Text

Initial Exam 2011-301 Draft Administrative JPMs
	ML111881135
Person / Time
Site:	Oconee
Issue date:	07/06/2011
From:	; NRC/RGN-II
To:	; Duke Energy Corp
References
	50-269/11-301, 50-270/11-301, 50-287/11-301
	Download: ML111881135 (175)
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ADMIN-115 Ri Page 1 of 11 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADM-115 CALCULATE AN ESTIMATED CRITICAL BORON CONCENTRATION CANDIDATE EXAMINER

ADMIN-115 Ri Page 2 of ii REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate an Estimated Critical Boron Concentration Alternate Path:

No Facility JPM #:

CRO-115 KIA Rating(s):

System: Generic KJA: 2.1.7 Rating: 4.4/4.7 Task Standard:

ECB calculation is performed and the resulting Boron concentration is within 10 ppmB of the key.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Classroom X Perform X Simulate

References:

PT/i /Al1 103/15, Reactivity Balance Procedure Validation Time: 15 minutes Time Critical: NO Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time:

Examiner: /

NAME SIGNATURE DATE COMMENTS

ADMIN-115 Ri Page 3 of ii SIMULATOR OPERATOR INSTRUCTIONS None

ADMIN-115 Ri Page 4 of ii Tools/Equipment/Procedures Needed:

PT/I /A/i 103/015, Reactivity Balance Procedure Computer with Reactivity Balance Program Loaded READ TO OPERATOR DIRECTION TO TRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 1 DATE: 1/04/11 Reactor Power = 100% for past week 1500: Power reduction to 65% at 5%/mm due to lB MFDWP problems 2101: Reactor Trip occurs CURRENT CONDITIONS DATE: 1/05/11, 0300 Unit 1 Reactor startup in progress

Beginning of Power History 150 EFPD

RCS Temperature = 534°F

Desired critical rod position = Group 6 @ 50% withdrawn

Group 8 = 35 % withdrawn

Boron Concentration = 1350 PPM INITIATING CUES The Control Room SRO directs you to perform the initial/original computerized Estimated Critical Boron Concentration calculation for startup one-hour from present time (0400) per PT/i/A/i 103/015, Reactivity Balance Procedure.

ADMIN-115 RI Page 5 of ii START TIME:

STEP 1: Candidate obtains a copy of PT/i/All 103/15, Reactivity Balance Procedure (Unit 1), Enclosure 13.5 (Computerized ECB Calculation).

SAT STANDARD: Candidate locates End. 13.5 in the provided copy of PT/1/A11103/15, Reactivity Balance Procedure (Unit 1).

UNSAT COMMENTS:

STEP 2: Step 2.1 This Enclosure must be performed twice the second is the separate verification. Circle whether this is the original or the verification: SAT STANDARD: Candidate should circle original.

COMMENTS: UNSAT STEP 3: Step 2.2 IF returning from a forced shutdown, SAT

Obtain the power history back to the last time of Xenon Equilibrium to perform the Xenon calculation from a source such as P1 server, OAC Log, RO Log, etc.

Attach actual power history to this enclosure UNSAT STANDARD: Candidate will obtain the power history from the information on the cue sheet.

Cue: Inform candidate that the cue sheet will serve as the power history printout COMMENTS:

ADMIN-115 Ri Page 6 of ii STEP 5: Step 2.3 Open RhoCalc SAT STANDARD: Candidate locates the RhoCalc icon on the Control Room PC and opens the program.

UNSAT Note: For exam security purposes, RhoCalc is being run from a CD and is therefore already open on the desktop and ready for use.

Cue: If the candidate asks, provide a hard copy of the Help File for ECB.

Cue: Inform the candidate that the RhoCaic program has been launched.

COMMENTS:

STEP 6: Step 2.4 Input appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print: SAT

Enter your name STANDARD: Candidate enters name in blank shown UNSAT COMMENTS:

STEP 7: Step 2.4 (cont.) CRITICAL STEP Input appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print: SAT

SelectUnit 1 STANDARD: Candidate uses pushbuttons on left of screen to select Unit 1.

UNSAT Cue: Inform candidate to ignore Error connecting to P1 server message.

COMMENTS:

ADMIN-115 Ri Page 7 of 11 STEP 8: Step 2.4 (cont.) CRITICAL STEP Input appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print:

SAT

Select ECB STANDARD: Candidate selects ECB under the Desired Calculation located in the middle of the screen UNSAT COMMENTS:

STEP 9: Step 2.4 (cont.) CRITICAL STEP Input appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print: SAT

Enter Shutdown Margin Conditions STANDARD: Candidate enters the following based in the given initial conditions:

UNSAT

RCSTemp534°F

Beginning of Power History = 150

Group5=100%

Group65O%

Group70%

Group8=35%

COMMENTS:

ADMIN-115 Ri Page 8 of 11 STEP 10: Step 2.4 (cont.)

Input appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print: SAT

Enter Fuel Condition Status

Enter # of RCPs in Operation UNSAT

Enter # of Inoperable Rods STANDARD: In the bottom right corner of the screen, the Candidate enters the following:

Fully Conditioned fuel

4 RCPs

0 Inoperable Rods Note: This section can be left blank when performing the ECB Note: The candidate may ask for a copy of PTIOIAIIIO3IO2O.

COMMENTS:

STEP 11: Step 2.4 (cont.) CRITICAL STEP Input appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print: SAT Select the Power History tab from the menu along the top of the page UNSAT STANDARD: The Power History Button is pressed.

COMMENTS:

ADMIN-115 Ri Page 9 of ii STEP 12: Step 2.4 (cont.) CRITICAL STEP Input appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print: SAT Enter the power history UNSAT STANDARD: Power history is entered per attached.

COMMENTS:

STEP 13: Step 2.4 (cont.) CRITICAL STEP In put appropriate data for the estimated critical boron calculation, Select Calculate ECB, and print: SAT

Select Calculations

Calculate the ECB UNSAT STANDARD: The Calculations button on the top menu is selected and then the Calculate ECB button is depressed.

The resulting ECB calculation should show an ECB of 790 ppmB at 0400; Range=+/-10 ppm (780800 ppm)

COMMENTS:

END OF TASK STOP TIME:

ADMIN-115 Ri Page 10 of 11 CRITICAL STEP EXPLANATIONS STEP # Explanation 7 Necessary to produce an accurate ECB.

8 Necessary to produce an accurate ECB.

9 Necessary to produce an accurate ECB.

11 Necessary to produce an accurate ECB.

12 Necessary to produce an accurate ECB.

13 Necessary to produce an accurate ECB.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 DATE: 1/04/11 Reactor Power = 100% for past week 1500: Power reduction to 65% at 5%/mm due to 1 B MFDWP problems 2101: Reactor Trip occurs CURRENT CONDITIONS DATE: 1/05/11, 0300 Unit 1 Reactor startup in progress

Cycle burn up = 150 EFPD

RCS Temperature = 534°F

Desired critical rod position = Group 6 @ 50% withdrawn

Group 8 = 35 % withdrawn

Boron Concentration = 1350 PPM INITIATING CUES The Control Room SRO directs you to perform the initial/original computerized Estimated Critical Boron Concentration calculation for startup one-hour from present time (0400) per PT/i/All 103/15, Reactivity Balance Procedure.

Re Clear Xenon History NI Response Limitatons PIN Data Help Input InFormation BIt Feed olume J Power flistory Calculations I Power Maneuver I I I For shutdown margins, an X must be placed in the

<at Selected Times I

I Date 1/4/2011 I

I Time 15:00 I

I I

Power 100 I

I XetSm Worth

-1578 1

First column For the desired shutdown margin time 1/4/2011 15:07 65 -1588 perio& 1/412011 16:00 65 -1712 1/412011 17:00 65 -1809 1/4/2011 18:00 65 -187 114/2011 19:00 65 -2.904 1/4/2011 20:00 85 -2.916 114/2011 21:00 65 -1913 114/2011 21:01 0 -1916 1/4/2011 22:00 0 -1218 1/4/2011 23:00 0 -3.452 1/5/2011 00:00 0 -3.623 1/5/2011 01:00 0 74 1/5/2011 02:00 0 -1811 1/5/2011 03:00 0 -3.844 1/5/2011 04:00 0 -1844 1/5/2011 05:00 1/5/2011 08:00 1/5/2011 07:00 115/2011 (twill Print Xenon jtflLjJ jail e > -, Inbox Microsof,.

jJ 301-1 SRO Out,.

f 3O1-1 O Outi.., kj Admin-115.doc

Directions for completing an Estimated Critical Boron Calculation Enter the following information:

Your name

Todays date. Must be a valid date.

Current Time (that you perform this calculation). Must be a valid time.

Select Appropriate Unit.

Select the appropriate Desired Calculation radio button. The required data will be highlighted.

RCS Temperature at time of criticality. Must be 525-560 °F.

Core Effective Full Power days (EFPD) at start of power history. Must be 0 -600 EFPD. Note that a value significantly beyond core life will cause an error in the XenonlSamarium calculation.

Desired CRD Groups 5-8 positions at time of criticality.

Enter Power History

Select the Power History tab.

When one date is entered, all dates fill in.

When one time is entered, all times fill in on a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months frequency. Intermediate times may be inserted by typing the desired time on top of the time it is to go before (for example, type 3:30 on top of 4:00 to insert it). Once a time is in, you cant delete it.

Power will automatically fill empty cells up it will interpolate if another different power is somewhere above it. Use this feature so you dont have to type 0 or 100 repeatedly. The power history only has to be entered as far down as is required to get to the selected time. The time will be at equilibrium Xenon, so ensure power history starts at last known equilibrium point.

The Clear Xenon history pull down menu may be used to erase all historical power data or clear data from the current cursor position down.

Run ECB calculation and print if desired.

Select the Calculation tab and press the Calculate ECB button.

The Return to Input Screen button will return you to the Input Information tab, and Print Output can be used to make a hard copy of the ECB.

The program will automatically calculate an ECB for each 0% FP time.

Duke Energy Procedure No.

Oconee Nuclear Station PT/l/A/1103/015 REACTIVITY BALANCE PROCEDURE (Unit 1) Revision No.

067 Electronic Reference No.

OXOO2WBQ Continuous Use PERFORMANCE I UNCONTROLLED FORPRINT * * * * * * * * * *

(ISSUED) PDF Format

PT/i/A/i 103/015 Page 2 of 8 Reactivity Balance Procedure

1. Purpose 1.1 To calculate the Boron concentration necessary to provide greater than 1% AK/K shutdown margin.

1.2 To calculate the actual shutdown margin when the reactor is shutdown.

1.3 To evaluate the available shutdown margin during power operation (e.g., in the event of an inoperable rod.)

1.4 To provide the minimum RCS Boron concentration required to ensure greater than 1%

AK/K shutdown margin to perform the Control Rod Drive (CRD) patch verification (for initial startup following refueling).

1.5 To estimate the critical rod configuration or the critical Boron concentration prior to startup.

1.6 To provide a method for preventing inadvertent criticality using subcritical multiplication measurement.

1.7 To provide nominal APSR position.

1.8 To provide the Minimum RCS Boron Concentration to maintain SSF Operability

2. References 2.1 Technical Specifications: 1.1, Definitions - Shutdown Margin 3.1.1, Shutdown Margin 3.1.4, Control Rod Group Aligment Limits 3.1.5, Safety Rod Position Limits 3.2.1, Regulating Rod Position Limits 3.3.9, Source Range Neutron Flux 3.9.1, Boron Concentration 2.2 Selected Licensee Commitments: 16.13.4, Reactivity Anomaly 2.3 Unit 1 - Physics Test Manual (PTM), ONEI-0400-55 2.4 Unit 1 - Core Operating Limits Report (COLR), ONEI-0400-50

PT/i/All 103/015 Page 3 of 8 2.5 Nuclear Systems Directive 304, Reactivity Management 2.6 Work Process Manual, Section 2.5, Testing

3. Time Required Two people - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for most enclosures

4. Prerequisite Tests None

5. Test Equipment Personal computer (for computerized calculations)

6. Limits and Precautions 6.1 The results of this procedure are used to make important operational decisions, therefore this procedure affects core reactivity. (R.M.)

6.2 Appropriate corrections have been made per this procedure, or actual plant conditions must be the same as the reference conditions stated on the appropriate enclosure(s).

(R.M.)

6.3 Separate verification is required for each calculation perfonned. For hand calculations, this requires that two people separately complete the appropriate enclosures for the desired calculation to verify the results are in agreement. For computerized calculations, this requires that two people separately run the computer code(s) or verify the input.

(R.M.)

6.4 JJ the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result. (R.M.)

6.5 Per Technical Specification 3.1.5 all safety rods (groups 1-4) must be fully withdrawn prior to MODE 2 entry (Keff> 0.99, SDM < 1% AKIK). (R.M.)

7. Required Unit Status None

8. Prerequisite System Conditions None

PT/i/A/i 103/0 15 Page 4 of 8

9. Test Method 9.1 Shutdown Boron Concentration:

Calculated in Enclosure 13.1, Shutdown Boron Concentration/Shutdown Margin Calculation, or 13.2, Computerized Shutdown Margin Calculation.

The shutdown Boron concentration provides a greater than 1.0% AIKJK shutdown margin with the worst case stuck rod assumed to be out.

A reference shutdown Boron concentration is obtained based on the cycle bumup, rod positions and RCS temperature. The reactivity worths of Xenon, Samarium, and the inoperable rod penalty (if applicable) are converted into their equivalent Boron concentrations. (Credit is taken only for the minimum Xenon worth occurring in a specified time interval, which should not exceed 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months . The Shutdown Boron concentration is valid Qfljy during that time interval. Due to uncertanities in the Xenon models, 0.8 times the Xenon and Samarium worth are used unless the RCS is below 450°F, in which case 0.5 times the Xenon and Samarium worths are used. Xenon and Samarium worths may be assumed to be zero for conservatism.) These Boron concentrations are then applied to the reference Boron concentration to provide the required Boron concentration for a greater than 1.0% AK/K shutdown margin (i.e., the shutdown Boron concentration).

9.2 Shutdown Margin Calculation while Shutdown:

Calculated in Enclosure 13.1, Shutdown Boron Concentration/Shutdown Margin Calculation or 13.2, Computerized Shutdown Margin Calculation.

The shutdown margin is the amount of reactivity by which the reactor is shutdown. The worst case stuck rod is assumed to be out. If operating with a known inoperable rod, an additional penalty is applied to account for that rod. This penalty need not be applied when the reactor is shutdown if that rod can be confinned to be fully inserted by redundant indications. The shutdown Boron concentration must first be found per step 9.1. The actual Boron concentration is then subtracted from this concentration and the result converted to % AK/K. 1.0% AK/K is then subtracted from this value to obtain the shutdown margin, expressed in % AK/K. A separate check for SSF RC Makeup System operability is performed, which takes credit for Xenon and requires the stuck rod penalty.

This limit is shown in Enclosure 13.20, Minimum RCS Boron Concentration to Maintain SSF Operability.

PT/i/A/i 103/015 Page 5 of 8 Following a shutdown, Control Rod Position at the time of Shutdown may be used with the Rod Position Limit curves (in COLR) to verify at least 1% z\K/K shutdown margin for the first 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months following shutdown (provided RCS Temperature stays?: 532°F and boron does not decrease). This may be necessary for shutdowns with an inoperable rod, since the more conservative calculation method (in Enclosure 13.1, Shutdown Boron ConcentrationlShutdown Margin Calculation, and 13.2, Computerized Shutdown Margin Calculation) may not show 1% KJK shutdown margin immediately after shutdown.

Boration should begin immediately to be able to show 1% t\KIK shutdown margin using the calculation method.

9.3 Shutdown Margin at Power:

Verified in Enclosure 13.18, Shutdown Margin Calculation at Power.

While at power, the available shutdown margin may be verified to be? 1% AKIK by using the Rod Position Limits curves (in COLR). Operation in the Acceptable Region of these curves ensures that the shutdown margin following a reactor trip will be? 1%

AKJK with the worst stuck rod out. There are curves for 3 and 4 RCP operation, and curves for 0 and 1 inoperable rod. A dropped rod is considered inoperable for the purposes of providing shutdown margin while at power.

9.4 Estimated Critical Rod Position:

Calculated in Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation.

The core excess reactivity is obtained based on the cycle bumup. The reactivity worths associated with Boron, Xenon, temperature correction (if RCS temperature not at 532°F) and Samarium are then obtained and summed with the core excess reactivity. The groups 5-7 positions are then determined for which the inserted rod worth when summed with all the above, yields a total core reactivity of 0.0% AKIK. The upper and lower rod position limits are then detennined and the actual critical rod positions are recorded.

9.5 Estimated Critical Boron Concentration:

Calculated in Enclosure 13.5, Computerized Estimated Critical Boron Calculation.

The core excess reactivity is obtained based on the cycle bumup. The reactivity worth associated with Xenon, temperature correction (if RCS temperature not at 532°F),

Samarium and the desired critical rod positions are summed with the core excess reactivity. The Boron concentration is then determined for which its reactivity worth, when summed with all the above, yields a total core reactivity of 0.0% AK/K.

PT/i/A/i 103/0 15 Page 6 of 8 9.6 Subcritical Multiplication Measurement:

Perfonned in 13.6, Computerized Subcritical Multiplication (1/M) Measurement.

With Group 1 at 50% wd, an initial source range (SR) count rate (C ) is recorded. During 0

control rod withdrawals, new counts (C) are recorded and used to calculate 1/M, or CO/C.

As criticality is approached, C/CO will approach infinity, and 1/M will approach zero.

Plotting 1/M versus rod worth provides a rough indication of what rod position will yield a critical condition, and acts as an indication of premature criticality, or criticality more than 0.75% AK/K below the Estimated Critical Position calculated in step 9.4.

10. Data Required 10.1 For Xenon Worth: Core EFPD and power history to time of last equilibrium xenon.

10.2 For Shutdown Boron Concentration/Shutdown Margin Calculation: Power History, Boron Concentration, RCS temperature, Core EFPD, Group 8 position, any inoperable rod penalty.

10.3 For Estimated Critical Rod Configuration: Boron Concentration, RCS temperature, Core EFPD, Group 8 Position, and power history.

10.4 For Estimated Critical Boron Configuration: RCS temperature, Core EFPD, desired critical rod configuration and power history.

10.5 For Subcritical Multiplication Measurement: ECP Control Rod position, time safety groups must be fully withdrawn, Unit, Cycle, Beginning of Cycle (Yes/No), EFPD, Graph Notify Lines (Yes/No). Xenon Free (Yes/No), and source range (SR) count rate.

11. Acceptance Criteria 11.1 Separate verifications for Shutdown Boron shall agree within 10 ppmB. The more conservative Shutdown Boron Concentration calculation shall be used to ensure at least a 1.0% AKIK shutdown margin.

11.2 Separate verifications for Estimated Critical Boron shall agree within 10 ppm.

11.3 Separate verifications for Estimated Critical Positions shall agree within 5% wd.

11.4 Acceptance criteria for 1/M approach to critical: Criticality is achieved within 0.75% Ak/k of the predicted critical rod position concentration.

11.5 Review criteria for 1/M approach to critical: Criticality achieved within 0.35%Ak/k of the predicted critical rod position for startups considered Xenon free, 0.5% AkIk review criteria for non-Xenon free startups.

PT/i/A/i 103/0 15 Page 7 of 8

12. Procedure Complete, or refer to, the appropriate enclosure(s):

Shutdown Margin Calculation while shutdown:

Enclosure 13.1, Shutdown Boron ConcentrationlShutdown Margin Calculation, or Enclosure 13.2 Computerized Shutdown Margin Calculation Estimated Critical Rod Position:

Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation Estimated Critical Boron Concentration:

Enclosure 13.5, Computerized Estimated Critical Boron Calculation Computerized Subcritical Multiplication (i/M) Measurement:

Enclosure 13.6, Computerized Subcritical Multiplication (1/M) Measurement Refueling Outage Boron Concentrations:

Enclosure 13.13, Refueling Outage Boron Concentrations Required Control Rod Group 8 Position:

Enclosure 13.14, Required Group 8 Position and Designed Cycle Length Designed Cycle Length Information:

Enclosure 13.14, Required Group 8 Position and Designed Cycle Length Required Shutdown Margin:

Enclosure 13.16, Shutdown Margin Requirements Shutdown Margin Calculation at power:

Enclosure 13.18, Shutdown Margin Calculation at Power RCS Boron Concentration for SSF Operability:

Enclosure 13.20, Minimum RCS Boron Concentration to Maintain SSF Operability

PT/i/A/i 103/0 15 Page 8 of 8 NOTE: Only the appropriate completed enclosures need be attached to the procedure cover sheet to be submitted for procedure completion.

13. Enclosures 13.1 Shutdown Boron Concentration/Shutdown Margin Calculation 13.2 Computerized Shutdown Margin Calculation 13.3 Computerized Shutdown Margin Calculation Documentation 13.4 Computerized Estimated Critical Rod Position Calculation 13.5 Computerized Estimated Critical Boron Calculation 13.6 Computerized Subcritical Multiplication (1/M) Measurement 13.7 Core Excess Reactivity vs. Bumup 13.8 Differential Boron Worth vs. Burnup 13.9 Temperature Coefficient vs. RCS Boron Concentration 13.10 Shutdown Boron Concentration vs. Bumup (Group 1 @ 0% wd) 13.11 Shutdown Boron Concentration vs. Burnup (Group 1 @ 50% wd) 13.12 Inoperable Rod Penalty for Individual Inoperable Rod 13.13 Refueling Outage Boron Concentrations 13.14 Required Group 8 Position and Designed Cycle Length 13.15 Power Defect vs. Reactor Power 13.16 Shutdown Margin Requirements 13.17 Control Rod Group Worths for Control Rod Drop Time Testing 13.18 Shutdown Margin Calculation at Power 13.19 Group 7 Control Rod Worth 13.20 Minimum RCS Boron Concentration to Maintain SSF Operability

Enclosure 13.1 PT/i/A/I 103/015 Shutdown Boron Concentration/Shutdown Page 1 of 5 Margin Calculation Calculation Performed By:_________________ Date: Time:________________

NOTE: This enclosure assumes the SDM computer code is unavailable.

1. Purpose The purpose of this enclosure is to manually calculate a shutdown margin.

2. Procedure 2.1 This enclosure must be perfonned twice the second is the separate verification. Circle whether this is the original or the verification:

Original May be performed by anyone trained on this procedure Separate Verification Must be Licensed Operator or a Qualified Reactor Engineer (N/A steps 2.10-2.13 for Separate Verification.)

2.2 Enter the conditions for which this calculation is effective:

Core Burnup: EFPD RCS Temperature °F CRD Grpl Posn: %w/d CRD Grp8 Posn: %w/d NOTE: The Xe/Sin time interval is normally 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . However, any time interval may be used.

This time interval is only required if credit is to be taken for XenonlSamariurn.

XenonlSarnarium time interval valid from date/time:_________________________ to date/time:_________________________

2.3 Obtain reference Shutdown Boron Concentration for the effective Bumup and RCS Temp of this calculation (2.2) from one of the following:

Enclosure 13.10, Shutdown Boron Concentration vs. Burnup (Group 1 @ 0% wd) if CRD Groups 1-7 are at 0%w/d Enclosure 13.11, Shutdown Boron Concentration vs. Bumup (Group 1 @ 50% wd) if CRD Grpl is at 50% and Grp2-7 are at 0%w/d L positive J

Enclosure 13.1 PT/i/A/i 103/0 15 Shutdown Boron Concentration/Shutdown Page 2 of 5 Margin Calculation 2.4 Adjust for non-reference conditions as follows:

2.4.1 IF available, independently obtain Xenon + Samarium worth from the QAC or PT. Use the minimum Xenon + Samarium worth which occurs at or between the time interval specified in 2.2 above.

LE desired zero may be used for conservatism.

IF the RCS temperature is at or above 450°, multiply by 0.8.

IF the RCS temperature is less than 450°F multiply by 0.5:

x I negative Xe+Srn Wrth 0.8 or 0.5 L negative 2.4.2 IF credit is taken for Xenon worth in 2.4.1, initial and attach the Xenon computer printout AND actual power history (from OAC log, TMS, PT, etc.)

to this enclosure.

2.4.3 j[ shutdown with a stuck rod (see step 9.2) obtain Inoperable Rod Penalty from Enclosure 13.12, Inoperable Rod Penalty for Individual Inoperable Rod:

Inoperable Rod Group#: Rod#: fl%J positive 2.4.4 IF this calculation is for CRDTTT, obtain the Control Rod Worth for the highest worth group to be tested for the applicable conditions from Enclosure 13.17, Control Rod Group Worths for Control Rod Drop Time Testing:

Rod Group#

sitive 9

2.4.5 2.4.6 Sum 2.4.1 + 2.4.3 +/- 2.4.4 L neg or pos Obtain boron concentration adjustment by dividing 2.4.5 by Differential I

Boron Worth from Enclosure 13.8, Differential Boron Worth vs. Burnup:

neg or pos step 2.4.5

/

negative End 13.8 [ neg or pos I

Enclosure 13.1 PT/1/A/1103/015 Shutdown Boron Concentration/Shutdown Page 3 of 5 Margin Calculation 2.4.7 IF Group 8 is NOT 30 40 %wd, AND bumup <APSR pull window (or No APSR pull this cycle) noted in Enclosure 13.14, Required Group 8 Position and Designed Cycle Length, subtract 50 ppmB from 2.4.6:

negorpos

- 50 ppmB = I negorpos 2.5 Determine required shutdown boron concentration as follows:

CAUTION: IF steps 2.4.6 OR 2.4.7 are negative values, THEN a negative number will be subtracted.

2.5.1 Subtract 2.4.7 (IF 2.4.7 applicable) OR 2.4.6 (IF 2.4.7 NOT applicable) from 2.3 to obtain the required Boron concentration for 1%Ak/k shutdown margin (assumes worst rod stuck out):

step 2.3 steps 2.4.7 or 2.4.6 Lpos or zero 2.5.2 Obtain minimum RCS Boron Concentration for SSF operability from Enclosure 13.20, Minimum RCS Boron Concentration to Maintain SSF Operability, using the Minimum Xenon from the effective time period:

Minimum RCS Boron for SSF operability =

pprnBl 2.5.3 Determine the minimum RCS Boron Concentration by recording the GREATER of step 2.5.1 and 2.5.2:

Minimum RCS Shutdown Boron Concentration pprnB 2.6 IF desired, calculate actual shutdown margin as follows:

2.6.1 Record actual RCS conditions:

RCS Boron Concentration: ppmB RCS Temperature 2.6.2 Subtract the required Boron concentration in 2.5.1 from the actual Boron concentration in 2.6.1, the result should be positive unless a 1%Aklk shutdown margin has NOT been established:

- =

step2.6.1 step2.5.1 Lshouldbepos

Enclosure 13.1 PT/1/A/11o3/o15 Shutdown Boron Concentration/Shutdown Page 4 of 5 Margin Calculation 2.6.3 Calculate the actual shutdown margin by multiplying 2.6.2 times the Differential Boron Worth from Enclosure 13.8, Differential Boron Worth vs.

Bumup and subtracting 1 %AkJk:

x - 1 %k/k step 2.6.2 negative should be neg End 13.8 2.7 Verify Separate Verification agrees within 10 ppmB of the Original on Step 2.5.3.

(R.M.)

2.8 IF this calculation is being used to verify shutdown margin for present reactor conditions, perform the following:

2.8.1 Verify that the shutdown margin (Step 2.6.3) is greater than 1%AKJK (i.e.

more negative than -1 .0%tK/K) (R.M.)

OR 2.8.2 Perfonn the following:

A. Notify Control Room SRO immediately.

B. IF within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of shut down, verify Shutdown Margin using COLR curve (verification method in step 9.2). (R.M.)

C. Initiate boration to establish adequate Shutdown Margin. (R.M.)

ops AND 2.8.3 Ensure the present boron concentration is greater than the boron concentration in 2.5.3.

2.9 IF this calculation is being used to project shutdown margin for future conditions, inform the Control Room SRO that the required boron concentration to ensure a greater than 1 %M<JK shutdown margin for the above reference conditions must be greater than the concentration in Step 2.5.3. (R.M.)

2.10 Discuss the results of the shutdown margin calculation with the Control Room SRO.

(N/A this step on separate verification calculation).

Control Room SRO 2.11 Attach the results of the shutdown margin calculations to a procedure cover sheet and turn the package over to the Control Room SRO. (N/A this step on the separate verification calculation.)

Enclosure 13.1 PT/i/A/i 103/015 Shutdown Boron Concentration/Shutdown Page 5 of 5 Margin Calculation 2.12 IF desired, place a copy of the shutdown margin in the Current Unit Shutdown Margins folder located in the Reactor Engineering procedure cabinet. (N/A this step on the separate verification calculation.)

NOTE: The Reactor Engineering mail code is ONO3CV.

2.13 WHEN the shutdown margin calculation is no longer required, return this procedure, including all applicable enclosures and attachments, to Reactor Engineering for procedure completion and review. (N/A this step on the separate verification calculation.)

Enclosure 13.2 PT/i/A/i 103/015 Computerized Shutdown Margin Calculation Page 1 of 2

1. Purpose The purpose of this enclosure is to calculate a shutdown margin using a Rho Caic.

2. Procedure Calculation Perfonried by:_____________________

2.1 This enclosure must be performed twice the second is the separate verification. Circle whether this is the original or the verification:

Original May be performed by anyone trained on this procedure Separate Verification Must be a Licensed Operator or a Qualified Reactor Engineer (N/A steps 2.7-2.10 for Separate Verification)

CAUTION: 1. IF the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result.

2. Xenon credit is required the EFPD input into the code SHALL correspond to the beginning of the power history, NOT the EFPD at the effective time of calculation.

3. The RhoCalc code uses the EFPD that is input to the code to lookup the shutdown boron concentration. Therefore, the EFPD used for shutdown margin when taking credit for Xenon may be less than the current burnup.

2.2 IF credit for Xenon is taken:

2.2.1 Obtain the power history back to the last time of Xenon Equilibrium to perform the Xenon calculation from a source such as PT server, OAC Log, RO Log, etc.

2.2.2 Attach actual power history (from OAC log, TMS, PT Server, etc.) to this enclosure.

2.3 Open RhoCalc.

NOTE: IF a printer is not available, Enclosure 13.3, Computerized Shutdown Margin Calculation Documentation, may be used to document this calculation.

2.4 Input appropriate data for the shutdown margin calculation, select Calculate SDM and print.

2.5 Verify that the final required RCS boron concentrations on Separate Verifications agree within 10 ppmB.

Enclosure 13.2 PT/1/A/11o3/o15 Computerized Shutdown Margin Calculation Page 2 of 2 2.6 IF calculation is being used to verify shutdown margin for present conditions, perform one of the following:

2.6.1 Verify that the shutdown margin is more negative than -1.00 %AkJk. (R.M.)

OR 2.6.2 Perform the Following:

A. Notify Control Room SRO immediately.

B. IF within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of shut down, verify Shutdown Margin using COLR curve (verification method in step 9.2). (R.M.)

C. Initiate boration to establish adequate SDM (R.M.)

ops 2.7 Discuss the results of the shutdown margin calculation with the Control Room SRO.

(N/A this step on separate verification calculation).

Room SRO 2.8 Attach results of shutdown margin calculation to the procedure and turn the package over to the Control Room SRO. (N/A this step on separate verification calculation).

2.9 IF desired, place a copy of the shutdown margin in the Current Unit Shutdown Margins folder located in the Reactor Engineering procedure cabinet. (N/A this step on the separate verification calculation.)

NOTE: The Reactor Engineering mail code is ONO3CV.

2.10 WHEN the shutdown margin calculation is no longer required, return this procedure, including all applicable enclosures and attachments, to Reactor Engineering for procedure completion and review. (N/A this step on the separate verification calculation.)

Enclosure 13.3 PT/1/A/11o3/o15 Computerized Shutdown Margin Calculation Page 1 of 1 Documentation

1. Purpose The purpose of this enclosure is to document the shutdown margin calculated in Enclosure 13.2, Computerized Shutdown Margin Calculation, when a printer is not available.

2. Procedure 2.1 After performing steps 2.1 through 2.4 of Enclosure 13.2, Computerized Shutdown Margin Calculation, copy the following infonnation off of the computer screen:

Performed By: Date/Time Calculation is Effective For:

Burnup EFPD RCS Temperature deg F Group 8 % wd Present Boron Concentration ppmB Xe/Sin Credit Calculation Good From: Date/Time To: Date/Time DBW % delta-k/k/pprnB Reference Shutdown Boron Concentration ppmB Xe+Sm Worth % delta-k/k Rod Penalty % delta-k/k Grp 8 Position Penalty Adjustment______ ppmB Rod Group Rod Number Xe/SrnlRod-Grp Out/Group 8 Boron Adjustment pprnB Boron Concentration Required for 1%k!k Shutdown ppmB Minimum RCS Boron Concentration required for SSF Operability ppmB Minimum RCS Boron Concentration pprnB Shutdown Margin at Present Conditions % delta-k/k RCS Temperature Group 1 at 0%wd Group 1 at 50%wd 60 200 300 400 449 450 500 532 Independent Verification:

Enclosure 13.4 PT/i/A/I 103/015 Computerized Estimated Critical Rod Position Page 1 of 4 Calculation

1. Purpose The purpose of this enclosure is to calculate an estimated critical rod position to be used during unit start up.

2. Procedure Calculation Performed by:_____________________

2.1 This enclosure must be performed twice the second is the separate verification. Circle whether this is the original or the verification:

Original Must be performed by a Licensed Operator (N/A next bullet step)

Separate Verification Must be performed by a Qualified Reactor Engineer (N/A steps 2.8-2.13 for Separate Verification)

NOTE: The only acceptance criterion is that measured RCS % design flow is greater than that required. RPS flows can be expected to deviate from baseline.

IF returning from a forced outage perform an RCS flow check using POWCALC.XLS AND attach results to this enclosure.

CAUTION: IF the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result.

NOTE: IF conducting an initial cycle startup the power history is 0% F. P.

2.2 IF returning from a forced shutdown:

2.2.1 Obtain the power history back to the last time of Xenon Equilibrium to perforni the Xenon calculation from a source such as P1 server, OAC Log, RO Log, etc.

2.2.2 Attach actual power history (from OAC log, TMS, P1 Server, etc.) to this enclosure.

2.3 Open RhoCalc.

Enclosure 13.4 PT/i/A/i 103/015 Computerized Estimated Critical Rod Position Page 2 of 4 Calculation NOTE: 1. EFPD input into the code shall correspond to the beginning of the power history, NOT the EFPD at the effective time of calculation.

2. When choosing the input Boron concentration during transient Xenon conditions sufficient time must be factored in to allow for changes to be made to the RCS and PZR Boron concentration, samples to be taken, the time required to pull Groups 1 4 -

to 100% wd, and any other time constraints noted by the 0CC.

3. The ECP time shall run sufficiently into the future to detennine if MODE 2 entry could occur with Group 5 <0%. This time of occurrence is required in step 2.7

4. Estimated conditions (i.e. RCS Boron/Temperature) at the time of criticality may be used.

2.4 Input appropriate data for the estimated critical rod position calculation, select Calculate ECP, and print.

2.5 Circle the appropriate response:

Were estimated conditions used for the ECP? Yes/No 2.6 Verify Separate Verifications agree on the ECP within 5%wd for all future time steps that have an ECP prediction.

Enclosure 13.4 PT/1/A/11o3/o15 Computerized Estimated Critical Rod Position Page 3 of 4 Calculation CAUTION: 1. All safety Rods (Groups 1-4) must be fully withdrawn prior to the time that Rod Posn @ Mode 2 Entry (T.S. 3.1.5) column reaches Group 5 <0%. T. S. 3.L5 prohibits entering Mode 2 (Keff> 0.99, SDM <1% dKJK) on the Safeties. jj Groups 1 4 can NOT be fully withdrawn prior to the Rod Posn Mode 2 Entry (T.S. 3.1.5) column indicating 5 <0%, any in-progress approach to critical must be aborted AND the RCS borated sufficiently to meet T.S. 3.1.5 requirements.

2. IF the RCS is sufficiently borated to account for Xe decay to Xe free conditions, Step 2.7.2 may be N/Aed because the T.S. 3.1.5 limit will NOT be reached AND Mode 2 (Keff> 0.99, SDM <1% dK!K) will NOT be entered on the Safeties.

2.7 Complete one of the following steps:

2.7.1 Verify that the RCS is sufficiently borated to account for Xe decay such that entry into T.S. 3.1.5 will NOT occur.

OR 2.7.2 Document the time/date of the time step immediately prior to the first occurrence of5 <0% in the Rod Posn Mode 2 Entry (T.S. 3.1.5) column of the ECP printout.

Time at which the safety rods must be fully withdrawn:

hours on 2.8 Discuss the results of ECP with the Control Room SRO. (N/A this step on separate verification calculation).

Room SRO 2.9 Attach results of ECP to the procedure and turn the package over to the Control Room SRO. (N/A this step on separate verification calculation).

2.10 Fill in the actual critical rod configuration and notification limit check on the computer printout. (N/A this step on separate verification calculation).

NOTE: The notification lines of 1/M.xls spreadsheet are the review and acceptance criteria of 1 1.4 and 1 1.5. IF these criteria are NOT met see the WPM section 2.5, Testing, Approach to Critical Rod Position.

2.11 Verify actual critical conditions are within 1/M.xls notification lines. (N/A this step on separate verification calculation.)

Enclosure 13.4 PT/i/A/i 103/0 15 Computerized Estimated Critical Rod Position Page 4 of 4 Calculation NOTE: The Reactor Engineering mail code is ONO3CV.

2.12 Forward the completed ECP, including all applicable enclosures and attachments, to Reactor Engineering. (N/A this step on the separate verification calculation.)

NOTE: The GO Nuclear Design Group requires the Procedure Completion Approved blank to be signed off prior to transmittal.

2.13 Transmit copy of completed ECP to GO Nuclear Design. (N/A this step on separate verification calculation.)

Enclosure 13.5 PT/1/A/11o3/o15 Computerized Estimated Critical Boron Page 1 of 2 Calculation

1. Purpose The purpose of this enclosure is to calculate an estimated critical boron concentration to be used during unit start up.

2. Procedure Calculation Perfonned by:______________________

2. 1 This enclosure must be perfonned twice the second is the separate verification. Circle whether this is the original or the verification:

Original Must be performed by a Licensed Operator Separate Verification Must be performed by a Qualified Reactor Engineer (N/A steps 2.8-2.10 for Separate Verification)

CAUTION: IF the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result.

NOTE: IF conducting an initial cycle startup the power history is 0% F. P.

2.2 IF returning from a forced shutdown:

2.2.1 Obtain the power history back to the last time of Xenon Equilibrium to perfonn the Xenon calculation from a source such as PT server, OAC Log, RO Log, etc.

2.2.2 Attach actual power history (from OAC log, TMS, PT Server, etc.) to this enclosure.

2.3 Open RhoCalc.

Enclosure 13.5 PT/i/A/I 103/0 15 Computerized Estimated Critical Boron Page 2 of 2 Calculation NOTE: 1. The target ECP is normally -Group 6 at 50% for reactor startups other than the initial cycle startup. This can be adjusted to plant conditions at the discretion of the SRO.

IF deviating from this position significantly, model the power increase using PT/0/A/1 103/020, Power Maneuvering Predictions, to ensure no problems will be encountered.

2. EFPD input into the code shall correspond to the beginning of the power history, NOT the EFPD at the effective time of calculation.

2.4 Input appropriate data for the estimated critical boron calculation, select Calculate ECB, and print.

NOTE: Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation, does NOT have to be used to calculate the ECP in step 2.5.

2.5 Run Rhocalc to calculate an ECP using the boron concentration found in the ECB above.

NOTE: When choosing the input Boron concentration for the ECP during transient Xenon conditions sufficient time must be factored in to allow for changes to be made to the RCS and PZR Boron concentration, samples to be taken, the time required to pull Groups I 4 -

to 100% wd, and any other time constraints noted by the 0CC.

2.6 Ensure that all Safety rod groups can be fully withdrawn one hour prior to the time that 5 < 0% shows in the Rod Posn @ MODE 2 Entry column of the ECP printout for the anticipated time of criticality.

2.7 Verify Separate Verifications agree on the ECB within 10 pprnB for all future time steps.

2.8 Discuss the results of ECB with the Control Room SRO. (N/A this step on separate verification calculation).

Room SRO 2.9 Attach results of ECB to the procedure and turn the package over to the Control Room SRO. (N/A this step on separate verification calculation).

NOTE: The Reactor Engineering mail code is ONO3CV.

2.10 WHEN the ECB is no longer required, return this procedure, including all applicable enclosures and attachments, to Reactor Engineering. (N/A this step on the separate verification calculation.)

Enclosure 13.6 PT/i/A/i 103/015 Computerized Subcritical Multiplication (1/M) Page 1 of 4 Measurement

1. Purpose The purpose of this enclosure is to perform 1/M measurements by spreadsheet during unit start up other than the initial cycle startup. PT/0/A/0711/001, Zero Power Physics Procedure, controls the initial cycle startup.

2. Procedure NOTE:

This procedure is performed by a Qualified Reactor Engineer. The Double Verification performed in step 2.7.6 shall be by a Licensed Operator.

Step 2.4 may be perfonned at any time and should be referenced at this time.

Calculation Performed By:_________________ Date:___________ Time:________________

CAUTION: The 1/M plot should only be used as an operator aid for predicting premature criticality and should NOT be relied upon for predicting critical rod position or as a substitution for Control Room indications.

NOTE: A control copy of 1M.xls is located in the following locations:

\\ONSFSOO\SYSCODES\Computer Support\ 1_M Spreadsheet\ 1_M.XLS

Reactor Engineering Fireproof Cabinet

SDQA 10135-ONS 2.1 Open spreadsheet 1_M.xls.

2.2 Perform the following Steps on the NI-i TAB (user input cells are yellow).

2.2.1 Enter appropriate Unit number 2.2.2 Enter appropriate Cycle number 2.2.3 Enter NO in the Begin of Cycle? field.

2.2.4 Enter current cycle EFPD into the EFPD field.

NOTE: Notify Lines can be selected or deselected at any time during this procedure at the users discretion.

2.2.5 IF desired, enter YES for Graph Notify Lines? field.

Enclosure 13.6 PT/i/A/i 103/015 Computerized SubcriticaL Multiplication (1/M) Page 2 of 4 Measurement NOTE: 1. Xenon free is defined as < 0.1%AKIK of Xenon present in the core. This number can be obtained from the OAC, Rho Calc, etc.

2. The review criteria for a Xenon free startup is +/- 0.35%AKIK The review criteria for a startup with xenon is +/- 0.5%AKIK.

2.2.6 Select whether startup will be Xenon free (YES) or (NO).

2.2.7 Enter the RhoCalc produced Rod Group and Rod Position at the time of desired criticality, from the ECP generated in Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation.

2.2.8 Enter the time Safety Groups must be fully withdrawn from the ECP generated in Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation.

NOTE: 1. Regardless of NI-i operability, the date and times at rod position hold points must be recorded on TAB NI-i.

2. All operable NIs should be used when performing this enclosure.

2.3 Determine the operable NIs with Operations.

2.4 Perform one of the following:

2.4.1 IF Step 2.5 of Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation was answered Yes, verify current conditions match those assumed in the ECP within + 5 ppmB and +/- 10 RCS Temperature.

OR 2.4.2 Perfonn Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation again using the current conditions as inputs.

2.5 In the appropriate tabs of the spreadsheet, record initial count rates Ci, C2 and C3 with CR Group 1 at 50 +/- 2%wd, CR Group 8 at 35+/- 5%wd.

NOTE: TS SR 3.2.1.3 requires verification of SDM within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving criticality.

2.6 Prior to withdrawing Group 1 from 50 to 100% withdrawn, verify SDM at the current RCS conditions.

Enclosure 13.6 PT/i/A/i 103/015 Computerized Subcritical Multiplication (1/M) Page 3 of 4 Measurement NOTE: 1. The same NI(s) selected for Co must be used consistently for the entire withdrawal sequence 1/M measurement.

2. After each pull, wait until count rate stabilizes before taking next set of counts. For example, it may only be necessary to wait thirty seconds after each pull on the safety groups. As the reactor gets closer to criticality, it may be necessary to wait several minutes after each pull before count rate stabilizes.

3. NOT all hold points may be used. The hold points in step 2.7.6 that are NOT used may be N/Aed.

t

4. By signing off hold points in step 2.7.6 the procedure user is documenting that steps 2.7.1 2.7.5 have been completed for each hold point or have been evaluated and detennined not to be required for that hold point.

2.7 Have Ops withdraw CR Groups to their upper limits, stopping with each applicable group at the positions listed below. At each position; (R.M.)

2.7.1 IF required, update the Rhocaic generated ECP portion of the 1/M.XLS spreadsheet. This assures that the correct predicted conditions are used in the 1/M.xls spreadsheet.

2.7.2 Wait approximately one minute, and then enter NI count rates into the appropriate tab of the spreadsheet.

NOTE: The evaluation as required in 2.7.3 may include further rod withdrawal to add positive reactivity equal to or less than one-half of the amounts remaining to provide the predicted criticality.

2.7.3 IF the Extrapolated Estimated Critical Rod Position indicates critical conditions prior to the lower limit of criticality OR lower notify limit of criticality, STOP further rod withdrawals and evaluate. (R.M.)

NOTE: Criticality must be achieved within 0.75% L\KIK of the ECP per Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation).

2.7.4 When any 1/M data point is plotted greater than the lower limit of criticality, the i/M measurement may be stopped.

2.7.5 IF criticality cannot be achieved within 0.75% AKIK of the ECP, notify the Operations Shift Manager, insert control rods to Group 1 at 50%w/d, request an immediate RCS Boron sample, AND notify Reactor Engineering. (R.M.)

Enclosure 13.6 PT/i/A/i 103/015 Computerized Subcritical Multiplication (1!M) Page 4 of 4 Measurement 2.7.6 Calculate 1/M.

Additional data points may be taken if desired.

CR Groups Rod Positions (within +/- 2%wd) 1 50 (Co) wd UPS QRE 1 100%wd Ups QRE 2 100%wd Ups QRE 3 iOO%wd Ups QRE 4 100%wd Ups QRE 5 50%wd Ups QRE 5 75%wd Ups QRE 6 25%wd Ups QRE 6 50%wd UPS QRE 6 75%wd UPS QRE 7 25%wd UPS QRE 7 50%wd UPS QRE 7 75%wd UPS QRE 7 100%wd UPS QRE 2.8 Ensure actual critical conditions are recorded on the ECP printout.

2.9 Print and attach the 1/M spreadsheet.

Enclosure 13.7 PT/i/A/i 103/0 15 Core Excess Reactivity vs. Burnup Page 1 of 1 Groups 1-7 @ 100%

Grp 8 35% wd (NOT @ 35% wd after 435 EFPD) 532 F NOXE EQSM 01C26 14 15 13 14 13 12 2 12 c

a) 11 10 0

10 U) cn9 a) 0 x

Ui a) 0 08 Use if Grp8 NOT 35% w/d 8 7

7 6

6 Use if GrpS @ 35% w/d 5 5 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 Core Burnup (EFPD)

0 G Enclosure 13.8 PT/i/A/i 103/015 Differential Boron Worth vs. Burnup Page 1 of 2 01C26

-0.013 HI H HF nterpolate to Actua Temperature I -

-0.012 -

300F

.0 -

E

0. -

- 400F 450F 0

0 o32F w 560F

-0.009 -

-0.008

-0.007 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 Core Burnup (EFPD)

o C Enclosure 13.8 PT/1/A/11o3/o15 Differential Boron Worth vs. Burnup Page 2 of 2 01C26 NOTE: The data in the Table below is taken from the Unit 1 Cycle 26 PTM, table 30. These values are used to generate the graph on page 1 of2.

TEMPERATURE EFPD 60 300 400 450 532 560 0 -0.01027 -0.00938 -0.00881 -0.00848 -0.00776 -0.00748 100 -0.01055 -0.00957 -0.00898 -0.00863 -0.00792 -0.00762 300 -0.01153 -0.01040 -0.00975 -0.00937 -0.00859 -0.00828 435 -0.01245 -0.01 124 -0.01053 -0.01006 -0.00923 -0.00891 500 -0.01301 -0.01172 -0.01090 -0.01041 -0.00962 -0.00928

0 0 Enclosure 13.9 PT/i/A/i 103/0 15 Temperature Coefficient vs. RCS Boron Concentration Page 1 of 1 532 F HZP Grp 7 @0% wil 01C26 0.000 0

-0.001 -0.001

-0.002 -0.002

-0003 :: ::: -0.003

-0.004 -0.004

-0.005 -0.005 6

Eooo 0)

-0.006 a) 0.007 0.007

-0.008 -0.008

-0.009 -0.009

,. H

-0.010 -0.01 1-0.011 -0.011

-0.012 -0.012 o

-0.013 -0.013

-0.014 -0.014 0.015

-0.016 -0.016

-0.017 ::: -0.017

-0.018 -0.018

-0.019 -0.019

-0.020 -0.02

-0.021 -0.021

-0.022 -0.022 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 RCS Boron Concentration (ppmb)

0 0 Enclosure 13.10 PT/i/A/I 103/0 15 Shutdown Boron Concentration vs. Burnup (Group 1 @ 0% id) Page 1 of 2 Groups 1-7 @ 0% wd Grp 8 @% wd (NOT @3% wd after 435 EFPD) 01C26 1500 1400 1300 N Assumes Worst Stuck Rod flu 1200 1100 1000 m

2 0.

o. 900 800 700 0

(3 600 0

30F 500 t Atu T P 300F 400 100 F 300 200 100 532F 0 360F 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 Core Burnup (EFPD)

0 Enclosure 13.10 PT/1/A11103/015 Shutdown Boron Concentration vs. Burnup (Group 1 @ 0% wd) Page 2 of 2 Groups 1-7 @ 0% wd Grp 8 35% wd (NOT @3% wd after 435 EFPD) 01C26 NOTE: The data in the Table below is taken from the Unit I Cycle 26 PTM, table 5. These values are used to generate the graph on page 1 of 2.

TEMPERATURE EFPD 60 300 400 450 532 560 Gp8at35 0 1502 1468 1428 1395 1303 1251 Gp8at35 100 1358 1315 1265 1224 1106 1045 Gp8at35 300 985 913 834 774 611 528 Gp8at35 435 685 590 494 424 233 137 Gp 8 NOT at 35 435 690 601 509 442 260 167 Gp 8 NOT at 35 490 566 468 370 298 105 9 Gp 8 NOT at 35 500 544 445 346 273 79 -19

0 0 Enclosure 13.11 PT/1/A!1103/015 Shutdown Boron Concentration vs. Burnup (Group 1 @ 50% wd) Page 1 of 2 Grps 2-7 @ 0% wd Grp 8 @5% wd (NOT @% wd after 435 EFPD) 01C26 1600 1500 1400 1300 Not A Wo S kRodOu 1200 1100 E 1000 a.

a.

c 900 0

(U 800 a)

C) 700 600 t at t A T ntr 60F 500 300 F 400 400 F 300 450 F 200 532 F 100 560 F 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 Care Burnup (EFPD)

0 Enclosure 13.11 PT/i/All 103/0 15 Shutdown Boron Concentration vs. Burnup (Group 1 @ 50% wd) Page 2 of 2 Grps 2-7 @ 0% wd Grp 8 @3% wd (NOT @3% wd after 435 EFPD) 01C26 NOTE: The data in the Table below is taken from the Unit I Cycle 26 PTM, table 7. These values are used to generate the graph on page I of2.

TEMPERATURE EFPD 60 300 400 450 532 560 Gp8at35 0 1563 1552 1531 1511 1447 1409 Gp8at35 100 1410 1396 1366 1339 1249 1202 Gp8at35 300 1010 969 913 868 734 666 Gp8at35 435 693 627 551 496 333 251 Gp 8 NOT at 35 435 695 627 551 496 333 251 Gp 8 NOT at 35 490 569 483 402 340 172 87 Gp 8 NOT at 35 500 547 459 375 312 143 57

Enclosure 13.12 PT/1/A/11o3/o15 Inoperable Rod Penalty for Individual Page 1 of 1 Inoperable Rod 01C26 Rod Rod Eighth Core Penalty Group No. Location (% \KIK) 1 1,2,3,4,5,6,7,8 K-il 0.35 2 1,2,3,4,5,6,7,8 M-13 1.72 3 2,4,6,8 K-09 0.05 3 1,3,5,7 H-b 0.05 4 1 H-08 0.01 4 2,3,4,5,6,7,8,9 L-14 0.70 5 2,5,8,11 M-11 1.21 5 1,3,4,6,7,9,10,12 K-13 0.81 6 2,4,6,8 L-10 0.32 6 1,3,5,7 H-14 0.25 7 2,4,6,8 N-12 1.72 7 1,3,5,7 H-12 0.50

Enclosure 13.13 PT/i/A/i 103/0 15 Refueling Outage Boron Concentrations Page 1 of 1 01C26 NOTE: This boron concentration will provide a shutdown margin of greater than 1% LK/K with the most reactive bank withdrawn and the worst case stuck rod out with cycle burnup at 0 EFPD. RCS temperature is between 60°F 532°F. All other banks are assumed to be fully inserted. It is also conservative for performing CRDTTT at 0 EFPD.

CRD Patch Verification and CRD Trip Time Testing:

> 1698 pprnB if Group 8 is 30-40% wd

> 1748 ppmB if Group 8 is NOT 30-40% wd (between 60°F - 532°F)

ZPPT All-Rods-Out Boron Concentration 1771 pprnB (at 532 °F)

NOTE: This boron concentration will provide a shutdown margin of greater than 1% z\K/K with all control rods withdrawn and no credit taken for Xenon for temperatures 33°F or greater.

Refueling Boron Concentration:

> 2220 pprnB (33°F or above)

Enclosure 13.14 PT/1/A/11o3/o15 Required Group 8 Position and Designed Page 1 of 1 Cycle Length 01C26 REQUIRED GROUP 8 POSITION:

CAUTION: 1. For reactor shutdown, use Group 8 position listed below unless otherwise directed by OP/i/A/i 102/0 10.

2. IF a reactor trip occurs during Group 8 withdrawal to 100%, Group 8 will be repositioned to 30 40 %wd.

3. The term APSR pull utilized below is defined as the planned course of action to pull group 8 from 30 40% to 100% withdrawn beginning at:

435 EFPD Prior to APSR pull During APSR pull After APSR pull Required Group 8 Required Group 8 Required Group8 Condition Position (% wd) Position (% wd) Position (%wd)

Approach to Criticality 30 40

- 30 40- 100 Steady State Operation 30 40 35 - 100 100 Reactor Shutdown 30-40 30-40 100 Group 8 may be inserted to 35% wd for increased shutdown margin.

DESIGNED CYCLE LENGTH:

The Oconee Unit 1 Cycle 26 designed cycle length is 480 500 EFPD.

0 Enclosure 13.15 PT/i/A/i 103/015 Power Defect vs. Reactor Power Page 1 of 1 Group 8 35% wd (NOT @% wd after 435 EFPD)

HFP EQXE EQSM 01C26

-3 500 EFPD

-2.5 I

-2 2 250 EFPD w

15-1.5 4EFPD 0

0

-0.5 0

0 10 20 30 40 50 60 70 80 90 100 Power Level (%FP)

Enclosure 13.16 PT/i/A/I 103/0 15 Shutdown Margin Requirements Page 1 of 1 01C26 The Shutdown Margin (SDM) shall be greater than 1% Ak/k. (Ref. TS 3.1.1 and COLR)

Enclosure 13.17 PT/1/A/11o3/o15 Control Rod Group Worths for Control Rod Page 1 of 1 Drop Time Testing 01C26 NOTE: Interpolate for intenediate temperatures.

Control Rod Group Worths for BOC CRDTTT, HZP, No Overlap Group8 @ 35% wd, NOXE CRGP 1 performed with CRGP2-7 in, CRGP2 performed with CRGPI,3-7 in, etc.

Rod Group 300F 532F 1 1.188 1.557 2 1.985 2.192 3 1.104 1.812 4 0.709 0.852 5 2.238 2.629 6 0.642 0.905 7 1.824 2.042 1-4 4.594 5-7 4.873 NOTE: These rod group woiihs are for worst-case Xenon conditions for eabh group.

Groups 1-7 Control Rod Group Worths For Trip Time Tests After BOC HZP, No Overlap, 525-557°F Group 8@35%wd CRGP 1 performed with CRGP2-7 in, CRGP2 perfonued with CRGP1, 3-7 in, etc.

Rod 4 250 500 Group EFPD EFPD EFPD 1 1.638 1.755 1.839 2 2.288 2.3 10 2.490 3 2.034 2.152 2.263 4 0.983 1.069 1.273 5 2.725 2.802 2.955 6 0.980 1.044 1.112 7 2.119 2.090 2.226

Enclosure 13.18 PT/i/A/I 103/015 Shutdown Margin Calculation at Power Page 1 of 1

1. Purpose 1.1 The purpose of this enclosure is to perfonn a shutdown margin calculation while at power.

2. Procedure Performed By:

NOTE: Step 2.1 applies only to control rod groups 1 through 6. Group 7 and the APSRs may be positioned as required.

2.1 IF any groups are NOT at 100% withdrawn (other than Group 7 and the APSRs) due to CRD movement PT:

2.1.1 Verify that only one group is NOT at 100% withdrawn.

2.1.2 Verify that the inserted group is ? 95% withdrawn.

NOTE: For a dropped rod/stuck rod scenario, utilize 1 inoperable rod graphs in the COLR. The rod position used should be the position of the controlling group (if the dropped/stuck rod is in the controlling group, the rod positions of remaining rods in that group should be used, not the group average.)

2.2 Verify one of the following:

2.2.1 Available shutdown margin is 1% AK!K. This is shown by verifying that the control rod position and power level are within the Acceptable Region or the Restricted Region on the appropriate curve for the number of RC Pumps and Inoperable rods in the COLR.

OR 2.2.2 Appropriate actions are taken per TS 3.1.4, 3.1.5, and 3.2.1 sv

0 Enclosure 13.19 PT/i/A/i 103/0 15 Group 7 Control Rod Worth Page 1 of 1 IIZP, NOXE and PKXE Group 8 @ Nominal Position 01C26 0

0.2 This graphprovided forinformationt - >1 -

I Note:isnotusedinanycahDuIationsintIs >

0.4 L Z ---i 0.6

+4EFPD NOXE 0.8 4EFPD PKXE 0

25OEFPD NOXE V X-25OEFPD PKXE 0

-500EFPD NOXE C

500EFPD PKXE 0

C.)

V 1.2 1.4 /_i- :z:E:

H 1.6 1.8 0 10 20 30 40 50 60 70 80 90 100 Group 7 Control Rod Position (%wd)

Minimum RCS Boron Concentration (ppm B)

N) C.) C D) CD C - N) C.)

C C C C C C C C C C C C 0 0 C C 0 0 0 0 0 C C C C C C C C C

C.)

C a)

C CD C

N)

S C

C a,

0

C w

c m C C.)

C C

rj rj C.)

C.-)

C C

C.)

a)

C C.)

CD C

N)

C C I.

C C>

a, C

C C

e Enclosure 13.20 PT/i/A/i 103/0 15 Minimum RCS Boron Concentration to Maintain SSF Operability Page 2 of 2 O1C26 NOTE: 1. IF xenon is <2.0%, use the No Xenon curve. IF xenon is between 2.0% AND 2.5%, use the Xenon2% curve. jj xenon is >2.5%, use the Xenon=2.5% curve.

2. IF the minimum required boron concentration to maintain SSF operability cannot be met using the limiting curves, then interpolation on EFPD and xenon is permitted.

3. Unless otherwise indicated, the boron values below assume Group 8 is at 35% withdrawn.

No Xenon & 525 F Xenon = 2.0% Xenon = 2.5%

EFPD Mm Boron Required for SSF Mm Boron Required for SSF Mm Boron Required for SSF 0 1266 1059 1030 4 1258 1050 1021 12 1242 1032 1002 25 1217 1003 972 50 1168 948 914 100 1071 842 802 150 948 715 668 200 825 596 541 250 703 478 421 300 580 359 304 350 441 226 172 400 302 93 40 435 204 -1 -52 500 31 -166 -215 435 231 with Group 8 NOT = 35% 25 with Group 8 NOT = 35% -26 with Group 8 NOT = 35%

500 51 with Group 8 NOT = 35% -146 with Group 8 NOT = 35% -196 with Group 8 NOT = 35%

Admin-112 R2 Page 1 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-1 12 Calculate Requirements to Makeup to the BWST CANDIDATE EXAMINER

Admin-112 R2 Page 2 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate requirements to makeup to the BWST Alternate Path:

No Facility JPM #:

Bank KIA Rating(s):

System: GEN K/A: 2.1.25 Rating: 3.9/4.2 Task Standard:

Calculate volume of CBAST and DW needed to yield the proper volume at the correct Boron concentration to makeup to the BWST.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Classroom X Perform X Simulate

References:

EOP Enclosure 5.4, Makeup to the BWST Validation Time: 13 minutes Time Critical: NO Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time:

Examiner: /

NAME SIGNATURE DATE COMMENTS

Admin-112 R2 Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin-112 R2 Page 4 of 8 Tools/Equipment/Procedures Needed:

FOP Enclosure 5.4, Makeup to the BWST

OPIOIAI11O8!001, Curves and General Information

COLR READ TO OPERATOR DIRECTION TO TRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS

Unit 1 shutdown and cool down in progress due to a tube rupture in the 1A SG

SGTR Tab in progress at Step 118

Unit 1 BWST level = 38 feet

Unit I BWST Boron concentration = 2500 ppm

1A BHUT level 40 inches

1A BHUT Boron Concentration = 240 ppm

CBAST Boron Concentration = 12,501 ppm INITIATING CUES The CR SRO instructs you to initiate FOP Enclosure 5.4 (Makeup to the BWST) to determine the required volumes of CBAST and DW to begin makeup to the BWST from 1A BHUT.

You are to calculate the required volumes of CBAST and DW to fill 1A BHUT to 182 inches and match the current BWST Boron concentration.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

Unit 1 shutdown and cool down in progress due to a tube rupture in the 1A SG

SGTR Tab in progress at Step 118

Unit 1 BWST level = 38 feet

Unit 1 BWST Boron concentration = 2500 ppm

1A BHUT level = 40 inches

1A BHUT Boron Concentration = 240 ppm

CBAST Boron Concentration = 12,501 ppm INITIATING CUES The CR SRO instructs you to initiate EOP Enclosure 5.4 (Makeup to the BWST) to determine the required volumes of CBAST and DW to begin makeup to the BWST from 1A BHUT.

You are to calculate the required volumes of CBAST and DW to fill 1A BHUT to 182 inches and match the current BWST Boron concentration.

Admin-112 R2 Page 5 of 8 START TIME:

STEP I: Step 1 CRITICAL STEP Determine current volume in 1A BHUT using any of the following:

OAC graphic CS01 SAT

BHUT Volume vs. Level Curve (End. 4.1) in OP/U/A/i 108/001 (Curves and General Information)

UN SAT STANDARD: Refer to BHUT Volume vs. Level Curve in OP/U/Ni 108/001 (Curves and General Information) and determine that the volume of water in the 1A BHUT is 14,000 gallons (40).

COMMENTS:

STEP 2: Step 2 CRITICAL STEP Determine volume of CBAST required per the following to yield a volume in 1A BHUT of 80,000 to 82,000 gals at 2500 ppm: SAT (BHUTVfX BHUTcf)- ( BHUTVI x BHUT)

CBASTC,

= # gallons of CBAST needed UNSAT

( 82,000x2,500) -(14,000 x 240) 12,501

= 16,130

gallons of CBAST needed STANDARD: Candidate calculates the required volumes from CBAST within 100 gallons of the above calculated values.

BHUTvf= Final BHUT volume (gal)

BHUTVI = Initial BHUT volume (gal)

BHUTcf= Final BHUT conc (ppmb)

BHUTC Initial BHUT conc (ppmb)

CBASTC CBAST conc (ppmb)

Note: Instructions are to fill IA BHUT to 182 which is correlates to 82,000 gal.

COMMENTS:

Admin-112 R2 Page 6 of 8 CRITICAL STEP STEP 3: Step 3 Determine volume of DW required per the following to yield a volume in SAT 1A BRUT of 80,000 to 82,000 gals at 2500 ppm:

BHUTvf BHUTvI # gallons CBAST needed UNSAT

- - = # gallons of DW needed 82,000 14,00016,130 = 51870

gallons of OW needed STANDARD: Candidate calculates the required volumes from DW within 100 gallons of the above calculated values.

COMMENTS END OF TASK STOP TIME:

Admin-112 R2 Page 7 of 8 CRITICAL STEP EXPLANATIONS STEP # Explanation 1 Required for determining the correct water volumes.

2 These calculations are required for determining the correct water volumes.

3 These calculations are required for determining the correct water volumes.

Enclosure 4.1 OP/O/AJ1 108/001 BHUT Volume Vs. Level Curve Page 1 of I Level (inches) 0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 90000 90000 I I I I I 80000 80000 70000 70000 III 60000 60000 I

(I)

C c) 0 50000 NOTE: Bleed Transfer Pump trips at 15 I 50000 Ct .

0) indicated level (29 actual level). {10}

0 I I C

C)

E 40000 40000 0

30000 ttEi2E:: 30000 20000 20000 I

10000 10000 0

0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 H,,,

160 170 180 190 200 0

Level (inches)

File: BHUT.jnb OSC-71 29

Enclosure 5.4 EP/1/AI1 800/001 Makeup to the BWST {25) Page 1 of 37 f ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Detennine current volume in I A BHUT using y of the following:

OAC graphic CSOI BHUT Volume vs Level Curve in OPIO/A/l 108/001 (Curves and General Information)

2. Determine volume of CBAST and DW required per the following to yield a volume in 1A BHUT of 80,000 to 82,000 gals at a concentration that complies with COLR requirements for the BWST:

Where:

BHUTf = Final BHUT volume (gal)

BHUTV Initial BHUT volume (gal)

BHUTCf Final BHUT conc (ppmb)

BHUTCI = Initial BHUT conc (ppmb)

CBASTC = CBAST conc (ppmb)

(BHUTVf x BHUTf) - (BHUTVI x BHUT)

= # gallons of CBAST needed CBASTC

gallons of CBAST needed BHUTvf - BHUTvi - # gallons CBAST needed # gallons of DW needed

gallons of DW needed

3. Verify boron addition to I A BHUT required.

r GO TO Step 46.

Enclosure 54 EPIlIAIl800Iool Makeup to the BWST {25} Page 3 of 37 f ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. quantity of boron needed for GO TO Step 6.

transfer to I A BHUT is available in the CBAST without going below minimum SLC required for CBAST.

5. GO TO Step 31.

6. Unit 1&2 BAMT is < 62. GO TO Step 9..

7. Locally perform the following:

A. Fill BAMT not to exceed 62 via DW-l 18 (BAMT Fill Isol Vlv)

(A-I, l&2 BAMT Rm).

B. Start Unit I &2 BAMT AGITATOR (A-2, l&2 Chem Add Panel).

C. Place Unit I &2 BAMT HEATER switch in AUTO (A-2, I &2 Chem Add Panel).

D. Unit l&2 BAMT temperature is 127°F, THEN notify Primary Chemistry to add chemicals.

8. WHEN ready to transfer Unit I &2 BAMT to CBAST, THEN continue in this enclosure.

9. Open ICS-62.

10. Locally perform the following (A-i, I &2 BAMT Rm):

A. Close CA-38 (Unit 1/2 HP Boric Acid Pump Suction Tell Tale).

B. Open the following:

CA-4 (Unit 1/2 BAMT Outlet)

CA-20 (Boric Acid Hdr To CBAST)

11. Verify B LP Boric Acid Pupip will be I . Locally start A LP Boric Acid Pump used for transfer of BAMT to CBAST. (A-2, I &2 Chem Add Panel).

2._ GOTO Step 14.

Enclosure 54 EP/1/A/1 800/001 Makeup to the BWST Page 5 of 37 ACTION1EXPETED RESPONSE RESPONSE NOT OBTAINED

12. open CA-il (AJB LPBAMT Pumps Disch Tie) (A- 1, 1 &2 BAMT Rin).

13. Locally start B LP Boric Acid Pump (A-2, 1&2 Chem Add Panel).

14. cycle DW-l 19 (Boric Acid Mix Pumps Suction Hdr Flush) (A-I, I &2 BAMT Rm).

15. Inform Units I and 2 to monitor for reactivity effects due to possible leakage of I &2 BAMT into LDST.

16. Locally perform the following (A-2, I &2 Chem Add Panel):

A. Place Unit l&2 BAMT HEATER switch in OFF.

B. Stop Unit I&2 BAMT AGITATOR.

17. WHEN transfer is complete, THEN locally stop the selected LP Boric Acid Pump (A-2, I&2 Chem Add Panel).

I 8 Locally perform the following (A-I, I &2 BAMT Rm):

A. Close CA-4 (Unit 1/2 BAMT Outlet).

B. Open DW-I 19 (Boric Acid Mix Pumps Suction Hdr Flush).

19. Locally start previously running LP Boric Acid Pump (A-2, 1&2 Chem Add Panel).

20. WHEN LP Boric Acid Pump has run for 5 minutes, THEN Ioca1ly stop LP Boric Acid Pump (A-2, I&2 Chem Add Panel).

Enclosure 5.4 EPI1/A/I 800/001 Makeup to the BWST {25} Page 7 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

21. Locally close the following (A-I, I &2 BAMT Rm):

CA-20 (Boric Acid Hdr To CBAST)

DW-1 19 (Boric Acid Mix Pumps Suction Hdr Flush)

22. ICS-62.

23. B LP Boric Acid Pump was used GO TO Step 25.

for transfer of I3AMT to CBAST.

24. Locally close CA-I I (A/B LP BAMT Pumps Disch Tie)

(A-1, l&2 BAMT Rm).

25. Locally open CA-38 (Unit 1/2 HP Boric Acid Pump Suction Tell Tale) (A-I, l&2 BAMT Rm).

26. quantity of boron needed for l._ Notify Primary Chemist of volume transfer to I A BHUT is available in the removed from Unit I &2 BAMT.

CBAST without going below minimum SLC required for CBAST. 2. GO TO Step 7

27. Open I CS-64.

28. Start I A CBAST PUMP.

29. Inform all units to monitor for reactivity effects due to possible leakage of CBAST into LDST.

30. Notifi Primary Chemist of the following:

Volume removed from Unit I &2 BAMT To sample Unit 1 CBAST for boron

31. WHEN boron addition to I A BHUT is desired, THEN close ICS-46.

32. Place T/O Sheet tag on the following:

ICS-46 IHP-16

.0 33. Place the following notes on I/O sheet:

Do not open ICS-46.

Do not open IHP-16.

Enclosure 5.4 EPI1/A/l 800/00 1 Makeup to the BWST Page 9 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

34. Open I CS-64.

35. Locally perform the following:

A. Close 1CS-148 (IA BHUT Outlet Block)

(A-I, Unit I BTP Rm).

B._ Open ICS-150

. (Bid Xfer Pump 1A Suct Tie)

(A-i, Unit I BTP Rm).

C._ Open ICS-66 (CBAST Tie To Bid Xfer Pumps)

(A-I hallway, 8 S of column 65 at CBAST).

36. 1A BLEED TRANSFER PUMP.

37. Monitor the following for unexpected level changes:

El,

IBBHUT

Unit I LDST

Unit I CBAST

38. IAAT unexpected level changes occur in GO TO Step 42.

Unit I tanks (lB BHUT, LDST, CBAST),

THEN GO TO Step 39.

39. Stop IA BLEED TRANSFER PUMP.

40. Determine and correct cause of unexpected level change.

41. Step 1.

42. WHEN CBAST addition to IA BI-IUT is complete, THEN stop IA BLEED TRANSFER PUMP.

Enclosure 5.4 EP/1/AI1 800/00 1 Makeup to the BWST{

}

25 Page 11 of37 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

43. Locally perform the following (A-I, Unit 1 BTP Rm):

A. Close I CS-66 (CBAST Tie To Bid Xfer Pumps).

B. Close ICS-150 (Bid Xfer Pump 1A Suet Tie).

C._ Open 1CS-148 (IA BHUT Outlet Block).

44. Remove T/O Sheet tag from the following:

ICS-46 IHP-16

45. Remove the following notes from T/O sheet:

Do not open 1CS-46.

(.) 46.

Do not open 1HP-16.

DW addition to IA BHUT GO TO Step 58.

required.

47. Ensure space is available in Waste Gas Tanks.

48. open IDW-174 (Bleed Holdup Tank Supply) (A-I, hallway S of freight elevator).

49. Locally throttle I CT-87 (Condensate To BHUT I A) as necessary to control flow and minimize vent header pressure (A-I, hallway).

Enclosure 5.4 EP/1/A/1 800/00 1 Makeup to the BWST {25} Page 13 of37 T ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

50. Monitor the following for unexpected level changes:

1BBHUT

Unit I CBAST

51. Notify Unit 2 to monitor the following for unexpected level changes:

2ABHUT

2BBHUT

Unit 2 CBAST

52. IAAT unexpected level changes occur in GO TO Step 56.

Unit I, OR Unit 2 BHUTs or CBASTs, V THEN GO TO Step 53.

53. close 1DW-174 (Bleed Holdup 0 Tank Supply)

(A-I, hallway S of freight elevator).

54. Determine and correct cause of unexpected level change.

55. GO TO Step 46.

56. WHEN DW addition to IA BHUT is complete, THEN continue in this enclosure.

57. Locally close the following:

IDW-l74 (Bleed Holdup Tank Supply)

(A-I, hallway S of freight elevator)

I CT-87 (Condensate To BHUT I A)

(A-l,hallway)

58. Start IA BLEED TRANSFER PUMP.

59. WHEN 1 A BHUT has been on recirc for 1/2 hour, V THEN notify Primary Chemistry to obtain 1A BHUT boron sample.

60. WHEN I A BI-IUT sample results are available, THEN continue in this enclosure.

Enclosure 5.4 EP/1/AJ1 800/001 Makeup to the BWST{

}

25 Page 15 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

61. GOTOStep 1.

limits for BWST boron requirements.

62. IAAT ll the following conditions exist: GO TO Step 72.

I B BHUT NOT being transferred to BWST Makeup to BWST required THEN perform Steps 63 71. -

63. Close 1HP-16.

64. Perform the following:

A. T/O sheet tag on IHP-16 control switch.

B. Do not operate IHP-16 on T/O sheet.

65. Notifi RP to perform the following:

. Perform surveys around BWST during transfer.

Adjust BWST radiological boundaries as necessary.

66. Ensure NONE of the following are in recirc:

Unit I BWST Unit 2 BWST 1&2 SFP

67. Locally open the following:

I CS-96 (Spent Fuel IX (Rinse) Block)

(A-2, around corner from Caustic Add Pump)

LWD-156 (SF IX Sluice)

(Rm 218, SF Cooler Rm)

68. Verify HPJ Purification Tagout is hung. GO TO Step 70.

Q 69. Locally open I CS-59 (Bleed Transfer Pumps Disch Tie) (A-I, RC Bleed Transfer Pump Rm).

Enclosure 5.4 EP/1/AJl 800/001 Makeup to the BWST {25} Page 17 of 37 ACTIONJEXPECTED RESPONSE RESPONSE NOT OBTAINED

70. Open 1 CS-46.

71. Locally throttle SF-47 (SF Filter Outlet To Unit 1 BWSY) based on the following (Rm 218, SF Cooler Rm):

. BWST < 46 maintain desired flow

. BWST 46 maintain flow <50 gpm

72. makeup from IA BHUT to GO TO Step 76.

BWST is in progress, AND y of the following conditions exist:

BWST makeup NO longer required IABI-IUTlevel 15 1A BLEED TRANSFER PUMP stopped due to low level in I A 0 BHUT THEN perfonu Steps 73 - 75.

73. Stop IA BLEED TRANSFER PUMP.

74. Close ICS-46.

75. Locally close the following:

I CS-96 (Spent Fuel IX (Rinse) Block)

(A-2, around corner from Caustic Add Pump)

LWD-156 (SF IX Sluice)

(Rm 218, SF Cooler Rm)

SF-47 (SF Filter Outlet To Unit I BWST) (Rm 218, SF CoolerRm)

[ 76. Verify use of lB BHUT for makeup to BWST is NOT desired.

NOTE At this point, repeated batches from IA BHUT can be used to makeup to the BWST or I B BHUT can be borated and alternate batches from both BHUTs can be used for makeup.

GO TO Step 81.

1 J

Enclosure 5.4 EP/1/AJ1 800/001 Makeup to the BWST 25) Page 19 of 37 I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I NOTE Preparations for mixing another batch in IA BHUT can be made while IA BHUT is being transferred to the BWST. If another batch will be necessary, returning to Step I will direct actions to mix a boron batch in the BAMT for transfer to CBAST if the CBAST does NOT contain sufficient volume for boron addition to IA BFTUT. This should minimize the time between batches from 1A BHUT to the BWST.

77. IAAT preparations for mixing another batch in IA BHUT is desired, THEN GO TO Step 1.

78. WHEN makeup operations to the BWST are complete, THEN notify RP of completion.

79. Perform the following:

A. Remove T/O sheet tag from IHP-16 control switch.

B. _Remove Do not operate IHP-16 from T/O sheet.

80. EXIT this enclosure.

Enclosure 5.4 EP/1/AI1 800/001 Makeup to the BWST {25) Page 21 of 37 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

Unit Status

-. Alternating batches from IA and lB BHUTs to the BWST is desired.

81; Determine current volume in I B BHUT using y of the following:

OAC graphic çsoi BHUT Volume vs Level Curve in OP/0/A/1 108/00 1 (Curves and General Information).

82. Determine volume of CBAST and DW required per the following to yield a volume in lB BHUT of 80,000 to 82,000 gals at a concentration that complies with COLR requirements for the BWST:

Where:

BHUTV = Final BHUT volume (gal)

BHUTV = Initial BHUT volume (gal)

BHUTCI Final BHUT conc (ppmb)

BHUTC = Initial BHUT conc (ppmb)

CBASTC = CBAST conc (ppmb)

(BHUTVf x BHUTf) - (BHUTV x BHUT

)

1

= # gallons of CBAST needed CBASTC

(____ )

gallons of CBAST needed BHUTV - BHUTV - # gallons CBAST needed = # gallons of DW needed

gallons of DW needed

Enclosure 5.4 EP/1/AJ1 800/00 1 Makeup to the BWST

}

25 Page 23 of 37 ACTIONIEXPECTED RESPONSE RESPONSE NOT 4 4 OBTA ED JI

83. quantity of boron needed for GO TO Step 85.

transfer to lB BHUT is available in the CBAST without going below minimum SLC required for CBAST. V

84. GOTO Step 110.

85. Unit 1&2 BAMT is < 62. GO TO Step 88.

86. Locally perform the following:

A. Fill BAMT not to exceed 62 via DW-1 18 (BAMT Fill Isol Vlv)

(A-I, l&2 BAMT Rm).

B. Start Unit I &2 BAMT AGITATOR (A-2, l&2 Chem Add Panel). V C. Place Unit I &2 BAMT HEATER V switch in AUTO (A-2, I &2 Chem Add Panel).

0 D. Unit 1&2 BAMT temperature is 127°F, THEN notify Primary Chemistry to add chemicals.

87. WHEN ready to transfer Unit I &2 BAMT to CBAST, THEN continue in this enclosure.

88. Locally perform the following (A-I, 1&2 BAMT Rm):

A. Close CA-38 (Unit 1/2 HP Boric Acid Pump Suction Tell Tale).

B. Open the following:

CA-4 (Unit 1/2 BAMT Outlet)

CA-20 (Boric Acid Hdr To CBAST)

89. ICS-62.

90. B LP Boric Acid Pump will be 1._ Locally start A LP Boric Acid Pump used for transfer of BAMT to CBAST. (A-2, I &2 Chem Add Panel).

2._ GOTO Step 93.

Enclosure 5.4 EP/1/AJ1 800/001 Makeup to the BWST {25) Page 25 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

91. (A/BLPBAMT Pumps Disch Tie) (A-i, 1&2 BAMT Rm).

92. Locally start B LP Boric Acid Pump (A-2, 1 &2 Chem Add Panel).

93. Locally cycle DW-1 19 (Boric Acid Mix Pumps Suction Hdr Flush) (A-i, 1 &2 BAMT Rm).

94. Inform all units to monitor for reactivity effects due to possible leakage of I &2 BAMT into LDST.

95. Locally perform the following (A-2, 1&2 Chem Add Panel):

A. Place Unit 1&2 BAMT HEATER a 96.

B.

switch in OFF.

Stop Unit I &2 BAMT AGITATOR.

WHEN transfer is complete, THEN locally stop the selected LP Boric Acid Pump (A-2, I &2 Chem Add Panel).

97. Locally perform the following (A-I, I&2 BAMT Jm):

A. Close CA-4 (Unit 112 BAMT Outlet).

B. Open DW-I 19 (Boric Acid Mix Pumps Suction Hdr Flush).

98. Locally start previously running LP Boric Acid Pump (A-2, I &2 Chem Add Panel).

99. WHEN LP Boric Acid Pump has run for 5 minutes, THEN locally stop LP Boric Acid Pump (A-2, 1 &2 Chem Add Pandl).

Enclosure 5.4 EP/1/A11 800/001 Makeup to the BWST {25} Page 13 of37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

50. Monitor the following for unexpected level changes:

. IBBHIJT

Unit 1 CBAST

51. Notify Unit 2 to monitor the following for unexpected level changes:

. 2ABHUT

. 2BBHUT

Unit 2 CBAST

52. IAAT unexpected level changes occur in GO TO Step 56.

Unit I, OR Unit 2 BHUTs or CBASTs, THEN GO TO Step 53.

53. close IDW-174 (Bleed Holdup Tank Supply)

(A-I, hallway S of freight elevator).

54. Determine and correct cause of unexpected level change.

55. GO TO Step 46.

56. WHEN DW addition to I A BHUT is complete, THEN continue in this enclosure.

57. Locally close the following:

IDW-174 (Bleed Holdup Tank Supply)

(A-I, hallway S of freight elevator)

I CT-87 (Condensate To BHUT I A)

(A-I, hallway)

58. Start IA BLEED TRANSFER PUMP.

59. WHEN 1 A BHUT has been on recirc for 1/2 hour, THEN notify Primary Cheistry to

. 60.

obtain 1A BHUT boron sample.

IA BHUT sample results are available, THEN continue in this enclosure.

Enclosure 5.4 EP/1IA/l 800/00 1 Makeup to the BWST {25) Page 15 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

61. is within COLR GOTO Step 1.

limits for BWST boron requirements.

62. IAAT ll the following conditions exist: GO TO Step 72.

lB BHUT NOT being transferred to BWST Makeup to BWST required ThEN perform Steps 63 71.-

63. Close 1HP-16.

64. Perform the following:

A. Place T/O sheet tag on IHP-16 control switch.

B. Place Do not operate 1 HP-I 6 on I/O sheet.

65. Notify RP to perform the following:

Perform surveys around BWST during transfer.

Adjust BWST radiological boundaries as necessary.

66. Ensure NONE of the following are in recirc:

Unit I BWST Unit 2 BWST 1&2 SFP

67. Locally open the following:

ICS-96 (Spent Fuel IX (Rinse) Block)

(A-2, around corner from Caustic Add Pump)

LWD-156 (SF IX Sluice)

(P.m 218, SF Cooler Rm)

68. Verify HPI Purification Tagout is hung. GO TO Step 70.

69. Locally open 1 CS-59 (Bleed Transfer Pumps Disch Tie) (A-I, RC Bleed Transfer Pump Rm).

Enclosure 5.4 EP/1/AJl 800/001 Makeup to the 25 BWST{

) Page 17 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

70. Open 1 CS-46.

71. Locally throttle SF47 (SF Filter Outlet To Unit 1 BWSY) based on the following (Rm 218, SF Cooler Rm):

. BWST < 46 maintain desired flow

. BWST 46 maintain flow <50 gpm

72. makeup from IA BHUT to GO TO Step 76.

BWST is in progress, AND y of the following conditions exist:

BWST makeup NO longer required IABHUTIeveI15 IA BLEED TRANSFER PUMP stopped due to low level in IA 0 BHUT THEN perform Steps 73 - 75.

73. IA BLEED TRANSFER PUMP.

74. Close ICS-46.

75. Locally close the following:

I CS-96 (Spent Fuel IX (Rinse) Block)

(A-2, around corner from Caustic Add Pump)

LWD-156 (SF IX Sluice)

(Rm 218, SF Cooler Rm)

SF-47 (SF Filter Outlet To Unit I BWST) (Rm 218, SF Cooler Rm)

NOTE At this point, repeated batches from IA BHUT can be used to makeup to the BWST or lB BHUT can be borated and alternate batches from both Bi-IUTs can be used for makeup.

76. Verify use of I B BHUT for makeup to GO TO Step 81.

BWST is NOT desired.

J

Enclosure 5.4 EPI1IA/l 800/001 Makeup to the BWST {25} Page 19 of 37 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 NOTE Preparations for mixing another batch in IA BHUT can be made while IA BHUT is being transferred to the BWST. If another batch will be necessary, returning to Step I will direct actions to mix a boron batch in the BAMT for transfer to CBAST if the CBAST does NOT contain sufficient volume for boron addition to IA BHUT. This should minimize the time between batches from 1A BHUT to the BWST.

77. IAAT preparations for mixing another batch in IA BHUT is desired,

THEN GO TO Step 1.

78. _WHEN makeup operations to the BWST are complete, THEN notify RP of completion.

79. Perform the following:

A. Remove TIO sheet tag from I HP- 16 control switch.

B. Remove Do not operate 1HP-16 from T/O sheet.

80. EXIT this enclosure.

Enclosure 54 EP/1/AI1 800/00 1 Makeup to the BWST {25} Page 21 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H

Unit Status Alternating batches from IA and lB BHUTs to the BWST is desired.

81 Determine current volume in I B BHUT using y of the following:

OAC graphic CSO1 BFIUT Volume vs Level Curve in OP/0/A/I 108/001 (Curves and General Information).

82. Determine volume of CBAST and DW required per the following to yield a volume in lB BHUT of 80,000 to 82,000 gals at a concentration that complies with COLR requirements for the BWST:

Where:

1 BHUTV = Fmal BHUT volume (gal)

BHUTVI = Initial BHUT volume (gal)

BHUTC = Final BHUT conc (ppmb)

BHUTC Initial BHUT conc (ppmb)

CBASTC CBAST conc (ppmb)

(BHUTV x BHUTCf) - (BHUTVI x BHUT)

= # gallons of CBAST needed CBASTC

(____ )

gallons of CBAST needed BHUTVf - BHUTV - # gallons CBAST needed # gallons of DW needed

gallons of OW needed

Enclosure 5.4 EP/1/AJ1 800/001 Makeup to the BWST {25} Page 23 of 37 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

83. Verif quantity of boron needed for GO TO Step 85.

transfer to 1 B B}{UT is available in the CBAST without going below minimum SLC required for CBAST.

84. GOTO Step 110.

85. Unit 1&2 BAMT is < 62. GO TO Step 88.

86. Locally perform the following:

A. Fill BAMT not to exceed 62 via DW-1 18 (BAMT Fill Isol Vlv)

(A-I, 1&2 BAMT Rm).

B. Start Unit I &2 BAMT AGITATOR (A-2, l&2 Chem Add Panel).

C. Place Unit I &2 BAMT HEATER switch in AUTO (A-2, I &2 Chem Add Panel).

D. WHEN Unit I &2 BAMT temperature is 127°F, THEN notify Primary Chemistry to add chemicals.

87. WHEN ready to transfer Unit I &2 BAMT to CBAST, THEN continue in this enclosure.

88. Locally perform the following (A-I, 1&2 BAMT Rm):

A. Close CA-38 (Unit 1/2 HP Boric Acid Pump Suction Tell Tale).

B. Open the following:

CA-4 (Unit 1/2 BAMT Outlet)

CA-20 (Boric Acid Hdr To CBAST)

89. 1CS-62.

90. Verify B LP Boric Acid Pump will be I. Locally start A LP Boric Acid Pump used for transfer of BAMT to CBAST. (A-2, I &2 Chem Add Panel).

2. GO TO Step 93.

Enclosure 5.4 EP/1/A/1 800/001 0 Makeup to the BWST {25} Page 25 of 37 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

91. Locally open CA-il (A/B LP BAMT Pumps Disch Tie) (A-i, 1&2 BAMT Pin).

92. Locally start B LP Bori Acid Pump (A-2, 1&2 Chem Add Panel).

93. Locally cycle DW- 119 (Boric Acid Mix Pumps Suction Fldr Flush) (A-i, 1 &2 BAMT Rm).

94. Inform all units to monitor for reactivity effects due to possible leakage of I &2 BAMT into LDST.

95. Locally perform the following (A-2, i&2 Chem Add Panel):

A. Place Unit 1&2 BAMT HEATER switch in OFF.

B. Stop Unit 1&2 BAMT AGITATOR.

96. WHEN transfer is complete, THEN locally stop the selected LP Boric Acid Pump (A-2, I &2 Chem Add Panel).

97. Locally perform the following (A-i, 1&2 BAMT Rni):

A. Close CA-4 (Unit 1/2 BAMT Outlet).

B. Open DW-l 19 (Boric Acid Mix Pumps Suction Hdr Flush).

98. Locally start previously running LP Boric Acid Pump (A-2, I &2 Chern Add Panel).

99. WHEN LP Boric Acid Pump has run for 5 minutes, THEN locally stop LP Boric Acid Pump (A-2, i&2 Chem Add Pane).

Enclosure 5.4 EP/1/A/1 800/00 1 Makeup to the BWST {251 Page 27 of 37 Q..

I - ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

]

100.Locally close the following (A-I, I&2 BAMT Rm):

CA-20 (Boric Acid Hdr To CBAST)

DW- 119 (Boric Acid Mix Pumps Suction Hdr Flush) 101._Close ICS.-62.

102._Verify B LP Boric Acid Pump was used GO TO Step 104.

for transfer of BAMT to CBAST.

103._ Locally close CA-Il (A/B LP BAMT Pumps Disch Tie) (A-I, I &2 BAMT Rm).

104._Locally open CA-38 (Unit 1/2 HP Boric Acid Pump Suction Tell Tale) (A-I, I&2 BAMT Rm).

I 05._ Verify quantity of boron needed for 1. Notify Primary Chemist of volume transfer to I B BHUT is available in the removed from Unit I &2 BAMT.

CBAST without going below minimum SLC required for CBAST. 2 GO TO Step 86 l0&_Open 1CS-64.

107._Start IA CBAST PUMP.

I 08._ Inform all units to monitor for reactivity effects due to possible leakage of CBAST into LDST.

I 09.Notify Primary Chemist of the following:

Volume removed from Unit I &2 BAMT To sample Unit I CBAST for boron.

I I 0_ WHEN boron addition to I B BHUT is desired, THEN close ICS-56.

111. Close 1CS-51.

Enclosure 5.4 EP/lfA/1 800/001 Makeup to the BWST {25) Page 29 of 37 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 12.Localiy perform the following (A-i, Bleed Transfer Pump Rm):

A. Close 1CS-149 (Bleed Tank lB Outlet Block).

B. Open 1CS-58 (Bleed Tank lB Recirculation).

C. Open ICS-60 (Bleed Transfer Pump lB Suction Tie).

I 13._Locally open ICS-66 (CBAST Tie To Bleed Transfer Pumps) (A-I hallway, 8 S of column 65 at CBAST).

114._Open 1CS-64.

I 15. Start lB BLEED TRANSFER PUMP.

1 16. Monitor the following for unexpected level changes:

IABHUT

Unit I LDST

. Unit I CBAST I I 7._ IAAT unexpected level changes occur in GO TO Step 121.

Unit I tanks (IA BHUT, LDST, CBAST),

THEN GO TO Step 118.

11 8. Stop lB BLEED TRANSFER PUMP.

I I 9. Determine and correct cause of unexpected level change.

120._GO TO Step 81.

121. WHEN CBAST addition to 1 B BHUT is complete, THEN stop lB BLEED TRANSFER PUMP.

Enclosure 5.4 EP/1/AI1 800/001 Makeup to the BWST Page 31 of37 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 22._ Locally close I CS-66 (CBAST Tie To Bleed Transfer Pumps) (A-i hallway, 8 S of column 65 at CBAST).

123. Locally perform the following (A-i, Bleed Transfer Pump Rm):

A. Close I CS-60 (Bleed Transfer Pump lB Suction Tie).

B. Open ICS-149 (Bleed Tank lB Outlet Block).

124._Verify DW addition to lB BHUT GO TO Step 136.

required.

125._Ensure space is available in Waste Gas Tanks.

126._Locally open IDW-174 (Bleed 1loldup Tank Supply) (A-I, hallway S of freight elevator).

127._Locally throttle ICT-88 (lB BHUT Condensate Supply) as necessary to control flow and minimize vent header pressure (A-I, N wall of Unit I BTP Rm).

I 28._ Monitor the following for unexpected level changes:

IABHUT

Unit 1 CBAST 129._Notify Unit 2 to monitor the following for unexpected level changes:

. 2ABHUT

. 2B BHUT

Unit 2 CBAST

Enclosure 5.4 EP/1/AIl 800/001 Makeup to the BWST Page 33 of 37 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 130._IAAT unexpected level changes occur in GO TO Step 134.

Unit 1, OR Unit 2 BHUTs or CBASTs, THEN GO TO Step 131.

131. Locally close 1 DW- 174 (Bleed Holdup Tank Supply) (A-I, hallway S of freight elevator).

I 32._ Determine and correct cause of unexpected level change.

133. GO TO Step 124.

134. WHEN DW addition to lB BHUT is complete, THEN continue in this enclosure.

I 35.Locally close the following:

0 IDW-174 (Bleed Holdup Tank Supply)

(A-i, hallway S of freight elevator)

ICT-88 (lB BHUT Condensate Supply)

(A-l,NwallofUnit I BTPRm) 136. Start lB BLEED TRANSFER PUMP.

137. Locally throttle I CS-58 to obtain 90-1 10 psig discharge pressure on I B BLEED TRANSFER PUMP (A-I, Bleed Transfer Pump Rm).

138. WHEN lB BHUT has been in recirc for 1/2 hour, THEN notify Primary Chemistry to obtain I B BHUT boron sample.

139._ WHEN lB BHUT sample results are available, THEN continue in this enclosure.

I 40. Verify I B BHUT boron is within COLR GO TO Step 81.

limits for BWST boron requirements.

Enclosure 5.4 EP/1/A/1 800/00 1 Makeup to the BWST {25} Page 35 of 37 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAiNED 141._ IAAT all the following conditions exist: GO TO Step 147.

1A BHUT NOT being transferred to BWST Makeup to BWST required THEN perform Steps 142 - 146.

142.Ensure NONE of the following are in recirc:

Unit I BWST Unit 2 BWST l&2SFP 143.Locally open the following:

I CS-96 (Spent Fuel IX (Rinse) Block)

(A-2, around corner from Caustic Add Pump)

LWD-156 (SF IX Sluice)

(Rm 218, SF Cooler Rm) 144._Open ICS56.

145. Start lB BLEED TRANSFER PUMP.

I 46. Locally throttle SF-47 (SF Filter Outlet To Unit I BWST) based on the following (Rrn 218, SF Cooler Rrn):

. BWST < 46 maintain desired flow

. BWST 46 maintain flow

- < 50 gpm I 47._ IAAT makeup from I B BHUT to GO TO Step 151.

BWST is in progress, AND py of the following conditions exist:

BWST makeup NO longer required 1BBHUT1eveI 15 lB BLEED TRANSFER PUMP stopped due to low level in lB BHUT THEN perform Steps 148 - 150.

Enclosure 5.4 EP/1/AI1 800/001 Makeup to the BWST Page 37 of 37 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 148._Stop lB BLEED TRANSFER PUMP.

149._Close 1CS-56.

150.Locally close the following:

ICS-96 (SpentFuel TX (Rinse) Block)

(A-2, around corner from Caustic Add Pump)

LWD-156 (SF IX Sluice)

(Rm 218, SF Cooler Rm)

SF-47 (SF Filter Outlet To Unit 1 BWST) (Rm 218, SF Cooler Rm)

NOTE Preparations for mixing another batch in IA BHUT can be made while 1 A BEUT is being transferred to the BWST. If another batch will be necessary, returning to Step I will direct actions to mix a boron batch in the BAMT for transfer to CBAST if the CBAST does NOT contain sufficient volume for boron addition to I A BHUT. This should minimize the time between batches from IA BHUTto the BWST.

151 ._ IAAT preparations for mixing another batch in IA BHUT is desired, THEN GO TO Step 1.

I 52._ WHEN makeup operations to the BWST are complete, THEN notify RP of completion.

153.Perform the following:

A. Remove TIO sheet tag from I HP-16 control switch.

B. Do not operate ll-IP-16 from T/O sheet.

154. EXIT this enclosure.

Admin-124 Ri Page 1 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-1 24 Determine Minimum Shift Staffing CANDIDATE EXAMINER

Admin-124 Ri Page 2 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Determine MINIMUM staffing requirements for the shift for NEOs, ROs and SROs Alternate Path:

NO Facility JPM #:

ADM IN-i 24 K/A Rating(s):

K/A Gen 2.1.4 Rating 3.3/3.8 Task Standard:

SLC 16.13.1-1 (Minimum Station Staffing Requirements) is used to correctly determine MINIMUM staffing requirements for the shift.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Classroom X Perform X Simulate

References:

SLC 16.13.1-1 (Minimum Station Staffing Requirements)

Validation Time: 15 mm. Time Critical: NO Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner:

/

NAME SIGNATURE DATE Comments

Admin-124 Ri Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin-124 Ri Page 4 of 9 Tools/Equipment/Procedures Needed:

SLC 16.13.1-1 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS

Unit 1 = 100% power

Unit2 73%

> 2A HPI Pump tagged out for the last 4 days

Unit3 = REQ Core off-load in progress

2 on-shift NEOs are qualified as Fire Brigade Leader

No other station groups have qualified fire brigade members INITIATING CUE What are the MINIMUM staffing requirements using the MINIMUM number of licensed personnel for the shift?

Position Minimum Number OSM STA SRO RO NLO SPOC N/A Chemistry Technician NIA RP Technician N/A

Admin-124 Ri Page 5 of 9 START TIME:

STEP 1: Reference SLC 16.13.1 STANDARD: Reference SLC 16.13.1-1 table SAT COMMENTS:

UNSAT STEP 2: Reference SLC 16.13.1-1 Table for plant conditions SAT STANDARD: Determine correct table column to be used:

Column for 2 units in MODE 1-4 from one control room based on:

UNSAT

. Unit 1 is in MODE 1 at 100%

. Unit 2 is in MODE 1 at 73% with 2A HPIP OOS for the last 4 days

. Unit 3 is in a RFO; core off-load in-progress COMMENTS:

STEP 3: Determine correct number from column for 2 units in MODE 1-4 from one control room STANDARD: 1 OSM, 1 STA, 4 SRO, 5 RO, and 8 NEO SAT COMMENTS:

UNSAT STEP 4: Determine that an available NEO is fire brigade leader qualified STANDARD: 2 on-shift NEOs are qualified as fire brigade leader SAT COMMENTS:

U NSAT

Admin-124 Ri Page 6 of 9 STEP 5: Adjust SRO and NEO staffing numbers per Step 4 STANDARD: Subtract 1 SRO based on NEO qualified as fire brigade leader:

SAT 1 OSM, 1 STA, 3 SRO, 5 RO, and 9 NEO COMMENTS:

UNSAT STEP 6: Reference TS 3.5.2.B STANDARD: Determine that TS 3.5.2.B is applicable:

2A HPIP OOS for> 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SAT COMMENTS:

UNSAT STEP 7: Adjust RO staffing numbers per Step 6 STANDARD: Add 1 RO based on TS 3.5.2.B applying 1 OSM, 1 STA, 3 SRO, 6 RO, and 9 NEO SAT COMMENTS:

UNSAT STEP 8: Adjust NEO staffing numbers per Step 6 STANDARD: Add 2 NEOs based on TS 3.5.2.B applying 1 OSM, 1 STA, 3 SRO, 6 RO, and 11 NEO SAT COMMENTS:

UNSAT

Admin-124 Ri Page 7 of 9 STEP 9: Adjust SRO staffing numbers due to core off-load in progress STANDARD: Add 2 SROs based on CORE ALTERATIONS in progress 1 OSM, 1 STA, 5 SRO, 6 RO, and 11 NEO SAT COMMENTS:

UN SAT STEP 10: Determine total staffing requirements CRITICAL STEP STANDARD: I OSM, I STA, 5 SRO, 6 RO, and II NEO SAT Position Minimum Number OSM UNSAT STA I SRO 5 RO 6 NLO II SPOC N/A Chemistry Technician N/A RP Technician N/A COMMENTS:

END OF TASK TIME STOP:

Admin-124 Ri Page 8 of 9 CRITICAL STEP EXPLANATIONS STEP # Explanation 10 Determine staffing requirements

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

Uniti =100% power

Unit2 = 73%

> 2A HPI Pump tagged out for the last 4 days

Unit3 = RFO

> Core off-load in progress

2 on-shift NEOs are qualified as Fire Brigade Leader

No other station groups have qualified fire brigade members INITIATING CUE What are the MINIMUM staffing requirements using the MINIMUM number of licensed personnel for the shift?

Position Minimum Number OSM STA SRO RO NLO SPOC NIA Chemistry Technician NIA RP Technician NIA

Minimum Station Staffing Requirements 16.13.1 16.13 CONDUCT OF OPERATIONS 16.13.1 Minimum Station Staffing Requirements COMMITMENT a. Minimum station staffing shall be as indicated in Table 16.13.1-1 and shall meet the following additional requirements:

1. At least one RO per unit shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODES 1, 2, 3, or 4, at least one licensed SRO shall be present in the control room.

2. At least one licensed operator shall be in the reactor building when fuel handling operations in the reactor building are in progress. In addition, during CORE ALTERATIONS including fuel loading and transfer, an SRO or an SRO limited to fuel handling shall be present to directly supervise the activity and, during this time, shall not be assigned to other licensed activities

3. If the computer for a reactor is inoperable for more than eight hours, an operator, in addition to those specified in ITS 5.2.2.b and 10 CFR 50.54(m) shall supplement the control room staff.

b. The Shift Technical Advisor shall be an experienced SRO.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements for A.1 Restore minimum station 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months minimum station staffing levels.

staffing not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.13.1.1 N/A N/A 16.13.1-1 05/13/04

Minimum Station Staffing Requirements 16.13.1 Table 16.13.1-1 MINIMUM STATION STAFFING REQUIREMENTS THREE UNITS TWO UNITS IN TWO UNITS IN ONE UNIT IN THREE UNITS IN MODES 1-4 MODES 1-4 MODES 1-4 MODES 1 -4 IN MODES 5 OR CONTROLLED CONTROLLED 6 OR NO MODE FROM TWO FROM ONE CONTROL CONTROL ROOMS ROOM OSM 1 1 1 1 1 STA 1 1 1 1 1 1

SRO 5 5 4 4 3 3

R0 6 5 5 4 3 2

1 NLO 8 8 8 8 7 SPOC 7 7 7 7 6 Chemistry Technician 1 1 1 1 1 RP Technician 3 3 3 3 3 1 SRD number can be reduced by one when a qualified NLO is designated the fire brigade leader. The NLO number must be increased by one, or one fire brigade member must be supplied from another organization.

2 NLO number must be increased by two when in ITS 3.5.2 Condition B.

3 RO number must be increased by one when in ITS 3.5.2 Condition B.

16.13.1-2 05/13/04

Minimum Station Staffing Requirements 16.13.1 BASES Some of the requirement(s) of this SLC section were relocated from TS 6.1.1.9 and TS Table 6.1-1 during the conversion to ITS. These requirements were initially relocated to SLC 16.13.5, Additional Operating Shift Requirements, dated 3/27/97.

The requirements of this SLC consolidate ONS station staffing requirements into one document. This SLC includes the shift manning requirements of ITS 5.2.2, 10 CFR 50 Appendix R Section lII.H, 10 CFR 50.54.m, Operations Management Procedures (OMPs), NSD 112, and the Emergency Plan. This SLC also includes the old requirements of SLC 16.13.1, Fire Brigade, dated 3/27/99 and SLC 16.13.5; Additional Operating Shift Requirements dated 3/27/99. The numbers for each position per shift are additive. For example, Table 16.13.1-1 requires a total of 5 SROs per shift (3 SROs required by 10 CFR 50.54(m)(2)(i) plus 1 additional SRO for the Fire Brigade and 1 additional for the ERO). The bases for the numbers in the first column of SLC Table 16.13.1-1 are as follows:

1 OSM (active SRO) Required by 50.54(m)(2)(ii) (implemented by OMP).

1 STA (active or inactive SRO) Required by ITS 5.2.2.g which indicates the individual fulfilling the STA position is the Shift Work Manager (implemented by OMP). Revision 50 to OMP 2-1 renamed the person fulfilling this position an STA. Note that pre-conversion TS Table 6.1-1, which implemented NUREG-0737 requirements, did not require an STA on shift when no units were in MODES 1-4. The SLC Table is more restrictive in that it requires an STA on shift at all times.

3 SROs (active SRO) Required by 10 CFR 50.54(m)(2)(i). Per ITS 5.2.2.b and 10 CFR 50.54(m)(2)(iii) at least 2 SROs must be in the control room.

1 SRO (active or inactive) or NLO Required by Appendix R Section III.H.

- Fire Brigade Implemented by OMP and NSD. Individual fulfilling position shall be a SRO or an NLO who is qualified to be a fire brigade leader. Per OMP this individual functions as fire brigade leader and is not available for control room activities when directing the fire brigade. Appendix R does not specify that the brigade leader be an SRO, it only specifies that the fire brigade leader have sufficient training in or knowledge of plant safety-related systems to understand the effects of fire and fire suppression systems on safe shutdown capability. When an 16.13.1-3 05/13/04

Minimum Station Staffing Requirements 16.13.1 NLO is serving as the fire brigade leader, the SRO number for each column in Table 16.13.1-1 may be reduced by one.

1 SRO (licensed or previously Required by Volume A, Section B, Figure B-2 of licensed) ERO the Emergency Plan. Implemented by OMP. SRO serves as the offsite communicator and the NRC communicator in the CR/TSC. This is permissible since the offsite communicator role is completed prior to the NRC communicator role starting.

5 ROs Required by 10 CFR 50.54(m)(2)(i).

1 RO - SSF Required by ITS 5.2.2.h, implemented by OMP.

Per ITS 5.2.2.h, the manpower necessary to operate the SSF will be exclusive of the fire brigade and the minimum operating shift that is required to be present in the Control Room. ITS 5.2.2.b andlO CFR 50.54(m)(2)(iii) require 3 of the 5 ROs required by 10 CFR 50.54(m)(2)(i) to be present in the control room when fuel is in the reactor. When all three units are in MODES 1-3, one RO per unit must be available to be dispatched to the SSF.

Since 3 ROs must be present in the Control Room only two are available to dispatch to the SSF.

Therefore, one additional RO, beyond what is required by 10 CFR 50.54(m)(2)(i), is required.

1 RO - ADV Amendment 314, 314, 314 requires that staffing level be increased by an additional RO beyond what is required in Table 16.13.1-1 when in Condition B of ITS 3.5.2. The additional RO is designated to respond to an event requiring activation of the SSF for the unit operating under ITS 3.5.2 Condition B. The additional RO role may be fulfilled by an SRO as long as the SRO is not being counted towards the number of required SROs listed in Table 16.13.1-1 and is qualified to tasks involving operation of the SSF systems.

When all three units are in MODES 1-4, a total of seven ROs are required; five per 10 CFR 50.54(m)(2)(I), one per ITS 5.2.2.h, and one per ITS 3.5.2 Condition B.

8 NLOs Required by 10 CFR 50 Appendix R Part III.H, ITS 5.2.2.a, Volume A, Appendix 8, Spill Prevention 16.13.1-4 05/13/04

Minimum Station Staffing Requirements 16.13.1 and Control and Counter Measures Plan, Revision 98-04, 10/98 of the Emergency Plan, and Volume A, Section B, Figure B-8 of the Emergency Plan.

Implemented by OMP. (Four for fire brigade, one NLO per Unit to complete critical AP and EOP actions and 1 for SSF equipment verification for the design basis Appendix R fire.) When an NLO is serving as the fire brigade leader, the NLO number for each column in Table 16.13.1-1 must be increased by one or one fire brigade member must be supplied from another organization.

The number of NLOs that are fire brigade qualified may be reduced provided that a like number of fire brigade qualified personnel are provided from other organizations. This does not change the total number of NLOs required; only the number required to be fire brigade qualified.

2 NLOs ADV License Amendment 314, 314, 314 requires that staffing levels be increased by an additional two NLOs beyond those required in Table 16.13.1-1 when in Condition B of ITS 3.5.2. The additional NLOs are designated for the purpose of operating the Atmospheric Dump Valves (ADV5) for the unit under ITS 3.5.2 Condition B. In addition, the NLOs with the responsibility for operating the ADVs will be designated to respond to the control room within five minutes and will not be given duties that will prevent this from happening.

7 SPOC Required by Volume A, Section B, Figure B-8 of the Emergency Plan and the Fire Plan (Volume A, Appendix 8, Spill Prevention and Control and Counter Measures Plan, Revision 98-04, 10/98).

Implemented by OMP 1-7 and NSD 112. Consists of two I&E technicians ERO qualified and knowledgeable of IP/0/A0050/003 (Power SSF Submersible Pump), two MM technicians ERO qualified and knowledgeable of MP/0/A11300/059 (Install SSF Submersible Pump), one supervisor or temporary supervisor qualified to establish the 050 and perform the OSC Maintenance Supervisor functions, and one additional person to help with pump installation as directed by SPOC supplied by one of the following groups in the order 16.13.1-5 05/13/04

Minimum Station Staffing Requirements 16.13.1 listed: SPOC, other maintenance personnel onsite, C&F, Chemistry, RP and Maintenance Overtime resources. Security will automaticafly supply one Security Guard to open doors and gates who will also assist with any maintenance activities to be performed. The Security Guard is counted as one of a total of 6 people needed to install the submersible pump. One other person is needed to establish the OSC for a total of 7. In the event of a fire, SPOC will respond to the fire until directed to install the submersible pump. A total of 5 SPOC personnel are assigned to the fire brigade. Per PIP 4-099-2987 problem evaluation, it is acceptable to consider these additional 5 Fire Brigade members to be available for other duties, such as installation of the SSF pump. This is based on Oconee Fire Brigade Guide #2, which contains guidance that allows fire brigade members to be released from the brigade for operational needs at the discretion of the OSC/TSC.

The number of SPOC personnel qualified as fire brigade members may be reduced, provided that the qualified fire brigade members from other organizations are increased by a like number. This does not change the total number of SPOC personnel required, only the number required to be fire brigade qualified.

1 Chemistry Technician - ERO Required by Volume A, Section B, Figure B-8 of the Emergency Plan. Implemented by OMP and Station Chemistry Manual 2.6. A Chemistry Technician who is fire brigade qualified may be credited toward fulfilling the ERO requirement and the fire brigade requirement. In the event of a fire, the Chemistry technician will respond to the fire until directed otherwise.

3 RP Technicians Three are required by Volume A, Section B, Figure B-8 of the Emergency Plan. One is required by ITS 5.2.2.d and may be counted towards fulfilling the ERO requirement. Implemented by HPIOIBI1 000/054. RP technicians who are fire brigade qualified may be credited toward fulfilling the ERO and TS requirements and the fire brigade requirement. In the event of a fire, the RP 16.13.1-6 05/13/04

Minimum Station Staffing Requirements 16.13.1 technician will respond to the fire until directed otherwise.

Minimum Station Staffing numbers for the SRO and RO positions in Table 16.13.1-1 change as a function of the number of units in MODES 1-4 and whether the operating Units are controlled from one or two Control Rooms. The number for the remaining positions in Table 16.13.1-1 is not affected by operational condition of the units.

10 CFR 50.54(m)(2)(i) requires 3 SROs when two units are in MODES 1-4 and controlled from two Control Rooms, 2 SROs when two units are in MODES 1-4 and controlled from a common control room, 2 SROs when one unit is MODES 1-4 and 1 SRO when no units are MODES 1-4. Thus considering fire brigade and ERO requirements, this results in the requirement for 5 SROs when two units are in MODES 1-4 and controlled from two Control Rooms, 4 SROs when two units are in MODES 1-4 and controlled from a common control room, 4 SROs when one unit is MODES 1-4 and 3 SROs when no units are MODES 1-4.

10 CFR 50.54(m)(2)(i) requires 5 ROs when two units are in MODES 1-4 and controlled from two Control Rooms, 4 ROs when two units are in MODES 1-4 and controlled from a common control room, 4 ROs when one unit is MODES 1-4 and 3 ROs when no units are MODES 1-4. OMPs require 2 ROs to man the SSF when two units are in MODES 1-3 and 1 RO when one unit is MODES 1-3. None are required when no units are in MODES 1-3.

Therefore, no additional ROs are required beyond what is required by 10 CFR 50.54(m)(2)(i) when less than three units are in MODES 1-3 with one exception. When two units are in MODES 1-3 and controlled from one Control Room one additional RO is required since 10 CFR 50.54(m)(2)(i) only requires 4 ROs when the two operating units (Units 1 and 2) are controlled from one control room. Since one RO (or SRO) must be present in the Control Room when fuel is in the reactor vessel, the two ROs required to man the SSF for the operating units are exclusive of the one RO required for each unit.

Therefore, a total of 5 ROs are required for this configuration.

The minimum staffing number for the SPOC and NLO positions is reduced by one when all three units are in MODE 4 or below. This reduction is allowed since the SSF is not required to be OPERABLE in these MODES. Therefore, there is no need for SPOC to provide a qualified individual to establish the OSC and no need for an NLO to perform SSF equipment verification.

SLC 16.13.1.a.1 requires at least one RO per unit to be present in the control room when fuel is in the reactor and one SRO to be present in the control room while in MODES 1-4. This requirement is based on 10 CFR 50.54(m)(2)(iii) and ITS 5.2.2.b. The first part of SLC 16.13.1 .a.2, which requires at least one licensed operator to be in the reactor building when fuel handling operations in the reactor building were in progress, was relocated during the ITS conversion from TS Table 6.1-1, Additional Requirement 3. This requirement has existed since the initial issuance of Oconee Technical Specifications. The second part of SLC 16.13.a.2, which requires that a SRO or an SRO limited to fuel handling activities be present to directly supervise CORE ALTERATIONS including fuel loading or transfer and be assigned no other duties, is based on 10 CFR 50.54(m)(2)(iv). SLC 16.13.1.a.3 which requires an operator, in 16.13.1-7 05/13/04

Minimum Station Staffing Requirements 16.13.1 addition to those specified in ITS 5.2.2.b to supplement the control room staff if the computer for a reactor is inoperable for more than eight hours, was relocated during the ITS conversion from TS Table 6.1-1, Additional Requirement 6. This requirement has also existed since the initial issuance of Oconee Technical Specifications. SLC 16.13.1.b, which specifies the STA shall be an experienced SRO was relocated during the ITS conversion from TS 6.1.1.9.

The primary purpose of the Fire Protection Program is to minimize both the probability and consequences of postulated fires. Despite designed active and passive Fire Protection Systems installed throughout the plant, a properly trained and equipped Fire Brigade organization of at least ten (Reference 8) members is needed to provide immediate response to fires that may occur at the site. This number is the result of a corrective action from Reference

10. This Fire Brigade requirement is normally met by using one SRO (or NLO qualified to be a fire brigade leader), 4 NLOs, and 5 SPOC personnel. However, this requirement can also be met by using personnel from other organizations (e.g., Chemistry, Radiation Protection, and Security).

Fire Brigade equipment and training conform to Oconees commitments to Appendix A to Branch Technical Position 9.5-I and supplemental NRC Staff guidelines including Nuclear Plant Functional Responsibilities, Administrative Controls and Quality Assurance.

This SLC is part of the Oconee Fire Protection Program and therefore subject to the provisions of Oconee Facility Operating License Conditions.

The following requirement was relocated from the TS 6.1.1.8 during the conversion to ITS. A training program for the fire brigade shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except that training sessions may be held quarterly.

ACTIONS Ai With the requirements for minimum station staffing not met, the minimum station staffing levels shall be restored within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time is consistent with ITS 5.2.2.c and d which allows 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to accommodate unexpected absence of on-duty shift crew members provided that immediate action is taken to restore the shift crew composition to within the minimum requirements.

REFERENCES:

1. Oconee UFSAR, Chapter 9.5.1.

2. Oconee Fire Protection SER dated August 11, 1978.

3. Oconee Fire Protection Review, (currently contained in the Fire Protection DBD) as revised.

4. Duke letter of January 16, 1978 to NRC in response to Nuclear Plant Functional Responsibilities, Administrative Controls, and Quality Assurance.

5. ITS 5.2.2, Amendment 300/300/300.

16.13.1-8 05/13/04

Minimum Station Staffing Requirements 16.13.1

6. 10 CFR 50.54(m).

7. Emergency Plan, Volume A, Section B, Figure B-8, Revision 97-01, 7/97.

8. Emergency Plan, Volume A, Appendix 8, Spill Prevention and Control and Counter Measures Plan, Revision 98-04, 10/98.

9. Station Chemistry Manual 2.6.

10. Problem Investigation Report Serial No. 1-089-0001.

11. Problem Investigation Process (PIP) Serial No. 4-099-2987.

12. ITS 3.5.2, Amendment 314/314/314.

13. NRC Regulatory Issue Summary (RIS) 2002-16, Current Incident Response Issues.

14. PIP 0-03-0233 16.13.1-9 05/13/04

HPI 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 High Pressure Injection (HPI)

LCO 3.5.2 The HPI System shall be OPERABLE with:

a. Two HPI trains OPERABLE;

b. An additional HPI pump OPERABLE;

c. Two LPI-HPI flow paths OPERABLE;

d. Two HPI discharge crossover valves OPERABLE;

e. HPI suction headers cross-connected; and

f. HP I discharge headers separated.

APPLICABILITY: MODES 1 and 2, MODE 3 with Reactor Coolant System (RCS) temperature

> 350°F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One HPI pump A.1 Restore HPI pump to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

OR AND One or more HPI A.2 Restore HPI discharge 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months discharge crossover crossover valve(s) to valve(s) inoperable. OPERABLE status.

(continued)

OCONEE UNITS 1, 2, & 3 3.5.2-1 Amendment Nos. 314, 314, & 314

HPI 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated POWER to 75% RTP.

Completion Time of Condition A not met. AND B.2 Verify by administrative 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months means that the ADV flow path for each steam generator is OPERABLE.

AND B.3 Restore HPI pump to 30 days from initial entry OPERABLE status. into Condition A AND B.4 Restore HPI discharge 30 days from initial entry crossover valve(s) to into Condition A OPERABLE status.

(continued)

OCONEE UNITS 1, 2, & 3 3.5.2-2 Amendment Nos. 314, 314, & 314

HPI 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One HPI train Ci NOTE inoperable. Only required when inoperable HPI train is incapable of automatic actuation and incapable of actuation through remote manual alignment.

Reduce THERMAL 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months POWER to 75% RTP.

AND C.2 NOTE Only required when THERMAL POWER 75% RTP.

Verify by administrative 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months means that the ADV flow path for each steam generator is OPERABLE.

AND C.3 Restore HPI train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

D. HPI suction headers D.1 Cross-connect HPI 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months not cross-connected. suction headers.

E. HPI discharge E.1 Hydraulically separate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months headers cross- HPI discharge headers.

connected.

(continued)

OCONEE UNITS 1, 2, & 3 3.5.2-3 Amendment Nos. 314, 314, & 314

HPI 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One LPI-HPI flow F.1 Restore LPI-HPI flow 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months path inoperable, path to OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of AND Condition B, C, D, E, or F not met. G.2 Reduce RCS 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months temperature to 350°F.

H. Two HPI trains H.1 Enter LCO 3.0.3. Immediately inoperable.

OR Two LPI-HPI flow paths inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify each HPI manual and non-automatic 31 days power operated valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.2 NOTE Not applicable to operating HPI pump(s).

Vent each HPI pump casing. 31 days (continued)

OCONEE UNITS 1, 2, & 3 3.5.2-4 Amendment Nos. 314, 314, & 314

HPI 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify each HPI pumps developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing Program required developed head.

SR 3.5.2.4 Verify each HPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.5 Verify each HPI pump starts automatically on 18 months an actual or simulated actuation signal.

SR 3.5.2.6 Verify, by visual inspection, each HPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet strainers show no evidence of structural distress or abnormal corrosion.

SR 3.5.2.7 Cycle each HPI discharge crossover valve and 18 months LPI-HPI flow path discharge valve.

OCONEE UNITS 1, 2, & 3 3.5.2-5 Amendment Nos. 348, 350, & 350

ADMIN 212 Ri Page 1 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-21 2 DETERMINE LTOP REQUIREMENTS CANDIDATE EXAMINER

ADMIN 212 Ri Page 2 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Determine LTOP Requirements Alternate Path:

No Facility JPM #:

MODIFIED K/A Rating(s):

System: 001 K/A: Gen2.2.14 Rating: 3.9/4.3 Task Standard:

Per OP/i /A/1104/049, Low Temperature Overpressure Protection, based on conditions provided and plant knowledge determine if LTOP requirements are being met.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Classroom X Perform X Simulate

References:

Validation Time: 30 mm Time Critical: NO Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time:

Examiner: I NAME SIGNATURE DATE COMMENTS --

ADMIN 212 Ri Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS NONE

ADMIN 212 Ri Page 4 of 12 Tools/Equipment/Procedures Needed:

-Attachment listing current plant conditions

-Working copy of OP/1/A!1104/049, LTOP, End. 4.13 ([TOP Requirements Logic Diagram)

READ TO OPERATOR DIRECTION TO TRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet provided.

INITIAL CONDITIONS Unit 1 controlling procedure for unit shutdown and cooldown is in progress for entering a refueling outage. Plant conditions are as described in the attachment provided.

INITIATING CUES Based on the conditions described above and by using any associated plant procedures, verify that [TOP requirements are being met per the provided End. 4.13 (LTOP Requirements Logic Diagram) of OP/i /A/1104/049 (Low Temperature Overpressure Protection).

If not being met, then list all the [TOP requirements that ULTIMATELY result in [TOP not being met. If any requirements are NOT being met, THEN document by listing on the provided copy of

[TOP Requirements Logic Diagram End. 4.13 of OP/I/All 104/049, [TOP.

ADMIN 212 Ri Page 5 of 12 START TIME:

STEP 1:

LTOP (HPI) Verify HPI deactivated per OP/i/Al 1104/049 (LTOP). SAT STANDARD: Refers to OP!1/A11i04/049 (LTOP) End. 4.13 and attachment and U NSAT determines that HPI is deactivated.

COMMENTS:

CRITICAL STEP STEP 2:

LTOP (CFT) Verify each CFT isolated per OP/i/All i04/049 (LTOP) when SAT CFT pressure 373 psig.

STANDARD: Determines from attachment that Core Flood Tanks (CFTs) are NOT UNSAT isolated in that:

1. lB CFT pressure is 375 psig (>373 psig) and

2. 1CF-2 is Closed with handwheel tagged BUT breaker NOT tagged open COMMENTS:

STEP 3:

LTOP (Pzr Level) SAT Verify Pzr level within LTOP limits per heatup/cooldown curves in OP/0/N1 108/OOi (Curves And General Information).

UNSAT STANDARD: Determines that Pzr Level is within limits; Pzr Level must be <220 inches. It is currently 218 inches.

COMMENTS:

ADMIN 212 Ri Page 6 of 12 STEP 4:

LTOP (Pressurizer Heater Bank 3 or 4)

Verify Pressurizer Heater Bank 3 OR 4 white tagged open per OP/i/Ni 104/049 (Low Pressure Overpressure Protection (LTOP). SAT STANDARD: Determines from attachment that Bank 4 Heaters are white tagged open. UNSAT Either Bank 3 or 4 heaters being deactivated meets requirements.

COMMENTS:

STEP 5:

LTOP (1RC-4)

Verify 1 RC-4 open when PORV is required to be operable. SAT STANDARD: 1 RC-4 is open when PORV required to be operable UNSAT COMMENTS:

STEP 6:

LTOP (1RC-4)

Verify 1 RC-4 open when the following conditions are met:

PORV removed SAT

1 RC-4 installed

1 RC-4 part of LTOP vent path UNSAT STANDARD: Verifies 1 RC-4 is open; but none of the above conditions require 1 RC-4 to be open COMMENTS:

ADMIN 212 Ri Page 7 of 12 STEP 7:

LTOP (RC Pressure) SAT Verify RCS < 525 psig when RCS > 220°F and 325°F.

OR Verify RCS <375 psig when RCS 220°F.

UN SAT STANDARD: Determines RC Pressure to be within limits COMMENTS:

STEP 8:

LTOP (RC Makeup Flow)

Verify 1 HP-120 travel stop operable per OP/i/Ni 104/049 (LTOP) SAT or HPI Pumps NOT capable of starting and injection into RCS via 1 HP-120.

STANDARD: 1HP-120 Travel Stop operable UNSAT COMMENTS:

STEP9: -Page9-SR 3.4.12.6 LTOP (OAC Alarms) SAT NOTE: The 225 Pressurizer Level Computer alarm is included in this check.

Verify 01 L31 53 NOT in alarm AND OAC operable. UNSAT IF 01 L31 53 in alarm, evaluate LTOP input points valid by using LTOP OAC Screen.

Refer to OP/1/N1104/049 (Low Temperature Overpressure Protection (LTOP).

STANDARD: Per Attachment, computer point is not in alarm (Pzr Level is <225 so the alarm is not actuated.)

COMMENTS:

ADMIN 212 Ri Page 8 of 12 STEP 10: SR 3.4.12.6 LTOP (OAC Alarms) (260 Pressurizer Level Computer alarm.)

Verify the following: SAT 1SA-2/C-3 RC Pressurizer Level High/Low Statalarm card NOT Pulled.

IF Either iSA/i 8/A-3 OR iSA/i 8/A-4 is in alarm OR card pulled, THEN verify the following Computer Point status: UNSAT

01X2256 Quality = GOOD Value = FALSE

OiX2274 Quality GOOD Value = FALSE

O1X2285 Quality = GOOD Value = FALSE STANDARD: Per attachment, SA Cards are not pulled and not in alarm COMMENTS:

STEP ii: SR 3.4.12.6 CRITICAL STEP LTOP (OAC Alarms) (315Pressurizer Level Computer alarm)

Verify 1 SA-2/C-4 RC Pressurizer Level Emerg High/Low Statalarm card SAT NOT Pulled.

UNSAT STANDARD: Determines per attachment, SA card is IS PULLED COMMENTS:

ADMIN 212 Ri Page 9 of 12 STEP 12: SR 3.4.12.6 CRITICAL STEP LTOP (HP Nitrogen System)

Verify 1N-121 white tagged closed per OP/i/All 104/049 (LTOP). SAT STANDARD: Determines per attachment that 1 N-i 21 is closed but NOT white tagged. UNSAT COMMENTS:

STEP 13: End. 4.13 LTOP (Logic Diagram) CRITICAL STEP Verify LTOP requirements met per Enclosure LTOP Requirements Logic Diagram of OP/i/Ni 104/049 (LTOP).

SAT STANDARD: Determines from the Logic diagram and the attachment that LTOP surveillance requirements are NOT satisfied due to 6 items in that:

1 B CFT is NOT isolated due to its breaker not tagged open UNSAT

1 B CFT pressure is 375 psig (must be less than 373 psig)

1SA-2/C4 alarm card is pulled (must be installed with no HIGH alarm)

1N-12i is closed but NOT tagged closed

No dedicated LTOP operator is assigned

LTOP vent or Pzr Relief standpipe (valve removed or greater vent path) is NOT established Candidate may list items such as the following that are LTOP gy requirements not surveillance requirements. These shall not be counted as part of the required answers and are annotated as such on the provided End. 4.13:

Tc<325°F

RV Head Off / or SG Primary Manway Off / or Pzr Manway Off NOTE: Incorrectly listing a reason(s) that satisfies LTOP requirements or does NOT ultimately result in requirements not being met will be counted towards overall unsatisfactory completion of the task.

COMMENTS:

END OF TASK STOP TIME:

ADMIN 212 Ri Page 10 of 12 CRITICAL STEP EXPLANATIONS STEP # Explanation 2 Requires determination of lB CFT NOT being isolated or depressurized 11 Requires determination that 1 SA-2/C4 alarm card is pulled (must be installed with no HIGH alarm) 12 Requires determination that 1 N-121 is closed but NOT tagged closed 13 Requires determination that:

No dedicated LTOP operator is assigned

LTOP vent or Pzr Relief stand pipe (valve removed or greater vent path) is NOT established

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 controlling procedure for unit shutdown and cooldown is in progress for entering a refueling outage. Plant conditions are as described in the attachment provided.

INITIATING CUES Based on the conditions described above and by using any associated plant procedures, verify that LTOP requirements are being met per the provided End. 4.13 (LTOP Requirements Logic Diagram) of OPI1IA/1104/049 (Low Temperature Overpressure Protection).

If not being met, then list all the LTOP requirements that ULTIMATELY result in LTOP not being met. If any requirements are NOT being met, THEN document by listing on the provided copy of LTOP Requirements Logic Diagram End. 4.13 of OP/11A111041049, LTOP.

Unit I Conditions For Determining LTOP Requirements Procedures in progress:

OP/i /A111021010, Controlling Procedure for Unit Shutdown

End. 4.10, S/D from Mode 3 to Mode 4 in progress NOTE: Any equipment or components associated with LTOP requirements that are not described below can be assumed to be in the desired position/condition to support Unit ls current plant status.

RCS Parameters:

Tc = 225°F slowly decreasing

RCS Pressure = 285 psig decreasing

Pressurizer Level = 218 inches decreasing slowly

LPI operation (Series Mode) in progress Primary Systems/Components status:

All HPI pumps are OFF

lB and 1C HPI Pumps are racked out and tagged

1A HPI Pump is racked in the TEST position and tagged

1HP-26 and 1HP-27 are closed; handwheels tagged; breakers tagged open

1HP-409 and -410 switches in CR have been tagged closed

1 CF-i is Closed / handwheel tagged and breaker tagged open

1 CF-2 is Closed / handwheel tagged and breaker not tagged open

iA CFT pressure = 368 psig stable

1 B CFT pressure 375 psig stable

1HP-120 Travel Stop installed

LTOP computer point OiL3i53 is not in alarm

1SA-2/C-3 and ISA-i 8/A-3, A-4 cards are not pulled and not in alarm

1 SA-2/C-4 card is pulled

1 N- 121 is closed but not tagged

Pressurizer Heater Bank 4 is deactivated with breaker white tagged

No dedicated LTOP Operator assigned

An LTOP Vent path ( 3.6 square inches) is not established

1 RC-4 is open

e .

Enclosure 4.13 OP/i/A/i 104/049 LTOP Requirements Logic Diagram Page 1 of I Performed By LTOP TRAIN 1 Date/Time LTOP TR?\IN 2 0

1A& lB HPlf s racked not or in test, and tagged HP-26 closed/handwheel tagged and bkr lagged open 1HP-409 CR switch tagged closed WOO IHP-410 CR switch tagged closed Pzr relief standpipe (vahve removed) or greater Vest path established

1C HPIP bkr racked oat nr in test, and tagged 1F-IP-27 closed/handwheel tagged and bkr tagged open LTOP I HP.409 CR switch tagged closed asO Requirements IHP-410 CR switch tagged closed Satisfied 1CF-lClosed/ handwheel tagged and bkr tagged open IA CFT depressarized to <373 psig 1CF-2 closndlhaedwheel tagged and bkr tagged open NOTE: Enc. 4.7 (LTOP Computer 1 B CFT depressur/zed to 0373 pug Points) contains a list of points associated with LTOP operability.

HPI NOT in operation and ahgned via I HP-120 1HP-120 Travel Stop Operable LTOP Con-cuter point 01L3153 not in alarm 1SA-21C-3. C-A cards Cot polled/not maiarr-n HIGH ISA-lg/A-3 card net polled/not in alarm Cemnp plo. 01X2256 AND D1X2274 Operabl ISA-t8/A-4 card not polled/net in alarm Camp. Pt O1X22g5 Operable DAC operabte IN-121 Tagged Closed Pzr Htr Bank 3 Deactroated Pzr Htr Bank 4 Deactivated RCS pressame within limits Palo PZR level Within lirnots SO PrimavMavwayOfl Dedicated LTOP Operator assigned Unit 1 LTOP Logic Rev 22.des LTDP Vent established O1LTOP000I.DES 08/20/09 rtr be lion RCS vent path is established per Enclosure 45 (LTOP Vent Paths), this requirement can considered met during I-WI testing.

Admin-213 Ri Page 1 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-21 3 Perform Surveillance to Verify SSF RCMUP Operability CANDIDATE EXAMINER

Admin-213 Ri Page 2 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform surveillance to verify SSF RCMUP Operability. If required, determine any TS/SLC conditions, actions, and completion times.

Alternate Path:

No Facility JPM #:

Admin-213 KIA Rating(s):

System: GEN K/A: 2.2.12 Rating: 3.7/4.1 Task Standard:

Verify SSF RCMUP Operability using:

1) OP/1/A/1105/014 (Control Room Instrumentation Operation And Information), Enclosure 4.1, Mode 1 & 2.

2) Enclosure Unit 1 &2 Spent Fuel Pool Level Vs Temperature Curve of OPIO/A/1 108/001 (Curves And General Information)

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Classroom X Perform X Simulate

References:

OP/1/A/1105!014, End. 4.1 OP/0/A11108!001, End. 4.34 VIirIfinn Time: 15 minutes Time Critical: NO Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS

Admin-213 Ri Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admn-213 Ri Page 4 of 8 Tools/Equipment/Procedures Needed:

OPI1/A111051014 (Control Room Instrumentation Operation And Information), End. 4.1 (Mode 1 & 2)

Enclosure 4.34 Unit 1 &2 Spent Fuel Pool Level Vs Temperature Curve of OP/0/A/1108/00l (Curves And General Information)

READ TO OPERATOR DIRECTION TO TRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS

U2E0C24 outage in progress

Unit 2 was shutdown (subcritical) on 4/15/11 at 0100

Unit 2 core is defueled

Spent Fuel Pool Level = -0.7 feet

Spent Fuel Pool Temperature 109°F

Current date and time: 4/30/11 at 2000

OP/1/A11105/014 (Control Room Instrumentation Operation And Information), End. 4.1 (Mode 1 & 2) in progress INITIATING CUES You are to perform SFP Level surveillance per OP/i/Ni 105/014, End. 4.1 on page 13 of 13.

If required, determine any applicable TSs/SLCs, actions, and completion times.

Admin-213 Ri Page 5 of 8 START TIME:

STEP 1: Determme the correct curves to use in Enclosure Unit 1 &2 Spent Fuel CRITICAL STEP Pool Level Vs Temperature Curve based on Mode and Core load conditions SAT STANDARD: Refer to NOTES on pages 1 and 4 of Enclosure Unit 1 &2 Spent Fuel Pool Level Vs Temperature Curve of OP/i 108/001. Determine that curves 4-6 apply due to Unit 2 currently being defueled; specifically UN SAT curves on Page 5 are to be used due to Unit 2 being defueled and not refueled and restored to Mode 3 after refueling.

COMMENTS:

STEP 2: Determine if all fuel in SFP has been subcritical > maximum days CRITICAL STEP specified on Enclosure Unit 1 &2 Spent Fuel Pool Level Vs Temperature Curve SAT STANDARD: Refer to Enclosure Unit 1&2 Spent Fuel Pool Level Vs Temperature Curve of OP/i 108/001. Determine that Unit 2s fuel has been subcritical for 15 days and 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months . This is less than the maximum days (<35) UN A T specified on Enclosure Unit i&2 Spent Fuel Pool Level Vs Temperature Curve.

COMMENTS:

STEP 3: Verify SEP level greater than specified on appropriate curve of Enclosure CRITICAL STEP Unit 1&2 Spent Fuel Pool Level Vs Temperature Curve.

SAT STANDARD: Determine that the correct curve on Page 5 is Day> 15 & 17.

Determine Spent Fuel Pool water temperature is 109°F by referring to Cue sheet.

UNSAT Determine Spent Fuel Pool water level is 0.70 feet by referring to Cue sheet.

Determine that SEP level is NOT Acceptable (not above the appropriate curve). Declare the Ui SSF RCMUP inoperable.

COMMENTS:

Admin-213 Ri Page 6 of 8 STEP 4: If required, determine any TS/SLC actions and completion times. CRITICAL STEP STANDARD: Determine that TS 3.10.1, Standby Shutdown Facility; Condition C should SAT be entered; Restore RCMU system to operable status within 7 days.

COMMENTS:

UNSAT STOP TIME:

Admin-213 Ri Page 7 of 8 CRITICAL STEP EXPLANATIONS STEP # Explanation 1 Required to determine the correct set of curves to be used.

2 Required calculation allowing the correct curve to be selected.

3 Required to determine that due to current conditions SFP level is adequate and therefore the Ui SSF RCMUP is inoperable.

4 Required to determine applicable TS/SLC entry(s) conditions, actions, and completions times.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

U2E0C24 outage in progress

Unit 2 was shutdown (subcritical) on 4/15/11 at 0100

Unit 2 core is defueled

Spent Fuel Pool Level = -0.7 feet

Spent Fuel Pool Temperature = 109°F

Current date and time: 4/30/11 at 2000

OP/1IA/11051014 (Control Room Instrumentation Operation And Information), End. 4.1 (Mode 1 & 2) in progress INITIATING CUES The Unit 1 Control Room SRO directs you to perform SFP Level surveillance per OP/1/A/1105/014, End. 4.1 on page 13 of 13. If required, determine any applicable TSs/SLCs, actions, and completion times.

Q Enclosure 4.1 OP/i/All 105/0 14 Model&2 Pagelofl3

1. Initial Conditions 1.1 Unit is in Mode 1 or 2.

1.2 Review Limits And Precautions.

2. Procedure 2.1 Perform Component checks as specified.

2.2 IF any Component check can NOT be performed as written, perform the following:

2.2.1 Support personnel/groups contacted (if any) AND information provided: (Additional page 1 s may attached (N) (D) be if necessary) 2.2.2 Describe corrective/compensatory actions being taken (procedure change, WR, PIP, etc.), and (N) (D) resolution date for those actions. (Additional page Is maybe attached if necessary)

Component description Corrective/Compensatory Action Resolution Date

e Enclosure 4.1 OP/i/A/i 105/014 Model&2 Page2ofl3 NOTE: Items may be performed anime during shift hours.

COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS Pressurizer Level (N) (D) 01E2301 Verify redundant level channels agree within 8 (Uncorrected) 01 E2303 on computer.

O1E2305 TS 3.10.1 SFP Temperature (N) (D) 01A0839 Record SFP temperature twice per shift and 1°F /°F verify< 141°F.

mit mit mit mit IF SFP temperature increases 2°F/12 hrs, evaluate and increase cooling as needed.

jj SFP temperature increases 5°F/12 hrs, Refer to AP/ 1-2/All 700/03 5 (Loss Of SFP Cooling And/Or Level).

IF> 141°F, SSF RCMUP is inoperable. Contact Duty MSE Engineer.

TS 3.7.5 PIP 0-05-00199 UST Temperature (N) (D) 01A0122 Verify UST temperature:

0 lAO 123 IF Rx Power 30% power, verify 125°F.

IF Rx Power < 30% power, verify 145°F.

IF> limit, refer to OP/1/A/1106/006 (Emergency FDW System) and issue PIP for operability_evaluation.

Enclosure 4.1 OP/i/A/i 105/0 14 Mode I & 2 Page 3 of 13 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS SLC 16.10.7 UST Temperature (N) (D) Verify UST temperature:

(Alternate Credited Unit) IF Rx Power 30% power, verify 125°F.

IF Rx Power < 30% power, verify 145°F.

IF> limit, refer to OP/i/A/i 106/006 (Emergency FDW System) and issue PIP for operability_evaluation.

SLC 16.7.2 AMSAC/DSS (N) (D) 01D2928 Verify no trips present AND status annunciators THRU indicate operable channels.

01D2935 Verify ISA-8 C-9/C-10/D-5/D-8 AND indicating lights on 1UB1.

Refer to OP/i/A/i 105/0 14 (Control Room Instrumentation Operation And information)for operability determinations.

SLC 16.7.3 SG A XSUR Level (N) (D) 01A1213 IF < 2% RTP, verify redundant levels agree Redundant Level 01E2052 within 6.

> 6 acceptable during momentary swings

(< 30 see).

SLC 16.7.3 SG A XSUR Level (N) (D) O1Ai213 IF SG on level control, verify all XSUR OAC Minimum Level 01E2052 indications 23.

< 23 are acceptable during momentary swings

(< 30 see)

SLC 16.7.3 SG B XSUR Level (N) (D) 01A1215 IF Rx < 2% RTP, verify redundant levels agree Redundant Level OlE2053 within 6.

> 6 acceptable during momentary swings

(<_30_see).

e Enclosure 4.1 OP/1/A11105/014 Model&2 Page4ofl3 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS SLC 16.7.3 SG B XSUR Level (N) (D) 01A1215 IF SG on level control, verify all XSUR OAC Minimum Level OlE2053 indications 23.

< 23 acceptable during momentary swings

(<_30_sec).

1 A SG SU Levels (N) (D) 01 E2000 IF Rx < 2% RTP, veri redundant levels agree 01E2001 within 2.

>2 acceptable during momentary swings

(<_30_sec).

lB SG SU Levels (N) (D) 01E2005 IF Rx <2% RTP, verify redundant levels agree 01E2006 within 2.

>2 acceptable during momentary swings

(<_30_sec).

SLC 16.7.5 1A SG OR Levels {1} (N) Verify redundant operating range recorder level channels agree within 3%.

SLC 16.7.5 lB SG OR Levels {I} (N) Verify redundant operating range recorder level channels agree within 3%.

SLC 16.7.5 SG Downcomer Temperatures (N) 01E2008 Verify All SG Downcomer Temperature 01E2009 computer points agree within 3°F of each other.

01E2012 01 E20 13 IF All SG Downcomer Temperatures DO NOT agree within 3°F of each other, then perform Enclosure 4.16 (Channel Check Of OTSG Downcorner Temperatures).

PIP_0-99-03857,_PIP_0-08-0 1226

Enclosure 4.1 OP/l/A11105/014 Model&2 Page5ofl3 COMPONENT 1900-0700 0700-1900 COMPUTER REQU WED CONDITIONS SG Shell (N) OIP1 892 Verify 0 1P1892 agrees within +/- 5°F of Temperatures 01P1893 OlP1893. IF 01P1892 does NOT agree within

+/- 5°F of01P1893 compare computer points for A SG Shell Temperatures (01A0968 01A0972) and B SG Shell Temperatures (01A0973 OlA0977) to determine if any points have failed. Issue a Work Request for any_problem_detected.

Station Condenser z\T (D) 01P1950 IF CCW inlet temperature > 68°F, verify or O*P 1950 (STATION CCW AVG TEMP RISE) 02P1950 22°F.

or 03P 1950 IF CCW inlet Temperature> 68°F AND 01P1950 (STATION CCW AVG TEMP RISE) comes into alarm (21.5°F), perform Enclosure 4.17 (CCW Discharge Temperature Guidelines).

iF 01P1950, 02P1950, and 03P1950 are all OOS, perform one of the following:

1) Verify all Units with CCW flow have CP O*P 1944 operable

2) Hourly Inlet/Outlet sheet performed per OP/0/AJl 108/00 1 (Curves And General Information) Enclosure Condenser Flow And Temperature Data.

CCW (D) 01P0761 Verify average CCW inlet temperature 80°F.

IF> 80°F, Perform Enclosure 4.15 (Hot Lake Water Surveillance). {OSC-2576}

Enclosure 4.1 OP/i/All 105/0 14 Model&2 Page6ofl3 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS Station CCW Discharge (D) 01P1949 Verify O*P1949 (STATION ENV 2 HR AVG Temperature or CCW DISCH TEMP) temperature 100°F.

02P 1949 or IF 0lP1949, O2P1949, and O3P1949 are itil O3P1949 OOS, perform oneof the following:

1) Verify 01 P076 5 (STATION ENV AVG CCW OUT TEMP) temperature 100°F.

2) Verify all Units with CCW flow have CP O*P 1942 operable

3) Hourly Inlet/Outlet sheet performed per OP/0/A/l 108/00 1 (Curves And General Information) Enclosure Condenser Flow And Temperature Data.

Unit CCW Discharge (D) 01 P0762 Verify 01 P0762 (UNIT 1 ENV AVG CCW Temperature OUT TEMP) 100°F.

IF O1P0762 (UNIT 1 ENV AVG CCW OUT TEMP) comes into alarm, perform Enclosure 4.17 (CCW Discharge Temperature Guidelines).

NOTE: This check is to prevent exceeding Station_CCW_Discharge_Temperature.

TS 3.5.2 LDST Pressure (N) (D) CR Gage Verify both LDST pressure/level relationships O1A2191 comply with OP/0/All 108/00 1 (Curves And General Information).

0 Enclosure 4.1 OP/i/A/i 105/0 14 Model&2 Page7ofl3 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS ESV Piping Low Point Heat (N) (D) O1E2738 Verify Temperature > 45°F.

Trace 01E2739 O1E2742 IF 45°F AND outside ambient temperature O1E2745 < 35°F, contact Engineering for an operability assessment/evaluation.

IF 45°F AND outside ambient temperature

_3 5°F,_issue_WR_to_repair.

Room Temperatures (N) (D) Record and compare room temperatures to those taken on previous shift.

A 3°F temperature increase observed from the Unit 1 Cable Rm. O1A1850 previous shift may be an indication of a problem with the WC System. IF this is indicated, Unit I Equip. Rm. OlAl851 REFERAP/1-2/AJ1700/036 (Degraded Control Room Area Cooling).

Unit 1&2 Control Rm.

HPI Pump Room Temperature (N) (D) Verify HPI Pump Room temperature is nominally 120°F.

Unit I HPI Pump Room IF Required conditions NOT met, refer to (Room 54) AP/1-2/A11700/037 (Degraded HPLLPI Room Cooling).

LPL/RBS Pump Room (N) (D) Verify LPJIRBS Pump Room temperature is Temperature nominally 105°F.

Unit 1 A LPJJRBS Pump IF Required conditions NOT met, refer to Room (Room 61) AP/I-2/A/1700/037 (Degraded HPT/LPI Room Cooling).

Unit 1&2 B LPLRBS Pump Room_(Room_62)

0 0 Enclosure 4.1 OP/l/A11105/014 Model&2 Page8ofl3 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS Containment Average (N) (D) O1A0006 Verify computer point with highest temperature Temperature 01A0019 value 140°F.

O1AOO2O 01A0021 IF> 140°F is exceeded, Contact EQ Engineer 01 A0027 and Reactor Building Ventilation Engineer.

01A0028 01A0043 IF> 175°F, contact MCE for operability 01 A2740 assessment/evaluation. (Reactor Building)

NOTE: Ifanyof the listed OAC points are OOS, contact MCE for monitoring guidance.

ES Channels 1 & 2 (N) (D) Verify no trips present AND status annunciators RC Press indicate operable channel.

ES Channels 3 & 4 (N) (D) Verify no trips present AND status annunciators RC Press indicate operable channel.

ES Channels I & 2 (N) (D) Verify no trips present AND status annunciators RB 4 psig indicate operable channel.

ES Channels 3 & 4 (N) (D) Verify no trips present AND status annunciators RB 4 psig indicate operable channel.

ES Channels 5 & 6 (N) (D) Verify no trips present AND status annunciators RB 4 psig indicate operable channel.

RP Low Press Trip (N) (D) Verify no trips present AND status annunciators RPS { 1 } indicate operable channel.

RP RCP/Flux/Imb Trip (N) (D) Verify no trips present AND status annunciators RPS { 1 } indicate operable channel.

RP High Temp Trip (N) (D) Verify no trips present AND status annunciators RPS { I } indicate operable channel.

Enclosure 4.1 OP/i/All 105/0 14 Mode 1 & 2 Page 9 of 13 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS RP Press/Temp Trip (N) (D) Verify no trips present AND status annunciators RPS { 1 } indicate operable channel.

RP High Press Trip (N) (D) Verify no trips present AND status annunciators RPS { 1 } indicate operable channel.

RP High Flux Trip (N) (D) Verify no trips present AND status annunciators RPS { 1 } indicate operable channel.

TS 3.10.1 RCS Boron Concentration (N) (D) Verify RCS Boron Concentration greater than Minimum RCS Boron Concentration to Maintain SSF Operability curve of PT/hAll 103/0 15 (Reactivity Balance).

IF minimum concentration is NOT met, SSF RC MU Pump is inoperable. Contact Duty Rx Engineer.

Control Rod Group Alignment (D) GD REG IF two Group 7 Control Rods are 2% above its Limits Group average AND two Group 7 Control Rods are 2% below its Group average, ensure OWPG has been contacted to schedule CRD alignment per OP/I/A/I 105/0 19 (Control Rod Drive System)._{PIP_O-06-03794}

TS 3.3.10 Wide Range Neutron Flux (N) (D) IF in Mode 1, verify NI-i, NI-2, NI-3 and NI-4 TS 3.3.8 agree within one of the following:

IF < 10% RTP, 3 LED Segments IF 10% RTP, 2 LED Segments.

0 Enclosure 4.1 OP/i/A/i 105/0 14 Mode I & 2 Page 10 of 13 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS TS 3.3.8 -

ICC Level Train A (D) Verify MALFLTNCT 00 message on diagnostic page of ICCM Plasma Display.

Verify RVLIS/ICCM/RG 1.97 TRAIN A TROUBLE annunciator (1SA-18/A-3) NOT in alarm.

Verify ICCM Gateway to OAC computer alarms NOT in alarm.

IF a MALFUNCTION FF message OR annunciator alarm is present ICCM Gateway to OAC computer alarms are in alarm, issue a Priority Work Request AND contact I&E to investigate problem AND refer to OP/i/All 105/0 12 (ICCM Operation And Guidelines) to determine operability of ICC channel.

TS 3.3.8 ICC Core Cooling Train A (D) Verify from Core Cooling core map 5 CETCs operable (do NOT indicate FAIL).

e Enclosure 4.1 OP/i/A/i 105/0 14 Model&2 Pagellofl3 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS TS 3.3.8 -

ICC Level Train B (D) Verify MALFUNCT 00 message on diagnostic page of ICCM Plasma Display.

Verify RVLIS/ICCM/RG 1.97 TRAIN B TROUBLE annunciator (1SA-18/A-4) NOT in alarm.

Verify ICCM Gateway to OAC computer alarms NOT in alarm.

a MALFUNCTION FF message OR annunciator alarm is present OR ICCM Gateway to OAC computer alarms are in alarm, issue a Priority Work Request AND contact I&E to investigate problem AND refer to OP/i/A/l 105/0 12 (ICCM Operation And Guidelines) to determine operability of ICC channel.

TS 3.3.8 ICC Core Cooling Train B (D) Verify from Core Cooling core map 5 CETCs operable (do NOT indicate FAIL).

TS 3.3.14 1A & lB MD EFDW Pumps (N) (D) Verify lights energized.

TS 3.7.5 OFF/AUTO/RUN Lights IF NOT, MD EFDW Pumps are inoperable and Auto_Start_capability_is_lost.

SLC 16.1 1.3 Sorrento Radiation (N) (D) Verify cunent time on RIA CRT within Monitor Time Check +/- 1 minute of current time on OAC CRT.

IF>_+/-_1_minute,_Contact_IT_to_reset_time.

TS 3.5.3 LPI Cooler A LPSW Flow (N) (D) O1A2 124 IF PAM Dixson is blinking AND with a reading TS 3.7.7 Dixson Indicator of zero, verify computer point O1A2124 for Train_A_is_+/-_150_gpm.

0 Enclosure 4.1 OP/l/A!1105/014 Model & 2 Page 12 of 13 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS TS 3.5.3 LPI Cooler B LPSW Flow (N) (D) 01A2125 IF PAM Dixson is blinking AND with a reading TS 3.7.7 Dixson Indicator of zero, verify computer point 01A2125 for Train_B_is_+/-_150_gpm.

TS 3.4.15 RB Normal Sump (N) Verify water level in RBNS on scale.

RB Emerg Sump (N) 01A0050 Verify Train A AND Train B Meters, Narrow Range Computer and Recorder (1MSCCR0003) agree within 1 ft.

800 mHz Radio IF Sunday Test the backup radio communications with the (N) System Operating Center (SOC) AND the Transmission Control Center (TCC).

SOC code 96 TCC codeIl IF communications fail notify SPOC.

RCS Xe33 equivalent IF Sunday Enter data into OAC per OP/0/AJ1 1 06/031 corrected activity OR (Primary to Secondary Leak Rate Monitoring Thursday and Instrumentation).

(N) 125 VDC Ground Detection (N) (D) Perform Enclosure 125 VDC Ground System Test Detection System Operation of OP/i/All 107/0 10 (Operation Of The Batteries And Battery Chargers).

IF required conditions CANNOT be met, notify_I&E.

SLC 16.9.6 Fire Alarm Cabinet (N) Verify Power AND Run LEDs are on AND no_Trouble/Alarm_lights_present.

e Enclosure 4.1 OP/l/Ai1105/014 Mode I & 2 Page 13 of 13 COMPONENT 1900-0700 0700-1900 COMPUTER REQUIRED CONDITIONS TS 3.10.1 SFP Level (N) (D) NOTE: Ensure correct curve based on Mode and Core load condition is used.

Verify SSF RCMUP Operable twice per shift per OP/0/A11 108/00 1 (Curves And General Information) Enclosure Unit I &2 Spent Fuel Pool Level Vs Temperature Curve.

IF_limit_exceeded,_SSF_RCMUP_is_inoperable.

LDST Level IF Verify redundant level channels I &2 CR Gage Saturday and Local Gage (1HPIPGO437) agree within 2.

(D)

LDST Pressure IF Verify redundant pressure channels 1 &2 CR Saturday Gage and Local Gage (1HPIPGO438) agree (D) within 1 psig.

1st Day Of Month Checks IF 1 St Day Perform Enclosure 4.18 (1st Day Of Month of Month Checks).

(D)

TS 3.4.15 RCS Leakage Detection (N) (D) IF Unit 1 > 95% FP AND NOT at Steady State, Instrumentation perform Enclosure 4.19 (IRIA-47 Compensatory Actions).

IF Unit 1 95% FP, perform Enclosure 4.19 (1RIA-47 Compensatory Actions).

Steady State defined as stable RCS Pressure, Temperature, Power Level, Pressurizer and Makeup Tank Levels, Makeup and Letdown, and_RCP_pump_seal_injection_and_return_flows.

Enclosure 4.34 OP/O/A/l 108/00 1 Unit 1&2 Spent Fuel Pool Level Vs. Temperature Curve Page 1 of 6 (For Aid In Determining SSF RCMU System Operability)

NOTE: 1. Pages 1-3 of this enclosure apply to core 1E0C25 defuel/refuel. Pages 4-6 apply to core 2E0C24 defuel/refuel.

2. Unit 2 will use curve on Page 2 of this enclosure from beginning of Unit I core offload until Unit 1 enters MODE 3.

3. BOTH Unit I AND Unit 2 will use curve on Page 3 of this enclosure after Unit I initially enters MODE 3 after refueling.

4. After Unit 1 enters MODE 3, if either Unit 1 or Unit 2 shuts down below MODE 3, the Unit remaining above MODE 3 will continue to use curve on Page 3 of this enclosure.

5. When all fuel in SFP has been subcritical > maximum days specified on applicable curve, SFP level is required to be above the lower level axis.

When using curve on page 2, and all fuel in SFP has been subcritical for> 11 days, level must be > - 2.00 ft

When using curve on page 3, and all fuel in SFP has been subcritical for> 13 days, level must be >- 2.00 ft

Enclosure 4.34 oP/O/A/1 108/00 1 Unit 1&2 Spent Fuel Pool Level Vs. Temperature Curve Page 2 of 6 (For Aid In Determining SSF RCMU System Operability)

Restrictions on Unit 1/2 Spent Fuel Pool From Beginning ACCEPTABLE of Core Offload Until Unit I Enters Mode 3 REGION (area above line)

UIEOC25 0.70 - - - - - -

0.60 - - -

0.50

= -

0.40 - -

u 0.30 = = N 0.20 =

A j

1 0 00.00 -

1 C L1 -

ci, -0.10 -

- C 0020 =

- E

-0.30 c-0.40- :

E -0.50 - T O

-0.60 - A w -0.70 -

B

-0.80 =

-0.90 L

-1.00 E

R

-1.30 E

-1.40

-1.50 o - -

G

-1.60 -

L1______ 0

-1.80 o

o -1.90 N

0 65 70 75 80 85 90 95 100 105 110 JJ 115 120 Temperature of Pool Water (°F), OSF TT0002P 125 130 135 140 145 ONTC-0-1O1A-0008-001 Rev. 5

0 0 Enclosure 4.34 OP/O/A/1 108/001 Unit I &2 Spent Fuel Pool Level Vs. Temperature Curve Page 3 of 6 (For Aid In Determining SSF RCMU System Operability)

Restrictions on Unit 1/2 Spent Fuel Pool and Both Units In Mode ACCEPTABLE 3, 2, or I REGION UIEOC25 (area above line) 0.70 0.60 0.50 0

C 0.40 0

I 0.30

-J 0.20 LL C, 0.10 0 0.00

-0.10 CC -0.20 C

-0.30 E

0 -0.40 C

-0.50 C)

> -0.60 0 -0.70 CC -0.80 1

C) -0.90 C)

.4- -1.00

-1.10 C)

> -1.20 C)

-J -1.30 I- -1.40 C)

-1.50 CC

-1.60

-1.70 0

0 -1.80 0

-1.90

-2.00

-2.10

-2.20 65 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 145 150 Temperature of Pool Water (°F), OSF TT0002P ONTC-0-1O1A-0008-002 Rev. 3

Enclosure 4.34 oP/O/A/l 108/00 1 Unit 1&2 Spent Fuel Pool Level Vs. Temperature Curve Page 4 of 6 (For Aid In Determining SSF RCMU System Operability)

NOTE: 1. Pages 4-6 of this enclosure apply to core 2E0C24 defuel/refuel.

2. Unit 1 will use curve on Page 5 of this enclosure from beginning of Unit 2 core offload until Unit 2 enters MODE 3.

3. BOTH Unit 1 AND Unit 2 will use curve on Page 6 of this enclosure after Unit 2 initially enters MODE 3 after refueling.

4. After Unit 2 enters MODE 3, if either Unit 1 or Unit 2 shuts down below MODE 3, the Unit remaining above MODE 3 will continue to use curve on Page 6 of this enclosure.

5. When all fuel in SFP has been subcritical> maximum days specifi ed on applicable curve, SFP level is required to be above the lower level axis.

When using curve on page 5, and all fuel in SFP has been subcritical for>

35 days, level must be> - 2.00 ft

When using curve on page 6, and all fuel in SFP has been subcritical for>

33 days, level must be >- 2.00 ft

0 0 0 Enclosure 4.34 OP/O/A/1 108/00 1 Unit 1&2 Spent Fuel Pool Level Vs. Temperature Curve Page 5 of 6 (For Aid In Determining SSF RCMU System Operability)

Restrictions on Unit 1/2 Spent Fuel Pool From Beginning ACCEPTABLE of Core Offload Until Unit 2 Enters Mode 3 REGION Note: Total leakage from 2SF-i and (area above Ine) U2E0C24 2SF-2 must be limited to 13 gpm.

0.70 0 I I II_ III I .Vl I I I I 0.60 H-0,50 t 7

H*l H IH H HHH- ri HHHH HHLIIII 0.40 0.30 0.20 A 0.10 LI_

Cl) 0.00 o -0.10

- C I

-0.20 .[ E

-0.30 iZ E -0.40

- 7: = z = =

P

-0.50

-0.60 A

-0.70 B

-0.80

-0.90 7 L

H

- -1.00 E

-1.10

-1.20 -r o_ zC- R Ti 2

= = E

-1.50

- -I

G

-1.60 Q -1.70

-1.80 0

-1.90 N

-2.00

. I

-2.10 H-

-2.20 -i--H- H I H+H E - .-#Hr i--- .*< Ef7 65 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 145 Temperature of Pool Water (°F), OSF TT0002P ONTC-0-IOIA-0008-001 Rev. 7

0 Enclosure 4.34 OP/O/A/1 108/00 1 Unit 1&2 Spent Fuel Pool Level Vs. Temperature Curve Page 6 of 6 (For Aid In Determining SSF RCMU System Operability)

Restrictions on Unit 12 Spent Fuel Pool and Both Units In ACCEPTABLE Mode 3. 2. or 1 REGION U2E0C24 - -

(area above line) o io 0.60 0.50 040 030 020 U) 0 0.oo.

0.10 U

-020 .

N

-030 -

w-Q.40 A o -0.50 CR-

-060 -

-080 EG:

- -090 -

p I w -100 -

-i,io -

-120 -

A N

-130 .

B 3 -1.40 --

L

-iso -

E

ç .---

Iii 65 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 145 150 Temperature of Pool Water (°F), OSF TT0002P ONTC-0-1O1A-00008-002 Rev. 4

Admin-305 Ri Page 1 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-305 Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (EDL)

CANDIDATE EXAMINER

Admin-305 Ri Page 2 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits Alternate Path:

N/A Facility JPM #:

N/A KIA Rating(s):

K/A: Gen2.3.4 Rating: 3.2/3.7 Task Standard:

Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (+/- 2 minutes).

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Classroom X Perform X Simulate

References:

NSD-507, Radiation Protection OMP 1-18, Implementation Standard During Abnormal And Emergency Events Validation Time: 20 mm. Time Critical: NO Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS

Admin-305 Ri Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin-305 Ri Page 4 of 8 ToolslEguipmentlProcedures Needed:

None READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS

1. Steam Generator Tube Rupture has occurred on Unit 3

2. Emergency Dose Limits are in effect

3. NEO A has received 1.26 R TEDE this year

4. The following tasks are required to be performed:

TASK TIME REQUIRED DOSE RATE 1 Close 3C-573 11 mm 6.15 R!hr 2 Open 3FDW-313 6 mm 18.25 R/hr 3 Open all Unit 3s ADV5 4.65 R/hr Note: Assume no dose is received while traveling between tasks.

INITIATING CUE Refer to the above information. NEO A has completed tasks 1 and 2 in the time required. How long does the NEO have to complete task 3 without exceeding his Emergency Dose Limits?

Admin-305 Ri Page 5 of 8 START TIME:

Note: Candidate may perform these steps in a different order; however, the calculated stay time should be correct.

Note: Candidate should understand the following:

1. EDLs is 5 Rem per event (LOCA or SGTR).

2. Current exposure for the year is not counted toward the Emergency Dose Limits (EDL).

STEP 1: Determine dose received while performing task 1. CRITICAL STEP STANDARD: Determine dose received while performing task 1. SAT 6.15 R/hrXihr/60 minXll min=1.13R UNSAT COMMENTS:

STEP 2: Determine dose received while performing task 2. CRITICAL STEP SAT STANDARD: Determine dose received while performing task 2.

18.25 R/hr X 1 hr/60 mm X 6 mm 1.83 R UNSAT COMMENTS:

STEP 3: Determine dose remaining from EDLs. CRITICAL STEP SAT STANDARD: Determine dose remaining from EDLs.

5R1.13R1.83R=2.04R UNSAT COMMENTS:

Admin-305 Ri Page 6 of 8 STEP 4: Determine time available for the NEO to complete task 3 without CRITICAL STEP exceeding EDL.

SAT STANDARD: Stay time is calculated to be:

Available Dose = 2.04 R = .44 hr X 60 mm 26.4 mm Dose Rate 4.65 RJhr ihr UNSAT

(+/- 2 minutes)

COMMENTS:

END OF TASK STOP TIME:

Admin-305 Ri Page 7 of 8 CRITICAL STEP EXPLANATIONS STEP # Explanation 1 Required to calculate stay time.

2 Required to calculate stay time.

3 Required to calculate stay time.

4 Required to calculate stay time.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

1. Steam Generator Tube Rupture has occurred on Unit 3

2. Emergency Dose Limits are in effect

3. NEO A has received 1.26 R TEDE this year

4. The following tasks are required to be performed:

TASK TIME REQUIRED DOSE RATE 1 Close 30-573 11 mm 6.15 R/hr 2 Open 3FDW-313 6 mm 18.25 R/hr 3 Open all Unit 3s ADVs 4.65 R/hr Note: Assume no dose is received while traveling between tasks.

INITIATING CUE Refer to the above information. NEO A has completed tasks 1 and 2 in the time required. How long does the NEO have to complete task 3 without exceeding his Emergency Dose Limits?

ADMIN-408 Ri Page 1 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-408 Determine Emergency Classification and Protective Action Recommendations (Complete Emergency Notification Form)

CANDIDATE EXAMINER

ADMIN-408 RI Page 2 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Determine Emergency Classification and Protective Action Recommendations (Complete Emergency Notification Form)

Alternate Path:

NO Facility JPM #:

New KIA Rating(s):

System: Gen K/A: 2.4.38 Rating: 2.4/4.4 Task Standard:

Appropriate classification is determined and associated Emergency Notification Form is completed.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Classroom X Perform X Simulate_____

References:

RP/0/B/1 000/0 1 RP/0/B/1 000/02 BASIS Document (Volume A, Section D of the Emergency Plan)

RP/0/B/1 000/0 1 5A Validation Time: 20 mm. Time Critical: Yes Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UN SAT Performance Time:

Examiner: /

NAME SIGNATURE DATE Comments

ADMIN-408 Ri Page 3 of 10 SIMULATOR OPERATOR INSTRUCTIONS NONE

ADMIN-408 Ri Page 4 of 10 Tools/Equipment/Procedures Needed:

RPIOIBI1000IO1 I RPIOIBI1000IO2 / RPIOIBI1000IO15A (optional) I Message Sheet #1 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS: THIS IS A DRILL 08:00:00 Unit 1 (Mode 1, 100%) has a SG Tube Rupture (SGTR) of 35 gpm in the 1A SG

. 1RIA-40 is in HIGH alarm 08:05:00 ERO activated by the OSM due to the SGTR 08:25:00 Offsite Communicator informs OSM that offsite agencies have received Message

1 at 0811 CURRENT CONDITIONS: THIS IS A DRILL While Unit 1 is shutting down due to the SGTR, the following event time-line occurs; 08:30:00 Unit 1 Turbine/Generator trips and CT-i locks out.

08:30:28 Unit 1 BOP dispatched to activate the SSF using AP/25, per EOP immediate manual actions step 3.5-RNO.

08:30:45 OATC performs Rule 3 for a loss of Main FDW; SG5 being fed by 1TDEFWP.

08:32:50 Control Room crew notifies OSM that BOTH Keowee Units have experienced Emergency Lockouts and that CT-5 is available. Unit 2 BOP is performing EOP End. 5.38 (Restoration of Power).

08:41:00 SSF RD reports that flow has been established to Unit is RCP Seals per AP/25 08:47:05 Power has not been restored. Enclosure 5.38 is still in progress.

INITIATING CUE Current time is 0848. Perform the required actions of the Emergency Coordinator:

1. Determine Emergency Classification

2. Complete appropriate Emergency Notification Form for current conditions THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment while classifying the event. When required, other operators will maintain the Emergency Coordinators Log and perform the duties of the Control Room Offsite Communicator.

ADMIN-408 RI Page 5 of 10 START TIME:

STEP 1: Classify the Event at 08:47:05 CRITICAL STEP STANDARD: Refer to RP/0/B/1000!01 (Emergency Classification) Enclosure 4.5 (Loss of Power). SAT Classify the event as a Site Area Emergency due to the following:

LOSS OF POWER

MFB I and 2 de-energized AND Failure to restore power to at UNSAT least one MFB within 15 minutes from the time of loss of both offsite and onsite AC power.

COMMENTS:

STEP 2: Commence the Off-Site Notification Form.

STANDARD: Go to RP!0/B/1000/002 (Control Room Emergency Coordinator SAT Procedure) and initiate procedure by determining symptoms for entry exist and check Step 1.1 COMMENTS: UNSAT STEP3: Step2.1.

STANDARD: Determine step 2.1 does not apply SAT COMMENTS:

UNSAT STEP 4: Step 2.2 TIME Declare the appropriate Emergency Classification level. CRITICAL STEP Classification SAE (UE, ALERT, SAE, GE)

Time Declared:

STANDARD: Declare a Site Area Emergency due to: SAT MFB 1 and 2 de-energized AND Failure to restore power to at least one MFB within 15 minutes from the time of loss of both offsite and onsite AC power. UNSAT STOP TIME #1: Time SAE Declared (SAT is < Start Time ÷ 15 minutes)

COMMENTS:

ADMIN-408 Ri Page 6 of 10 STEP 5: Step 2.3 & 2.4 STANDARD: Determine Steps 2.3 and 2.4 do not apply SAT COMMENTS:

UNSAT STEP 6: Step 2.5 Appoint Control Room Offsite Communicator(s) and notify him to be prepared to transmit messages.

SAT STANDARD: Per Initial Conditions, Offsite Communicator is already established COMMENTS:

UNSAT STEP 7: Step 2.6 IAAT Changing plant conditions require an emergency classification upgrade, THEN Notify Offsite Communicator to complete the in-progress notifications per RP!0/B/1 000/1 5A, (Offsite Communications From The SAT CR)

AND Re-initiate a clean copy of this procedure for the upgraded classification and stop this procedure.

UN SAT STANDARD: An Upgrade is about to occur with the SAE declaration. The communicator is notified to complete Message #1. A clean message sheet for the Upgrade to SAE is started.

COMMENTS:

STEP 8: Step 2.7 CRITICAL STEP Obtain the appropriate Offsite Notification form from the Emergency Plan cart. SAT STANDARD: Initial Site Area Emergency form # 4.5.S.1 isselected and candidate continues to fill-out the above form per the Step 2.7 substeps. UNSAT COMMENTS:

ADMIN-408 Ri Page 7 of 10 STEP 9: Step 2.7 CRITICAL STEP Ensure EAL # as determined by RP/0/B/1000/001 matches Line 4. (4.5.S.1)

Line 1 - Mark appropriate box Drill or Actual Event (DRILL) SAT Line 1 - Enter Message # (#2)

Line 2 - Mark Initial (INITIAL marked)

UNSAT Line 6 A. Mark Is Occurring if any of the following are true:

RlAs 40, 45, or 46 are increasing or in alarm (TRUE-Is Occurring is marked due to RIA-40 in alarm)

If containment is breached

Containment pressure> 1 psig B. Mark None if none of the above is applicable.

Line 7 - If Line 6 Box B or C is marked, mark Box D. Otherwise mark Box A (mark D)

Line 8 - Mark Stable unless an upgrade or additional PARs are anticipated within an hour. (Stable, improving or degrading- does not matter- this part will not be a critical step)

Refer to Enclosure 4.9, (Event Prognosis Definitions)

Line 10 - Military time and date of declaration (Refer to date/time in Step 2.2)

(Inserts time from STEP 1)

Line 11 - If more than one unit affected, mark All (Unit I only)

Line 12 - Mark affected unit(s) (reference Line 11) AND enter power level of affected unit(s) or time/date of shutdown {14}

Line 13 - If the OSM has no remarks, write None (NOT BLANK)

If Condition A exists ensure following PARs are included Line 5.

A. Evacuate: Move residents living downstream of the Keowee Hydro Project dams to higher ground B. Other: Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed.

Line 17 - OSM signature, CURRENT Time/Date (MUST SIGN)

STANDARD: Correctly fills out Emergency Notification Form in accordance with Key:

NOTE: All of the BLUE high-lighted items on the form are CRITICAL (17 items; 80% 14 items; can miss 3 items).

COMMENTS:

ADMIN-408 Ri Page 8 of 10 STEP 10: Step 2.7 Continued TIME Line 17 - OSM signature, CURRENT Time/Date (MUST SIGN) CRITICAL STEP STANDARD: Correctly fills out Emergency Notification Form in accordance with Form complete within 15 minutes of classification in step 1.

STOP TIME #2: Time for Notification (SAT is <Stop Time #1 + 15 minutes)

COMMENTS:

END OF TASK

ADMIN-408 Ri Page 9 of 10 CRITICAL STEP EXPLANATIONS STEP # Explanation 1 The candidate needs to be able to utilize the procedure and determine the conditions meet a Site Area Emergency classification.

4 This is a time critical step. The candidate needs to declare the SAE within 15 minutes of beginning the JPM. (The start of the JPM is the beginning of the assessment period) 8 The correct form that matches the EAL # is selected.

9 The emergency notification form is accurately filled-out; items highlighted in BLUE on the KEY are the critical items.

10 This is a time critical step. The Candidate needs to complete the notification form within 15 minutes from the time the EAL was declared. (Declaration time is the time recorded in JPM step 4)

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS: THIS IS A DRILL 08:00:00 Unit 1 (Mode 1, 100%) has a SC Tube Rupture (SGTR) of 35 gpm in the 1A SG

. 1RIA-40 is in HIGH alarm 08:05:00 ERO activated by the OSM due to the SGTR 08:25:00 Offsite Communicator informs OSM that offsite agencies have received Message

1 at 0811 CURRENT CONDITIONS: THIS IS A DRILL While Unit 1 is shutting down due to the SGTR, the following event time-line occurs:

08:30:00 Unit 1 Turbine/Generator trips and CT-i locks out.

08:30:28 Unit 1 BOP dispatched to activate the SSF using AP/25, per EOP immediate manual actions step 3.5 RNO.

08:30:45 OATC performs Rule 3 for a loss of Main FDW; SGs being fed by 1TDEFWP.

08:32:50 Control Room crew notifies OSM that BOTH Keowee Units have experienced Emergency Lockouts and that CT-5 is available. Unit 2 BOP is performing EOP End. 5.38 (Restoration of Power).

08:41:00 SSF RO reports that flow has been established to Unit is RCP Seals per AP/25 08:47:05 Power has not been restored. Enclosure 5.38 is still in progress.

INITIATING CUE Current time is 0848. Perform the required actions of the Emergency Coordinator:

1. Determine Emergency Classification

2. Complete appropriate Emergency Notification Form for current conditions THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment while classifying the event. When required, other operators will maintain the Emergency Coordinators Log and perform the duties of the Control Room Offsite Communicator.

-* KE Y*

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM

1. DRILL ACTUAL EVENT MESSAGE #

2. INITIAL ØFOLLOW-UP NOTIFICATION: TIME DATE I I AUTHENTICATION #

3. SITE: Oconee Nuclear Site Confirmation Phone # (864) 882-7076

4. EMERGENCY ØUNUSUAL EVENT ALERT QSITE AREA EMERGENCY GENERAL EMERGENCY CLASSIFICATION:

BASED ON EAL# 4.5.S.1 EAL DESCRIPTION A loss of all offsite and onsite AC power for more than 15 minutes occurred with plant operating conditions requiring reactor coolant temperatures to has be maintained greater than 200F.

Current plant conditions DO NOT threaten public safety.

5. PROTECTIVE ACTION RECOMMENDATIONS:

ENONE EVACUATE SHELTER EJ CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.

ØOTHER

6. EMERGENCY RELEASE: ØNone jIs Occurring QHas Occurred

7. RELEASE SIGNIFICANCE: ØNot applicable Within normal operating limits Above normal operating limits lJnder Evaluation

8. EVENT PROGNOSIS: Ølmproving StabIe Degrading

9. METEOROLOGICAL DATA: Wind Direction* from degrees Wind Speed* mph

(* May not be available Precipitation*

for Initial Stability Class*

Notifications) EJ EJ E1 EI EEJ III EJ io.Ø DECLARATION

11. AFFECTED UNIT(S):

[] TERMINATION Time O8-fl Date To k Z EJ EJ Eti

12. Unit Status:

(Unattected Unit(s) status Not ltequrred for Initial Ui () % Power Shutdown at: Time O3o Date Notifications)

EJ U2 % Power Shutdown at: Time Date I I E1 U3 %Power Shutdown at: Time Date / /

13. REMARKS: 1ai.

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: Elevated Mixed Groun d UNITS:Ci CiIsec lICi/sec MAGNITUDE: Noble Gases: lodines: Particulates: Other:

FORM: Airborne Start Time: Date: / I Stop Time: Date I I

ØLiquid Start Time: Date: / / Stop Time: Date / I

15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date / /

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles 5 Miles 10 Miles Curc1

17. APPROVED BY:

oF

Title:

Emergency Coordinator Time: Date: / I NOTIFIED BY: RECEIVED BY: Time: Date: I I

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM

1. DRILL ACTUAL EVENT MESSAGE# I

2. INITIAL FOLLOW-UP NOTIFICATION: TIME 09i ( DATE (0 OLJ 5 AUTHENTICATION # L/ 7

3. SITE: Oconee Nuclear Site Confirmation Phone # (864) 882-7076

4. EMERGENCY ØUNUSUAL EVENT ElALERT SITE AREA EMERGENCY GENERAL EMERGENCY CLASSIFICATION:

BASED ON EAL# 4.2.U.1 EAL DESCRIPTION Water is leaking from the reactor coolant system in excess of allowed limits.

Current plant conditions DO NOT threaten public safety. --

5. PROTECTIVE ACTION RECOMMENDATIONS: ENONE (.k( 1 fflesdJl EVACUATE J

SHELTER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH EI CONSIDER OTHER

6. EMERGENCY RELEASE: None is Occurring Has Occurred

7. RELEASE SIGNIFICANCE: SNot applicable ElWithin normal operating limits QAbove normal operating limits Under Evaluation

8. EVENT PROGNOSIS: lmproving Stable Degrading

9. METEOROLOGICAL DATA: Wind Direction* from degrees Wind Speed* mph

(*

May not be available for Initial Precipitation* Stability Class* iZl EJ iJ EI i:i EJ EJ Notifications) io.Ø DECLARATION

[]

TERMINATION Time 09)0) Date TOtm4 t.

11 AFFECTED UNIT(S): Iii EJ El

12. Unit Status: Ui % Power Shutdown at: Time Date I I (Unaffected Unit(s) Status Not -tequired for Initial Notifications) U2 % Power Shutdown at: Time Date I /

EJ U3 % Power Shutdown at: Time Date I /

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: Elevated Mixed Ground UNITS:ECi Ci/sec lJCi/sec MAGNITUDE: Noble Gases: lodines: Particulates: Other:

FORM: ØAirborne Start Time: Date: / Stop Time: Date Liquid Start Time: Date: / Stop Time: Date

15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date I /

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles 5 Miles 10 Miles 17.APPROVEDBY: LC Ca,,ch4

Title:

Emergency Coordinator Time: Oo7 Date..d4y/9%.

NOTIFIED BY: V. jO/,(-f1- RECEIVED BY: Time: Date: I I

ML111881135

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