F U 1.10.12 Record final PRT Level (M1P0202): %

U 1.10.13 Record final NCDT Level (Ml P0203): %

Unit 1

Enclosure 13.2 PT/1/A,/4lSoIool B NC Leakage Determination Using Manual Page 4 of 10 Calculations NOTE: IF change in Tave greater than 0.25°F (0.1°F using OAC), calculation is invalid and must be repeated.

U 1.10.14 Calculate change in NC System Tave:

°F Initial (Step 1.10.4) Final (Step 1.10.11)

U 1.10.15 Calculate VCT Leakage Rate:

[Initial Level (%) Final Level (%) 1 x (19.3 Gal/%)

Stop Time Start Time (Mm)

[ - ]x19.3 Initial (Step 1.10.2) Final (Step 1.10.9) gpm Stop Time (Step 110.8) Start Time (Step 1.10.1)

EJ 1.10.16 Calculate PZR Leakage Rate:

[Initial Level (%) Final Level (%)1 x (132.5 Gal/%) X (0.01613)

Stop Time Start Time (Mm)

[ - ]x 132.5 x 0.01613 Initial (Step 1.10.3) Final (Step 1.10.10)

Stop Time (Step 1.10.8) Start Time (Step 1.10.1) 0 1.10.17 Calculate Total Leakage:

+ = gpm VCT Leakage Rate (Step 1.10.15) PZR Leakage Rate (Step 1.10.16)

U 1.10.18 Using Enclosure 13.4 (PRT Volume), record the following:

InitialPRT Volume: gal (Step 1.10.5)

Final PRT Volume: gal (Step 1.10.12)

U 1.10.19 Calculate PRT Leakage Rate:

Final Volume (Step 1.10.18) InitialVolume (Step 1.10.18) = gpm Stop Time (Step 1.10.8) Start Time (Step 1.10.1)

I Specific Volume for saturated liquid at PZR temperature.

Unit 1

Enclosure 13.2 PT/1/A141501001 B NC Leakage Determination Using Manual Page 5 of 10 Calculations LI 1.10.20 Using Enclosure 13.3 (NCDT Volume), record the following:

Initial NCDT Volume: gal (Step 1.10.6)

Final NCDT Volume: gal (Step 1.10.13)

LI 1.10.21 Calculate NCDT Leakage Rate:

Final Volume (Step 1.10.20) Initial Volume (Step 1.10.20) gpm Stop Time (Step 1.10.8) Start Time (Step 1.10.1)

LI 1.10.22 Record the following:

NC Sample Purge Flow value recorded in Autolog: gpm

Any quantified (measured) leakage that has been identified: gpm LI 1.10.23 Calculate Total Background Leakage:

gpm NC Purge (Step 1.10.22) Quantified (Step 1.10.22)

LI 1.10.24 Calculate Identified Leakage:

+ +_____________ (<lOgpm) 2 gpm PRT Leakage Rate (Step 1.10.19) NCDT Leakage Rate (Step 1.10.21) Background Leakage (Step 1.10.23)

LI 1.10.25 Calculate Unidentified Leakage:

- 2 (< I gpm) gprn Total Leakage (Step 1.10.17) Identified Leakage (Step 1.10.24)

LI 1.10.26 Determine Total NC Pump #1 Seal Leakoff flow:

NC Pump 1A #1 Seal Leakoff Flow gpm 2(< 4.0 gpm)

NC Pump lB #1 Seal Leakoff Flow +_________ gpm 2(< 4.0 gpm)

NC Pump 1C #1 Seal Leakoff Flow +_________ gpm 2(< 4.0 gpm) 2(<

NC Pump 1D #1 Seal Leakoff Flow +_________ gpm 4.0 gpm) 2 Total NC Pumps #1 Seal Leakoff =_________ gpm < 16.3 gpm) 2 Acceptance Criteria Value Unit 1

Enclosure 13.2 PT/1/A!4150/OO1 B NC Leakage Determination Using Manual Page 6 of 10 Calculations NOTE: 0 should be entered below for any negative identified or unidentified value.

0 1.10.27 Calculate Total Accumulative Leakage:

+ + gpm

(

3 <2ogpm)

Identified (Step 1.1024) Unidentified (Step 1.10.25) Total NC Seal Leakoff(Step 1,10.26) Total Accumulative Leakage 1.11 Determine Primary to Secondary Leakage by performing the following:

1.11.1 IF in Mode 1 AND greater than or equal to 40% RTP, record indication on the following:

1EMF71:

gpd

1EMF72: gpd

1EMF73: gpd

1EMF74: gpd 1.1 1.1.1 IF any N-16 EMF inoperable, perform the following:

A. Notify Secondary Chemistry to provide Primary to Secondary leakage.

/

Person Notified Date Time 0 B. Record Primary to Secondary leakage as determined by Secondary Chemistry: gpd O C. Record date and time Primary to Secondary leakage was determined (provided by Secondary Chemistry):

/

Date Time 1.11.2 IF in Mode 1 AND less than 40% RTP, perform the following:

1.11.2.1 Notify Secondary Chemistry to provide Primary to Secondary leakage.

/

Person Notified Date Time This value is a total primary to secondary leakage of all four S/Gs. A value of less than or equal to 135 gpd conservatively implies leakage through any one S/G is less than or equal to 135 gpd.

Uiiitl

Enclosure 13.2 PT/1/A1415o/ool B NC Leakage Determination Using Manual Page 7 of 10 Calculations Q 1.11.2.2 Record Primary to Secondary leakage as determined by Secondary Chemistry: gpd 4

U 1.11.2.3 Record date and time Primary to Secondary leakage was determined (provided by Secondary Chemistry):

/

Date Time 1.11.3 IF in Modes 2, 3 or 4, perform the following:

1.11.3.1 Notify Secondary Chemistry to provide Primary to Secondary leakage via grab sample.

/

Person Notified Date Time U 1.11.3.2 Record Primary to Secondary leakage as determined by Secondary Chemistry grab sample: gpd U 1.11.3.3 Record date and time Primary to Secondary leakage was determined (provided by Secondary Chemistry):

/

Date Time Calculated By:__________________________________ Date: Time:

Checked By: Date: Time:

This value is a total primary to secondary leakage of all four S/Gs. A value of less than or equal to 135 gpd conservatively implies leakage through any one S/G is less than or equal to 135 gpd.

Unit 1

Enclosure 13.2 PT/1IA/415o/ool B NC Leakage Determination Using Manual Page 8 of 10 Calculations U 1.12 In Autolog, perform the following:

NOTE:

Calculations run during power escalation AND other than Mode 1 calculations should be identified as such.

The first calculation is considered the first calculation after 18:00 hrs for normal operation 1.12.1 Enter the following values with any pertinent comments:

U IDENTIFIED leakage (Step 1.10.24)

U IJNIDENTIFIED leakage (Step 1.10.25)

U TOTAL NC PUIvIPS #1 SEAL LEAKOFF leakage (Step 1.10.26)

U TOTAL leakage (Step 1.10.27)

O CALCULATION START TIME U Primary to Secondary leakage 1.12.2 other than the first calculation for the day, record reason and any pertinent comments.

NOTE: Unidentified Leakage values are expected to be within +/-0.5 gpm for Manual Calculations. Exceeding +/-0.5 gpm does NOT invalidate leakage calculation.

1.13 IF unidentified leakage NOT between +/-0.5 gpm, notify Primary System Engineer.

/

Person Notified Date Time Unit 1

Enclosure 13.2 PT/1/A14150/001 B NC Leakage Determination Using Manual Page 9 of 10 Calculations 1.14 Evaluate Acceptance Criteria per one of the following:

D 1 .14.1 Check Acceptance Criteria specified in Section 11 met.

OR 1.14.2 ! Acceptance Criteria specified in Section 11 NOT met, perform the following:

1.14.2.1 Log applicable Tech Spec or SLC. {PIP M-07-00393}

5R0 1.14.2.2 IF Total NC Pumps #1 Seal Leakoff is greater than 16.3 gpm, SRO declare SSF capability degraded.

1.14.2.3 IF Total Accumulative Leakage is greater than 20 gpm Total SRO NC Pumps #1 Seal Leakoff greater than 16.3 gpm, notify Security of degraded SSF capabilities.

/

Person Notified Date Time 1.14.2.4 !J. any NC Pump #1 Seal Leakoff has a sustained value of greater SRO than Qj3, equal to 4.0 gpm, notify SSS Engineer and Security of degraded SSF capability.

/

Person Notified Date Time 1.15 IF this is the second Leakage Calculation and elevated leakage is indicated, evaluate performing PT/1/A/41 50/00 1 D (Identifying NC System Leakage).

1.16 Lower NCDT level less than 48%.

1.17 Close 1WL-23 (NCDT Level Control).

1.18 Place 1WL-23 Mode Select to AUTO.

Unit 1

Enclosure 13.2 IA/4150/001 B 1

PT/

NC Leakage Determination Using Manual Page 10 of 10 Calculations 1.19 Notify Radwaste Chemistry of the following:

LI NC System leakage calculation is complete LI PRT, NCDT and VCT sampling or venting maybe initiated {PIPM-00-0615}

/

Person Notified Date Time 1.20 Notify Primary Chemistry of the following:

LI NC System leakage calculation is complete LI NC System sampling may be initiated

/

Person Notified Date Time 1.21 IF Unit 1 at 100% RTP AND OAC is available, perform Enclosure 13.5 (Evaluation of NC System Unidentified Leakage Results).

End of Enclosure Unit 1

Enclosure 13.3 PT/1/A/415o/ool B NCDT Volume Page 1 of 1 NCDT LEVEL % NCDT VOLIJME NCDT LEVEL % NCDT VOLUME NCDT LEVEL % NCDT VOLUME (Gal) (Gal) (Gal) 0 19.7 35 123.1 70 247.3 1 21.9 36 126.6 71 250.7 2 24.1 37 130.1 72 254.0 3 26.4 38 133.6 73 257.3 4 28.8 39 137.1 74 260.6 5 31.2 40 140.7 75 263.9 6 33.7 41 144.3 76 267.2 7 36.2 42 147.8 77 270.4 8 38.8 43 151.4 78 273.6 9 41.4 44 155.0 79 276.8 10 44.1 45 158.6 80 279.9 11 46.9 46 162.2 81 283.0 12 49.6 47 165.8 82 286.1 13 52.5 48 169.4 83 289.1 14 55.3 49 173.0 84 292.1 15 58.2 50 176.6 85 295.1 16 61.2 51 180.2 86 298.0 17 64.2 52 183.8 87 300.9 18 67.2 53 187.5 88 303.8 19 70.3 54 191.1 89 306.6 20 73.4 55 194.7 90 309.4 21 76.5 56 198.2 91 312.1 22 79.6 57 201.8 92 314.7 23 82.8 58 205.4 93 317.4 24 86.0 59 209.0 94 319.9 25 89.3 60 212.5 95 322.4 26 92.6 61 216.1 96 324.9 27 95.9 62 219.6 97 327.3 28 99.2 63 223.1 98 329.6 29 102.5 64 226.6 99 331.9 30 105.9 65 230.1 100 334.0 31 109.3 66 233.6 32 112.7 67 237.0 33 116.2 68 240.5 34 119.6 69 243.9 End of Enclosure Unit 1

Enclosure 13.4 PT/1/A1415o/ool B PRT Volume Page 1 of 1 PRT LEVEL % PRT VOLUME PRT LEVEL % f PRT VOLUME PRT LEVEL % PRT VOLUME (Gal) J (Gal) (Gal) 0 303.2 35 4472.0 70 9799.8 1 371.9 36 4621.5 71 9942.5 2 445.6 37 4771.8 72 10084.0 3 523.9 38 4922.8 73 10224.1 4 606.7 39 5074.6 74 10362.9 5 693.6 40 5227.0 75 10500.3 6 784.5 41 5379.9 76 10636.1 7 879.0 42 5533.4 77 10770.4 8 977.0 43 5687.3 78 10903.1 9 1078.3 44 5841.7 79 11034.1 10 1182.7 45 5996.4 80 11163.3 11 1290.0 46 6151.4 81 11290.6 12 1400.2 47 6306.6 82 11416.0 13 1513.0 48 6461.9 83 11539.3 14 1628.4 49 6617.4 84 11660.6 15 1746.2 50 6772.9 85 11779.6 16 1866.2 51 6928.4 86 11896.2 17 1988.5 52 7083.8 87 12010.4 18 2112.9 53 7239.0 88 12122.0 19 2239.2 54 7394.1 89 12231.0 20 2367.5 55 7548.9 90 12337.0 21 2497.6 56 7703.4 91 12440.0 22 2629.4 57 7857.5 92 12539.9 23 2763.0 58 8011.2 93 12636.3 24 2898.1 59 8164.3 94 12729.2 25 3034.8 60 8316.9 95 12818.3 26 3172.9 61 8468.9 96 12903.4 27 3312.4 62 8620.3 97 12984.2 28 3453.3 63 8770.9 98 13060.5 29 3595.5 64 8920.7 99 13132.0 30 3738.9 65 9069.6 100 13198.3 31 3883.4 66 9217.7 32 4029.1 67 9364.8 33 4175.7 68 9510.9 34 4323.4 69 9655.9 End of Enclosure Unit 1

Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA2SRO 2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 2 of 12 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Perform/Review a Manual NC JPM No.: 2010 Admin JPM A2 Leakage Calculation SRO K/A

Reference:

GKIA 2.2.12 (4.1)

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 100% power.

The Unit 1 OAC point Ml L4554 is out of service.

PT/1/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.

A manual NC System leakage calculation is in progress in accordance with PT/i /A141 50/001 B (Reactor Coolant Leakage Calculation)

Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A14150/OO1B (Reactor Coolant Leakage Calculation) has been completed through Step 1.9.

Task Standard: The operator will complete all calculations in accordance with the attached Key, identify that the Unidentified RCS Leakage Technical Specification has been exceeded, and the required ACTION.

Required Materials: None.

General

References:

PT/i/A14200/040 (Reactor Coolant Leakage Detection)

PT/i /A/41 50/001 B (Reactor Coolant Leakage Calculation)

McGuire Unit 1 Technical Specifications 2010 Admin JPM A2 SRO

- NUREG 1021, Revision 9

Appendix C Page 3 of 12 Form ES-C-i Job Performance Measure Worksheet Handouts: PTI1IA!4150/OO1B (Reactor Coolant Leakage Calculation) marked up as follows:

Step 7.1 Initialed Steps 8.1 through 8.5 Initialed.

Step 12.1 Enclosure 13.2 Checkbox is checked.

PT/i /A/41 50/001 B (Reactor Coolant Leakage Calculation) Enclosure 13.2 (NC Leakage Determinations Using Manual Calculations) marked up as follows:

Step 1.1 Checkbox is checked/Initialed.

Step 1.2 Initialed.

Step 1.3Initialed.

Determine VCT Purge Status Checkbox is checked.

Secured Checkbox is checked.

NC System leakage calculation is in progress Checkbox is checked.

To refrain from sampling Checkbox is checked.

Person Notified Mike Smith Todays Date/Time Step 1.4 Initialed.

NC System leakage calculation is in progress Checkbox is checked.

To check that NC sample Checkbox is checked.

NC System sampling Checkbox is checked.

Person Notified Melvin Smith Todays Date/Time Step 1.5 Initialed.

Step 1.6 All Checkboxes checked/Initialed.

Step 1.7 Initialed.

Step 1.7.1 Initialed.

Step 1.7.2 Initialed.

Step 1.8 Initialed.

Step 1.9Initialed.

Enclosure 13.3 (NCDT Volume) of PT/1/A/41501001B (Reactor Coolant Leakage Calculation)

Enclosure 13.4 (PRT Volume) of PT/1/A/4150/OO1B (Reactor Coolant Leakage Calculation)

McGuire Technical Specifications Initiating Cue: Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, by performing Steps 1.10 and 1.11, AND evaluate the Acceptance Criteria.

Identify any Technical Specifications impacted and any required ACTION.

2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 4 of 12 Form ES-C-i Job Performance Measure Worksheet Time Critical Task: NO Validation Time: 25 minutes 2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 5 of 12 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions!Cue, and asso ciated Datasheet (Last two (2)

Pages of this JPM); and Handout PTII!A!4150/OOIB proc edure body marked up as described, Enclosure 13.2 marked up as described, Encl osure 13.3 and Enclosure 13.4.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Enclosure 13.2, Steps The operator transposes 1.10.1 through 13,22,26 raw data from the Data and 1.11.1) Sheet provided.

Record raw data.

2 (Enclosure 13.2, Step The operator calculates the 1.10.14) Calculate change change in NC System Tave in NC System Tave: to be f, and records.

3 (Enclosure 13.2, Step The operator calculates the 1.10.15) Calculate VCT VCT Leakage Rate to be Leakage Rate: 1.55 gpm, and records.

4 (Enclosure 13.2, Step The operator calculates the 1.10.16) Calculate PZR PZR Leakage Rate to be Leakage Rate: 0.02 gpm, and records.

5 (Enclosure 13.2, Step The operator calculates the 1.10.17) Calculate Total Total Leakage to be 1.57 Leakage: g, and records.

2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 6 of 12 Form ES-C-I PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Enclosure 13.2 Step The operator uses 1.10.18) Using Enclosure Enclosure 13.4 and an 13.4 (PRT Volume) record initial PRT Level of 76.0 %,

the followin and determines that initial PRT Volume is 10636.1 Initial PRT Volume g, and records.

Final PRT Volume The operator uses Enclosure 13.4 and interpolates a PRT Volume for 76.1% to be 10649.5 and records.

7 (Enclosure 13.2, Step The operator calculates the 1.10.19) Calculate PRT PRT Leakage Rate to be Leakage Rate: .19 gpm, and records.

8 (Enclosure 13.2, Step 1.10. The operator uses

20) Using Enclosure 13.3 Enclosure 13.3 and an (NCDT Volume), record the initial NCDT Level of 30.0%,

following: and determines that initial Initial NCDT Volume NCDT Volume is 105.9 gal, and records.

Final NCDT Volume The operator uses Enclosure 13.3 and a final NCDT Level of 33.0%, and determines that final NCDT Volume is 116.2 gal, and records.

9 (Enclosure 13.2, Step The operator calculates the 1.10.21) Calculate NCDT NCDT Leakage Rate to be Leakage Rate: .14 gpm, and records.

10 (Enclosure 13.2, Step The operator calculates the 1.10.23) Calculate Total Total Background Leakage Background Leakage: to be 0 gpm, and records.

2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 7 of 12 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

1 1 (Enclosure 13.2, Step The operator calculates the 1.10.24) Calculate Identified Identified Leakage to be Leakage: 0.33 (+/-10%) qpm, and records.

12 (Enclosure 13.2, Step The operator calculates the 1.10.25) Calculate Unidentified Leakage to be Unidentified Leakage: 1.24 (+/-10%) qpm, and records.

13 (Enclosure 13.2, Step The operator calculates the 1.10.26) Determine Total Total NC Pumps #1 Seal NC Pump #1 Seal Leakoff: Leakoff to be 12.8 (+/-10%)

and records.

14 (Enclosure 13.2, Step The operator calculates the 1.10.27) Calculate Total Total Accumulative Accumulative Leakage: Leakage to be 14.37

(+/-10%) qpm, and records.

15 (Enclosure 13.2) Calculated The operator places their By! Date/Time: name in the Calculated by BLOCK, and signs.

The operator enters the Date and Time.

2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 8 of 12 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

16 Technical Specification The operator returns the LCD 3.4.13: completed Enclosure 13.2 and reports that LCD RCS operational LEAKAGE 3.4.13.b (1 gpm unidentified shall be limited to: LEAKAGE) has been exceeded.

a. No pressure boundary LEAKAGE; The operator identifies that

b. 1 gpm unidentified CONDITIDN A is met, RCS LEAKAGE; Operational LEAKAGE not within limits for reasons

c. 10 gpm identified other than pressure LEAKAGE: boundary LEAKAGE or primary to secondary

d. 389 gallons per day LEAKAGE; AND that the total primary to REQUIRED ACTION is to secondary LEAKAGE Reduce LEAKAGE to within through all steam limits, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

generators (SGs); and

e. 135 gallons per day primary to secondary Examiner NOTE:

LEAKAGE through See KEY on Page 10 of any one steam this JPM.

generator (SG).

APPLICABILITY:

MODES 1, 2, 3, and 4.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 9 of 12 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 Admin JPM A2 SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 10 of 12 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Enclosure 13.2, Step 1.10.14 (JPM Step 2): Change in NC System Tave:

584.8°F 584.8°F = 0°F Enclosure 13.2, Step 1.10.15 (JPM Step 3): VCT Leakage Rate:

(53.4% 47.6%) x19.3 gallons/%/72 minutes = 1.55 gallons per minute (gpm)

Enclosure 13.2, Step 1.10.16 (JPM Step 4): PZR Leakage Rate:

(54.9% 54.1%) x 132.5 gallons/% x .01613 /72 minutes = 0.02 gallons per minute (gpm)

Enclosure 13.2, Step 1.10.17 (JPM Step 5): Total Leakage:

1.55 gpm + 0.02 gpm = 1.57 gpm Enclosure 13.2, Step 1.10.18 (JPM Step 6): PRT Final Volume:

(10770.4-10636.1)/10 = 13.43/.1% PRT Level, 10636.1 + 13.43 10649.53 (gal)

Enclosure 13.2, Step 1.10.19 (JPM Step 7): Total PRT Leakage:

(10649.5 gallons 10636.1 gallons)/72 minutes = 0.19 gallons per minute (gpm)

Enclosure 13.2, Step 1.10.21 (JPM Step 9): Total NCDT Leakage:

(116.2 gallons 105.9 gallons)/72 minutes = 0.14 gallons per minute (gpm)

Enclosure 13.2, Step 1.10.23 (JPM Step 10): Total Background Leakage:

(0 gpm + 0 gpm) = 0 gpm Enclosure 13.2, Step 1.10.24 (JPM Step 11): Identified Leakage:

(.19 gpm + .14 gpm + 0 gpm) = 0.33 gpm Enclosure 13.2, Step 1.10.25 (JPM Step 12): Unidentified Leakage:

(1.57 gpm .33 gpm) = 1.24 gpm Enclosure 13.2, Step 1.10.26 (JPM Step 13): Total NC Pumps #1 Seal Leakoff:

(2.8 gpm + 3.6 gpm + 3.1 gpm + 3.3 gpm) = 12.8 gpm 3.2, Step 1.10.27 (JPM Step 14): Total Accumulative Leakage:

(.33 gpm + 1.24 gpm + 12.8 gpm) = 14.37 gpm LCO 3.4.13.b (1 gpm unidentified LEAKAGE) has been exceeded, CONDITION A is met, RCS Operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE; AND that the REQUIRED ACTION is to Reduce LEAKAGE to within limits, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2010 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS: Unit 1 is at 100% power.

The Unit 1 OAC point M1L4554 is out of service.

PTI1/A142001040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.

A manual NC System leakage calculation is in progress in accordance with PTI1IA/41501001B (Reactor Coolant Leakage Calculation)

Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/i /A14i 50/001 B (Reactor Coolant Leakage Calculation) has been completed through Step 1.9.

INITIATING CUE: Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, by performing Steps 1.10 and 1.11, AND evaluate the Acceptance Criteria.

Identify any Technical Specifications impacted and any required ACTION.

NUREG 1021, Revision 9

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Duke Energy Procedure No.

McGuire Nuclear Station pT/lfAI4l5ofool B Reactor Coolant Leakage Calculation Revision No.

067 Electronic Reference No.

MCOO47QI Continuous Use PERFORMANCE I UNCONTROLLED FOR PRINT* * * * * * * * * *

(ISSUED) PDF Format

PT/1/A14150/001 B Page2of7 Revision History (significant issues, limited to one page)

Rev 067 Changed format of procedure to split out calculation performed by OAC and performed by manual calculation. Combined leakage calculation using the OAC steps with current Enclosure 13.1 and renamed enclosure NC Leakage Calculation Using OAC.

Combined manual leakage calculation steps with Enclosure 13.2 and renamed enclosure NC Leakage Determination Using Manual Calculation.

Changed all references throughout procedure to include these format changes.

End. 13.5. Added Independent Verification sign offs for calculation of seven day rolling average of Unidentified Leakage. {PIP M-09-1307}

Revised current steps for determining if Tier Two or Tier Three Action levels exceeded to reference step numbers associated with determination. Intent is to cIarif steps.

Reworded steps that state IF directed by engineering to IF advised by engineering.

Definition of directed changed with new fatigue rule.

Added PIP M-09-1857 as an additional reference to NCP seal leakage basis.

Modified steps that begin with WHEN to reflect NSD 704 Rev 016 requirements.

Rev 066 Body of procedure.

Added a limit and precaution about manipulation of VA System during leakage calculation has an affect on VCT level.

Re-worded Step 12.6.17. The leakage calculation is considered valid after 60 minutes but is preferred to run up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The step as written requires the operator to print calculation after 60 minutes when 1 of 3 conditions met. This is procedure use and adherence issue. Re-worded step to give operator flexibility to print calculation summary between 60 minutes and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Re-worded Step 12.6.35. If operator performs section 12.6.16 to abort leakage calculation early, enclosure 13.1 is not performed. 12.6.35 directs operator to perform End. 13.5, however, this enclosure requires data from enclosure 13.1. Re-worded step to stipulate if unit at 100% RTP AND End. 13.1 completed, then perform End. 13.5.

Procedure use and adherence issue.

Rev 065

Added step to make operator aware that if leakage calc ran for greater than 30 minutes but less than 60 minutes, the data can still be valid if it meets certain conditions.

Added step to record status of VCT purge at beginning of procedure.

Added steps to take NV-137A hard to VCT and back to AUTO prior to starting leakage calculation.

End. 13.5. Reworded section if any Tier One, Two, or Three Action level is exceeded to make it easier to understand.

Unit 1

PT/1/A14150/OO1 B Page 3 of 7 Reactor Coolant Leakage Calculation

1. Purpose To determine NC System Leakage using the Operator Aid Computer (OAC) or manual calculations to ensure Tech Spec requirements met.

2. References 2.1 Tech Spec TS SR 3.4.13.1, 3.4.13.2, TS 3.4.15 2.2 SLC 16.9.7 Standby Shutdown System 2.3 MCS-1274.OO-OO-0016 (License Renewal Basis Spec), Section 4.29 2.4 UFSAR Chapter 18 (Aging Management Program and Activities), Table 18-1, Reactor Coolant Operational Leakage Monitoring Program 2.5 SLC 16.7.6 Radiation Monitoring for Plant Operation 2.6 WCAP-16423-NP (Methodology for calculating Unidentified NC System leakage) 2.7 WCAP-16465-NP (Action levels and response guidelines for increasing Unidentifed NC System leakage less than Tech Spec limits) 2.8 MCC-1201.O1-OO-0053 (MNS Unit 1 & 2 NC Pump Response to Loss of Seal Cooling)

3. Time Required 3.1 One operator for three hours every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4. Prerequisite Test None

5. Test Equipment None Unit 1

PT/1/A14150/0O1 B Page4of7

6. Limits and Precautions ii NC System Tave, Reactor Power, Containment Temperature, and SM Pressure should remain constant during calculation.

Positioning valves during calculation which could adversely affect results will invalidate the calculation.

Performing Leakage Calculation between 3 am and 8 am on Wednesdays may cause calculation to fail due to OAC weekly backup routine.

Performing PT/1/A/4200/019 (ECCS Pump and Piping Vent) during calculation could adversely affect results and will invalidate the calculation.

d Manipulation of VA System should be avoided while performing Leakage Calculation due to affect on VCT level.

7. Required Unit Status 7.1 NC System filled and vented with a steam bubble in the Pzr.

8. Prerequisite System Conditions 8.1 NC System Tave at steady state condition. (+/- 0.5°F) 8.2 Reactor Power at steady state condition. (+/- 0.2%)

8.3 Main Steam pressure at steady state condition. (+/- 1%)

8.4 NCDT and PRT will NOT need to be pumped down during calculation.

NOTE: Background leakage consists of known valve stem leakage and NC Sample Purge Flow.

background leakage provided, data meets the following requirements:

Measured within last 7 days

Associated system conditions unchanged since calculated Unit 1

PT/1/A/4150/00l B Page 5 of 7

9. Test Method OAC available for leakage calculation, NC System leakage is calculated using a water Vinventory balance around the NC System based on input data from the OAC. OAC NC System Leakage Calculation will be initiated once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and will then run automatically for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . During the first 15 minutes of calculation, no correlation coefficient will be displayed.

)1? elapsed time greater than 60 minutes, program data may be used for leakage calculation when one of the following sets of criteria met:

TOTAL LEAKAGE BEST NOT between +/-0.15 gpm and TOTAL LEAKAGE CORRELATION COEFF greater than 0.6 OR y TOTAL LEAKAGE BEST less than 0.15 gpm and IDENTIFIED LEAKAGE BEST greater than or equal to BACKGROUND LEAKAGE.

OR

/TOTAL LEAKAGE BEST less than 0.1 gpm IF plant stability can NOT be maintained AND elapsed time greater than 30 minutes, leakage

/alculation data may be used when absolute value for Total Leakage Correlation Coefficient greater than or equal to 0.50 and Identified Leakage Best greater than or equal to Background Leakage.

jOAC is partially or wholly unavailable, NC System leakage will be calculated manually.

fiitial data will be recorded followed by final data after 60 75 minute wait. Tank volume I gallon conversion and water densities are used in equations to determine NC System leakage.

Ix1ividua1 NC Pump #1 Seal Leakoff flows will be recorded and compared to the maximum llowable limit of 4.0 gpm.

imary to Secondary Leakage will be recorded from EMF indication(s) or Chemistry sample 1

P 6nd compared to a maximum of 135 gpd through any one steam generator or a maximum of 389 gpd through all steam generators.

7OTAL ACCUMULATIVE LEAKAGE will be calculated using IDENTIFIED LEAKAGE EST, UNIDENTIFIED LEAKAGE BEST and TOTAL NC PUMP SEAL LEAKOFF FLOWS.

Unit 1

PT/1/A14150/OO1 B Page 6 of 7

10. Data Required 1 Enclosure 13.1 (NC Leakage Calculation Using OAC) or Enclosure 13.2 (NC Leakage Determination Using Manual Calculations).

W2 J! Unit 1 at 100% RTP, Enclosure 13.5 (Evaluation of NC System Unidentified Leakage Results) 416:3 Indicate on cover sheet of this procedure under Remarks Section any special system alignments made for this calculation.

11. Acceptance Criteria I NC System Identified Leakage shall be limited to 10 gpm. (Reference TS 3.4.13)

Yf.2 NC System Unidentified Leakage shall be limited to 1 gpm. (Reference TS 3.4.13) a4.3 Total NC Pumps #1 Seal Leakoff shall be limited to 16.3 gpm. (Reference SLC 16.9.7)

{PIP 04-3317}

14.4 Total Accumulative Leakage (sum of Identified Leakage, Unidentified Leakage, and NC Pumps #1 Seal Leakoff) shall be limited to 20 gpm. (Reference SLC 16.9.7)

{PIP M99-3926}

YI.5 Each NC Pump #1 Seal Leakoff flow shall be limited to a sustained value of less than 4.0 gpm. (Reference SLC 16.9.7, MCC-1201.01-00-0053) {PIP 05-779, M-09-1857}

jL6 Primary to Secondary Leakage shall be limited to 135 gpd through any one steam generator and 389 gpd through all steam generators. (Reference TS 3.4.13)

12. Procedure 12.1 Perform one of the following:

O Enclosure 13.1, NC Leakage Calculation Using OAC OR Enclosure 13.2, NC Leakage Determination Using Manual Calculations Unit 1

PT/1/A/4150/OO1 B Page7of7

13. Enclosures 13.1 NC Leakage Calculation Using OAC 13.2 NC Leakage Determination Using Manual Calculations 13.3 NCDT Volume 13.4 PRT Volume 13.5 Evaluation of NC System Unidentified Leakage Results End of Body Unit 1

Enclosure 13.2 PTI1/A/41501001 B NC Leakage Determination Using Manual Page 1 of 10 Calculations

1. Procedure 1.1 Evaluate all outstanding R&Rs that may impact performance of this procedure.

NOTE: IF Unit 1 in Mode 3 or 4, this procedure is NOT required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation have elapsed.

The first calculation is considered the first calculation after 18:00 hrs for normal operation.

1.2 IF more than one leakage calculation performed per shift, a brief explanation should be entered on Autolog indicating reason for repeating calculation.

NOTE: ./ VCT A continuous vent is maintained on the PRT and a continuous purge is maintained on the by Radwaste Chemistry.

1.3 Notify Radwaste Chemistry of the following:

Li Determine VCT purge status:

D Active Secured NC System leakage calculation is in progress IiTo refrain from sampling PRT, NCDT and VCT or changing vent (purge) status of PRT, NCDT and VCT {PIPM-00-0615}

/

Person Notified Date Time 1.4 Notify Primary Chemistry of the following:

NC System leakage calculation is in progress To check that NC Sample Purge Flow value is unchanged from the current Auto log entry (Prerequisite System Condition 8.5)

NC System sampling shall only be performed with permission from the Control Room

/

Person Notified Date Time c2i .5 Ensure adequate VCT level to prevent auto makeup during calculation.

Unit 1

Enclosure 13.2 PT/1/A,415o/ool B NC Leakage Determination Using Manual Page 2 of 10 Calculations NOTE: Leakage Calculation will be invalid if any valve in Step 1.6 or 1.7 is repositioned during calculation.

1.6 Check closed:

1NC-58A (PRT Spray Supply Block) 1NI-9A (NC Cold Leg Inj From NV) 1NI-1OB (NC Cold Leg Inj From NV) 1NV-39A (A NC Pump Standpipe Fill) 1NV-55B (B NC Pump Standpipe Fill) 1NV-71A (C NC Pump Standpipe Fill) g 1NV-87B (D NC Pump Standpipe Fill) 1NV-171A (BA Blender To VCT Inlet) 1NV-175A (BA Blender To VCT Outlet)

F1 INV-221A (NV Pumps Suct From FWST) 1NV-222B (NV Pumps Suct From FWST) 1.7 IF 1NV-137A (NC Filters Otlt 3-Way Cntrl) in AUTO, perform the following:

1.7.1 Place 1NV-137A to T VCT position.

1.7.2 HOLD until 1NV-137A indicates VCT, THEN place 1NV-137A to AUTO.

1.8 Place 1WL-23 Mode Select in MAN.

1.9 Close 1WL-23 (NCDT Pump Level Control).

Unit 1

Enclosure 13.2 PT/1/A!4l5o/ool B NC Leakage Determination Using Manual Page 3 of 10 Calculations Li 1.10 Perform the following:

NOTE: IF available, the OAC should be used to obtain data required for calculation.

Li 1.10.1 RecordStartTime:

Li 1.10.2 Record initial VCT Level (M1PO2OI): %

El 1.10.3 Record initial PZR Level (Ml P0200): %

NOTE: IF Tave less than 530°F AND OAC unavailable, Tave must be calculated using WR TH and Tc.

Li 1.10.4 Record initial NC System Tave (M1P1479): °F Li 1.10.5 Record initial PRT Level (M1P0202): %

Li 1.10.6 Record initial NCDT Level (M1P0203): %

1.10.7 HOLD until 60 75 minutes elapsed.

Li 1.10.8 Record Stop Time:

Li 1.10.9 Record final VCT Level (M1PO2O1): %

Li 1.10.10 Record final PZR Level (M1PO200): %

NOTE: IF Tave less than 530°F AND OAC unavailable, Tave must be calculated using WR TH andTc.

Li 1.10.11 Record final NC System Tave (M1P1479): °F Li 1.10.12 Record final PRT Level (M1P0202): %

Li 1.10.13 Record final NCDT Level (M1P0203): %

Unit 1

Enclosure 13.2 PT/1/A/4150/Oo1 B NC Leakage Determination Using Manual Page 4 of 10 Calculations NOTE: IF change in Tave greater than 0.25°F (0.1°F using OAC), calculation is invalid and must be repeated.

LI 1.10.14 Calculate change in NC System Tave:

- °F Initial (Step 1.10.4) Final (Step 1.10.11)

LI 1.10.15 Calculate VCT Leakage Rate:

[Initial Level (%) Final Level (%) 1 x (19.3 Gal/%)

Stop Time Start Time (Mm)

[ - ]x19.3 Initial (Step 1.10.2) Final (Step 1.10.9) = gpm Stop Time (Step 1.10.8) Start Time (Step 1.10.1)

LI 1.10.16 Calculate PZR Leakage Rate:

[Initial Level (%) Final Level (%)] x (132.5 Gal/%) X (0.016)3)

Stop Time Start Time (Mm)

[ - ]x 132.5x0.01613 Initial (Step 1.10.3) Final (Step 1.10.10)

Stop Time (Step 1.10.8) Start Time (Step 1.10.1)

LI 1.10.17 Calculate Total Leakage:

+ gpm VCT Leakage Rate (Step 1.10.15) PZR Leakage Rate (Step 1.10.16)

LI 1.10.18 Using Enclosure 13.4 (PRT Volume), record the following:

Initial PRT Volume: gal (Step 1.10.5)

Final PRT Volume: gal (Step 1.10.12)

LI 1.10.19 Calculate PRT Leakage Rate:

Final Volume (Step 1.10.18) Initial Volume (Step 1.10.18) = gpm Stop Time (Step 1.10.8) Start Time (Step 1.10.1)

Specific Volume for saturated liquid at PZR temperature.

Unit 1

Enclosure 13.2 PT/1/A1415o/ool B NC Leakage Determination Using Manual Page 5 of 10 Calculations LI 1.10.20 Using Enclosure 13.3 (NCDT Volume), record the following:

Initial NCDT Volume: gal (Step 1.10.6)

Final NCDT Volume: gal (Step 1.10.13)

LI 1.10.21 Calculate NCDT Leakage Rate:

Final Volume (Step 1.10.20) Initial Volume (Step l.IQ.20) gpm Stop Time (Step 1.10.8) Start Time (Step 1.10.1)

LI 1.10.22 Record the following:

NC Sample Purge Flow value recorded in Autolog: gpm

Any quantified (measured) leakage that has been identified: gpm LI 1.10.23 Calculate Total Background Leakage:

= gpm NC Purge (Step 1.10.22) Quantified (Step 1.10.22)

LI 1.10.24 Calculate Identified Leakage:

+ +____________ gpm

(

2 <logpm)

PRT Leakage Rate (Step 1.10.19) NCDT Leakage Rate (Step 1.10.21) Background Leakage (Step 1.10.23)

LI 1.10.25 Calculate Unidentified Leakage:

- gpm

(

2 <lgpm)

Total Leakage (Step 1,10.17) Identified Leakage (Step 1.10.24)

LI 1.10.26 Determine Total NC Pump #1 Seal Leakoff flow:

NC Pump 1A #1 Seal Leakoff Flow gpm 2(< 4.0 gpm)

NC Pump lB #1 Seal Leakoff Flow +_________ gpm 2(< 4.0 gpm)

NC Pump 1C #1 Seal Leakoff Flow +_________ gpm 2(< 4.0 gpm)

NC Pump 1D #1 Seal Leakoff Flow +_________ gpm 2(< 4.0 gpm) 2 Total NC Pumps #1 Seal Leakoff =_________ gpm < 16.3 gpm) 2 Acceptance Criteria Value Unit 1

Enclosure 13.2 PTI1IAJ4150/ool B NC Leakage Determination Using Manual Page 6 of 10 Calculations NOTE: 0 should be entered below for any negative identified or unidentified value.

0 1.10.27 Calculate Total Accumulative Leakage:

+ + (<2Ogpm) 3 gpm Identified (Step 1.10.24) Unidentified (Step 1.10.25) Total NC Seal Leakoff (Step 1.10.26) Total Accumulative Leakage 1.11 Determine Primary to Secondary Leakage by performing the following:

1 11.1

. IF in Mode 1 AND greater than or equal to 40% RTP, record indication on the following:

1EMF71:

gpd

1EMF72: gpd

1EMF73: gpd

1EMF74:

1.11.1.1 jj any N- 16 EMF inoperable, perform the following:

A. Notify Secondary Chemistry to provide Primary to Secondary leakage.

/

Person Notified Date Time Q B. Record Primary to Secondary leakage as determined by Secondary Chemistry: gpd 0 C. Record date and time Primary to Secondary leakage was determined (provided by Secondary Chemistry):

/

Date Time 1.11.2 IF in Mode 1 AND less than 40% RTP, perform the following:

1.11.2.1 Notify Secondary Chemistry to provide Primary to Secondary leakage.

/

Person Notified Date Time This value is a total primary to secondary leakage of all four S/Gs. A value of less than or equal to 135 gpd conservatively implies leakage through any one S/G is less than or equal to 135 gpd.

UÜit 1

Enclosure 13.2

/PTI 1A!4150/OO1 B NC Leakage Determination Using Manual Page 7 of 10 Calculations LI 1.11.2.2 Record Primary to Secondary leakage as determined by Secondary Chemistry: gpd 4

LI 1.11.2.3 Record date and time Primary to Secondary leakage was determined (provided by Secondary Chemistry):

/

Date Time 1.11.3 IF in Modes 2, 3 or 4, perform the following:

1.11.3.1 Notify Secondary Chemistry to provide Primary to Secondary leakage via grab sample.

/

Person Notified Date Time LI 1.11.3.2 Record Primary to Secondary leakage as determined by Secondary Chemistry grab sample: 4 gpd LI 1.1 1.3.3 Record date and time Primary to Secondary leakage was determined (provided by Secondary Chemistry):

/

Date Time Calculated By:__________________________________ Date: Time:

Checked By: Date: Time:

This value is a total primary to secondary leakage of all four S/Gs. A value of less than or equal to 135 gpd conservatively implies leakage through any one S/G is less than or equal to 135 gpd.

Unit 1

Enclosure 13.2 PT/1/A14150/O01 B NC Leakage Determination Using Manual Page 8 of 10 Calculations El 1.12 In Autolog, perform the following:

NOTE:

Calculations run during power escalation AND other than Mode 1 calculations should be identified as such.

The first calculation is considered the first calculation after 18:00 hrs for normal operation.

1.12.1 Enter the following values with any pertinent comments:

El IDENTIFIED leakage (Step 1.10.24)

El UNIDENTIFIED leakage (Step 1.10.25)

El TOTAL NC PUMPS #1 SEAL LEAKOFF leakage (Step 1.10.26)

El TOTAL leakage (Step 1.10.27)

El CALCULATION START TIME El Primary to Secondary leakage 1.12.2 IF other than the first calculation for the day, record reason and any pertinent comments.

NOTE: Unidentified Leakage values are expected to be within +/-0.5 gpm for Manual Calculations. Exceeding +/-0.5 gpm does NOT invalidate leakage calculation.

1.13 IF unidentified leakage NOT between +/-0.5 gpm, notify Primary System Engineer.

/

Person Notified Date Time Unit 1

Enclosure 13.2 PT/1/A1415o/ool B NC Leakage Determination Using Manual Page 9 of 10 Calculations 1.14 Evaluate Acceptance Criteria per one of the following:

El 1.14.1 Check Acceptance Criteria specified in Section 11 met.

OR 1.14.2 j Acceptance Criteria specified in Section 11 NOT met, perform the following:

1.14.2.1 Log applicable Tech Spec or SLC. {PIP M-07-00393}

SRO 1.14.2.2 Total NC Pumps #1 Seal Leakoff is greater than 16.3 gpm, SRO declare SSF capability degraded.

1.14.2.3 Total Accumulative Leakage is greater than 20 gpm Total SRO NC Pumps #1 Seal Leakoff greater than 16.3 gpm, notify Security of degraded SSF capabilities.

/

Person Notified Date Time 1.14.2.4 any NC Pump #1 Seal Leakoff has a sustained value of greater SRO than equal to 4.0 gpm, notify SSS Engineer and Security of degraded SSF capability.

/

Person Notified Date Time 1.15 IF this is the second Leakage Calculation and elevated leakage is indicated, evaluate performing PT/i /A/4 150/001 D (Identifying NC System Leakage).

1.16 Lower NCDT level less than 48%.

1.17 Close IWL-23 (NCDT Level Control).

1.18 Place 1WL-23 Mode Select to AUTO Unit 1

Enclosure 13.2 PT/1/A/415o/ool B NC Leakage Determination Using Manual Page 10 of 10 Calculations 1.19 Notify Radwaste Chemistry of the following:

El NC System leakage calculation is complete El PRT, NCDT and VCT sampling or venting may be initiated {PIPM-00-0615}

I Person Notified Date Time 1.20 Notify Primary Chemistry of the following:

El NC System leakage calculation is complete El NC System sampling may be initiated

/

Person Notified Date Time 1.21 IF Unit 1 at 100% RTP AND OAC is available, perform Enclosure 13.5 (Evaluation of NC System Unidentified Leakage Results).

End of Enclosure Unit 1

Enclosure 13.3 PT/11A14150/001 B NCDT Volume Page 1 of 1 NCDT LEVEL % NCDT VOLUME NCDT LEVEL % NCDT VOLUME NCDT LEVEL % NCDT VOLUME (Gal) (Gal) (Gal) 0 19.7 35 123.1 70 247.3 1 21.9 36 126.6 71 250.7 2 24.1 37 130.1 72 254.0 3 26.4 38 133.6 73 257.3 4 28.8 39 137.1 74 260.6 5 31.2 40 140.7 75 263.9 6 33.7 41 144.3 76 267.2 7 36.2 42 147.8 77 270.4 8 38.8 43 151.4 78 273.6 9 41.4 44 155.0 79 276.8 10 44.1 45 158.6 80 279.9 11 46.9 46 162.2 81 283.0 12 49.6 47 165.8 82 286.1 13 52.5 48 169.4 83 289.1 14 55.3 49 173.0 84 292.1 15 58.2 50 176.6 85 295.1 16 61.2 51 180.2 86 298.0 17 64.2 52 183.8 87 300.9 18 67.2 53 187.5 88 303.8 19 70.3 54 191.1 89 306.6 20 73.4 55 194.7 90 309.4 21 76.5 56 198.2 91 312.1 22 79.6 57 201.8 92 314.7 23 82.8 58 205.4 93 317.4 24 86.0 59 209.0 94 319.9 25 89.3 60 212.5 95 322.4 26 92.6 61 216.1 96 324.9 27 95.9 62 219.6 97 327.3 28 99.2 63 223.1 98 329.6 29 102.5 64 226.6 99 331.9 30 105.9 65 230.1 100 334.0 31 109.3 66 233.6 32 112.7 67 237.0 33 116.2 68 240.5 34 119.6 69 243.9 End of Enclosure Unit 1

Enclosure 13.4 PT/1/A14150/001 B PRT Volume Page 1 of I PRT LEVEL % PRT VOLUME PRT LEVEL % PRT VOLUME PRT LEVEL % PRT VOLUME (Gal) (Gal) (Gal) 0 303.2 35 4472.0 70 9799.8 1 371.9 36 4621.5 71 9942.5 2 445.6 37 4771.8 72 10084.0 3 523.9 38 4922.8 73 10224.1 4 606.7 39 5074.6 74 10362.9 5 693.6 40 5227.0 75 10500.3 6 784.5 41 5379.9 76 10636.1 7 879.0 42 5533.4 77 10770.4 8 977.0 43 5687.3 78 10903.1 9 1078.3 44 5841.7 79 11034.1 10 1182.7 45 5996.4 80 11163.3 11 1290.0 46 6151.4 81 11290.6 12 1400.2 47 6306.6 82 11416.0 13 1513.0 48 6461.9 83 11539.3 14 1628.4 49 6617.4 84 11660.6 15 1746.2 50 6772.9 85 11779.6 16 1866.2 51 6928.4 86 11896.2 17 1988.5 52 7083.8 87 12010.4 18 2112.9 53 7239.0 88 12122.0 19 2239.2 54 7394.1 89 12231.0 20 2367.5 55 7548.9 90 12337.0 21 2497.6 56 7703.4 91 12440.0 22 2629.4 57 7857.5 92 12539.9 23 2763.0 58 8011.2 93 12636.3 24 2898.1 59 8164.3 94 12729.2 25 3034.8 60 8316.9 95 12818.3 26 3172.9 61 8468.9 96 12903.4 27 3312.4 62 8620.3 97 12984.2 28 3453.3 63 8770.9 98 13060.5 29 3595.5 64 8920.7 99 13132.0 30 3738.9 65 9069.6 100 13198.3 31 3883.4 66 9217.7 32 4029.1 67 9364.8 33 4175.7 68 9510.9 34 4323.4 69 9655.9 End of Enclosure Unit 1

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGI

a. No pressure bounda \* S-

b. 1 gpm unidentified L

\ (- ccp

c. 10 gpm identified LE ci

d. 389 gallons per day h all steam generators (S

e. 135 gallons per day . .... . ....

one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS Operational A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within within limits.

limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

OR Primary to secondary LEAKAGE not within limits.

McGuire Units I and 2 3.4.13-1 Amendment Nos. 237/219

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 NOTES NOTE Only required to

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after be performed establishment of steady state operation. during steady state operation

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS Operational LEAKAGE is within limits by 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months performance of RCS water inventory balance.

SR 3.4.13.2 NOTE Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is < 135 gallons 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months per day through any one SG and < 389 gallons per day total through all SGs.

McGuire Units 1 and 2 3.4.13-2 Amendment Nos. 237 / 219

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM A3 ROISRO 2010 Admin JPM A3 ROISRO NUREG 1021, Revision 9

Appendix C Page 2 of 1 1 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Perform a Unit Vent Flow JPM No.: Exam 2010 Admin -

Calculation of a Containment Air JPM A3 RO/SRO Release K/A

Reference:

GKIA2.3.1i (3.8/3.8)

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: GWR Package #2010013 for Unit 1 Containment Air Release is currently in use to conduct a series of Containment air releases.

During the first release, conducted using Enclosure 4.2 (Air Release Mode With VQ Flow Monitor Operable) of OP/i/A16450/017 (Containment Air Addition and Release), the Unit 1 VQ Monitor became inoperable.

The crew stopped the release and continued the air release using Enclosure 4.3 (Air Release Mode with VQ Flow Monitor Inoperable) of OP/i /A16450/0i 7 (Containment Air Addition and Release).

Three previous releases have been made; including the one which was made with the Unit 1 VQ Flow Monitor in operation.

At 1743 on 8/4/1 0, containment pressure was 0.17 PSIG and a VQ release was initiated to reduce pressure to 0 12 PSIG per Step 3.8 of Enclosure 4.3.

This release was secured at 1839 on 8/4/10 and the procedure was completed through step 3.7.1 for this release.

RP has requested that the current GWR paperwork be closed out after the on-going release.

2010 Admin JPM A3 RO/SRO NUREG 1021, Revision 9

Appendix C Page 3 of 1 1 Form ESC-1 Job Performance Measure Worksheet Task Standard: The operator will calculate the volume of air released from the Containment during the final release, and determine the total volume of air released in the series of four releases in accordance with the provided KEY.

Required Materials: Calculator General

References:

OPI1/A16450/017 (Containment AirAddition and Release) 2010 Admin JPM A3 ROISRO NUREG 1021, Revision 9

Appendix C Page 4 of 1 1 Form ES-C-i Job Performance Measure Worksheet Handouts: Handout #1 Enclosure 4.2 (Air Release Mode With VQ Flow Monitor Operable) of OPI1/A/6450/017 (Containment Air Addition and Release) marked up as follows:

Step 2.1 Initialed.

Step 2.2 Initialed.

Step 2.3 Initialed.

Step 2.4 Initialed, GWR# 2010013 recorded.

Step 3.1 Checkbox is checked and Initialed.

Step 3.2 Initialed.

Step 3.2.1 Initialed and CV initialed.

Step 3.2.2 Initialed and CV initialed.

Step 3.2.3 Initialed and Mike Cline/Date/Time Recorded consistent with first release Date/Time (8/4/10 0903).

Step 3.3 Initialed.

Step 3.3.1 Initialed.

Step 3.3.2 Checkbox is checked and Initialed.

Step 3.4 Initialed and CV initialed.

Step 3.5 Initialed.

Step 3.6 Initialed.

Step 3.7 Initialed.

Step 3.7.1 Checkbox is checked and Initialed.

Step 3.7.2 Checkbox is checked and Initialed.

Step 3.7.3 Initialed and CV initialed, VQ Monitor flow is recorded as 1594, and Actual Volume Released is recorded as 15,940.

Step 3.7.4 Initialed.

Step 3.7.5 Checkbox is checked and Initialed.

Step 3.8.1 Checkbox is checked and Initialed.

Step 3.8.2 Checkbox is checked and Initialed.

Step 3.8.3 Checkbox is checked and Initialed.

Step 3.8.4 Checkbox is checked and Initialed.

Step 3.8.5 Both Checkbox are checked and Initialed.

Step 3.8.6 Initialed.

Step 3.9 Initialed.

2010 Admin JPM A3 RO/SRO NUREG 1021, Revision 9

Appendix C Page 5 of 1 1 Form ES-C-i Job Performance Measure Worksheet Page 5 of 5 (Attachment 1) is marked up as foflows: Sheet I of I IVQ-2B Open IVQ-2B Closed Doer CV VQ Flow DatelTime Doer CV DatelTime Monitor Counting (q)

Initial Initial 814110 0903 Initial Initial 8I4!10 1016 Handout #2 - Enclosure 4.3 (Air Release Mode With VQ Flow Monitor Inoperable) of OP/i 1AI645010 17 (Containment Air Addition and Release) marked up as follows:

Step 2.1 Initialed.

Step 2.2 Initialed.

Step 2.3 Initialed.

Step 2.4Initialed, GWR# 2010013 recorded.

Step 3.1 Checkbox is checked and Initialed.

Step 3.2 Initialed.

Step 3.2.1 Initialed and CV initialed.

Step 3.2.2 Initialed and CV initialed.

Step 3.2.3 Initialed and Person Notified/Date/Time Recorded consistent with release Date/Time on Page 6 of 6.

Step 3.3 Initialed.

Step 3.4 Initialed and CV initialed.

Step 3.5.1 Checkbox is checked and Initialed.

Step 3.5.2 Checkbox is checked and Initialed.

Step 3.5.3 Checkbox is checked and Initialed.

Step 3.5.4 Both Checkbox are checked and Initialed.

Step 3.5.5 Checkbox is checked and Initialed.

Step 3.5.6 Initialed.

Step 3.6 NA and Initialed.

Step 3.7 Initialed.

Step 3.7.1 Checkbox is triple-checked and Initialed.

Step 3.7.2-3 Checkbox is double-checked and Initialed.

Step 3.8 Initialed.

Step 3.9.1 through 3.9.3 Initialed.

2010 Admin JPM A3 RO/SRO NUREG 1021, Revision 9

Appendix C Page 6 of 1 1 Form ES-C-i Job Performance Measure Worksheet Page 6 of 6 (Attachment 1) is marked as follows: Sheet I of I IVQ-2B Open IVQ-2B Closed Doer CV DatelTime Start Doer CV DatelTime Stop 3 Ft Total Ft 3

Pressure Pressure Released Released (psig) (psig)

Initial Initial 814110 1117 0.21 Initial Initial 814/10 1258 0.12 21,469.28 21,469.28 Initial Initial 814/10 1432 0.19 Initial Initial 8!4110 1547 0.12 15,534.63 37,003.91 Initial Initial 8I4I10 1743 0.17 Initial Initial 0.12 Initiating Cue: You have been directed to calculate the volume released for this release and complete all required paperwork starting with Step 3.7.2, AND, since this is the last release perform Steps 3.9.4 through 3.9.8 of Enclosure 4.3 to determine the total volume released from the Containment.

The CRS notified RP (Mike Cline) at 1840 on 8/4/10 that the release has been terminated.

Complete all required paperwork.

Time Critical Task: NO Validation Time: 15 minutes 2010 Admin JPM A3 ROISRO NUREG 1021, Revision 9

Appendix C Page 7 of 1 1 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handouts

1 and #2.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Enclosure 4.3, Step 3.7.2) The operator records 814110 Record stop date/time on 1839 in the 1VQ-2B Closed Attachment I Date)Time Block of Attachment 1.

2 (Step 3.7.3) Calculate The operator uses Table 1 volume released using the of Enclosure 4.3 and following and record on determines X to be 10.51 Attachment 1. (Start Pressure of 0.17).

Cu. Ft. Released = X + The operator uses Table 1 (YxZ) of Enclosure 4.3 and Where: determines Yto be 201.1 (Start Pressure of 0.17).

X and Y are from Table 1 The operator uses Z is actual release duration Attachment 1 of Enclosure in minutes from Attachment 4.3 and determines Z to be

1. 56(StopTimeof 1839-Start Time of 1743).

The operator calculates volume released as follows:

10.51 +(201.i x 56) =

11,272.11+/-1% (See KEY),

and records this value in the 1VQ-2B Closed Cubic Ft Released Block of Attachment 1.

3 (Step 3.9.4) Ensure release The operator ensures stop date/time recorded on 814110 1839 recorded in the Attachment 1 1VQ-2B Closed Date/Time Block of Attachment 1.

4 (Step 3.9.5) Notify RP that The operator recognizes release has been from the initial conditions terminated that RP has been notified.

2010 Admin JPM A3 ROJSRO NUREG 1021, Revision 9

Appendix C Page 8 of 1 1 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 (Step 3.9.6) Determine The operator adds the Total Cu. Ft Released on volume of this most recent Attachment 1. release (11,272.11) to the total previously released on Attachment 1 (37,003.91) and determines that the total volume released is 48,276.02 ft3 +/-1% (See KEY).

The operator records this value in the 1VQ-2B Closed Total Cubic Ft Released Block of Attachment 1.

6 (Step 3.9.7) Record Total The operator records Cu. Ft Released from 48,276.02 in the IVQ-2B Attachment 1: 3 ft Closed Cubic Ft Released Block of Attachment 1.

7 (Step 3.9.8) IF Enclosure The operator observes Step 4.2 (Air Release Mode With 3.7.3 of Enclosure 4.2 and VQ Flow Monitor Operable) determines that 15,940 ft3 was used during this had been released when release, perform the the VQ Monitor was following: operable, and records this (Step 3.9.8.1) Record value on Enclosure 4.3, Actual Volume Released Step 3.9.8.1.

from Enclosure 4.2, Step 373.

The operator adds the total (Step 3.9.8.2) Calculate volume released recorded Total Volume Released as in Step 3.9.7 (48,276.02) follows: and the total volume ft 3 + released recorded in Step ft 3 3.9.8.1 (15,940), and Step 310.7 Step 3108.1 Total Vol Rel determines the Total Volume Released for this

series of Containment Air Releases is 64,216.02 ft 3

+/-1% (See KEY).

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2010 Admin JPM A3 RO/SRO NUREG 1021, Revision 9

Appendix C Page 9 of 1 1 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No: 2010 Admin JPM A3 RO/SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2010 Admin JPM A3 RO/SRO NUREG 1021, Revision 9

Appendix C Page 10 of 1 1 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Enclosure 4.3, Attachment 1:

RED fifled in at start of JPM.

GREEN = filled in during JPM performance IVQ-2B Open IVQ-2B Closed Doer CV Date/Time Start Doer CV DatelTime Stop 3 Ft Total Ft 3

Pressure Pressure Released Released (psig) (psig)

Initial Initial 814110 1117 0.21 Initial Initial 8I4!10 1258 0.12 21,469.28 21,469.28 Initial Initial 814110 1432 0.19 Initial Initial 814I10 1547 0.12 15,534.63 37,003.91 Initial Initial 814/10 1743 0.17 Initial Initial 814110 1839 0.12 11,272.11 48,276.02 Enclosure 4.3, Step 3.7.3 (JPM Step 2): Volume released, current release:

10.51 ft 3 + (201.1 ftlmin x 56 mm ) = 11,272.11 ft 3 3 Enclosure 4.3, Step 3.9.6 (JPM Step 3): Total Volume released, during performance of Enclosure 4.3:

11,272.11 ft 3 + 37,003.91 ft3 = 48,276.02 +/-1% ft 3 (47,793.26 48758.78)

Enclosure 4.3, Step 3.9.8.2 (JPM Step 5): Total Volume released, during performance of GW Permit:

48,276.02 ft 3 + 15940 3 ft = 64,216.02+/-1% ft (63,573.86 -64,858.18) 2010 Admin -JPMA3 RO/SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS: GWR Package#2010013for Unit 1 Containment Air Release is currently in use to conduct a series of Containment air releases.

During the first release, conducted using Enclosure 4.2 (Air Release Mode With VQ Flow Monitor Operable) of OP/i /A16450/Oi 7 (Containment Air Addition and Release), the Unit 1 VQ Monitor became inoperable.

The crew stopped the release and continued the air release using Enclosure 4.3 (Air Release Mode with VQ Flow Monitor Inoperable) of OP/i /A/6450/01 7 (Containment Air Addition and Release).

Three previous releases have been made; including the one which was made with the Unit I VQ Flow Monitor in operation.

At 1743 on 8/4/10, containment pressure was 0.17 PSIG and a VQ release was initiated to reduce pressure to 0.12 PSIG per Step 3.8 of Enclosure 4.3.

This release was secured at 1839 on 8/4/10 and the procedure was completed through step 3.7.1 for this release.

RP has requested that the current GWR paperwork be closed out after the on-going release.

INITIATING CUE: You have been directed to calculate the volume released for this release and complete all required paperwork starting with Step 3.7.2, AND, since this is the last release perform Steps 3.9.4 through 3.9.8 of Enclosure 4.3 to determine the total volume released from the Containment.

The CRS notified RP (Mike Cline) at 1840 on 8/4/10 that the release has been terminated.

Complete all required paperwork.

NUREG 1021, Revision 9

Duke Energy Procedure No.

McGuire Nuclear Station OP/l/A/6450/017 Containment Air Release and Addition System Revision No.

037 Electronic Reference No.

MC00475F Continuous Use PERFORMANCE I

* * * * * * * * *1jI..4CQNTRQLLEDFORPRNT* * * * * * * * * *

(ISSUED) PDF Format

OPI1/A/6450/0 17 Page 2 of 3 Revision History (significant issues, limited to one page)

Rev 037 Changed all references from DV to CV per NSD 700 Revision 006. Changed all references from Person Contacted to Person Notified per procedure writer guidelines. Modified steps throughout procedure that started with WHEN to reflect NSD 704 Rev 016 requirements.

End. 4.5 and 4.6. Re-worded step for evaluating R&Rs when preparing to return to normal alignment after testing. If maintenance was not performed for penetration being tested, do not have to check R&Rs again.

End. 4.2, 4.3. Re-worded steps to allow operator to make subsequent VQ releases per Attachment 1 instead of back to steps of procedure to aid in procedure use and adherence. There is normally a large number of releases performed while this procedure is outstanding since it is normally open for one month at a time.

End. 4.3. Updated Attachment 1 to determine cubic foot released per step 3.7.3 (that gives direction to calculating the amount released).

End. 4.8. Added IF AT ANY TIME to section if VQ monitor becomes inoperable or stops counting. Moved this step prior to starting release for better procedure use and adherence. Changed step to record VQ Flow Monitor reading on GWR paperwork when GWR paperwork available. Originally procedure recorded zero.

Re-worded Section 3.7 like Section 3.8 for recording start time of release.

Rev 036

End. 4.2. Added steps to reset VQ Flow monitor at beginning of procedure. This accounts for initiating the release and transitioning from End. 4.3 with VQ Flow monitor inoperable. Made old step 3.8 conditional if not making subsequent releases

End. 4.2 and 4.8. Reformatted table in Attachment 1 to make more space for Date/Time to be recorded.

End. 4.3. Made old step 3.8 conditional if not making subsequent releases.

End. 4.5 and 4.6. Changed signoff requiring clearance from WCCSRO to SRO.

Rev 035

Enclosure 4.6, Arranged steps for aligning penetration for testing to make procedure more efficient.

Enclosure 4.3 and 4.8, Formatted data table to include a column to keep a running total of cubic feet released. Thi relieves operators from having to total all the numbers when table is completed.

Rev 034 The following was changed due to PIP M-07-00033:

Enclosure 4.1, 4.2, 4.3, 4.8. T.S. 3.9.4 changed definition of core alterations. Added recently to make statement read recently irradiated fuel assemblies.

Enclosure 4.9, if sample switch to lower is off greater than 15 minutes, then EMF-38L is inoperable.

Unit 1

OP/1/A/6450/O 17 Page 3 of 3 Containment Air Release And Addition System

1. Purpose To outline operation of VQ System in the Air Addition Mode and the Air Release Mode.

2. Limits and Precautions 2.1 Containment Pressure Tech Spec limit is +/-0.3 psig.

2.2 All Engineered Safeguards Valves shall be cycled electrically after any manual operation.

2.3 Valves operated in this procedure shall be operated by normal means only. Artificial assistance prohibited (Examples: Tightening an MOV with handwheel or using a cheater-bar on a manual valve).

3. Procedure See Section 4.

4. Enclosures 4.1 Air Addition Mode 4.2 Air Release Mode With VQ Flow Monitor Operable 4.3 Air Release Mode With VQ Flow Monitor Inoperable 4.4 Valve Checklist 4.5 Establishing Conditions For Testing Penetration 1M-243 4.6 Establishing Conditions For Testing Penetration 1M-384 4.7 Swapping VQ Filters 4.8 Emergency VQ Release Without GWR Release Paperwork 4.9 Operation of 1EMF 38, 39, 40 Sample Blower End of Body Unit 1

Enclosure 4.2 OP/1/A/6450/0 17 Air Release Mode With VQ Flow Monitor Page 1 of5 Operable

1. Limits and Precautions 1./ Containment Pressure Tech Spec limit is +/-0.3 psig.

1 .Q All Engineered Safeguards Valves shall be cycled electrically after any manual operation.

2. Initial Conditions 2.1 Per Tech Spec 3.9.4, movement of recently irradiated fuel assemblies within Containment, is NOT in progress. {PIP M-05-1608, PIP M-07-0033, CAPR}

2.2 VQ Flow Monitor is operable.

2.3 Containment pressure requires an air release.

2.4 GWR # 2O QOk 3 has been issued.

3. Procedure 1 Evaluate all outstanding R&Rs that may impact performance of this procedure.

3.2 IF 1EMF-39L monitoring release, perform the following:

c\ 3.2.1 Ensure 1EMF-39L Trip 1 setpoint set per GWR.

y iAL 3.2.2 Ensure 1EMF-39L Trip 2 setpoint set per GWR.

ck 3.2.3 Notify RP to update 1EMF-39L setpoints in EMF Setpoint Log.

I Person Notified Date Time

!J this is initial release Qj directed to this enclosure from Enclosure 4.3, (Air Release Mode With VQ Flow Monitor Inoperable), perform the following:

3.3.1 Reset VQ Flow Monitor:

w/3.3.2 Record Release start date and time on GWR paperwork.

3.4 Throttle 1VQ-4 (VQ To Unit Vent Control) 15% open.

JL 3.5 Ensure 1VQ-2B (Cont Air Rel Outside Isol) closed.

3.6 Open 1VQ-1A (Cont Air Rel Inside Isol).

Unit 1

Enclosure 4.2 oP/1/A/645o/o17 Air Release Mode With VQ Flow Monitor Page 2 of 5 Operable 3.7 IF AT ANY TIME VQ Flow Monitor stops counting OR becomes inoperable, perform the following:

[(3.7.1 Ensure 1VQ-2B (Cont Air Rel Outside Isol) closed per Attachment i.

Ensure release stop date / time recorded on Attachment 1.

I_ir 3.7.3 Record VQ Flow Monitor actual volume released as follows: {PIP 05-5685}

)594 xlO= j94O 3 ft VQ Flow Monitor Actual Volume Released 3.7.4 Reset VQ Flow Monitor.

M3.7.5 Exit this enclosure and go to Enclosure 4.3 (Air Release Mode With VQ Flow Monitor Inoperable).

3.8 Start initial VQ release as follows:

3.8.1 Open I VQ-2B (Cont Air Rel Outside Isol) per Attachment 1.

3.8.2 Maintain a release rate less than 300 cfm by throttling 1VQ-4 (VQ To Unit Vent Control).

d3.8.3 Record that VQ Flow Monitor is counting on Attachment 1.

3.8.4 Record start date / time on Attachment 1.

3.8.5 Record the following in Auto Log:

I:r(/Release number ll1 Start time 3.8.6 Ensure Release Initiation on GWR is completed.

cK 3.9 To secure release, close lVQ2B (Cont Air Rel Outside Isol) per Attachment I.

3.10 IF AT ANY TIME it is desired to throttle 1 VQ-4 (VQ To Unit Vent Control) in subsequent releases, maintain release rate less than 300 cfm.

3.11 IF subsequent releases with existing GWR are required, maintain containment pressure less than 0.20 psig per Attachment 1.

Unit 1

Enclosure 4.2 oP/1/A/645o/o17 Air Release Mode With VQ Flow Monitor Page 3 of 5 Operable 3.12 IF desired to close out existing GWR, perform the following:

3.12.1 Close 1VQ-1A (Cont Air Rel Inside Iso!).

3.12.2 Close 1VQ-4 (VQ To Unit Vent Control).

cv 3.12.3 Ensure 1VQ-2B (Cont Air Rel Outside Isol) closed per Attachment 1.

3.12.4 Ensure release stop date / time recorded on Attachment 1.

3.12.5 Notify RP that VQ release has been terminated and 1EMF-38, 1EMF-39, and 1EMF-40 setpoints need to be evaluated. {PIP l-M97-1925}

/

Person Notified Date Time 3.12.6 Record VQ Flow Monitor total volume released as follows: {PIP 05-5685}

cv xlO= 3 ft VQ Flow Monitor Total Volume Released 3.12.7 IF Enclosure 4.3 (Air Release Mode With VQ Flow Monitor Inoperable) was used during this release, perform the following:

LI 3.12.7.1 Record Total Cu Ft Released from Enclosure 4.3, Attachment 1:

3 ft Li 3.12.7.2 Calculate Total Volume Released as follows:

+

3 ft =

3 ft 3 ft Step 3.12.6 Step 3.12.7.1 Total Vol Rel Unit 1

Enclosure 4.2 OP/1/A/6450/017 Air Release Mode With VQ Flow Monitor Page 4 of 5 Operable 3.12.8 Record the following in Auto Log:

Li Release number Li Stop time Li Volume released Li 3.12.9 Record release stop date/time on GWR.

Li 3.12.10 Record and CV Total Vol. ReV on GWR. (Step 3.12.6 or Step 3.12.7.2)

{Pll 05-5685}

3.12.11 Ensure Release Completion on GWR is completed.

Li 3.12.12 RouteGWRtoSRO.

3.12.13 Reset VQ Flow Monitor.

Unit 1

Enclosure 4.2 OP/1/A/6450/O 17 Air Release Mode With VQ Flow Monitor Page 5 of 5 Operable Attachment 1 Sheet of 1VQ-2B Open 1VQ-2B Closed Doer CV VQ Flow Date/Time Doer CV Date/Time Monitor Counting V)

-f1 / /0 oO3 /4 AD lvi End of Enclosure Unit 1

Enclosure 4.3 OP/l/A/6450/o17 Air Release Mode With VQ Flow Monitor Page 1 of 6 Inoperable

1. Limits and Precautions 1.1 Wntainment Pressure Tech Spec limit is +/-0.3 psig.

1.2 w(uioperation.

Engineered Safeguards Valves shall be cycled electrically after any manual

2. Initial Conditions 2.1 Per Tech Spec 3.9.4, movement of recently irradiated fuel assemblies within Containment, is NOT in progress. {PW M-05-1608, PIP M-07-0033, CAPR}

2.2 VQ Flow Monitor is inoperable.

2.3 Containment pressure requires an air release.

2JL 2.4 GWR# OOO has been issued.

3. Procedure 1 Evaluate all outstanding R&Rs that may impact performance of this procedure.

3.2 IF 1EMF-39L monitoring release, perform the following:

3.2.1 Ensure IEMF-39L Trip 1 setpoint set per GWR.

3.2.2 Ensure 1EMF-39L Trip 2 setpoint set per GWR.

CV L 3.2.3 Notify RP to update 1EMF-39L setpoints in EMF Setpoint Log.

\<e C\ /

Person Notified Date Time 2i2_ 3.3 Open 1VQ-1A (Cont Air Rel Inside Isol).

NOTE: jIVQ-4 (VQ To Unit Vent Control) is required to be in full open position for air releases with VQ Flow Monitor inoperable.

3.4 Fully open 1VQ-4 (VQ To Unit Vent Control).

Unit 1

Enclosure 4.3 OP/1/A/6450/017 Air Release Mode With VQ Flow Monitor Page 2 of 6 Inoperable 3.5 Start initial VQ release as follows:

3.5.1 Open 1 VQ-2B (Cont Air Rel Outside Iso!) per Attachment 1.

13.5.2 Record start date I time on Attachment 1.

Record start pressure on Attachment 1.

3.5.4 Record the following in Auto Log:

IRelease number EY Start time Record release start date / time on GWR.

i)2_. 3.5.6 Ensure ??Release Initiation t on GWR is completed.

3.6 IF AT ANY TIME VQ Flow Monitor becomes operable, perform the following:

3.6.1 Ensure 1VQ-2B (Cont Air Rel Outside Iso!) closed per Attachment 1.

3.6.2 Ensure release stop date I time recorded on Attachment 1.

3.6.3 Record Total Cu. Ft. Released on Attachment 1. {PIP 05-5685}

cv U 3.6.4 Exit this enclosure and go to Enclosure 4.2 (Air Release Mode With VQ Flow Monitor Operable).

Unit 1

Enclosure 4.3 OP/1/A/6450/017 Air Release Mode With VQ Flow Monitor Page 3 of 6 Inoperable 3.7 HOLD until containment pressure reaches 0.12 psig, THEN secure VQ release as follows:

L/3.7.1 Close 1VQ-2B (Cont Air Rel Outside Isol) per Attachment 1.

l3 .7.2 Record stop date / time on Attachment 1.

Calculate volume released using the following and record on Attachment 1:

(Documentation of calculation NOT required)

Cu.Ft.Released=X+(YxZ)

Where: X and V are from Table 1 Z is actual release duration in minutes from Attachment 1 3

ft + ( /min X 3

ft mm) 3 ft X (Table) Y (Table) Z (Release Duration)

Table 1 Start Pressure Stop Pressure X V (Always 0.12)

(psig) (psig) )

3 (ft lmin) 3 (ft 0.12 0.12 0 0 0.13 0.12 0 188.29 0.14 0.12 0.64 191.71 0.15 0.12 2.39 194.98 0.16 0.12 5.60 198.10 0.17 0.12 10.51 201.10 0.18 0.12 17.31 203.99 0.19 0.12 26.13 206.78 0.20 0.12 37.07 209.47 0.21 0.12 50.21 212.07 0.22 0.12 65.57 214.60 0.23 0.12 83.20 217.06 0.24 0.12 103.09 219.44 Unit 1

Enclosure 4.3 OP/1/A/6450/017 Air Release Mode With VQ Flow Monitor Page 4 of 6 Inoperable 3.8 IF subsequent releases required, maintain containment pressure less than 0.20 psig per Attachment 1.

3.9 IF it is desired to close out existing GWR, perform the following:

3.9.1 Close 1VQ-1A (Cont Air Rel Inside Isol).

£5LY ,, 3.9.2 Close 1VQ-4 (VQ To Unit Vent Control).

4.

L 3.9.3 Ensure 1VQ-2B (Cont Air Rel Outside Isol) closed per Attachment 1.

3.9.4 Ensure release stop date / time recorded on Attachment 1.

3.9.5 Notify RP that VQ release has been terminated and 1EMF-38, 1EMF-39, and 1EMF-40 setpoints need to be evaluated. {PIP 1-M97-1925}

/

Person Notified Date Time EJ 3.9.6 Determine Total Cu. Ft Released on Attachment 1.

0 3.9.7 Record Total Cu. Ft Released from Attachment 1: 3 ft 3.9.8 IF Enclosure 4.2 (Air Release Mode With VQ Flow Monitor Operable) was used during this release, perform the following:

O 3.9.8.1 Record Actual Volume Released from Enclosure 4.2, Step 3.7.3:

3 ft LI 3.9.8.2 Calculate Total Volume Released as follows:

ft 3 ft Step 3.9.7 Step 3.9.8.1 Total Vol Rel Unit 1

Enclosure 4.3 OP/1/A/6450/Ol 7 Air Release Mode With VQ Flow Monitor Page 5 of 6 Inoperable 3.9.9 Record the following in Auto Log:

D Release number U Stop time U Volume released U 3.9.10 Record release stop date / time on GWR.

U 3.9.11 Record and CV Total Vol. Re!. on GWR. (Step 3.9.7 or Step 3.9.8.2)

{P1P 05-5685}

3.9.12 Ensure Release Completion on GWR is completed.

U 3.9.13 RouteGWRtoSRO.

Unit 1

Enclosure 4.3 0PI1IA/645o1o17 Air Release Mode With VQ Flow Monitor Page 6 of 6 Inoperable Attachment 1 Sheet I of 1VQ-2B Open 1VQ-2B Closed Doer CV Date/Time Start Doer CV Date/Time Stop Pressure Cubic Ft Total Cubic Ft Pressure (psig) Released per Released (psig) Step 3.7.3

&, S-rc\ 4 4 /ic i\7 c. Lrr W4/ic 0.12 iL,49.28 U,428 SLr(\ &J4Ac O Jfl 1 4

P 4;:1io if7 0.12 (3 373fl O. swr 0.12 0.12 0.12 0.12 0.12 0.12 0.12 0.12 0.12 0.12 0.12 Total Cu. Ft Released End of Enclosure Unit 1

Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA4SRO 2010 Admin JPM A4 SRO

- NUREG 1021, Revision 9

Appendix C Page 2 of 1 1 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Provide an Updated PAR JPM No.: 2010 Admin JPM A4 SRO KIA

Reference:

GKIA 2.4.44 (4.4)

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: A LOCA inside containment has occurred on Unit 1.

The crew implemented EPI1IAJ5000IECA-i .1 (Loss of Emergency Coolant Recirc) due to multiple ECCS component failures.

A Containment Red Path and a Core Cooling Red Path have occurred.

The Emergency Coordinator declared a General Emergency per RP/0/A15700/000, Enclosure 4.1, EAL #4.1 .G.2 (Loss of Any two Barriers AND Potential loss of the third).

An Emergency Notification Form, along with the initial PAR was sent at the appropriate time.

The following conditions exist 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the start of the event.

The radioactive release is still on-going.

The wind speed is 9 mph.

The wind direction is 158.9°.

EMF51 A and B reading is 800 R/hr.

A Radioactive Release is still in progress above normal limits.

The OAC is NOT available.

2010 Admin JPM A4 SRO

- NUREG 1021, Revision 9

Appendix C Page 3 of 1 1 Form ES-C-i Job Performance Measure Worksheet Task Standard: The operator will determine the PAR for the current conditions to be as reflected on the provided KEY.

Required Materials: None General

References:

RP/01A157001000 (Classification of Emergency)

RP101B157001029 (Notifications to Offsite Agencies from the Control Room)

Handouts: Initial Emergency Notification Form Copy of Enclosure 4.4 (Offsite Protective Action Recommendation) of RP101B157001029 (Notifications to Offsite Agencies from the Control Room) marked up to step 2.

Initiating Cue: Based on the present conditions, the OSM directs you to update the PAR by completing steps 2 through 12 of Enclosure 4.4 (Offsite Protective Action Recommendation) of RP/01B15700/029 (Notifications to Offsite Agencies from the Control Room)

Complete the Sections below as appropriate Time Critical Task: NO Validation Time: 10 minutes 2010 Admin JPM A4 SRO

- NUREG 1021, Revision 9

Appendix C Page 4 of 1 1 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM) and Handout the Initial Emergency Notification Form and Enclosure 4.4 of RP!01B157001029 marked up to step 2.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Enclosure 4.4, Step 1) If a The operator recognizes General Emergency is per the initial conditions this declared, determine initial step is already complete.

Protective Action Recommendation

2 (Step 2) If Wind Speed is The operator recognizes less than or equal to that Wind Speed is greater than 5 mph, and proceeds to Step 3.

2010 Admin JPM A4 SRO

- NUREG 1021, Revision 9

Appendix C Page 5 of 1 1 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 (Step 3) If Wind Speed is The operator uses the greater than 5mph, Table and determines that evacuate and shelter zones the applicable Wind as shown in the table below Direction range is 157.6-based on wind direction 180.00.

Caution 1: Once a zone is The operator observes that selected for evacuation, it Sectors A, B, C, L, M, and should not be removed. N are recommended to be evacuated for a 2 mile radius, and 5 miles Caution 2: A short term downwind.

release is any release that can be projected to be 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months or less in duration. The operator observes that An example would be a Sectors D, E, F, G, H, I, J, puff release. A controlled K, 0, P, Q, R and S are release is one that can be recommended to be started or stopped at the sheltered.

licensees discretion, such as the venting of Containment for pressure The operator applies control. If a release is short Caution 1, and recognizes term and controlled, then that Sectors D, 0 and R sheltering in lieu of have previously been evacuation should be evacuated, and although considered. the Table recommends that they be sheltered, they must remain evacuated.

The operator recognizes that Caution 2 does NOT apply.

The operator recommends that Sectors A, B, C, D, L, M, N, 0 and R remain evacuated for a 2 mile radius, and 5 miles downwind; and that Sectors E, F, G, H, I, J, K, P, Q, and S are remain sheltered.

2010 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 6 of 1 1 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4 (Step 4) If notified by RP The operator recognizes Dose Assessment that dose that no RP Dose projections or field Assessments have been measurements indicate that made, and proceeds to thyroid dose will be greater Step 5.

than 5 Rem 5 (Step 5) For any other The operator recognizes Protective Action that there are no other Recommendation, Check E PARs, and proceeds to (Other), and record Step 6.

information

6 (Step 6) After the initial PARS are transmitted to offsite agencies, check for large fission product inventory in Containment as follows:

The operator recognizes (Step 6.1) If the OAC is that the OAC is NOT available..., available and proceeds.

(Step 6.2) If the OAC is The operator recognizes unavailable, use the that 1 EMF5I A and B following EMFs: 1EMF51A, readings must be used.

1EMF51B (Step 6.3) Check if The operator uses the table Containment radiation level in the Time after Shutdown exceeds the following limits column of 0-2 hours, and based on time after compares the 1 EMF51A shutdown:

and B readings of 800 RJhr to the established limit of 864 R/hr determining that the Large Fission Product Inventory in Containment has NOT been met.

2010 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 7 of 1 1 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

7 (Step 7) If Containment The operator recognizes radiation level exceeds that the radiation levels are limits in Step 6.3 NOT exceeded, and proceeds to Step 8.

8 (Step 8) A McGuire EPZ The operator acknowledges Map is located on Page 8 of and proceeds to Step 9.

8, if it is desired to visually see zones evacuated or sheltered.

9 (Step 9) If notified by RP The operator recognizes Dose Assessment that dose that no RP Dose projections or field Assessments have been measurements indicate that made, and proceeds to thyroid dose will be greater Step 10.

than 5 Rem 10 (Step 10) On a continuing The operator acknowledges basis, evaluate specific and proceeds to Step 1 1.

plant conditions including:

large fission product inventory in Containment, EMF 51 A/B readings, offsite dose projections, wind speed and wind direction, field monitoring team data, and assess the need to update Protective Action Recommendations made to the states and counties in the previous notification.

II (Step 1 1) Review dose The operator recognizes projections with the on-shift that no Dose Assessments dose assessor (if available) have been made, and to determine if Protective proceeds to Step 12.

Action Recommendations are required beyond the 10-mile radius.

2010 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 8 of 1 1 Form ES-C-I PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

12 (Step 12) If Protective The operator recognizes Action Recommendations that no RP Dose are required beyond 10 Assessments have been miles.... made, and returns the completed PAR marked up as established on the KEY.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2010 Admin JPM A4 SRO

- NUREG 1021, Revision 9

Appendix C Page 9 of 1 1 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2010 Admin JPM A4 SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2010 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 10 of 1 1 Form ES-C-i VERIFICATION OF COMPLETION KEY:

PROTECTIVE ACTION RECOMMENDATIONS:

A None Evacuate: A, B, C, D, L, M, N, 0 and R remain evacuated for a 2 mile radius, and

5 miles downwind Shelter: E, F, G, H, I, J, K, P, Q, and S Consider the Use of KI (Potassium Iodide) in accordance with State Plans and Policy:

D NA Other: NA E

2010 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions: A LOCA inside containment has occurred on Unit 1.

The crew implemented EP/i !AI5000IECA-1 .1 (Loss of Emergency Coolant Recirc) due to multiple ECCS component failures.

A Containment Red Path and a Core Cooling Red Path have occurred.

The Emergency Coordinator declared a General Emergency per RP/0/A/5700/000, Enclosure 4.1, EAL #4.1 .G.2 (Loss of Any two Barriers AND Potential loss of the third).

An Emergency Notification Form, along with the initial PAR was sent at the appropriate time.

The following conditions exist 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the start of the event:

The radioactive release is still on-going.

The wind speed is 9 mph.

The wind direction is 158.9°.

EMF51 A and B reading is 800 R/hr.

A Radioactive Release is still in progress above normal limits.

The OAC is NOT available.

INITIATING CUE: Based on the present conditions, the OSM directs you to update the PAR by completing steps 2 through 12 of Enclosure 4.4 (Offsite Protective Action Recommendation) of RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room).

Complete the Sections below as appropriate.

NUREG 1021, Revision 9

Duke Energy Procedure No.

McGuire Nuclear Station Rp/O/B/5700/029 NOTIFICATIONS TO OFFSITE AGENCIES FROM THE Revision No.

CONTROL ROOM 009 Electronic Reference No.

MPOO72VO Reference Use PERFORMANCE I

* * * * * * * * *IJNCONTROLLED FOR PRJ1%JT* * * * * * * * * *

(ISSUED) PDF Format

Enclosure 4.4 RP/0/B/5700/029 Offsite Protective Action Recommendations Page 1 of 8 NOTE: 1. Protective Action Recommendations (PARs) for the public apply during a General Emergency, and include sheltering, evacuation and consideration of KI use. PARs are based on plant conditions independent of projected dose, and can also be based on projected dose. Protective Action Guides (PAGs) are levels of radiation dose at which prompt protective actions should be initiated and are based on EPA-400-R-92-00 1, Manual of protective Action Guides and Protective Actions for Nuclear Incidents. The projected dose PARs specified in this enclosure are based on the PAGs listed below.

The PAG for KI is taken from Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies, FDA Guidance, November 2001 and Guidance for Industry, KI in Radiation Emergencies, Questions and Answers, FDA, December 2002. {23}

PROTECTIVE ACTION GUIDES (PAGs)

Projected Dose Total Effective Dose Committed Dose Recommendation Equivalent (TEDE) Equivalent (CDE)

Thyroid

< I rem < 5 rem No Protective Action is required based on projected dose.

> 1 rem > 5 rem Evacuate affected zones and shelter the remainder of the 10-mile EPZ not evacuated.

N/A > 5 rem Consider the use of 1<1 (potassium iodide) in accordance with State Plans and Policy.

2. j desired, you may refer to the flow chart of page 2 of this enclosure. {PIP M 5137, C.A.3}

Enclosure 4.4 RP/O/B/5700/029 Offsite Protective Action Recommendations Page 2 of 8 General Emergency no i_declared Recommend evacuation t11 Recommend: of 2-mile radius and zones 5 wind speed Evacuate zones: miles downwind.

less than or A, B, C, D, L, M, N, 0, R Recommend shelter-in-place equal to (5 miles around) remaining zones. Refer to yes Shelter-in-place zones: End. 4.4, pg. 4 of 8.

E, F, G, H,, J, K, P, 0, S Recommend the consideration INITIAL PAR DETERMINATION of KI use by the public. {23}

UPGRADE PAR Continue monitoring parameters in this flowchart loop to recommend PAR upgrades:

DETERMINATION .__J 1. Assess containment conditions for a large fission product inventory, dose projection calculations, wind speed, wind direction and field monitoring team data to determine the need to update PARs.

J 2. Review dose projections to determine if protective actions are required beyond the 10-mile EPZ.

Are Is offsite dose a large fission projections V speed or N product inventory no 1 rem TEDE no ../,ind direction changeN. no greater than gap activity and/or / sufficiently to affect zones in containment? 5 rem CDE thyroid previously Refer to End. 4.4, in anyzones not pg. 5of8. previously evacuated?

yes Recommend the consideration yes yes of KI use by the public. {23}

Recommend evacuation t of Recommend evacuationt 11 of Recommend evacuationm Evacuate unless conditions make 5-mile radius and 10 miles affected zone(s) with dose projections of additional zone(s) per evacuation dangerous as determined by downwind. 1 rem TEDE and/or End. 4.4, pg. 4 of 8. state and ocal agencies, e.g., dangerous Shelter-in-place 5remCDE thyroid. Shelter-in-place for any travel conditions or special populations.

all other zones not previously Shelter remainder of 10-mile EPZ zones not previously Consider shelter-in-place for a short term evacuated. Refer to End. 4.4, previously evacuated. release if accurately projected to be <three evacuated. hours and controlled by the licensee.

pg. 6 of 8.

Enclosure 4.4 RP/0/B/5700/029 Offsite Protective Action Recommendations Page 3 of 8 IF a General Emergency is declared, determine Initial Protective Action Recommendations as follows (PIP-M-02-6 163):

Obtain the wind speed and direction, use chart recorder 1EEBCR9 100, point #5 (Average Lower Wind Speed) and point #8 (Average Upper Wind Direction).

a Wind Direction (Point 8):

Wind Speed (Point 5): 9 rc ph 1.2 IF Chart Recorder unavailable, obtain wind direction from one of the following sources, preferred sequence:

D A. Unit I OAC:

Average Upper Wind Direction M1P0847

Average Lower Wind Speed M1P0848.

EJ B. DPC Meteorologist (9-704-382-0139 or 9-704-373-7896).

D C. National Weather Service in Greer, S.C. (9-864-879-1085 or 9-800-268-7785).

2. IF wind speed less than or equal to 5 MPH, recommend the following:

CAUTION: 1. Once a zone is selected for evacuation, it should not be removed. {PIP-M-03-3483}

2. A short term release is any release that can be projected to be 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months or less in duration. An example would be a puff release. A controlled release is one that can be started and stopped at the licensees discretion, such as the venting of Containment for pressure control. IF a release is short term and controlled, THEN sheltering in lieu of evacuation should be considered. {PIP-M-05-363 1 }

Q 2.1 Evacuate zones A, B, C, D, L, M, N, 0, R. (See Caution 2 above)

LI 2.2 Shelter zones E, F, G, H, I, J, K, P, Q, S.

Enclosure 4.4 RP/O/B/5700/029 Offsite Protective Action Recommendations Page 4 of 8

3. IF wind speed is greater than 5 MPH, evacuate and shelter zones as shown in the table below based on wind direction:

CAUTION: 1. Once a zone is selected for evacuation, it should not be removed. {PIP-M-03-3483}

2. A short term release is any release that can be projected to be 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months or less in duration. An example would be a puff release. A controlled release is one that can be started and stopped at the licensees discretion, such as the venting of Containment for pressure control. IF a release is short term and controlled, THEN sheltering in lieu of evacuation should be considered. {PIP-M-05-363 1 }

Protective Action Zones Determination Wind Speed Greater than 5 Miles per Hour Wind Direction (deg from N)

Chart Recorder 1EEBCR9 100 Point # 8 Average Upper Wind Evacuate* Shelter Direction 2 Mile Radius-5 Mile Downwind Remaining Sectors 0.1 22.5

- B,C,D,L,M,O,R A,E,F,G,H,I,J,K,N,P,Q,S 22.6 45.0 B,C,D,L,M,O,R A,E,F,G,H,I,J,K,N,P,Q,S 45.1 67.5 B,C,D,L,M,O,R A,E,F,G,H,I,J,K,N,P,Q,S 67.6 90.0 B,C,D,L,M,N,O,R A,E,F,G,H,I,J,K,P,Q,S 90.1 112.5 B,C,L,M,N,O,R A,D,E,F,G,H,I,J,K,P,Q,S 112.6 135.0 A,B,C,L,M,N,O,R D,E,F,G,H,I,J,K,P,Q,S 135.1 157.5 A,B,C,L,M,N,O D,E,F,G,H,I,J,K,P,Q,R,S 157.6 180.0 A,B,C,L,M,N D,E,F,G,H,I,J,K,O,P,Q,R,S 180.1 202.5 A,B,C,L,M,N D,E,F,G,H,I,J,K,O,P,Q,R,S 202.6 225.0 A,B,C,D,L,M,N E,F,G,H,I,J,K,O,P,Q,R,S 225.1 247.5 A,B,C,D,L,M E,F,G,H,I,J,K,N,O,P,Q,R,S 247.6 270.0 A,B,C,D,L,M E,F,G,H,I,J,K,N,O,P,Q,R,S 270.1 292.5 A,B,C,D,L,M E,F,G,H,I,J,K,N,O,P,Q,R,S 292.6 315.0 A,B,C,D,L,M E,F,G,H,I,J,K,N,O,P,Q,R,S 315.1 337.5 B,C,D,L,M,R A,E,F,G,H,I,J,K,N,O,P,Q,S 337.6 360.0 B,C,D,L,M,R A,E,F,G,H,I,J,K,N,O,P,Q,S See Cautions 1 and 2 above.

4. IF notified by RP Dose Assessment that dose projections or field measurements indicate that Thyroid dose will be ? 5 Rem, KI use by the General Public must be recommended in accordance with State Plans and Policy. {PTP-G-03-606}

5. For any other Protective Action Recommendation, check E (Other) and record informtion.

Enclosure 4.4 RP/O/B/5700/029 Offsite Protective Action Recommendations Page 5 of 8

6. After the Initial PARS are transmitted to offsite agencies, check for large fission product inventory in containment as follows:

6.1 IF the OAC is available, call up the following computer points based on need:

Unit 1 OAC Unit 2 OAC M1A0829 M2A0829 M1A0835 M2A0835.

6.2 IF the OAC is unavailable, use the following EMFs:

Unit 1 Unit 2 IEMF51A 2EMF51A 1EMF51B 2EMF51B.

D 6.3 Check if containment radiation level exceeds the following limits based on time after shutdown:

TIME AFTER SHUTDOWN (hours) EMF5 I A(B) reading(R/HR)

>0-2 864

>2-4 624

>4-8 450

>8 265

Enclosure 4.4 RP/0/B/5 700/02 9 Offsite Protective Action Recommendations Page 6 of 8

7. IF containment radiation level exceeds limits in Step 6.3, perform the following:

El 7.1 Evacuate and shelter zones in the table below based on wind direction:

CAUTION: I. Once a zone is selected for evacuation, it should not be removed. {PIP-M-03-3483}

2. A short term release is any release that can be projected to be 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months or less in duration. An example would be a puff release. A controlled release is one that can be started and stopped at the licensees discretion, such as the venting of Containment for pressure control. a release is short term and controlled, THEN sheltering in lieu of evacuation should be considered. {PIP-M-05-363 1 }

Protective Action Zones Determination For Containment Radiation Levels Exceeding GAP Activity Wind Direction (deg from N)

Chart Recorder I EEBCR9 100 Point # 8 Average Upper Wind Evacuate* Shelter Direction 5 Mile Radius-lO Mile Downwind Remaining Sectors 0.1 22.5

- A,B,C,D,E,F,L,M,N,O,R,S G,H,I,J,K,P,Q 22.6 45.0 A,B,C,D,E,L,M,N,O,Q,R,S F,G,H,I,J,K,P 45.1 67.5 A,B,C,D,E,L,M,N,O,Q,R,S F,G,H,I,J,K,P 67.6 90.0 A,B,C,D,L,M,N,O,P,Q,R,S E,F,G,H,I,J,K 90.1 112.5 A,B,C,D,K,L,M,N,O,P,Q,R,S E,F,G,H,I,J 112.6 135.0 A,B,C,D,I,K,L,M,N,O,P,Q,R,S E,F,G,H,J 135.1 157.5 A,B,C,D,I,K,L,M,N,O,P,Q,R E,F,G,H,J,S 157.6 180.0 A,B,C,D,I,J,K,L,M,N,O,P,R E,F,G,H,Q,S 180.1 202.5 A,B,C,D,G,H,I,J,K,L,M,N,O,P,R E,F,Q,S 202.6 225.0 A,B,C,D,G,H,I,J,K,L,M,N,O,P,R E,F,Q,S 225.1 247.5 A,B,C,D,F,G,H,I,J,L,M,N,O,R E,K,P,Q,S 247.6 270.0 A,B,C,D,F,G,H,I,J,L,M,N,O,R E,K,P,Q,S 270.1 292.5 A,B,C,D,E,F,G,H,J,L,M,N,O,R I,K,P,Q,S 292.6 315.0 A,B,C,D,E,F,G,L,M,N,O,R H,I,J,K,P,Q,S 315.1 337.5 A,B,C,D,E,F,G,L,M,N,O,R H,I,J,K,P,Q,S 337.6 360.0 A,B,C,D,E,F,L,M,N,O,R,S G,H,I,J,K,P,Q See Cautions 1 and 2 above.

Enclosure 4.4 RP/O/B/5700/029 Offsite Protective Action Recommendations Page 7 of 8 U 8. A McGuire EPZ map is located on page 8 of 8, if it is desired to visually see zones evacuated or sheltered.

9. IF notified by RP Dose Assessment that dose projections or field measurements indicate that Thyroid dose will be? 5 Rem, KI use by the General Public must be recommended in accordance with State Plans and Policy. {PIP-G-03-606}

10. On a continuing basis, evaluate specific plant conditions including: large fission product inventory in containment, EMF 51 A/B readings, offsite dose projections, wind speed and wind direction, field monitoring team data, and assess the need to update Protective Action Recommendations made to the states and counties in the previous notification.

11. Review dose projections with the on-shift dose assessor (if available) to determine if Protective Action Recommendations are required beyond the 10-mile EPZ.

12. IF Protective Action Recommendations are required beyond 10 miles, notify the states and counties and request that they consider sheltering/evacuating the general populations located beyond the affected 10-mile EPZ.

Enclosure 4.4 RP/O/B/5700/029 Offsite Protective Action Recommendations Page 8 of 8 McGUIRE PROTECTWE ACTION ZONES (2 and 5 mile radius, inner circles) 10-MILE EPZ N

,00

FOR ADMIN JPM A4 SRO TRAINING USE ONLY ENF Handout NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM

1. DRILL ACTUAL EVENT MESSAGE# 1 2 9INITIAL FOLLOW-UP NOTIFICATION: TIME DATE AUTHENTICATION #

TE: McGuire Nuclear Site Confirmation Phone # (704) 875-6044

4. EMERGENCY EUNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY CLASSIFICATION:

BASED ON EAL# 4.1 .G.2 EAL DESCRIPTION: Loss of Any Two Fission Product Barriers and Potential Loss of the Third

5. PROTECTIVE ACTION RECOMMENDATIONS: ENONE

EVACUATE A, B, C, D, L, M, N, 0 and R SHELTER E, F, G, H, I, J, K, P, Q, and S J CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY. NA OTHEFNA

6. EMERGENCY RELEASE: ENone Is Occurring Has Occurred

7. RELEASE SIGNIFICANCE: ENOt applicable EWithin normal operating limits Above normal operating limits Under Evaluation

8. EVENT PROGNOSIS: lmproving EStable Degrading

9. METEOROLOGICAL DATA: Wind Direction* from 132.5 degrees Wind Speed* 4 mph

(* May not be available for Initial Precipitation* None Stability Class* EJ EJ EJ EJ EJ EEl EJ Notifications) 10.

[j DECLARATION [] TERMINATION Time EventStartTime Date Today / Today / Today 1 FECTED UNIT(S):

J III i:ii E nt Status:

(Unattected Unit(s) 5tatus Not Kequired tor Initial Eul 0 % Power Shutdown at: Time T minus 10 Date TODAY I TODAY I TODAY Notifications) EU2 100 % Power Shutdown at: Time Date I I U3 % Power Shutdown at: Time Date

13. REMARKS:

FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)

EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6A IS SELECTED.

14. RELEASE CHARACTERIZATION: TYPE: EElevated EMixed Ground UNITS:ECi CiIsec pCi/sec MAGNITUDE: Noble Gases: lodines: Particulates: Other:

FORM: EAirborne Start Time: Date: I / Stop Time Date I I Liquid Start Time: Date: I I Stop Time Date / I

15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date I I

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles 5 Miles 10 Miles

17. APPROVED BY

Title:

Emergency Coordinator Time: Time Date 1OiiY/TODAY / TODAY NOTIFIED BY: RECEIVED BY: Time: Date I I ADMIN JPM A4 SRO FOR TRAINING USE ONLY

ML102640745

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