Text

Initial Exam 2009-302 Final Administrative JPMs
	ML100830118
Person / Time
Site:	Watts Bar
Issue date:	02/11/2010
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/09-302
	Download: ML100830118 (259)
	v • d • e

FACILITY NAME: Watts Bar Section 12 REPORTNUMBER:

__

________________

_ FINAL ADMINISTRATIVE JPMS CONTENTS:

ADMIN JPMs o 'As given' with changes made during administration annotated Location of Electronic Files: Submitted By:

OJ Ii /};/1 M /" Verified By: 1/ J we... . .>.Vvf ) J FACILITY NAME: __ .;..;W;..;::;;a:.=.;;tt;.;;;..s..;;;;B;;.;;;:a:.:,...r

__ Section 12

_______ _ FINAL ADMINISTRATIVE JPMS CONTENTS:

ADMIN JPMs o 'As given' with changes made during administration annotated Location of Electronic Files: Submitted By:

WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam A.1-1 RO/SRO Determine License Status WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam A.1-1 RO/SRO Determine License Status

) Task: WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam Determine License Status Active I Inactive Alternate Path: NI A Facility JPM #: None Safety Function:

Title: KIA 2.1.1 Knowledge of conduct of operations requirements Rating(s):

3.8/4.2 CFR: 41.10/45.13 Preferred Evaluation Location:

Preferred Evaluation Method: Simulator x

References:

Task Number: Task Standard:

Validation Time: In-Plant Perform x Simulate OPDP-10, "License Status Maintenance, Reactivation and Proficiency for Licensed Positions

," Rev. 1 RO-119-PAI-2.07-001 Title: Maintain active NRC License Applicant determines the correct status of each of the four Reactor Operator licenses.

Operator C and D are active, Operator A and B are Inactive 10 minutes Time Critical:

Yes No X ---===========================================================================

Applicant:

Time Start: NAME SSN Time Finish: Performance Rating: SAT UNSAT Performance Time Examiner:

__________________________

__

NAME SIGNATURE DATE ===========================================================================

COMMENTS WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam Determine License Status Active I Inactive Alternate Path: N/A Facility JPM #: None Safety Function:

Title: 2.1.1 Knowledge of conduct of operations requirements Rating(s):

3.8/4.2 CFR: 41.10/45.13 Preferred Evaluation Location:

Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate -=-=------

References:

Task Number: Task Standard:

Validation Time: OPDP-10, "License Status Maintenance, Reactivation and Proficiency for Licensed Positions

," Rev. 1 RO-119-PAI-2.07-001 Title: Maintain active NRC License Applicant determines the correct status of each of the four Reactor Operator licenses.

Operator C and D are active, Operator A and B are Inactive 10 minutes Time Critical:

Yes No X -----\---------------------------------------------------------------------------

1---------------------------------------------------------------------------

i Applicant:

Time Start: NAME SSN Time Finish: __ _ Performance Rating: SAT UNSAT Performance Time Examiner:

___________

_ ------______ 1 __ -NAME SIGNATURE DATE ===========================================================================

COMMENTS

) DIRECTION TO APPLICANT:

WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT 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. Four Reactor Operators have the following history: 2. All four have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years. 3. None of the 4 has worked any shift since 12/01/09.

4. Active/Inactive status and time on shift since October 1, 2009 is as follows for each of the Reactor Operators:

Table continued on next page. ) DIRECTION TO APPLICANT:

WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT 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. Four Reactor Operators have the following history: 2. All four have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years. 3. None of the 4 has worked any shift since 12/01/09.

4. Active/Inactive status and time on shift since October 1, 2009 is as follows for each of the Reactor Operators:

Table continued on next page.

INITIATING CUES: WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam 1. You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OAC position on the 0700 -1900 shift on January 31, 2010. INITIATING CUES: WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam 1. You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OAC position on the 0700 -1900 shift on January 31, 2010.

) ) WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ STEP 1.: Determine the Active 1 Inactive status of Operator A license. STANDARD:

e shift on 10106/09 DOES NOT count due to the 2.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months absence. OPDP-10, Section 3.2.4.B states "Absences from the Control Room for extended periods (Le., Fitness-far-Duty testing) will not count towards shift functions." COMMENTS:

STEP 2.: Determine the Active 1 Inactive status of Operator B license. STANDARD:

COMMENTS:

PAGE 5 OF 8 SAT/UNSAT CRITICAL STEP SAT UNSAT CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ STEP 1.: Determine the Active / Inactive status of Operator A license. STANDARD:

2.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months absence. OPDP-10, Section 3.2.4.B states "Absences from the Control Room for extended periods (i.e., Fitness-for-Duty testing) will not count towards shift functions." COMMENTS:

STEP 2.: Determine the Active / Inactive status of Operator B license. STANDARD:

COMMENTS:

PAGE 5 OF 8 SAT/UNSAT CRITICAL STEP SAT UNSAT CRITICAL STEP SAT UNSAT STEP 3.: STANDARD:

WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam STEP/STANDARD Determine the Active / Inactive status of Operator C license. Applicant determines the license is Active because the license was reactivated in the previous quarter, including working 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the Unit 1 OAC. The operator has also worked 4 twelve hour shifts in a license position during the quarter. COMMENTS: ,STEP4.: Determine the Active / Inactive status of Operator D license. ) STANDARD:

Applicant determines the license is Active because the license was reactivated in the previous quarter and that the required 5 twelve hour shifts in a license position during the quarter have also been completed.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time during which the plant tour was conducted does count as "actively performing the functions of an operator." COMMENTS:

END OF TASK STOP TIME __ _ ) PAGE 6 OF 8 SAT/UNSAT SAT UNSAT SAT UNSAT STEP 3.: STANDARD:

WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam STEP/STANDARD Determine the Active / Inactive status of Operator C license. Applicant determines the license is Active because the license was reactivated in the previous quarter, including working 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the Unit 1 OAC. The operator has also worked 4 twelve hour shifts in a license position during the quarter. COMMENTS: ,STEP 4.: Determine the Active / Inactive status of Operator D license. I I STANDARD:

Applicant determines the license is Active because the license was reactivated in the previous quarter and that the required 5 twelve hour shifts in a license position during the quarter have also been completed.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time during which the plant tour was conducted does count as "actively performing the functions of an operator." COMMENTS:

END OF TASK STOP TIME __ _ PAGE 6 OF 8 SAT/UNSAT SAT -UNSAT -SAT -UNSAT -

APPUCANTCUESHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPUCANT:

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. Four Reactor Operators have the following history: 2. All four have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years. 3. None of the 4 has worked any shift since 12/01/09.

4. Active/Inactive status and time on shift since October 1, 2009 is as follows for each of the Reactor Operators:

Table continued on next page. A.1-1 RO/SRO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:

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. Four Reactor Operators have the following history: 2. All four have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years. 3. None of the 4 has worked any shift since 12/01/09.

4. Active/Inactive status and time on shift since October 1, 2009 is as follows for each of the Reactor Operators:

Table continued on next page. A.1-1 RO/SRO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) INITIATING CUES: 1. You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OAG position on the 0700 -1900 shift on January 31, 2010. A.1-1 RO/SRO APPUCANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) INITIATING CUES: 1. You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OAG position on the 0700 -1900 shift on January 31, 2010. A.1-1 RO/SRO

) APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:

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. Four Reactor Operators have the following history: 2. All four have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years. 3. None of the 4 has worked any shift since 12/01/09.

4. Active/Inactive status and time on shift since October 1,2009 is as follows for each of the Reactor Operators:

Table continued on next page. A.1-1 RO/SRO ) ) APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:

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. Four Reactor Operators have the following history: 2. All four have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years. 3. None of the 4 has worked any shift since 12/01/09.

4. Active/lnactive status and time on shift since October 1, 2009 is as follows for each of the Reactor Operators:

Operator A License was active on October 1, 2009. 10102/09 Worked 0700-1900 shift as Unit 1 OAC. 10103/09 Worked 0700-1900 shift as Unit 1 OAC. 10104/09 Worked 0700-1900 shift in the Tagging Office. 10105/09 Worked 0700-1900 shift as Unit 1 OAC. 10106/09 Worked 0700-1900 shift as Unit 1 OAC. Called for Fitness for Duty Random Test., and was absent from the Control Room for 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . 11/14/09 Worked 1900-0700 shift as Unit 1 OAC. 11/17/09 Worked 1900-0700 shift as Unit 1 CRO. Operator B License was active on October 1, 2009. 10101/09 Worked 0700-1900 shift as Unit 1 OAC. 10102/09 Worked 0700-1900 shift in the Tagging Office. 10103/09 Worked 0700-1900 shift as Unit 1 CRO. 10105/09 Worked 0700-1900 shift as Unit 1 OAC. 10/14/09 Worked 1900-0700 shift as Unit 1 OAC. 11/02/09 Worked 0700-1900 shift in the Tagging Office. Operator C License was inactive on October 1, 2009. 10/5/09 thru 10/09/09 worked 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the Unit 1 OAC and completed all requirements for license reactivation.

11112/09 Worked 0700-1900 shift as Unit 1 OAC. 11/13/09 Worked 0700-1900 shift as Unit 1 OAC. 11/15/09 Worked 0700-1900 shift as Unit 1 OAC. 11/21/09 Worked 1900-0700 shift as Unit 1 OAC. Table continued on nextpage.

A.1-1 RO/SRO

) APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) INITIATING CUES: 1. You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OAG position on the 0700 -1900 shift on January 31, 2010. A.1-1 RO/SRO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) Operator 0 License was active on October 1, 2009. 10107109 Worked 0700-1900 shift as Unit 1 OAC. 10108/09 Worked 0700-1900 shift as Unit 1 OAC. Absent from the Control Room for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months while conducting a plant tour for a Reactor Operator who is reactivating their license. 10109/09 Worked 0700-1900 shift as Unit 1 OAC. 10/10109 Worked 0700-1900 shift as Unit 1 OAC. 10/11/09 Worked 0700-1900 shift as Unit 1 OAC. INITIATING CUES: 1. You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OAC position on the 0700 -1900 shift on January 31,2010. A.1-1 RO/SRO U!D TITLE OPDP-10 License Status Maintenance, Rev. 0001 Reactivation and Proficiency for Page 10f 20 Non-Licensed Positions Quality Related o Yes D No NPG Standard Department Procedure Effective Date 05-07-2009 I I Responsible Peer Team/Working Group: Operations Approved by: O. J. Miller 5-6-09 Corporate Functional Manager Date -[i!a] TITLE OPDP-10 License Status Maintenance, Rev. 0001 Reactivation and Proficiency for Page 1 of 20 Non-Licensed Positions Quality Related o Yes o No NPG Standard Department Procedure Effective Date 05-07-2009 Responsible Peer Team/Working Group: Operations Approved by: O. J. Miller 5-6-09 Corporate Functional Manager Date -

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 2 of20 Revision Log Revision or Affected Change Effective Page Number Date Numbers Description of Revision/Change 0 02/29/08 All Initial issue. This procedure removed from OPDP-1 Revision 8 Appendix 0 titled "License Status -Active/Inactive License".

Form OPDP-1-4 moved into OPDP-10 renumbered as Form OPDP-10-1.

1 05/07/09 All General revision.

Re-wrote procedure to make it as generic as possible for all of NPG, and changed wording for clarification through-out procedure.

Appendixes combined and reorganized and some were deleted. Form OPDP-1 0-1 deleted and incorporated into Appendix A. NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 2 of 20 Revision Log Revision or Affected Change Effective Page Number Date Numbers Description of Revision/Change 0 02/29/08 All Initial issue. This procedure removed from OPDP-1 Revision 8 Appendix 0 titled "License Status -Active/Inactive License".

Form OPDP-1-4 moved into OPDP-10 renumbered as Form OPDP-10-1.

1 05/07/09 All General revision.

Re-wrote procedure to make it as generic as possible for all of NPG, and changed wording for clarification through-out procedure.

Appendixes combined and reorganized and some were deleted. Form OPDP-10-1 deleted and incorporated into Appendix A.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 3 of 20

.. -Table of Contents 1.0 PURPOSE .................................................................................................................................

4 2.0 SCOPE ......................................................................................................................................

4 3.0 PROCESS .................................................................................................................................

4 3.1 Active License Status Maintenance

...........................................................................................

4 3.2 NUCLEAR PLANT REQUIREMENTS FOR MAINTAINING ACTIVE LICENSE STATUS .....................................................................................................................................

4 3.2:1 PURPOSE ............................................................................

.....................................

4 3.

2.2 REFERENCES

/BACKGROUND

................................................................................

4 3.2.3 RESPONSiBILITIES

...................................................................................................

5 3.2.4 INSTRUCTIONS

..................................................................................................

...... 5 3.2.5 DOCUMENTATION

....................................................................................................

6 3.3 NUCLEAR PLANT REQUIREMENTS FOR RETURNING AN INACTIVE LICENSE TO ACTIVE STATUS ................................................................................................

7 3.3.1 PURPOSE ..................................................................................................................

7 3.

3.2 REFERENCES

/BACKGROUND

................................................................................

7 3.3.3 RESPONSiBILITIES

...................................................................................................

7 3.3.4 INSTRUCTIONS

.........................................................................................................

7 3.3.5 DOCUMENTATION

....................................................................................................

9 3.4 STA and AUO Proficiency

........................................................................................................

10 4.0 RECORDS .............................*.................................................................................................

10 4.1 QA Records .............................................................................................................................

10 4.2 Non-QA Records ......................................................................................................................

10 5.0 DEFINITIONS

..........................................................................................................................

10 6.0 REQUIREMENTS AND REFERENCES

..................................................................................

10 Appendix A: Return to Active Status Checklist..

.....................................................................

11 Appendix B: Activation of SRO Licensejdlnited to Fuel Handling .......................................

18 Appendix C: Active Licensed Maintenance for Off-Shift Personnel Quarterly On-Shift Time Documentation

.............................................................................

20 NPG. Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 3 of 20 Table of Contents 1.0 PURPOSE .................................................................................................................................

4 2.0 SCOPE .......................................................................................................................................

4 3.0 PROCESS .........................................................................................

.......................................

4 3.1 Active License Status Maintenance

...........................................................................................

4 3.2 NUCLEAR PLANT REQUIREMENTS FOR MAINTAINING ACTIVE LICENSE STATUS .....................................................................................................................................

4 3.2.1 PURPOSE ....................

.............................................................................................

4 3.

2.2 REFERENCES

/BACKGROUND

................................................................................

4 3.2.3 RESPONSiBILITIES

...................................................................................................

5 3.2.4 INSTRUCTIONS

.........................................................................................................

5 3.2.5 DOCUMENTATION

....................................................................................................

6 3.3 NUCLEAR PLANT REQUIREMENTS FOR RETURNING AN INACTIVE LICENSE TO ACTIVE STATUS ................................................................................................

7 3.3.1 PURPOSE ..................................................................................................................

7 3.

3.2 REFERENCES

/BACKGROUND

................................................................................

7 3.3.3 RESPONSiBILITIES

...................................................................................................

7 3.3.4 INSTRUCTIONS

.........................................................................................................

7 3.3.5 DOCUMENTATION

....................................................................................................

9 3.4 STA and AUO Proficiency

........................................................................................................

10 4.0 RECORDS ...............................................................................................................................

10 4.1 QA Records .............................................................................................................................

10 4.2 Non-QA Records ......................................................................................................................

10 5.0 DEFINITIONS

..........................................................................................................................

10 6.0 REQUIREMENTS AND REFERENCES

..................................................................................

10 Appendix A: Return to Active Status Checklist..

.....................................................................

11 Appendix B: Activation of SRO Licensejdrrtited to Fuel Handling .......................................

18 Appendix C: Active Licensed Maintenance for Off-Shift Personnel Quarterly On-Shift Time Documentation

.............................................................................

20

) NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 4 of 20 1.0 PURPOSE The purpose of this procedure is to provide instructions for the maintenance of NRC SRO and RO licenses and for reactivation of SRO and RO licenses if inactive at Nuclear Power Group (NPG) sites and for proficiency requirements for STA position and AUO position.

2.0 SCOPE This procedure applies to the reactivation and maintenance of Senior Reactor Operator and Reactor Operator licenses in accordance with 1 OCFR55.53 and to SRO limited Fuel Handling License activation at NPG sites. (Maintenance of proficiency for STAs and AUOs is contained in TRN-11:6 and TRN-11.1.)

3.0 PROCESS 3.1 Active License Status Maintenance A. To maintain an active status, the licensee shall actively perform the functions of an operator or senior operator for a minimum of seven 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts a calendar quarter or five 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts a calendar quarter. It is the licensee's responsibility to maintain cognizance of his/her license status. B. Each site will ensure a listing of "Active" license status is provided to the SM at the end of each quarter. If an individual's license is currently listed as being "Inactive" (not on the active list), it is imperative that he or she not perform in a TS licensed position.

3.2 NUCLEAR PLANT REQUIREMENTS FOR MAINTAINING ACTIVE LICENSE STATUS 3.2.1 PURPOSE The purpose of this section is to provide administrative instructions in order to comply with 10CFR55.53 (e), ... "actively performing the functions of an operator or senior operator." 3.

2.2 REFERENCES

/BACKGROUND A. References

1. 10 CFR 50.54(m)(2)(i)

2. 10 CFR 55.4 3. 10 CFR 55.53(e) 4. NUREG-1262

-Preface; pages 71-80 5. NUREG-1021

-ES-605 6. Technical Specification NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 4 of20 1.0 PURPOSE The purpose of this procedure is to provide instructions for the maintenance of NRC SRO and RO licenses and for reactivation of SRO and RO licenses if inactive at Nuclear Power Group (NPG) sites and for proficiency requirements for STA position and AUO position.

2.0 SCOPE This procedure applies to the reactivation and maintenance of Senior Reactor Operator and Reactor Operator licenses in accordance with 1 OCFR55.53 and to SRO limited Fuel Handling License activation at NPG sites. (Maintenance of proficiency for STAs and AUOs is contained in TRN-11:6 and TRN-11.1.)

3.0 PROCESS 3.1 Active License Status Maintenance A. To maintain an active status, the licensee shall actively perform the functions of an operator or senior operator for a minimum of seven 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts a calendar quarter or five 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts a calendar quarter. It is the licensee's responsibility to maintain cognizance of his/her license status. B. Each site will ensure a listing of "Active" license status is provided to the SM at the end of each quarter. If an individual's license is currently listed as being "Inactive" (not on the active list), it is imperative that he or she not perform in a TS licensed position.

3.2 NUCLEAR PLANT REQUIREMENTS FOR MAINTAINING ACTIVE LICENSE STATUS 3.2.1 PURPOSE The purpose of this section is to provide administrative instructions in order to comply with 10CFR55.53 (e), ... "actively performing the functions of an operator or senior operator." 3.

2.2 REFERENCES

/BACKGROUND A. References

1. 10 CFR 50.54(m)(2)(i)

2. 10 CFR 55.4 3. 10 CFR 55.53(e)

4. NUREG-1262

-Preface; pages 71-80 5. NUREG-1021

-ES-605 6. Technical Specification NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 5 of 20 3.

2.2 REFERENCES

/BACKGROUND (continued)

B. To maintain active status, per 55.53(e), Conditions of License, the licensee shall actively perform the functions of an operator or senior operator on a minimum of seven (7) 8-hour or five (5) 12-hour shifts per calendar quarter. . C. Actively performing the functions of an operator or senior operator means that an individual has a position on the shift crew that requires the individual to be licensed as defined in Technical Specification, and that the individual carries out and is responsible for the duties covered by that position.

D. Technical Specifications and 10 CFR 50.54 specify the minimum requirement per shift. E. Licensed personnel who do not meet these requirements are designated as inactive licensees.

3.2.3 RESPONSIBILITIES A. All licensed personnel who maintain an active license shall comply with these requirements.

B. All licensed personnel who maintain an active license and are OFF SHIFT (not part of a rotating shift) shall provide on-shift documentation quarterly to the Operations Superintendent.

[Appendix C]. C. The Operations Superintendent is responsible for administering this program and documentation.

3.2.4 INSTRUCTIONS A. Individuals assigned to the following positions, AND NO OTHERS, on each shift, are considered to be actively performing the functions of an operator or senior operator in order to maintain active license status: . 1. Shift Manager 2. Unit Supervisor

[Control Room SRO] 3. Licensed Unit Operators assigned Control Room duties. B. To be granted credit for a shift, the individual will be present from shift turnover thru shift turnover.

Short absences from the Control Room are acceptable (i.e., rest room visits, pre-job briefs, plant tours, supervising activities).

Absences from the Control Room for extended periods (i.e., Fitness-for-Duty testing) will not count towards shift functions.

For these type of cases, the time absence will be made up by working additional time on another shift or an additional shift. C. The shift period is defined by the schedule worked by the rotating shift crews. Either 12-hour or 8-hour shifts is the normal. If a 12-hour shift rotation is used, then a minimum of five (5) shifts in a licensed position per quarter, or if an 8-hour shift rotation is used, then a minimum of seven (7) shifts in a licensed position per quarter is required in order to remain "active." NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 5 of 20 3.

2.2 REFERENCES

/BACKGROUND (continued)

B. To maintain active status, per 55.53(e), Conditions of License, the licensee shall actively perform the functions of an operator or senior operator on a minimum of seven (7) 8-hour or five (5) 12-hour shifts per calendar quarter. C. Actively performing the functions of an operator or senior operator means that an individual has a position on the shift crew that requires the individual to be licensed as defined in Technical Specification, and that the individual carries out and is responsible for the duties covered by that position.

D. Technical Specifications and 10 CFR 50.54 specify the minimum requirement per shift. E. Licensed personnel who do not meet these requirements are designated as inactive licensees.

3.2.3 RESPONSIBILITIES A. All licensed personnel who maintain an active license shall comply with these requirements.

B. All licensed personnel who maintain an active license and are OFF SHIFT (not part of a rotating shift) shall provide on-shift documentation quarterly to the Operations Superintendent.

[Appendix C]. C. The Operations Superintendent is responsible for administering this program and docu mentation.

3.2.4 INSTRUCTIONS A. Individuals assigned to the following positions, AND NO OTHERS, on each shift, are considered to be actively performing the functions of an operator or senior operator in order to maintain active license status: 1. Shift Manager 2. Unit Supervisor

[Control Room SRO] 3. Licensed Unit Operators assigned Control Room duties. B. To be granted credit for a shift, the individual will be present from shift turnover thru shift turnover.

Short absences from the Control Room are acceptable (i.e., rest room visits, pre-job briefs, plant tours, supervising activities).

Absences from the Control Room for extended periods (i.e., Fitness-for-Duty testing) will not count towards shift functions.

For these type of cases, the time absence will be made up by working additional time on another shift or an additional shift. C. The shift period is defined by the schedule worked by the rotating shift crews. Either 12-hour or 8-hour shifts is the normal. If a 12-hour shift rotation is used, then a minimum of five (5) shifts in a licensed position per quarter, or if an 8-hour shift rotation is used, then a minimum of seven (7) shifts in a licensed position per quarter is required in order to remain "active."

) \"C::--) NPGStandard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 6 of 20 3.2.4 INSTRUCTIONS (continued)

D. Technical Specifications / 1 OCFR50 for each site contains the requirement for the minimum number of licenses required.

However, only the positions listed for the applicable site as listed in 3.2.4A above qualify for license maintenance.

E. Ifthe operating crews com/ertfrom an 8-hour to a 12-hour, or a 12-hour to an 8-hour shift rotation schedule during a calendar quarter, then the number of shifts required to be worked in a licensed position to be credited for active license maintenance on the combination of shifts (8's and 12's) will be in accordance with the following:

8-Hour Shifts TO 12-Hour Shifts 12-Hour Shifts TO 8-Hour Shifts # Shifts Completed

Additional Shifts # Shifts Completed

Additional Shifts Prior to Change Needed On New Prior to Change Needed On New Schedule Schedule 6 1 4 2 5 2 3 '3 4 3 2 5 3 3 1 6 2 4 0 7 1 5 --0 5 --F. The individual assigned to one of the positions designated for maintaining an active license, shall log "in" and "out" on the Narrative Lo!;) for each shift worked. G. The Shift Manager on each shift shall verify that the data entered into the "Shift Staffing Log" in the Narrative Log is correct for their shift. H. A Shift Manager shall actively perform the functions of a Shift Manager a minimum of . seven 8-hour or five 12-hour shifts per calendar quarter to remain current as a Shift Manager. 3.2.5 DOCUMENTATION A. Appendix C contains the form "Active Licensed Maintenance for Off-Shift Personnel, Quarterly On-Shift Time Documentation" that is submitted by active off-shift licensed individuals each quarter to the Operations Superintendent. . B. The Control Room logs are the legal record of watchstanderassignment.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 6 of20 3.2.4 INSTRUCTIONS (continued)

D. Technical Specifications / 1 OCFR50 for each site contains the requirement for the minimum number of licenses required.

However, only the positions listed for the applicable site as listed in 3.2.4A above qualify for license maintenance.

E. If the operating crews convert from an 8-hour to a 12-hour, or a 12-hour to an 8-hour shift rotation schedule during a calendar quarter, then the number of shifts required to be worked in a licensed position to be credited for active license maintenance on the combination of shifts (8's and 12's) will be in accordance with the following:

8-Hour Shifts TO 12-Hour Shifts 12-Hour Shifts TO 8-Hour Shifts # Shifts Completed

Additional Shifts # Shifts Completed

Additional Shifts Prior to Change Needed On New Prior to Change Needed On New Schedule Schedule 6 1 4 2 5 2 3 3 4 3 2 5 3 3 1 6 2 4 0 7 1 5 --0 5 --F. The individual assigned to one of the positions designated for maintaining an active license, shall log "in" and "out" on the Narrative Log for each shift worked. G. The Shift Manager on each shift shall verify that the data entered into the "Shift Staffing Log" in the Narrative Log is correct for their shift. H. A Shift Manager shall actively perform the functions of a Shift Manager a minimum of seven 8-hour or five 12-hour shifts per calendar quarter to remain current as a Shift Manager. 3.2.5 DOCUMENTATION A. Appendix C contains the form "Active Licensed Maintenance for Off-Shift Personnel, Quarterly On-Shift Time Documentation" that is submitted by active off-shift licensed individuals each quarter to the Operations Superintendent.

B. The Control Room logs are the legal record of watchstander assignment.

) ) ) / NPG Standard License Status Maintenance, OPDP-10 3.3 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 7 of 20 --------NUCLEAR PLANT REQUIREMENTS FOR RETURNING AN INACTIVE LICENSE TO ACTIVE STATUS 3.3.1 PURPOSE This section is intended to provide guidance, to return a licensed individual to an active status. 3.

3.2 REFERENCES

/BACKGROUND A. The Code of Federal Regulation, 10 CFR55.53 f(2) specifies returning a license to active status. The intent of the code is to ensure proficiency in the conduct of licensed activities prior to assuming licensed duties. The following requirements are addressed as part of this code: 1. The qualifications and status of the licensee are current and valid. This requirement ensures the licensee has completed all required requalification training, including plant modifications and industry events; and secondly, that all conditions of his/her license are still being met. 2. This licensee has completed a minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under the direction of a reactor operator or senior operator, as appropriate, and in the position to which the individual will be assigned.

This ensures that an active license is directing or performing the manipulations of plant controls, and allows the inactive individual to obtain proficiency at his/her watch station. Included within the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months is the following:

a. A complete review of turnover procedures by the reactor operator or senior reactor operator as appropriate for the position, to ensure that the licensee is familiar with current shift turnover practices.

b. A complete tour of the plant, to ensure the individual is aware of changing plant conditions that have occurred since he/she has been inactive.

The individual performing the tour will be accompanied by an active Licensed Reactor Operator or an active Licensed Senior Reactor Operator, as appropriate.

3.3.3 RESPONSIBILITIES A. All licensed personnel who maintain a license shall comply with these requirements to return to active status. The Operations Superintendent is responsible for administering the process. 3.3.4 INSTRUCTIONS A. The following guidelines are to be used when reactivating a license: 1. Prior to standing the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual shall meet with the Operation Training Manager and the Operations Superintendent to discuss his/her current status and any standards and/or expectations.

For certain individuals, additional requirements may be imposed (greater than those required by code) if directed by the Operations Superintendent.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 7 of 20 3.3 NUCLEAR PLANT REQUIREMENTS FOR RETURNING AN INACTIVE LICENSE TO ACTIVE STATUS 3.3.1 PURPOSE This section is intended to provide guidance, to return a licensed individual to an active status. 3.

3.2 REFERENCES

/BACKGROUND A. The Code of Federal Regulation, 10 CFR55.53 f(2) specifies returning a license to active status. The intent of the code is to ensure proficiency in the conduct of licensed activities prior to assuming licensed duties. The following requirements are addressed as part of this code: 1. The qualifications and status of the licensee are current and valid. This requirement ensures the licensee has completed all required requalification training, including plant modifications and industry events; and secondly, that all conditions of his/her license are still being met. 2. This licensee has completed a minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under the direction of a reactor operator or senior operator, as appropriate, and in the position to which the individual will be assigned.

This ensures that an active license is directing or performing the manipulations of plant controls, and allows the inactive individual to obtain proficiency at his/her watch station. Included within the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months is the following:

a. A complete review of turnover procedures by the reactor operator or senior reactor operator as appropriate for the position, to ensure that the licensee is familiar with current shift turnover practices.

b. A complete tour of the plant, to ensure the individual is aware of changing plant conditions that have occurred since he/she has been inactive.

The individual performing the tour will be accompanied by an active Licensed Reactor Operator or an active Licensed Senior Reactor Operator, as appropriate.

3.3.3 RESPONSIBILITIES A. All licensed personnel who maintain a license shall comply with these requirements to return to active status. The Operations Superintendent is responsible for administering the process. 3.3.4 INSTRUCTIONS A. The following guidelines are to be used when reactivating a license: 1. Prior to standing the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual shall meet with the Operation Training Manager and the Operations Superintendent to discuss his/her current status and any standards and/or expectations.

For certain individuals, additional requirements may be imposed (greater than those required by code) if directed by the Operations Superintendent.

) ) NPG Standard License Status Maintenance, OPDP-10 Department ,Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 8 of 20 3.3.4 INSTRUCTIONS (continued)

2. The following positions are the only ones that qualify for reactivation of a license: a. Shift Manager b. Unit Supervisor

[Control Room SRO] c. Licensed Unit Operators assigned Control Room duties. 3. The individual shall be under the direct supervision of an active licensed individual in the position to which the individual will be assigned.

To receive credit for a shift, the individual will be present from shift turnover thru shift turnover.

Short absences from the Control Room are acceptable (Le., rest room visits, pre-job briefs, plant tours, supervising activities);

however, the total re-activation time under supervision will total at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months . 4. The individual shall make a*Narrative log entry at the start of the shift which will include the following at a minimum: a. Name and time of assuming shift b. Shift Position (as identified in 3.3.4.A.2) assumed under direction

c. Name of the operators (Board and Desk), Control Room SRO, or Shift Manager providing supervision.

5. The individual shall make a Narrative Log entry at the end of the shift indicating they have completed the shift under supervision.

A copy of the Narrative log for each shift worked shall be obtained for processing after the break-in is complete.

This will be the entire log for the shift worked and not selected entries. 6. The individual shall complete Appendix A, page 2, for each shift listing unit, shift, position assuming, along with the activities,the individual was personally involved in. Time, Position, Unit, Activity, and Date must be filled out for each activity performed.

The position the individual is holding must be one of the three indicated in step 3.3.4.A.2.

Appendix A is to be used to account for a plant tour and shift turnover briefing.

Appendix A is required to be signed by the Operations Superintendent ensuring that all appendix pages have been reviewed and once reviewed, these pages will be submitted with the reactivation documentation and will become part of the individuals training record. Attach a copy of security door printouts for both the licensed individual reactivating and the supervising active license for each reactivation shift. 7. If an individual moves from one unit to another unit during the same shift for the purpose of breaking-in on the other unit, the individual shall make an log entry indicating that they are moving to the other unit to continue their break-in.

Another entry, to include the areas in 3.3.4.A.4, will be made when the individual goes under instruction on the new unit. This requirement is not applicable to an individual being re-activated as a Shift Manager since the break-in would still be under the same individual.

NPG Standard License Status Maintenance, OPDP-10 Department ,Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 8 of20 3.3.4 INSTRUCTIONS (continued)

2. The following positions are the only ones that qualify for reactivation of a license: a. Shift Manager b. Unit Supervisor

[Control Room SRO] c. Licensed Unit Operators assigned Control Room duties. 3. The individual shall be under the direct supervision of an active licensed individual in the position to which the individual will be assigned.

To receive credit for a shift, the individual will be present from shift turnover thru shift turnover.

Short absences from the Control Room are acceptable (Le., rest room visits, pre-job briefs, plant tours, supervising activities);

however, the total re-activation time under supervision will total at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months . 4. The individual shall make a>Narrative log entry at the start of the shift which will include the following at a minimum: a. Name and time of assuming shift b. Shift Position (as identified in 3.3.4.A.2) assumed under direction

c. Name of the operators (Board and Desk), Control Room SRO, or Shift Manager providing supervision.

5. The individual shall make a Narrative Log entry at the end of the shift indicating they have completed the shift under supervision.

A copy of the Narrative log for each shift worked shall be obtained for processing after the break-in is complete.

This will be the entire log for the shift worked and not selected entries. 6. The individual shall complete Appendix A, page 2, for each shift listing unit, shift, position assuming, along with the activities the individual was personally involved in. Time, Position, Unit, Activity, and Date must be filled out for each activity performed.

The position the individual is holding must be one of the three indicated in step 3.3.4.A.2.

Appendix A is to be used to account for a plant tour and shift turnover briefing.

Appendix A is required to be signed by the Operations Superintendent ensuring that all appendix pages have been reviewed and once reviewed, these pages will be submitted with the reactivation documentation and will become part of the individuals training record. Attach a copy of security door printouts for both the licensed individual reactivating and the supervising active license for each reactivation shift. 7. If an individual moves from one unit to another unit during the same shift for the purpose of breaking-in on the other unit, the individual shall make an log entry indicating that they are moving to the other unit to continue their break-in.

Another entry, to include the areas in 3.3.4.A.4, will be made when the individual goes under instruction on the new unit. This requirement is not applicable to an individual being re-activated as a Shift Manager since the break-in would still be under the same individual.

) / NPG Standard License'Status Maintenance, OPDP":10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 9 of 20 3.3.4 INSTRUCTIONS (continued)

8. The individual shall review the turnover procedures with an active reactor operator or senior reactor operator, as applicable.

The Plant Operations Manager, Operations Superintendent, and/or Operations Support Superintendent will determine the minimum procedures to be reviewed.

9. As a minimum, the following shall be completed to satisfy the plant tour requirement:

a. Review of Control Room logs and equipment status in order to ascertain current plant status and configuration.

b. Review of radiological conditions in the plant. c. Tour of accessible plant areas as listed in Appendix A, pages 5,6 or 7, with special attention if safety-related systems are involved.

(1) Prior to beginning the tour, a discussion should be held with the Shift Manager to obtain guidance on which areas to focus on during the plant tour. (2) Document the tour on Appendix A, page 4. (3) The plant tour will be performed by the individual accompanied by an active Licensed Reactor Operator or an active Senior Reactor Operator, as applicable,and logged in the Narrative Log. B. Returning an Inactive Shift Manager to active Status 1. Before resumption of independent Shift Manager duties, the Plant Manager or designee will certify the following: (In addition to Section 3.3.4A) a. The individual has completed 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of break-in under a currently active Shift Manager. b. Documentation of completion shall be forwarded to Operations Training Manager for retention.

3.3.5 DOCUMENTATION The completed Appendix A with Narrative logs, and all required signatures on the "Return To Active Status Checklist" (Appendix A) shall be completed prior to being reactivated.

The "Return To Active Status Checklist" form,Appendices A, and the narrative logs will then become part of the individual's training record. For the Shift Manager, the log of activities outside of the Control Room will also become part of the individual's training record, if applicable.

Complete and Attach Appendix A Page 1 of 7, Licensee Documentation Form (SRO & RO), as the cover-sheet for this record. NPG Standard LicenseStatus Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 9 of 20 3.3.4 INSTRUCTIONS (continued)

8. The individual shall review the turnover procedures with an active reactor operator or senior reactor operator, as applicable.

The Plant Operations Manager, Operations Superintendent, and/or Operations Support Superintendent will determine the minimum procedures to be reviewed.

9. As a minimum, the following shall be completed to satisfy the plant tour requirement:

a. Review of Control Room logs and equipment status in order to ascertain current plant status and configuration.

b. Review of radiological conditions in the plant. c. Tour of accessible plant areas as listed in Appendix A, pages 5, 6 or 7, with special attention if safety-related systems are involved.

(1) Prior to beginning the tour, a discussion should be held with the Shift Manager to obtain guidance on which areas to focus on during the plant tour. (2) Document the tour on Appendix A, page 4. (3) The plant tour will be performed by the individual accompanied by an active Licensed Reactor Operator or an active Senior Reactor Operator, as applicable, and logged in the Narrative Log. B. Returning an Inactive Shift Manager to active Status 1. Before resumption of independent Shift Manager duties, the Plant Manager or designee will certify the following: (In addition to Section 3.3.4A) a. The individual has completed 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of break-in under a currently active Shift Manager. b. Documentation of completion shall be forwarded to Operations Training Manager for retention.

3.3.5 DOCUMENTATION The completed Appendix A with Narrative logs, and all required signatures on the "Return To Active Status Checklist" (Appendix A) shall be completed prior to being reactivated.

The "Return To Active Status Checklist" form, Appendices A, and the narrative logs will then become part of the individual's training record. For the Shift Manager, the log of activities outside of the Control Room will also become part of the individual's training record, if applicable.

Complete and Attach Appendix A Page 1 of 7, Licensee Documentation Form (SRO & RO), as the cover-sheet for this record.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 10 of 20 3.4 STA and AUO Proficiency A. The STA will remain active by complying with Section 3.4 of TRN-11.6.

B. The AUO will remain active by complying with requirements of TRN-11 .1. 4.0 RECORDS 4.1 QA Records Appendix A, "Return to Active Status Checklist" Appendix B, "Activation of SRO License Limited to Fuel Handling" 4.2 Non-QA Records Appendix C, "Active Licensed Maintenance for Off-Shift Personnel Quarterly On-Shift Time Documentation" 5.0 DEFINITIONS None 6.0 REQUIREMENTS AND REFERENCES Requirements and References are contained in the "OPDP-10 REQ & REF" document.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 10 of 20 3.4 ST A and AUO Proficiency A. The ST A will remain active by complying with Section 3.4 of TRN-11.6.

B. The AUO will remain active by complying with requirements of TRN-11.1.

4.0 RECORDS 4.1 QA Records Appendix A, "Return to Active Status Checklist" Appendix B, "Activation of SRO License Limited to Fuel Handling" 4.2 Non-QA Records Appendix C, "Active Licensed Maintenance for Off-Shift Personnel Quarterly On-Shift Time Documentation" 5.0 DEFINITIONS None 6.0 REQUIREMENTS AND REFERENCES Requirements and References are contained in the "OPDP-10 REQ & REF" document.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 11 of 20 Appendix A (Page 1 of 7) Return to Active Status Checklist LICENSEE DOCUMENTATION FORM COVER SHEET (SRO & RO) A. License Status Current Licensee B. 40 Hours on Shift SRO 0 RO 0

Attach copy of Operating Log for each shift. C. Tour of Plant (Check box below when complete) o AppendixA D. Shift Turnover (check one) 1. Attended shift turnover briefings No. of Times ____ _ 2. Observed shift turnover No. of Times -----3. Reviewed shift turnover checklist applicable to the position Date -----Printed Name Licensee's Signature E. Licensee qualifications current and valid including:

A physical in the last two years.

Satisfactory completion of license operator requalification training . . Operations Training Manager/Designee Date F. Documentation

Attach copies of applicable forms from Appendix A. G. Licensee meets reactivation requirements in Appendix A and is reinstated to active status. Operations Superintendent/Designee Date , ) NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 11 of 20 Appendix A (Page 1 of 7) Return to Active Status Checklist LICENSEE DOCUMENTATION FORM COVER SHEET (SRO & RO) A. License Status Current Licensee B. 40 Hours on Shift SRO D RO D

Attach copy of Operating Log for each shift. C. Tour of Plant (Check box below when complete)

D AppendixA D. Shift Turnover 1. Attended shift turnover briefings

2. Observed shift turnover (check one) 3. Reviewed shift turnover checklist applicable to the position No. of Times -----No. of Times -----Date -----Printed Name Licensee's Signature E. Licensee qualifications current and valid including:

A physical in the last two years.

Satisfactory completion of license operator requalification training.

Operations Training Manager/Designee Date F. Documentation

Attach copies of applicable forms from Appendix A. G. Licensee meets reactivation requirements in Appendix A and is reinstated to active status. Operations SuperintendenUDesignee Date NPG Standard Department Procedure Licensee License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix A (Page 2 of 7) Return to Active Status Checklist OPDP-10 Rev. 0001 Page 12 of 20 The licensed individual has completed a minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under the direction of an active licensed operator of qualifications equal to or above the position to which the individual will be assigned.

This instruction shall be one on one. SRO-licensed individuals assuming a SROposition shall perform the actions and responsibilities of the Unit Supervisor (US) or Shift Manager (SM). SRO or RO-licensed individuals assuming an RO position shall perform the actions of a Unit Operator (UO). Active SROs are fully qualified to perform RO duties. The 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months must have included a complete review of all required shift tumover procedures.

One complete on-coming shift turnover and one complete off-going shift turnover including briefing, board walkdown, etc. is required for license re-activation.

SRO licensed individuals who reactivate their license solely to allow watchstanding in the UO must complete 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions as a Unit UO under the directions of a UO prior to being assigned to the position.

Attach a copy of security door printouts for both the licensed individual reactivating and the supervising license for each date listed below Narrative Log Entry made including the following:

Name & time assuming shift Licensee Shift Position assumed under direction, Name of operator providing supervision I Supervisor Date Hrsl Reactivation Activities Position Supervising Completed Total Performed Each Shift/Unit

(circle one) Licensee I SRO/RO I SRO/RO I SRO/RO I SRO/RO I SRO/RO On-coming Shift Turnover SRO/RO Off-Going Shift Turnover SRO/RO I Total hours of Reactivation Activities at the end of this shift. (Required

40) I __ HRS Narrative Log Entry made for completion of shift Licensee Copy of Completed Narrative Logs attached to this form Licensee Licensed individual has reviewed the required reading, standing orders, and ODMls for the Licensee period of absence or for the most recent requalification cycle to present date whichever is shorter and the current standing orders. Shift Manager has reviewed this form (SM) Verified by: ________________

_ Superintendent

-Shift Operations Date NPG Standard Department Procedure Licensee License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix A (Page 2 of 7) Return to Active Status Checklist OPDP-10 Rev. 0001 Page 12 of 20 The licensed individual has completed a minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under the direction of an active licensed operator of qualifications equal to or above the position to which the individual will be assigned.

This instruction shall be one on one. SRO-licensed individuals assuming a SRO position shall perform the actions and responsibilities of the Unit Supervisor (US) or Shift Manager (SM). SRO or RO-licensed individuals assuming an RO position shall perform the actions of a Unit Operator (UO). Active SROs are fully qualified to perform RO duties. The 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months must have included a complete review of all required shift turnover procedures.

One complete on-coming shift turnover and one complete off-going shift turnover including briefing, board walkdown, etc. is required for license re-activation.

SRO licensed individuals who reactivate their license solely to allow watchstanding in the UO must complete 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions as a Unit UO under the directions of a UO prior to being assigned to the position.

Attach a copy of security door printouts for both the licensed individual reactivating and the supervising license for each date listed below Narrative Log Entry made including the following:

Name & time assuming shift Licensee Shift Position assumed under direction, Name of operator providing supervision Supervisor Date Hrsl Reactivation Activities Position Supervising Completed Total Performed Each ShiftlUnit

(circle one) Licensee I SRO/RO I SRO/RO I SRO/RO I SRO/RO I SRO/RO On-coming Shift Turnover SRO/RO Off-Going Shift Turnover SRO/RO I Total hours of Reactivation Activities at the end of this shift. (Required

40) I __ HRS Narrative Log Entry made for completion of shift Licensee Copy of Completed Narrative Logs attached to this form Licensee Licensed individual has reviewed the required reading, standing orders, and ODMls for the Licensee period of absence or for the most recent requalification cycle to present date whichever is shorter and the current standing orders. Shift Manager has reviewed this form (SM) Verified by: -----------------------------------------

Superintendent

-Shift Operations Date NPG Standard Department To: Operations Training Manager From: Operations Superintendent License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix A (Page 3 of 7) Return to Active Status Checklist Date NAME: ________________________________________

___ OPDP-10 Rev. 0001 Page 13 of 20 A. Licensee requalification training is current, including a simulator evaluation within the past 12 months in the position(s) to be assumed and the licensee has had a physical in the last two years. (To be verified prior to standing the 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under instruction.)

Date: . I Operational Training Manager B. The qualifications and status of the licensed individual listed above are current and valid, and Standards and Expectations have been discussed, prior to standing the 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under instruction.

Date: Operational Superintendent C. If the licensee has a medical restriction requiring corrective lenses, the licensee will verify that he/she has the proper corrective lenses required to Don SCBA available while performing license duties (N/A if corrective lenses are not required).

Date: Licensee D. The above licensed individual has completed at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under the direction of an operator or senior operator, as appropriate, including a complete tour of the plant accompanied by an active licensed RO or SRO, as applicable, and review of all required shift turnover procedures.

Date: Licensee Date: Shift Manager Date: Operations Superintendent Date: Operations Manager E. The above licensed individual is authorized to resume licensed activities.

Date: Plant Manager F. Complete and Attach Appendix A Page 1, Licensee Documentation Form (SRO & RO) as the cover sheet for this documentation.

cc: Operations Manager Training File . Licensee Date: REQUIREMENTS FOR RETURNING AN INACTIVE LICENSE TO ACTIVE STATUS NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Appendix A (Page 3 of 7) Page 13 of 20 Return to Active Status Checklist To: Operations Training Manager From: Operations Superintendent Date NAME ________________________________________

__ A. Licensee requalification training is current, including a simulator evaluation within the past 12 months in the position(s) to be assumed and the licensee has had a physical in the last two years. (To be verified prior to standing the 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under instruction.)

Date: I I -------Operational Training Manager B. The qualifications and status of the licensed individual listed above are current and valid, and Standards and Expectations have been discussed, prior to standing the 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under instruction.

Date: ___ I __ 1 __ __ Operational Superintendent C. If the licensee has a medical restriction requiring corrective lenses, the licensee will verify that he/she has the proper corrective lenses required to Don SCBA available while performing license duties (N/A if corrective lenses are not required).

Date: I I ---------Licensee D. The above licensed individual has completed at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under the direction of an operator or senior operator, as appropriate, including a complete tour of the plant accompanied by an active licensed RO or SRO, as applicable, and review of all required shift turnover procedures.

Date: I I ---------Licensee Date: I I ---------Shift Manager Date: I I ---------Operations Superintendent Date: I I ---------Operations Manager E. The above licensed individual is authorized to resume licensed activities.

Date: I I ---------Plant Manager F. Complete and Attach Appendix A Page 1, Licensee Documentation Form (SRO & RO) as the cover sheet for this documentation.

cc: Operations Manager Training File Licensee Date: I I -------REQUIREMENTS FOR RETURNING AN INACTIVE LICENSE TO ACTIVE STATUS

) NPG Standard License Status Maintenance, Department Reactivation and Proficiency for Procedure Non-Licensed Positions NAME: Licensee Appendix A (Page 4 of7) Return to Active Status Checklist (Completed ONCE per Reactivation)

Date: ______ _

Areas discussed with the Shift Manager to Tour in addition to the required areas specified on Appendix A pages 5, 6 or 7. As a minimum they should include Review Control Room Logs Radiological Conditions in the plant Significant Modifications and major maintenance activities.

OPDP-10 Rev. 0001 Page 14 of 20 (Shift Manager)

Areas other than those listed on Appendix A pages 5, 6 or 7 that were toured with another Licensed Operator and discussed with the Shift Manager

Licensed Operator verified Tour. (Tour Verifier)

Plant Tour discussed with Shift Manager (Shift Manager)

Narrative Log Entry made for completion of tour as well as being logged in as break-in for the tour duration. (Licensee)

Shift Turnover Procedure Reviewed NOTE: ROs CANNOT sign for SROs. (Licensed Operator)

Required amount of shifts have been completed (5-12 hour or 7-8 hours shifts) (Licensee)

NPG Standard License Status Maintenance, Department Reactivation and Proficiency for Procedure Non-Licensed Positions NAME: Licensee Date: Appendix A (Page 4 of 7) Return to Active Status Checklist (Completed ONCE per Reactivation)

Areas discussed with the Shift Manager to Tour in addition to the required areas specified on Appendix A pages 5, 6 or 7. As a minimum they should include Review Control Room Logs Radiological Conditions in the plant Significant Modifications and major maintenance activities.

OPDP-10 Rev. 0001 Page 14 of 20 (Shift Manager)

Areas other than those listed on Appendix A pages 5, 6 or 7 that were toured with another Licensed Operator and discussed with the Shift Manager

Licensed Operator verified Tour. (Tour Verifier)

Plant Tour discussed with Shift Manager (Shift Manager)

Narrative Log Entry made for completion of tour as well as being logged in as break-in for the tour duration. (Licensee)

Shift Turnover Procedure Reviewed NOTE: ROs CANNOT sign for SROs. (Licensed Operator)

Required amount of shifts have been completed (5-12 hour or 7-8 hours shifts) (Licensee)

) NPG Standard Department Procedure License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix A (Page 5 of 7) Return to Active Status Checklist BFN Tour Checklist OPDP-10 Rev. 0001 Page 15 of 20 During the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual has completed a plant tour including all areas listed below (excluding high radiation areas) under the direction of an operator (active license) or senior operator (active license) as appropriate.

Tours will include a review of all required NLO shift turnover procedures.

Attach a copy of the security door printouts for both the licensed individual reactivating and the supervising licensee for each date listed below. From NUREG-1021

-ES-605, "If a utility has developed a checklist of areas to tour, it is generally inappropriate to skip plant areas and mark the items as non-applicable unless there is sufficient justification (e.g., personnel or radiation hazard)." . Date Time List Areas Toured Supervising Licensee All elevations of Reactor Building including the Refuel Floor All elevations of Turbine Building All elevations of Control Building Units 1 & 3 Diesel Generator Buildings All elevations of the Intake Pumping Station including RHRSW/EECW p'ump Rooms Outside areas including the Stack, Off Gas Building, Transformer Yard, Switchyard, and Dry Cask Storage Review AUO Shift Turnovers Verified by: _________

--:'::---=-_-::-

___ _ Superintendent

-Shift Operations Date NPG Standard Department Procedure License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix A (Page 5 of 7) Return to Active Status Checklist BFN Tour Checklist OPDP-10 Rev. 0001 Page 15 of 20 During the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual has completed a plant tour including all areas listed below (excluding high radiation areas) under the direction of an operator (active license) or senior operator (active license) as appropriate.

Tours will include a review of all required NLO shift turnover procedures.

Attach a copy of the security door printouts for both the licensed individual reactivating and the supervising licensee for each date listed below. From NUREG-1021

-ES-605, "If a utility has developed a checklist of areas to tour, it is generally inappropriate to skip plant areas and mark the items as non-applicable unless there is sufficient justification (e.g., personnel or radiation hazard)." . Date Time List Areas Toured Supervising Licensee All elevations of Reactor Building including the Refuel Floor All elevations of Turbine Building All elevations of Control Building Units 1 & 3 Diesel Generator Buildings All elevations of the Intake Pumping Station including RHRSW/EECW Pump Rooms Outside areas including the Stack, Off Gas Building, Transformer Yard, Switchyard, and Dry Cask Storage Review AUO Shift Turnovers Verified by: ------------------------------------

Superintendent

-Shift Operations Date

) NPG Standard Department Procedure License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix A (Page 6 of 7) Return to Active Status Checklist SON Tour Checklist OPDP-10 Rev. 0001 Page 16 of 20 During the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual has completed a plant tour including all areas listed below (excluding high radiation areas) under the direction of an operator (active license) or senior operator (active license) as appropriate.

Tours will include a review of all required NLO shift turnover procedures.

Attach a copy of the security door printouts for both the licensed individual reactivating and the supervising licensee for each date listed below. From NUREG-1021

-ES-605, "If a utility has developed a checklist of areas to tour, it is generally inappropriate to skip plant areas, and mark the items as non-applicable unless there is sufficient justification (e.g., personnel or radiation hazard)." Date Time List Areas Toured Supervising Licensee All Levels of Auxiliary Building All Levels of Turbine Building and Cond 01 Building Diesel Generator Building All Levels of Control Building Outside Areas, including CCW Building, New Makeup 01 Building and Switchyard ERCW Structure Review AUO Shift Turnovers Verified by:

Superintendent

-Shift Operations Date NPG Standard Department Procedure License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix A (Page 6 of 7) Return to Active Status Checklist SQN Tour Checklist OPDP-10 Rev. 0001 Page 16 of 20 During the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual has completed a plant tour including all areas listed below (excluding high radiation areas) under the direction of an operator (active license) or senior operator (active license) as appropriate.

Tours will include a review of all required NLO shift turnover procedures.

Attach a copy of the security door printouts for both the licensed individual reactivating and the supervising licensee for each date listed below. From NUREG-1021

-ES-605, "If a utility has developed a checklist of areas to tour, it is generally inappropriate to skip plant areas and mark the items as non-applicable unless there is sufficient justification (e.g., personnel or radiation hazard)." Date Time List Areas Toured Supervising Licensee All Levels of Auxiliary Building All Levels of Turbine Building and Cond 01 Building Diesel Generator Building All Levels of Control Building Outside Areas, including CCW Building, New Makeup 01 Building and Switchyard ERCW Structure Review AUO Shift Turnovers Verified by: ------------------------------------

Superintendent

-Shift Operations Date

) NPG Standard Department Procedure License Status Maintenance, . Reactivation and for Non-Licensed Positions Appendix A (Page 7 of 7) Return to Active Status Checklist WBN Tour Checklist OPDP-10 Rev. 0001 Page 17 of 20 During the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual has completed a plant tour including all areas listed below (excluding high radiation areas) under the direction of an operator (active license) or senior operator (active license) as appropriate.

Tours will include a review of all required NLO shift turnover procedures.

Attach a copy of the security door printouts for both the licensed individual reactivating and the supervising licensee for each date listed below. From NUREG-1 021 ES-605, "If a utility has developed a checklist of areas to tour, it is generally inappropriate to skip plant areas and mark the items as non-applicable unless there is sufficient justification (e.g., personnel or radiation hazard)." Date Time List Areas Toured Supervising Licensee All Levels of Auxiliary Building All Levels of Turbine Building Diesel Generator Building All Levels of Intake Pumping Station Outside Areas, including CCW Building, New Makeup 01 Building and Switchyard All Levels of Control Building Review AUO Shift Turnovers --Verified by: -----------------------------------

Superintendent -Shift Operations Date ) NPG Standard Department Procedure License Status Maintenance, Reactivation and for Non-Licensed Positions Appendix A (Page 7 of 7) Return to Active Status Checklist WBN Tour Checklist OPDP-10 Rev. 0001 Page 17 of 20 During the minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions, the licensed individual has completed a plant tour including all areas listed below (excluding high radiation areas) under the direction of an operator (active license) or senior operator (active license) as appropriate.

Tours will include a review of all required NLO shift turnover procedures.

Attach a copy of the security door printouts for both the licensed individual reactivating and the supervising licensee for each date listed below. From NUREG-1021

-ES-605, "If a utility has developed a checklist of areas to tour, it is generally inappropriate to skip plant areas and mark the items as non-applicable unless there is sufficient justification (e.g., personnel or radiation hazard)." Date Time List Areas Toured Supervising Licensee All Levels of Auxiliary Building All Levels of Turbine Building Diesel Generator Building All Levels of Intake Pumping Station Outside Areas, including CCW Building, New Makeup DI Building and Switchyard All Levels of Control Building Review AUO Shift Turnovers Verified by: ------------------------------------

Superintendent

-Shift Operations Date

) NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 18 of 20 Appendix B (Page 1 of 2) Activation of SRO License Limited to Fuel Handling Licensed Individual/EIN NOTE Personnel who activate their SRO License Limited to' Fuel Handling MAY NOT stand watch in the Main Control Room or any other position that requires an active licensed SRO. The above named licensed individual has successfully completed the following:

Uninterrupted participation in the Licensed Operator Requalification Program or met with the Superintendent

-Operations Training or Designee to discuss the material from all requalification sessions which were missed. Verified by: _____________

:-__ _ Operations Training Manager or Designee Date Work for one shift, (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) moving fuel under the direction of an active licensed SRO***. Position Moving Date* Fuel Moving Fuel Hours** Active Licensed SRO*** *Should include shift turnover.

- Must include a total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months moving fuel under the direction of an active licensed SRO. In accordance with 1 OCFRSO,S4(m)(2)(iv) the individual reactivating and the active license holder shall be assigned no other duties. ***Active SRO or Active SRO Limited to Fuel Handling.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 18 of 20 Appendix 8 (Page 1 of 2) Activation of SRO License Limited to Fuel Handling Licensed Individual/EIN NOTE Personnel who activate their SRO License Limited to Fuel Handling MAY NOT stand watch in the Main Control Room or any other position that requires an active licensed SRO. The above named licensed individual has successfully completed the following:

Uninterrupted participation in the Licensed Operator Requalification Program or met with the Superintendent

-Operations Training or Designee to discuss the material from all requalification sessions which were missed. Verified by: ------------------------------------

Operations Training Manager or Designee Date Work for one shift, (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) moving fuel under the direction of an active licensed SRO***. Position Moving Date* Fuel Moving Fuel Hours** Active Licensed SRO*** *Should include shift turnover.

- Must include a total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months moving fuel under the direction of an active licensed SRO. In accordance with 1 OCFR50.54(m)(2)(iv) the individual reactivating and the active license holder shall be assigned no other duties. ***Active SRO or Active SRO Limited to Fuel Handling.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 19 of 20 Appendix B (Page 2 of 2) Activation of SRO License Limited to Fuel Handling The licensed individual has completed a tour of fuel handling areas with an active Senior Licensed Operator***

including all levels of the Fuel Handling Area, (excluding high radiation areas) and the Reactor Containment Building (if fuel handling activities are in progress).

Verified by: ________________

_ Superintendent

-Shift Operations Date I certify the requirements for returning to active status, limited to fuel handling, as listed in OMM-001, Section 5.5.2, have been met for the above named licensed individual.

Verified by: ________________

_ Superintendent

-Shift Operations Date ***Active SRO or Active SRO Limited to Fuel Handling.

After receiving the final review signature, this checklist becomes a QA RECORD and should be submitted to Management Services.

NPG Standard License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 19 of 20 Appendix B (Page 2 of 2) Activation of SRO License Limited to Fuel Handling The licensed individual has completed a tour of fuel handling areas with an active Senior Licensed Operator***

including all levels of the Fuel Handling Area, (excluding high radiation areas) and the Reactor Containment Building (if fuel handling activities are in progress).

Verified by: ------------------------------------

Superintendent

-Shift Operations Date I certify the requirements for returning to active status, limited to fuel handling, as listed in OMM-001, Section 5.5.2, have been met for the above named licensed individual.

Verified by: ------------------------------------

Superintendent

-Shift Operations Date ***Active SRO or Active SRO Limited to Fuel Handling.

After receiving the final review signature, this checklist becomes a QA RECORD and should be submitted to Management Services.

NPG Standard Department Procedure NAME: License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix C (Page 1 of 1) OPDP-10 Rev. 0001 Page 20 of 20 Active Licensed Maintenance for Off-Shift Personnel Quarterly On-Shift Time Documentation

Station: BFN SQN WBN (circle the appropriate one) I certify that on the dates listed below, I performed the licensed duties as defined in 10 CFR 55 for a minimum of five (5) 12-hour shifts, seven (7) 8-hour shifts, or combination as described in this procedure.

Covering Quarter: o Jan -March o April-June o July -Sept o Oct-Dec DATE Start Time of UNIT POSITIONS Shift Shift 1: Shift 2: Shift 3: Shift 4: Shift 5(2) Shift 6(1) (2) Shift 7(1)(2) NOTE: (1) The Day 6 & 7 slot is to be used if one does not complete a full shift on one of the previous days. NOTE: (2) Once the form is completed, forward to Operations Superintendent.

Do not retain form until the end of the quarter. Signature:

Date: ------I I I I I I I : I I I ) NPG Standard Department Procedure NAME: License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Appendix C (Page 1 of 1) OPDP-10 Rev. 0001 Page 20 of 20 Active Licensed Maintenance for Off-Shift Personnel Quarterly On-Shift Time Documentation Station: BFN SQN WBN (circle the appropriate one) I certify that on the dates listed below, I performed the licensed duties as defined in 10 CFR 55 for a minimum of five (5) 12-hour shifts, seven (7) 8-hour shifts, or combination as described in this procedure.

Covering Quarter: o Jan -March o April-June o July -Sept o Oct -Dec DATE Start Time of UNIT POSITIONS Shift Shift 1: Shift 2: Shift 3: Shift 4: Shift 5(2) Shift 6(1) (2) Shift 7(1) (2) NOTE: (1) The Day 6 & 7 slot is to be used if one does not complete a full shift on one of the previous days. NOTE: (2) Once the form is completed, forward to Operations Superintendent.

Do not retain form until the end of the quarter. Signature:

Date: ------

WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam t! A.1-2 RO Perform RCS Deboration Calculation 1 OF 7 WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam A.1-2 RO Perform RCS Deboration Calculation PAr,F 1 OF 7 WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam EVALUATION SHEET Task: Perform RCS Deboration Calculation.

Alternate Path: NI A Facility JPM #: None Safety Function:

Title: KIA 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Rating{s):

3.9/4.2 CFR: 41.10/45.13 Preferred Evaluation Location:

Preferred Evaluation Method: Simulator x In-Plant Perform x Simulate -------

References:

Task Number: Task Standard:

Validation Time: SOI-62.04, "cvcs Purification System," Rev. 53 TI-59, "Boron Tables," Rev. 7 RO-062-TI-59-001 Title: Perform boron concentration change calculations.

Applicant calculates the amount of time required to reduce RCS boron concentration from 50 ppm to 45 ppm using SOI-62.04, "cvcs Purification System," Appendix B, "RCS Deboration Calculation" and TI-59, "Boron Tables." 10 minutes Time Critical:

Yes No X ---======================================================.=====================

Applicant:

Time Start: NAME SSN Time Finish: Performance Rating: SAT UNSAT Performance Time Examiner:

__________________________

__

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAr,F? OF 7 WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam EVALUATION SHEET Task: Perform RCS Deboration Calculation.

Alternate Path: N/A Facility JPM #: None Safety Function:

Title: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Rating(s):

3.9/4.2 CFR: 41.10/45.13 Preferred Evaluation Location:

Preferred Evaluation Method: Simulator X In-Plant -"--"---Perform X Simulate -"--"----

References:

Task Number: .. Task Standard: ) Validation Time: SOI-62.04, "cvcs Purification System," Rev. 53 TI-59, "Boron Tables," Rev. 7 RO-062-TI-59-00 1 Title: Perform boron concentration change calculations.

Applicant calculates the amount of time required to reduce RCS boron concentration from 50 ppm to 45 ppm using SOI-62.04, "cvcs Purification System," Appendix B, "RCS Deboration Calculation" and TI-59, "Boron Tables." 10 minutes Time Critical:

Yes No X ----=--=---===========================================================================

Applicant:

Time Start: NAME SSN Time Finish: __ _ Performance Rating: SAT UNSAT Performance Time Examiner:

__ -NAME SIGNATURE DATE ===========================================================================

COMMENTS PA(;F ? OF 7

) ./ WATTS BAR NUCLEAR PLANT . A.1-2 RO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

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. The unit is in Mode 1 coasting down prior to refueling.

2. Current RCS C B is 50 ppm. 3. Current RCS temperature is 575°F . . 4. Mixed Bed A contains fresh, unborated resin. 5. Maximum letdown flow will be used during this evolution.

6. You are an extra operator.

INITIATING CUES: 1. The Unit SRO has directed you to perform SOI-62.04, "CVCS Purification System,: Appendix B "RCS Deboration Calculation," to estimate the time that CVCS Mixed Bed Demineralizer

'A' must be in service in order to reduce RCS . boron concentration to 45 ppm. 2. Report the results of your calculation to the Unit SRO. OF 7 ) WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

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. The unit is in Mode 1 coasting down prior to refueling.

2. Current RCS C s is 50 ppm. 3. Current RCS temperature is 575°F. 4. Mixed Bed A contains fresh, unborated resin. 5. Maximum letdown flow will be used during this evolution.

6. You are an extra operator.

INITIATING CUES: 1. The Unit SRO has directed you to perform SOI-62.04, "CVCS Purification System,: Appendix B "RCS Deboration Calculation," to estimate the time that CVCS Mixed Bed Demineralizer

'A' must be in service in order to reduce RCS boron concentration to 45 ppm. 2. Report the results of your calculation to the Unit SRO. PAr,F 1 OF 7 WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam 1 STEP/STANDARD SAT/UNSAT START TIME: __ _ STEP 1: STANDARD:

[1] INDICATE Mixed Bed for which this calculation is being performed (CHECK ONLY ONE.) Mixed Bed A OR Mixed Bed B ----From INITIAL CONDITIONS, the applicant checks Mixed Bed A. COMMENTS:

SAT UNSAT ) NOTE This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown / flow being directed through the mixed bed being placed in service, and the following: ) QI -V Cf= Co e Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm) V = Res Volume at operating temperature (gals) T = Time (minutes)

PAGE 4 OF 7 WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ STEP 1: STANDARD:

[1] INDICATE Mixed Bed for which this calculation is being performed (CHECK ONLY ONE.) Mixed Bed A OR Mixed Bed B ----------------From INITIAL CONDITIONS, the applicant checks Mixed Bed A. COMMENTS:

SAT/UNSAT SAT UNSAT ) NOTE This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:

() T -V Cf= Co e Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flovv Rate (Letdown Flow in gpm) V = ReS Volume at operating temperature (gals) T = Time (minutes)

PAGE 4 OF 7 WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam ') STEP/STANDARD SAT/UNSAT

,'"-STEP 2: STANDARD:

From INITIAL CONDITIONS, applicant records 575°F as the current RCS temperature.

COMMENTS:

STEP 3: ) STANDARD:

I Applicant locates TI-59, and selects Appendix L, and records 87813.5 as the RCS volume. COMMENTS: ) PAGE 5 OF 7 SAT UNSAT CRITICAL STEP SAT UNSAT STEP 2: STANDARD:

WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam STEP/STANDARD

[2] RECORD current RC$ Temperature:

From INITIAL CONDITIONS, applicant records 575°F as the current RCS temperature.

COMMENTS:

STEP 3: [3] RECORD RCS Volume (V) based on current RCS Temp using TI-59 (first page of App D through ApR N, as appropriate.) ) STANDARD:

! Applicant locates TI-59, and selects Appendix L, and records 87813.5 as the RCS volume. COMMENTS:

PAGE 5 OF 7 SAT/UNSAT SAT UNSAT CRITICAL STEP SAT UNSAT

) WATTS BAR NUCLEAR PLANT A.1-2 RO STEP 4: -In (Cf/C o) V Time=-----

Q Time = STANDARD:

Nov. 2009 NRC Exam STEP/STANDARD -In ( ppm/----ppm) gals ______ gpm minutes Applicant enters letdown flow of 120 gpm, since the INITIAL CONDITIONS requires letdown flow to be at maximum, and RCS volume of 87813.5 gallons. Applicant calculates time of 73 to 80 minutes. Applicant reports the results of the calculation to the Unit Supervisor.

EVALUATOR'S CUE: When the applicant reports the result of the calculation to the Unit Supervisor, acknowledge using repeat back. State that "another operator will complete Step 5 of Appendix B." COMMENTS:

END OF TASK STOP TIME __ _ PAGE 6 OF 7 SAT/UNSAT CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam STEPISTANDARD STEP 4: [4] PERFORM the following calculation to time in service: -In (Cf/C o) V Time=-----

Q Time = STANDARD: -In ( __ ppmf---ypm)

__ gals =-----------

_____ gpm minutes Applicant enters letdown flow of 120 gpm, since the INITIAL CONDITIONS requires letdown flow to be at maximum, and RCS volume of 87813.5 gallons. Applicant calculates time of 73 to 80 minutes. Applicant reports the results of the calculation to the Unit Supervisor. , EVALUATOR'S CUE: When the applicant reports the result of the ) calculation to the Unit Supervisor, acknowledge using repeat back. State that "another operator will complete Step 5 of Appendix B. " COMMENTS:

END OF TASK STOP TIME __ _ PAGE 6 OF 7 SATIUNSAT CRITICAL STEP SAT UNSAT l(Ei ') NOTE [1] SOI-62.04 WBN CVCS PURIFICATION SYSTEM 1 APPENDIX B Page 1 of 1 RCS DEBORATION CALCULATION Revision 53 Page 77 of 85 INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY . I I"ilia I CDttkftm5 Mixed Bed A" OR Mixed Bed B L . This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:

2L -V Cf= Co e Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm) V = RCS Volume at operating temperature (gals) T = Time (minutes)

[2] RECORD current RCS Temperature:

Temp [3] RECORD RCS Volume (V) based on current RCS Temp using TI-59 (first page of App 0 through App N, as appropriate.)

Volume [4] PERFORM the following calculation to estimate time in service: -In (Cf/C o) V -In TT;i11.(.

Time = = ------------

Q 120 gpm Time = ]7.1 minutes A-11.w 75 -/0 80 [5] RECORD Mixed Bed Run times for which this Calculation is being MHwles performed (Times can be obtained from Attachment 1 for the associated demin). I 1 121 3 141 5 I 617 I 8 Run time Total time Initials ).tt:'-/ \(E'-I NOTE [1] KEY WBN SOI-62.04 CVCS PURIFICATION SYSTEM 1 APPENDIX B Page 1 of 1 RCS DEBORATION CALCULATION Revision 53 Page 77 of 85 INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY . I I"ih;, I CDttkftlt15 Mixed Bed A V OR Mixed Bed B L . This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:

OT -V Cf= Co e Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm) V = RCS Volume at operating temperature (gals) T = Time (minutes)

[2] RECORD current RCS Temperature:

[3] RECORD RCS Volume (V) based on current RCS Temp using TI-59 (first page of App 0 through App N, as appropriate.)

Volume [4] PERFORM the following calculation to estimate time in service: -In (Cf/C o) V -In (6ppm/$t>ppm) u;i11.' Time = = ------------

Q IZO _--,----=-

__ 9 pm Time = 77.1 minutes .411."" 75 -/0 80 [5] RECORD Mixed Bed Run times for which this Calculation is being MitvJ/eS performed (Times can be obtained from Attachment 1 for the associated demin). 1 2 3 4 5 6 7 8 Run time Total time Initials

) APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:

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. The unit is in Mode 1 coasting down prior to refueling . . 2. . Current RCs C s is 50 ppm. 3. Current RCs temperature is 575°F. 4. Mixed Bed A contains fresh, unborated resin. 5. Maximum letdown flow will be used during this evolution.

6. You are an extra operator.

INITIATING CUES: 1. The Unit sRO has directed you to perform 501-62.04, "CVCS Purification System,: Appendix B "RCs Deboration Calculation," to estimate the time that CVCS Mixed Bed Demineralizer

'A' must be in service in order to reduce RCs boron concentration to 45 ppm. 2. Report the results of your calculation to the Unit sRO. A.1-2 RO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) ') DIRECTION TO APPLICANT:

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. The unit is in Mode 1 coasting down prior to refueling.

2. Current RCS C B is 50 ppm. 3. Current RCS temperature is 575°F. 4. Mixed Bed A contains fresh, unborated resin. 5. Maximum letdown flow will be used during this evolution.

6. You are an extra operator.

INITIATING CUES: 1. The Unit SRO has directed you to perform 501-62.04, "CVCS Purification System,: Appendix B "RCS Deboration Calculation," to estimate the time that CVCS Mixed Bed Demineralizer

'A' must be in service in order to reduce RCS boron concentration to 45 ppm. 2. Report the results of your calculation to the Unit SRO. A.1-2 RO NOTE ) WBN 1 CVCS PURIFICATION SYSTEM APPENDIXB Page 1 of 1 RCS DEBORA TION CALCULATION SOI-62.04 Revision 53 Page 77 of 85 [1] INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY ONE.) Mixed Bed A OR Mixed Bed B This calculation is based on the Mixed Bed being a freshunborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:

-.QI. Cf= Co e -V Where: Cf = Final Boron Concentration Co= Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm) V = RCS Volume at operating temperature (gals) T = Time (minutes)

[2] RECORD current RCS Temperature:

[3] RECORD RCS Volume (V) based on current ReS Temp using TI-59 (first page of App D through App N, as appropriate.)

RCSTemp ___ RCS Volume [4] PERFORM the following calculation to estimate time in service: -In' (CtfC o) V Time=-----In ( ppm/_ppm) gals [5] Q ______ *gpm Time = minutes RECORD Mixed Bed Run times for which this Calculation is being performed (Times can be obtained from Attachment 1 for the associated demin). I 1 I 2 I 3 I 4 I 5 I 6 I 7 I 8 Run time Total time Initials NOTE WBN 1 CVCS PURIFICATION SYSTEM APPENDIX B Page 1 of 1 RCS DEBORATION CALCULATION SOI-62.04 Revision 53 Page 77 of 85 [1] INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY ONE.) Mixed Bed A OR Mixed Bed B ----This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:

-2I. Cf= Co e -V Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm) V = RCS Volume at operating temperature (gals) T = Time (minutes)

[2] RECORD current RCS Temperature:

____ RCS Temp [3] RECORD RCS Volume (V) based on current RCS Temp using TI-59 (first page of App 0 through App N, as appropriate.)

____ RCS Volume [4] PERFORM the following calculation to estimate time in service: -In ( __ ,ppm/_ppm)

___ gals Time=-----

=------------

Q _____ gpm Time = minutes [5] RECORD Mixed Bed Run times for which this Calculation is being performed (Times can be obtained from Attachment 1 for the associated demin). 1 234 5 678 Run time Total time Initials WBN 0 TI-59 BORON TABLES APPENDIX L Page 1 of 8 BORON TABLES ReS AT 575°F TI-59 Revision 6 Page 84 of 100 *****************************************************************.****************

WATTS BAR BORON TABLES PRESSURIZER LEVEL (% SPAN) 46.3 RCS LIQUID VOLUME (GAL) 87813.5 RCS LIQUID MASS (LB) = 530016.4 PRIMARY MAKEUP WATER BORIC ACID SYSTEM SYSTEM SYSTEM TEMPERATURE (DEG F) 575.0 70.0 70.0 PRESSURE (PSIG) 2235.0 .1 .1 DENSITY (LB/FT**3) 45.1501 62.3086 62.9940 SPECIFIC GRAVITY 1.0000 1. 0000 1.0110 BORON CONCENTRATION (PPM) o -2500 .0 6820.0 *********************************************************************************

WBN 0 TI-59 BORON TABLES APPENDIX L Page 1 of 8 BORON TABLES FOR ReS AT 575°F TI-59 Revision Page 84 *********************************************************************************

WATTS BAR BORON TABLES PRESSURIZER LEVEL (% SPAN) 46.3 RCS LIQUID VOLUME (GAL) 87813.5 RCS LIQUID MASS (LB) 530016.4 PRIMARY MAKEUP WATER BORIC ACID SYSTEM SYSTEM SYSTEM TEMPERATURE (DEG F) 575.0 70.0 70.0 PRESSURE (PSIG) 2235.0 .1 .1 DENSITY (LB/FT**3) 45.1501 62.3086 62.9940 SPECIFIC GRAVITY 1. 0000 1. 0000 1.0110 BORON CONCENTRATION (PPM) 0 -2500 .0 6820.0 *********************************************************************************

6 of 100 WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam I A.1-2 SRO Review of Estimated Critical Position Calculation PAr,F 1 nF WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam / A.1-2 SRO Review of Estimated Critical Position Calculation PAr,F 1 OF Task: Alternate Path: Facility JPM #: KIA Rating(s):

Task Standard:

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam EVALUATION SHEET Review of Estimated Critical Position Calculation.

None 3-0T-JPM ADA 1.6 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2)

Prior to taking the reactor critical, verify estimated critical position calculation in accordance with 1-SI-0-11

,"Estimated Critical Position." Preferred Evaluation Location:

Preferred Evaluation Method: Simulator

References:

Task Number: Validation Time: Classroom x Perform 1-SI-0-11, "Estimated Critical Position," Rev 14 WCAP-16880-P, NuPOP for WBN Unit 1, Cycle 9 x Simulate Nuclear Operating Book (NOB) Sheet A-5, "Negative MTC Withdrawal Limit Curve," Rev. 3 Core Operating Limit Report (COLR), Figure 1, "Control Bank Insertion Limit Versus Therma'i Power Four Loop Operation," Rev. 1 SRO-085-S 1-0-11-00 1 Applicable for: RO SRO x 10 minutes Time Critical:

Yes No x ---------------------------------------------------------------------------

Applicant:

Time Start: NAME SSN Time Finish: ----Performance Rating: SAT UNSAT Performance Time Examiner:'

NAME SIGNATURE DATE ===========================================================================

COMMENTS

()F 1::l Alternate Path: Facility JPM #: KJARating(s):

Task Standard:

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam EVALUATION SHEET Review of Estimated Critical Position Calculation.

None 3-0T-JPM ADA 1.6 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2)

Prior to taking the reactor critical, verify estimated critical position calculation in accordance with 1-SI-0-11

,"Estimated Critical Position." Preferred Evaluation Location:

Preferred Evaluation Method: Simulator

References:

Task Number: Validation Time: Classroom x Perform 1-SI-0-11, "Estimated Critical Position," Rev 14 WCAP-16880-P, NuPOP for WBN Unit 1, Cycle 9 x Simulate Nuclear Operating Book (NOB) Sheet A-5, "Negative MTC Withdrawal Limit Curve," Rev. 3 Core Operating Limit Report (COLR), Figure 1, "Control Bank Insertion Limit Versus Thermal Power Four Loop Operation," Rev. 1 SRO-085-SI-0-11-001 Applicable for: RO SRO x 10 minutes Time Critical:

Yes No x ===========================================================================

Applicant:

Time Start: NAME SSN Time Finish: ----Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE ===========================================================================

COMMENTS

()F

) WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam . DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

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. The unit is in Mode 3 making preparations to startup following refueling. 2. Current RCS C B is 2870 ppm. 3. Current RCS temperature is 557°F. 4. Unit startup will be via control rods. 5. PET 107 performance data predicts ARO Critical C B as 1700 ppm. 6. Desired Control Bank D rod position at criticality is 160 steps. 7. Initial startup following refueling is scheduled for next shift. 8. The extra operator assigned to the shift has performed1-SI-0-11, "Estimated Critical Position," Section 6.5, "ECP Hand Calculation Following a Refueling Outage." INITIATING CUES: As the Unit Supervisor, you are to review 1-SI-0-11, "Estimated Critical Position," Section 6.5, "ECP Hand Calculation Following a RefueJingOutage," and identify any and all errors in the calculfltion.

PAGF OF WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

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. The unit is in Mode 3 making preparations to startup following refueling.

2. Current RCS C B is 2870 ppm. 3. Current RCS temperature is 557°F. 4. Unit startup will be via control rods. ) 5. PET 107 performance data predicts ARO Critical C B as 1700 ppm. 6. Desired Control Bank D rod position at criticality is 160 steps. 7. Initial startup following refueling is scheduled for next shift. 8. The extra operator assigned to the shift has performed 1-SI-0-11, "Estimated Critical Position," Section 6.5, "ECP Hand Calculation Following a Refueling Outage." INITIATING CUES: As the Unit Supervisor, you are to review 1-SI-0-11, "Estimated Critical Position," Section 6.5, "ECP Hand Calculation Following a Refueling Outage," and identify any and all errors in the PAr,F ::l ()F 1::l WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam '1 STEP/STANDARD SAT/UNSAT ) START TIME: __ _ STEP 1: [1] RECORD the following from NuPOP Table 4-8: STANDARD:

A. All Rods Out (ARO) Critical Cb: __ ppm. B. Differential Boron Worth (OBW) at the ARO Critical Cb: __ pcm/ppm. ERRORS TO BE IDENTIFIED:

Applicant refers to NuPOP Table 4-8, III. Boron Endpoint Dataand determines thatthe 1482 entry is incorrect.

Applicant determines that the -6.2 pcm/ppm entry is also incorrect.

COMMENTS:

PAGE 4 OF 13 CRITICAL STEP SAT UNSAT \ WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ sAT/UNsAT NOTE TO EVALUATOR:

A marked-up copy of 1-51-0-11, "Estimated Critical Position," is provided to the applicant for review and approval.

This information is in the JPM package AFTER the APPLICANT CUE SHEET. A key is also provided which indicates the erroneous entries to be identified by the applicant.

The key is located BEFORE the APPLICANT CUE SHEET. STEP 1: [1] RECORD the following from NuPOP Table 4-8: STANDARD:

A. All Rods Out (ARO) Critical Cb: __ ppm. B. Differential Boron Worth (DBW) at the ARO Critical Cb: __ pcm/ppm. ERRORS TO BE IDENTIFIED:

CRITICAL STEP SAT UNSAT / Applicant refers to NuPOP Table 4-8, III. Boron Endpoint Data and determines that the 1482 entry is incorrect.

Applicant determines that the -6.2 pcm/ppm entry is also incorrect.

COMMENTS:

PAGE 4 OF 13 WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam ) STEP/STANDARD SAT/UNSAT STEP 2: [2] RECORD the desired Control Bank D rod position for initial SAT criticality (Le. ECP): UNSAT ECP= steps STANDARD:

Applicant determines that correct rod position of 160 was entered in the blank for desired Control Bank D rod position.

COMMENTS:

STEP 3. [3] RECORD the inserted integral rod worth for the desired SAT critical rod position (Step 6.5[2]) from NuPOP Table 7-30: UNSAT Inserted Rod Worth = pcm STANDARD:

Applicant refers to Table 7-30 and determines that the correct value of 254.3 was inserted in the Inserted Rod Worth blank.

PAGE 5 OF 13 STEP 2: STANDARD:

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD

[2] RECORD the desired Control Bank D rod position for initial criticality (Le. ECP): ECP = steps Applicant determines that correct rod position of 160 was entered in the blank for desired Control Bank D rod position.

COMMENTS:

STEP 3. STANDARD:

[3] RECORD the inserted integral rod worth for the desired critical rod position (Step 6.5[2]) from NuPOP Table 7-30: Inserted Rod Worth = ___ pcm Applicant refers to Table 7-30 and determines that the correct value of 254.3 was inserted in the Inserted Rod Worth blank. COMMENTS:

PAGE 5 OF 13 SAT/UNSAT SAT UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam ') STEP/STANDARD . I SAT/UNSAT ) STEP 4: [4] IF performing a dilute-to-critical, THEN CALCULATE the critical boron concentration at the ECP as follows: STANDARD:

Applicant determines that this step is not applicable since the INITIAL CONDITIONS state that the startup will be conducted using the critical" method. COMMENTS:

STEP 5: [5] IF performing a pull-to-critical, THEN PERFORM the following SUb-steps:

STANDARD:

A. RECORD the ARO Critical Cb inferred by the Sub-Critical Rod Worth Measurement from PET-107: Inferred ARO Cb = ppm From the INITIAL CONDITIONS, the applicant determines that the correct value of 1700 was entered. COMMENTS:

PAGE 6 OF 13 SAT UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP 4: [4] IF performing a dilute-to-critical, THEN CALCULATE the critical boron concentration at the ECP as follows: STANDARD:

Applicant determines that this step is not applicable since the INITIAL CONDITIONS state that the startup will be conducted using the critical" method. COMMENTS:

STEP 5: [5] IF performing a pull-to-critical, THEN PERFORM the following sUb-steps:

STANDARD:

A. RECORD the ARO Critical Cb inferred by the Sub-Critical Rod Worth Measurement from PET-107: Inferred ARO Cb = ppm From the INITIAL CONDITIONS, the applicant determines that the correct value of 1700 was entered. COMMENTS:

PAGE 6 OF 13 SAT UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2SRO Nov. 2009 NRC Exam ') STEP/STANDARD SAT/UNSAT STEP 6: [5] IF performing a pull-to-critical, THEN PERFORM the following sUb-steps:

B. CALCULATE the critical boron concentration at the ECP as follows: ECC Cb = Inferred ARO Cb + (Inserted Rod Worth ECC Cb = ppm + 'ppm (Step 6.5[5]A ) (Step 6.5[3]) ECC Cb = ppm for Bank D at __ steps STANDARD:

ERRORS TO BE IDENTIFIED:

DBW) __ pcm/ppm (Step 6.5[1]B) Applicant determines that the differential boron worth value entered is incorrect, and the sign applied to the value in this step is incorrect.

Applicant determines that the calculated ECC Cb is incorrect. ) COMMENTS:

STEP 6: STANDARD:

[6] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). Applicant reviews COLR, Figure 1, "Control Bank Insertion Limits Versus Thermal Power Four Loop Operation" and determines that the 0 power insertion limit is 64 steps on Control Bank C. COMMENTS:

PAGE 7 OF 13 CRITICAL STEP SAT UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD STEP 6: [5] IF performing a pull-to-critical, THEN PERFORM the following sUb-steps:

B. CALCULATE the critical boron concentration at the ECP as follows: ECC Cb = Inferred ARO Cb + (Inserted Rod Worth DSW) ECC Cb = ppm + ppm _pcmippm (Step 6.5[5]A ) (Step 6.5[3]) (Step 6.5[1]S) ECCCb = ppm forBank D at __ steps STANDARD:

ERRORS TO BE IDENTIFIED:

Applicant determines that the differential boron worth value entered is incorrect, and the sign applied to the value in this step is incorrect.

Applicant determines that the calculated ECC Cb is incorrect. ) COMMENTS:

STEP 6: STANDARD:

[6] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). Applicant reviews COLR, Figure 1, "Control Bank Insertion Limits Versus Thermal Power Four Loop Operation" and determines that the 0 power insertion limit is 64 steps on Control Bank C. COMMENTS:

PAGE 7 OF 13 SAT/UNSAT CRITICAL STEP SAT UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam ) STEP/STANDARD SAT/UNSAT STEP 7: STANDARD:

[7] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2] D (Acceptance Criteria 5.1 B). Applicant determines that the Negative MTC Withdrawal Limit is not applicable by referring to Nuclear Operating Book (NOB) Sheet A-5 Negative MTC Withdrawal Limit Curve and marks the step N/A. COMMENTS:

NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. ------------,-..,.----,---,---,--:--

SAT UNSAT

-1

\1.:}> >>:-------------------------i -----------------i-_ -------_.i---i-__ -----------

i_ ----------STEP 8: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: A. DETERMINE the Upper 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[31-1000 pcm = pcm Bank C at steps & Bank D at steps STANDARD:

Applicant determines that the -745.7 pcm value for the Upper 1000 pcm limit is satisfied with Control Banks C and D at 228 steps. COMMENTS:

PAGE 8 OF 13 SAT UNSAT STEP 7: STANDARD:

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD

[7] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2] D (Acceptance Criteria 5.1 B). Applicant determines that the Negative MTC Withdrawal Limit is not applicable by referring to Nuclear Operating Book (NOB) Sheet A-5 Negative MTC Withdrawal Limit Curve and marks the step N/A. COMMENTS:

NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. SAT/UNSAT SAT UNSAT NOTE TO EVALUATOR:

JPM Steps 8 through 13 are all associated with 1-51-0-11 Step '\ 8. I STEP 8: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: A. DETERMINE the Upper 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] -1000 pcm = pcm Bank C at ___ steps & Bank D at ___ steps STANDARD:

Applicant determines that the -745.7 pcm value for the Upper 1000 pcm limit is satisfied with Control Banks C and D at 228 steps. COMMENTS:

PAGE 8 OF 13 SAT UNSAT

\ WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD STEP 9: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: B. DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 1000 pcm = pcm Bank C at steps & Bank D at steps STANDARD:

Applicant determines that the 1254.3 pcm value for the Lower 1000 pcm limit is satisfied with Control Banks C at 162 steps and D at 46 steps. COMMENTS:

SAT/UNSAT SAT UNSAT )------------------------'--------+--------1 r STEP 10: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: STANDARD:

C. DETERMINE the Upper 750 pcm Limit from NuPOP Table 7-30: Step 6.5[3] -750 pcm = pcm Bank C at steps & Bank D at steps Applicant determines that the -495.7 pcm value for the Upper 1000 pcm limit is satisfied with Control Banks C and D at 228 steps. COMMENTS:

PAGE 9 OF 13 SAT UNSAT I WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD STEP 9: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: B. DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 1000 pcm = pcm Bank C at ___ steps & Bank D at steps STANDARD:

Applicant determines that the 1254.3 pcm value for the Lower 1000 pcm limit is satisfied with Control Banks C at 162 steps and D at 46 steps. COMMENTS:

STEP 10: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: STANDARD:

C. DETERMINE the Upper 750 pcm Limit from NuPOP Table 7-30: Step 6.5[3] -750 pcm = pcm Bank C at ___ steps & Bank D at ___ steps Applicant determines that the -495.7 pcm value for the Upper 1000 pcm limit is satisfied with Control Banks C and D at 228 steps. COMMENTS:

PAGE 9 OF 13 SAT/UNSAT SAT UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam ') STEP/STANDARD SAT/UNSAT STEP 11: [8] CALCULATE, AND RECORD the UPPER and LOWER SAT Acceptance Bands: UNSAT D. DETERMINE the Lower 7S0 pcm Limit from NuPOP Table 7-30: Step 6.S[3] + 7S0 pcm = pcm Bank C at steps & Bank D at steps STANDARD:

Applicant determines that the 1004.3 pcm value for the Lower 1000 pcm limit is satisfied with Contror Banks C at 182 steps and D at 66 steps. COMMENTS:

STEP 12: [8] CALCULATE, AND RECORD the UPPER and LOWER SAT Acceptance Bands: UNSAT E. DETERMINE the Upper SOD pcm Limit from NuPOP Table 7-30: Step6.S[3]

-SOD pcm = pcm Bank C at steps & Bank D at . steps STANDARD:

Applicant determines that the -245.7 pcm value for the Upper 1000 pcm limit is satisfied with Control Banks C and D at 228 steps. COMMENTS:

/ PAGE100F13 WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STAN DARD STEP 11: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: STANDARD:

D. DETERMINE the Lower 750 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 750 pcm = pcm Bank C at ___ steps & Bank D at ___ steps Applicant determines that the 1004.3 pcm value for the Lower 1000 pcm limit is satisfied with Control Banks C at 182 steps and D at 66 steps. COMMENTS:

SAT/UNSAT SAT UNSAT \\

STEP 12: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: STANDARD:

E. DETERMINE the Upper 500 pcm Limit from NuPOP Table 7-30: Step 6.5[3] -500 pcm = pcm Bank C at ___ steps & Bank D at ___ steps Applicant determines that the -245.7 pcm value for the Upper 1000 pcm limit is satisfied with Control Banks C and D at 228 steps. COMMENTS:

PAGE 10 OF 13 SAT UNSAT

) WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD STEP 13: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: STANDARD:

F. DETERMINE the Lower 500 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 500 pcm = pcm Bank C at steps & Bank D at steps Applicant determines that the 754.3 pcm value for the Lower 1000 pcm limit is satisfied with Control Banks C at 204 steps and D at 88 steps. COMMENTS:

STEP 14: [9] RECORD the following:

A. Date of calculation: / / ---B. Time of calculation:

STANDARD:

Applicant determines that the date and time are entered in the appropriate blanks. COMMENTS:

SAT/UNSAT SAT UNSAT SAT UNSAT NOTE: A technical review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.

PAGE 11 OF 13 ) WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD STEP 13: [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: STANDARD:

F. DETERMINE the Lower 500 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 500 pcm = pcm Bank C at ___ steps & Bank 0 at ___ steps Applicant determines that the 754.3 pcm value for the Lower 1000 pcm limit is satisfied with Control Banks C at 204 steps and 0 at 88 steps. COMMENTS:

SAT/UNSAT SAT UNSAT \

STEP 14: [9] RECORD the following:

A. Date of calculation: / / ---B. Time of calculation:

STANDARD:

Applicant determines that the date and time are entered in the appropriate blanks. COMMENTS:

SAT UNSAT NOTE: A technical review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.

PAGE 11 OF 13

'j WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD STEP 14: [10] OBTAIN review of calculations and results by task qualified individual.

An STA or SRO may also perform this review. STANDARD:

Applicant states that the package contains errors and must be returned to the individual who performed the calculations for corrections.

Applicant DOES NOT sign at Step 10. CUE: COMMENTS:

END OF TASK STOP TIME __ _ PAGE 12 OF 13 SAT/UNSAT CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD STEP 14: [10] OBTAIN review of calculations and results by task qualified individual.

An STA or SRO may also perform this review. STANDARD:

Applicant states that the package contains errors and must be returned to the individual who performed the calculations for corrections.

Applicant DOES NOT sign at Step 10. CUE: COMMENTS:

END OF TASK STOP TIME __ _ PAGE 12 OF 13 SAT/UNSAT CRITICAL STEP SAT UNSAT

) KE'1 KE'f WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 25 of 69 Data Package: Page _, _ of 4 Date ............--

6.5 ECP Hand Calculation Following a Refueling Outage RECORD the following from NuPOP Table 4-8:

Sh,ou.lJ b<-. All Rods Out (ARO) Critical C b: 14e-z.. ppm. p ffWl ) &"Oifferential Boron Worth (OBW) at the ARO Critical C b: t.. ."ZO pcm/ppm. (Ee.ROR Q,.ov..ld kx. ') ....-a.-RECORD the desired Control Bank 0 rod position for initial \y criticality (i.e. ECP): ECP = I (,,0 steps RECORD the inserted integral rod worth for the desired critical rod position (Step 6.5[2]) from NuPOP Table 7-30: Inserted Rod Worth = Z5'4.3 pcm &. IF performing a diMe-to-critical, THEN CALCULATE the critical boron concentration at the ECP as follows: ECC C b = ARO C b + (Inserted Rod Worth DBW) ECC C b = ppm + _____ pcm ..,. __ pcm/ppm (Step 6.5[1]A) (Step 6.5[3]) (Step 6.5[1]B) ECC C b = ___ ppm for Bank D at steps & IF performing a pull-to-critical, THEN PERFORM the following sUb-steps:

KEY RECORD the ARO Critical C b inferred by the Sub-Critical Rod Worth Measurement from PET-107: Inferred ARO C b = 1700 ppm ---.A.,.. Key KE'-( KE'I WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 25 of 69 Data Package: Page _, _ of 4 Date .........---

6.5 ECP Hand Calculation Following a Refueling Outage RECORD the following from NuPOP Table 4-8:

b<.-. All Rods Out (ARO) Critical C b: 14f> 1. ppm. I ffYVI) &Oifferential Boron Worth (OBW) at the ARO Critical C b: ('.'ZO pcm/ppm. ') .........-RECORD the desired Control Bank 0 rod position for initial \y criticality (i.e. ECP): ECP = I (,,0 steps RECORD the inserted integral rod worth for the desired critical rod position (Step 6.5[2]) from NuPOP Table 7-30: Inserted Rod Worth = 154.3 pcm & tF performing a dilute-to-critical, THEN CALCULATE the critical boron concentration at the ECP as follows: ECC C b = + (Inserted Rod Worth -'-DBW) ECC C b = ppm + (Step 6.5[1]A) ECC C b = ___ ppm _____ pcm (Step 6.5[3]) __ pcm/ppm (Step 6.5[1]B) for Bank D at steps ---& IF performing a pull-to-critical, THEN PERFORM the following SUb-steps:

KEY RECORD the ARO Critical C b inferred by the Sub-Critical Rod Worth Measurement from PET-107: Inferred ARO C b = 1700 ppm 6.5 EQ.yZ0\2.:

\oL. . Ke'f WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 26 of 69 Data Package: Page __ of __ ECP Hand Calculation Following a Refueling Outage (continued) CALCULATE the critical boron concentration at the ECP KE"Y Date __ _ EGG G b = Inferred ARO G b + (Inserted Rod Worth DBW) (E:R..f?cl..1

\falv!.. .:5l.1.oLdJ bG-EGC G b = 1700 ppm + Z. S+."! pcm pcm/ppm -\i") (Step 6.5[5]A ) (Step 6.5[3]) (Step 6.5[1]B)

EGG G b = 17+\ ppm for Bank D at steps VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). &IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2]0 (Acceptance Criteria 5.1 B). NOTE --a..-......-...-The 1000 pcm lower limit may be used for Mode 2 entry call. CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: DETERMINE the Upper 1000 pcm Limit from NuPOP Step 6.5[3] -1000 pcm = -74c-pcm Bank C at ZZ & steps & Bank 0 at steps DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 1000 pcm = JW pcm Bank C at '" 2... steps & Bank 0 at # steps KEi KEY 6.5 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 26 of 69 Data Package: Page __ of __ ECP Hand Calculation Following a Refueling Outage (continued) CALCULATE the critical boron concentration at the ECP KE"Y Date __ _ ECC C b = Inferred ARO C b + (Inserted Rod Worth +-DBW) (EJ?..((r:L 1 \falv!. :>0ot,l"lJ. ECC C b = 1700 ppm + 2. S+.,! pcm +-pcm/ppm -\i") (Step 6.5[5]A ) (Step 6.5[3]) (Step 6.5[1]B) 17+\ ppm for Bank D at I {PO steps VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). '&.IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2]0 (Acceptance Criteria 5.1 B). NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: KE'1 DETERMINE the Upper 1000 pcm Limit from NuPOP Step 6.5[3] -1000 pcm = -741. pcm Bank C at ZZ & steps & Bank 0 at 22& steps DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 1000 pcm = pcm Bank C at 't-'2... steps & Bank 0 at # steps WBN Estimated Critical Position 1-SI-0-11 I Unit 1 Rev. 0014 27

__ . _____ Data Package: Page __ of __ Date __ _ 6.5 ECP Hand Calculation Following a Refueling Outage (continued)

G DETERMINE the Upper 750 pcm Limit from NuPOP Table l3( 7-30: Step 6.5[3] -750 pcm = pcm Bank C at Z2.6 steps & Bank 0 at ZZS steps DETERMINE the Lower 750 pcm Limit from NuPOP Table \..::>l7-30:

Step 6.5[3] + 750 pcm = pcm Bank C at 18"2. steps & Bank 0 at steps 'I<?""\ DETERMINE the Upper 500 pcm Limit from NuPOP Table \.:SZ.7 -30: Step 6.5[3] -500 pcm =-2.4(' pcm Bank C at Z-z.S steps & Bank 0 at '2Z8 steps DETERMINE the Lower 500 pcm Limit from NuPOP Table Step 6.5[3] + 500 pcm = 75'.., pcm Bank C at M steps & Bank 0 at Be. steps RECORD the following: Date of calculation: -a-/ ... /-----B. Time of calculation:....

----,...-&.-A review of the ECP during the performance of this I performing any associated reactivity manipulations.

ction should be performed prior to review of calculations and. results by task qualified V individual.

An STA or SRO may also perform this review. Ke'-/ KfEY KE.'1 KE-/ WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 27 of 69 Data Package: Page __ of __ Date __ _ 6.5 ECP Hand Calculation Following a Refueling Outage (continued)

G DETERMINE the Upper 750 pcm Limit from NuPOP Table l3( 7-30: Step 6.5[3] -750 pcm = pcm Bank C at Zz.e steps & Bank 0 at zzS steps DETERMINE the Lower 750 pcm Limit from NuPOP Table \..:)l7-30:

Step 6.5[3] + 750 pcm = pcm Bank C at steps & Bank 0 at steps 'l<?""\ DETERMINE the Upper 500 pcm Limit from NuPOP Table \..:SZ.7 -30: Step 6.5[3] -500 pcm =-2.4(' pcm Bank C at 2.26 steps & Bank 0 at '2Z8 steps DETERMINE the Lower 500 pcm Limit from NuPOP Table '-.)( 7-30: Step 6.5[3] + 500 pcm = 75'.., pcm Bank C at M steps & Bank 0 at BE!> steps RECORD the following: Date of calculation:

-.../ ... / ...... B. Time of calculation:'" : -Z-----A review of the ECP during the performance of this I performing any associated reactivity manipulations.

ction should be performed prior to review of calculations and results by task qualified V individual.

An STA or SRO may also perform this review.

E--/ WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 28 of 69 Data Package: Page __ of __ Date __ _ 6.5 ECP Hand Calculation Following a Refueling Outage (continued)

[11] OBTAIN SM/US review and approval of ECP. SM/US , ) Kf,'i I(E7 K.e-/ WBN Estimated Critical Position 1-81-0-11 Unit 1 Rev. 0014 Page 28 of 69 Data Package: Page __ of __ 6.5 ECP Hand Calculation Following a Refueling Outage (continued)

[11] OBTAIN SM/US review and approval of ECP. l Date __ _ SM/US I(E7 APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) ) DIRECTION TO APPLICANT:

! . ) ) 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. The unit is in Mode 3 making preparations to startup following refueling.

2. Current RCSC B is -2870 ppm. 3. Current ReS temperature is 557°F. 4. Unit startup will be via control rods. 5. PET 107 performance data predicts ARO Critical C B as 1700 ppm. 6. Desired Control Bank D rod position at criticality is 160 steps. 7. Initial startup following refueling is scheduled for next shift. ) 8. The extra operator assigned to the shift has performed 1-SI-0-11, Estimated Critical Position, Section 6.5, ECP Hand Calculation Following a Refueling Outage .. INITIATING CUES: As the Unit Supervisor, you are to review 1-SI-0-11, "Estimated Critical Position," Section 6.5, ECP Hand Calculation Following a Refueling Outage, and identify any and all errors in the calculation. . A.1-2SRO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) ) DIRECTION TO APPLICANT:

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. The unit is in Mode 3 making preparations to startup following refueling.

2. Current RCs C B is 2870 ppm. 3. Current RCs temperature is 557°F. 4. Unit startup will be via control rods. 5. PET 107 performance data predicts ARO Critical C B as 1700 ppm. 6. Desired Control Bank D rod position at criticality is 160 steps. 7. Initial startup following refueling is scheduled for next shift. 8. The extra operator assigned to the shift has performed 1-51-0-11, Estimated Critical Position, Section 6.5, ECP Hand Calculation Following a Refueling Outage. INITIATING CUES: As the Unit Supervisor, you are to review 1-51-0-11, "Estimated Critical Position," Section 6.5, ECP Hand Calculation Following a Refueling Outage, and identify any and all errors in the calculation.

A.1-2sRO

'\ I J [i!a] Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-51-0-11 Estimated Critical Position Revision 0014 Quality Related Level of Use: Continuous Use Effective Date: 09-16-2009 Responsible Organization:*

RXE, Reactor Engineering Prepared By: Lukus S. Barnes Approved By: C. Dale Greer Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-51-0-11 Estimated Critical Position Revision 0014 Quality Related Level of Use: Continuous Use Effective Date: 09-16-2009 Responsible Organization:

RXE, Reactor Engineering Prepared By: Lukus S. Barnes Approved By: C. Dale Greer WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 2 of 69 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change Rev 10 10/25/04 2,29 NON-INTENT change to add steps in Section 7.0 to manually place the shutdown monitors in the shutdown monitor mode after performance of ICRR using 11M mode. Rev 11 08/26/2005 1 -5,7, REVISION to address Reactivity Management 11 -14, 15, issues for WBN PER 84170. Updated 17,18,21, references, deleted Reactor Trip Data Book, and 26 -30 added Technical Reviewer sign-off, calculated

+1-500 pcm administrative limit band, and added 500 pcm review criteria.

10CFR50.59 Screening Review is NOT required.

Rev 12 08/25/2006 All REVISION to allow adjustments to the ECC due to anticipated CIPS effects per WBN PER 105805. Allow Sub-Critical Rod Worth Measurement results to be used as ECC for startup after a refueling.

Also, editorial changes to improve the ICRR figure and to add additional administrative criteria (750 pcm), add additional provisions for IGRR data collection for other than control banks, add additional ICRR Data Sheet and fix typos. Rev. 13 03/17/08 All REVISION to add guidance on BEACON General 3D Calc method for determining ECC. Added guidance on BEACON ECC method for determining ECC. Added adjustments to ECC boron concentration to account for CIPS and B-10 changes. Added guidance to use BEACON to predict the ICRR plots at the various criticality limits. Incorporates new bank overlap per DCN 52265. This procedure has been converted from Word 95 to Word XP using Rev. 12 by the Conversion Team. Rev. 14 09/16/09 All NON-INTENT change to clarify qualification and requirements of post-performance reviewer for ECP calculations (PER 169236). Re-ordered prerequisite steps. WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 2 of 69 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change Rev 10 10/25/04 2,29 NON-INTENT change to add steps in Section 7.0 to manually place the shutdown monitors in the shutdown monitor mode after performance of ICRR using 11M mode. Rev 11 08/26/2005 1 -5,7, REVISION to address Reactivity Management 11 -14, 15, issues for WBN PER 84170. Updated 17,18,21, references, deleted Reactor Trip Data Book, and 26 -30 added Technical Reviewer sign-off, calculated

+1-500 pcm administrative limit band, and added 500 pcm review criteria.

10CFR50.59 Screening Review is NOT required.

Rev 12 08/25/2006 All REVISION to allow adjustments to the ECC due to antiCipated CIPS effects per WBN PER 105805. Allow Sub-Critical Rod Worth Measurement results to be used as ECC for startup after a refueling.

Also, editorial changes to improve the ICRR figure and to add additional administrative criteria (750 pcm), add additional provisions for ICRR data collection for other than control banks, add additional ICRR Data Sheet and fix typos. Rev. 13 03/17/08 All REVISION to add guidance on BEACON General 3D Calc method for determining ECC. Added guidance on BEACON ECC method for determining ECC. Added adjustments to ECC boron concentration to account for CIPS and B-10 changes. Added guidance to use BEACON to predict the ICRR plots at the various criticality limits. Incorporates new bank overlap per DCN 52265. This procedure has been converted from Word 95 to Word XP using Rev. 12 by the Conversion Team. Rev. 14 09/16/09 All NON-INTENT change to clarify qualification and requirements of post-performance reviewer for ECP calculations (PER 169236). Re-ordered prerequisite steps.

WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 3 of 69 Table of Contents

1.0 INTRODUCTION

..........................................................................................................

5 1 .1 Purpose ........................................................................................................................

5 1.2 Scope ............................................................................................................................

5 1.2.1 Operability Tests to be Performed

..................................................................

5 1.2.2 Surveillance Requirements Fulfilled and Modes .............................................

5 1.3 Frequency and Conditions

............................................................................................

5

2.0 REFERENCES

.............................................................................................................

6 2.1 Performance References

..............................................................................................

6 2.2 Developmental References

............................................................. , ..........

..................

6 3.0 PRECAUTIONS AND LIMITATIONS

...........................................................................

7 4.0 PREREQUISITE ACTIONS ..........................................................................................

9 4.1 Preliminary Actions .......................................................................................................

9 4.2 Approvals and Notification

..........................................................................................

10 5.0 ACCEPTANCE CRITERIA .........................................................................................

11 5.1 TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA ........................................

11 5.2 OTHER ACCEPTANCE CRITERIA ............................................................................

11 5.3 REVIEW CRITERIA ....................................................................................................

11 6.0 PERFORMANCE

........................................................................................................

12 6.1 Sections to be Performed

...........................................................................................

12 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data ....................

13 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data ............................................................................................................................

17 6.4 ECP Hand Calculation Using Previous At-Power Data ...............................................

21 6.5 ECP Hand Calculation Following a Refueling Outage ................................................

25 6.6 ECP Calculation using BEACON General 3D Calc .....................................................

29 6.7 ECP Calculation using BEACON ECC ........................................................................

39 6.8 Detector Reliability and/or Base Count Rate Determination

.......................................

48 6.9 ICRR Monitoring

.........................................................................................................

50 6.10 Critical Data Evaluation

...............................................................................................

54 7.0 POST PERFORMANCE ACTiViTy ............................................................................

55 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 3 of 69 Table of Contents

1.0 INTRODUCTION

..........................................................................................................

5 1.1 Purpose ........................................................................................................................

5 1.2 Scope ............................................................................................................................

5 1.2.1 Operability Tests to be Performed

..................................................................

5 1.2.2 Surveillance Requirements Fulfilled and Modes .............................................

5 1.3 Frequency and Conditions

............................................................................................

5

2.0 REFERENCES

.............................................................................................................

6 2.1 Performance References

..............................................................................................

6 2.2 Developmental References

...........................................................................................

6 3.0 PRECAUTIONS AND LIMITATIONS

...........................................................................

7 4.0 PREREQUISITE ACTIONS ..........................................................................................

9 4.1 Preliminary Actions .......................................................................................................

9 4.2 Approvals and Notification

..........................................................................................

10 5.0 ACCEPTANCE CRITERIA .........................................................................................

11 5.1 TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA ........................................

11 5.2 OTHER ACCEPTANCE CRITERIA ............................................................................

11 5.3 REVIEW CRITERIA ....................................................................................................

11 6.0 PERFORMANCE

........................................................................................................

12 6.1 Sections to be Performed

...........................................................................................

12 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data ....................

13 6.3 REACTW/REACTINW ECP Calculation USing Previous Zero Power Data ............................................................................................................................

17 6.4 ECP Hand Calculation Using Previous At-Power Data ...............................................

21 6.5 ECP Hand Calculation Following a Refueling Outage ................................................

25 6.6 ECP Calculation using BEACON General 3D Calc .....................................................

29 6.7 ECP Calculation using BEACON ECC ........................................................................

39 6.8 Detector Reliability and/or Base Count Rate Determination

.......................................

48 6.9 ICRR Monitoring

.........................................................................................................

50 6.10 Critical Data Evaluation

...............................................................................................

54 7.0 POST PERFORMANCE ACTiViTy ............................................................................

55 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 4 of 69 Table of Contents (continued) 8.0 RECORDS ..................................................................................................................

56 8.1 QA Records ................................................................................................................

56 8.2 Non-QA Records ........................................................................................................

56 Appendix A: ICRR Monitoring

......... .............................................................................

57 Appendix B: Predicted ICRRs ........................................................................................

63 Appendix C: BEACON ECC ............................................................................................

66 Figure 1: ICCR VS Control Bank Position ...............................................................

67 Figure 2: CIPS Adjustment.

......................................................................................

68 Source Notes .............................................................................................

69 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 4 of 69 Table of Contents (continued) 8.0 RECORDS ..................................................................................................................

56 8.1 QA Records ................................................................................................................

56 8.2 Non-QA Records ........................................................................................................

56 Appendix A: ICRR Monitoring

......................................................

.................................

57 Appendix B: Predicted ICRRs ........................................................................................

63 Appendix C: BEACON ECC ...................................................

.........................................

66 Figure 1: ICCR VS Control Bank Position ..............................................

.................

67 Figure 2: CIPS Adjustment.

............................................

..........................................

68 Source Notes .............................................................................................

69 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 5 of69

1.0 INTRODUCTION

1.1 Purpose This instruction provides detailed steps for predicting the rod position or RCS boron concentration (C b) at which reactor criticality will be achieved.

This instruction also provides guidance for monitoring the approach to criticality.

1.2 Scope 1.2.1 Operability Tests to be Performed This instruction calculates the estimated critical conditions (ECC) i.e. critical rod position and boron concentration given existing conditions.

The control rod position is then verified to be above rod insertion limits and below administrative rod withdrawal limits for maintaining a negative moderator temperature coefficient (if applicable).

This instruction also monitors the approach to critical with collection and analysis of Inverse Count Rate Ratio (ICRR) data 1. 1.2.2 Surveillance Requirements Fulfilled and Modes Performance of this Instruction satisfies the following Surveillance Requirement (SR): SURVEILLANCE APPLICABLE PERFORMANCE REQUIREMENT MODES MODES SR 3.1.7.1 1,2 1 2 2 ,3 (1) with Keff 1 (2) with Keff < 1 1.3 Frequency and Conditions This Instruction is to be initiated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of achieving criticality.

WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 5 of 69

1.0 INTRODUCTION

1.1 Purpose This instruction provides detailed steps for predicting the rod position or RCS boron concentration (C b) at which reactor criticality will be achieved.

This instruction also provides guidance for monitoring the approach to criticality.

1.2 Scope 1.2.1 Operability Tests to be Performed This instruction calculates the estimated critical conditions (ECC) i.e. critical rod position and boron concentration given existing conditions.

The control rod position is then verified to be above rod insertion limits and below administrative rod withdrawal limits for maintaining a negative moderator temperature coefficient (if applicable).

This instruction also monitors the approach to critical with collection and analysis of Inverse Count Rate Ratio (lCRR) data 1. 1.2.2 Surveillance Requirements Fulfilled and Modes Performance of this Instruction satisfies the following Surveillance Requirement (SR): SURVEILLANCE REQUIREMENT SR3.1.7.1 (1) with Keff 1 (2) with Keff < 1 1.3 Frequency and Conditions APPLICABLE PERFORMANCE MODES MODES 1,2 1 22,3 This Instruction is to be initiated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of achieving criticality.

WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 6 of 69

2.0 REFERENCES

2.1 Performance References A. Core Operations Limit Report (COLR). B. Nuclear Operating Book (NOB), Sheet A-5, Negative MTC Withdrawal Limit Curve. C. Nuclear Parameters and Operations Package (NuPOP) for the applicable unit/cycle.

D. PET-201, Initial Criticality and Low Power Physics Testing. E. Computer Program REACTW Version WB2.0 and REACTW Computer Program User's Guide. F. Computer Program REACTINWVersion 2.0 and REACTINW Computer Program User's Guide. G. TI-54, Xenon Worth. H. TI-55, Samarium Worth. I. PCT-05-529, Axial Offset Validity Criteria Revision 3; June 30,2005 J. TI-7.014, Estimated Critical Condition (ECC) B-10 Adjustments 2.2 Developmental References A. SPP-10A, Reactivity Management Program. B. Unit 1 Technical Specifications, Section 3.1.7. C. BEACON Users Manual. WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 6 of 69

2.0 REFERENCES

2.1 Performance References A. Core Operations Limit Report (COLR). B. Nuclear Operating Book (NOB), Sheet A-5, Negative MTC Withdrawal Limit Curve. C. Nuclear Parameters and Operations Package (NuPOP) for the applicable unit/cycle.

D. PET-201, Initial Criticality and Low Power Physics Testing. E. Computer Program REACTW Version WB2.0 and REACTW Computer Program User's Guide. F. Computer Program REACTINW Version 2.0 and REACTINW Computer Program User's Guide. G. TI-54, Xenon Worth. H. TI-55, Samarium Worth. /. PCT-05-529, Axial Offset Validity Criteria Revision 3; June 30, 2005 J. TI-7.014, Estimated Critical Condition (ECC) B-10 Adjustments 2.2 Developmental References A. SPP-10.4, Reactivity Management Program. B. Unit 1 Technical Specifications, Section 3.1.7. C. BEACON Users Manual.

WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 7 of 69 3.0 PRECAUTIONS AND LIMITATIONS A. When using REACTW, REACTINW, or BEACON, this instruction requires an individual qualified in the use of the computer program, as defined in RXE Qualification Standard Practical Factor ESP320.311, ESP320.333, or ESP320.338, as applicable.

B. The same method should be used to determine both previous and current parameters to ensure accurate estimates of reactivity changes. C, When using REACTW to calculate estimated critical rod positions or estimated critical boron concentration, the computer inputs should be verified against the data tables from the NuPOP to ensure the input is within the range of the tables. (Done automatically when REACTINW is used). D. The NuPOP for the applicable unit and cycle must be used when performing this Instruction.

Care must be taken to use the tables for the correct burnup range. The burnup ranges are defined in NuPOP, Section 8.3. E. Xenon and its associated precursors may be in error after a reboot/startup of the plant computer.

Guidance for updating these values can be obtained from Reactor Engineering.

F. Samarium worth must be estimated by Reactor Engineering for each case when 10 days of power history is NOT available.

G. The 1000 pcm lower limit must be greater than COLR Rod Insertion Limit at zero power. H. Criticality must be anticipated at any time when positive reactivity is being added to the core.2 I. Personnel responsible for monitoring ICRR data are to immediately advise the Unit SRO of any unanticipated or unexplained response.

J. If ICRR data indicates that criticality will occur outside of the +/-750 pcm Allowable Tolerance Band of the estimated critical position with the ICRR value < 0.2, the Unit SRO is to be advised that the startup must be stopped. K. The ICRR curve "general trend" must be monitored to ensure the curve does NOT exhibit any abnormalities.

L. Following incremental additions of reactivity, a pause of 1 to 4 minutes should occur prior to ICRR data collection.

This will allow subcritical multiplication to increase thermal neutron flux to approximately its equilibrium value. As criticality is approached (i.e., keff approaches 1.0), neutron flux stabilization time should become longer prior to data collection.

This approach permits a more accurate determination to be made of core reactivity changes, and predicted critical condition.

3 ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 7 of 69 3.0 PRECAUTIONS AND LIMITATIONS A. When using REACTW, REACTINW, or BEACON, this instruction requires an individual qualified in the use of the computer program, as defined in RXE Qualification Standard Practical Factor ESP320.311, ESP320.333, or ESP320.338, as applicable.

B. The same method should be used to determine both previous and current parameters to ensure accurate estimates of reactivity changes. C, When using REACTW to calculate estimated critical rod positions or estimated critical boron concentration, the computer inputs should be verified against the data tables from the NuPOP to ensure the input is within the range of the tables. (Done automatically when REACTINW is used). D. The NuPOP for the applicable unit and cycle must be used when performing this Instruction.

Care must be taken to use the tables for the correct burnup range. The burnup ranges are defined in NuPOP, Section 8.3. E. Xenon and its associated precursors may be in error after a reboot/startup of the plant computer.

Guidance for updating these values can be obtained from Reactor Engineering.

F. Samarium worth must be estimated by Reactor Engineering for each case when 10 days of power history is NOT available.

G. The 1000 pcm lower limit must be greater than COLR Rod Insertion Limit at zero power. H. Criticality must be antiCipated at any time when positive reactivity is being added to the core.2 I. Personnel responsible for monitoring ICRR data are to immediately advise the Unit SRO of any unanticipated or unexplained response.

J. If ICRR data indicates that criticality will occur outside of the +/-750 pcm Allowable Tolerance Band of the estimated critical position with the ICRR value < 0.2, the Unit SRO is to be advised that the startup must be stopped. K. The ICRR curve "general trend" must be monitored to ensure the curve does NOT exhibit any abnormalities.

L. Following incremental additions of reactivity, a pause of 1 to 4 minutes should occur prior to ICRR data collection.

This will allow subcritical multiplication to increase thermal neutron flux to approximately its equilibrium value. As criticality is approached (i.e., keff approaches 1.0), neutron flux stabilization time should become longer prior to data collection.

This approach permits a more accurate determination to be made of core reactivity changes, and predicted critical condition.

3 .

') ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 8 of 69 3.0 PRECAUTIONS AND LIMITATIONS (continued)

M. When the ScalarlTimer is used, the count period (d T) for ICRR monitoring may be adjusted at the discretion of the Test Director (minimum of 10 seconds or at least 1000 counts/d T period). N. It is permissible to re-normalize ICRR plots to 1.0 at any time at the discretion of the Test Director OR when the ICRR value has decreased to a point where it is difficult to establish ICRR trends (e.g., re-normalize when the ICRR reaches 0.2). An acceptable method for re-normalization is to use the most recent count rate (C i) value as the new base count rate (Co). O. A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations by task qualified RXE or SRO/ST A. ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 8 of 69 3.0 PRECAUTIONS AND LIMITATIONS (continued)

M. When the ScalarlTimer is used, the count period for ICRR monitoring may be adjusted at the discretion of the Test Director (minimum of 10 seconds or at least 1 000 T period). N. It is permissible to re-normalize ICRR plots to 1.0 at any time at the discretion of the Test Director OR when the ICRR value has decreased to a point where it is difficult to establish ICRR trends (e.g., re-normalize when the ICRR reaches 0.2). An acceptable method for re-normalization is to use the most recent count rate (C i) value as the new base count rate (Co). O. A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations by task qualified RXE or SRO/ST A.

WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 9

___ .. ____ Data Package: Page _, _ of ..1-4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions RECORD start date and time on Surveillance Task Sheet. A primary method for performance of this instruction is use of the computer codes REACTINW or REACTW (which are verified and validated personal computer codes). A backup method is to use another computer with the verified and validated codes. These codes are installed on the TVA network and at least one personal computer in the Main Control Room. The use of BEACON is the other primary method. Hand calculations may also be performed as a backup method. ' IF REACTW or REACTINW are to be used, THEN OBTAIN PC with REACTWand/or REACTINW software installed in accordance with Release Memorandums. IF BEACON is to be used, THEN ACCESS the BEACON software via the HP workstation or through a PC with either Hummingbird Exceed, BlueZone, or other approved ethernet software installed.

Reference 2.1.1 contains guidance in performing the CIPS adjustment. IF an adjustment to the ECC is desired to account for CIPS effects, THEN PERFORM the following.

OTHERWISE, MARK this step N/A. INTEGRATE the Actual to Predicted Axial Offset \y. differences over the cycle life. J tAO

d BU = %

MWO/MTU !VjA N 4.0 WBN Estimated Critical Position Unit 1 Data Package: Page _, _ of PREREQUISITE ACTIONS 1-SI-0-11 Rev. 0014 Page 9 of 69 4.1 Preliminary Actions " RECORD start date and time on Surveillance Task Sheet. A primary method for performance of this instruction is use of the computer codes REACTINW or REACTW (which are verified and validated personal computer codes). A backup method is to use another computer with the verified and validated codes. These codes are installed on the TVA network and at least one personal computer in the Main Control Room. The use of BEACON is the other primary method. Hand calculations may also be performed as a backup method. IF REACTW or REACTINW are to be used, THEN OBTAIN PC with REACTWand/or REACTINW software installed in accordance with Release Memorandums. IF BEACON is to be used, THEN ACCESS the BEACON software via the HP workstation or through a PC with either Hummingbird Exceed, BlueZone, or other approved ethernet software installed.

Reference 2.1.1 contains guidance in performing the CIPS adjustment.

IF an adjustment to the ECC is desired to account for CIPS effects, THEN PERFORM the following.

OTHERWISE, MARK this step N/A. (S) INTEGRATE the Actual to Predicted Axial Offset " differences over the cycle life. J MO

d BU = %

MWO/MTU ----NA WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 10 of 69 Data Package: Page of 4.1 Preliminary Actions (continued) DETERMINE the increase in HZP reactivity from Figure 2.

= pcm '& DETERMINE the equivalent boron concentration increase by dividing the Step 4.1 [4]B value by the absolute difference of the differential boron worth from NuPOP Figure 6-22.

=

/ IDBWI = /1 ___ 1

= (+), __ _

!i/A-If the initial RCS B-10 concentration was significantly less than 19.78% and significant dilutions and/or borations were made to the RCS since the BEACON K bias was calibrated, then the ECC should be adjusted to account for B-1 0 concentration changes. Examples of significant dilutions or borations include the following:

At MOL at 800 ppm and 18% B-10, a dilution of 6,000 gal of Primary Water can result in a reactivity effect of up to 10 ppm. t MOL at 800 ppm and 18% B-10, a boration of 9,000 gal of Boric Acid can result in a reactivity effect of up to 10 ppm. At MOL at 800 ppm and 18% B-10, an RCS cooldown to Mode 5 results in significant makeup due to shrinkage. IF an adjustment to the ECC is desired to account for B-1 0 concentration changes, THEN PERFORM TI-7.014 and RECORD the net change in the ECC boron concentration due to the B-10 adjustment:

= (-) ppm 4.2 Approvals and Notification None !i/A-WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 10 of 69 Data Package: Page of 4.1 Preliminary Actions (continued) DETERMINE the increase in HZP reactivity from Figure 2.

= pcm DETERMINE the equivalent boron concentration increase " by dividing the Step 4.1 [4]B value by the absolute difference of the differential boron worth from NuPOP Figure 6-22.

=

/ IDBWI = ____ /1 ___ _

If the initial RCS B-10 concentration was significantly less than 19.78% and significant dilutions and/or borations were made to the RCS since the BEACON K bias was calibrated, then the ECC should be adjusted to account for B-1 a concentration changes. Examples of significant dilutions or borations include the following:

At MOL at 800 ppm and 18% B-10, a dilution of 6, 000 gal of Primary Water can result in a eactivity effect of up to 10 ppm. t MOL at 800 ppm and 18% B-10, a boration of 9,000 gal of Boric Acid can result in a r c ivity effect of up to 10 ppm. At MOL at 800 ppm and 18% B-10, an RCS cooldown to Mode 5 results in significant makeup due to shrinkage.

IF an adjustment to the ECC is desired to account for B-1 a concentration changes, THEN PERFORM TI-7.014 and RECORD the net change in the ECC boron concentration due to the B-10 adjustment:

= (-) ___ ppm 4.2 Approvals and Notification None WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 11 of 69 5.0 ACCEPTANCE CRITERIA 5.1 TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA A. Estimated Critical Rod Position (ECP) is above the Control Bank Insertion Limits specified in the COLR. B. Estimated critical rod position is below the Negative MTC Withdrawal Limit Curve in the NOB (if applicable).

5.2 OTHER ACCEPTANCE CRITERIA A. Estimated Critical Rod Position (ECP) was within 1000 pcm of the actual critical conditions.

B. Estimated Critical Rod Position (ECP) was within 750 pcm of the actual critical conditions. (If the ICRR projects criticality outside 750 pcm of the ECP with the ICRR value < 0.2, then the reactor startup is to be aborted.)

C. NIS Source Range channels are within one half (%) decade of each other. 5.3 REVIEW CRITERIA Estimated Critical Rod Position (ECP) was within 500 pcm of the actual critical conditions. (If the ECP was outside 500 pcm of the actual critical conditions, then a WBN PER is to be generated.) ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 11 of 69 5.0 ACCEPTANCE CRITERIA 5.1 TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA A. Estimated Critical Rod Position (ECP) is above the Control Bank Insertion Limits specified in the COLR. B. Estimated critical rod position is below the Negative MTC Withdrawal Limit Curve in the NOB (if applicable).

5.2 OTHER ACCEPTANCE CRITERIA A. Estimated Critical Rod Position (ECP) was within 1000 pcm of the actual critical conditions.

B. Estimated Critical Rod Position (ECP) was within 750 pcm of the actual critical conditions. (If the ICRR projects criticality outside 750 pcm of the ECP with the ICRR value < 0.2, then the reactor startup is to be aborted.)

C. NIS Source Range channels are within one half decade of each other. 5.3 REVIEW CRITERIA Estimated Critical Rod Position (ECP) was within 500 pcm of the actual critical conditions. (If the ECP was outside 500 pcm of the actual critical conditions, then a WBN PER is to be generated.)

) 6.0 WBN Estimated Critical Position Unit 1 Data Package: Page -3..-of PERFORMANCE 1-SI-0-11 Rev. 0014 Page 12 of 69 Date ;1v---6.1 Sections to be Performed

(& ' ENSURE Precautions and Limitations in Section 3.0 have been reviewed.

ENSURE Prerequisite Actions in Section 4.0 have been met. NOTES Familiarization with the User's Guides and release memorandums for REACTW and ." REACTINW will allow proper use of the computer programs and input of data. Use of Zero Power method is discouraged when the startup burnup is 3 EFPD greater than the previous startup's burnup. INDICATE sections to be performed: Section 6.2, REACTW/REACTINW ECP Calculation Y Using Previous At-Power Data. G Section 6.3, REACTW/REACTINW ECP Calculation Using Previous Zero Power Data. &. Section 6.4, ECP Hand Calculation Using Previous At-Power Data. Section 6.5, ECP Hand Calculation Following a Refueling

'-Outage. Section 6.6, ECP Calculation Using BEACON General 3D DCalc. & Section 6.7, ECP Calculation Using BEACON ECC Section 6.8, Detector Reliability and/or Base Count Rate Section 6.9, leRR Monitoring.

6.10, Critical Data Evaluation.

@ PERFORM selected section(s).

o o o Ii1" o o o o o 6.0 WBN Estimated Critical Position Unit 1 Data Package: Page -PERFORMANCE 1-SI-0-11 Rev. 0014 Page 12 of 69 6.1 Sections to be Performed ENSURE Precautions and Limitations in Section 3.0 have been reviewed.

ENSURE Prerequisite Actions in Section 4.0 have been met. NOTES Date IYv-Familiarization with the User's Guides and release memorandums for REACTW and REACTINW will allow proper use of the computer programs and input of data. Use of Zero Power method is discouraged when the startup burnup is 3 EFPD greater than the previous startup's burnup. INDICATE sections to be performed:

xtl Section 6.2, REACTW/REACTINW ECP Calculation

'-?< Using Previous At-Power Data. Q Section 6.3, REACTW/REACTINW ECP Calculation Using Previous Zero Power Data. Section 6.4, ECP Hand Calculation Using Previous c::::>( At-Power Data. Section 6.5, ECP Hand Calculation Following a Refueling , Outage. Section 6.6, ECP Calculation Using BEACON General 3D DCalc. & Section 6.7, ECP Calculation Using BEACON ECC Section 6.8, Detector Reliability and/or Base Count Rate Section 6.9, leRR Monitoring.

6.10, Critical Data Evaluation.

@ PERFORM selected section(s).

o o o o o o o o WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 13 of 69 Data Package: Page __ of __ Date __ _ 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data NOTE The following data can be obtained from the ICS Reactor Engineering Data Log. [1] RECORD the following data from the last stable at-power condition before shutdown and values expected for the reactor startup for input into the REACTW or REACTINW computer program: A. Reactor power prior to shutdown:

% RTP. B. Samarium (Sm) parameters for ECP. Select one:

Input Effective Samarium Power: %.

Input last 10 days' at power' power history.

Input Sm effective worth (See TI-55). C. Core average burnup: MWD/MTU. D. Boron Concentration (C b): ppm. E. Bank D Position:

steps. F. Delta Flux (<>>: %. G. Weighted Average Delta Flux (<>>: % (Reactor Trip Report or NuPOP Table 7-28) H. Shutdown Date and Time: I I -------Length of time since plant shutdown:

hrs. o o o ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 13 of 69 Data Package: Page __ of __ 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data NOTE Date ___ _ The following data can be obtained from the ICS Reactor Engineering Data Log. [1] RECORD the following data from the last stable at-power condition before shutdown and values expected for the reactor startup for input into the REACTW or REACTINW computer program: A. Reactor power prior to shutdown:

% RTP. B. Samarium (Sm) parameters for ECP. Select one:

Input Effective Samarium Power: %.
Input last 10 days' at power' power history.
Input Sm effective worth (See TI-55). C. Core average burn up: MWD/MTU. D. Boron Concentration (C b): ppm. E. Bank D Position:
steps. F. Delta Flux (D>: %. G. Weighted Average Delta Flux (8<1>>: % (Reactor Trip Report or NuPOP Table 7-28) H. Shutdown Date and Time: I I -------Length of time since plant shutdown:
____ hrs. 0 0 0
\ \ ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 14 of 69 Data Package: Page __ of __ Date __ _ 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data (continued)
I. Xenon and Iodine values at shutdown for ECP. Select one. 1. NoXe. 2. Equilibrium Xe and 1-use STEADY STATE Tables Equilibrium Rx Power for Xe 3. Input Xe and I -use TI-54 (NIX Tables) % of Full Power Equilibrium concentration for Xe % of Full Power Equilibrium concentration for I 4. Use Xe and I -from LAST Xenon Run % of Full Power Equilibrium concentration for Xe % of Full Power Equilibrium concentration for I J. Expected core avg. temperature at startup: OF. NOTE 0 0 % 0 % % 0 % % If adjustments to the ECC will be made to account for CIPS or B-1 0 concentration changes, then the expected boron concentration at startup used as input into REACTINW in the following step should subtract the value(s) for L1C b CIPS and L1C b B-10 recorded in Steps 4.1 [4] and 4.1 [5], respectively.
The L1C b CIPS and L1C b B-10 values will be added back in later. K. Expected boron concentration at startup: ppm. L. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank 0 (from NOB Sheet A-5, if applicable):
_____ steps. [2] RUN REACTW or REACTINW ECC program, AND PRINT the output file. \ WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 14 of 69 Data Package: Page __ of __ Date 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data (continued)
I. Xenon and Iodine values at shutdown for ECP. Select one. 1. NoXe. 0 2. Equilibrium Xe and I -use STEADY 8T ATE Tables 0 Equilibrium Rx Power for Xe % 3. Input Xe and I -use TI-54 (NIX Tables) 0 % of Full Power Equilibrium concentration for Xe % % of Full Power Equilibrium concentration for I % 4. Use Xe and I -from LAST Xenon Run 0 % of Full Power Equilibrium concentration for Xe % % of Full Power Equilibrium concentration for I % J. Expected core avg. temperature at startup: of. NOTE If adjustments to the ECC will be made to account for CIPS or B-1 0 concentration changes, then the expected boron concentration at startup used as input into REACTINW in the following step should subtract the value(s) for CIPS and 8-10 recorded in Steps 4.1 [4] and 4.1 [5], respectively.
The CIPS and 8-10 values will be added back in later. K. Expected boron concentration at startup: ____ ppm. L. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank D (from NOB Sheet A-5, if applicable):
______ steps. [2] RUN REACTW or REACTINW ECC program, AND PRINT the output file.
) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 15 of 69 Data Package: Page __ of __ Date __ _ 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data (continued)
[3] ENSURE input data is correct and within the range of the data tables in the NuPOP AND NOTIFY Reactor Engineering of any data outside the range for evaluation (NOT required if REACTINW is used). [4] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limit, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limit. [5] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). [6] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.2[1]L (Acceptance Criteria 5.1 B). [7] COMPLETE required entries on the REACTW output data sheets. [8] RECORD 1000 pcm lower limit: Bank D at steps. Bank C at steps. [9] ATTACH computer printouts to Data Package. WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 15 of 69 Data Package: Page __ of __ Date 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data (continued)
[3] ENSURE input data is correct and within the range of the data tables in the NuPOP AND NOTIFY Reactor Engineering of any data outside the range for evaluation (NOT required if REACTINW is used). [4] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limit, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limit. [5] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). [6] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.2[1]L (Acceptance Criteria 5.1 B). [7] COMPLETE required entries on the REACTW output data sheets. [8] RECORD 1000 pcm lower limit: Bank D at steps. Bank C at steps. [9] ATTACH computer printouts to Data Package.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 16 of 69 Data Package: Page __ of __ Date ___ _ 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data (continued)
[10] IF an adjustment to the ECC is desired to account for either CIPS or B-10 concentration change effects, THEN PERFORM the following:
A. DETERMINE the adjusted ECC boron concentration by adding Step 4.1 [4]C and 4.1 [5] values to the estimated critical boron concentration from the REACTWor REACTI NW output. EGG G b =
+
+
EGG G b = ppm + ppm + ppm (REAGTW) (Step 4.1 [4]G) (Step 4.1 [5]) EGG G b = ___ ppm B. ANNOTATE the REACTWor REACTINWoutput to reflect the adjusted ECC boron concentration.
NOTE A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[11] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review. [12] OBTAIN SM/US review and approval of ECP. SM/US WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 PaJle 16 of 69 Data Package: Page __ of __ Date ___ _ 6.2 ECP REACTW/REACTINW Calculation Using Previous At-Power Data (continued)
[10] IF an adjustment to the ECC is desired to account for either CIPS or B-10 concentration change effects, THEN PERFORM the following:
A. DETERMINE the adjusted ECC boron concentration by adding Step 4.1 [4]C and 4.1 [5] values to the estimated critical boron concentration from the REACTWor REACTINWoutput.
LiC b REACTW + + ECC C b = ppm + ppm + ppm (REACTW) (Step 4.1 [4]C) (Step 4.1 [5]) ___ ppm B. ANNOTATE the REACTWor REACTINWoutput to reflect the adjusted ECC boron concentration.
NOTE A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[11] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review. [12] OBTAIN SM/US review and approval of ECP. SM/US WBN Estimated Critical Position 1-SI-0-11 I Unit 1 Rev. 0014 Page 17 of 69 I Data Package: Page __ of __ Date __ _ 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data NOTES 1) The following data can be obtained from the ICS Reactor Engineering Data Log. 2) Use of Zero Power method is discouraged when the startup burnup is 3 EFPD or more greater than the previous startup's burnup. [1] RECORD the following data from a previous reactor startup for input into the REACTWor REACTINW computer program: A. Core average burnup: MWD/MTU. B. Core average temperature:
of. C. Boron Concentration (C b): ppm. D. Xenon and Effective Samarium values at startup:
Xenon Worth: (-) PCM.
Eff. Samarium Worth: (-) PCM. E. Delta Axial Offset: %. F. Bank D Position:
steps. [2] RECORD the following data for input into the REACTWor REACTINW computer program from last stable at-power condition before shutdown:
A. Reactor (Rx) power prior to shutdown:
%. B. Sm parameters for ECP. Select one.
Input Effective Samarium Power: %.
Input last 10 days 'at power' power history.
Input Sm effective worth (See TI-55). C. Core average burn up: MWD/MTU. D. Boron Concentration (C b): ppm. D D D WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 17 of 69 Data Package: Page __ of __ 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data NOTES Date ___ _ 1) The following data can be obtained from the ICS Reactor Engineering Data Log. 2) Use of Zero Power method is discouraged when the startup burnup is 3 EFPD or more greater than the previous startup's burnup. [1] RECORD the following data from a previous reactor startup for input into the REACTW or REACTINW computer program: A. Core average burnup: ____ MWD/MTU. B. Core average temperature:
OF. C. Boron Concentration (C b): ppm. D. Xenon and Effective Samarium values at startup:
Xenon Worth: (-) _____ PCM.
Eff. Samarium Worth: (-) ____ PCM. E. Delta Axial Offset: %. F. Bank D Position:
steps. [2] RECORD the following data for input into the REACTWor REACTI NW computer program from last stable at-power condition before shutdown:
A. Reactor (Rx) power prior to shutdown:
%. B. Sm parameters for ECP. Select one.
Input Effective Samarium Power: ___ %.
Input last 10 days 'at power' power history.
Input Sm effective worth (See TI-55). C. Core average burnup: ____ MWD/MTU. D. Boron Concentration (C b): ____ ppm. D D D WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 18 of 69 Data Package: Page __ of __ 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
E. Bank D Position:
steps. F. Delta Flux (8cI>>: %. G. Weighted Average Delta Flux (8cI>>: %. (Reactor Trip Report or NuPOP Table 7-28) H. Shutdown Date and Time: / / . -------Length of time since plant shutdown:
hrs. I. Xenon and Iodine values at shutdown for ECP. Select one. 1. NoXe. 2. Equilibrium Xe and 1-use STEADY STATE Tables Equilibrium Rx Power for Xe 3. Input Xe and I -use TI-S4 (NIX Tables) % of Full Power Equilibrium concentration for Xe % of Full Power Equilibrium concentration for I 4. Use Xe and I -from LAST Xenon Run % of Full Power Equilibrium concentration for Xe % of Full Power Equilibrium concentration for I J. Expected core avg. temperature at startup: of. K. Expected critical boron concentration at startup: ____ ppm. L. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank D from NOB Sheet A-5 (if applicable):
____ steps. Date ___ _ D D % D % % D %
% WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 18 of 69 Data Package: Page __ of __ 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
E. Bank D Position:
____ steps. F. Delta Flux (<><p): ___ %. G. Weighted Average Delta Flux (<><p): %. (Reactor Trip Report or NuPOP Table 7-28) H. Shutdown Date and Time: / / -------Length of time since plant shutdown:
_____ hrs. I. Xenon and Iodine values at shutdown for ECP. Select one. 1. NoXe. 2. Equilibrium Xe and 1-use STEADY STATE Tables Equilibrium Rx Power for Xe 3. Input Xe and I -use TI-54 (NIX Tables) % of Full Power Equilibrium concentration for Xe % of Full Power Equilibrium concentration for I 4. Use Xe and I -from LAST Xenon Run % of Full Power Equilibrium concentration for Xe % of Full Power Equilibrium concentration for I J. Expected core avg. temperature at startup: of. K. Expected critical boron concentration at startup: ____ ppm. L. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank D from NOB Sheet A-5 (if applicable):
____ steps. Date ----0 0 % 0 % % 0 % %
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 19 of 69 Data Package: Page __ of __ 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
[3] RUN REACTW or REACTINW ECC program, AND PRINT the output file. [4] ENSURE input data is correct and within the range of the data tables in the NuPOP AND NOTIFY Reactor Engineering of any data outside the range for evaluation (NOT required if REACTINW is used). [5] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limit, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limit. [6] VERIFY ECP is above the Control Bank Insertion limits in the COLR (Acceptance Criteria 5.1A). [7] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.3[2]L (Acceptance Criteria 5.1 B). [8] COMPLETE required entries on the REACTW output data sheets. [9] ATTACH computer printouts to Data Package. [10] RECORD the 1000 pcm lower limit: Bank D at steps. Bank C at steps. Date ___ _ ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 19 of 69 Data Package: Page __ of __ 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
[3] RUN REACTW or REACTINW ECC program, AND PRINT the output file. [4] ENSURE input data is correct and within the range of the data tables in the NuPOP AND NOTIFY Reactor Engineering of any data outside the range for evaluation (NOT required if REACTINW is used). [5] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limit, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limit. [6] VERIFY ECP is above the Control Bank Insertion limits in the COLR (Acceptance Criteria 5.1A). [7] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.3[2]L (Acceptance Criteria 5.1 B). [8] COMPLETE required entries on the REACTW output data sheets. [9] ATTACH computer printouts to Data Package. [10] RECORD the 1000 pcm lower limit: Bank D at steps. Bank C at steps. Date __ _
6.3 WBN Estimated Critical Position 1-81-0-11 Unit 1 Rev. 0014 Page 20 of 69 Data Package: Page __ of __ REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
NOTE Date ___ _ A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[11] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review. [12] OBTAIN SM/US review and approval of ECP. SM/US WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Pa_ge 20 of 69 Data Package: Page __ of __ 6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
NOTE Date ___ _ A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[11] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review. [12] OBTAIN SM/US review and approval of ECP. SM/US WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 21 of 69 Data Package: Page __ of __ Date 6.4 ECP Hand Calculation Using Previous At-Power Data [1 ] RECORD the following data from the last stable at-power condition before shutdown for input into a copy of NuPOP Table 7-16: A. Shutdown Date and Time: I I -------B. Reactor power before shutdown:
%. C. Effective Samarium Power (i.e. last 10 days 'at power' power history average):
%. D. Core average burn up: MWD/MTU. E. Boron Concentration (C b): ppm. F. Bank D Position:
steps. G. Delta Flux (8>: %. H. Weighted Average Delta Flux: %. (Reactor Trip Report or NuPOP Table 7-28) [2] RECORD the following:
A. Expected Date and Time of criticality:
_1_1 __ :_ Time since plant shutdown:
hrs B. Expected Core average temperature at startup: OF ----NOTE If adjustments to the ECC will be made to account for CIPS or B-10 concentration changes, then the expected boron concentration at startup in the following step should subtract the value(s) for CIPS and B-10 recorded in Steps 4.1 [4]C and 4.1 [5], respectively.
The and values will be added back in later. C. Expected boron concentration at startup: ppm D. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank D from NOB Sheet A-5 (if applicable):
____ steps WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 21 of 69 Data Package: Page __ of __ 6.4 ECP Hand Calculation Using Previous At-Power Data [1] RECORD the following data from the last stable at-power condition before shutdown for input into a copy of NuPOP Table 7-16: [2] A. Shutdown Date and Time: I I -------B. Reactor power before shutdown:
%. C. Effective Samarium Power (i.e. last 10 days 'at power' power history average):
%. D. Core average burn up: MWD/MTU. E. Boron Concentration (C b): ppm. F. Bank D Position:
steps. G. Delta Flux (8>: %. H. Weighted Average Delta Flux: %. (Reactor Trip Report or NuPOP Table 7-28) RECORD the following:
A. Expected Date and Time of criticality:
_1_1 __ :_ Time since plant shutdown:
____ hrs B. Expected Core average temperature at startup: of ----NOTE Date ----If adjustments to the ECC will be made to account for CIPS or B-10 concentration changes, then the expected boron concentration at startup in the following step should subtract the value(s) for and recorded in Steps 4.1[4]C and 4.1[5], respectively.
The CIPS and 8-10 values will be added back in later. C. Expected boron concentration at startup: ppm D. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank D from NOB Sheet A-5 (if applicable):
____ steps
') /' WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 22 of 69 Data Package: Page __ of __ Date ___ _ 6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
[3] CALCULATE ECP using NuPOP ECP calculation worksheets from Table 7-16, AND RECORD signature and date on each data sheet. [4] IF an adjustment to the ECC is desired to account for either CIPS or B-10 concentration change effects, THEN PERFORM the following:
A. DETERMINE the adjusted ECC boron concentration by adding Steps 4.1 [4]C and 4.1 [5] values to the estimated critical boron concentration from the NuPOP Table 7-16 worksheet:
EGG G b = ilG b NuPOP + ilG b CIPS + ilG b 8-10 EGG G b =
ppm + ppm + ppm (NuPOP) (Step 4.1 [4]G) (Step 4.1 [5]) EGG G b = ___ ppm B. ANNOTATE the NuPOP Table 7-16 worksheet to reflect the adjusted ECC boron concentration.
NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. [5] RECORD Total Reactivity Change (Step E.1 of NuPOP Table 7-16 worksheet)
= pcm. [6] CALCULATE AND RECORD the administrative ECC-ACC limits from NuPOP Table 7-29 using the MO from NuPOP Table 7-16 Step D.13 and reactivity values listed below: A. Upper 1000 pcm limit: Step 6.4[5] -1000 pcm = pcm. Bank C at steps & Bank D at steps WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 22 of 69 Data Package: Page __ of __ Date ___ _ 6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
[3] CALCULATE ECP using NuPOP ECP calculation worksheets from Table 7-16, AND RECORD signature and date on each data sheet. [4] IF an adjustment to the ECC is desired to account for either CIPS or B-1 0 concentration change effects, THEN PERFORM the following:
A. DETERMINE the adjusted ECC boron concentration by adding Steps 4.1 [4]C and 4.1 [5] values to the estimated critical boron concentration from the NuPOP Table 7-16 worksheet:
EGG G b =
+ + EGG G b = ___ ppm + ppm + ppm (NuPOP) (Step 4.1 [4]G) (Step 4.1 [5]) EGG G b = ___ ppm B. ANNOTATE the NuPOP Table 7-16 worksheet to reflect the adjusted ECC boron concentration.
NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. [5] RECORD Total Reactivity Change (Step E.1 of NuPOP Table 7-16 worksheet)
= pcm. [6] CALCULATE AND RECORD the administrative ECC-ACC limits from NuPOP Table 7-29 using the MO from NuPOP Table 7-16 Step 0.13 and reactivity values listed below: A. Upper 1000 pcm limit: Step 6.4[5] -1000 pcm = pcm. Bank C at ___ steps & Bank 0 at ___ steps
) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 PaJle 23 of 69 Data Package: Page __ of __ Date ___ _ 6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
B. Lower 1000 pcm limit: Step 6.4[5] + 1000 pcm = pcm. Bank C at steps & Bank 0 at steps C. Upper 750 pcm limit: Step 6.4[5] -750 pcm = pcm. Bank Cat steps & Bank 0 at steps o. Lower 750 pcm limit: Step 6.4[5] + 750 pcm = pcm. Bank Cat steps & Bank 0 at steps E. Upper 500 pcm threshold:
Step 6.4[5] -500 pcm = pcm. Bank Cat steps & Bank 0 at steps F. Lower 500 pcm threshold:
Step 6.4[5] + 500 pcm = pcm. Bank Cat steps & Bank 0 at steps [7] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limits, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limits. [8] ATTACH ECP worksheets to Data Package. [9] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). [10] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2]0 (Acceptance Criteria 5.1 B). WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 23 of 69 Data Package: Page __ of __ Date __ _ 6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
B. Lower 1000 pcm limit: Step 6.4[5] + 1000 pcm = pcm. Bank C at steps & Bank 0 at steps C. Upper 750 pcm limit: Step 6.4[5] -750 pcm = pcm. Bank Cat steps & Bank 0 at steps O. Lower 750 pcm limit: Step 6.4[5] + 750 pcm = pcm. Bank Cat steps & Bank 0 at steps E. Upper 500 pcm threshold:
Step 6.4[5] -500 pcm = pcm. Bank Cat steps & Bank 0 at steps F. Lower 500 pcm threshold:
Step 6.4[5] + 500 pcm = pcm. Bank Cat steps & Bank 0 at steps [7] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limits, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limits. [8] ATTACH ECP worksheets to Data Package. [9] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). [10] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2]0 (Acceptance Criteria 5.1 B).
) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 24 of 69 Data Package: Page
__ of __ Date ___ _ 6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
[11] RECORD the following:
A. Date of calculation: / / B. Time of calculation:
___ _ NOTE A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[12] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review. [13] OBTAIN SM/US review and approval of ECP. SM/US WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 24 of 69 Data Package: Page __ of __ Date ----6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
[11] RECORD the following:
A. Date of calculation: / / B. Time of calculation:

NOTE A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.

[12] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review. [13] OBTAIN SM/US review and approval of ECP. SM/US
) 6.5 WBN Estimated Critical Position 1*51*0*11 Unit 1 Rev. 0014 Page 25 of 69 Data Package: Page of Date ECP Hand Calculation Following a Refueling Outage RECORD the following from NuPOP Table 4-8: .
Rods Out (ARO) Critical C b: 1481. ppm. "& Differential Boron Worth (DBW) at the ARO Critical C b: -".20 pcm/ppm. 1"1,..-'@< '& RECORD the desired Control Bank D rod position for initial criticality (i.e. ECP): ECP = J {gO steps RECORD the inserted integral rod worth for the desired critical rod position (Step 6.5[2]) from NuPOP Table 7-30: I nserted Rod Worth = ZS"t.j. 5 pcm IF performing a dilute-to-critical, THEN CALCULATE the critical boron concentration at the ECP as follows: EGG G b = AROG b + (Inserted Rod Worth DBW) /b---EGG G b = ppm + _____ pcm + __ pcm/ppm (Step 6.5[1 ]A) (Step 6.5[3]) (Step 6.5[1 ]B) EGG G b = ___ ppm for Bank 0 at steps & IF performing a pull-to-critical, THEN PERFORM the following sub-steps: RECORD the ARO Critical C b inferred by the Sub-Critical Rod Worth Measurement from PET-107: Inferred ARO C b = 11eo ppm "t..--WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 25 of 69 Data Package: Page of 6.5 ECP Hand Calculation Following a Refueling Outage RECORD the following from NuPOP Table 4-8: All Rods Out (ARO) Critical C b: 1481 ppm. Differential Boron Worth (DBW) at the ARO Critical C b: -".20 pcm/ppm. RECORD the desired Control Bank D rod position for initial criticality (i.e. ECP): ECP = J {gO steps RECORD the inserted integral rod worth for the desired critical rod position (Step 6.5[2]) from NuPOP Table 7-30: Inserted Rod Worth = tc;q . .3 pcm @ IF performing a dilute-to-critical, THEN CALCULATE the critical boron concentration at the ECP as follows: Date ECC C b = + (Inserted Rod Worth D8W) ECC C b = ppm + _____ pcm + __ pcm/ppm (Step 6.5[1]A) (Step 6.5[3]) (Step 6.5[1]8) ECC C b = ___ ppm for 8ank D at ___ steps & IF performing a pull-to-critical, THEN PERFORM the following sub-steps:
>Y:\ RECORD the ARO Critical Cb inferred by the Sub-Critical Rod Worth Measurement from PET-107: Inferred ARO C b = 1100 ppm
') WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 26 of 69 Data Package: Page L of ...:1.-Date LV' 6.5 ECP Hand Calculation Following a Refueling Outage (continued) CALCULATE the critical boron concentration at the ECP ECC C b = Inferred ARO C b + (Inserted Rod Worth + DBW) ECC C b = 1100 ppm (Step 6.5[5]A ) + .lS"4.3 pcm (Step 6.5[3]) + ".7-pcm/ppm (Step 6.5[1 ]B) ECC C b = 174' ppm for Bank 0 at 'iDO steps VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). i. IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2]D (Acceptance Criteria 5.1 B). NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: A. DETERMINE the Upper 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] -1000 pcm = -74(" pcm Bank C at e steps & Bank D at 2.2 e-steps B. DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 1000 pcm = 'zs4 pcm Bank C at ' 2. steps & Bank D at 4<0 steps /\..----WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 26 of 69 Data Package: Page of 6.5 ECP Hand Calculation Following a Refueling Outage (continued)
/<;} CALCULATE the critical boron concentration at the ECP Date /V ECC C b = Inferred ARO C b + (Inserted Rod Worth DBW) ECC C b = 1100 ppm (Step 6.5[5]A ) + ZS"4.3 pcm (Step 6.5[3]) + ".1-. pcm/ppm (Step 6.5[1]B) ECC C b = 174\ ppm for Bank 0 at I fcO steps VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.4[2]0 (Acceptance Criteria 5.1 B). NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. [8] CALCULATE, AND RECORD the UPPER and LOWER Acceptance Bands: A. DETERMINE the Upper 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] -1000 pcm = -74lP pcm Bank C at 7.2 e, steps & Bank 0 at 22 steps B. DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30: Step 6.5[3] + 1000 pcm = I zs4 pcm Bank Cat Ito z. steps & Bank 0 at 4<0 steps WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 27 of 69 Data Package: Page of 6.5 ECP Hand Calculation Following a Refueling Outage (continued) )C) DETERMINE the Upper 750 pcm Limit from NuPOP Table LX 7-30: Step 6.5[3] -750 pcm = -49(" pcm Bank C at B steps & Bank 0 at U.S steps DETERMINE the Lower750 pcm Limit from NuPOP Table LXZ-30: Step 6.5[3] + 750 pcm = 1004 pcm Bank Cat l S z.. steps & Bank 0 at lQto steps DETERMINE the Upper 500 pcm Limit from NuPOP Table L:XJ-30: Step 6.5[3] -500 pcm = -Z'i-S' pcm Bank Cat z.2e steps & Bank 0 at zze steps the Lower 500 pcm Limit from NuPOP Table Step 6.5[3] + 500 pcm = 75"'4 pcm Bank Cat 2t>4 steps & Bank 0 at 88 steps 13( RECORD the following:
A. Date of calculation:
.....,....
---B. Time of calculation:
A-: -""l--------NOTE rt,.....--
V't----A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[10] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review. WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 27 of 69 Data Package: Page of 6.5 ECP Hand Calculation Following a Refueling Outage (continued)
"!C) DETERMINE the Upper 750 pcm Limit from NuPOP Table LX 7-30: Step 6.5[3] -750 pcm = -4gs pcm Bank C at ;?2 B steps & Bank D at steps DETERMINE the pcm Limit from NuPOP Table l.:XZ-30: Step 6.5[3] + 750 pcm = 1004 pcm Bank C at I e z.. steps & Bank D at to Co steps ')(;\ DETERMINE the Upper 500 pcm Limit from NuPOP Table lY-J-30: Step 6.5[3] -500 pcm = S" pcm Bank Cat 22a steps & Bank D at z.ze steps t<7)DETERMINE the Lower 500 pcm Limit from NuPOP Table LXZ-30: Step 6.5[3] + 500 pcm = 7'£>>4 pcm Bank Cat 2t>4 steps & Bank D at 88 steps & RECORD the following:
A. Date of calculation:

B. Time of calculation:

/t-: .....-1...---

NOTE J/L,---A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.

[10] OBTAIN review of calculations and results by task qualified individual.
An STA or SRO may also perform this review.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 ) Page 28 of 69 Data Package: Page of Date ----6.5 ECP Hand Calculation Following a Refueling Outage (continued)
[11] OBTAIN SM/US review and approval of ECP. SM/US ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 28 of 69 Data Package: Page of Date __ _ 6.5 ECP Hand Calculation Following a Refueling Outage (continued)
[11] OBTAIN SM/US review and approval of ECP. SM/US
') WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 29 of 69 Data Package: Page __ of __ Date __ _ 6.6 ECP Calculation using BEACON General 3D Calc NOTE Familiarization with BEACON User's Guides will enable proper use of BEACON. [1] PERFORM the following to obtain the Reference Statepoint:
A. START BEACON for the current unit and cycle. B. SELECT BEACON Analysis>
Function>
General 3D Calc. NOTE Up until the last depletion step, "Boron" searches may be performed.
The input of the actual RCS boron concentration and the "None" search need only be performed in the last depletion step. C. DEPLETE a BEACON model to the exact conditions of a stable plant condition just prior to the plant shutdown using a "Criticality Search" of "None" and "Time Step" depletions.
D. RECORD the following information:
Model: Power: rei Tin: OF Burnup: MWD/MTU K eff: Boron: ppm D Bank: steps (actual) (actual) (actual) (calculated) (actual) (actual) \ I WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 29 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc NOTE Familiarization with BEACON User's Guides will enable proper use of BEACON. [1] PERFORM the following to obtain the Reference Statepoint:
A. START BEACON for the current unit and cycle. B. SELECT BEACON Analysis>
Function>
General 3D Calc. NOTE Up until the last depletion step, "Boron" searches may be performed.
The input of the actual RCS boron concentration and the "None" search need only be performed in the last depletion step. C. DEPLETE a BEACON model to the exact conditions of a stable plant condition just prior to the plant shutdown using a "Criticality Search" of "None" and "Time Step" depletions.
D. RECORD the following information:
Model: Power: rei Tin: Burnup: MWD/MTU K eff: Boron: ppm D Bank: steps (actual) (actual) (actual) ( calculated) (actual) (actual)
) WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 30 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
[2] PERFORM the following to obtain the Shutdown Statepoint:
NOTE It does not matter that "Desired K" defaults to 1.00000 in the following depletions.
A. DEPLETE the BEACON model created in Step 6.6[1]C to mimic reactor operations from the time of the Reference Statepoint to the time of the reactor shutdown using a "Criticality Search" of "Boron" and "Time Step" depletions.
B. RECORD the following information:
Model: Power: 0 rei (defined)
Tin: 557 of (defined)
Burnup: MWD/MTU ( calculated)
Time: hr ( calculated)
Shutdown Date and Time: _1_1-at ----NOTE If a "Rods" search will be performed in the following step AND if adjustments to the ECC will be made to account for CIPS or B-10 concentration changes, then the expected boron concentration at startup used as input into BEACON should subtract the value(s) for L1C b CIPS and L1Cb B-10 recorded in Steps 4.1 [4]C and 4.1 [5] , respectively.
The L1C b CIPS and L1Cb B-10 values will be added back in later. [3] PERFORM the following to obtain the Startup Statepoint:
A. DEPLETE the BEACON Model created in Step 6.6[2]A to the conditions for the reactor startup with the "K eff' from Step 6.6[1]0 entered as "Desired K" and using a "Time Step" depletion.
A "Criticality Search" of either "Boron" or "Rods" may be used depending upon which parameter is desired to remain fixed. WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 30 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
[2] PERFORM the following to obtain the Shutdown Statepoint:
NOTE It does not matter that "Desired K" defaults to 1.00000 in the following depletions.
A. DEPLETE the BEACON model created in Step 6.6[1]C to mimic reactor operations from the time of the Reference Statepoint to the time of the reactor shutdown using a "Criticality Search" of "Boron" and "Time Step" depletions.
B. RECORD the following information:
Model: Power: 0 rei (defined)
Tin: 557 of (defined)
Burnup: MWD/MTU (calculated)
Time: hr (calculated)
Shutdown Date and Time: I I at -------NOTE If a "Rods" search will be performed in the following step AND if adjustments to the ECC will be made to account for CIPS or B-10 concentration changes, then the expected boron concentration at startup used as input into BEACON should subtract the value(s) for L1CbCIPS and L1C b B-10 recorded in Steps 4.1[4]C and 4.1[5], respectively.
The L1CbCIPS and L1C b B-10 values will be added back in later. [3] PERFORM the following to obtain the Startup Statepoint:
A. DEPLETE the BEACON Model created in Step 6.6[2]A to the conditions for the reactor startup with the "K eff' from Step 6.6[1]0 entered as "Desired K" and using a "Time Step" depletion.
A "Criticality Search" of either "Boron" or "Rods" may be used depending upon which parameter is desired to remain fixed.
6.6 ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 31 of 69 Data Package: Page __ of __ Date-'--__ ECP Calculation using BEACON General 3D Calc (continued)
8. RECORD the following information:
Model: Power: 0 rei (defined)
Tin: 557 of (defined)
Burnup: MWD/MTU (same) Time: hr (calculated)
Keff: (from Step 6.6[1]D) Boron: ppm Xe Worth: pcm (calculated)
Sm Worth: pcm (calculated)
D Bank: steps Startup Date and Time: _1_1-at ----[4] ADJUST the EGG boron concentration for GIPS or 8-10 concentration change effects by adding Steps 4.1 [4]G and 4.1 [5] values to the estimated critical boron concentration from Step 6.6[3]8, as applicable:
EGG G b = ilGbBEACON
+ ilGbCIPS + ilG b B-10 EGG G b = ppm + ppm + ppm (Step 6.6[3]B) (Step 4.1 [4]G) (Step 4.1 [5]) EGG G b = ___ ppm ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 31 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
B. RECORD the following information:
Model: Power: 0 rei (defined)
Tin: 557 of (defined)
Burnup: MWD/MTU (same) Time: hr ( calculated)
K eff: (from Step 6.6[1]D) Boron: ppm Xe Worth: pcm ( calculated)
Sm Worth: pcm ( calculated)
D Bank: steps Startup Date and Time: _1_1-at ----[4] ADJUST the ECC boron concentration for CIPS or B-10 concentration change effects by adding Steps 4.1 [4]C and 4.1 [5] values to the estimated critical boron concentration from Step 6.6[3]B, as applicable:
EGG G b = + + EGG G b = ppm + ppm + ppm (Step 6.6[3]B) (Step 4.1 [4]G) (Step 4.1 [5]) EGG G b = ___ ppm WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 32 of 69 Data Package: Page __ of __ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
[5] PERFORM the following to obtain the K eff value with Control Banks Inserted (CBI): A. DEPLETE the BEACON Model created in Step 6.6[3]A with Control Banks Inserted (CBI) using a "Criticality Search" of "None" and a Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months . B. RECORD the following information:
Model: Date ___ _ K eff: (calculated) o Bank: 0 steps (defined)
C Bank: 0 steps (defined)
B Bank: 0 steps (defined)
A Bank: 0 steps (defined)
[6] PERFORM the following to obtain the K eff value with control banks at the Rod Insertion Limit (RIL): A. DEPLETE the BEACON Model created in Step 6.6[5]A with control banks at the Rod Insertion Limit (RIL) using a "Criticality Search" of "None" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months . B. RECORD the following information:
Model: Keff: o Bank: o steps C Bank: steps B Bank: steps A Bank: 228 steps (calculated) (defined) (COLR) (COLR) (defined)
WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 32 of 69 Data Package: Page __ of __ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
[5] PERFORM the following to obtain the K eff value with Control Banks Inserted (CBI): A. DEPLETE the BEACON Model created in Step 6.6[3]A with Control Banks Inserted (CBI) using a "Criticality Search" of "None" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months . B. RECORD the following information:
Model: Date ___ _ K eff: (calculated)
D Bank: 0 steps (defined)
C Bank: 0 steps (defined)
B Bank: 0 steps (defined)
A Bank: 0 steps (defined)
[6] PERFORM the following to obtain the K eff value with control banks at the Rod Insertion Limit (RIL): A. DEPLETE the BEACON Model created in Step 6.6[5]A with control banks at the Rod Insertion Limit (RIL) using a "Criticality Search" of "None" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months . B. RECORD the following information:
Model: Keff: D Bank: o steps C Bank: steps B Bank: steps A Bank: 228 steps (calculated) (defined) (COLR) (COLR) (defined)
) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 33 of 69 Data Package: Page __ of __ Date __ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
[7] PERFORM the following to obtain the K eff value with control banks at the Full Out Rod Position:
A. DEPLETE the BEACON Model created in Step 6.6[6]A with control banks at the Full Out Rod Position using a "Criticality Search" of "None" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months . B. RECORD the following information:
Model: Keff: (calculated)
D Bank: steps (NOB Sh A-7) C Bank: steps (NOB Sh A-7) B Bank: steps (NOB Sh A-7) A Bank: steps (NOB Sh A-7) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 33 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
[7] PERFORM the following to obtain the K eff value with control banks at the Full Out Rod Position:
A. DEPLETE the BEACON Model created in Step 6.6[6]A with control banks at the Full Out Rod Position using a "Criticality Search" of "None" and a Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months . B. RECORD the following information:
Model: K eff: (calculated)
D Bank: steps (NOB Sh A-7) C Bank: steps (NOB Sh A-7) B Bank: steps (NOB Sh A-7) A Bank: steps (NOB Sh A-7)
'\ ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 34 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE A facsimile of Appendix B Table 1 may be completed and attached to the data package in place of Appendix B Table 1. [8] PERFORM the following to obtain the bank positions associated with the conditions listed in Appendix B Table 1 with the reactor critical (lCRR = 0): A. RECORD the reference effective multiplication factor, Kel ef , for each condition in Table 1 from the "K eff' value recorded in earlier steps as specified.
B. CALCULATE AND RECORD the effective multiplication factor, Desired K, for each condition in Table 1 using the applicable values from Table 1 according to the following equation:
Desired K = K Ref eff (Limit) Ref
1-Keff 100,000 C. DEPLETE the previous BEACON Model for each "Desired K" in Appendix B Table 1 using a "Criticality Search" of "Rods" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months AND RECORD the Control Bank positions in Appendix B Table 1. WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 PaJJ_e 34 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE A facsimile of Appendix B Table 1 may be completed and attached to the data package in place of Appendix B Table 1. [8] PERFORM the following to obtain the bank positions associated with the conditions listed in Appendix B Table 1 with the reactor critical (ICRR = 0): A. RECORD the reference effective multiplication factor, Kel ef , for each condition in Table 1 from the "K eff' value recorded in earlier steps as specified.
B. CALCULATE AND RECORD the effective multiplication factor, Desired K, for each condition in Table 1 using the applicable values from Table 1 according to the following equation:
Desired K = K Ref eff 1 _ K Ref. ( Limit ) eff 100000 , C. DEPLETE the previous BEACON Model for each "Desired K" in Appendix B Table 1 using a "Criticality Search" of "Rods" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months AND RECORD the Control Bank positions in Appendix B Table 1.
\ WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 35 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE If it is not desired to predict the ICRR plots for the ECC or the various administrative limits, then Step 6.6[9] through 6.6[11] may be marked N/A. NOTE A facsimile of Appendix B Table 2 may be completed and attached to the data package in place of Appendix B Table 2. [9] PERFORM the following to obtain the bank positions associated with the conditions listed in Appendix B Table 2 with the ICRR at the 8-Fold point (ICRR = 0.125): A. RECORD the reference effective multiplication factor, Kel ef , for each condition in Table 2 from the "K eff' value recorded in earlier steps as specified.
B. CALCULATE and RECORD the effective multiplication factor, Desired K, for each condition in Table 2 using the "K eff' value from Step 6.6[5]B as Kel BI and the applicable values from Table 2 according to the following equation:
Desired K = Keff CEI + Jig
K Ref eff (Limit) Ref. 1-Keff 100,000 -K CEI eff C. DEPLETE the previous BEACON Model for each "Desired K" in Appendix B Table 2 using a "Criticality Search" of "Rods" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months and RECORD the Control Bank positions in Appendix B Table 2. WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 35 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE If it is not desired to predict the ICRR plots for the ECC or the various administrative limits, then Step 6.6[9] through 6.6[11] may be marked N/A. NOTE A facsimile of Appendix B Table 2 may be completed and attached to the data package in place of Appendix B Table 2. [9] PERFORM the following to obtain the bank positions associated with the conditions listed in Appendix B Table 2 with the ICRR at the 8-Fold point (ICRR = 0.125): A. RECORD the reference effective multiplication factor, Kel ef , for each condition in Table 2 from the "K eff' value recorded in earlier steps as specified.
B. CALCULATE and RECORD the effective multiplication factor, Desired K, for each condition in Table 2 using the "K eff' value from Step 6.6[5]B as KetP B1 and the applicable values from Table 2 according to the following equation: . eBI 7/ DesIred K = Keff + /S
K Ref eff 1 _ K Ref. ( Limit ) eff 100000 , -K eBI eff C. DEPLETE the previous BEACON Model for each "Desired K" in Appendix B Table 2 using a "Criticality Search" of "Rods" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months and RECORD the Control Bank positions in Appendix B Table 2.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 36 of 69 Data Package: Page __ of __ Date __ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE A facsimile of Appendix B Table 3 may be completed and attached to the data package in place of Appendix B Table 3. [10] PERFORM the following to obtain the bank positions associated with the conditions listed in Appendix B Table 3 with the ICRR at the 4-Fold point (ICRR = 0.25): A. RECORD the reference effective multiplication factor, Kel ef , for each condition in Table 3 from the "K eff' value recorded in earlier steps as specified.
B. CALCULATE and RECORD the effective multiplication factor, Desired K, for each condition in Table 3 using the "K eff' value from Step 6.6[5]B as Kei B' and the applicable values from Table 3 according to the following equation:
Desired K = Keff CBI + X
K Ref eff (Limit) Ref. 1 -Keff 100,000 -K CBI eff C. DEPLETE the previous BEACON Model for each "Desired K" in Appendix B Table 3 using a "Criticality Search" of "Rods" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months AND RECORD the Control Bank positions in Appendix B Table 3. ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 36 of 69 Data Package: Page __ of __ Date ___ _ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE A facsimile of Appendix B Table 3 may be completed and attached to the data package in place of Appendix B Table 3. [10] PERFORM the following to obtain the bank positions associated with the conditions listed in Appendix B Table 3 with the ICRR at the 4-Fold point (ICRR = 0.25): A. RECORD the reference effective multiplication factor, Kel ef , for each condition in Table 3 from the "K eff" value recorded in earlier steps as specified.
B. CALCULATE and RECORD the effective multiplication factor, Desired K, for each condition in Table 3 using the "K eff" value from Step 6.6[5]B as Keff CB1 and the applicable values from Table 3 according to the following equation:
CBI 3/ DesIred K = Keff + /4* K Ref eff 1 _ K Ref. [ Limit ) eff 100000 , -K CBI eff C. DEPLETE the previous BEACON Model for each "Desired K" in Appendix B Table 3 using a "Criticality Search" of "Rods" and a "Time Step" depletion of 0 hours0 days 0 hours 0 weeks 0 months AND RECORD the Control Bank positions in Appendix B Table 3.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 37 of 69 Data Package: Page __ of __ 6.6 ECP Calculation using BEACON General 3D Calc (continued)
[11] PLOT the projected ICRRs (i.e. 0.0, 0.125, and 0.25) for each condition specified in the tables of Appendix B as a function of the recorded rod positions.
[12] RECORD the following information:
A. Expected Date & Time of Criticality:
I I at -----B. Expected Critical Rod Position on Bank 0 (Step 6.6[3]B):
___ steps C. Expected Critical C b (Step 6.6[4]): ppm O. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank 0 (from NOB Sheet A-5, if applicable):
___ steps NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. [13] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limits, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limits. [14] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acc Crit). [15] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.6[12]0 (Acc Crit). [16] RECORD the following:
A. Date of calculation:
I I B. Time of calculation:

Date ___ _ WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 37 of 69 Data Package: Page __ of __ 6.6 ECP Calculation using BEACON General 3D Calc (continued)

[11] PLOT the projected ICRRs (i.e. 0.0, 0.125, and 0.25) for each condition specified in the tables of Appendix B as a function of the recorded rod positions.
[12] RECORD the following information:
A. Expected Date & Time of Criticality: / / at -----B. Expected Critical Rod Position on Bank 0 (Step 6.6[3]B):
___ steps C. Expected Critical C b (Step 6.6[4]): ppm O. Negative Moderator Temperature Coefficient Withdrawal Limit on Bank 0 (from NOB Sheet A-5, if applicable):
___ steps NOTE "-The 1000 pcm lower limit may be used for Mode 2 entry call. [13] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limits, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limits. [14] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acc Crit). [15] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.6[12]0 (Acc Crit). [16] RECORD the following:
A. Date of calculation: / / ---B. Time of calculation:
___ _ Date __ _
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 38 of 69 Data Package: Page __ of __ Date ----6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[17] OBTAI N review of calculations and results by task qualified individual.
[18] OBTAIN SM/US review and approval of ECP. SM/US WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 38 of 69 Data Package: Page __ of __ Date ----6.6 ECP Calculation using BEACON General 3D Calc (continued)
NOTE A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.
[17] OBTAIN review of calculations and results by task qualified individual.
[18] OBTAIN SM/US review and approval of ECP. SM/US 6.7 WBN Estimated Critical Position Unit 1 Data Package: Page __ of __ ECP Calculation using BEACON ECC NOTE 1-SI-0-11 Rev. 0014 Page 39 of 69 Date ___ _ Familiarization with BEACON User's Guides will enable proper use of BEACON. [1] PERFORM the following to obtain the Reference Statepoint:
[1.1] START BEACON for the current unit and cycle. NOTE The input model shall mimic the core conditions for the last 120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months of operating history and shall be properly calibrated to a flux map per TI-7.020 and have a calibrated K bias per TI-7.020.
The "current model is preferred, although it may be manually depleted to a convenient reference time. The "trip" model may be used, but must be validated prior to use. [1.2] IF the "trip" model file is being considered for the ECC model input file, THEN VALIDATE by performing the following:
otherwise proceed to Step 6.7[1.3] A. SELECT BEACON Monitor> Function>
Cycle History Oata. B. SELECT "Table" as the "Data Display Format" from the "Plant History Data Selection" pop-up window. C. SELECT a "Time Interval" that includes the reactor shutdown.
D. SELECT "Calendar Time" from the "Exposure" tab. E. SELECT "AO Rod Value" from the "Table Only" tab. F. SELECT any other parameter(s) useful in identifying the reactor shutdown.
\ , 6.7 WBN Estimated Critical Position Unit 1 Data Package: Page __ of __ ECP Calculation using BEACON ECC NOTE 1-SI-0-11 Rev. 0014 Page 39 of 69 Date ___ _ Familiarization with BEACON User's Guides will enable proper use of BEACON. [1] PERFORM the following to obtain the Reference Statepoint:
[1.1] START BEACON for the current unit and cycle. NOTE The input model shall mimic the core conditions for the last 120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months of operating history and shall be properly calibrated to a flux map per TI-7.020 and have a calibrated K bias per TI-7.020.
The "current' model is preferred, although it may be manually depleted to a convenient reference time. The "trip" model may be used, but must be validated prior to use. [1.2] IF the "trip" model file is being considered for the ECC model input file, THEN VALIDATE by performing the following:
otherwise proceed to Step 6.7[1.3] A. SELECT BEACON Monitor> Function>
Cycle History Data. B. SELECT "Table" as the "Data Display Format" from the "Plant History Data Selection" pop-up window. C. SELECT a "Time Interval" that includes the reactor shutdown.
D. SELECT "Calendar Time" from the "Exposure" tab. E. SELECT "AO Rod Value" from the "Table Only" tab. F. SELECT any other parameter(s) useful in identifying the reactor shutdown.
6.7 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 40 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
G. SELECT the "Display" button. H. REVIEW the "AO Rod Values" subsequent to the reactor shutdown from the "History Data" pop-up window. I. IF the value remains stable at approximately the value that existed prior to the reactor shutdown, AND its absolute value remains less than 0.001, THEN CONCLUDE the "trip" model is acceptable AND CONTINUE with Step 6.7[1.3].
J. IF further evaluation of the "trip" model file is necessary, THEN PERFORM the following.
OTHERWISE CONTINUE with Step 6.7[1.3].
K. SELECT BEACON Analysis>
Function>
General 3D Calc. L. SELECT the "trip" "Model Input File". M. DEPLETE the model to a convenient time. N. OPEN the "Model Output File" generated in Step 6.7[1.2]M using Personal Files (blue barn) from Iwbn 11beaconlwbr1 c#loutput directory.
O. IF the value for "Axial Offset Corrector" on the COR Core Summary -Predicted" edit of the output file is approximately equal to the "AO Rod Value" prior to the reactor shutdown, AND its absolute value is less than 0.001, THEN CONCLUDE the "trip" model is acceptable.
[1.3] OBTAIN a calibrated BEACON model for a desired reference time. Date ___ _ ) 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 40 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
G. SELECT the "Display" button. H. REVIEW the "AO Rod Values" subsequent to the reactor shutdown from the "History Data" pop-up window. I. IF the value remains stable at approximately the value that existed prior to the reactor shutdown, AND its absolute value remains less than 0.001, THEN CONCLUDE the "trip" model is acceptable AND CONTINUE with Step 6.7[1.3].
J. IF further evaluation of the "trip" model file is necessary, THEN PERFORM the following.
OTHERWISE CONTINUE with Step 6.7[1.3].
K. SELECT BEACON Analysis>
Function>
General 3D Calc. L. SELECT the "trip" "Model Input File". M. DEPLETE the model to a convenient time. N. OPEN the "Model Output File" generated in Step 6.7[1.2]M using Personal Files (blue barn) from /wbn 1 /beacon/wbr1 c#/output directory.
O. IF the value for "Axial Offset Corrector" on the COR Core Summary -Predicted" edit of the output file is approximately equal to the "AO Rod Value" prior to the reactor shutdown, AND its absolute value is less than 0.001, THEN CONCLUDE the "trip" model is acceptable.
[1.3] OBTAIN a calibrated BEACON model for a desired reference time. Date ___ _
6.7 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 41 of 69 Data Package: Page __ of __ Date ___ _ ECP Calculation using BEACON ECC (continued)
[1.4] RECORD the following information:
Model: Reference Time ----__ 1 __ 1_-Power: rei (actual) Burnup: MWO/MTU (actual) K eff: ( calculated)
Boron: ppm (actual) D Bank: steps (actual) [2] PERFORM the following to initiate the ECC calculations:
[2.1] SELECT BEAGON Analysis>
Function>
EGG. [2.2] SELECT the desired "Model Input File" from 6.7[1.3] [2.3] ENTER the desired "Summary Results File". [2.4] ENSURE the appropriate "Calibration File". [2.5] RECORD what was entered: Model Input File: Summary Results File: 1------------1 Calibration File: .
[2.6] SELECT the desired "Calculation Type" on the "Calc Options" tab. [2.7] SELECT the desired "Time Frame" on the "Calc Options" tab. 6.7 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 41 of 69 Data Package: Page __ of __ Date __ _ ECP Calculation using BEACON ECC (continued)
[1.4] RECORD the following information:
Model: Reference Time ------__ 1 __ 1---Power: rei (actual) Burnup: MWD/MTU (actual) K eft: (calculated)
Boron: ppm (actual) D Bank: steps (actual) [2] PERFORM the following to initiate the ECC calculations:
[2.1] SELECT BEAGON Analysis>
Function>
EGG. [2.2] SELECT the desired "Model Input File" from 6.7[1.3] [2.3] ENTER the desired "Summary Results File". [2.4] ENSURE the appropriate "Calibration File". [2.5] RECORD what was entered: Model Input File:
Summary Results File:
Calibration File: [2.6] SELECT the desired "Calculation Type" on the "Calc Options" tab. [2.7] SELECT the desired "Time Frame" on the "Calc Options" tab.
) 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 42 of 69 Data Package: Page __ of __ Date ___ _ ECP Calculation using BEACON ECC (continued)
[2.8] RECORD what was selected:
Calculation Type Time Frame: D Boron vs. Time D 0-16 Hours D Rods VS. Time D 12-36 Hours D Boron VS. Rods D 1-4 Days D 3-31 Days D User Defined Start Time: I I hr Time Step: hr Number of Steps: 1-1 ______ -----' [2.9] IF the reactor startup will be performed via a critical", THEN SELECT the "Acceptance Band Search" of "Rods" on the "Band Options" tab. [2.10] IF the reactor startup will be performed via a critical", THEN SELECT the "Acceptance Band Search" of "Boron" on the "Band Options" tab. NOTE The BEACON ECC will need to be performed 3 times; once each for the 2:. 500 pcm, 2:. 750 pcm, and 2:. 1000 pcm bands. [2.11] ENTER the appropriate "Acceptance Band Bias" on the "Band Options" tab. ) 6.7 WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 42 of 69 Data Package: Page __ of __ Date ECP Calculation using BEACON ECC (continued)
[2.8] RECORD what was selected:
Calculation Type Time Frame: 0 Boron vs. Time 0 0-16 Hours 0 Rods vs. Time 0 12-36 Hours 0 Boron vs. Rods 0 1-4 Days 0 3-31 Days 0 User Defined Start Time: hr f------------1 Time Step: hr Number of Steps: '------------'
[2.9] IF the reactor startup will be performed via a critical", THEN SELECT the "Acceptance Band Search" of "Rods" on the "Band Options" tab. [2.10] IF the reactor startup will be performed via a critical", THEN SELECT the "Acceptance Band Search" of "Boron" on the "Band Options" tab. NOTE ----The BEACON ECC will need to be performed 3 times; once each for the 2:. 500 pcm, 2:. 750 pcm, and 2:. 1000 pcm bands. [2.11] ENTER the appropriate "Acceptance Band Bias" on the "Band Options" tab.
) 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 43 of69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
[2.12] RECORD what was selected:
Acceptance Band Search: I D Rods D Boron [2.13] VERIFY the "Model Type" of "3D" is selected on the "Model Geometry" tab. [2.14] SELECT the appropriate "Radial Geometry" on the "Model Geometry" tab. NOTE Date ___ _ The Ala Correction (AOROD) adjustment performed by the BEACON Monitor function is specifically designed to adjust the ANC-based prediction of the core axial power distribution to account for true core conditions, such as Crud Induced Power Shift (CIPS), as determined during the last calibration.
The impact of this adjustment can be selectively removed. The removal of this correction may effectively simulate the behavior of the CIPS mechanism following a reactor trip. IF CIPS adjustments are desired, THEN the Ala Correction should be de-selected.
[2.15] IF CIPS effects are to be modeled for this ECC, THEN DE-SELECT the "A/O Correction" of the "Model Geometry" tab. [2.16] RECORD what was selected:
Model Type: Radial Geometry:
I D Full Core D Quarter/Eighth Core [D Use Ala Correction 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 43 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
[2.12] RECORD what was selected:
Acceptance Band Search: D Rods D Boron [2.13] VERIFY the "Model Type" of "3D" is selected on the "Model Geometry" tab. [2.14] SELECT the appropriate "Radial Geometry" on the "Model Geometry" tab. NOTE Date ___ _ The Ala Correction (AOROD) adjustment performed by the BEACON Monitor function is specifically designed to adjust the ANC-based prediction of the core axial power distribution to account for true core conditions, such as Crud Induced Power Shift (CIPS), as determined during the last calibration.
The impact of this adjustment can be selectively removed. The removal of this correction may effectively simulate the behavior of the CIPS mechanism following a reactor trip. IF CIPS adjustments are desired, THEN the Ala Correction should be de-selected.
[2.15] IF CIPS effects are to be modeled for this ECC, THEN DE-SELECT the "A/O Correction" of the "Model Geometry" tab. [2.16] RECORD what was selected:
Model Type: Radial Geometry:
D Full Core D Quarter/Eighth Core I D Use Ala Correction 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 44 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
[2.17] VERIFY the "Use Depleted B-10" box is not selected on the "Core Conditions" tab. NOTE Date ___ _ If a "Rods" search will be performed in the following step AND if adjustments to the ECC will be made to account for B-1 0 concentration changes, then the expected boron concentration at startup used as input into BEACON should subtract the value for L1C b 8-10 recorded in Step 4.1 [5]. The L1C b 8-10 value will be added back in later. [2.18] IF "Rods vs, Time" was selected as the "Calculation Type" in Step 6.7[2.6], THEN ENTER the desired "Nominal Boron" on the "Core Conditions" tab. [2.19] VERIFY the desired K-bias value on the "Core Conditions" tab corresponds to the current K-bias from the applied model calibration.
[2.20] RECORD what was entered: Nominal Boron: C==:J ppm (N/A if Boron vs. Time) Desired K-bias: C==:J ) 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 44 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
[2.17] VERIFY the "Use Depleted B-10" box is not selected on the "Core Conditions" tab. NOTE Date ___ _ If a "Rods" search will be performed in the following step AND if adjustments to the ECC will be made to account for B-10 concentration changes, then the expected boron concentration at startup used as input into BEACON should subtract the value for .6.Cb B-10 recorded in Step 4.1 [5]. The .6.Cb B-10 value will be added back in later. [2.18] IF "Rods vs, Time" was selected as the "Calculation Type" in Step 6.7[2.6], THEN ENTER the desired "Nominal Boron" on the "Core Conditions" tab. [2.19] VERIFY the desired K-bias value on the "Core Conditions" tab corresponds to the current K-bias from the applied model calibration.
[2.20] RECORD what was entered: Nominal Boron: c=J ppm (N/A if Boron vs. Time) Desired K-bias: c=J
) WBN Estimated Critical Position 1-81-0-11 Unit 1 Rev. 0014 Page 45 of 69 Data Package: Page __ of __ Date ___ _ 6.7 ECP Calculation using BEACON ECC (continued)
NOTE The "Use Rod Overlap" box may need to be de-selected if the Full Out Position for the quarter does not correspond to the nominal Full Out Position assumed in the cycle design. [2.21] IF "Boron vs. Time" was selected as the "Calculation Type" in Step 6.7[2.6], THEN ENTER the desired rod positions on the "Rod Positions" tab AND RECORD what was entered: D Bank: steps C Bank: steps B Bank: steps Full Out Position:
steps [2.22] SELECT the "Calculate" button at the bottom of the "BEACON Analysis-ECC" window. [2.23] WHEN the calculation is complete, THEN SELECT the "OK" button on the "BEACON Calculation Messages" pop-up window AND SELECT the "Review" button at the bottom of the "BEACON Analysis-ECC" window. [2.24] OBTAIN a copy of the output. [3] PERFORM the following to complete the ECC calculations:
[3.1] RECORD the following values in Appendix C Table 1 for each desired time step from the output obtained in Step 6.7[2.24]:
Time since Input Model
D Bank Position
RCS Boron Concentration (Cb) WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 45 of 69 Data Package: Page __ of __ Date ___ _ 6.7 ECP Calculation using BEACON ECC (continued)
NOTE The "Use Rod Overlap" box may need to be de-selected if the Full Out Position for the quarter does not correspond to the nominal Full Out Position assumed in the cycle design. [2.21] IF "Boron vs. Time" was selected as the "Calculation Type" in Step 6.7[2.6], THEN ENTER the desired rod positions on the "Rod Positions" tab AND RECORD what was entered: o Bank: steps f-------j C Bank: steps B Bank: steps Full Out Position:
steps [2.22] SELECT the "Calculate" button at the bottom of the "BEACON Analysis-ECC" window. [2.23] WHEN the calculation is complete, THEN SELECT the "OK" button on the "BEACON Calculation Messages" pop-up window AND SELECT the "Review" button at the bottom of the "BEACON Analysis-ECC" window. [2.24] OBTAIN a copy of the output. [3] PERFORM the following to complete the ECC calculations:
[3.1] RECORD the following values in Appendix C Table 1 for each desired time step from the output obtained in Step 6.7[2.24]:
Time since Input Model
0 Bank Position
RCS Boron Concentration (C b)
) ) ) 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 46 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
[3.2] RECORD the dCb 8-10 value from Step 4.1 [5] into Appendix C Table 1 for each time step. [3.3] ADJUST the ECC boron concentration for B-10 concentration change effects by adding the dCb 8-10 values to the RCS Boron Concentration (Cb) for each time step in Appendix C Table 1. [3.4] RECORD the Calendar Date and Time in Appendix C Table 1 for each time step. [4] RECORD the following information for the ECC Time step to be used for the Reactor Startup from Appendix C Table 1:
Expected Date & Time of Criticality:
I I at -----* Expected Critical Rod Position on Bank D: steps
Expected Critical Cb: ppm [5] RECORD the Negative Moderator Temperature Coefficient Withdrawal Limit on Bank D (from NOB Sheet A-5, if applicable):
steps NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. [6] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limits, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limits. [7] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). [8] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.7[5] (Acceptance Criteria 5.1 B). Date __ _ 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 46 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
[3.2] RECORD the 8-10 value from Step 4.1 [5] into Appendix C Table 1 for each time step. [3.3] ADJUST the ECC boron concentration for B-10 concentration change effects by adding the 8-10 values to the RCS Boron Concentration (Cb) for each time step in Appendix C Table 1. [3.4] RECORD the Calendar Date and Time in Appendix C Table 1 for each time step. [4] RECORD the following information for the ECC Time step to be used for the Reactor Startup from Appendix C Table 1:
Expected Date & Time of Criticality: / / at -----* Expected Critical Rod Position on Bank D: steps
Expected Critical C b: ppm [5] RECORD the Negative Moderator Temperature Coefficient Withdrawal Limit on Bank D (from NOB Sheet A-5, if applicable):
steps NOTE The 1000 pcm lower limit may be used for Mode 2 entry call. [6] IF the 1000 pcm lower limit is less than the COLR Rod Insertion Limits, THEN RE-PERFORM ECP for different conditions until the 1000 pcm lower limit is above the COLR Rod Insertion Limits. [7] VERIFY ECP is above the Control Bank Insertion Limits in the COLR (Acceptance Criteria 5.1A). [8] IF applicable, THEN VERIFY ECP is below the Negative MTC Withdrawal Limit from Step 6.7[5] (Acceptance Criteria 5.1 B). Date ___ _
) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 47 of 69 i Data Package: Page __ of __ Date __ _ 6.7 ECP Calculation using BEACON ECC (continued)
[9] RECORD the UPPER and LOWER Acceptance Bands from the output obtained in Step 6.7[2.24]
for the ECC Time step to be used for the Reactor Startup: A. Upper 1000 pcm Limit Bank Cat steps & Bank D at steps B. Lower 1000 pcm Limit Bank Cat steps & Bank D at steps C. Upper 750 pcm Limit Bank C at steps & Bank D at steps D. Lower 750 pcm Limit Bank Cat steps & Bank D at steps E. Upper 500 pcm Threshold Bank C at steps & Bank D at steps F. Lower 500 pcm Threshold Bank C at steps & Bank D at steps [10] RECORD the following:
A. Date of calculation: I I ---B. Time of calculation:

NOTE A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.

[11] OBTAIN review of calculations and results by task qualified individual.
[12] OBTAIN SM/US review and approval of the ECP. SM/US 6.7 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 47 of 69 Data Package: Page __ of __ ECP Calculation using BEACON ECC (continued)
[9] RECORD the UPPER and LOWER Acceptance Bands from the output obtained in Step 6.7[2.24]
for the ECC Time step to be used for the Reactor Startup: A. Upper 1000 pcm Limit Bank C at steps & Bank D at steps B. Lower 1000 pcm Limit Bank C at steps & Bank D at steps C. Upper 750 pcm Limit Bank C at steps & Bank D at steps D. Lower 750 pcm Limit Bank C at steps & Bank D at steps E. Upper 500 pcm Threshold Bank C at steps & Bank D at steps F. Lower 500 pcm Threshold Bank C at steps & Bank D at steps [10] RECORD the following:
A. Date of calculation: / / ---B. Time of calculation:

NOTE Date ___ _ A review of the ECP during the performance of this instruction should be performed prior to performing any associated reactivity manipulations.

[11] OBTAIN review of calculations and results by task qualified individual.
[12] OBTAIN SM/US review and approval of the ECP. SM/US WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 48 of 69 Data Package: Page __ of __ 6.8 Detector Reliability and/or Base Count Rate Determination NOTE Section 6.8 must be performed prior to initiating ICRR monitoring.
[1 ] [2] [3] [4] RECORD N-131 Count Rate (CR) cps MULTIPLY Step 6.8[1] by 10(1/2) cps MULTIPLY Step 6.8[1 ] by 10(-1/2) cps RECORD N-132 Count Rate (CR) cps [5] VERIFY STEP 6.8[4] falls within the range or equal to Steps 6.8[2] and 6.8[3] (Other Acceptance Criteria 5.2C). [6] IF channel count rates are NOT within +/- decade, THEN NOTIFY SM/SRO. [7] RECORD the Base Count Rate information for channel(s) of interest on Appendix A, as appropriate.
[8] CHECK source range detector Audio Count Rate circuit CHANNEL SELECTOR switch is set to desired position (N-31 or N-32), is operating, and emitting a detectable tone.3 [9] CHECK Startup Rate (SUR) Meters on 1-M-13 selected to a Source Range Detector.
[10] IF switch positions needs changing, as determined by the Test Director, THEN REQUEST Operations to select appropriate positions for Step 6.8[8] and 6.8[9] above. Date ___ _ \ ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 P,!ge 48 of 69 Data Package: Page __ of __ 6.8 Detector Reliability and/or Base Count Rate Determination NOTE Section 6.8 must be performed prior to initiating ICRR monitoring.
[1 ] [2] [3] [4] [5] [6] [7] [8] [9] [10] RECORD N-131 Count Rate (CR) cps MULTIPLY Step 6.8[1] by 10(1/2) cps MUL TIPL Y Step 6.8[1] by 10(-1/2) cps RECORD N-132 Count Rate (CR) cps VERIFY STEP 6.8[4] falls within the range or equal to Steps 6.8[2] and 6.8[3] (Other Acceptance Criteria 5.2C). IF channel count rates are NOT within +/- decade, THEN NOTIFY SM/SRO. RECORD the Base Count Rate information for channel(s) of interest on Appendix A, as appropriate.
CHECK source range detector Audio Count Rate circuit CHANNEL SELECTOR switch is set to desired position (N-31 or N-32), is operating, and emitting a detectable tone.3 CHECK Startup Rate (SUR) Meters on 1-M-13 selected to a Source Range Detector.
IF switch positions needs changing, as determined by the Test Director, THEN REQUEST Operations to select appropriate positions for Step 6.8[8] and 6.8[9] above. Date __ _
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 49 j>1§9 Data Package: Page __ of __ 6.8 Detector Reliability and/or Base Count Rate Determination (continued)
CAUTION Date ___ _ Placing Shutdown Monitor to 11M mode will disable Shutdown Monitoring and bring in the High Flux at Shutdown alarm; therefore, this step should be performed after High Flux At Shutdown is BLOCKED. [11] IF High Flux At Shutdown has been BLOCKED and it is desired to place the Source Range Shutdown Monitoring Panels to 11M mode, THEN REQUEST Unit SRO to place the Source Range Shutdown Monitoring Panels to 11M mode by PRESSING the button marked 11M. ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 49 of 69 Data Package: Page __ of __ 6.8 Detector Reliability and/or Base Count Rate Determination (continued)
CAUTION Date ___ _ Placing Shutdown Monitor to 11M mode will disable Shutdown Monitoring and bring in the High Flux at Shutdown alarm; therefore, this step should be performed after High Flux At Shutdown is BLOCKED. [11] IF High Flux At Shutdown has been BLOCKED and it is desired to place the Source Range Shutdown Monitoring Panels to 11M mode, THEN REQUEST Unit SRO to place the Source Range Shutdown Monitoring Panels to 11M mode by PRESSING the button marked 11M.
) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 50 of 69 Data Package: Page __ of __ Date __ _ 6.9 ICRR Monitoring NOTES 1) Section 6.8 must be performed prior to initiating ICRR monitoring to collect base count rate data and to set the Shutdown Monitor to the 11M mode. 2) The Test Director will have determined which detector or detectors are to be used for ICRR monitoring based on the evolution.
[1] VERIFY the estimated critical control bank position is within the limits specified in the COLR: ABOVE the Control Bank Insertion Limits (Acceptance Criteria 5.1.A) Yes o BELOW the Negative MTC Withdraw Limit in NOB 0 Sheet A-5 (Acceptance Criteria 5.1.B, if applicable)
AND RECORD the date and time: I I -----[2] DETERMINE, based on the evolution being performed, the method to be used for determining ICRR (11M) information and prepare the appropriate data sheets from Appendix A. [3] DETERMINE which ICRR Plot(s) are to be made, data collection frequency I time duration for the ICRR monitoring based on the evolution being performed.
[4] ENSURE information at the top of appropriate ICRR Monitoring Sheets (Appendix A) is filled in. No o o N/A o WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 50 of 69 Data Package: Page __ of __ Date ----6.9 ICRR Monitoring NOTES 1) Section 6.8 must be performed prior to initiating ICRR monitoring to collect base count rate data and to set the Shutdown Monitor to the 11M mode. 2) The Test Director will have determined which detector or detectors are to be used for ICRR monitoring based on the evolution.
[1] VERIFY the estimated critical control bank position is within the limits specified in the COLR: ABOVE the Control Bank Insertion Limits (Acceptance Criteria 5.1.A) Yes D BELOW the Negative MTC Withdraw Limit in NOB D Sheet A-5 (Acceptance Criteria 5.1.B, if applicable)
AND RECORD the date and time: I I -----[2] DETERMINE, based on the evolution being performed, the method to be used for determining ICRR (11M) information and prepare the appropriate data sheets from Appendix A. [3] DETERMINE which ICRR Plot(s) are to be made, data collection frequency I time duration for the ICRR monitoring based on the evolution being performed.
[4] ENSURE information at the top of appropriate ICRR Monitoring Sheets (Appendix A) is filled in. No D D N/A D
) ') 6.9 WBN Estimated Critical Position Unit 1

Data Package: Page __ of __ ICRR Monitoring (continued)
NOTE 1-SI-0-11 Rev. 0014 -J>>Cige 51_Qf 69 Date __ _ Data and place keeping for Steps 6.9[5] through 6.9[10] are recorded on Appendix A. [5] IF desired and time permits and not already performed, THEN CALCULATE the desired ICRR values that would be expected if criticality were to occur at the Acceptance and Review Criteria limits per Step 6.6 and ANNOTATE the ICRR plots accordingly. . NOTES 1) The following steps are GENERIC for alllCRR monitoring and will be repeated numerous times. 2) When the ScalarlTimer is used, the count period may be adjusted at the discretion of the Test Director (minimum of 10 seconds and at least 1 000 T period). 3) Following incremental additions of reactivity, a pause of 1 to 4 minutes should occur prior to ICRR data collection to allow subcritical multiplication to increase thermal neutron flux to approx. its equilibrium value. As criticality is approached (i.e., keff approaches 1.0), neutron flux stabilization time should become longer prior to data collection.
This approach permits a more accurate determination to be made of core reactivity changes, and predicted critical condition.
[6]. OBTAIN and RECORD, at the data collection frequency determined by the Test Director, count, count rate or 11M data for applicable detector(s).
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 51 of 69 Data Package: Page __ of __ Date ___ _ 6.9 ICRR Monitoring (continued)
NOTE Data and place keeping for Steps 6.9[5] through 6.9[10] are recorded on Appendix A. [5] IF desired and time permits and not already performed, THEN CALCULATE the desired ICRR values that would be expected if criticality were to occur at the Acceptance and Review Criteria limits per Step 6.6 and ANNOTATE the ICRR plots accordingly.
NOTES 1) The following steps are GENERIC for alllCRR monitoring and will be repeated numerous times. 2) When the ScalarlTimer is used, the count period may be adjusted at the discretion of the Test Director (minimum of 10 seconds and at least 1 000 T period). 3) Following incremental additions of reactivity, a pause of 1 to 4 minutes should occur prior to ICRR data collection to allow subcritical multiplication to increase thermal neutron flux to approx. its equilibrium value. As criticality is approached (i.e., keff approaches 1.0), neutron flux stabilization time should become longer prior to data collection.
This approach permits a more accurate determination to be made of core reactivity changes, and predicted critical condition.
[6] OBTAIN and RECORD, at the data collection frequency determined by the Test Director, count, count rate or 11M data for applicable detector(s).
) ) WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 52 of 69 Data Package: Page __ of __ " Date __ _ 6.9 ICRR Monitoring (continued)
[7] COMPUTE and RECORD the ICRR for applicable detector(s):
Base Count Rate (Co) ICRR = = Count Rate (C i) NOTES 1) The Test Director will determine which ICRR plots are required based on the evolution.
2) It is NOT required to use the figures provided in Appendix A for plotting ICRR data. Larger graph paper or a computer can be used at the discretion of the Test Director.
[8] PLOT the resultant ICRR for applicable detector(s) as a function of the parameter specified by the Test Director.
Examples:
A. ICRR vs Control Bank Position.
B. ICRR vs Time. C. ICRR vs Gallons of Primary Water Added. D. ICRR vs RCS Boron Concentration.
[9] DETERMINE the predicted critical condition by straight line extrapolation of the two most recent ICRR data points on the graph to an ICRR value of zero at the axis, AND REVIEW the plotted ICRR data with the Unit Supervisor for trends which indicate reactivity abnormalities AND for criticality predictions within the next withdrawal sequence.
[10] IF ICRR performance is for OTHER than approach to criticality, AND criticality is predicted before the next ICRR, THEN 4 A. STOP positive reactivity additions, AND B. NOTIFY the SRO, AND C. CONTINUE to monitor ICRR verses time, AND D. EVALUATE to determine the cause before proceeding.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 52 of 69 Data Package: Page __ of __ . Date ____ _ 6.9 ICRR Monitoring (continued)
[7] COMPUTE and RECORD the ICRR for applicable detector(s):
Base Count Rate (Co) --------------
= ICRR = Count Rate (C i) NOTES 1) The Test Director will determine which ICRR plots are required based on the evolution.
2) It is NOT required to use the figures provided in Appendix A for plotting ICRR data. Larger graph paper or a computer can be used at the discretion of the Test Director.
[8] PLOT the resultant ICRR for applicable detector(s) as a function of the parameter specified by the Test Director.
Examples:
A. ICRR vs Control Bank Position.
B. ICRR vs Time. C. ICRR vs Gallons of Primary Water Added. D. ICRR vs RCS Boron Concentration.
[9] DETERMINE the predicted critical condition by straight line extrapolation of the two most recent ICRR data points on the graph to an ICRR value of zero at the axis, AND REVIEW the plotted ICRR data with the Unit Supervisor for trends which indicate reactivity abnormalities AND for criticality predictions within the next withdrawal sequence.
[10] IF ICRR performance is for OTHER than approach to criticality, AND criticality is predicted before the next ICRR, THEN 4 A. STOP positive reactivity additions, AND B. NOTIFY the SRO, AND C. CONTINUE to monitor ICRR verses time, AND D. EVALUATE to determine the cause before proceeding.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 53 of 69 Data Package: Page __ of __ Date ___ _ 6.9 ICRR Monitoring (continued)
NOTES 1) IF criticality is predicted close to the next planned hold point OR IF the control rods are passing through a region of especially high worth, THEN The recommendation of a sooner hold point should be considered.
2) The reactor startup should NOT be aborted until the ICRR becomes less than 0.2. If the ICRR data is NOT behaving as expected, additional hold points should be used to confirm criticality will be achieved within the 750 pcm Review Criteria.
[11] IF criticality is predicted before the next ICRR, THEN 4 A. EVALUATE the ECP for:
Time of calculation
+/-500 pcm Review Criteria * +/-750 pcm Other Acceptance Criteria * +/-1000 pcm Acceptance Criteria B. IF advisable, THEN RECOMMEND to the SRO continued startup. [12] CONTINUE monitoring ICRR data by repeating Steps 6.9[6] through 6.9[12] until directed by the Test Director to stop. 1 WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 53 of 69 Data Package: Page __ of __ Date ___ _ 6.9 ICRR Monitoring (continued)
NOTES 1) IF criticality is predicted close to the next planned hold point OR IF the control rods are passing through a region of especially high worth, THEN The recommendation of a sooner hold point should be considered.
2) The reactor startup should NOT be aborted until the ICRR becomes less than 0.2. If the ICRR data is NOT behaving as expected, additional hold points should be used to confirm criticality will be achieved within the 750 pcm Review Criteria.
[11] IF criticality is predicted before the next ICRR, THEN 4 A. EVALUATE the ECP for:
Time of calculation
+/-500 pcm Review Criteria * +/-750 pcm Other Acceptance Criteria * +/-1000 pcm Acceptance Criteria B. IF advisable, THEN RECOMMEND to the SRO continued startup. [12] CONTINUE monitoring ICRR data by repeating Steps 6.9[6] through 6.9[12] until directed by the Test Director to stop.
) WBN Estimated Critical Position Unit 1 Data Package: Page __ of __ 6.10 Critical Data Evaluation
[1] RECORD the following critical data, AND EVALUATE against the ECp.4 1-51-0-11 Rev. 0014 Page 54 of 69 A. Date and time for ECP: _1_1 ___ . __ B. Date and time of criticality:
_1_1 ___ : __ C. Core average temperature:
of. D. Control bank position:
steps. E. C b: ppm. [2] VERIFY the elapsed time from Step 6.9[1] to Step 6.10[1]B was less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . [3] VERIFY ECP was within 1000 pcm of actual criticality (Other Acceptance Criteria 5.2A). [4] VERIFY ECP was within 750 pcm of actual criticality (Other Acceptance Criteria 5.2B). [5] VERIFY ECP was within 500 pcm of actual criticality (Review Criteria 5.3). Date __ _ WBN Estimated Critical Position Unit 1 Data Package: Page __ of __ 6.10 Critical Data Evaluation
[1] RECORD the following critical data, AND EVALUATE against the ECp.4 A. Date and time for ECP: I I 1-51-0-11 Rev. 0014 Page 54 of 69 -------B. Date and time of criticality:
_1_1 ___ : __ C. Core average temperature:
___ oF. D. Control bank position:
___ steps. E. C b: ppm. [2] VERIFY the elapsed time from Step 6.9[1] to Step 6.10[1] B was less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . [3] VERIFY ECP was within 1000 pcm of actual criticality (Other Acceptance Criteria 5.2A). [4] VERIFY ECP was within 750 pcm of actual criticality (Other Acceptance Criteria 5.2B). [5] VERIFY ECP was within 500 pcm of actual criticality (Review Criteria 5.3). Date __ _
7.0 WBN Estimated Critical Position Unit 1 Data Package: Page __ of __ POST PERFORMANCE ACTIVITY 1-SI-0-11 Rev. 0014 Page 55 of 69 [1] NOTIFY SM/Unit SRO that this instruction is field complete.
[2] RECORD completion date & time on Surveillance Task Sheet. [3] IF ECP was NOT within 500 pcm of actual criticality, THEN ENSURE the ECP differences are documented in a WBN PER in accordance with the Corrective Action Program. NOTE Date ___ _ PlaCing Shutdown Monitor to Shutdown Monitor mode will enable Shutdown Monitoring; therefore, this step should be performed after the Source Range drawer has been de-energized.
[4] REQUEST Unit SRO to place the Source Range N-31 Shutdown Monitor Panel to Shutdown Monitor mode by PRESSING the button marked 1/M on panel 1-NI-92-133-D. (May be NA'd if 11M mode NOT used.) [5] ENSURE high flux Alarm LED on paneI1-NI-92-133-D is NOT LIT. [6] ENSURE HIGH FLUX AT SHUTDOWN bistable on CH I NEUTRON MON SOURCE RNG DWR, 1-NI-92-131-D, is NOT LIT. [7] REQUEST Unit SRO to place the Source Range N-32 Shutdown Monitor Panel to Shutdown Monitor mode by PRESSING the button marked 11M on panel 1-NI-92-134-E. (May be NA'd if 11M mode NOT used.) [8] ENSURE high flux Alarm LED on paneI1-NI-92-134-E is NOT LIT. [9] ENSURE HIGH FLUX AT SHUTDOWN bistable on CH II NEUTRON MON SOURCE RNG DWR, 1-NI-92-132-E, is NOT LIT. 7.0 WBN Estimated Critical Position Unit 1 Data Package: Page __ of __ POST PERFORMANCE ACTIVITY 1-SI-0-11 Rev. 0014 Page 55 of 69 [1] NOTIFY SMIUnit SRO that this instruction is field complete.
[2] RECORD completion date & time on Surveillance Task Sheet. [3] IF ECP was NOT within 500 pcm of actual criticality, THEN ENSURE the ECP differences are documented in a WBN PER in accordance with the Corrective Action Program. NOTE Date __ _ Placing Shutdown Monitor to Shutdown Monitor mode will enable Shutdown Monitoring; therefore, this step should be performed after the Source Range drawer has been de-energized.
[4] REQUEST Unit SRO to place the Source Range N-31 Shutdown Monitor Panel to Shutdown Monitor mode by PRESSING the button marked 11M on panel 1-NI-92-133-D. (May be NA'd if 11M mode NOT used.) [5] ENSURE high flux Alarm LED on panel 1-NI-92-133-D is NOT LIT. [6] ENSURE HIGH FLUX AT SHUTDOWN bistable on CH I NEUTRON MON SOURCE RNG DWR, 1-NI-92-131-D, is NOT LIT. [7] REQUEST Unit SRO to place the Source Range N-32 Shutdown Monitor Panel to Shutdown Monitor mode by PRESSING the button marked 11M on paneI1-NI-92-134-E. (May be NA'd if 11M mode NOT used.) [8] ENSURE high flux Alarm LED on paneI1-NI-92-134-E is NOT LIT. [9] ENSURE HIGH FLUX AT SHUTDOWN bistable on CH II NEUTRON MON SOURCE RNG DWR, 1-NI-92-132-E, is NOT LIT.
WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 56 of 69 Data Package: Page __ of __ Date ___ _ 7.0 POST PERFORMANCE ACTIVITY (continued)
NOTE Starting the exposure calculation on the ICS is performed from the CORE EXPOSURE FUNCTION MENU (turn on code "corx"). To start the calculations the previous cycle's exposure calculations must have been turned OFF or it may be turned off at this time prior to starting the function.
A YES answer is required to be entered in the ICS when queried. [10] IF this is the initial startup after a refueling, THEN . ENSURE the Core Exposure function on the ICS Computer is started for the cycle .. 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
A. Completed parts of Sections 4.0,6.0, and 7.0 B. Section 5.0. C. Surveillance Task Sheet. D. Completed Appendix Data Sheets. E. Other sheets added during performance.
8.2 Non-QA Records None WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 56 of 69 Data Package: Page __ of __ Date ___ _ 7.0 POST PERFORMANCE ACTIVITY (continued)
NOTE Starting the exposure calculation on the ICS is performed from the CORE EXPOSURE FUNCTION MENU (turn on code "corx"). To start the calculations the previous cycle's exposure calculations must have been turned OFF or it may be turned off at this time prior to starting the function.
A YES answer is required to be entered in the ICS when queried. [10] IF this is the initial startup after a refueling, THEN . ENSURE the Core Exposure function on the ICS Computer is started for the cycle .. 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
A. Completed parts of Sections 4.0, 6.0, and 7.0 B. Section 5.0. C. Surveillance Task Sheet. D. Completed Appendix Data Sheets. E. Other sheets added during performance.
8.2 Non-QA Records None
') ) WBN Unit 1 Estimated Critical Position Appendix A (Page 1 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page_57 _()f 69 Data Package: Page __ of __ Date ___ _ Time ICRR Monitoring Using Shutdown Monitor 11M Display SOURCE RANGE CHANNEL: N-131, and N-132 ITEM: UNITS: 8ankiD & Position (Steps) ICRR [11M] Channel N-131 ICRR [11M] Channel N-132 Initial Reviewed by: _____________
_ WBN Unit 1 Estimated Critical Position Appendix A (Page 1 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 57 of 69 Data Package: Page __ of __ Date ___ _ ICRR Monitoring Using Shutdown Monitor 11M Display SOURCE RANGE CHANNEL: N-131, and N-132 ITEM: Bank 10 & ICRR [11M] ICRR [11M] Time Position Channel Channel Initial UNITS: (Steps) N-131 N-132 Reviewed by: ---------------
) WBN Unit 1 Estimated Critical Position Appendix A (Page 2 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 58 of 69 ICRR Monitoring Using Shutdown Monitor 11M Display VS. ROD POSITION SOURCE RANGE CHANNEL: N-131, and N-132 Bank Bank Position ICRR [11M] ICRR [11M] 10 (Steps) Channel N-131 ChannelN-132 Initial
..
CBA 50 CBA 100 CBAlB 150/34 CBAlB 200/84 CBB/C 134/18 CBB/C 184/68 CBC/O 118/2 CBC/O 168/52 CBCID CBO CBO CBO CBO CBO CBO '-----------Reviewed By: _______________
_ WBN Unit 1 Estimated Critical Position Appendix A (Page 2 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 58 of 69 ICRR Monitoring Using Shutdown Monitor 11M Display VS. ROD POSITION SOURCE RANGE CHANNEL: N-131, and N-132 Bank Bank Position ICRR [11M] ICRR [11M] 10 (Steps) Channel N-131 Channel N-132 Initial CBA 50 CBA 100 CBAlB 150/34 CBAlB 200/84 CBB/C 134/18 CBB/C 184/68 CBC/O 118/2 CBC/O 168/52 CBC/O CBO CBO CBO CBO CBO CBO Reviewed By: ------------------------------
) WBN Unit 1 Estimated Critical Position Appendix A (Page 3 of 6) ICRR Monitoring 1-81-0-11 Rev. 0014 Page 59 of 69 Data Package: Page __ of __ Date __ _ ICRR MONITORING USING COUNT RATE METER SOURCE RANGE CHANNEL: N-131 0, or N-132 0 Bank Bank Count Rate Base Count Rate Position (C;) (Co) ICRR [Co/C;l Initial 10 (Steps) [Countsl Ll Tl (cps) Initial Co CBA 50 CBA 100 CBAlB 150/34 ; CBAlB 200/84 CBB/C 134/18 CBB/C 184/68 CBCID 118/2 CBCID 168/52 CBCID CBO CBO CBO CBO CBO CBO Reviewed By: _______________
_ ) WBN Unit 1 Estimated Critical Position Appendix A (Page 3 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 59 of 69 Data Package: Page __ of __ Date ___ _ ICRR MONITORING USING COUNT RATE METER SOURCE RANGE CHANNEL: N-131 0, or N-132 0 Bank Bank Count Rate Base Count Rate 10 Position (C i) (Co) ICRR [Co/Cil Initial (Steps) (cps) Initial Co CBA 50 CBA 100 CBAlB 150/34 CBAlB 200/84 CBB/C 134/18 CBB/C 184/68 CBCID 118/2 CBCID 168/52 CBCID CBO CBO CBO CBO CBO CBO Reviewed By: ------------------------------
) WBN Unit 1 Estimated Critical Position Appendix A (Page 4 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 60 of 69 Data Package: Page __ of __ Date __ _ ICRR MONITORING USING SCALAR TIMER SOURCE RANGE CHANNEL: N-131 0, or N-132 0 Count Count Rate Base ICRR Bank Period (C i) Count Rate (Co) [Co/Cil Initial Bank Position Counts [L\T] [Counts/L\T] (cps) 10 (Steps) (sec) (cps) c, f i0/ Initial L\T and Co iif ..
J
.... ***.*.**.**l*!
. ... **.*.Ci(.0s.fi;.*
....
CBA 50 CBA 100 CBAlB 150/34 CBAlB 200/84 CBB/C 134/18 CBB/C 184/68 CBC/O 118/2 CBCID 168/52 CBCID CBO CBO CBO CBO CBO Reviewed By: _______________
_ WBN Unit 1 Estimated Critical Position Appendix A (Page 4 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 60 of 69 Data Package: Page __ of __ Date ___ _ ICRR MONITORING USING SCALAR TIMER SOURCE RANGE CHANNEL: N-131 D, or N-132 D Bank Count Count Rate Base Bank Position Counts Period (C i) Count Rate (Co) ICRR 10 (Steps) [fiT] [Countsl fi T] (cps) [CO/C i] Initial (sec) (cps)
Initial fiT and Co CBA 50 CBA 100 CBAlB 150/34 CBAlB 200/84 CBB/C 134/18 CBB/C 184/68 CBC/O 118/2 CBC/O 168/52 CBC/O CBO CBO CBO CBO CBO Reviewed By: -----------------------------
WBN Unit 1 Estimated Critical Position Appendix A (Page 5 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 61 of 69 Data Package: Page __ of __ Date __ _ ICRR MONITORING USING COUNT RATE METER SOURCE RANGE CHANNEL: N-131 D or N-132 D COUNT RATE BASE COUNT ITEM: (C;) ICRR UNITS:
T)] RATE (Co) [CalC;] INITIAL (CPS) (CPS) INITIAL AND Co Reviewed By: _______________
_ WBN Unit 1 Estimated Critical Position Appendix A (Page 5 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 61 of 69 Data Package: Page __ of __ Date __ _ ICRR MONITORING USING COUNT RATE METER SOURCE RANGE CHANNEL: N-131 0 or N-132 0 COUNT RATE BASE COUNT ITEM: (C i) RATE (Co) ICRR UNITS: [COUNTS/(,1.
T)l (CPS) [Co/Cil INITIAL (CPS) INITIAL ,1.T AND Co Reviewed By: -----------------------------
) WBN Unit 1 Estimated Critical Position Appendix A (Page 6 of 6) ICRR Monitoring 1-81-0-11 Rev. 0014 Page 62 of 69 Data Package: Page __ of __ Date __ _ ICRR MONITORING USING SCALAR TIMER SOURCE RANGE CHANNEL: N-131 D or N-132 D COUNTING COUNT RATE (C i) BASE COUNT ITEM: COUNTS PERIOD ICRR INITIAL UNITS: (ilT) [COUNTS/(il T)] RATE (Co) [Co/C i] (SEC) (CPS) (CPS) INITIAL ilT AND Co Reviewed By: ______________
_ WBN Unit 1 Estimated Critical Position Appendix A (Page 6 of 6) ICRR Monitoring 1-51-0-11 Rev. 0014 Page 62 of 69 Data Package: Page __ of __ Date __ _ ICRR MONITORING USING SCALAR TIMER SOURCE RANGE CHANNEL: N-131 0 or N-132 0 COUNTING COUNT RATE (C i) BASE COUNT ITEM: COUNTS PERIOD ICRR INITIAL UNITS: (L'lT) [COUNTS/(L'l T)l RATE (Co) [Co/Cil (SEC) (CPS) (CPS) INITIAL L'lT AND Co Reviewed By: -----------------------------
WBN Unit 1 Estimated Critical Position Appendix B (Page 1 of 3) Predicted ICRRs Data Package: Page __ of __ Table 1 1-51-0-11 Rev. 0014 Page 63 of 69 Date ___ _ ROD POSITIONS AT CRITICALITY (ROD SEARCH) (Step 6.6[8]A) (Step 6.6[8]B) (Step 6.6[8]C) Condition Keff Ref Limit Desired K C Bank o Bank (pcm) (steps) (steps) Rod Insertion Limit (Step 6.6[6]B) 0 Lower 1000 pcm Limit (Step 6.6[1]0) -1000 Lower 750 pcm Limit (Step 6.6[1]0) -750 Lower 500 pcm Threshold (Step 6.6[1]0) -500 Estimated Critical (Step 6.6[1]0) 0 Condition All Rods Out (Step 6.6[7]B) 0 Upper 500 pcm Threshold (Step 6.6[1]0) 500 Upper 750 pcm Limit (Step 6.6[1]0) 750 Upper 1000 pcm Limit (Step 6.6[1]0) 1000 Performed By: Reviewed By: WBN Unit 1 Estimated Critical Position Appendix B (Page 1 of 3) Predicted ICRRs Data Package: Page __ of __ Table 1 1-51-0-11 Rev. 0014 Page 63 of 69 Date ----ROD POSITIONS AT CRITICALITY (ROD SEARCH) (Step 6.6[8]A) (Step 6.6[8]B) (Step 6.6[8]C) Condition K Ref eft Limit Desired K C Bank o Bank (pcm) (steps) (steps)
Rod Insertion Limit (Step 6.6[6]B) 0 Lower 1000 pcm Limit (Step 6.6[1]0) -1000 Lower 750 pcm Limit (Step 6.6[1]0) -750 Lower 500 pcm Threshold (Step 6.6[1]0) -500 Estimated Critical (Step 6.6[1]0) 0 Condition All Rods Out (Step 6.6[7]B) 0 Upper 500 pcm Threshold (Step 6.6[1]0) 500 Upper 750 pcm Limit (Step 6.6[1]0) 750 Upper 1000 pcm Limit (Step 6.6[1]0) 1000 Performed By: Reviewed By:
WBN Unit 1 Condition Rod Insertion Limit Lower 1000 pcm Limit Lower 750 pcm Limit Lower 500 pcm Threshold Estimated Critical Condition All Rods Out Upper 500 pcm Threshold Upper 750 pcm Limit Upper 1000 pcm Limit Estimated Critical Position Appendix B (Page 2 of 3) Predicted ICRRs Table 2 Rev. 0014 Page 64 of 69 ROD POSITIONS AT 8-Fold (ROD SEARCH) (Step 6.6[9]A) (Step 6.6[9]B) (Step 6.6[9]C) Kef! Ref Limit Desired K C Bank o Bank (pcm) (steps) (steps) (Step 6.6[6]B) 0 (Step 6.6[1]0) -1000 (Step 6.6[1]0) -750 (Step 6.6[1]0) -500 (Step 6.6[1]0) 0 (Step 6.6[7]B) 0 (Step 6.6[1]0) 500 (Step 6.6[1]0) 750 (Step 6.6[1]0) 1000 Performed By: Reviewed By: WBN Unit 1 Condition Rod Insertion Limit Lower 1000 pcm Limit Lower 750 pcm Limit Lower 500 pcm Threshold Estimated Critical Condition All Rods Out Upper 500 pcm Threshold Upper 750 pcm Limit Upper 1000 pcm Limit Estimated Critical Position Appendix B (Page 2 of 3) Predicted ICRRs Table 2 Rev. 0014 Page 64 of 69 ROD POSITIONS AT 8-Fold (ROD SEARCH) (Step 6.6[9]A) (Step 6.6[9]B) (Step 6.6[9]C) Kel ef Limit Desired K C Bank o Bank (pcm) (steps) (steps) (Step 6.6[6]B) a (Step 6.6[1]0) -1000 (Step 6.6[1]0) -750 (Step 6.6[1]0) -500 (Step 6.6[1]0) a (Step 6.6[7]B) a (Step 6.6[1]0) 500 (Step 6.6[1]0) 750 (Step 6.6[1]0) 1000 Performed By: Reviewed By:
WBN Unit 1 Condition Rod Insertion Limit Lower 1000 pcm Limit Lower 750 pcm Limit Lower 500 pcm Threshold Estimated Critical Condition All Rods Out Upper 500 pcm Threshold Upper 750 pcm Limit Upper 1000 pcm Limit Estimated Critical Position Appendix B (Page 3 of 3) Predicted ICRRs Table 3 1-51-0-11 Rev. 0014 Page 65 of 69 ROD POSITIONS AT 4-Fold (ROD SEARCH) (Step 6.6[1 O]A) (Step 6.6[10]8) (Step 6.6[1 O]C) K.,lef Limit Desired K C 8ank o 8ank (pcm) (steps) (steps) (Step 6.6[6]8) 0 (Step 6.6[1]0) -1000 (Step 6.6[1 ]0) -750 (Step 6.6[1 ]0) -500 (Step 6.6[1]0) 0 (Step 6.6[7]8) 0 (Step 6.6[1 ]0) 500 (Step 6.6[1]0) 750 (Step 6.6[1]0) 1000 -----------Performed By: Reviewed By: WBN Unit 1 Condition Rod Insertion Limit Lower 1000 pcm Limit Lower 750 pcm Limit Lower 500 pcm Threshold Estimated Critical Condition All Rods Out Upper 500 pcm Threshold Upper 750 pcm Limit Upper 1000 pcm Limit Estimated Critical Position Appendix B (Page 3 of 3) Predicted ICRRs Table 3 1-51-0-11 Rev. 0014 Page 65 of 69 ROD POSITIONS AT 4-Fold (ROD SEARCH) (Step 6.6[1 O]A) (Step 6.6[1 O]B) (Step 6.6[1 O]C) K"ff Ref Limit Desired K C Bank D Bank (pcm) (steps) (steps) (Step 6.6[6]B) 0 (Step 6.6[1]D) -1000 (Step 6.6[1]D) -750 (Step 6.6[1]D) -500 (Step 6.6[1]D) 0 (Step 6.6[7]B) 0 (Step 6.6[1]D) 500 (Step 6.6[1]D) 750 (Step 6.6[1]D) 1000 Performed 8y: Reviewed 8y:
WBN Unit 1 Estimated Critical Position Appendix C (Page 1 of 1) BEACON ECC 1-51-0-11 Rev. 0014 Page 66 of 69 Data Package: Page __ of __ Date ___ _ Time Since . D Bank C b ECC C b Calendar Date Input Model Position (ppm) (ppm) (ppm) and Time (hrs) (steps) Step 6.7[3.1] Step 6.7[3.1] Step 6.7[3.1] Step 6.7[3.2] Step 6.7[3.3] Step 6.7[3.4] Performed by: Reviewed by: WBN Unit 1 Estimated Critical Position Appendix C (Page 1 of 1) BEACON ECC Data Package: Page __ of __ Time Since D Bank C b ilC b B-1O Input Model Position (ppm) (ppm) (hrs) (steps) Step 6.7[3.1] Step 6.7[3.1] Step 6.7[3.1] Step 6.7[3.2] Performed by: Reviewed by: 1-51-0-11 Rev. 0014 Page 66 of 69 Date ___ _ ECC C b Calendar Date (ppm) and Time Step 6.7[3.3] Step 6.7[3.4]
>, \ I WBN Unit 1 0 50 1.1 1 0_9 0_8 0_7 0_6 <;.> i-j 0_5 0_4 0_3 0_2 0_1 0 0 50 Estimated Critical Position Figure 1 (Page 1 of 1) 1-SI-0-11 Rev. 0014 Page 67 of 69 ICCR VS Control Bank Position 2 52 102 152 68 118 168 218 CBC 34 84 134 184 CBB 100 150 200 CBA 100 150 200 250 300 350 400 450 500 Total Rod Steps CONTROL BANK POSITION, Steps (Assuming Bank Overlap) Performed By: Reviewed By: 202 CBD 550 600 ) WBN Unit 1 0 50 1.1 1 0.9 0.8 0.7 0.6 U 1-1 0.5 0.4 0.3 0.2 0.1 0 0 50 Estimated Critical Position Figure 1 (Page 1 of 1) 1-SI-0-11 Rev. 0014 Page 67 of 69 ICCR VS Control Bank Position 2 52 102 152 68 118 168 218 CBC 34 84 134 184 CBB 100 150 200 CBA 100 150 200 250 300 350 400 450 500 Total Rod Steps CONTROL BANK POSITION, Steps (Assuming Bank Overlap) Performed By: Reviewed By: 202 CBD 550 600 1 t>t .;.l ::. .;.l 0 Q) .z: WBN Unit 1 Estimated Critical Position Figure 2 (Page 1 of 1) CIPS Adjustment 1-SI-0-11 Rev. 0014 Page 68 of 69 1000 > 9 00 -I---' ...... ...... -+--...... --+-:----+---""""'....!,-
......
800 700
...... .....:-'-......
600 500 400 MO 200 -I-'----'-!-.-
...... 100 o ,. o 10000 20000 30000 40000 50000 Absolute Value [ f DAO d BU] (%
MWD/MTU) 60000 >t .j.l '1"'1 > '1"'1 .j.l 0 Q) WBN Unit 1 Estimated Critical Position Figure 2 (Page 1 of 1) CIPS Adjustment 1-SI-0-11 Rev. 0014 Page 68 of 69 900 --------------------------------

800 ------------------------

700 ----------------------------------------------

600 500 400 300 200 ----------------------------------------

100 --------------------------------------

o 10000 20000 30000 40000 50000 60000 Absolute Value [ f DAO d BU] (%
MWD/MTU)
) WBN Unit 1 Estimated Critical Position Source Notes (Page 1 of 1) 1-SI-0-11 Rev. 0014 Page 69 of 69 Implementing Requirements Statement Source Document Statement Requires 11M monitoring SOER 88-002, Recommendation 2 1 Criticality must be expected anytime SOER 84-002, Recommendation 8 2 positive reactivity is being added to the core. Requires periodic pauses during rod withdrawal to allow neutron level stabilization and the use of the Audio Count Rate Speaker. Premature Criticality Events During Reactor Startup. SOER 88-002 Recommendation 6 3 SOER 88-002 Rec. 7 4 WBN Unit 1 Estimated Critical Position Source Notes (Page 1 of 1) 1-51-0-11 Rev. 0014 69 of 69 Implementing Requirements Statement Source Document Statement Requires 11M monitoring SOER 88-002, Recommendation 2 1 Criticality must be expected anytime SOER 84-002, Recommendation 8 2 positive reactivity is being added to the core. Requires periodic pauses during rod withdrawal to allow neutron level stabilization and the use of the Audio Count Rate Speaker. Premature Criticality Events During Reactor Startup. SOER 88-002 Recommendation 6 3 SOER 88-002 Rec. 7 4 WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam I A.2-1 RO Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." PAGE 1 OF 17 WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam I A.2-1 RO Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." PAGE 1 OF 17 Task: Alternate Path: Facility JPM #: WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam EVALUATION SHEET Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." N/A New Safety Function:
N/A Title: N/A KIA 2.2.12 Knowledge of surveillance procedures.
Rating(s):
3.7/4.1 CFR: Preferred Evaluation Location:
Preferred Evaluation Method: Simulator x
References:
Task Number: Task Standard:
Validation Time: Classroom Perform X Simulate 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Rev. 30. . RO-113-GEN-004 Title: Perform surveillance tests. Applicant performs data collection for Data Sheet 1, pages 1 through 4 of 1-SI-0-2A-03, "1900-0700 Shiftand Daily Surveillance Log Mode Three." and identifies instruments that do not meet the acceptable range identified in the instruction.
minutes Time Critical:
Yes No X ---===========================================================================
Applicant:
Time Start: NAME SSN Time Finish: Performance Rating: SAT UNSAT Performance Time Examiner:
_____
NAME SIGNATURE DATE ===========================================================================
COMMENTS PAGE 2 OF 17 Alternate Path: Facility JPM #: WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam EVALUATION SHEET Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." N/A New Safety Function:
N/A Title: N/A KIA 2.2.12 Knowledge of surveillance procedures.
Rating(s):
3.7/4.1 Preferred Evaluation Location:
Preferred Evaluation Method: Simulator X Classroom Perform X Simulate -------
References:
Task Number: Task Standard:
Validation Time: 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Rev. 30. RO-113-GEN-004 Title: Perform surveillance tests. Applicant performs data collection for Data Sheet 1, pages 1 through 4 of 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." and identifies instruments that do not meet the acceptable range identified in the instruction.
minutes Time Critical:
Yes No X -----===========================================================================
Applicant:
Time Start: NAME SSN Time Finish: Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE ===========================================================================
COMMENTS PAGE 2 OF 17 WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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. The Unit is in Mode 3, with no LCO entries at this time. 2. Portions of the field data have been entered by NAUOs. 3. You are the Unit Operator responsible to perform and review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." ) INITIATING CUES: 1. You are to complete 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, pages 1 through 4 of 15. Another Unit Operator will complete the remainder of Data Sheet 1. 2. When you have finished performing the assigned pages of Data Sheet 1, and addressed any deviations, notify the Unit Supervisor that you have completed your task. PAGE 3 OF 17 WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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. The Unit is in Mode 3, with no LCO entries at this time. 2. Portions of the field data have been entered by NAUOs. 3. You are the Unit Operator responsible to perform and review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." ) INITIATING CUES: 1. You are to complete 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, pages 1 through 4 of 15. Another Unit Operator will complete the remainder of Data Sheet 1. 2. When you have finished performing the assigned pages of Data Sheet 1, and addressed any deviations, notify the Unit Supervisor that you have completed your task. PAGE 3 OF 17 WATTS 81 NUCLEAR PLANT );(.2-1 RO Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
1. ENSURE NRC Examination Security has been established.
2. Right click on 319, and then select RESET. 3. Enter the password.
4. Select "Yes" on the INITIAL CONDITION RESET pop-up window. 5. ENSUREthe following information appears on the Director Summary Screen: pi-1-2a 05150 sg #1 stm hdr eh 1 0 00:00:00 00:00:00 pi-1-2b 05150 sg #1 stm hdr eh 2 0 00:00:00 00:00:00 pi-1-5 05150 sg #1 main stm hdr 0 00:00:00 00:00:00 li-3-55 05050 sg #2 level ind 0 00:00:00 00:00:00 li-68-335a 05350 res przr Ivl(m-4) 0 00:00:00 00:00:00 I li-63-52 09030 sis rwst level ind 0 00:00:00 00:00:00 6. Place simulator in RUN and acknowledge any alarms. 7. Place simulator in FREEZE until Examiner cue is given. PAGE 4 OF 17 00:00:00 1045 1044.98 00:00:00 1055 1054.97 00:00:00 1150 1149.99 00:00:00 30 37.8133 00:00:00 35 34.9986 00:00:00 90 89.9991 WATTS 81 NUCLEAR PLANT H.2-1 RO Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
1. ENSURE NRC Examination Security has been established.
2. Right click on 319, and then select RESET. 3. Enter the password.
4. Select "Yes" on the INITIAL CONDITION RESET pop-up window. 5. ENSURE the following information appears on the Director Summary Screen: Key Type Event Delay Inserted pi-1-2a 05150 sg #1 stm hdr eh 1 0 00:00:00 00:00:00 pi-1-2b 05150 sg #1 stm hdr eh 2 0 00:00:00 00:00:00 pi-1-5 05150 sg #1 main stm hdr 0 00:00:00 00:00:00 li-3-55 05050 sg #2 level ind 0 00:00:00 00:00:00 li-68-335a 05350 res przr Ivl(m-4) 0 00:00:00 00:00:00 li-63-52 09030 sis rwst level ind 0 00:00:00 00:00:00 6. Place simulator in RUN and acknowledge any alarms. 7. Place simulator in FREEZE until Examiner cue is given. PAGE 4 OF 17 Ramp Initial Final Value 00:00:00 1045 1044.98 00:00:00 1055 1054.97 00:00:00 1150 1149.99 00:00:00 30 37.8133 00:00:00 35 34.9986 00:00:00 90 89.9991 WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ SAT/UNSAT EXAMINERS CUE: Provide a marked-up copy of 1-SI-0-2A-03 to applicant.
The following are the items to be marked: Ref 8 , SR Neutron Mon CH 1 and CH II -enter 2 cps Ref. 16, 480V Rx MOV Boards -enter check mark for 1-BKR-63-1A OR 1-BKR-63-1B, 1-BKR-63-22A OR 1-BKR-63-22B.
Ref. 20, CNTMT Press -Enter check mark for 1-PDI-30-42, and enter "0" in the Data column. Enter check mark for 1-PDI-30-43, and enter "0" in the Data column. Enter check mark for 1-PDI-30-44, and enter "0" in the Data column. Enter check mark for 1-PDI-30-45, and enter "0" in the Data column. STEP 1: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 1, Reference 3 data collection and determine if Acceptance Criteria are met. 1-M-2 I I 1-U-2-230A 0 3 I Pnl 0-L-209 CST A Level OR T15M!708 i-U-2-230B 0 STANDARD:
2: 200,000 gallons Petform Data Sheet 3 of 1-SI-0-2-00 gallons I "CST Level" Applicant enters value for either 1-U-2-230A or 1-U-2-230B whichever was selected.
If applicant gallons is entered in the Data column .. If applicant selects 1 gallons is entered in the Data column. Applicant determines that the gallon acceptance criterion is met. COMMENTS:
PAGE 5 OF 17 SAT UNSAT ) L WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ SATIUNSAT EXAMINERS CUE: Provide a marked-up copy of 1-SI-0-2A-03 to applicant.
The following are the items to be marked: Ref 8 , SR Neutron Mon CH 1 and CH II -enter 2 cps Ref. 16, 480V Rx MOV Boards -enter check mark for 1-BKR-63-1A OR 1-BKR-63-1B, 1-BKR-63-22A OR 1-BKR-63-22B.
Ref. 20, CNTMT Press -Enter check mark for 1-PDI-30-42, and enter "0" in the Data column. Enter check mark for 1-PDI-30-43, and enter "0" in the Data column. Enter check mark for 1-PDI-30-44, and enter "0" in the Data column. Enter check mark for 1-PDI-30-45, and enter "0" in the Data column. STEP 1: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 1, Reference 3 data collection and determine if Acceptance Criteria are met. 1-M-2 1-1I-2-230A 0 3 Pnl 0-l-209 CST A level OR T15M/70a 1-1I-2-230B 0 STANDARD: 200,000 gallons Perform Data Sheet 3 of 1-SI-0-2-00 gallons "CST level" Applicant enters value for either 1-U-2-230A or 1-U-2-230B whichever was selected.
If applicant selects 1-Ll-2-230A, approximately 390,000 gallons is entered in the Data column .. If applicant selects 1-Ll-2-230B, approximately 300,000 gallons is entered in the Data column. Applicant determines that the 2:200,000 gallon acceptance criterion is met. COMMENTS:
PAGE 5 OF 17 SAT UNSAT
'r STEP 2. 4 I-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference 4 data collection and determine if Acceptance Criteria are met. 1-PI-1-2A psig SG 1 Press 1-PI-1-2B
"-;OSt> psig 1-PI-1-5 . ( "'-114<> psig 1-PI-1-9A lOBO psig SG 2 Press 1-PI-1-9B Operable.
1080 psig Contact SRO 1-PI-1-12 Channel /080 psig to Check, and Lo10 psig consult Tech 1-PI-1-20A MCD s; 90 Specs. SG 3 Press 1-PI-1-20B psig psig 1-PI-1-23 1070 psig 1-PI-1-27A 1070 psig SG 4 Press 1-PI-1-27B 10'1P psig 1-PI-1-30 I04c> psig Applicant obtains current readings for SG Pressure and records them on the data sheet, and determines ,UV'i< t;: ,<,1: '-/, ' ,-;;/;.'.";:>
.. , ',;;>f/:, ';,,' .. " " ',;; .-."f:> _ " _ ,<;:/';' _,' -Ii; --__
-,'
__ <<:>-
_
__ ,,_ -----,: ,::.------
--" ,j . NO].vXnl1.in EXAMINER'S CUE: If asked about 1-PI-1-5 indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
EXAMINER'S CUE: If asked to review previous shift's SI-2 Data, state that the Unit Supervisor will retrieve data. If pursued further, then say that the Unit Supervisor reviewed data and all instrumentation was within MCD. COMMENTS:
PAGE 6 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT STEP 2. 4 t-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference 4 data collection and determine if Acceptance Criteria are met. 1-PI-1-2A
""'040 psig SG 1 Press 1-PI-1-2S
.... ;050 psig 1-PI-1-5 C 4114<> psig 1-PI-1-9A i060 psig 1-PI-1-9S Operable.
1080 psig Contact SRO 1-PI-1-12 Channel psig to 1-PI-1-20A Check, and 1010 psig consult Tech MCD s 90 1-PI-1-20B psig J()(gO psig Specs. SG 2 Press SG 3 Press 1-PI-1-23 1070 psig 1-PI-1-27A
/()10 psig SG 4 Press 1-PI-1-27B 1010 psig 1-PI-1-30 lOtto psig Applicant obtains current readings for SG Pressure and records them on 1 the data sheet, and determines that SG 1 Pressure channeI1-PI-1-5 is , ". NOT within Maximum Channel Deviation (MCD) of 90 psig. EXAMINER'S CUE: If asked about 1-PI-1-5 indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
EXAMINER'S CUE: If asked to review previous shift's SI-2 Data, state that the Unit Supervisor will retrieve data. If pursued further, then say that the Unit Supervisor reviewed data and all instrumentation was within MCD. COMMENTS:
PAGE 6 OF 17 SATIUNSAT CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam \
STEP 3: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference 5 data collection and determine if Acceptance Criteria are met. 1-U-3-42 % SG 1 Level 1-U-3-39 1-U-3-38 1-U-3-55 Operable at 1-U-3-52 32% NR [for OPERABLE Contact SRO 1-U-3-51 to 1-U-3-97 loops], consult Tech Channel 1-1 1-:1-94 Check, and Specs, SG 2 Level 5 I 1-M-4 5G 3 Level l-U-3-93 MCDs6,O% 1-U-3-110 5G 4 Level 1-U-3-107 1-U-3-106
% STANDARD:
Applicant obtains current readings for SG Level and records them on the
.9 )
6v.Q.%.J EXAMINER'S CUE: If asked about 1-U-3-55 indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
EXAMINER'S CUE: If asked to review previous shift's SI-2 Data, state that the Unit Supervisor will retrieve data. If pursued further, then say that the Unit Supervisor reviewed data and all instrumentation was within MCD. COMMENTS:
PAGE 7 OF 17 CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam Irl -------------------------------------------------------,-----------, STEP/STANDARD SAT/UNSAT STEP 3: PERFORM 1*SI*O*2A*03, Data Sheet 1, Page 1, Reference 5 data collection and determine if Acceptance Criteria are met. 1-L1-3-42
.. .39 % SG 1 Level 1-L1-3-39 % 1-L1-3-38
% 1-L1-3-55 Operable at C ,,,.2>0 %) 1-L1-3-52 32% NR [for
% Contact SRO 1-L1-3-51 OPERABLE fc..40 % to 1-L1-3-97 loops], consult Tech Channel 1-L1-3-94 Check, and
% Specs, SG 2 Level 5 1-M-4 SG 3 Level 1-L1-3-93
% 1-Ll-3-110
,... 38 % SG 4 Level 1-Ll-3-107 f"-' 38 % 1-Ll-3-106 V3g % STANDARD:
Applicant obtains current readings for SG Level and records them on the data sheet, and determines that SG 2 Level channel 1-U-3-55 is NOT ) within MCD is within s 6.0%. EXAMINER'S CUE: If asked about 1*LI*3*55 indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
EXAMINER'S CUE: If asked to review previous shift's SI*2 Data, state that the Unit Supervisor will retrieve data. If pursued further, then say that the Unit Supervisor reviewed data and all instrumentation was within MCD. COMMENTS:
PAGE 7 OF 17 CRITICAL STEP SAT UNSAT STEP 4: 8 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 8 data collection and determine if Acceptance Criteria are met. Operable, Channel Check, and MCD SR Neutron 1-NI-92-131A
,,'"';, p'"' m;,", Cootao' 1/2 decade SRO to Mon CH I [0.3CR1<CR2
2. CPS(2) consult <3.0CR1].
Tech Spec Reading should be the s. I 1-N 1-92-132A I average value SR Neutron observed over a I Z CPS(2) Mon CH II 30 second perIod Applicant determines that the Source Range Monitors are Operable and within the MCD tolerance.
COMMENTS:
pAGE 8 OF 17 SAT/UNSAT SAT UNSAT STEP 4: 8 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 8 data collection and determine if Acceptance Criteria are met. Operable, Channel Check, and MCD SR Neutron 1-NI-92-131A value is plus or minus Mon CH I 1/2 decade Contact [0.3CR1 <CR2 SRO to <3.0CR1].
2. CPS(2) consult Reading should be the Tech Spec s. SR Neutron 1-NI-92-132A average value Mon CH II observed over a 2 30 second period CPS(2) Applicant determines that the Source Range Monitors are Operable and within the MCD tolerance.
COMMENTS:
pAGE 8 OF 17 SAT/UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam 1 STEP/STANDARD SAT/UNSAT ) STEP 5: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 9 data collection and determine if Acceptance Criteria are met. 1-U-68-339A Operable, less than or A 2(, % Contact 9 1-M-4 PZR Level 1-U-68-335A equal t080%, ,,( .-. 3'/-SRO Channel Check, an to consult 1-U-68-320 MCD s;6.0% 4-Tech Spec % s. STANDARD:
Applicant obtains current read data sheet. determines th for PZR Level and records them on the EXAMINER'S CUE: If asked about 1-Ll-68-335A indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
EXAMINER'S CUE: If asked to review previous shift's SI-2 Data, state that the Unit Supervisor will retrieve data. If pursued further, then say that the Unit Supervisor reviewed data and all instrumentation was within MCD. COMMENTS:
PAGE 9 OF 17 CRITICAL STEP SAT UNSAT STEP 5: 9 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 9 data collection and determine if Acceptance Criteria are met. 1-Ll-68-339A Operable, less than or A 241 % Contact ...i-'" ....... -:--;;;;;;;;;;;:::-l S RO 1-Ll-68-335A equal t080%, """ 3 tl Channel Check, an-L T to consult Tech Spec 1-Ll-68-320 MCD ::; 6.0% "-% s. PZR Level Applicant obtains current readings for PZR Level and records them on the data sheet, determines that PZR level channel 1-U-68-335A is NOT within MCD is within::;;
6.0%. EXAMINER'S CUE: If asked about 1-Ll-68-33SA indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
} EXAMINER'S CUE: If asked to review previous shift's SI-2 Data, state that the Unit Supervisor will retrieve data. If pursued further, then say that the Unit Supervisor reviewed data and all instrumentation was within MCD. COMMENTS:
PAGE 9 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT 2 \ STEP 6: 10 I 1-M-5 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 2, Reference 10 data collection and determine if Acceptance Criteria are met. 1-PI-68-340A Operable psig Contact 1-PI-68-334 channel check, psig SRO PZR Press greater than or equal to consult 1-PI-68-323 to 2214psig and psig Tech Spec 1-PI-68-322 55 psig. s psig Applicant enters data and determines that all PZR Pressure channels meet acceptance criteria.
COMMENTS:
PAGE 10 OF 17 SAT/UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam \\-----------------------------.,-----------, I STEP 6: 10 1-M-5 STANDARD:
STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 10 data collection and determine if Acceptance Criteria are met. 1-PI-68-340A Operable 22",0 psig Contact 1-PI-68-334 channel check, ... ,,2.24-0 psig SRO PZR Press greater than or equal ..
to consult 1-PI-68-323 to 2214psig and ... psig Tech Spec 1-PI-68-322 MCDs 55 psig. ... ..,:u.40 s psig Applicant enters data and determines that all PZR Pressure channels meet acceptance criteria.
COMMENTS:
PAGE 10 OF 17 SAT/UNSAT SAT UNSAT
) STEP 7: 15 I 1-M-5 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 15 data collection and determine if Acceptance Criteria are met. RCS loops RCP Status 1,2,3,4 RCP 1 1-HS-6S-SAA 1-HS-6S-SBA 1-HS-6S-31AA RCP2 1-H S-6S-31 BA I 1-HS-68-50AA RCP 3 1-HS-68-50BA RCP 4 I 1-HS-68-73AA 1-HS-68-73BA Two loops operable; two loops in operation if capable of rod withdrawal (one loop jf NOT) RCP 1 2 3 4 ON !it" [!(' Iil" Ii!"" OFF 0 0 0 0 tj Coo,,,, SRO to consult J!. (1) Tech Spec s. (1) (1) Applicant enters data for the RCPs and determines that acceptance criteria are met. COMMENTS:
PAGE 11 OF 17 SAT/UNSAT SAT UNSAT STEP 7: 15 1-M-5 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 15 data collection and determine if Acceptance Criteria are met. RCS Loops RCP Status 1,2,3,4 RCP 1 1-HS-68-SAA Two loops operable; 1-HS-6S-8SA two loops in operation 1-H S-68-31 AA jf capable of rod RCP 2 1-H S-68-31 SA withdrawal (one loop if 1-HS-68-50AA NOT) RCP 3 1-H S-68-50SA RCP4 1-H S-68-73AA 1-HS-68-73SA RCP 1 2 3 4 ON OFF 0 0 0 0 'K (1) (1) R (1) ({ (1) Contact SROto consult Tech Spec s, Applicant enters data for the RCPs and determines that acceptance criteria are met. COMMENTS:
PAGE 11 OF 17 SAT/UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam ) STEP/STANDARD SAT/UNSAT STEP 8: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 16 data collection and determine if Acceptance Criteria are met. Ref I Location I Description Instrument
T S Limit Data I Ace NOT Met RWSTto RHR 1-FCV-63-1 OPEN IE'" 16 I 1-M-6 I ECCS Suction (1-HS-63-1 A) OPEN CLOSED 0 SI Pumps to CL 1, 1-FCV-63-22 OPEN [It'" 2,3,4 ( 1-HS-63-22A)
CLOSED 0 Shunt BKR 1A i-A OFF I Contact SRO to c!2E1 1-BKR-63-1 A At least one ON OR breaker OFF consult I Breaker 1-BKR-63-1 B OFF I Tech Specs. 480V Rx 1A1-A cl10A ON MOV Boards I Shunt BKR 1B1-B 1-BKR-63-22A OFF 0 cl2F2 At least one ON OR Breaker 1-BKR-63-22B breaker OFF OFF rY' 1B1-B cl11D ON 0 STANDARD:
Applicant enters data from 1-M-6 and determines that all acceptance criteria are metfor 1-FCV-63-1 and 1-FCV-63-22.
EXAMINER'S NOTE: Local information will be marked on the Data Sheet provided to the applicant, as indicated in the INITIAL CONDITIONS.
COMMENTS:
PAGE 12 OF 17 SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam ) STEP 8: Ref Location 16 l-M-6 480V Rx MOV Boards STANDARD:
PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 16 data collection and determine if Acceptance Criteria are met. Description Instrument
T S Limit Data Acc NOT Met RWSTto RHR 1-FCV-63-l OPEN [i(' ECCS Suction (1-HS-63-1A)
CLOSED 0 OPEN SI Pumps to CL 1, 1-FCV-63-22 OPEN [R'" 2,3,4 (1-HS-63-22A)
CLOSED 0 Shunt BKR 1A1-A 1-BKR-63-1A OFF 0 c!2E1 At least one ON Ii!"" Contact SRO to OR consult Breaker 1-BKR-63-1 B breaker OFF OFF [Y Tech Specs. 1A 1-A cJ10A ON 0 Shunt BKR 1B1-B 1-BKR-63-22A OFF 0 cl2F2 At least one ON [iI""'" OR Breaker 1-BKR-63-22B breaker OFF OFF 1B1-B cll1D ON 0 Applicant enters data from 1-M-6 and determines that all acceptance criteria are met for 1-FCV-63-1 and 1-FCV-63-22.
EXAMINER'S NOTE: Local information will be marked on the Data Sheet provided to the applicant, as indicated in the INITIAL CONDITIONS.
COMMENTS:
PAGE 12 OF 17 SAT UNSAT 2 ) STEP 9: 17 i-M-6 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 17 data collection and determine if Acceptance Criteria are met. 1-U-63-180 Operable, 0 % CNTMT 1-U-63-i81 Channel check, 0 % Sump Level i-U-63-182 and 0 % 1-U-63-183 MCD::;6.0%
0 % Contact SRO to 9f> consult i-U-53-S0 Operable, % Specs RWST Level i-U-63-Si Channel check, % % i-U-53-S2 andMCD ( % ::> i-U-53-S3
7.0% % Applicant enters data and determines that CNTMT SUMP channels meet acceptance criteria.
EXAMINER'S CUE: If asked about 1-Ll-63-52 indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
EXAMINER'S CUE: If asked to review previous shift's SI-2 Data, state that the Unit Supervisor will retrieve data.-If pursued further, then say that the Unit Supervisor reviewed data and all ,instrumentation was within MCD. COMMENTS:
PAGE 13 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT STEP 9: 17 1-M-6 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 17 data collection and determine if Acceptance Criteria are met. 1-U-63-180 Operable, 0 % CNTMT 1-U-63-181 Channel check, 0 % Sump Level 1-U-63-182 and 0 % 1-U-63-183 MCDo::6.0%
0 % Contact SRO \0 consult Tech 1-U-63-50 Operable, 9f> % Specs 1-U-63-51 Channel check, % RWST Level and MCD ( :> 1-U-63-52
% 1-U-63-53
'07.0% 96 % Applicant enters data and determines that CNTMT SUMP channels meet acceptance criteria.
Applicant enters data and determines that 1-L1-63-52, RWST Level channel does NOT meet acceptance criteria.
') EXAMINER'S CUE: If asked about 1-U-63-S2 indication, acknowledge receipt of the information and direct the applicant to complete data taking as assigned.
EXAMINER'S CUE: If asked to review previous shift's SI-2 Data, state that the Unit Supervisor will retrieve data. If pursued further, then say that the Unit Supervisor reviewed data and all instrumentation was within MCD. COMMENTS:
PAGE 13 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam 2 STEP/STANDARD SAT/UNSAT ) 1 ) STEP 10: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference SAT 18 data collection and determine if Acceptance Criteria are met. UNSAT 1-FCV-63-118 OPEN I¥" CL Accum 1 Outlet I (1-HS-63-118A)
CLOSED 1-FCV-63-98 Valves OPEN Contact SRO to CL Accum 2 Outlet (1-HS-63-98A)
Open-wh'en Pzr CLOSED consult 18 I 1-M-6 1-FCV-63-BO pressure OPEN Tech Specs. CL Accum 3 Outlet (1-HS-63-80A)
>1000 psig. CLOSED 1-FCV-63-67 OPEN CL Accum 4 Outlet (1-HS-63-67A)
CLOSED STANDARD:
Applicant enters data and determines that all valves are in their required positions and meet acceptance criteria.
COMMENTS:
PAGE 14 OF 17 STEP 10: 18 1-M-6 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 18 data collection and determine if Acceptance Criteria are met. CL Accum 1 Outlet 1-FCV-63-118 OPEN lit' (1-HS-63-118A)
CLOSED 0 CL Accum 2 Outlet 1-FCV-63-9S Valves OPEN Ii!'" (1-HS-63-98A)
Open-wh'en Pzr CLOSED 0 Contact SRO to consult CL Accum 3 Outlet 1-FCV-63-80 pressure OPEN IiiJ"'" Tech Specs. (1-HS-63-S0A)
>1000 psig. CLOSED 0 CL Accum 4 Outlet 1-FCV-63-67 OPEN rY (1-HS-63-67A)
CLOSED 0 Applicant enters data and determines that all valves are in their required positions and meet acceptance criteria.
COMMENTS:
PAGE 14 OF 17 SAT/UNSAT SAT UNSAT
\ ) STEP 11: WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 4, Reference 19 data collection and determine if Acceptance Criteria are met. Ref I Location I Description I Instrument
T S Limit Data I Acc NOT Met CL Accum 1 1-U-63-129 " 7810 gal Lvi I 1-U-63-1'19
7630 and ,;8000 7f)IO gal CLAccum 2 I i-U-63-109 oal and MCD ,; 96 7el<;" gal Check operability gal. Chemistry is to ' by acceptable Lvi I 1-U-63-99 be notified to , ..
gal deviation between pertorm 1-SI-63-6 gal redundant level and CLAccum 3 I U-63-S9 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months iftank pressure channels Lvi I 1-L1-63-S-J level is increased 2: "'7fJ1O gal when pressurizer 75 gal and tank NOT pressure is above CLAccum4 . L1-63-S2 filled from RWST n) ..., 7810 gal -1000 psig If deviation limit is ,9 I Hvl-6 I Lvi '1-L1-63-60
,. 7810 gal exceeded.
CLAccum 1 1-PI-63-'128
... psig determine the Press i-PI-63-126
.-psig channel inoper-able AND record only CLAccum 2 I I-PI-63-108
.. b4D psig the operable channel. This Press I 1-PI-63-106
6'10 and ,;660 psig 1..(Q1jO pSig channel check is and MCD ,; 30 ' ,. CLAccum 3 1-PI-63-88 psigi') " 1;"1-0 psig NOT a technical Press 1-PI-63-86
,. *('30 psig specification re-quiremenl.
CL Accum4 1-PI-63-62 ... r,40 psig Press 1-PI-63-6'1 p51g STANDARD:
Applicant enters data and determines that all Cold Leg accumulator level and pressure channels meet acceptance criteria.
COMMENTS:
PAGE 15 OF 17 SATIUNSAT SAT UNSAT STEP 11: Ref Location '\9 H,'I-6 ) STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 4, Reference 19 data collection and determine if Acceptance Criteria are met. Description Instrument
T S Limit Data Acc NOT Met CL Accum 1 'I-U-63-129
.. 78/0 gal Lvi 1-U-63-1 '19 ;:,7630 and s8000 .., r7e>IO gal 1-U-63-109 gal and MCD s 96 gal Check operability CLAccum 2 gal Chemistry is to ' by acceptable Lvi 1-U-63-99 be notified to ,
gal deviation between perform 1-SI-63-6
'r>-78(O redundant level and CLAccum 3 'I-U-63-S9 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months iftank
gal pressure channels Lvi 1-U-63-8'1 level is increased
'2:
gal when pressurizer 75 gal and tank NOT pressure is above CLAccum4 'I-U-63-82 filled from RWST O)..., 18/0 gal '1000 psig If cleviation limit is Lvi 'I-U-63-60
'" 78/0 gal exceeded, CLAccum 1 I-PI-63-'128
... 6;,4° psig cletermine the Press 1-PI-53-126 " channel inoper-able psig AND record only CLAccum 2 l-PI-63-'108 fa Ipft> psig theopemble Press 2:6'10 and s660 psig psig channel. This 1-PI-53-106 and IvlCD s 30 ' .. channel check is CLAccum 3 1-PI-63-88 psig Pi .. h"/-O psig NOT a technical Press 1-PI-63-86
.. *('30 psig specification re-Cjuirernent CL Accum4 1-PI-63-62
""'f640 psig Press psig Applicant enters data and determines that all Cold Leg accumulator level and pressure channels meet acceptance criteria.
COMMENTS:
PAGE 15 OF 17 SAT/UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam C) STEP/STANDARD SAT/UNSAT ) I STEP 12: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 4, Reference 20 data collection and determine if Acceptance Criteria are met. l-PDI-30-42
!if Operable, Channel o psig (2) or Point P1000A 0 Check, and MCD of l-PDI-30-43 the following:
o psjg(2) 20 or I CNTMT Press or Point P1001A MCD s; H psig (Ind) Contact SRO to consult T ecrl Specs 1-PDI-30-44 MCD'S 0.8 psig or Point P1002A (mixed) o psig c:} l-PDI-30-45 MCD'S 0.5 psig o psig(2! or Point P1003A 0 (computer)
STANDARD:
Applicant enters data and determines that all channels meet acceptance criteria.
COMMENTS:
END OF TASK STOP TIME __ _ PAGE 16 OF 17 SAT UNSAT ) I STEP 12: WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1*SI*0*2A*03, Data Sheet 1, Page 4, Reference 20 data collection and determine if Acceptance Criteria are met. 1-PDI-30-42 Operable, Channel 0 or Point P 1 OOOA Check, and MCD of psig 2) 1-PDI-30-43 Ill"'" the following:
0 or Point Pi001A 0 psig f2) I-M-6 or MCD :s 1.0 psig (Ind) Contact SRO to 20 ICS CNTMT Press 'IE consult Tech Specs l-PDI-30-44 MCD 5 0.8 psig or Point P1002A 0 (mixed) 0 psig (2) 1-PDI-30-45 rK' MCD:S 0.5 psig 0 or Point P 1003A 0 (cornputer) psig C?\ STANDARD:
Applicant enters data and determines that all channels meet acceptance criteria.
COMMENTS:
END OF TASK STOP TIME __ _ PAGE 16 OF 17 SAT/UNSAT SAT UNSAT APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) ) DIRECTION TO APPLICANT:
/ ) ) 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. The Unit is in Mode 3, with no LCO entries at this time. 2. Portions of the field data have been entered by NAUOs. 3. You are the Unit Operator responsible to perform and review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." INITIATING CUES: 1. You are to complete 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, pages 1 through 4 of 15. Another Unit Operator will complete the remainder of Data Sheet 1. 2. When you have finished performing the assigned pages of Data Sheet 1, and . addressed any deviations, notify the Unit Supervisor that you have completed your task. A.2-1 RO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) ) DIRECTION TO APPLICANT:
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. The Unit is in Mode 3, with no LCO entries at this time. 2. Portions of the field data have been entered by NAUOs. 3. You are the Unit Operator responsible to perform and review 1*SI*0*2A*03, "1900*0700 Shift and Daily Surveillance Log Mode Three." INITIATING CUES: 1. You are to complete 1*SI*0*2A*03, "1900*0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, pages 1 through 4 of 15. Another Unit Operator will complete the remainder of Data Sheet 1. 2. When you have finished performing the assigned pages of Data Sheet 1, and addressed any deviations, notify the Unit Supervisor that you have completed your task. A.2-1 RO
[i!D Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-SI-0-2A-03 1900 -0700 Shift And Daily Surveillance Log Mode Three Revision 0030 Quality Related Level of Use: Continuous Use Effective Date: 03-19-2008 Responsible Organization:
OPS, Operations Prepared By: Scot Newell Approved By: Kathy Keefer Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-SI-0-2A-03 1900 -0700 Shift And Daily Surveillance Log Mode Three Revision 0030 Quality Related Level of Use: Continuous Use Effective Date: 03-19-2008 Responsible Organization:
OPS, Operations Prepared By: Scot Newell Approved By: Kathy Keefer WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 2 of 39 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 26 02/01/06 2,3,14,15 Added additional MCD guidance (PER 74382). 23 Revised Ref. 21 and 22 to reflect Tech Spec change Package WBN-TS-04-17, which contains requirements for opening the penetrations in the Shield Bldg. Dome during Cycle 7 operation.
32 Added 1-FI-90-400 for Shield Building Flow indication.
Added capability to use 1-FI-90-400 in Attachment
1. 27 08/04/06 All This procedure has been converted from Word 95 to Word 2002 XP using rev 26, by Austin Norris. All Changed verify to check or ensure. 7, 9, 18, 36 Moved Freq requirements to Step 1.2.2A. Changed all footnote references to superscript.
Deleted FRP references and footnotes
"", ., and (14) for Step 1.2.2E; PER 74137. Changed step 6.1.M bullets to 6.1.N -P. Changed containment temperature to ICS on Data Sheet 2. 28 10/18/06 2,22, Technical Specification change, WBN-TS-05-06 for Steam Generator secondary side water level. 26 Deleted Notes on Ref 21 and 22 to remove Tech Spec change WBN-TS-04-17, Shield Bldg Hatches. 29 T ACF 1-05-0004-090, RM-90-106
& 112 alert and alarm setpoints returned to normal. 29 09/14/07 2,29 TACF 1-07-0006-090 allows rad monitor aligned to lower containment to have background setpoint adjusted from NE SSD setpoint due to RCS leak inside containment.
30 03/19/08 2,29 Deleted foot note 1 for reference 25 for T ACF 1-07-0006-090 RTN. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 2 of 39 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 26 02/01/06 2,3,14,15 Added additional MCD guidance (PER 74382). 23 Revised Ref. 21 and 22 to reflect Tech Spec change Package WBN-TS-04-17, which contains requirements for opening the penetrations in the Shield Bldg. Dome during Cycle 7 operation.
32 Added 1-FI-90-400 for Shield Building Flow indication.
Added capability to use 1-FI-90-400 in Attachment
1. 27 08/04/06 All This procedure has been converted from Word 95 to Word 2002 XP using rev 26, by Austin Norris. All Changed verify to check or ensure. 7,9, 18,36 Moved Freq requirements to Step 1.2.2A. Changed all footnote references to superscript.
Deleted FRP references and footnotes -To, ., and (14) for Step 1.2.2E; PER 74137. Changed step 6.1.M bullets to 6.1.N -P. Changed containment temperature to ICS on Data Sheet 2. 28 10/18/06 2,22, Technical Specification change, WBN-TS-05-06 for Steam Generator secondary side water level. 26 Deleted Notes on Ref 21 and 22 to remove Tech Spec change WBN-TS-04-17, Shield Bldg Hatches. 29 TACF 1-05-0004-090, RM-90-106
& 112 alert and alarm setpoints returned to normal. 29 09/14/07 2,29 TACF 1-07-0006-090 allows rad monitor aligned to lower containment to have background setpoint adjusted from NE SSD setpoint due to RCS leak inside containment.
30 03/19/08 2,29 Deleted foot note 1 for reference 25 for T ACF 1-07-0006-090 RTN.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 ') Mode Three Page 3 of 39 Table of Contents
1.0 INTRODUCTION
..........................................................................................................
5 1.1 Purpose ........................................................................................................................
5 1.2 Scope ............................................................................................................................
5 1.2.1 Operability Tests to be Performed
..................................................................
5 1.2.2 Surveillance Requirements Fulfilled
................................................................
7 1.3 Frequency and Conditions
..........................................................................................
10 1.3.1 Performance Definitions
................................................................................
10 1.3.2 MCD Calculation Methods ............................................................................
10
2.0 REFERENCES
.....................................................
.....................................................
11 2.1 Performance References
............................................................................................
11 2.2 Developmental References
.........................................................................................
11 2.2.1 TVA Procedures
............................................................................................
11 2.2.2 Vendor Manuals ............................................................................................
12 2.2.3 Other .............................................................................................................
12 3.0 PRECAUTIONS AND LIMITATIONS
.........................................................................
13 4.0 PREREQUISITE ACTIONS ........................................................................................
14 4.1 Preliminary Actions .....................................................................................................
14 4.2 Approvals and Notifications
........................................................................................
14 5.0 ACCEPTANCE CRITERIA .........................................................................................
15 5.1 Test Acceptance Criteria .............................................................................................
15 5.2 Notifications and Actions .............................................................................................
15 6.0 PERFORMANCE
........................................................................................................
16 6.1 Performance Requirements
........................................................................................
16 6.2 GENERAL ...................................................................................................................
19 7.0 POST PERFORMANCE ACTIVITIES
........................................................................
20 8.0 RECORDS ..................................................................................................................
21 8.1 QA Records ................................................................................................................
21 8.2 Non-QA Records ........................................................................................................
21 Data Sheet 1: Mode 3 Surveillance Log: 1900-0700
......................................................
22 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 3 of 39 Table of Contents
1.0 INTRODUCTION
...........................................................................................................
5 1.1 Purpose ........................................................................................................................
5 1.2 Scope ............................................................................................................................
5 1.2.1 Operability Tests to be Performed
..................................................................
5 1.2.2 Surveillance Requirements Fulfilled
................................................................
7 1.3 Frequency and Conditions
..........................................................................................
10 1.3.1 Performance Definitions
................................................................................
10 1.3.2 MCD Calculation Methods ............................................................................
10
2.0 REFERENCES
...........................................................................................................
11 2.1 Performance References
............................................................................................
11 2.2 Developmental References
.........................................................................................
11 2.2.1 TVA Procedures
............................................................................................
11 2.2.2 Vendor Manuals ............................................................................................
12 2.2.3 Other .............................................................................................................
12 3.0 PRECAUTIONS AND LIMITATIONS
.........................................................................
13 4.0 PREREQUISITE ACTIONS ........................................................................................
14 4.1 Preliminary Actions .....................................................................................................
14 4.2 Approvals and Notifications
........................................................................................
14 5.0 ACCEPTANCE CRITERIA .........................................................................................
15 5.1 Test Acceptance Criteria .............................................................................................
15 5.2 Notifications and Actions .............................................................................................
15 6.0 PERFORMANCE
........................................................................................................
16 6.1 Performance Requirements
........................................................................................
16 6.2 GENERAL ...................................................................................................................
19 7.0 POST PERFORMANCE ACTIVITIES
........................................................................
20 8.0 RECORDS ..................................................................................................................
21 8.1 QA Records ................................................................................................................
21 8.2 Non-QA Records ........................................................................................................
21 Data Sheet 1: Mode 3 Surveillance Log: 1900-0700
......................................................
22 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 4 of 39 Table of Contents (continued)
Data Sheet 2: Inoperable Components
...........................................................................
37 Attachment 1: Determining Annulus AP TIS Limit .............. ...........................................
38 Sour:ce Notes .............................................................................................
39 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 4 of 39 Table of Contents (continued)
Data Sheet 2: Inoperable Components
...........................................................................
37 Attachment 1: Determining Annulus ilP TIS Limit ..............
...........................................
38 Source Notes .............................................................................................
39
, WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 5 of 39
1.0 INTRODUCTION
1.1 Purpose This Instruction provides directions for the following:
A. Recording data required by Surveillance Requirements that can be satisfied on a log type data sheet on a shift and daily log. B. Initiation of appropriate actions for abnormal conditions.
1.2 Scope 1.2.1 Operability Tests to be Performed The following verifications are performed by this Instruction:
1. Annulus i1P Channel Checks: a. Annulus to Atmospheric i1P Channel Check. b. Annulus to Containment i1P Channel Check. 2. Condensate Storage Tank (CST) Volume. 3. CNTMT Pressure Channel Check. 4. CNTMT Purge Air Exhaust Channel Check. 5. CNTMT Sump Level Channel Check. 6. CNTMT Radiation Monitor Channel Check. 7. Control Room Air Intake Radiation Monitor Channel Check. 8. Emergency Core Cooling System (ECCS) Channel Checks: a. ECCS subsystems operable.
b. ECCS Cold Leg (CL) Accumulators Isolation Valve Alignment.
c. ECCS CL Accumulators Level Channel Check. d. ECCS CL Accumulators Pressure Channel Check. 9. Fuel Pool Area Radiation Monitor Channel Check. 10. Ice Condenser Door Position Channel Check. \ .1 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 5 of 39
1.0 INTRODUCTION
1.1 Purpose This Instruction provides directions for the following:
A. Recording data required by Surveillance Requirements that can be satisfied on a log type data sheet on a shift and daily log. B. Initiation of appropriate actions for abnormal conditions.
1.2 Scope 1.2.1 Operability Tests to be Performed The following verifications are performed by this Instruction:
1. Annulus Channel Checks: a. Annulus to Atmospheric Channel Check. b. Annulus to Containment Channel Check. 2. Condensate Storage Tank (CST) Volume. 3. CNTMT Pressure Channel Check. 4. CNTMT Purge Air Exhaust Channel Check. 5. CNTMT Sump Level Channel Check. 6. CNTMT Radiation Monitor Channel Check. 7. Control Room Air Intake Radiation Monitor Channel Check. 8. Emergency Core Cooling System (ECCS) Channel Checks: a. ECCS subsystems operable.
b. ECCS Cold Leg (CL) Accumulators Isolation Valve Alignment.
c. ECCS CL Accumulators Level Channel Check. d. ECCS CL Accumulators Pressure Channel Check. 9. Fuel Pool Area Radiation Monitor Channel Check. 10. Ice Condenser Door Position Channel Check.
) ) '" (1) (2) (3) (4) (5) (6) (7) (8) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 7 of 39 -----_ ... -------1.2.2 Surveillance Requirements Fulfilled A. The following designators are used in the "Freq" column: 1 At least once per hour 4 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 8 At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months S Atleast once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months P Completed prior to each release B. Performance of this Instruction satisfies the following Surveillance Requirements (SRs): SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES MODES SR p3.3.1.1-5 2(1),3(2).(3) 2,3,4,5,6 4(2).(3), 5(2).(3) SR p3.3.2.1-1.c 1,2,3 1,2,3 SR p3.3.2.1-1.d 1,2,3(4) 1,2,3 SR p3.3.2.1-1.e 1,2,3(4) 1,2,3 SR p3.3.2.1-2.c 1,2,3 1,2,3 SR p3.3.2.1-3.b.(3) 1,2,3 1,2,3 SR p3.3.2.1-4.c 1,2(5),3(5) 1,2,3 SR p3.3.2.1-4.d.(1) 1, 2(5), 3(4).(5) 1,2,3 SR p3.3.2.1-4.d.(2) 3(5).(6) 3 SR p3.3.2.1-5.b 1 ,2(7), 3(7) 1,2,3 SR p3.3.2.1-6.b 1,2,3 1,2,3 SR p3.3.2.1-7.b 1,2,3,4 1,2,3,4 -SR p3.3.2.1-S.b.(1) 1,2,3 1,2,3 SR p3.3.2.1-S.b.(2) 1,2,3 1,2,3 Ref Freq S S 20 S 10 S 4 S 20 S 20 S 20 S 4 S 4 S 5 S 5 S 17 S 10 -S 10 S The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. -Below the P-6 (Intermediate Range Neutron Flux) interlocks.
With RTBs closed and Rod Control System capable of rod withdrawal.
With RTBs open. In this condition.
source range function does NOT provide reactor trip but does provide indication.
Above P-11 (Pressurizer Pressure) interlock.
Except when all MSIVs are closed & deactivated.
Function automatically blocked above P-11 (Pressurizer Interlock) setpoint and is enabled below P-1'1 when safety injection on Steam Line Pressure Low is manually blocked. Except when all MFIVs, MFRVs, and their bypass valves are closed and deactivated or isolated by a closed manual valve. NOT Used. (1) (2) (3) (4) (5) (6) (7) (8) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 7 of 39 1.2.2 Surveillance Requirements Fulfilled A. The following designators are used in the "Freq" column: 1 At least once per hour 4 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 8 At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months o At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months P Completed prior to each release B. Performance of this Instruction satisfies the following Surveillance Requirements (SRs): SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES MODES SR p3.3.1.1-5 2(1),3(2),(3) 2,3,4,5,6 4 (2),(3), 5(2),(3) SR p3.3.2.1-1.c 1,2,3 1,2,3 SR p3.3.2.1-1.d 1,2,3(4) 1,2,3 SR p3.3.2.1-1.e 1,2,3(4) 1,2,3 SR p3.3.2.1-2.c 1,2,3 1,2,3 SR p3.3.2.1-3.b.(3) 1,2,3 1,2,3 SR p3.3.2.1-4.c 1,2(5),3(5) 1,2,3 SR p3.3.2.1-4.d.(1) 1, 2(5), 3(4),(5) 1,2,3 SR p3.3.2.1-4.d.(2) 3(5),(6) 3 SR p3.3.2.1-5.b 1 ,2(7), 3(7) 1,2,3 SR p3.3.2.1-6.b 1,2,3 1,2,3 SR p3.3.2.1-7.b 1,2,3,4 1,2,3,4 . SR p3.3.2.1-B.b.(1) 1,2,3 1,2,3 SR p3.3.2.1-B.b.(2) 1,2,3 1,2,3 Ref Freq B S 20 S 10 S 4 S 20 S 20 S 20 S 4 S 4 S 5 S 5 S 17 S 10 S 10 S The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSO) is used instead of the Tech Spec value. Below the P-6 (Intermediate Range Neutron Flux) interlocks.
With RTBs closed and Rod Control System capable of rod withdrawal.
With RTBs open. In this condition, source range function does NOT provide reactor trip but does provide indication.
Above P-11 (Pressurizer Pressure) interlock.
Except when all MSIVs are closed & deactivated.
Function automatically blocked above P-11 (Pressurizer Interlock) setpoint and is enabled below P-11 when safety injection on Steam Line Pressure Low is manually blocked. Except when all MFIVs, MFRVs, and their bypass valves are closed and deactivated or isolated by a closed manual valve. NOT Used.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 ) Mode Three Page 8 of 39 1.2.2 Surveillance Requirements Fulfilled (continued)
SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES Ref Freq MODES SR p3.3.6.1-3 1,2,3,4(9) 1,2,3,4,5,6 29 S SR p3.3.7.1-2 All (10) All 27 S SR p3.3.8.1-2 All (11) All (11) 26 S SR p3.4.9.1 oTo 1,2,3 1,2,3 9 S SR p3.4.15.1 1,2,3,4 1,2,3,4 25 S SR p3.4.5.1 3 3 15 S SR p3.4.5.20T0 3 3 5 S SR p3.5.1.1 1,2,3(12) 1,2,3 18 S i SR p3.5.1.2 1,2,3(12) 1,2,3 19 S SR p3.5.1.3 1,2,3(12) 1,2,3 19 S SR p3.5.2.1 1,2,3 1,2,3 16 S SR p3.6.4.1 oTo 1,2,3,4 1,2,3,4 21 S SR p3.6.11.1 oTo 1,2,3,4 1,2,3,4 24 S ) SR p3.6.12.1 1,2,3,4 1,2,3,4 23 S SR p3.6.15.1 oTo 1,2,3;4 1,2,3,4 22 S SR p3.7.6.1 1,2,3,4(13) 1,2,3,4 3 S LCO p3.6.12 Action B.1 1,2,3,4 1,2,3,4 24 4 LCO p3.7.6 Action A1 1,2,3,4(13) 1,2,3,4 3 4&S "" The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. (9) During movement of irradiated fuel assemblies wIthin containment.
(10) Required in Modes 1 through 6, AND during movement of irradiated fuel assemblies.
(11) During movement of irradiated fuel assemblies within the fuel handling area. (12) With pressurizer pressure greater than 1000 psig. (13) When steam generator is relied upon for heat removal. ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 8 of 39 1.2.2 Surveillance Requirements Fulfilled (continued)
SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES Ref Freq MODES SR p3.3.6.1-3 1,2,3,4(9) 1,2,3,4,5,6 29 S SR p3.3.7.1-2 All (10) All 27 S SR p3.3.8.1-2 All (11) All (11) 26 S SR p3.4.9.1 ofo 1,2,3 1,2,3 9 S SR p3.4.15.1 1,2,3,4 1,2,3,4 25 S SR p3.4.5.1 3 3 15 S SR p3.4.5.20f0 3 3 5 S SRp3.5.1.1 1,2,3(12) 1,2,3 18 S SR p3.5.1.2 1,2,3(12) 1,2,3 19 S SR p3.5.1.3 1,2,3(12) 1,2,3 19 S SR p3.5.2.1 1,2,3 1,2,3 16 S SR p3.6.4.1 ofo 1,2,3,4 1,2,3,4 21 S SR p3.6.11.1 ofo 1,2,3,4 1,2,3,4 24 S SR p3.6.12.1 1,2,3,4 1,2,3,4 23 S SR p3.6.15.10f0 1,2,3,4 1,2,3,4 22 S SR p3.7.6.1 1,2,3,4(13) 1,2,3,4 3 S LCO p3.6.12 Action B.1 1,2,3,4 1,2,3,4 24 4 LCO p3.7.6 Action A1 1,2,3,4(13) 1,2,3,4 3 4&S '" The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. (9) During movement of irradiated fuel assemblies within containment.
(10) Required in Modes 1 through 6, AND during movement of irradiated fuel assemblies.
(11) During movement of irradiated fuel assemblies within the fuel handling area. (12) With pressurizer pressure greater than 1000 psig. (13) When steam generator is relied upon for heat removal.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 9 of 39 1.2.2 Surveillance Requirements Fulfilled (continued)
C. Performance of this Instruction satisfies or partially (p) satisfies the following Technical Surveillance Requirements (TSR): SURVEILLANCE APPLICABLE PERFORMANCE MODES Ref REQUIREMENTS MODES TSR p3.1.2.1 1,2,3 1,2,3 65 TSR p3.6.1.1 '" 1 ,2,3,4 1 ,2,3,4 24 TSR p3.6.2.1 1,2,3,4 1,2,3,4 23 TSR p3.6.2.3 1,2,3,4 1,2,3,4 23 TSR p3.7.5.1 All All 65 TR p3.6.1 Action B.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.3 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.2 Action A.1 1,2,3,4 1,2,3,4 24 ... The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used* instead of the Tech Spec value. Freq S S S S S 1&S 1 1&S 1&S 1 4 D. Performance of this Instruction satisfies the following Offsite Dose Calculation Manual Surveillance Requirements (OSRs): ODCM SURVEILLANCE APPLICABLE MODES PERFORMANCE MODES Ref REQUIREMENTS OSR p2.1.2-3.f All (20) AII(2O) OSR p2.1.2-4.e All All (20) Both Unit 1 and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement.
59 59 E. Fulfillment of special conditions will initiate the following requirements:
SURVEILLANCE REQUIREMENTS APPLICABLE MODES PERFORMANCE MODES TR p3.6.1 Action A.1 1,2,3,4 1,2,3,4 Freq D D Freq S WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 9 of 39 1.2.2 Surveillance Requirements Fulfilled (continued)
C. Performance of this Instruction satisfies or partially (p) satisfies the following Technical Surveillance Requirements (TSR): SURVEILLANCE APPLICABLE PERFORMANCE MODES Ref REQUIREMENTS MODES TSR p3.1.2.1 1,2,3 1,2,3 65 TSR p3.6.1.10f0 1,2,3,4 1,2,3,4 24 TSR p3.6.2.1 1,2,3,4 1,2,3,4 23 TSR p3.6.2.3 1,2,3,4 1,2,3,4 23 TSR p3.7.5.1 All All 65 TR p3.6.1 Action B.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.3 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.2 Action A.1 1,2,3,4 1,2,3,4 24 "" The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSO) is used' instead of the Tech Spec value. Freq S S S S S 1&S 1 1&S 1&S 1 4 D. Performance of this Instruction satisfies the following Offsite Dose Calculation Manual Surveillance Requirements (OSRs): ODCM SURVEILLANCE APPLICABLE MODES PERFORMANCE MODES Ref REQUIREMENTS OSR p2.1.2-3.f AII(2O) AII(2O) OSR p2.1.2-4.e All All (20) Both Unit 1 and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement.
59 59 E. Fulfillment of special conditions will initiate the following requirements:
SURVEILLANCE REQUIREMENTS APPLICABLE MODES PERFORMANCE MODES Ref TR p3.6.1 Action A.1 1,2,3,4 1,2,3,4 24 Freq 0 0 Freq S
) WBN 1900*0700 1*SI*0*2A*03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 10 of 39 1.3 Frequency and Conditions A. This Instruction is to be performed every 1900 -0700 shift when unit is in Mode 3. This instruction should be performed in Mode 4 prior to Mode 3 entry to ensure Mode 3 requirements are met. 1.3.1 Performance Definitions A. Channel Check* The qualitative assessment by observation of channel behavior during operation.
This determination includes, where possible, comparison of the channel indication and status with other indications or status derived from independent instrument channels measuring the same parameter.
B. Maximum Channel Deviation (MCD) -The difference between the highest channel indication of a parameter and the lowest channel indication of the same parameter.
MCD units are the same as the applicable measured parameter units unless otherwise stated in applicable requirement.
If deviation limit is exceeded, determine which channel is inoperable AND Record only the operable channel unless stated otherwise.
Instrument Maintenance/Engineering shall assist in determining if operability limits have been exceeded.
C. Operable or Operability*
A system, subsystem, train, component, or device is operable or has operability when it is capable of performing its speCified function(s) and when all necessary attendant instrumentation, controls, electrical power (normal or emergency), cooling, and seal water, lubrication, or other auxiliary equipment required for the system, subsystem, train, component, or device to perform its specified function(s) is also capable of performing its related support function(s).
1.3.2 MCD Calculation Methods See 1-SI-0-2-00 for explanation of MCD Calculations.
WBN 1900 -0700 1-SI-0-2A-03 Unit1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 10 of 39 1.3 Frequency and Conditions A. This Instruction is to be performed every 1900 -0700 shift when unit is in Mode 3. This instruction should be performed in Mode 4 prior to Mode 3 entry to ensure Mode 3 requirements are met. 1.3.1 Performance Definitions A. Channel Check -The qualitative assessment by observation of channel behavior during operation.
This determination includes, where possible, comparison of the channel indication and status with other indications or status derived from independent instrument channels measuring the same parameter.
B. Maximum Channel Deviation (MCD) -The difference between the highest channel indication of a parameter and the lowest channel indication of the same parameter.
MCD units are the same as the applicable measured parameter units unless otherwise stated in applicable requirement.
If deviation limit is exceeded, determine which channel is inoperable AND Record only the operable channel unless stated otherwise.
Instrument Maintenance/Engineering shall assist in determining if operability limits have been exceeded.
C. Operable or Operability -A system, subsystem, train, component, or device is operable or has operability when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electrical power (normal or emergency), cooling, and seal water, lubrication, or other auxiliary equipment required for the system, subsystem, train, component, or device to perform its specified function(s) is also capable of performing its related support function(s).
1.3.2 MCD Calculation Methods See 1-SI-0-2-00 for explanation of MCD Calculations.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 11 of 39
2.0 REFERENCES
2.1 Performance References . A. Core Operating Limits Report. B. Nuclear Operating Book (NOB), 1. Sheet A-1, Target Band VS Power Level. 2. Sheet A-5, Negative MTC Withdrawal Limit Curve. C. SOI-90.02, Gaseous Process Radiation Monitors.
2.2 Developmental References 2.2.1 TVA Procedures A. 1-0DI-90-2, Steam Generator Blowdown Release B. 1-0DI-90-25, Condenser Vacuum Exhaust Release. C. 1-SI-63-6, Cold Leg Accumulators Boron Determination.
D. 1-SI-68-25, Recalibration of Channell Reactor Coolant System Flow Loops. E. 1-SI-68-26, Recalibration of Channel II Reactor Coolant System Flow Loops. F. 1-SI-68-27, Recalibration of Channel III Reactor Coolant System Flow Loops. G. 1-SI-68-31, Reactor Coolant System Total Flow Measurement.
H. 1-SI-68-32, Reactor Coolant System Water Inventory Balance. I. 1-SI-68-68, 18 Month Channel Calibration RCS Loop 1 Wide Range Hot Leg Temperature Loop 1-LPT-68-1 (T-413A).
J. 1-SI-90-25, Inoperable Lower Containment Radiation Monitor. K. ECI-1.0, NPDES Plant Effluents.
L. Backup Ice Condenser Temperature Monitoring.
i I ! WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 11 of 39
2.0 REFERENCES
2.1 Performance References A. Core Operating Limits Report. B. Nuclear Operating Book (NOB), 1. Sheet A-1, Target Band VS Power Level. 2. Sheet A-5, Negative MTC Withdrawal Limit CUNeo C. SOI-90.02, Gaseous Process Radiation Monitors.
2.2 Developmental References 2.2.1 TVA Procedures A. B. C. D. E. F. G. H. I. J. K. L. 1-001-90-2, Steam Generator Blowdown Release 1-001-90-25, Condenser Vacuum Exhaust Release. 1-SI-63-6, Cold Leg Accumulators Boron Determination.
1-SI-68-25, Recalibration of Channel I Reactor Coolant System Flow Loops. 1-SI-68-26, Recalibration of Channel II Reactor Coolant System Flow Loops. 1-SI-68-27, Recalibration of Channel III Reactor Coolant System Flow Loops. 1-SI-68-31, Reactor Coolant System Total Flow Measurement.
1-SI-68-32, Reactor Coolant System Water Inventory Balance. 1-SI-68-68, 18 Month Channel Calibration RCS Loop 1 Wide Range Hot Leg Temperature Loop 1-LPT-68-1 (T-413A).
1-SI-90-25, Inoperable Lower Containment Radiation Monitor. ECI-1.0, NPDES Plant Effluents.
Backup Ice Condenser Temperature Monitoring.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 12 of 39 ---_ .. _------2.2.1 TVA Procedures (continued)
M. Offsite Dose Calculation Manual (ODCM). N. SOI-14.o.3, Condensate Demineralizer Waste Disposal.
O. SOI-1S.o.1, Steam Generator Blowdown (SGBD) System. P. SOI-77.o.1, Liquid Waste Disposal.
2.2.2 Vendor Manuals A. VM-o.74S, Vendor (Technical)
Manual for Tracor Westronics Equipment.
B. VM-o.16S, Vendor (Technical)
Manual for Loose Parts Monitoring System. 2.2.3 Other NOTE Setpoint and Scaling Documents referenced for Technical Specification Operability Limit clarification.
A. Fire Protection Report, Part II, Fire Protection Plan, Section 14.1. B. II-S-92-o.11 R1, Indicated Low Reactor Coolant System Flow. (TROIID: SQN II-S-92-o.11 R 1). C. N3-61-4o.o.1, System Description for the Ice Condenser System. D. Nuclear Operating Book (NOB), Sheet A-S. E. 1-4SW-6o.S-242, Electrical Tech Spec Compliance Tables. F. 1-4SW-6o.S-;243; Electrical Tech Spec Compliance Tables. G. SOPER93o.138, Generic Applicability to Watts Bar Steam Generator PressurelTemperature Limitations SON LCO 3.7.2IWBN TR 3.7.1. H. Unit 1 Technical Requirements Manual 3. f2.1, 3.6.1, 3.6.2, 3.7.1.
I. Unit 1 Technical Specification 3.1.S, 3.1.6, 3.1.7, 3.3.1,3.3.2,3.3.6, 3.3.7, 3.3.8, 3.4.1,3.4.4,3.4.9, 3.4.1S, 3.S.1, 3.S.2, 3.6.4, 3.6.11, 3.6.12, 3.6.1S, 3.7.6. J. LER 97-0.13 DIG Operability with DIG exhaust or panel fan out of service. K. Annulus Differential Pressure Analysis, RIMS number T69 o.So.321 0.0.3. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 12 of 39 2.2.1 TVA Procedures (continued)
M. Offsite Dose Calculation Manual (ODCM). N. SOI-14.03, Condensate Demineralizer Waste Disposal.
O. SOI-15.01, Steam Generator Blowdown (SGBD) System. P. SOI-77.01, Liquid Waste Disposal.
2.2.2 Vendor Manuals A. VM-0745, Vendor (Technical)
Manual for Tracor Westronics Equipment.
B. VM-0165, Vendor (Technical)
Manual for Loose Parts Monitoring System. 2.2.3 Other NOTE Setpoint and Scaling Documents referenced for Technical Specification Operability Limit clarification.
A. Fire Protection Report, Part II, Fire Protection Plan, Section 14.1. B. II-S-92-011 R1, Indicated Low Reactor Coolant System Flow. (TROI 10: SON II-S-92-011 R1). C. N3-61-4001, System Description for the Ice Condenser System. D. Nuclear Operating Book (NOB), Sheet A-5. E. 1-45W-605-242, Electrical Tech Spec Compliance Tables. F. 1-45W-605-243; Electrical Tech Spec Compliance Tables. G. SOPER930138, Generic Applicability to Watts Bar Steam Generator PressurelTemperature Limitations SON LCO 3.7.2IWBN TR 3.7.1. H. Unit 1 Technical Requirements Manual 3.1.2.1,3.6.1, 3.6.2,3.7.1.
I. Unit 1 Technical Specification 3.1.5, 3.1.6, 3.1.7, 3.3.1,3.3.2, 3.3.6, 3.3.7, 3.3.8, 3.4.1, 3.4.4, 3.4.9, 3.4.15, 3.5.1, 3.5.2, 3.6.4, 3.6.11, 3.6.12, 3.6.15, 3.7.6. J. LER 97-013 DIG Operability with DIG exhaust or panel fan out of service. K. Annulus Differential Pressure Analysis, RIMS number T69 050321 003.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 13 of 39 3.0 PRECAUTIONS AND LIMITATIONS A. When BOTH a radiation monitor and recorder are listed, checking the recorder does NOT satisfy the Tech Spec requirement.
The monitor must be read to satisfy the requirement.
\) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 13 of 39 3.0 PRECAUTIONS AND LIMITATIONS A. When BOTH a radiation monitor and recorder are listed, checking the recorder does NOT satisfy the Tech Spec requirement.
The monitor must be read to satisfy the requirement.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 14 of 39 Date __ _ Page, __ _ 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions [1] RECORD start date and time on Surveillance Task Sheet. [2] IF required, THEN OBTAIN RWP. 4,2 Approvals and Notifications
[1] OBTAIN SM/Unit SRO approval on the Surveillance Task Sheet to perform this Instruction.
of __ _ WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 14 of 39 Date __ _ Page __ _ 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions [1] RECORD start date and time on Surveillance Task Sheet. [2] IF required, THEN OBTAIN RWP. 4.2 Approvals and Notifications
[1] OBTAIN SM/Unit SRO approval on the Surveillance Task Sheet to perform this Instruction.
of __ _
'\ WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 15 of 39 5.0 ACCEPTANCE CRITERIA 5.1 Test Acceptance Criteria A. Specific quantitative or qualitative requirements that are intended to be checked by this Instruction are listed by each item where the data is recorded.
B. All data must be completed within four hours of shift relief to ensure 1.25 frequency is met. 5.2 Notifications and Actions A. Noncompliance with Acceptance Criteria requires Unit SRO notification as soon as safely possible.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 15 of 39 5.0 ACCEPTANCE CRITERIA 5.1 Test Acceptance Criteria A. Specific quantitative or qualitative requirements that are intended to be checked by this Instruction are listed by each item where the data is recorded.
B. All data must be completed within four hours of shift relief to ensure 1.25 frequency is met. 5.2 Notifications and Actions A. Noncompliance with Acceptance Criteria requires Unit SRO notification as soon as safely possible.
') ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 16 of 39 6.0 PERFORMANCE 6.1 Performance Requirements . A. Prior to making any mode changes which are more restrictive, review of the shift and daily data sheets is required to ensure compliance with applicable surveillance requirements for that mode. Starting new data sheets for the appropriate mode must be considered.
B. To meet MCD limits, data for individual instrument channels are required to be compared for deviation.
C. Items that require channel check that do NOT have an MCD listed in Tech Spec Limits column are to be considered acceptable when the following requirements are met: 1. Equipment is energized.
2. Indication is reading a value consistent with present plant conditions. (For radiation monitors, indication must be reading at least background.)
D. Exceeding the MCD column limits when performing Channel Checks may require considering the channel(s) inoperable unless stated otherwise.
Contact Instrument Maintenance/Engineering for operability determination.
E. Ensure meters are read consistently from same angle. Use gage face mirrors (if present) and ensure gage needle and its reflection are in alignment.
If gage . has no mirror in the face, read gage from as close to perpendicular to .gage face as possible.
F. Pegged High or Low meters: 1. If a meter indication is pegged high (or pegged low), a defensible channel deviation cannot be determined because of the uncertainty of the parameter being measured -the value could actually be greater (or less than) the pegged high or pegged low value. 2. In order for potential problems to be identified early, if the meter approaches to within two meter divisions of full scale high (or low), the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken. 3. For any meter pegged high or low, ensure a WO is initiated.
The operability of this meter and any alarm, control, or protective functions of the associated loop should also be evaluated.
G. In order for potential problemsto be identified early, if any channel deviation exceeds 80% of the MCD limit, the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 16 of 39 6.0 PERFORMANCE 6.1 Performance Requirements A. Prior to making any mode changes which are more restrictive, review of the shift and daily data sheets is required to ensure compliance with applicable surveillance requirements for that mode. Starting new data sheets for the appropriate mode must be considered.
B. To meet MCD limits, data for individual instrument channels are required to be compared for deviation.
C. Items that require channel check that do NOT have an MCD listed in Tech Spec Limits column are to be considered acceptable when the following requirements are met: 1. Equipment is energized.
2. Indication is reading a value consistent with present plant conditions. (For radiation monitors, indication must be reading at least background.)
D. Exceeding the MCD column limits when performing Channel Checks may require considering the channel(s) inoperable unless stated otherwise.
Contact Instrument Maintenance/Engineering for operability determination.
E. Ensure meters are read consistently from same angle. Use gage face mirrors (if present) and ensure gage needle and its reflection are in alignment.
If gage has no mirror in the face, read gage from as close to perpendicular to gage face as possible.
F. Pegged High or Low meters: 1. If a meter indication is pegged high (or pegged low), a defensible channel deviation cannot be determined because of the uncertainty of the parameter being measured -the value could actually be greater (or less than) the pegged high or pegged low value. 2. In order for potential problems to be identified early, if the meter approaches to within two meter divisions of full scale high (or low), the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken. 3. For any meter pegged high or low, ensure a WO is initiated.
The operability of this meter and any alarm, control, or protective functions of the associated loop should also be evaluated.
G. In order for potential problems to be identified early, if any channel deviation exceeds 80% of the MCD limit, the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 17 of 39 6.1 Performance Requirements (continued)
H. Any work orders generated during performance of Data Sheets require documentation in Remarks at the bottom of the appropriate data sheet. I. Inoperable instruments are required to have entered in the appropriate data space. J. Data spaces for instruments in modes which do NOT apply can have N/A entered in them. K. The following are guidelines for radiation monitors and recorders:
CAUTION When source checking to determine operability, care should be used to prevent actuation of any high level trip or isolation function initiated by a radiation monitor. 1. Radiation levels are to be compared to data taken on the previous shift. 2. Any questionable monitor may be source checked to aid in determining operability.
A slight deflection of the indicator is all that is necessary to confirm source check response.
3. A radiation monitoring channel is to be considered operable if it responds to a source check, monitor is in service, and instrument malfunction annunciation due to low flow is clear. 4. Radiation recorders are to be considered operable if operating properly, inking clearly, legible, and running on time. 5. If gas or particulate sampler flow rotameter is inoperable, the respective monitor is also inoperable.
6. Inoperable instruments are to be reported to SRO. 7. Chemistry is to be notified as follows: a. If a monitor is inoperable and a release is being made via this pathway, Chemistry is to be notified to perform applicable 001 until monitor is declared operable.
b. If a conditional SI is required, Chemistry is to be notified to perform appropriate SI. 8. Tech Specs are to be referenced for applicable actions. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 17 of 39 6.1 Performance Requirements (continued)
H. Any work orders generated during performance of Data Sheets require documentation in Remarks at the bottom of the appropriate data sheet. I. Inoperable instruments are required to have INOP entered in the appropriate data space. J. Data spaces for instruments in modes which do NOT apply can have N/A entered in them. K. The following are guidelines for radiation monitors and recorders:
CAUTION When source checking to determine operability, care should be used to prevent actuation of any high level trip or isolation function initiated by a radiation monitor. 1. Radiation levels are to be compared to data taken on the previous shift. 2. Any questionable monitor may be source checked to aid in determining operability.
A slight deflection of the indicator is all that is necessary to confirm source check response.
3. A radiation monitoring channel is to be considered operable if it responds to a source check, monitor is in service, and instrument malfunction annunciation due to low flow is clear. 4. Radiation recorders are to be considered operable if operating properly, inking clearly, legible, and running on time. 5. If gas or particulate sampler flow rotameter is inoperable, the respective monitor is also inoperable.
6. Inoperable instruments are to be reported to SRO. 7. Chemistry is to be notified as follows: a. If a monitor is inoperable and a release is being made via this pathway, Chemistry is to be notified to perform applicable 001 until monitor is declared operable.
b. If a conditional SI is required, Chemistry is to be notified to perform appropriate SI. 8. Tech Specs are to be referenced for applicable actions.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 18 of 39 6.1 Performance Requirements (continued)
9. A WO is to be initiated and the WO number noted in Remarks. 10. The applicable Inoperable Radiation Monitor/Recorder Data Table, is to be completed for inoperable monitor(s) or recorder(s).
L. The following are guidelines for inoperable flow rate measuring devices 1. SRO is to be notified that device is inoperable.
2. A Work Order to have flow rate measuring device repaired is to be initiated and WO number recorded in Remarks. 3. Applicable tracking data sheet is to be completed.
4. Original date and time flow rate device was declared inoperable is to be recorded on each day's data sheet so the 30 day time limit for inoperable monitors is NOT exceeded.
5. Chemistry is to be notified as follows: a. If an iodine sampler flow rotameter is inoperable and requires a portable sampler in accordance with the ODCM, Chemistry is to be notified to install a temporary backup sampler AND perform applicable 001. b. If a special SI is required, Chemistry is to be notified to perform appropriate SI. 6. If a flow rate device is declared inoperable, readings for flow rate devices are to be recorded on applicable Inoperable FlowRate Measuring Device Data Table every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . M. M&TE (Measuring and Test Equipment) may be substituted for installed permanent plant instrumentation as long as the M& TE is at least as accurate as the permanent plant instrumentation.
N. M&TE to be installed and removed by WO (or TACF), which shall also configure valves to place M& TE in-service (or out-of-service).
O. Evaluate LCO entry whenever connecting/disconnecting M&TE or whenever M&TE is aligned to plant systems or left unattended.
LCO entry may NOT be required if the M&TE is installed as a TACF per SPP-9.5. P. Document the M&TE substitution, including the WO number (or TACF number) and M&TE 10 number on the appropriate data sheet in the remarks section. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 18 of 39 6.1 Performance Requirements (continued)
9. A WO is to be initiated and the WO number noted in Remarks. 10. The applicable Inoperable Radiation Monitor/Recorder Data Table, is to be completed for inoperable monitor(s) or recorder(s).
L. The following are guidelines for inoperable flow rate measuring devices 1. 8RO is to be notified that device is inoperable.
2. A Work Order to have flow rate measuring device repaired is to be initiated and WO number recorded in Remarks. 3. Applicable tracking data sheet is to be completed.
4. Original date and time flow rate device was declared inoperable is to be recorded on each day's data sheet so the 30 day time limit for inoperable monitors is NOT exceeded.
5. Chemistry is to be notified as follows: a. If an iodine sampler flow rotameter is inoperable and requires a portable sampler in accordance with the ODCM, Chemistry is to be notified to install a temporary backup sampler AND perform applicable 001. b. If a special 81 is required, Chemistry is to be notified to perform appropriate
81. 6. If a flow rate device is declared inoperable, readings for flow rate devices are to be recorded on applicable Inoperable Flow Rate Measuring Device Data Table every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . M. M&TE (Measuring and Test Equipment) may be substituted for installed permanent plant instrumentation as long as the M& TE is at least as accurate as the permanent plant instrumentation.
N. M&TE to be installed and removed by WO (or TACF), which shall also configure valves to place M& TE in-service (or out-of-service).
O. Evaluate LCO entry whenever connecting/disconnecting M&TE or whenever M& TE is aligned to plant systems or left unattended.
LCO entry may NOT be required if the M&TE is installed as a TACF per 8PP-9.5. P. Document the M&TE substitution, including the WO number (or TACF number) and M&TE 10 number on the appropriate data sheet in the remarks section.
) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 19 of 39 Date ----Page ___ _ of ----6.2 GENERAL [1] ENSURE prerequisite actions in Section 4.0 have been met. NOTE Information on specific items in the data sheets is contained in 1-SI-0-2-00 reference appendix with an associated reference number. [2] PERFORM Data Sheet 1 & 2. [3] ENSURE Data Sheet 1 & 2 have been completed and Acceptance Criteria reviewed within four hours of assuming shift. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 19 of 39 Date ----Page ___ _ of ___ _ 6.2 GENERAL [1] ENSURE prerequisite actions in Section 4.0 have been met. NOTE Information on specific items in the data sheets is contained in 1-SI-0-2-00 reference appendix with an associated reference number. [2] PERFORM Data Sheet 1 & 2. [3] ENSURE Data Sheet 1 & 2 have been completed and Acceptance Criteria reviewed within four hours of assuming shift.
\) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 20 of 39 Date __ _ Page __ _ 7.0 POST PERFORMANCE ACTIVITIES
[1] ENSURE all Acceptance Criteria have been met OR appropriate corrective action has been taken. [2] NOTIFY SM/Unit SRO that this Instruction is complete.
[3] PRESENT completed data sheets for SRO review. [4] RECORD completion date and time on Surveillance Task Sheet. of ---WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 20 of 39 Date __ _ Page __ _ 7.0 POST PERFORMANCE ACTIVITIES
[1] ENSURE all Acceptance Criteria have been met OR appropriate corrective action has been taken. [2] NOTIFY SM/Unit SRO that this Instruction is complete.
[3] PRESENT completed data sheets for SRO review. [4] RECORD completion date and time on Surveillance Task Sheet. of __ _
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 21 of 39 8.0 RECORDS 8.1 QARecords The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
Completed Data Package. 8.2 Non-QA Records None WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 21 of 39 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
Completed Data Package. 8.2 Non-QA Records None
) WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log ------------
Mode Three Data Sheet 1 (Page 1 of 15) 1-SI-0-2A-03 Rev. 0030 Page 22 of 39 Mode 3 Surveillance Log: 1900-0700 Date __ _ Page, __ _ I Ref I Location I Description I Instrument
T S Limit Data 1-M-2 3 PnI0-L-209 T15M1708 4 1-M-4 5 1-M-4 1-U-2-230A D ;::: 200,000 CST A Level OR gallons 1-U-2-230B D 1-PI-1-2A SG 1 Press 1-PI-1-2B 1-PI-1-5 1-PI-1-9A SG 2 Press 1-PI-1-9B Operable, 1-PI-1-12 Channel Check, and 1-PI-1-20A MCD 90 SG 3 Press 1-PI-1-20B psig 1-PI-1-23 1-PI-1-27A SG 4 Press 1-PI-1-27B 1-PI-1-30 1-U-3-42 SG 1 Level 1-U-3-39 1-U-3-38 1-U-3-55 Operable at SG 2 Level 1-U-3-52 ;::: 32% NR [for 1-U-3-51 OPERABLE 1-U-3-97 loops], Channel SG 3 Level 1-U-3-94 Check,and 1-U-3-93 1-U-3-110 SG 4 Level 1-U-3-107 1-U-3-106 Initials INDICATE acc met OR action in "Ace not Met" column initiated.
gallons psig psig psig psig psig psig psig psig psig psig psig psig %
% % °ia % % % % % %
%
% Performer's Initials of ---Acc NOT Met Perform Data Sheet 3 of 1-SI-0-2-00 "CST Level" Contact SRO to consult Tech Specs, Contact SRO to consult Tech Specs, SRO's Initials Remarks: ____________________________________ __________________________________
__ WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 1 of 15) 1-SI-0-2A-03 Rev. 0030 Page 22 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page ___ _ I Ref I Location I Description Instrument
T 5 Limit Data 1-M-2 1-LJ-2-230A D 3 PnI0-L-209 CST A Level OR 200,000 T15M/708 1-LJ-2-230B D gallons gallons 1-PI-1-2A psig SG 1 Press 1-PI-1-2B psig 1-PI-1-5 psig 1-PI-1-9A psig SG 2 Press 1-PI-1-9B Operable, psig 1-PI-1-12 Channel psig 4 1-M-4 Check, and 1-PI-1-20A MCD::; 90 psig SG 3 Press 1-PI-1-20B psig psig 1-PI-1-23 psig 1-PI-1-27A psig SG 4 Press 1-PI-1-27B psig 1-PI-1-30 psig 1-LJ-3-42
% SG 1 Level 1-LJ-3-39
% 1-LJ-3-38
% 1-LJ-3-55 Operable at °io SG 2 Level 1-LJ-3-52 32% NR [for % 5 1-M-4 Remarks: 1-LJ-3-51 OPERABLE loops], 1-LJ-3-97 Channel SG 3 Level 1-LJ-3-94 Check, and 1-LJ-3-93 MCD::;6"0%
1-LJ-3-110 SG 4 Level 1-LJ-3-107 1-LJ-3-106 Initials INDICATE acc met OR action in "Ace not Met" column initiated" % % % % % % % Performer's Initials of ___ _ Acc NOT Met Perform Data Sheet 3 of 1-SI-0-2-00 "CST Level" Contact SRO to consult Tech Specs" Contact SRO to consult Tech Specs" SRO's Initials Ref 8 9 10 15 ) Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 2 of 15) 1-SI-0-2A-03 Rev. 0030 Page 23 of 39 Mode 3 Surveillance Log: 1900-0700 Date ---Page, __ _ of __ _ Location Description Instrument
T S Limit Operable, Channel Check, and MCD SR Neutron 1-NI-92-131A value is plus or minus Mon CH I 1/2 decade [0:3CR1 <CR2 1-M-4 <3.0CR1].
Reading should be the SR Neutron 1-N 1-92-132A average value Mon CH II observed over a 30 second period 1-Ll-68-339A Operable, less than or 1-M-4 PZR Level 1-Ll-68-335A equal to80%, ChannelCheck,and 1-Ll-68-320 MCD:S:6.0%
1-PI-68-340A Operable 1-PI-68-334 channel check, 1-M-5 PZR Press greater than or equal 1-PI-68-323 to 2214psig and 1-PI-68-322 MCD:s: 55 psig. RCS Loops RCP Status 1,2,3,4 RCP 1 1-HS-68-8AA Two loops operable; 1-HS-68-8SA two loops in operation 1-M-5 1-HS-68-31 AA if capable of rod RCP2 withdrawal (one loop if 1-H S-68-31 SA NOT) RCP3 1-HS-68-50AA 1-HS-68-50B-A RCP4 1-HS-68-73AA 1-HS-68-73SA
--(1) Loop status is to be written in data space (Operable (0), Running (R), or INOP). (2) See 1-SI-0-2-00 Ref. 8 if indication is less than 0.2 CPS. Initials INDICATE ace met OR action in "Ace not Met" column initiated.
Data CPS(2) CPS(2) % % % psig psig psig psig RCP 1 234 ON D D D D OFF D D D D (1) (1) (1) (1) Performer's Initials Acc NOT Met Contact SROto consult Tech Spec s. Contact SRO to consult Tech Spec s. Contact SRO to consult Tech Spec s Contact SROto consult Tech Spec s. SRO's Initials Ref 8 9 10 15 Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 2 of 15) 1-SI-0-2A-03 Rev. 0030 Page 23 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page ___ _ of ___ _ Location Description Instrument
T S Limit Operable, Channel Check, and MCD SR Neutron 1-NI-92-131A value is plus or minus Mon CH I 1/2 decade [0.3CR1<CR2 1-M-4 <3.0CR1].
Reading should be the SR Neutron 1-NI-92-132A average value Mon CH II observed over a 30 second period 1-LJ-68-339A Operable, less than or 1-LJ-68-335A equal to80%, 1-M-4 PZR Level Channel Check, and 1-LJ-68-320 MCD 1-PI-68-340A Operable 1-PI-68-334 channel check, 1-M-5 PZR Press greater than or equal 1-PI-68-323 to 2214psig and 1-PI-68-322 55 psig. RCS Loops RCP Status 1,2,3,4 RCP 1 1-HS-68-8AA Two loops operable; 1-HS-68-8BA two loops in operation 1-M-5 1-HS-68-31AA if capable of rod RCP2 withdrawal (one loop if 1-HS-68-31BA NOT) RCP 3 1-HS-68-50AA 1-HS-68-50BA RCP4 1-HS-68-73AA 1-HS-68-73BA (1) Loop status is to be written in data space (Operable (0), Running (R), or INOP). (2) See 1-SI-0-2-00 Ref. 8 if indication is less than 0.2 CPS. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Data CPS(2) CPS(2) % % % psig psig psig psig RCP 1 2 3 4 ON 0000 OFF 0 0 DO (1) (1)
(1) (1) Performer's Initials Acc NOT Met Contact SROto consult Tech Spec s. Contact SRO to consult Tech Spec s. Contact SRO to consult Tech Spec s Contact SROto consult Tech Spec s. SRO's Initials Ref 16 ) 17 18 ) Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 3 of 15) 1-SI-0-2A-03 Rev. 0030 Page 24 of 39 Mode 3 Surveillance Log: 1900-0700 Date, ___ _ Page __ _ of ___ _ Location 1-M-6 480V Rx MOV Boards 1-M-6 1-M-6 Description Instrument
T S Limit RWSTto RHR 1-FCV-63-1 ECCS Suction (1-HS-63-1A)
OPEN SI Pumps to CL 1, 1-FCV-63-22 2,3,4 (1-HS-63-22A)
Shunt BKR 1A1-A c/2E1 1-BKR-63-1 A At least one OR breaker OFF Breaker 1-BKR-63-1B 1A1-A c/1 OA Shunt BKR 1B1-B c/2F2 1-BKR-63-22A At least one OR breaker OFF Breaker 1-BKR-63-22B 1B1-Bc/11D 1-U-63-180 Operable, CNTMT 1-U-63-181 Channel check, Sump Level 1-U-63-182 and 1-U-63-183 MCD 1-U-63-50 Operable, 1-U-63-51 Channel check, RWST Level and MCD 1-U-63-52 1-U-63-53 CL Accum 1 Outlet 1-FCV-63-118 (1-HS-63-118A)
CL Accum 2 Outlet 1-FCV-63-98 Valves (1-HS-63-98A)
Open-when Pzr pressure CLAccum 3 Outlet 1-FCV-63-80 (1-HS-63-80A)
>1000 psig, CL Accum 4 Outlet 1-FCV-63-67 (1-HS-63-67A)
Initials INDICATE ace met OR action in "Ace not Met" column initiated.
Data Acc NOT Met OPEN D CLOSED D OPEN D CLOSED D OFF D ON D Contact SRO to consult OFF D Tech Specs. ON D OFF D ON D OFF D ON D % % % % Contact SRO to consult Tech % Specs % % % OPEN D CLOSED D OPEN D CLOSED D Contact SRO to consult OPEN D Tech Specs, CLOSED D OPEN D CLOSED D Performer's Initials SRO's Initials Ref 16 ..... 17 18 ) Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 3 of 15) 1-SI-0-2A-03 Rev. 0030 Page 24 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ___ _ Location 1-M-6 480V Rx MOV Boards 1-M-6 1-M-6 Description Instrument
T 5 Limit RWSTto RHR 1-FCV-63-1 ECCS Suction (1-HS-63-1A)
OPEN SI Pumps to CL 1, 1-FCV-63-22 2,3,4 (1-HS-63-22A)
Shunt BKR 1A1-A c12E1 1-BKR-63-1 A At least one OR breaker OFF Breaker 1-BKR-63-1 B 1A1-A c/1 OA Shunt BKR 1B1-B c/2F2 1-BKR-63-22A At least one OR breaker OFF Breaker 1-BKR-63-22B 1 B1-B c/11D 1-U-63-180 Operable, CNTMT 1-U-63-181 Channel check, Sump Level 1-U-63-182 and 1-U-63-183 MCD :0;6.0% 1-U-63-50 Operable, 1-U-63-51 Channel check, RWST Level and MCD 1-U-63-52 1-U-63-53
0;7.0% CL Accum 1 Outlet 1-FCV-63-118 (1-HS-63-118A)
CL Accum 2 Outlet 1-FCV-63-98 Valves (1-HS-63-98A)
Open-when Pzr pressure CL Accum 3 Outlet 1-FCV-63-80 (1-HS-63-80A)
>1000 psig. CL Accum 4 Outlet 1-FCV-63-67 (1-HS-63-67 A) Initials INDICATE ace met OR action in "Ace not Met" column initiated.
Data Acc NOT Met OPEN D CLOSED D OPEN D CLOSED D OFF D Contact SRO to ON D consult OFF D Tech Specs. ON D OFF D ON D OFF D ON D % % % % Contact SRO to consult Tech % Specs % % % OPEN D CLOSED D OPEN D CLOSED D Contact SRO to consult OPEN D Tech Specs. CLOSED D OPEN D CLOSED D Performer's SRO's Initials Initials
) } Ref 19 20 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Date ___ _ Location Description CLAccum 1 Lvi CLAccum 2 Lvi CL Accum 3 Lvi CLAccum 4 1-M-6 Lvi CLAccum 1 Press CLAccum 2 Press CLAccum 3 Press CLAccum 4 Press 1-M-6 or CNTMT Press ICS Mode Three Page 25 of 39 -_ .. __ ... _-------------
Data Sheet 1 (Page 4 of 15) Mode 3 Surveillance Log: 1900-0700 Page ___ _ Instrument
T S Limit Data 1-U-63-129 gal 1-U-63-119 27630 and :s;8000 gal 1-U"63-109 gal and MCD :s; 96 gal gal. Chemistry is to 1-U-63-99 be notified to gal perform 1-SI-63-6 1-U-63-89 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if tank gal 1-U-63-81 level is increased 2 gal 75 gal and tank NOT 1-U-63-82 filled from RWST.(1) gal 1-U-63-60 gal 1-PI-63-128 psig 1-PI-63-126 psig 1-PI-63-108 psig 1-PI-63-106 2610 and :S;660 psig and MCD psig 1-PI-63-88 psig (1) psig 1-PI-63-86 psig 1-PI-63-62 psig 1-PI-63-61 psig 1-PDI-30-42 D Operable, Channel or Point P1 OOOA D Check, and MCD of psig (2) 1-PDI-30-43 D the following:
or Point P1 001A D MCD:s; 1.0 psig (lnd) psig (2) 1-PDI-30-44 D MCD :s; 0.8 psig or Point P1 002A D (mixed) psig (2) 1-PD 1-30-45 D MCD :s; 0.5 psig or Point P1 003A D (computer) psig (2) (1) When Pzr pressure greater than 1000 psig. (2) Instrument used for data is to be checked. POI is preferred instrument.
Initials INDICATE ace met OR action in "Ace not Met" column initiated.
Performer's Initials Remarks: of ___ _ Acc NOT Met Check operability by acceptable deviation between redundant level and pressure channels when pressurizer pressure is above 1000 psig. If deviation limit is exceeded, determine the channel inoper-able AND record only the operable channel. This channel check is NOT a technical specification re-quirement.
Contact SRO to consult Tech Specs SRO's Initials Ref 19 \ ) 20 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Date ___ _ Location Description CLAccum 1 Lvi CLAccum 2 Lvi CLAccum 3 Lvi CLAccum 4 1-M-6 Lvi CLAccum 1 Press CLAccum 2 Press CLAccum 3 Press CLAccum 4 Press 1-M-6 or CNTMT Press ICS Mode Three Page 25 of 39 Data Sheet 1 (Page 4 of 15) Mode 3 Surveillance Log: 1900-0700 Page ___ _ Instrument
T 5 Limit Data 1-U-63-129 gal 1-U-63-119 7630 and gal 1-U-63-109 gal and MCD 96 gal gal. Chemistry is to 1-U-63-99 be notified to gal perform 1-SI-63-6 1-U-63-89 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if tank gal 1-U-63-81 level is increased gal 75 gal and tank NOT 1-U-63-82 filled from RWST.(1) gal 1-U-63-60 gal 1-PI-63-128 psig 1-PI-63-126 psig 1-P 1-63-108 psig 1-PI-63-106 0 and psig and MCD $i. 30 psig 1-PI-63-88 psig (1) psig 1-PI-63-86 psig 1-PI-63-62 psig 1-PI-63-61 psig 1-PDI-30-42 0 Operable, Channel or Point P1 OOOA 0 Check, and MCD of psig (2) 1-PDI-30-43 0 the following:
or Point P1 001A 0 MCD 1.0 psig (lnd) psig (2) 1-PDI-30-44 0 MCD 0.8 psig or Point P1 002A 0 (mixed) psig (2) 1-PD 1-30-45 0 MCD 0.5 psig or Point P1 003A 0 (computer) psig (2) (1) When Pzr pressure greater than 1000 psig. (2) Instrument used for data is to be checked. POI is preferred instrument.
Initials INDICATE ace met OR action in "Ace not Met" column initiated.
Performer's Initials ') Remarks: of ___ _ Acc NOT Met Check operability by acceptable deviation between redundant level and pressure channels when pressurizer pressure is above 1000 psig. If deviation limit is exceeded, determine the channel inoper-able AND record only the operable channel. This channel check is NOT a technical specification re-quirement.
Contact SRO to consult Tech Specs SRO's Initials
) ) Ref 21 I WBN* 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Date Description CNTMT-ANN 1-M-9 ,1.P 1-M-9 I Annulus ,1.P Mode Three Page 26 of 39 Data Sheet 1 (Page 5 of15) Mode 3 Surveillance Log: 1900-0700 Page Instrument
T 5 Limit 1-PDI-30-133 D ,1.P between -0.07 or and 0.27 psid 1-PDI-30-30C D 1-PDI-30-126 More negative than or equal value on Attachment 1 " H 2 0(1) i-PO 1-30-127 and MCD < 0:7 "H 2 O point Y2203A D Data psid(2) " H 2 0(4) " H 2 0(4) of I Acc NOT Met Contact SRO to consult Tech Specs. 22 I ICS Shield or N/A-used for 1-M-9 Building Flow 1-FI-90-400 D Attachment 1 or Data Sheet 37(3) D SCFM Tech Spec Acceptance value from " H 2 0(4) Attachment 1 (1) 1-PDI-30-126 and 1-PDI-30-127 have a range of 0 -10" H 2 0 and indicate negative pressure relative to atmosphere (e.g. an indication of 6" H 2 0 is more negative than negative 5.5" H 2 0) (2) 1-PDI-30-30C on 1-L-10 may be substituted for 1-PDI-30-133 to check Tech Spec compliance.
(3) Perform data sheet 37 of 1-SI-0-2-00 to determine shield building flow if ICS point and 1-FI-90-400 are unavailable whenever shield building exhaust stack has flow. This flow is required in order to determine Tech Spec value for Annulus 1l.P on Attachment
1. (4) N/A during venting operations, required annulus entries, or Aux Bldg isolations not exceeding 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration.
Remarks: Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials ) Ref 21 22 WBN Unit 1 Date 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 5 of15) 1-SI-0-2A-03 Rev. 0030 Page 26 of 39 Mode 3 Surveillance Log: 1900-0700 Page of Location Description Instrument
T 5 Limit Data Acc NOT Met CNTMT-ANN 1-PDI-30-133 D LlP between -0.07 1-M-9 LlP or and 0.27 psid 1-PDI-30-30C D psid(2) 1-PDI-30-126 More negative than or equal value on " H 2 0(4) 1-M-9 Annulus LlP 1-PD 1-30-127 Attachment 1 " H 2 0(1) and MCD 0:7 "H 2 O " H 2 0(4) Contact SRO to consult point Y2203A D Tech Specs. (1 ) (2) ICS Shield or N/A-used for 1-M-9 Building Flow 1-FI-90-400 D Attachment 1 or Data Sheet 37(3) D SCFM Tech Spec Acceptance value from " H 2 0(4) Attachment 1 1-PDI-30-126 and 1-PDI-30-127 have a range of 0 -10" H 2 0 and indicate negative pressure relative to atmosphere (e.g. an indication of 6" H 2 0 is more negative than negative 5.5" H 2 0) 1-PDI-30-30C on 1-L-10 may be substituted for 1-PDI-30-133 to check Tech Spec compliance.
(3) Perform data sheet 37 of 1-SI-0-2-00 to determine shield building flow if ICS point and 1-FI-90-400 are unavailable whenever shield building exhaust stack has flow. This flow is required in order to determine Tech Spec value for Annulus .6.P on Attachment
1. (4) N/A during venting operations, required annulus entries, or Aux Bldg isolations not exceeding 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration.
Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials Remarks:
) WBN 'Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 6 of 15) 1-SI-0-2A-03 Rev. 0030 Page 27 of 39 Mode 3 Surveillance Log: 1900-0700 Ret Location Description Instrument
TS Limit Data Acc NOT Met 23 24 Remarks: 1-M-10 Ice Cndnsr Door 1-XI-61-187 Operable, all doors ('>/) Contact SRO to consult Status Position closed, and Channel Tech Specs and perform Monitoring Check data sheet 23. System 1-M-10 Ice Bed 1-TR-61-138 Operable, :s; 25.2°F, Table If 1-TR-61-138 and Local Temperature Channel Check, and below Ice CondTemp Monitoring minimum of two . monitoring panel are System RTDs per inoperable, perform Data group operable.
(1) Sheet 24 of 1-SI-0-2-00 "Inoperable Ice Bed Monitoring System" (1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded.
All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. (2) Fulfills LCO 3.6.12 Action B.1 or TR 3.6.2 Action A.1, when maximum ice bed temp s 25.2°F once every four hours. (3) Fulfills TR 3.6.1 Action B.1.2 and/or Action C.1.2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials WBN 'Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 6 of 15) 1-SI-0-2A-03 Rev. 0030 Page 27 of 39 Mode 3 Surveillance Log: 1900-0700 Ret Location Description Instrument
TS Limit Data Acc NOT Met 23 24 Remarks: 1-M-10 Ice Cndnsr Door 1-XI-61-187 Operable, all doors (,f) Contact SRO to consult Status Position closed, and Channel Tech Specs and perform Monitoring Check data sheet 23. System 1-M-10 Ice Bed 1-TR-61-138 Operable, ::; 25.2°F, Table If 1-TR-61-138 and Local Temperature Channel Check, and below Ice Cond Temp Monitoring minimum of two monitoring panel are System RTDs per inoperable, perform Data group operable.
(1) Sheet 24 of 1-SI-0-2-00 "Inoperable Ice Bed Monitoring System" (1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded, All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. (2) Fulfills LCO 3.6.12 Action B.1 or TR 3,6.2 Action A.1, when maximum ice bed temp s; 25.2°F once every four hours, (3) Fulfills TR 3,6,1 Action B.1.2 and/or Action C.1 ,2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials
) WBN Unit 1 1900 -0700 Shift And Daily SurveiUance Log Mode Three Data Sheet 1 (Page 7 of 15) 1-SI-0-2A-03 Rev. 0030 Page 28 of 39 Mode 3 Surveillance Log: 1900-0700 Date __ _ Page __ _ of __ _ TE PT Data TE PT Data TE PT Data 138 1 139 16 N/A N/A N/A 141 2 142 17 143 31 EL 801 144 3 EL 776 145 18 EL 756 146 32 Group 7(1)(2) Group 4(1)(2) Group 1(1)(2) 147 4 148 19 149 33 150 5 151 20 152 34 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 153 6 154 21 155 35 156 7 157 22 N/A N/A N/A EL 801 159 8 EL 776 160 23 EL 756 161 36 Group 8(1)(2) Group 5(1)(2) Group 2(1)(2) 165 9 166 24 167 37 183 10 184 25 185 38 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 168 11 169 26 170 39 171 12 172 27 173 40 EL 801 174 13 EL 776 175 28 EL 756 176 41 Group 9(1)(2) Group 6(1)(2) Group 3(1)(2) 177 14 178 29 179 42 180 15 181 30 N/A N/A N/A 1 1 1 Two Highest Temps 2 ' Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 TOTAL OF TOTALS+ 18 MEAN ICE BED OPTIMUM MEAN ICE PERFORMER REVIEWER INITIALS SUMS TEMP (3) BED TEMP INITIALS +18 15°F TO 20°F (1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded.
All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. (2) Fulfills LCO 3.6.12 Action B.1 or TR 3.6.2 Action A.1 , when maximum ice bed temp once every four hours. (3) Fulfills TR 3.6.1 Action B.1.2 and/or Action C.1.2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE ace met OR action in "Ace not Met" column initiated.
Performer's Initials SRO's Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 7 of 15) 1-SI-0-2A-03 Rev. 0030 Page 28 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page ___ _ of ___ _ TE PT Data TE PT Data TE PT Data 138 1 139 16 N/A N/A N/A 141 2 142 17 143 31 EL 801 144 3 EL 776 145 18 EL 756 146 32 Group 7(1)(2) Group 4(1)(2) Group 1 (1)(2) 147 4 148 19 149 33 150 5 151 20 152 34 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 153 6 154 21 155 35 156 7 157 22 N/A N/A N/A EL 801 159 8 EL 776 160 23 EL 756 161 36 Group 8(1)(2) Group 5(1)(2) Group 2(1)(2) 165 9 166 24 167 37 183 10 184 25 185 38 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 168 11 169 26 170 39 171 12 172 27 173 40 EL 801 174 13 EL 776 175 28 EL 756 176 41 Group 9(1)(2) Group 6(1)(2) Group 3(1)(2) 177 14 178 29 179 42 180 15 181 30 N/A N/A N/A 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 TOTAL OF TOTALS+ 18 MEAN ICE BED OPTIMUM MEAN ICE PERFORMER REVIEWER INITIALS SUMS TEMP (3) BED TEMP INITIALS +18 15°F TO 20°F (1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded.
All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. ) Remarks: (2) Fulfills LCO 3.6.12 Action B.1 or TR 3.6.2 Action A.1, when maximum ice bed temp s; 25.2°F once every four hours. (3) Fulfills TR 3.6.1 Action B.1.2 and/or Action C.1.2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials Ref 25 ') I 26 27 Remarks: ) WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 8 of 15) 1-SI-0-2A-03 Rev. 0030 Page 29 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ___ _ Location 0-M-12 or ICS 0-M-12 or ICS 0-M-12 or ICS Description Instrument
T S Limit 1-RM-90-106A 0 or point R1012A 0 1-RM-90-106B 0 or point R1013A 0 Operable and Lower and UpperCNTMT 1-RM-90-112A 0 Channel Check Gas and or Particulate point R1015A 0 1-RM-90-112B 0 or point R1016A 0 1-RR-90-106 1-RR-90-112 Operable 0-RM-90-1 02 0 or Spend Fuel Pit point R9011A 0 Operable and Area 0-RM-90-1 03 0 Channel Check or point R9012A 0 0-RM-90-125 0 or point R1025A 0 0-RM-90-126 0 Operable and MCR Intake or Channel Check point R1026A 0 0-RR-90-125 0-RR-90-126 Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met If monitor aligned to cpm Lower Containment is inoperable, the other monitor is to be re-cpm aligned using SOI-90.02.
If both monitors are inoper-cpm able, SRO is to be notified, 1-SI-68-32 is to be performed, and Chemistry Count-cpm room is to be notified (-V) to perform 1-SI-90-25.
(-V) mr/hr Contact SRO to consult Tech Specs mr/hr cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. (-V) (-V) Performer's SRO's Initials Initials Ref 25 ) '26 27 Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 8 of 15) 1-SI-0-2A-03 Rev. 0030 Page 29 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ___ _ Location 0-M-12 or ICS 0-M-12 or ICS 0-M-12 or ICS Description Instrument
T 5 Limit 1-RM-90-106A 0 or point R1012A 0 1-RM-90-106B 0 or point R1013A 0 Operable and Lower and UpperCNTMT 1-RM-90-112A 0 Channel Check Gas and or Particulate point R1015A 0 1-RM-90-112B 0 or point R1016A 0 1-RR-90-106 1-RR-90-112 Operable 0-RM-90-1 02 0 or Spend Fuel Pit point R9011A 0 Operable and Area 0-RM-90-1 03 0 Channel Check or point R9012A 0 0-RM-90-125 0 or point R1025A 0 0-RM-90-126 0 Operable and MCR Intake or Channel Check point R1026A 0 0-RR-90-125 0-RR-90-126 Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met If monitor aligned to cpm Lower Containment is inoperable, the other monitor is to be re-cpm aligned using SOI-90.02.
If both monitors are inoper-cpm able, SRO is to be notified, 1-SI-68-32 is to be performed, cpm and Chemistry Count-room is to be notified (,J) to perform 1-SI-90-25.
(,J) mr/hr Contact SRO to consult Tech Specs mr/hr cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. (,J) (,J) Performer's SRO's Initials Initials
) Ref 28 29 ) Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three . Data Sheet 1 (Page 9 of 15) 1-SI-0-2A-03 Rev. 0030 Page 30 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page ___ _ of ___ _ Location O-M-12 or ICS AUX BLDG A2U/713 or ICS Description Instrument # T 5 Limit CCS HxA Out 1-RM-90-123 0 Operable and Liquid or Channel Check point R1023A 0 (Info Only-T.S.
N/A) 1-RM-90-130A 0 CNTMT or Purge Air Exh point R1027A 0 Operable and Radiation Channel Check Monitor 1-RM-90-131A 0 or point R1028A 0 Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met Contact SRO. See Section 6.1 K. cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. IF both monitors inoperable, suspend purge flow immediately per ODCM cpm table 1.1.2-6.a Performer's Initials SRO's Initials WBN Unit 1 Date Ref Location O-M-12 or 28 ICS AUX BLDG 29 A2U/713 or ICS Remarks: 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 9 of 15) 1-SI-0-2A-03 Rev. 0030 Page 30 of 39 Mode 3 Surveillance Log: 1900-0700

Page of ______ _ Description Instrument

T S Limit CCS HxA Out 1-RM-90-123 0 Operable and Liquid or Channel Check point R1023A 0 (Info Only-T.S.
N/A) 1-RM-90-130A 0 CNTMT or Purge Air Exh point R1027A 0 Operable and Radiation Channel Check Monitor 1-RM-90-131A 0 or point R1028A 0 Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met Contact SRO. See Section 6.1 K. cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. IF both monitors inoperable, suspend purge flow immediately per ODCM cpm table 1.1.2-6.a Performer's SRO's Initials Initials Ref 59 ) 67 I Remarks: WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 31 of 39 -------------
Data Sheet 1 (Page 10 of 15) Mode 3 Surveillance Log: 1900-0700 Date __ _ Page __ _ 'location Description Instrument
T S Limit Unit 1 Shield I Bldg Exhaust AEB729 Tritium Flow' 1-SMPL-90-801 Operable Rate Monitor Unit 2 Shield Bldg Exhaust AEB 729 Tritium Flow 2-SMPL-90-801 Operable Rate Monitor . Aux Bldg and AUX BLDG Fuel Handling 786 Exhaust Tritium 0-SMPL-90-800 Operable Flow Rate Monitor Tech Specs per N/A 1-SI-0-10(1)
N/A 1-SI-0-10 (1) Conditional performance cannot be substituted for periodic performance.
Initials indicate acc met OR action in "Ace not Met" column initiated.
Data (.y) (.y) (.y) Completed or in progress for the required performance frequency interval 0 (.y) Performer's Initials of ---Acc NOT Met , If Tritium flow rate measuring device is inoperable, SRO and Chemistry are to be notified.
Initiate WO and record number in remarks section. N/A SRO's Initials Ref 59 \ 67 ! I Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 10 of 15) 1-SI-0-2A-03 Rev. 0030 Page 31 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page ___ _ Location Description Instrument # T S Limit Data Unit 1 Shield AEB 729 Bldg Exhaust 1-SMPL-90-801 Operable Tritium Flow Rate Monitor (-/) Unit 2 Shield Bldg Exhaust AEB 729 Tritium Flow 2-SMPL-90-801 Operable Rate Monitor (-/) . Aux Bldg and AUX BLDG Fuel Handling Exhaust Tritium 0-SMPL-90-800 Operable (1) 786 Flow Rate Monitor Tech Specs per N/A 1-SI-0-10(1)
N/A 1-SI-0-10 Conditional performance cannot be substituted for periodic performance.
Initials indicate acc met OR action in "Ace not Met" column initiated.
(-/) Completed or in progress for the required performance frequency interval 0 (-/) Performer's Initials of ----Acc NOT Met If Tritium flow rate measuring device is inoperable, SRO and Chemistry are to be notified.
Initiate WO and record number in remarks section. N/A SRO's Initials Ref J } 65 WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 11 of 15) 1-SI-0-2A-03 Rev. 0030 Page 32 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ___ _ Location J Description I Instrument 1 T S Limit I Data I Acc NOT Met Control Building_
NORMAL LIMITS Control Room South Wall 0-TI-30-5219 el755 Control Room across from 0-TI-30-5220 1-M-9 el 755 Next to 480V SO BO 0-TI-30-5201 Transformer 1A2-A el 772 Next to 480V SO BO 0-TI-30-5202 Transformer 1 B 1-B el 772 Next to 480V Rx MOV 0-TI-30-5203 Bd 1A2-A el 772 Behind 125V Vital Batt 0-TI-30-5204 Cha!:9.er 6-S el 772 Next to 480V Rx MOV 0-TI-30-5205 Bd 2A2-A el772 Next to 480V SO BO 0-TI-30-5206 Transformer 2A2-A el 772 Next to 480V SO BO 0-TI-30-5207 Transformer 2B2-B el 772 Next to 480V Rx MOV 0-TI-30-5208 Bd 2B2-B el 772 U1 Mech Equip Rm el772 0-TI-30-5209 SO BO Rm U1 behind stairs 0-TI-30-521 0 S-A3 el757 SO BO Rm U2 behind stairs 0-TI-30-5211 S-A13 el757 Refuel Floor U1 beside Aux 0-TI-30-5212 Boration Makeup Tank el 757 Computer room at center of 0-TI-30-5226 the room* el 708 Aux Instrument Room el708 0-TI-30-5233 Initials indicate ace met OR action in "Ace not Met" column initiated.
80°F of Readings on this page may be taken in

:; 80°F of any order. In all sections of Ref ::; 104°F of 65, use of Fluke 52 digital thermometer or ::; 104°F of equivalent is acceptable for ::; 83°F of temperature indicators not present ::; 83°F of or inoperable.
83°F OF

:; 104°F of ::; 104°F of Contact SRO to consult Technical
83°F of Requirements section 3.7.5.1. SRO should

:; 91°F of evaluate normal AND abnormal limits. ::; 85°F of Perform Data Sheets 65 of 1-SI-0-2-00
85°F of "Out of Limit Hourly Temperature".
104°F of

:; 74°F of ::; 90°F of Performer's SRO's Initials Initials Ref ) 65 pmarks: j WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 11 of 15) 1-SI-0-2A-03 Rev. 0030 Page 32 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ___ _ Location I Description Instrument T S Limit Data Acc NOT Met Control Building NORMAL LIMITS Control Room South Wall 0-TI-30-5219 el755 Control Room across from 1-M-9 el 755 0-TI-30-5220 Next to 480V SO BO 0-TI-30-5201 Transformer 1A2-A el 772 Next to 480V SO BO 0-TI-30-5202 Transformer 1 B 1-B el 772 Next to 480V Rx MOV 0-TI-30-5203 Bd 1A2-A el 772 Behind 125V Vital Batt 0-TI-30-5204 Charger 6-S el 772 Next to 480V Rx MOV 0-TI-30-5205 Bd 2A2-A el 772 Next to 480V SO BO 0-TI-30-5206 Transformer 2A2-A el 772 Next to 480V SO BO 0-TI-30-5207 Transformer 2B2-B el 772 Next to 480V Rx MOV 0-TI-30-5208 Bd 2B2-B el 772 U1 Mech Equip Rm e1772 0-TI-30-5209 SO BO Rm U1 behind stairs 0-TI-30-521 0 S-A3 el757 SO BO Rm U2 behind stairs 0-TI-30-5211 S-A13 el757 Refuel Floor U 1 beside Aux 0-TI-30-5212 Boration Makeup Tank el 757 Computer room at center of 0-TI-30-5226 the room el 708 Aux Instrument Room el 708 0-TI-30-5233 Initials indicate ace met OR action in "Ace not Met" column initiated. 80°F Readings on this of page may be taken in 80°F of any order. 104°F In all sections of Ref OF 65, use of Fluke 52 104°F digital thermometer or OF equivalent is 83°F acceptable for OF temperature 83°F indicators not present OF or inoperable. 83°F OF 104°F OF 104°F OF Contact SRO to 83°F consult Technical OF Requirements section 91°F 3.7.5.1. SRO should OF evaluate normal AND 85°F abnormal limits. OF Perform Data Sheets 85°F 65 of 1-SI-0-2-00 OF "Out of Limit Hourly 104°F Temperature".
OF 74°F OF 90°F OF Performer's SRO's Initials Initials
) Ref 65 -WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 12 of 15) 1-SI-0-2A-03 . Rev. 0030 Page 33 of 39 Mode 3 Surveillance Log: 1900-0700 Date ----Location I Description U1 outside supply fan room el737 South steam vault room U 1 el730 North steam vault room U1 el730 Between UHI Accumulators el729 U1 across from AFW pumps el713 U1 outside AFW pump room door el692 U2 near Boric Acid con-centrate filter vault el692 Next to 0-L-629 el 676 U1 Blender Station South Wall el713 Behind BAT Ael713 Behind BAT B el 713 Instrument
T S Limit Auxiliary Building Normal Limits 0-TI-30-5213 0-TI-30-5228 0-TI-30-5227 0-TI-30-5218 0-TI-30-5214 0-TI-30-5215 0-TI-30-5216 0-TI-30-5217 1-TI-62-240 1-TI-62-239 2-TI-62-239 Initials indicate acc met OR action in "Acc not Met" column initiated.
104°F 250°F 250°F

:; 92°F ::; 104°F ::; 104°F ::; 104°F ::; 104°F 263°F 263°F 263°F Page of ___ _ Data Acc NOT Met Readings on this of page may be taken in any order. of In all sections of Ref 65, use of Fluke 52 of digital thermometer or equivalent is of acceptable for temperature indicators not present or of inoperable.
Contact SRO to OF consult Technical Requirements section 3.7.5.1. SRO should evaluate OF normal AND abnormal limits. Perform Data Sheets 65 of 1-SI-0-2-00 "Out of Limit Hourly of Temperature".
Contact SRO to consult Technical of Requirements section 3.1.1.1 &Ior 3.1.2.1 Perform Data of Sheet 65 of 1-SI-0-2-00 "Out of Limit Hourly of Temperature".
Performer's SRO's Initials Initials Ref } J 65 WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 12 of 15) 1-SI-0-2A-03 Rev. 0030 Page 33 of 39 Mode 3 Surveillance Log: 1900-0700 Date ----Location I Description U 1 outside supply fan room el737 South steam vault room U1 el730 North steam vault room U1 el730 Between UHI Accumulators el729 U1 across from AFW pumps el713 U1 outside AFW pump room doorel692 U2 near Boric Acid con-cent rate filter vault el692 Next to 0-L-629 el 676 U1 Blender Station South Wall el713 Behind BAT A el 713 Behind BAT B el 713 Instrument
T 5 Limit Auxiliary Building Normal Limits 0-TI-30-5213 0-TI-30-5228 0-TI-30-5227 0-TI-30-5218 0-TI-30-5214 0-TI-30-5215 0-TI-30-5216 0-TI-30-5217 1-TI-62-240 1-TI-62-239 2-TI-62-239 Initials indicate acc met OR action in "Acc not Met" column initiated.
s; 104°F 50°F 50°F s; 92°F s; 104°F s; 104°F s; 104°F s; 104°F 63°F 63°F 63°F Page of ______ _ Data Acc NOT Met Readings on this of page may be taken in any order. of In all sections of Ref 65, use of Fluke 52 of digital thermometer or equivalent is of acceptable for temperature indicators not present or of inoperable.
Contact SRO to of consult Technical Requirements section 3.7.5.1. SRO should evaluate of normal AND abnormal limits. Perform Data Sheets 65 of 1-SI-0-2-00 "Out of Limit Hourly OF Temperature".
Contact SRO to consult Technical of Requirements section 3.1.1.1 &Ior 3.1.2.1 Perform Data of Sheet 65 of 1-SI-0-2-00 "Out of Limit Hourly of Temperature".
Performer's SRO's Initials Initials WBN Unit 1 ') 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 13 of 15) 1-SI-0-2A-03 Rev. 0030 Page 34 of 39 Mode 3 Surveillance Log: 1900-0700 Ref 65 \ } 65 Date ___ _ Location I Description Instrument # T S Limit Outside Normal Limits 1 A-A DIG Rm near DIG set 0-TI-30-5229
0

50°F el742 1 B-B DIG Rm near DIG set OcTI-30-5230
0

50°F el742 2A-A DIG Rm near DIG set 0-TI-30-5231
0

50°F el742 2B-B DIG Rm near DIG set 0-TI-30-5232
0

50°F el742 2B-B DIG Rm on wall by bat-tery charger el 742 0-TI-30-5221 S; 104°F Next to 480V Diesel Aux Bd 2B1-B e1760.5 0-TI-30-5222 S; 104°F C-S DIG Rm on wall near DIG set el742 TI-36 ;::0: 50°F Pumpin! Station (IPS) Next to 480V IPS bd & NORMAL LIMITS trans-former (A bus) el 711 0-TI-30-5223
0

50°F & < 104°F In B train ERCW pump rm 0-TI-30-5224 s; 120°F el741 Next to 480V IPS bd & 0-TI-30-5225 S; 104°F trans-former (B bus) el 711 Mech Equip Rm A near ERCW ;::0: 50°F & & HPFP instru sense lines 0-TI-30-5245 el722 S; 104°F Mech Equip Rm B near ERCW ;::0: 50°F & & HPFP instru sense lines 0-TI-30-5246 el722 s; 104°F Initials indicate ace met OR action in "Ace not Met" column initiated.
}emar'ks:
Page __ _ Data Acc NOT Met Readings on this page may be of taken in any order. In all sections of Ref 65, use of of Fluke 52 digital thermometer or equivalent is acceptable for of temperature indicators not present or inoperable.
of Contact SRO to consult Technical of Requirements section 3.7.5.1. SRO should evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourly Temperature".
C-S DIG temp only taken IF C-S DIG declared Operable.
NIA if NOT operable Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourly Temperature" of Contact SRO to consult of Technical Requirements section 3.7.5.1. SRO should of evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourly Temperature".
of Performer's SRO's Initials Initials I WBN Unit 1 ) 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 13 of 15) 1-SI-0-2A-03 Rev. 0030 Page 34 of 39 Mode 3 Surveillance Log: 1900-0700 Ref 65 ) 65 Date ___ _ Location I Description Instrument
T S Limit Outside Normal Limits 1A-A DIG Rm near DIG set 0-TI-30-5229 250°F el742 18-8 DIG Rm near DIG set OcTI-30-5230 250°F el742 2A-A DIG Rm near DIG set 0-TI-30-5231 250°F el742 28-8 DIG Rm near DIG set 0-TI-30-5232 250°F el742 28-8 DIG Rm on wall by bat-tery charqer el 742 0-TI-30-5221 104°F Next to 480V Diesel Aux 8d 281-8 e1760.5 0-TI-30-5222 104°F C-S DIG Rm on wall near DIG setel742 TI-36 250°F Station (IPS) Next to 480V IPS bd & NORMAL LIMITS trans-former (A bus) el 711 0-TI-30-5223 250°F & < 104°F In 8 train ERCW pump rm 0-TI-30-5224 120°F el741 Next to 480V IPS bd & 0-TI-30-5225 104°F trans-former (8 bus) el 711 Mech Equip Rm A near ERCW 250°F & & HPFP instru sense lines 0-TI-30-5245 el722 104°F Mech Equip Rm 8 near ERCW 250°F & & HPFP instru sense lines 0-TI-30-5246 el722 104°F Initials indicate acc met OR action in "Acc not Met" column initiated.
jemarks: I Page of ___ _ Data Acc NOT Met Readings on this page may be OF taken in any order. In all sections of Ref 65, use of of Fluke 52 digital thermometer or equivalent is acceptable for of temperature indicators not present or inoperable.
of Contact SRO to consult Technical of Requirements section 3.7.5.1. SRO should evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-O-2-00 "Out of of Limit Hourly Temperature".
C-S DIG temp only taken IF C-S DIG declared Operable.
NIA if NOT operable Perform Data Sheet 65 of 1-SI-O-2-00 "Out of of Limit Hourly Temperature" OF Contact SRO to consult of Technical Requirements section 3.7.5.1. SRO should of evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourly Temperature".
of Performer's SRO's Initials Initials WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Date ___ _ Ref Location I Description Various DIG Electrical Bd. 66 Rooms NOMENCLATURE DG 1A-A RM EXH FAN 1 (1-FAN-30-447)
DG 1A-A RM GEN/PNL VENT FAN (1-FAN-30-491)
DG 1A-A ELEC BOARD ROOM EXH FAN (1-FAN-30-459)
DG 1A-A RM EXH FAN 2 (1-FAN-30-451 ) DG 2A-A RM EXH FAN 1 (2-FAN-30-448) ,pG 2A-A ROOM GEN/PANEL VENT f-AN (2-FAN-30-492)
JDG 2A-A ELEC BOARD ROOM EXH FAN (2-FAN-30-460)
DG 2A-A RM EXH FAN 2 (2-FAN-30-452)
DG 1 B-B ROOM EXH FAN 1 (1-FAN-30-449)
DG 1 B-B RM GEN/PNL VENT FAN (1-FAN-30-493)
DG 1 B-B ELEC BOARD ROOM EXH FAN (1-FAN-30-461)
DG 1 B-B ROOM EXH FAN 2 (1-FAN-30-453)
DG 2B-B ROOM EXH FAN 1 (2-FAN-30-450)
DG 2B-B ROOM GEN/PNL VENT FAN (2-FAN-30-494 ) DG 2B-B ELEC BOARD ROOM EXH FAN (2-FAN-30-462)
DG 2B-B RM EXH FAN 2 (2-FAN-30-454 ) Remarks: ) Mode Three Data Sheet 1 (Page 14 of 15) Page 35 of 39 -------------------
Mode 3 Surveillance Log: 1900-0700 Instrument
T S Limit Outside See following Bkrs & HS in table required position LOCATION BKR 480V Diesel POSITION Auxiliary Bd. 1A1-A C/2B ON 1A1-A C/4D ON 1A1-A C/4E ON 1A2-A C/2B ON 2A1-A C/2B ON 2A1-A C/4D ON 2A1-A C/4E ON 2A2-A C/2B ON 1B1-BC/2B ON 1B1-BC/4D ON 1B1-BC/4E ON 1B2-B C/2B ON 2B1-B C/2B ON 2B1-B C/4D ON 2B1-B C/4E ON 2B2-B C/2B ON Initials indicate ace met OR action in "Ace not Met" column initiated.
Page of ___ _ Data Acc NOT Met See following Notify SRO of need to evaluate DIG operability using Data Sheet 66 of table 1-SI-0-2-00 Bkr& HS in HS POSITION UNID Required Position?
PULL 1-BKR-30-447 I DYES STANDBY 1-HS-30-447C DNO N/A 1-BKR-30-491 DYES DNO P-AUTO 1-BKR-30-459 I DYES 1-HS-30-459C D NO P-AUTO 1-BKR-30-451 I DYES 1-HS-30-451 C DNO PULL 2-BKR-30-448 I DYES STANDBY 2-HS-30-448C DNO N/A 2-BKR-30-492 DYES DNO P-AUTO 2-BKR-30-460 I DYES 2-HS-30-460C DNO P-AUTO 2-BKR-30-452 I DYES 2-HS-30-452C DNO PULL 1-BKR-30-449 I DYES STANDBY 1-HS-30-449C DNO N/A 1-BKR-30-493 DYES D NO P-AUTO 1-BKR-30-461 I DYES 1-HS-30-461 C DNO P-AUTO 1-BKR-30-453 I DYES 1-HS-30-453C DNO PULL 2-BKR-30-450 I DYES STANDBY 2-HS-30-450C DNO N/A 2-BKR-30-494 DYES DNO P-AUTO 2-BKR-30-462 I DYES 2-HS-30-462C DNO P-AUTO 2-BKR-30-454 I DYES 2-HS-30-454C DNO Performer's SRO's Initials Initials WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Date ___ _ Ref Location I Description Various DIG Electrical Bd. 66 Rooms NOMENCLATURE DG 1A-A RM EXH FAN 1 (1-FAN-30-447)
DG 1A-A RM GEN/PNL VENT FAN (1-FAN-30-491 ) DG 1A-A ELEC BOARD ROOM EXH FAN (1-FAN-30-459)
DG 1A-A RM EXH FAN 2 (1-FAN-30-451 ) DG 2A-A RM EXH FAN 1 (2-FAN-30-448)
DG 2A-A ROOM GEN/PANEL VENT y-AN (2-FAN-30-492)
DG 2A-A ELEC BOARD ROOM EXH FAN (2-FAN-30-460)
DG 2A-A RM EXH FAN 2 (2-FAN-30-452)
DG 1 B-B ROOM EXH FAN 1 (1-FAN-30-449)
DG 1 B-B RM GEN/PNL VENT FAN (1-FAN-30-493)
DG 1 B-B ELEC BOARD ROOM EXH FAN (1-FAN-30-461)
DG 1 B-B ROOM EXH FAN 2 (1-FAN-30-453)
DG 2B-B ROOM EXH FAN 1 (2-FAN-30-450)
DG 2B-B ROOM GEN/PNL VENT FAN (2-FAN-30-494 ) DG 2B-B ELEC BOARD ROOM EXH FAN (2-FAN-30-462)
DG 2B-B RM EXH FAN 2 (2-FAN-30-454)
Remarks: ) Mode Three Data Sheet 1 (Page 14 of 15) Pa_ge 35 of 39 Mode 3 Surveillance Log: 1900-0700 Instrument
T S Limit Outside See following Bkrs & HS in table required position LOCATION BKR 480V Diesel POSITION Auxiliary Bd. 1A1-A C/2B ON 1A1-A C/4D ON 1A1-A C/4E ON 1A2-A C/2B ON 2A1-A C/2B ON 2A1-A C/4D ON 2A1-A C/4E ON 2A2-A C/2B ON 1B1-BC/2B ON 1B1-BC/4D ON 1B1-BC/4E ON 1B2-B C/2B ON 2B1-B C/2B ON 2B1-B C/4D ON 2B1-B C/4E ON 2B2-B C/2B ON Initials indicate acc met OR action in "Acc not Met" column initiated.
Page of ___ _ Data Acc NOT Met See following Notify SRO of need to evaluate DIG operability using Data Sheet 66 of table 1-SI-0-2-00 Bkr& HS in HS POSITION UNID Required Position?
PULL 1-BKR-30-447 I DYES STANDBY 1-HS-30-447C DNO N/A 1-BKR-30-491 DYES DNO P-AUTO 1-BKR-30-459 I DYES 1-HS-30-459C D NO P-AUTO 1-BKR-30-451 I DYES 1-HS-30-451 C DNO PULL 2-BKR-30-448 I DYES STANDBY 2-HS-30-448C DNO N/A 2-BKR-30-492 DYES D NO P-AUTO 2-BKR-30-460 I DYES 2-HS-30-460C DNO P-AUTO 2-BKR-30-452 I DYES 2-HS-30-452C D NO PULL 1-BKR-30-449 I DYES STANDBY 1-HS-30-449C D NO N/A 1-BKR-30-493 DYES D NO P-AUTO 1-BKR-30-461 I DYES 1-HS-30-461 C DNO P-AUTO 1-BKR-30-453 I DYES 1-HS-30-453C DNO PULL 2-BKR-30-450 I DYES STANDBY 2-HS-30-450C D NO N/A 2-BKR-30-494 DYES D NO P-AUTO 2-BKR-30-462 I DYES 2-HS-30-462C DNO P-AUTO 2-BKR-30-454 I DYES 2-HS-30-454C DNO Performer's SRO's Initials Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 15 of 15) 1-SI-0-2A-03 Rev. 0030 Page 36 of 39 Mode 3 Surveillance Log: 1900-0700 WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 15 of 15) 1-SI-0-2A-03 Rev. 0030 Page 36 of 39 Mode 3 Surveillance Log: 1900-0700
) WBN 1900 -0700 Unit 1 Shift And Daily Surveillance Log Date ___ _ Mode Three Data Sheet 2 (Page 1 of 1) Inoperable Components 1-SI-0-2A-03 Rev. 0030 Page 37 of 39 Page ___ _ of ----IF any of the following components are inoperable (when required OPERABLE) during the 1900 -0700 shift, THEN the applicable Data Sheets from 1-SI-0-2-00 are to be performed and attached to this package: INOPERABLE COMPONENT CST Level Inoperable Ice Condenser Inlet Door Monitoring System Inoperable Ice Bed Monitoring System Inoperable Unit 1 Shield Building Stack Flow Monitor Inoperable Diffuser Discharge Effluent Flow Monitor Inoperable CVES Flow Monitor Inoperable Auxiliary Building Stack Flow Monitor Inoperable Liquid Radwaste Effluent Line Flow Monitor Inoperable Condensate Demin Effluent Flow Monitor Inoperable SGBD to CTBD Flow Monitor Inoperable Service Building Stack Flow Monitor ICS Out Of Limit Hourly Temperature Periodic Temperature Check from DG Bldg Roof Remarks: 1-51-0-2-00 DATA SHEET Data Sheet 3 0 Data Sheet 23 0 Data Sheet 24 0 Data Sheet 37 0 Data Sheet 38 0 Data Sheet 45 0 Data Sheet 51 0 Data Sheet 55 0 Data Sheet 58 0 Data Sheet 60 D Data Sheet 62 D Data Sheet 63 D Data Sheet 65 D Data Sheet 66 D INITIALS WBN Unit 1 Date 1900 -0700 Shift And Daily Surveillance Log ----Mode Three Data Sheet 2 (Page 1 of 1) Inoperable Components 1-SI-0-2A-03 Rev. 0030 Pa_ge 37 of 39 Page ___ _ of ___ _ IF any of the following components are inoperable (when required OPERABLE) during the 1900 -0700 shift, THEN the applicable Data Sheets from 1-SI-0-2-00 are to be performed and attached to this package: INOPERABLE COMPONENT CST Level Inoperable Ice Condenser Inlet Door Monitoring System Inoperable Ice Bed Monitoring System Inoperable Unit 1 Shield Building Stack Flow Monitor Inoperable Diffuser Discharge Effluent Flow Monitor Inoperable CVES Flow Monitor Inoperable Auxiliary Building Stack Flow Monitor Inoperable Liquid Radwaste Effluent Line Flow Monitor Inoperable Condensate Demin Effluent Flow Monitor Inoperable SGBD to CTBD Flow Monitor Inoperable Service Building Stack Flow Monitor ICS Out Of Limit Hourly Temperature Periodic Temperature Check from DG Bldg Roof Remarks: 1-51-0-2-00 DATA SHEET Data Sheet 3 D Data Sheet 23 D Data Sheet 24 D Data Sheet 37 D Data Sheet 38 D Data Sheet 45 D Data Sheet 51 D Data Sheet 55 D Data Sheet 58 D Data Sheet 60 D Data Sheet 62 D Data Sheet 63 D Data Sheet 65 D Data Sheet 66 D INITIALS
') ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three 38 of 39 Attachment 1 (Page 1 of 1) Determining Annulus AP TIS Limit SHIELD VENT STACK ADJUSTED Annulus SHIELD VENT STACK ADJUSTED Annulus FLOW ICS Point Y2203A AP TIS Limit (IN WC) FLOW ICS Point Y2203A AP TIS Limit (IN WC) (SCFM)) (SCFM) 0 -5.50 14500 -5.80 500 -5.50 15000 -5.82 1000 -5.50 15500 -5.84 1500 -5.50 16000 -5.86 2000 -5.51 16500 -5.88 2500 -5.51 17000 -5.91 3000 -5.52 17500 -5.93 3500 -5.52 18000 -5.95 4000 -5.53 18500 -5.98 4500 -5.53 19000 -6.01 5000 -5.54 19500 -6.03 5500 -5.55 20000 -6.06 6000 -5.55 20500 -6.09 6500 -5.56 21000 -6.12 7000 -5.57 21500 -6.14 7500 -5.58 22000 -6.17 8000 -5.59 22500 -6.20 8500 -5.61 23000 -6.24 9000 -5.62 23500 -6.27 9500 -5.63 24000 -6.30 10000 -5.65 24500 -6.33 10500 -5.66 25000 -6.37 11000 -5.67 25500 -6.40 11500 -5.69 26000 -6.44 12000 -5.71 26500 -6.47 12500 -5.72 27000 -6.51 13000 -5.74 27500 -6.55 13500 -5.76 28000 -6.58 14000 -5.78 NOTES 1) Shield Bldg Vent Stack Flow reading to be taken from ICS log pt Y2203A or 1-FI-90-400.
IF ICS point and flow indicator are unavailable, perform Data Sheet 37 of 1-SI-0-2-00 to determine shield building flow. 2) If flow reading is between two values, use next higher flow value. i i WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 38 of 39 Attachment 1 (Page 1 of 1) Determining Annulus AP TIS Limit SHIELD VENT STACK ADJUSTED Annulus SHIELD VENT STACK ADJUSTED Annulus FLOW ICS Point Y2203A TIS Limit (IN WC) FLOW ICS Point Y2203A TIS Limit (IN WC) (SCFM)) (SCFM) 0 -5.50 14500 -5.80 500 -5.50 15000 -5.82 1000 -5.50 15500 -5.84 1500 -5.50 16000 -5.86 2000 -5.51 16500 -5.88 2500 -5.51 17000 -5.91 3000 -5.52 17500 -5.93 3500 -5.52 18000 -5.95 4000 -5.53 18500 -5.98 4500 -5.53 19000 -6.01 5000 -5.54 19500 -6.03 5500 -5.55 20000 -6.06 6000 -5.55 20500 -6.09 6500 -5.56 21000 -6.12 7000 -5.57 21500 -6.14 ) 7500 -5.58 22000 -6.17 8000 -5.59 22500 -6.20 8500 -5.61 23000 -6.24 9000 -5.62 23500 -6.27 9500 -5.63 24000 -6.30 10000 -5.65 24500 -6.33 10500 -5.66 25000 -6.37 11000 -5.67 25500 -6.40 11500 -5.69 26000 -6.44 12000 -5.71 26500 -6.47 12500 -5.72 27000 -6.51 13000 -5.74 27500 -6.55 13500 -5.76 28000 -6.58 14000 -5.78 NOTES 1) Shield Bldg Vent Stack Flow reading to be taken from ICS log pt Y2203A or 1-FI-90-400.
IF ICS point and flow indicator are unavailable, perform Data Sheet 37 of 1-SI-0-2-00 to determine shield building flow. . 2) If flow reading is between two values, use next higher flow value.
) WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Source Notes (Page 1 of 1) 1-SI-0-2A-03 Rev. 0030 Page 39 of 39 Requirements Statement Source Document See 1-SI-0-2-00 "Shift and Daily Surveillance Log Master" Implementing Statement ) WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Source Notes (Page 1 of 1) 1-SI-0-2A-03 Rev. 0030 Page 39 of 39 Requirements Statement Source Document See 1-SI-0-2-00 "Shift and Daily Surveillance Log Master" Implementing Statement WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam A.2-1 SRO Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." PAGE 1 OF 17 WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam A.2-1 SRO Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." PAGE 1 OF 17 Task: Alternate Path: Facility JPM #: WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam EVALUATION SHEET Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." N/A New Safety Function:
N/A Title: N/A KIA 2.2.12 Knowledge of surveillance procedures Rating(s):
3.7/4.1 CFR: Preferred Evaluation Location:
Preferred Evaluation Method: Simulator X Classroom Perform X Simulate
References:
Task Number: Task Standard:
Validation Time: 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Rev. 30. RO-113-GEN-004 Title: Perform surveillance tests. Applicant reviews data collected for Data Sheet 1, pages 1 through 4 of 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." identifies instruments that do not meet the acceptable range identified in the instruction, and implements the corrective actions for the identified instruments.
minutes Time Critical:
Yes No X ---===========================================================================
Applicant:
Time Start: NAME SSN Time Finish: Performance Rating: SAT UNSAT Performance Time Examiner:
_________
__ ----------------------.1------
NAME SIGNATURE DATE ===========================================================================
COMMENTS PAGE 2 OF 17 Alternate Path: Facility JPM #: WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam EVALUATION SHEET Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." N/A New Safety Function:
N/A Title: N/A KIA 2.2.12 Knowledge of surveillance procedures Rating(s):
3.7/4.1 Preferred Evaluation Location:
Preferred Evaluation Method: Simulator X Classroom Perform X Simulate -----=-=----
References:
Task Number: Task Standard:
Validation Time: 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Rev. 30. RO-113-GEN-004 Title: Perform surveillance tests. Applicant reviews data collected for Data Sheet 1, pages 1 through 4 of 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." identifies instruments that do not meet the acceptable range identified in the instruction, and implements the corrective actions for the identified instruments.
minutes Time Critical:
Yes No X _----C-__ _ ===========================================================================
Applicant:
Time Start: NAME SSN Time Finish: __ _ Performance Rating: SAT UNSAT Performance Time Examiner:

1_-----

NAME SIGNATURE DATE ===========================================================================
COMMENTS PAGE 2 OF 17
) ) WATTS BAR NUCLEAR PLANT .A.2-1 SRO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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. The Unit is in Mode 3 with RCS temperature controlled by the Steam Dumps at 557°F, with no LCO entries at this time. 2. Portions of the field data have been entered by ROs and NAUOs. 3. You are the Unit Supervisor and the Shift Manager assigned to review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three" for discrepancies and take appropriate action(s), if any, once the review is complete.
INITIATING CUES: 1. You are to review 1-SI-0-2A-03,"1900-0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, [pages 1 through 4](of 15.) 2. When you have finished reviewing the assigned pages of Data Sheet 1, address any deviations, and identify any actions required by Technical Specifications.
PAGE 3 OF 17 WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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. The Unit is in Mode 3 with RCS temperature controlled by the Steam Dumps at 557°F, with no LCO entries at this time. 2. Portions of the field data have been entered by ROs and NAUOs. 3. You are the Unit Supervisor and the Shift Manager assigned to review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three" for discrepancies and take appropriate action(s), if any, once the review is complete.
INITIATING CUES: 1. You are to review 1-SI-0-2A-03,"1900-0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, [pages 1 through 4](of 15.) 2. When you have finished reviewing the assigned pages of Data Sheet 1, address any deviations, and identify any actions required by Technical Specifications.
PAGE 3 OF 17
',--i' WATTS 81 NUCLEAR PLANT ')d-1 SRO Nov. 2009 NRC Exam S'IMULATOR OPERATOR INSTRUCTIONS:
1. ENSURE NRC Examination Security has been established.
2. Right click on 319, and then select RESET. 3. Enter the password.
4. Select "Yes" on the INITIAL CONDITION RESET pop-up window. 5. ENSURE the following information .appears on the Director Summary Screen: pi-1-2a 05150 s9 #1 stm hdr eh 1 0 00:00:00 00:00:00 pi-1-2b 05150 s9 #1 stm hdr eh 2 0 00:00:00 .00:00:00 pi-1-5 05150 s9 #1 main stm hdr 0 00:00:00 00:00:00 1i-3-55 05050 s9 #2 level ind 0 00:00:00 00:00:00 1i-68-335a 05350 res przr Ivl(m-4) 0 00:00:00 00:00:00 1i-63-52 09030 sis rwst level ind 0 00:00:00 00:00:00 6. Place simulator in RUN and acknowledge any alarms. 7. Place simulator in FREEZE until Examiner cue is given. PAGE 4 OF 17 00:00:00 1045 1044.98 00:00:00 1055 1054.97 00:00:00 1150 1149.99 00:00:00 30 37.8133 00:00:00 35 34.9986 00:00:00 90 89.9991 WATTS 81 NUCLEAR PLANT k.2-1 SRO Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
1. ENSURE NRC Examination Security has been established.
2. Right click on 319, and then select RESET. 3. Enter the password.
4. Select "Yes" on the INITIAL CONDITION RESET pop-up window. 5. ENSURE the following information appears on the Director Summary Screen: Key Type Event Delay Inserted pi-1-2a 05150 sg #1 stm hdr eh 1 0 00:00:00 00:00:00 pi-1-2b 05150 sg #1 stm hdr eh 2 0 00:00:00 00:00:00 pi-1-5 05150 sg #1 main stm hdr 0 00:00:00 00:00:00 li-3-55 05050 sg #2 level ind 0 00:00:00 00:00:00 li-68-335a 05350 res przr Ivl(m-4) 0 00:00:00 00:00:00 1i-63-52 09030 sis rwst level ind 0 00:00:00 00:00:00
6. Place simulator in RUN and acknowledge any alarms. 7. Place simulator in FREEZE until Examiner cue is given. PAGE 4 OF 17 Ramp Initial Final Value 00:00:00 1045 1044.98 00:00:00 1055 1054.97 00:00:00 1150 1149.99 00:00:00 30 37.8133 00:00:00 35 34.9986 00:00:00 90 89.9991
) /' ) WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ STEP 1: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 1,Reference 3 data collection and determine if Acceptance
'Criteria are met. 1-M-2 3 I Pnl 0-L-209 I CST A Level T15MI708 STANDARD:
1-Ll-2-230A Ii'" OR 1-Ll-2-230B 0 :?:2oo,000 gallons .... 3-,0,000 gallons Perform Data 8heet30f 1-81-0-2-00
CST Level" Applicant determines that 1-Ll-2-230A reading, approximately 390,000 gallons, is within acceptance criteria.
COMMENTS:
PAGE 5 OF 17 . SAT/UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD START TIME: __ _ EXAMINERS CUE: Provide a marked-up copy of 1-SI-0-2A-03 to applicant.
STEP 1: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 1, Reference 3 data collection and determine if Acceptance Criteria are met. 1-M-2 3 Pnl 0-L-209 CST A Level T15M1708 STANDARD:
1-Ll-2-230A OR 1-Ll-2-230B o :e 200,000 gallons .....
gallons Perform Data Sheet 3 of 1-SI-0-2-00 "CST Level" Applicant determines that 1-U-2-230A reading, approximately 390,000 gallons, is within acceptance criteria. ) COMMENTS:
PAGE 5 OF 17 SAT/UNSAT SAT UNSAT
) L ) STEP 2. 4 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference 4 data collection and determine if Acceptance Criteria are met. 1-PI-1-2A psig SG 1 Press 1-PI-1-2B psig 1-PI-1-5 t;.1J40 D 1-PI-1-9A
'1'-" I() I!Jo psig SG 2 Press i-PI-1-9B Operable, * '" IO£!M:) psig ContactSRO i-PI-1-12 Channel toet:> psig to Check, and" r 1()70 psig consult Tech 1-PI-1-20A MCD:<;;90 Specs. SG 3 Press i-PI-1-20B psig .. I\. 10110 psig 1-PI-1-23
... 107() psig 1-PI-1-27A
,,\'" I01f) psig SG4 Press 1-PI-1-27B
.1'-10"0 psig 1-PI-1-30 I'"""
psig EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. Applicable Tech Specs: COMMENTS:
PAGE 6 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT STEP 2. 4 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference 4 data collection and determine if Acceptance Criteria are met. 1-PI-1-2A SG 1 Press 1-PI-1-2B 1-PI-1-5 1-PI-1-9A SG 2 Press 1-PI-1-9S 1-PI-1-12 1-PI-1-20A SG 3 Press 1-PI-1-20S f---------1 1-PI-1-23 1-PI-1-27A SG 4 Press 1-PI-1-27B f---------j 1-PI-1-30 psig i-'-lObO psig p s l9..D .1'--lOBo psig Operable, _'" /080 psig Channel -' IDeO psig Check. and MCD:5: 90 /070 psig psig _I\. JOIIO psig ,I'-10 7() psig 'I'-101'0 psig .j\. 10",0 psig l'-1040 psig Contact SRO to consult Tech Specs. Applicant determines that SG 1 Pressure channel 1-PI-1-5 is NOT within '1 MCD of 90 psig. The applicant CIRCLES the 1150 psig value for 1-PI-1-5, I identifies' the associated Tech Specs and writes the Tech Specs in the space provided at the bottom of the data sheet page. EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. Applicable Tech Specs: 3.3.2, Function 1. e. Condition D -72 hrs to place channel in trip. 3.3.2, Function 4. d. (1), Condition D -72 hrs to place channel in trip. COMMENTS:
PAGE 6 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT
) L ) STEP 3: 5 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference 5 data collection and determine if Acceptance Criteria are met. U-3-42
% SG 1 Level 1-U-3-39 ...... % 1-U-3-38
% 1-U-3-55 Operable at <:.. ....... --aO % D SG2 Level 1-U-3-52 <! 32% NR [for -40 % ContactSRO 1-U-3-51 OPERABLE ... 40 % to loops], 1-U-3-97 Channel ....... 3S % consult Tech SG 3 Level 1-U-3-94 Check, and No.3e % Specs. 1-U-3-93 MCO:;,;e.O%
..-% 1-U-3-110
,.... .36 % SG4 Level 1-U-3-107 % 1-U-3-10e
"""" 38 % EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. Applicable Tech Specs: COMMENTS:
PAGE 7 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT STEP 3: 5 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 1, Reference 5 data collection and determine if Acceptance Criteria are met. 1-Ll-3-42
% SG 1 Level 1-Ll-3-39
"" % 1-Ll-3-38
..... % 1-Ll-3-55 Operable at ....... 30 % ) 1-Ll-3-52
0:32% NR [for -40 % Contact SRO 1-Ll-3-51 OPERABLE N 40 % to 1-Ll-3-97 loops], .38 % consult Tech Channel 1-Ll-3-94 Check, and N3e % Specs. SG 2 Level f---------I SG 3 Level 1-Ll-3-93 MCD SO; 6.0% ....... % 1-Ll-3-110
...... .38 % 1-Ll-3-107
....... 3e % 1-Ll-3-106
""'" 3e % SG4 Level f---------I Applicant determines that SG 2 Level channel 1-U-3-55 is NOT within MCD ) :s; 6.0%: The applicant CIRCLES the 29% value for 1-Ll-3-55, identifies the associated Tech Specs and writes the Tech Specs in the space provided at the bottom of the data sheet page. EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. Applicable Tech Specs: 3.3.2, Function 5. b, Condition I -72 hrs to place channel in trip. 3.3.2, Function 6. b, Condition M -72 hrs to place channel in trip. 3.3.3, Function 15, Condition A -Restore channel within 30 days. COMMENTS:
PAGE 7 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT
) STEP 4: 8 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 8 data collection and determine if Acceptance Criteria are met. Operable, Channel Check, and MCD Contact va.lue is plus or minus SR Neutron 1-NI-92-131A 1/2 decade SROto Mon CH I [0.3CR1 <CR2 Z CPSI2i consult <3.0CR1].
Tech Spec Reading should be the s. I 1-N 1-92-132A I average value Z SR Neutron observed over a CPS(2) Mon CH II 30 second period Applicant determines that the Source Range Monitors are Operable and within the MCD tolerance.
COMMENTS:
PAGE 8 OF 17 SAT/UNSAT SAT UNSAT STEP 4: 8 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 8 data collection and determine if Acceptance Criteria are met. Operable, Channel Check, and MCD SR Neutron 1-NI-92-131A value is plus or minus Mon CH I 1/2 decade Contact [O.3CR1 <CR2 Z SROto <3.0CR1].
CPSI2) consult Reading should be the Tech Spec s. SR Neutron 1-N 1-92-132A average value Mon CH II observed over a Z 30 second period CPS (2) Applicant determines that the Source Range Monitors are Operable and within the MCD tolerance.
COMMENTS:
PAGE 8 OF 17 SAT/UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam ) STEP/STANDARD SAT/UNSAT ) STEP 5: 9 1-M-4 STANDARD:
PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 9 data collection and determine if Acceptance Criteria are met. 1-Ll-68-339A Operable, less than or 1too24> % Contact PZRLevel 1-Ll-68-335A equal t080%, .... .3S' SRO Channel Check, a 1-Ll-68-320 MCD <6.0% ..... 27* Tech Spec % s. ----------_._-EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. Applicable Tech Specs: COMMENTS:
PAGE 9 OF 17 CRITICAL STEP SAT UNSAT STEP 5: 9 1-M-4 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 2, Reference 9 data collection and determine if Acceptance Criteria are met. 1-U-68-339A Operable, less than or "" Z(Q % Contact SRO 1-U-68-335A equal t080%, ./ ..... 3'5 consult
____________
Tech Spec 1-Ll-68-320 MCD:; 6.0% -'I.. 27 . % s. PZR Level Applicant determines that PZR Level channel 1-Ll-68-335A is NOT within MCD (:::; 6.0%). The applicant CIRCLES the value for1-L1-68-335A identifies the associated Tech Specs and writes the Tech Specs in the space provided at the bottom of the data sheet page. EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. ) Applicable Tech Specs: 3.3.3, Function 13, Condition A -Restore within 30 days. COMMENTS:
PAGE 9 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT r STEP 6: 10 1-M-5 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 10 data collection and determine if Acceptance Criteria are met. PZR Press 1-PI-68-340A 1-PI-68-334 1-PI-68-323 1-PI-68-322 Operable -J> 1. z.r" psig channel check, Z ZI B psig greater than or equal to 2214psig and -z.ZZO psig MCDs 55 psig. "., fit" .
pSlg Contact SRO to consult Tech Spec s Applicant determines that all PZR Pressure channels meet acceptance criteria.
However, the difference between 1-PI-68-340A and 1-PI-68-334 is 47 psig, which is greater than 80% of the MCD, and requires that a Work Order be written. COMMENTS:
PAGE 10 OF 17 SAT/UNSAT SAT UNSAT STEP 6: 10 1-M-5 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 10 data collection and determine if Acceptance Criteria are met. PZR Press l-PI-68-340A l-PI-68-334 l-P 1-68-323 l-PI-68-322 Operable -i' .. Z. z.r. psig channel check, -r-Z ZI B psig greater than or equal to 2214psig and f'I---z..ZZO psig MCDs 55 psig. \t-', z:z.!,O psig Contact SRO to consult Tech Spec s Applicant determines that all PZR Pressure channels meet acceptance criteria.
However, the difference between 1-PI-68-340A and 1-PI-68-334 is 47 psig, which is greater than 80% of the MCD, and requires that a Work Order be written. COMMENTS:
PAGE 10 OF 17 SAT/UNSAT SAT UNSAT
) " STEP 7: 15 I 1-M-5 I . STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD I SAT/UNSAT PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference SAT 15 data collection and determine if Acceptance Criteria are met. UNSAT RCS Loops RCP Status 1,2,3,4 RCP 1 1-HS-68-8AA 1-HS-68-8BA 1-HS-68-31AA RCP2 1-HS-68-31BA RCP 3 I 1-HS-68-50AA 1-HS-68-50BA RCP 4 I 1-HS-68-73AA
1-HS-68-73BA Two loops operable; two loops in operation if capable of rod withdrawal (one loop jf NOT) RCP 1 2 3 4 ON lif'1W' Ii!'"Iir"" OFFD D D D t+/-j ll) Contact .... SRO to consult (Z. (1)
Spec \1) e. (1) Applicant determines that acceptance criteria are met. COMMENTS:
PAGE 11 OF 17 STEP 7: 15 1-M-5 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 15 data collection and determine if Acceptance Criteria are met. RCS Loops RCP Status 1,2,3,4 RCP 1 1-HS-68-8AA Two loops operable; 1-HS-68-8BA hllo loops in operation 1-H S-68-31 AA if capable of rod RCP2 1-HS-68-31BA vvithdrawal (one loop if 1-H S-68-50AA NOT) RCP 3 1-H S-68-50BA RCP4 1-HS-68-73AA 1-HS-68-73BA RCP 1 2 3 4 ON Iif'IiI'"
....... OFF 0 DOD (t (1) (1) (1) e. (1) Contact SRO to consult Tech Spec s. Applicant determines that acceptance criteria are met. COMMENTS:
PAGE 11 OF 17 SAT/UNSAT SAT UNSAT
\ STEP 8: Ref I Location I 16 I 1-M-6 WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 16 data collection and determine if Acceptance Criteria are met. Description Instrument
T S Limit Data I Acc NOT Met RWSTto RHR 1-FCV-63-1 OPEN I§(' ECCS Suction (1-HS-63-1A)
CLOSED D OPEN SI Pumps to CL 1, 1-FCV-63-22 OPEN IE" 2,3,4 (1-HS-63-22A)
CLOSED D Shunt BKR 1A1-A OFF Contact SRO to cl2E1 1-BKR-63-1 A At least one ON OR consult breaker OFF I Breaker 1-BKR-63-1 B OFF I Tech Specs. 480V Rx 1A i-A cl10A ON D MOV Boards I Shunt BKR 1B1-B OFF cl2F2 1-BKR-63-22A At least one ON OR Breaker 1-BKR-63-22B breaker OFF OFF lit""" 1B1-B cl11D ON D STANDARD:
Applicant determines that all acceptance criteria are met for 1-FCV-63-1 and 1-FCV-63-22.
COMMENTS:
PAGE 12 OF 17 SAT/UNSAT SAT UNSAT STEP 8: Ref Location 16 1-M-6 48DV Rx MOV Boards STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 16 data collection and determine if Acceptance Criteria are met. Description Instrument
T S Limit Data Acc NOT Met RWSTto RHR 1-FCV-63-1 OPEN IIit ECCS Suction (1-HS-63-1A)
CLOSED 0 OPEN (i( SI Pumps to CL 1, 1-FCV-63-22 OPEN 2,3,4 (1-HS-63-22A)
CLOSED 0 Shunt BKR 1A1-A 1-BKR-63-1 A OFF 0 Contact SRO to c!2E1 At least one ON 1!!1'" OR consult Breaker 1-BKR-63-1 B breaker OFF OFF rr-Tech Specs. 1A1-A cl1DA ON 0 Shunt BKR 1B1-B 1-BKR-63-22A OFF c/2F2 At least one ON OR Breaker 1-BKR-63-22B breaker OFF OFF 1B1-B c!11D ON 0 Applicant determines that all acceptance criteria are met for 1-FCV-63-1 and 1-FCV-63-22.
COMMENTS:
PAGE 12 OF 17 SATIUNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam '\ rl-------------------------------------------------------------------------------------------.------------------, STEP/STANDARD SATIUNSAT STEP 9: 17 1-M-6 STANDARD:
PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 17 data collection and determine if Acceptance Criteria are met. i-U-63-180 Operable, 0 % CNTMT i-Ll-63-181 Channel check, 0 0/0 Sump Level 1-U-53-i82 and 0 % 1-U-63-183 MCD0;;6.0%
0 % Contact SRO to .... eye consult Tech i-Ll-63-50 Operable, % Specs RWSTLevel i-U-63-51 Channel check, ",,-t-11?> % i-U-53-52 and MCDC """"0 % :> HI-53-53 0;;7.0% 4. "til % Applicant determines that CNTMT SUMP channels meet acceptance criteria.
.

.
i3.**WQ"rk
.:;x; **
.. :,. **. , . <: "4'!' ' *;;;; ** ily ** 1!..
7; i;'i; ;*/4"," ." . .*.. . ***..** f.**I;;.,.
,. ",. ," .. /07 .. * "
LEStl1E3vaJye EVALUATOR NOTE: This channel is NOT a PAM designated channel. EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. Applicable Tech Specs:
.
,,/" "".>.<; ,
',.;/Ah!%J<:;"x>, ,W/<:, .'.:'<"'" ,'" ,',;> ."",-;,,,,,,,,,.rJ'i""""'"
,/>,,/ "/""'" ",;L .,.<','/",<:C/'-'" ',;"",///y,,Jv,/.,',,, hpurs. COMMENTS:
PAGE 13 OF 17 CRITICAL STEP SAT UNSAT STEP 9: STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 17 data collection and determine if Acceptance Criteria are met. % Operable, 0 1--------1 Channel check, and 0 % MCD:::6.0%
c> % Contact SRO to consult Tech Operable, "" q e % Specs Channel check, A. % 1--------1 and MCDC ..". q 0 %;; :::7.0% A. % Applicant determines that CNTMT SUMP channels meet acceptance criteria.
Applicant determines that 1-Ll-63-53 RWST Level channel does NOT meet acceptance criteria, and requires that a Work Order be written. The ) applicant CIRCLES the value for 1-Ll-63-53.
! EVALUATOR NOTE: This channel is NOT a PAM designated channel. EVALUATOR NOTE: The applicant may determine the need to write a Work Order to troubleshoot and repair the channel. This is NOT REQUIRED to satisfy the CRITICAL STEP. Applicable Tech Specs: 3.3.2, Function 7.b, Condition K, Place channel in BYPASS within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . COMMENTS:
PAGE 13 OF 17 SAT/UNSAT CRITICAL STEP SAT UNSAT STEP 10: 18 I 1-M-6 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 18 data collection and determine if Acceptance Criteria are met. CL Accum 1 Outlet 1-FCV-63-118 OPEN IJ!l'" (1-HS-63-118A)
CLOSED CL Accum 2 Outlet 1-FCV-63-98 Valves OPEN (1-HS-63-98A)
Open-when Pzr CLOSED Contact SRO to CL Accum 3 Outlet 1-FCV-63-80 pressure OPEN consult ( 1-HS-63-80A)
>1000 psig. CLOSED 0 Tech Specs. CL Accum 4 Outlet 1-FCV-63-67 OPEN I!I'" (1-HS-63-67A)
CLOSED 0 Applicant determines that all valves are in their required positions and meet acceptance criteria.
COMMENTS:
PAGE 14 OF 17 SAT/UNSAT SAT UNSAT STEP 10: 18 1-M-6 STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference 18 data collection and determine if Acceptance Criteria are met. CL Accum 1 Outlet 1-FCV-63-118 OPEN IH" (1-HS-63-118A)
CLOSED 0 CL Accum 2 Outlet 1-FCV-63-98 Valves OPEN Ii!" (1-HS-63-98A)
Open-when Pzr CLOSED 0 Contact SRO to consult CL Accum 3 Outlet 1-FCV-63-80 pressure OPEN I!!'" Tech Specs. ( 1-HS-63-80A)
>1000 psig. CLOSED 0 CL Accum 4 Outlet 1-FCV-63-67 OPEN [!( (1-HS-63-67A)
CLOSED 0 Applicant determines that all valves are in their required positions and meet acceptance criteria.
COMMENTS:
PAGE 14 OF 17 SAT/UNSAT SAT UNSAT WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam ') STEP/STANDARD SAT/UNSAT STEP 11: Ref I Location I 19 I I STANDARD:
PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 4, Reference 19 data collection and determine if Acceptance Criteria are met. Description I Instrument
TS Limit Data I Ace NOT Met CLAccum 1 1 129 ,/ 78\0 flal Lvi I 'I 1 '19 d630 and S:8000 78'0 gal CLAccum2 I I gal and MCO s: 96 j..1SIt;'
gal Check operability gaL Chemist!'1 is to by acceptable Lvi I be notilied to "'" iSi'5" gal deviation betvveen perform 'I I--7e&0 gal redundant level and CLAccum3 I 'I within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if tank" pressure channels Lvi I '1 level is increased?
.1'1 '" 7810 gal when pressurizer 75 gal and tank NOT pressure is above CLAccum4 'I lilled from RWST(11 /' V7Bro gal 1000 psig If deviation limit is Lvi
,. "'-reto gal exceeded, CLAccum 1 1 128 .. psig determine the Press 1 i'--fD3S'" psig channel AND record only CLAccum 2 I
.,I ""4" psig the operable Press I 2610 and S:13130 psi9 .... .... b'lO psig channel, Trlis 1 106 channel check is and IvIeD s: 30 "40 psig NOT a technical CLAccum 3 psig(1) ; specification Press , ""'0 psig CLAccum4
,.,
psig Press
1.-psig Applicant determines that all Cold Leg accumulator level and pressure channels meet acceptance criteria.
COMMENTS:
PAGE 15 OF 17 SAT UNSAT STEP 11: Ref Location 19 'I-M-6 ) STANDARD:
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 4, Reference 19 data collection and determine if Acceptance Criteria are met. Description Instrument
T S Limit Data Acc NOT Met CL Accum 1 1-U-63-129 ,I< 7810 gal Lvi 'J-U-63-n 9 2:7630 and s8000 ... 18,0 gal 1-U-63-109 qal and MCD s 96 qal Check operability CLAccum 2 gal Chemistry is to .... by acceptable Lvi 1-L1-63-99 be notified to .... iSt':) gal deviation between perform'I-SI-63-6 7el0 gal redundant level and CLAcclim 3 'I-Ll-63-S9 within 6 Ilours if tank" pressure channels Lvi 1-Ll-63-8'J level is increased 2: "
gal when pressurizer 75 gal and tank NOT pressure is above CLAcGum4 '1-Ll-63-82 filled from R'NSr") '" V18ro gal 1000 psig If deviation limit is Lvi 1-Ll-63-60
...
gal exceeded, CLAccum 1 J-PI-63-'128
,-psig determine the Press fD 3 S'" psig channel inoper-able 1-PI-63-126 AND record only CL Accum 2 1-PI-63-W8 psig the operable channel This Press 1-PI-63-106 2:6 Wand s660 psi9 ..... ',.;/qqo psig channel clleck is and rvlCD s 30 NOT a technical CLAccum 3 1-PI-63-88 psig (il ... psig Press I-PI-63-86 psig specification re-qllirement CLAccum 4 1-PI-63-62
..., 'r-bqQ psig Pre.55 1-PI-63-I3'J
.>'If; "30 psig Applicant determines that all Cold Leg accumulator level and pressure channels meet acceptance criteria.
COMMENTS:
PAGE 15 OF 17 SAT/UNSAT SAT UNSAT
) /L.. STEP 12: WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 4, Reference 20 data collection and determine if Acceptance Criteria are met. l-PDI-30-42 iY Operable, Channel 0 psig (2) or Point P1000A 0 Check, anel MCD 01 1-PDI-30-43 the foil owing: 0 or Point P1001A MCD <;; 1.0 psig (Ind] psig (2) Contact SRO to 20 I 1-M-6 or I CNTMT Press consult Tech Specs ICS 1-PDI-30-44 IVICD <;; 0.8 psig or Point P1002A (mixed) 0 psig(2) 1-PDI-30-45 MCD <;; 0.5 psig 0 psig(2) or Point P1003A 0 (computer)
STANDARD:
Applicant determines that all channels meet acceptance criteria.
COMMENTS:
SAT/UNSAT SAT UNSAT STOP TIME __ _ ') PAGE 16 OF 17 STEP 12: WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 4, Reference 20 data collection and determine if Acceptance Criteria are met. 1-PDI-30-42 tY' Operal)le, Channel 0 or Point P1000A 0 Check, and Iv1CD of psig (2j 1-PDI-30-43 tY' the following:
or Point P1001A 0 0 psig e2j 'I-M-6 or MCD s 1_0 psig (Incl) Contact SRO to 20 CNTMT Press ICS consult Tecf, Specs l-PDI-30-44 MCD';; 0,8 psig or Point P1002A 0 (mixed) 0 psig en 1-PDI-30-45 IT MCD,;; 0.5 psig 0 or Point P1003P, 0 (computer) . C) PSI<;l' STANDARD:
Applicant determines that all channels meet acceptance criteria.
COMMENTS:
STOP TIME __ _ PAGE 16 OF 17 SATIUNSAT SAT UNSAT
",-,-APPLICANT CUE. SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) ) DIRECTION TO APPLICANT:.
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. The Unit is in Mode 3 with RCS temperature controlled by the Steam Dumps at 557°F, with no LCO entries at this time. 2. Portions of the field data have been entered by ROs and NAUOs. 3. You are the Unit Supervisor and the Shift Manager assigned to review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three" for discrepancies and take appropriate action(s), if any, once the review is complete. ) INITIATING CUES: / ') 1. You are to review 1-SI-0-2A-03,"1900-0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, [pages 1 through 4](of 15.) 2. When you have finished reviewing the assigned pages of Data Sheet 1, address any deviations, and identify any actions required by Technical Specifications.
A.2-1 SRO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) ) DIRECTION TO APPLICANT:
'> ) 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. The Unit is in Mode 3 with RCS temperature controlled by the Steam Dumps at 557°F, with no LCO entries at this time. 2. Portions of the field data have been entered by ROs and NAUOs. 3. You are the Unit Supervisor and the Shift Manager assigned to review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three" for discrepancies and take appropriate action(s), if any, once the review is complete.
INITIATING CUES: 1. You are to review 1-SI-0-2A-03,"1900-0700 Shift and Daily Surveillance Log Mode Three," Data Sheet 1, [pages 1 through 4](of 15.) 2. When you have finished reviewing the assigned pages of Data Sheet 1, address any deviations, and identify any actions required by Technical Specifications.
A.2-1 SRO
) [ml Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-SI-0-2A-03 1900 -0700 Shift And Daily Surveillance Log Mode Three Revision 0030. Quality Related Level of Use: Continuous Use Effective Date: 03-19-2008 Responsible Organization:
OPS, Operations' Prepared By: Scot Newell Approved By: Kathy Keefer Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-SI-0-2A-03 1900 -0700 Shift And Daily Surveillance Log Mode Three Revision 0030. Quality Related Level of Use: Continuous Use Effective Date: 03-19-2008 Responsible Organization:
OPS, Operations Prepared By: Scot Newell Approved By: Kathy Keefer WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 ') Mode Three Page 2 of 39 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 26 02/01/06 2,3,14,15 Added additional MCD guidance (PER 74382). 23 Revised Ref. 21 and 22 to reflect Tech Spec change Package WBN-TS-04-17, which contains requirements for opening the penetrations in the Shield Bldg. Dome during Cycle 7 operation.
32 Added 1-FI-'90-400 for Shield Building Flow indication.
Added capability to use 1-FI-90-400 in Attachment
1. 27 08/04/06 All This procedure has been converted from Word 95 to Word 2002 XP using rev 26, by Austin Norris. All Changed verify to check or ensure. 7,9, 18,36 Moved Freq requirements to Step 1.2.2A. Changed all footnote references to superscript.
Deleted FRP references and footnotes oTo, ., and (14) for Step 1.2.2E; PER 74137. Changed step 6.1.M bullets to 6.1.N -P. Changed containment temperature to ICS on, Data Sheet 2. 28 10/18/06 2,22, Technical Specification change, WBN-TS-05-06 for Steam Generator secondary side water level. 26 Deleted Notes on Ref 21 and 22 to remove Tech Spec change WBN-TS-04-17, Shield Bldg Hatches. 29 TACF 1-05-0004-090, RM-90-106
& 112 alert and alarm setpoints returned to normal. 29 09/14/07 2,29 T ACF1-07 -0006-090 allows rad monitor , aligned to lower containment to have background setpoint adjusted from NE SSD setpoint due to RCS leak inside containment.
30 03/19/08 2,29 Deleted foot note 1 for reference 25 for T ACF 1-07 -0006-090 RTN. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 2 of 39 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 26 02/01/06 2,3,14,15 Added additional MCD guidance (PER 74382). 23 Revised Ref. 21 and 22 to reflect Tech Spec change Package WBN-TS-04-17, which contains requirements for opening the penetrations in the Shield Bldg. Dome during Cycle 7 operation.
32 Added 1-FI-90-400 for Shield Building Flow indication.
Added capability to use 1-FI-90-400 in Attachment
1. 27 08/04/06 All This procedure has been converted from Word 95 to Word 2002 XP using rev 26, by Austin Norris. All Changed verify to check or ensure. 7,9, 18,36 Moved Freq requirements to Step 1.2.2A. Changed all footnote references to superscript.
Deleted FRP references and footnotes oTo, ., and (14) for Step 1.2.2E; PER 74137. Changed step 6.1.M bullets to 6.1.N -P. Changed containment temperature to ICS on. Data Sheet 2. 28 10/18/06 2,22, Technical Specification change, WBN-TS-05-06 for Steam Generator secondary side water level. 26 Deleted Notes on Ref 21 and 22 to remove Tech Spec change WBN-TS-04-17, Shield Bldg Hatches. 29 T ACF 1-05-0004-090, RM-90-106
& 112 alert and alarm setpoints returned to normal. 29 09/14/07 2,29 TACF 1-07-0006-090 allows rad monitor , aligned to lower containment to have background setpoint adjusted from NE SSD setpoint due to RCS leak inside containment.
30 03/19/08 2,29 Deleted foot note 1 for reference 25 for T ACF 1-07-0006-090 RTN.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 'j Mode Three Page 3 of 39 Table of Contents
1.0 INTRODUCTION
.............................................................
............................................
5 1.1 Purpose/ .........................................................................................................................
5 1.2 Scope ............................................................................................................................ 5 1.2.1 Operability Tests to be Performed
..................................................................
5 1.2.2 Surveillance Requirements Fulfilled
................................................................
7 1.3 Frequency and Conditions
..........................................................................................
1 0 *1.3.1 Performance Definitions
................................................................................
10 1.3.2 MCD Calculation Methods ............................................................................
10
2.0 REFERENCES
...........................................................................................................
11 2.1 Performance References
............................................................................................
11 2.2 Developmental References
.........................................................................................
11 2.2.1 TVA Procedures
............................................................................................
11 2.2.2 Vendor Manuals ............................................................................................
12 2.2.3 Other .............................................................................................................
12 ) 3.0 PRECAUTIONS AND LIMITATIONS
.........................................................................
13 4.0 PREREQUISITE ACTIONS ........................................................................................
14 4.1 Preliminary Actions .................................................................................
.....................
14 4.2 Approvals and Notifications
........................................................................................
14 5.0 ACCEPTANCE CRITERIA .........................................................................................
15 5.1 Test Acceptance Criteria ................................................................ , ............................
15 5.2 Notifications and Actions .............................................................................................
15 6.0 PERFORMANCE
........................................................................................................
16 6.1 Performance Requirements
........................................................................................
16 6.2 GENERAL.'
..................................................................................................................
19 7.0 POST PERFORMANCE ACTIVITIES
........................................................................
20 8.0 RECORDS ....................................................................................
.............................
21 8.1 QA Records ..........................................
.....................................................................
21 8.2 Non-QA Records ........................................................................................................
21 Data Sheet 1: Mode 3 Surveillance Log: 1900-0700
......................................................
22 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 3 of 39 Table of Contents
1.0 INTRODUCTION
..........................................................................................................
5 1.1 Purpose ........................................................................................................................
5 1.2 Scope ............................................................................................................................
5 1.2.1 Operability Tests to be Performed
..................................................................
5 1.2.2 Surveillance Requirements Fulfilled
................................................................
7 1.3 Frequency and Conditions
..........................................................................................
10 1.3.1 Performance Definitions
................................................................................
10 1.3.2 MCD Calculation Methods ............................................................................
10
2.0 REFERENCES
...........................................................................................................
11 2.1 Performance References
............................................................................................
11 2.2 Developmental References
.........................................................................................
11 2.2.1 TVA Procedures
............................................................................................
11 2.2.2 Vendor Manuals ............................................................................................
12 2.2.3 Other .............................................................................................................
12 3.0 PRECAUTIONS AND LIMITATIONS
.........................................................................
13 4.0 PREREQUISITE ACTIONS ........................................................................................
14 4.1 Preliminary Actions .....................................................................................................
14 4.2 Approvals and Notifications
........................................................................................
14 5.0 ACCEPTANCE CRITERIA .........................................................................................
15 5.1 Test Acceptance Criteria .............................................................................................
15 5.2 Notifications and Actions .............................................................................................
15 6.0 PERFORMANCE
........................................................................................................
16 6.1 Performance Requirements
........................................................................................
16 6.2 GENERAL ....................................................................................................................
19 7.0 POST PERFORMANCE ACTIVITIES
......................................................
..................
20 8.0 RECORDS ............................................................................................................
...... 21 8.1 QA Records ................................................................................................................
21 8.2 Non-QA Records ........................................................................................................
21 Data Sheet 1: Mode 3 Surveillance Log: 1900-0700
......................................................
22 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 4 of 39 Table of Contents (continued)
Data Sheet 2: Inoperable Components
...........................................................................
37 Attachment 1: Determining Annulus TIS Limit ..........................................................
38 Source Notes .............................................................................................
39 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 4 of 39 Table of Contents (continued)
Data Sheet 2: Inoperable Components
...........................................................................
37 Attachment 1: Determining Annulus LlP TIS Limit ..........................................................
38 Source Notes .............................................................................................
39 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 5 of 39
1.0 INTRODUCTION
1.1 Purpose This Instruction provides directions for the following:
A. Recording data required by Surveillance Requirements that can be satisfied on a log type data sheet on a shift and daily log. B. Initiation of appropriate actions for abnormal conditions.
1.2 Scope 1.2.1 Operability Tests to be Performed The following verifications are performed by this Instruction:
1. Annulus i1P Channel Checks: a. Annulus to Atmospheric i1P Channel Check. b. Annulus to Containment i1P Channel Check. 2. Condensate Storage Tank (CST) Volume. 3. CNTMT Pressure Channel Check. 4. CNTMT Purge Air Exhaust Channel Check. 5. CNTMT Sump Level Channel Check. 6. CNTMT Radiation Monitor Channel Check. 7. Control Room Air Intake Radiation Monitor Channel Check. 8. Emergency Core Cooling System (ECCS) Channel Checks: a. ECCS subsystems operable.
b. ECCS Cold Leg (CL) Accumulators Isolation Valve Alignment.
c. ECCS CL Accumulators Level Channel Check. d. ECCS CL Accumulators Pressure Channel Check. 9. Fuel Pool Area Radiation Monitor Channel Check. 10. Ice Condenser Door Position Channel Check. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 5 of 39
1.0 INTRODUCTION
1.1 Purpose This Instruction provides directions for the following:
A. Recording data required by Surveillance Requirements that can be satisfied on a log type data sheet on a shift and daily log. B. Initiation of appropriate actions for abnormal conditions.
1.2 Scope 1.2.1 Operability Tests to be Performed The following verifications are performed by this Instruction:
1. Annulus Channel Checks: a. Annulus to Atmospheric Channel Check. b. Annulus to Containment Channel Check. 2. Condensate Storage Tank (CST) Volume. 3. CNTMT Pressure Channel Check. 4. CNTMT Purge Air Exhaust Channel Check. 5. CNTMT Sump Level Channel Check. 6. CNTMT Radiation Monitor Channel Check. 7. Control Room Air Intake Radiation Monitor Channel Check. 8. Emergency Core Cooling System (ECCS) Channel Checks: a. ECCS subsystems operable.
b. ECCS Cold Leg (CL) Accumulators Isolation Valve Alignment.
c. ECCS CL Accumulators Level Channel Check. d. ECCS CL Accumulators Pressure Channel Check. 9. Fuel Pool Area Radiation Monitor Channel Check. 10. Ice Condenser Door Position Channel Check.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 6 of 39 -------------------
1.2.1 Operability Tests to be Performed (continued)
11. Ice Bed Temperature Channel Check. 12. Neutron Flux Instrumentation Channel Check. 13. Pressurizer (Pzr) Level Channel Check. 14. Pressurizer Pressure Channel Check. 15. RCWand ERCW Pump Run Times. 16. Refueling Water Storage Tank (RWST) Level Channel Check 17. SG Narrow Range Water Level Channel Check. 18. Steam Line Pressure Channel Check. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three PaJte 6 of 39 \ 1.2.1 Operability Tests to be Performed (continued)
11. Ice Bed Temperature Channel Check. 12. Neutron Flux Instrumentation Channel Check. 13. Pressurizer (pzr) Level Channel Check. 14. Pressurizer Pressure Channel Check. 15. RCWand ERCW Pump Run Times. 16. Refueling Water Storage Tank (RWST) Level Channel Check 17. SG Narrow Range Water Level Channel Check. 18. Steam Line Pressure Channel Check.
) ) "" (1 ) (2) (3) (4) (5) (6) (7) (8) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 7 of 39 1.2.2 Surveillance Requirements Fulfilled A. The following designators are used in the "Freq" column: 1 At least once per hour 4 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 8 At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months o At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months P Completed prior to each release B. Performance of this Instruction satisfies the following Surveillance Requirements (SRs): SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES MODES SR p3.3.1.1-5 2(1),3(2),(3) 2,3,4,5,6 4(2),(3), 5(2),(3) SR p3.3.2.1-1.c 1,2,3 1,2,3 SR p3.3.2.1-1.d 1,2,3(4) 1,2,3 SR p3.3.2.1-1.e 1,2,3(4) 1,2,3 SR p3.3.2.1-2.c 1,2,3 1,2,3 SR p3.3.2.1-3.b.(3) 1,2,3 1,2,3 SR p3.3.2.1-4.c 1,2(5),3(5) 1,2,3 SR p3.3.2.1-4.d.(1) 1,2(5),3(4),(5) 1,2,3 SR p3.3.2.1-4.d.(2) 3(5),(6) 3 SR p3.3.2.1-5.b 1,2(7), 3(7) 1,2,3 SR p3.3.2.1-6.b 1,2,3 1,2,3 SR p3.3.2.1-7.b 1,2,3,4 1,2,3,4 SR p3.3.2.1-B.b.(1) 1,2,3 1,2,3 SR p3.3.2.1-B.b.(2) 1,2,3 1,2,3 Ref Freq B S 20 S 10 S 4 S 20 S 20 S 20 S 4 S 4 S 5 S 5 S 17 S 10 S 10 S The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. Below the P-6 (Intermediate Range Neufron Flux) interlocks.
With RTBs closed and Rod Control System capable of rod withdrawal.
With RTBs open. In this condition, source range function does NOT provide reactor trip but does provide indication.
Above P-11 (Pressurizer Pressure) interlock.
Except when all MSIVs are closed & deactivated.
Function automatically blocked above P-11 (Pressurizer Interlock) setpoint and is enabled below P-11 when safety injection on Steam Line Pressure Low is manually blocked. Except when all MFIVs, MFRVs, and their bypass valves are closed and deactivated or isolated by a closed manual valve. NOT Used. ) (1 ) (2) (3) (4) (5) (6) (7) (8) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 7 of 39 1.2.2 Surveillance Requirements Fulfilled A. The following designators are used in the "Freq" column: 1 At least once per hour 4 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 8 At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months o At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months P Completed prior to each release B. Performance of this Instruction satisfies the following Surveillance Requirements (SRs): SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES MODES SR p3.3.1.1-5 2(1),3(2),(3) 2,3,4,5,6 4 (2),(3), 5(2),(3) SR p3.3.2.1-1.c 1,2,3 1,2,3 SR p3.3.2.1-1.d 1,2,3(4) 1,2,3 SR p3.3.2.1-1.e 1,2,3(4) 1,2,3 SR p3.3.2.1-2.c 1,2,3 1,2,3 SR p3.3.2.1-3.b.(3) 1,2,3 1,2,3 SR p3.3.2.1-4.c 1,2(5),3(5) 1,2,3 SR p3.3.2.1-4.d.(1) 1,2(5),3(4),(5) 1,2,3 SR p3.3.2.1-4.d.(2) 3(5),(6) 3 SR p3.3.2.1-5.b 1,2(7), 3(7) 1,2,3 SR p3.3.2.1-6.b 1,2,3 1,2,3 SR p3.3.2.1-7.b 1,2,3,4 1,2,3,4 SR p3.3.2.1-B.b.(1) 1,2,3 1,2,3 SR p3.3.2.1-B.b.(2) 1,2,3 1,2,3 Ref Freq B S 20 S 10 S 4 S 20 S 20 S 20 S 4 S 4 S 5 S 5 S 17 S 10 S 10 S The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. Below the P-6 (Intermediate Range Neutron Flux) interlocks.
With RTBs closed and Rod Control System capable of rod withdrawal.
With RTBs open. In this condition, source range function does NOT provide reactor trip but does provide indication.
Above P-11 (Pressurizer Pressure) interlock.
Except when all MSIVs are closed & deactivated.
Function automatically blocked above P-11 (Pressurizer Interlock) setpoint and is enabled below P-11 when safety injection on Steam Line Pressure Low is manually blocked. Except when all MFIVs, MFRVs, and their bypass valves are closed and deactivated or isolated by a closed manual valve. NOT Used.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 8 of 39 1.2.2 Surveillance Requirements Fulfilled (continued)
SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES Ref Freq MODES SR p3.3.6.1-3 1,2,3,4(9) 1,2,3,4,5,6 29 S SR p3.3.7.1-2 All (10) All 27 S SR p3.3.8.1-2 All (11) All (11) 26 S SR p3.4.9.1.r.
1,2,3 1,2,3 9 S SR p3.4.15.1 1,2,3,4 1,2,3,4 25 S SR p3.4.5.1 3 3 15 S SR p3.4.5.2.r.
3 3 5 S SRp3.5.1.1 1,2,3(12) 1,2,3 18 S SR p3.5.1.2 1,2,3(12) 1,2,3 19 S SR p3.5.1.3 1,2,3(12) 1,2,3 19 S SR p3.5.2.1 1,2,3 1,2,3 16 S SR p3.6.4.1 .r. 1,2,3,4 1,2,3,4 21 S SRp3.6.11.1.r.
1,2,3,4 1,2,3,4 24 S SR p3.6.12.1 1,2,3,4 1,2,3,4 23 S ) SR p3.6.15.1.r.
1,2,3,4 1,2,3,4 22 S SR p3.7.6.1 1,2,3,4(13) 1,2,3,4 3 S LCO p3.6.12 Action B.1 1,2,3,4 1,2,3,4 24 4 LCO p3.7.6 Action A1 1,2,3,4(13) 1,2,3,4 3 4&S "'" The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. (9) During movement of irradiated fuel assemblies within containment.
(10) Required in Modes 1 through 6, AND during movement of irradiated fuel assemblies.
(11) During movement of irradiated fuel assemblies within the fuel handling area. (12) With pressurizer pressure greater than 1000 psig. (13) When steam generator is relied upon for heat removal. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 8 of 39 1.2.2 Surveillance Requirements Fulfilled (continued)
SURVEILLANCE REQUIREMENTS APPLICABLE PERFORMANCE MODES Ref Freq MODES SR p3.3.6.1-3 1,2,3,4(9) 1,2,3,4,5,6 29 S SR p3.3.7.1-2 All (10) All 27 S . SR p3.3.8.1-2 All (11) All (11) 26 S SR p3.4.9.1 '" 1 ,2,3 1 ,2,3 9 S SR p3.4.15.1 1,2,3,4 1,2,3,4 25 S SR p3.4.5.1 3 3 15 S SR p3.4.5.2", 3 3 5 S SRp3.5.1.1 1,2,3(12) 1,2,3 18 S SR p3.5.1.2 1,2,3(12) 1,2,3 19 S SR p3.5.1.3 1,2,3(12) 1,2,3 19 S SR p3.5.2.1 1,2,3 1,2,3 16 S SR p3.6.4.1 '" 1 ,2,3,4 1 ,2,3,4 21 S SR p3.6.11.1
'" 1 ,2,3,4 1 ,2,3,4 24 S SR p3.6.12.1 1,2,3,4 1,2,3,4 23 S SR p3.6.15.1'" 1 ,2,3,4 1 ,2,3,4 22 S SR p3.7.6.1 1,2,3,4(13) 1,2,3,4 3 S . LCO p3.6.12 Action B.1 1,2,3,4 1,2,3,4 24 4 LCO p3.7.6 Action A1 1,2,3,4(13) 1,2,3,4 3 4&S "" The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. (9) During movement of irradiated fuel assemblies within containment.
(10) Required in Modes 1 through 6, AND during movement of irradiated fuel assemblies.
(11) During movement of irradiated fuel assemblies within the fuel handling area. (12) With pressurizer pressure greater than 1000 psig. (13) When steam generator is relied upon for heat removal.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 9 of 39 ----------
1.2.2 Surveillance Requirements Fulfilled (continued)
C. Performance of this Instruction satisfies or partially (p) satisfies the following Technical Surveillance Requirements (TSR): SURVEILLANCE APPLICABLE PERFORMANCE MODES Ref REQUIREMENTS MODES T5R p3.1.2.1 1,2,3 1,2,3 65 T5R p3.6.1.10f0 1,2,3,4 1,2,3,4 24 T5R p3.6.2.1 1,2,3,4 1,2,3,4 23 T5R p3.6.2.3 1,2,3,4 1,2,3,4 23 T5R p3.7.5.1 All All 65 TR p3.6.1 Action 8.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.3 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.2 Action A.1 1,2,3,4 1,2,3,4 24 -------_._-'" The mor.e conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. Freq 5 5 5 5 5 1&5 1 1&5 1&5 1 4 D. Performance of this Instruction satisfies the following Offsite Dose Calculation Manual Surveillance Requirements (OSRs): ODCM SURVEILLANCE APPLICABLE MODES PERFORMANCE MODES Ref REQUIREMENTS 05R p2.1.2-3.f All (20) AII(2O) 05R p2.1.2-4.e All All ----_ ... -(20) Both Unit 1 and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement.
59 59 E. Fulfillment of special conditions will initiate the following requirements:
SURVEILLANCE REQUIREMENTS APPLICABLE MODES PERFORMANCE MODES Ref TR p3.6.1 Action A.1 1,2,3,4 1,2,3,4 24 -------Freq D D Freq 5 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 9 of 39 1.2.2 Surveillance Requirements Fulfilled (continued)
C. Performance of this Instruction satisfies or partially (p) satisfies the following Technical Surveillance Requirements (TSR): SURVEILLANCE APPLICABLE PERFORMANCE MODES Ref REQUIREMENTS MODES T5R p3.1.2.1 1,2,3 1,2,3 65 T5R p3.6.1.1.r.
1,2,3,4 1,2,3,4 24 T5R p3.6.2.1 1,2,3,4 1,2,3,4 23 T5R p3.6.2.3 1,2,3,4 1,2,3,4 23 T5R p3.7.5.1 All All 65 TR p3.6.1 Action B.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action B.1.3 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.1 1,2,3,4 1,2,3,4 24 TR p3.6.1 Action C.1.2 1,2,3,4 1,2,3,4 24 TR p3.6.2 Action A.1 1,2,3,4 1,2,3,4 24 ... The mor.e conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSD) is used instead of the Tech Spec value. Freq 5 5 5 5 5 1&5 1 1&5 1&5 1 4 D. Performance of this Instruction satisfies the following Offsite Dose Calculation Manual Surveillance Requirements (OSRs): ODCM SURVEILLANCE APPLICABLE MODES PERFORMANCE MODES Ref REQUIREMENTS 05R p2.1.2-3.f AII(2O) AII(2O) 05R p2.1.2-4.e All All (20) Both Unit 1 and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement.
59 59 E. Fulfillment of special conditions will initiate the following requirements:
SURVEILLANCE REQUIREMENTS APPLICABLE MODES PERFORMANCE MODES Ref TR p3.6.1 Action A.1 1,2,3,4 1,2,3,4 24 Freq D D Freq 5
) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 10 of 39 1.3 Frequency and Conditions A. This Instruction is to be performed every 1900 -0700 shift when unit is in Mode 3. This instruction should be performed in Mode 4 prior to Mode 3 entry to ensure Mode 3 requirements are met. 1.3.1 Performance Definitions A. Channel Check -The qualitative assessment by observation of channel behavior during operation.
This determination includes, where pOSSible, comparison of the channel indication and status with other indications or status derived from independent instrument channels measuring the same parameter.
B. Maximum Channel Deviation (MCD) -The difference between the highest channel indication of a parameter and the lowest channel indication of the same parameter.
MCD units are the same as the applicable measured parameter units unless otherwise stated in applicable requirement.
If deviation limit is exceeded, determine which channel is inoperable AND Record only the operable channel unless stated otherwise.
Instrument Maintenance/Engineering shall assist in determining if operability limits have been exceeded.
C. Operable or Operability -A system, subsystem, train, component, or device is operable or has operability when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electrical power (normal or emergency), cooling, and seal water, lubrication, or other auxiliary equipment required for the system, subsystem, train, component, or device to perform its specified function(s) is also capable of performing its related support function(s).
1.3.2 MCD Calculation Methods See 1-SI-0-2-00 for explanation of MCD Calculations.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 10 of 39 1.3 Frequency and Conditions A. This Instruction is to be performed every 1900 -0700 shift when unit is in Mode 3. This instruction should be performed in Mode 4 prior to Mode 3 entry to ensure Mode 3 requirements are met. 1.3.1 Performance Definitions A. Channel Check -The qualitative assessment by observation of channel behavior during operation.
This determination includes, where possible, comparison of the channel indication and status with other indications or status derived from independent instrument channels measuring the same parameter.
B. Maximum Channel Deviation (MCD) -The difference between the highest channel indication of a parameter and the lowest channel indication of the same parameter.
MCD units are the same as the applicable measured parameter units unless otherwise stated in applicable requirement.
If deviation limit is exceeded, determine which channel is inoperable AND Record only the operable channel unless stated otherwise.
Instrument Maintenance/Engineering shall assist in determining if operability limits have been exceeded.
' C. Operable or Operability
-A system, subsystem, train, component, or device is operable or has operability when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electrical power (normal or emergency), cooling, and seal water, lubrication, or other auxiliary equipment required for the system, subsystem, train, component, or device to perform its specified function(s) is also capable of performing its related support function(s).
1.3.2 MCD Calculation Methods See 1-SI-0-2-00 for explanation of MCD Calculations.
) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 11 of 39
2.0 REFERENCES
2.1 Performance References A. Core Operating Limits Report. B. Nuclear Operating Book (NOB), 1. Sheet A-1, Target Band VS Power Level. 2. Sheet A-5, Negative MTC Withdrawal Limit Curve. C. SOI-90.02, Gaseous Process Radiation Monitors.
2.2 Developmental References 2.2.1 TVA Procedures A. 1-0DI-90-2, Steam Generator Blowdown Release B. 1-0DI-90-25, Condenser Vacuum Exhaust Release. C. 1-SI-63-6, Cold Leg Accumulators Boron Determination.
D. 1-SI-68-25, Recalibration of Channel I Reactor Coolant System Flow Loops. E. 1-SI-68-26, Recalibration of Channel II Reactor Coolant System Flow Loops. F. 1-SI-68-27, Recalibration of Channel III Reactor Coolant System Flow Loops. G. 1-SI-68-31, Reactor Coolant System Total Flow Measurement.
H. 1-SI-68.;.32, Reactor Coolant System Water Inventory Balance. I. 1-SI-68-68, 18 Month Channel Calibration RCS Loop 1 Wide Range Hot Leg Temperature Loop 1-LPT-68-1 (T-413A).
J. 1-SI-90-25, Inoperable Lower Containment Radiation Monitor. K. ECI-1.0, NPDES Plant Effluents.
L. Backup Ice Condenser Temperature Monitoring.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 11 of 39
2.0 REFERENCES
2.1 Performance References A. Core Operating Limits Report. B. Nuclear Operating Book (NOB), 1. Sheet A-1, Target Band VS Power Level. 2. Sheet A-5, Negative MTC Withdrawal Limit Curve. C. SOI-90.02, Gaseous Process Radiation Monitors.
2.2 Developmental References 2.2.1 TVA Procedures A. 1-001-90-2, Steam Generator Blowdown Release B. 1-001-90-25, Condenser Vacuum Exhaust Release. C. 1-SI-63-6, Cold Leg Accumulators Boron Determination.
D. 1-SI-68-25, Recalibration of Channel I Reactor Coolant System Flow Loops. E. 1-SI-68-26, Recalibration of Channel II Reactor Coolant System Flow Loops. F. 1-SI-68-27, Recalibration of Channel III Reactor Coolant System Flow Loops. G. 1-SI-68-31, Reactor Coolant System Total Flow Measurement.
H. 1-SI-68.;.32, Reactor Coolant System Water Inventory Balance. I. 1-SI-68-68, 18 Month Channel Calibration RCS Loop 1 Wide Range Hot Leg Temperature Loop 1-LPT-68-1 (T-413A).
J. 1-SI-90-25, Inoperable Lower Containment Radiation Monitor. K. ECI-1.0, NPDES Plant Effluents.
L. Backup Ice Condenser Temperature Monitoring.
) ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 12 of 39 2.2.1 TVA Procedures (continued)
M. Offsite Dose Calculation Manual (ODCM). N. SOI-14.03, Condensate Demineralizer Waste Disposal.
O. SOI-1S.01, Steam Generator Blowdown (SGBD) System. P. SOI-77.01, Liquid Waste Disposal.
2.2.2 Vendor Manuals A. VM-074S, Vendor (Technical)
Manual for Tracor Westronics Equipment.
B. VM-016S, Vendor (Technical)
Manual for Loose Parts Monitoring System. 2.2.3 Other NOTE Setpoint and Scaling Documents refer!3nced for Technical Specification Operability Limit clarification.
A. Fire Protection Report, Part II, Fire Protection Plan, Section 14.1. B. II-S-92-011 R1, Indicated Low Reactor Coolant System Flow. (TROIID: SON II-S-92-011 R1). C. N3-61-4001, System Description for the Ice Condenser System. D. Nuclear Operating Book (NOB), Sheet A-S. E. 1-4SW-60S-242, Electrical Tech Spec Compliance Tables. F. 1-4SW-60S-243, Electrical Tech Spec Compliance Tables. G. SOPER930138, Generic Applicability to Watts Bar Steam Generator PressurelTemperature Limitations SON LCO 3.7.2IWBN TR 3.7.1. H. Unit 1 Technical Requirements Manual 3.1.2.1,3.6.1,3.6.2,3.7.1.
I. Unit 1 Technical Specification 3.1.S, 3.1.6, 3.1.7, 3.3.1, 3.3.2, 3.3.6, 3.3.7, 3.3.8, 3.4.1,3.4.4,3.4.9, 3.4.1S, 3.S.1, 3.S.2, 3.6.4, 3.6.11, 3.6.12, 3.6.1S, 3.7.6. J. LER 97-013 DIG Operability with DIG exhaust or panel fan out of service. K. Annulus Differential Pressure Analysis, RIMS number T69 OS0321 003. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 12 of 39 2.2.1 TVA Procedures (continued)
M. Offsite Dose Calculation Manual (ODCM). N. SOI-14.03, Condensate Demineralizer Waste Disposal.
O. SOI-1S.01, Steam Generator Blowdown (SGBD) System. P. SOI-77.01, Liquid Waste Disposal.
2.2.2 Vendor Manuals A. VM-074S, Vendor (Technical)
Manual for Tracor Westronics Equipment.
B. VM-016S, Vendor (Technical)
Manual for Loose Parts Monitoring System. 2.2.3 Other NOTE Setpoint and Scaling Documents referenced for Technical SpeCification Operability Limit clarification.
A. Fire Protection Report, Part II, Fire Protection Plan, Section 14.1. B. II-S-92-011 R1, Indicated Low Reactor Coolant System Flow. (TROI 10: SON II-S-92-011 R1). C. N3-61-4001, System Description for the Ice Condenser System. D. Nuclear Operating Book (NOB), Sheet A-S. E. 1-4SW-60S-242, Electrical Tech Spec Compliance Tables. F. 1-4SW-60S-243, Electrical Tech Spec Compliance Tables. G. SOPER930138, Generic Applicability to Watts Bar Steam Generator PressurelTemperature Limitations SON LCO 3.7.2IWBN TR 3.7.1. H. Unit 1 Technical Requirements Manual 3.1.2.1, 3.6.1, 3.6.2, 3.7.1.
I. Unit 1 Technical Specification 3.1.S, 3.1.6, 3.1.7, 3.3.1, 3.3.2, 3.3.6, 3.3.7, 3.3.8, 3.4.1,3.4.4,3.4.9, 3.4.1S, 3.S.1, 3.S.2, 3.6.4, 3.6.11,3.6.12, 3.6.1S, 3.7.6. J. LER 97-013 DIG Operability with DIG exhaust or panel fan out of service. K. Annulus Differential Pressure Analysis, RIMS number T69 OS0321 003.
) 3.0 WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 13 of 39 PRECAUTIONS AND LIMITATIONS A. When BOTH a radiation monitor and recorder are listed, checking the recorder does NOT satisfy the Tech Spec requirement.
The monitor must be read to satisfy the requirement.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 13 of 39 3.0 PRECAUTIONS AND LIMITATIONS A. When BOTH a radiation monitor and recorder are listed, checking the recorder does NOT satisfy the Tech Spec requirement.
The monitor must be read to satisfy the requirement.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 14 of 39 Date __ _ Page __ _ 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions [1] RECORD start date and time on Surveillance Task Sheet. [2] IF required, THEN OBTAIN RWP. 4.2 Approvals and Notifications
[1] OBTAIN SM/Unit SRO approval on the Surveillance Task Sheet to perform this Instruction.
of ___ _ WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 14 of 39 Date __ _ Page __ _ 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions [1] RECORD start date and time on Surveillance Task Sheet. [2] IF required, THEN OBTAIN RWP. 4.2 Approvals and Notifications
[1] OBTAIN SM/Unit SRO approval on the Surveillance Task Sheet to perform this Instruction.
of __ _
WBN 1900 -0700* 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 15 of 39 ____ 5.0 ACCEPTANCE CRITERIA 5.1 Test Acceptance Criteria A. Specific quantitative or qualitative requirements that are intended to be checked by this Instruction are listed by each item where the data is recorded.
B. All data must be completed within four hours of shift relief to ensure 1.25 frequency is met. 5.2 Notifications and Actions A. Noncompliance with Acceptance Criteria requires Unit SRO notification as soon as safely possible.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Pajle 15 of 39 5.0 ACCEPTANCE CRITERIA 5.1 Test Acceptance Criteria A. Specific quantitative or qualitative requirements that are intended to be checked by this Instruction are listed by each item where the data is recorded.
B. All data must be completed within four hours of shift relief to ensure 1.25 frequency is met. 5.2 Notifications and Actions A. Noncompliance with Acceptance Criteria requires Unit SRO notification as soon as safely possible.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 16 of 39 6.0 PERFORMANCE 6.1 Performance Requirements A. Prior to making any mode changes which are more restrictive, review of the shift and daily data sheets is required to ensure compliance with applicable surveillance requirements for that mode. Starting new data sheets for the appropriate mode must be considered.
B. To meet MCD limits, data for individual instrument channels are required to be compared for deviation.
C. Items that require channel check that do NOT have an MCD listed in Tech Spec Limits column are to be considered acceptable when the following requirements are met: 1. Equipment is energized.
2. Indication is reading a value consistent with present plant conditions. (For radiation monitors, indication must be reading at least background.)
D. Exceeding the MCD column limits when performing Channel Checks may require considering the channel(s) inoperable unless stated otherwise.
Contact Instrument Maintenance/Engineering for operability determination.
E. Ensure meters are read consistently from same angle. Use gage face mirrors (if present) and ensure gage needle and its reflection are in alignment.
If gage has no mirror in the face, read gage from as close to perpendicular to gage face as possible.
F. Pegged High or Low meters: 1. If a meter indication is pegged high (or pegged low), a defensible channel deviation cannot be determined because of the uncertainty of the parameter being measured -the value could actually be greater (or less than) the pegged high or pegged low value. 2. In order for potential problems to be identified early, if the meter approaches to within two meter divisions of full scale high (or low), the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken . . 3. For any meter pegged high or low, ensure a WO is initiated.
The operability of this meter and any alarm, control, or protective functions of the associated loop should also be evaluated.
G. In order for potential problems to be identified early, if any channel deviation exceeds 80% of the MCD limit, the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken. ) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 16 of 39 6.0 PERFORMANCE 6.1 Performance Requirements A. Prior to making any mode changes which are more restrictive, review of the shift and daily data sheets is required to ensure compliance with applicable surveillance requirements for that mode. Starting new data sheets for the appropriate mode must be considered.
B. To meet MCD limits, data for individual instrument channels are required to be compared for deviation.
C. Items that require channel check that do NOT have an MCD listed in Tech Spec Limits column are to be considered acceptable when the following requirements are met: 1. Equipment is energized.
2. Indication is reading a value consistent with present plant conditions. (For radiation monitors, indication must be reading at least background.)
D. Exceeding the MCD column limits when performing Channel Checks may require considering the channel(s) inoperable unless stated otherwise.
Contact Instrument Maintenance/Engineering for operability determination.
E. Ensure meters are read consistently from same angle. Use gage face mirrors (if present) and ensure gage needle and its reflection are in alignment.
If gage has no mirror in the face, read gage from as close to perpendicular to gage face as possible.
F. Pegged High or Low meters: 1. If a meter indication is pegged high (or pegged low), a defensible channel deviation cannot be determined because of the uncertainty of the parameter being measured -the value could actually be greater (or less than) the pegged high or pegged low value. 2. In order for potential problems to be identified early, if the meter approaches to within two meter divisions of full scale high (or low), the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken. 3. For any meter pegged high or low, ensure a WO is initiated.
The operability of this meter and any alarm, control, or protective functions of the associated loop should also be evaluated.
G. In order for potential problems to be identified early, if any channel deviation exceeds 80% of the MCD limit, the Unit Supervisor should be notified so that the condition can be evaluated and appropriate corrective actions taken.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 17 of 39 6.1 Performance Requirements (continued)
H. Any work orders generated during performance of Data Sheets require documentation in Remarks at the bottom of the appropriate data sheet. I. Inoperable instruments are required to have INOP entered in the appropriate data space. J. Data spaces forinstruments in modes which do NOT apply can have N/A entered in them. K. The following are guidelines for radiation monitors and recorders:
CAUTION When source checking to determine operability, care should be used to prevent actuation of any high level trip or isolation function initiated by a radiation monitor. 1. Radiation levels are to be compared to data taken on the previous shift. 2. Any questionable monitor may be source checked to aid in determining operability.
A slight deflection of the indicator is all that is necessary to confirm source check response.
3. A radiation monitoring channel is to be considered operable if it responds to a source check, monitor is in service, and instrument malfunction annunciation due to low flow is clear. 4. Radiation recorders are to be considered operable if operating properly, inking clearly, legible, and running on time. 5. If gas or particulate sampler flow rotameter is inoperable, the respective monitor is also inoperable.
6. Inoperable instruments are to be reported to SRO. 7. Chemistry is to be notified as follows: a. If a monitor is inoperable and a release is being made via this pathway, Chemistry is to be notified to perform applicable 001 until monitor is declared operable.
b. If a conditional SI is required, Chemistry is to be notified to perform appropriate SI. 8. Tech Specs are to be referenced for applicable actions. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 17 of 39 6.1 Performance Requirements (continued)
H. Any work orders generated during performance of Data Sheets require documentation in Remarks at the bottom of the appropriate data sheet. I. Inoperable instruments are required to have INOP entered in the appropriate data space. J. Data spaces for instruments in modes which do NOT apply can have N/A entered in them. K. The following are guidelines for radiation monitors and recorders:
CAUTION When source checking to determine operability, care should be used to prevent actuation of any high level trip or isolation function initiated by a radiation monitor. 1. Radiation levels are to be compared to data taken on the previous shift. 2. Any questionable monitor may be source checked to aid in determining operability.
A slight deflection of the indicator is all that is necessary to confirm source check response.
3. A radiation monitoring channel is to be considered operable if it responds to a source check, monitor is in service, and instrument malfunction annunciation due to low flow is clear. 4. Radiation recorders are to be considered operable if operating properly, inking clearly, legible, and running on time. 5. If gas or particulate sampler flow rotameter is inoperable, the respective monitor is also inoperable.
6. Inoperable instruments are to be reported to SRO. 7. Chemistry is to be notified as follows: a. If a monitor is inoperable and a release is being made via this pathway, Chemistry is to be notified to perform applicable 001 until monitor is declared operable.
b. If a conditional SI is required, Chemistry is to be notified to perform appropriate SI. 8. Tech Specs are to be referenced for applicable actions.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 18 of 39 6.1 Performance Requirements (continued)
9. A WO is to be initiated and the WO number noted in Remarks. 10. The applicable Inoperable Radiation Monitor/Recorder Data Table, is to be completed for inoperable monitor(s) or recorder(s).
L. The following are guidelines for inoperable flow rate measuring devices 1. SRO is to be notified that device is inoperable.
2. A Work Order to have flow rate measuring device repaired is to be initiated and WO number recorded in Remarks. 3. Applicable tracking data sheet is to be completed.
4. Original date and time flow rate device was declared inoperable is to be recorded on each day's data sheet so the 30 day time limit for inoperable monitors is NOT exceeded.
5. Chemistry is to be notified as follows: a. If an iodine sampler flow rotameter is inoperable and requires a portable sampler in accordance with the ODCM, Chemistry is to be notified to install a temporary backup sampler AND perform applicable 001. b. If a special SI is required, Chemistry is to be notified to perform appropriate SI. 6. If a flow rate device is declared inoperable, readings for flow rate devices are to be recorded on applicable Inoperable Flow Rate Measuring Device Data Table every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . M. M&TE (Measuring and Test Equipment) may be substituted for installed permanent plant instrumentation as long as the M& TE is at least as accurate as the permanent plant instrumentation.
N. M&TE to be installed and removed by WO (or TACF), which shall also configure valves to place M&TE in-service (or out-of-service).
O. Evaluate LCO entry whenever connecting/disconnecting M& TE or whenever M& TE is aligned to plant systems or left unattended.
LCO entry may NOT be required if the M&TE is installed as a TACF per SPP-9.5. P. Document the M&TE substitution, including the WO number (or TACF number) and M&TE 10 number on the appropriate data sheet in the remarks section. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three PaJle 18 of 39 6.1 Performance Requirements (continued)
9. A WO is to be initiated and the WO number noted in Remarks. 10. The applicable Inoperable Radiation Monitor/Recorder Data Table, is to be completed for inoperable monitor(s) or recorder(s).
L. The following are guidelines for inoperable flow rate measuring devices 1. 8RO is to be notified that device is inoperable.
2. A Work Order to have flow rate measuring device repaired is to be initiated and WO number recorded in Remarks. 3. Applicable tracking data sheet is to be completed.
4. Original date and time flow rate device was declared inoperable is to be recorded on each day's data sheet so the 30 day time limit for inoperable monitors is NOT exceeded.
5. Chemistry is to be notified as follows: a. If an iodine sampler flow rotameter is inoperable and requires a portable sampler in accordance with the ODCM, Chemistry is to be notified to install a temporary backup sampler AND perform applicable 001. b. If a special 81 is required, Chemistry is to be notified to perform appropriate
81. 6. If a flow rate device is declared inoperable, readings for flow rate devices are to be recorded on applicable Inoperable Flow Rate Measuring Device Data Table every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . M. M&TE (Measuring and Test Equipment) may be substituted for installed permanent plant instrumentation as long as the M& TE is at least as accurate as the permanent plant instrumentation.
N. M&TE to be installed and removed by WO (or TACF), which shall also configure valves to place M&TE in-service (or out-of-service).
O. Evaluate LCO entry whenever connecting/disconnecting M&TE or whenever M& TE is aligned to plant systems or left unattended.
LCO entry may NOT be required if the M& TE is installed as a TACF per 8PP-9.5. P. Document the M&TE substitution, including the WO number (or TACF number) and M&TE 10 number on the appropriate data sheet in the remarks section.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 19 of 39 Date ----Page __ _ of ----6.2 GENERAL [1] ENSURE prerequisite actions in Section 4.0 have been met. NOTE Information on specific items in the data sheets is contained in 1-SI-0-2-00 reference appendix with an associated reference number. [2] PERFORM Data Sheet 1 & 2. [3] ENSURE Data Sheet 1 & 2 have been completed and Acceptance Criteria reviewed within four hours of assuming shift. WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 19 of 39 Date ___ _ Page ___ _ of ___ _ 6.2 GENERAL [1] ENSURE prerequisite actions in Section 4.0 have been met. NOTE Information on specific items in the data sheets is contained in 1-SI-0-2-00 reference appendix with an associated reference number. [2] PERFORM Data Sheet 1 & 2. [3] ENSURE Data Sheet 1 & 2 have been completed and Acceptance Criteria reviewed within four hours of assuming shift.
WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 20 of 39 Date __ _ Page __ _ 7.0 POST PERFORMANCE ACTIVITIES
[1] ENSURE all Acceptance Criteria have been met OR appropriate corrective action has been taken. [2] NOTIFY SM/Unit SRO that this Instruction is complete.
[3] PRESENT completed data sheets for SRO review. [4] RECORD completion date and time on Surveillance Task Sheet. of ----WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 20 of 39 Date ---Page __ _ 7.0 POST PERFORMANCE ACTIVITIES
[1] ENSURE all Acceptance Criteria have been met OR appropriate corrective action has been taken. [2] NOTIFY SM/Unit SRO that this Instruction is complete.
[3] PRESENT completed data sheets for SRO review. [4] RECORD completion date and time on Surveillance Task Sheet. of __ _
) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Pajte 21 of 39 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
Completed Data Package. 8.2 Non-QA Records None WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 21 of 39 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
Completed Data Package. 8.2 Non-QA Records None
) WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 1 of 15) 1-SI-0-2A-03 Rev. 0030 Page 22 of 39 Mode 3 Surveillance Log: 1900-0700 Date Toda.1 Page I I Ref I Location I Description I Instrument
T S Limit Data Ill'" 1-M-2 1-U-2-230A 200,000 3 PnI0-L-209 CST A Level OR gallons T15M1708 1-U-2-230B D gallons 1-PI-1-2A
/040 psig SG 1 Press 1-PI-1-2B
/DIIO psig 1-PI-1-5 114<> psig 1-PI-1-9A loBo psig SG 2Press 1-PI-1-9B Operable, /OeO psig* 1-PI-1-12 Channel loeo psig 4 1-M-4 Check, and /070 psig 1-PI-1-20A MCD S; 90 SG 3 Press 1-PI-1-20B psig lotto psig 1-PI-1-23
/010 psig 1-PI-1-27A 1010 psig SG 4 Press 1-PI-1-27B
/0"0 psig 1-PI-1-30 1040 psig 1-U-3-42 32> % SG 1 Level 1-U-3-39 % 1-U-3-38 % . 1-U-3-55 Operable at 3D % SG 2 Level 1-U-3-52 32% NR [for .fo % 5 1-M-4 Remarks: 1-U-3-51 OPERABLE 1-U-3-97 loops], Channel SG 3 Level 1-U-3-94 Check, and 1-U-3-93 MCD S;6.0% 1-U-3-110 SG 4 Level 1-U-3-107 1-U-3-106

Initials INDICATE ace met OR action in "Accnot Met" column initiated.

1<> 39 38 J." 38 .36 as Ai.D % % % % % % % Performer's Initials of It;' Acc NOT Met Perform Data Sheet 3 of 1-SI-0-2-00 "CST Level" Contact SRO to consult Tech Specs.
Contact SRO to consult Tech Specs. SRO's Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 1 of 15) 1-SI-0-2A-03 Rev. 0030 Page 22 of 39 Mode 3 Surveillance Log: 1900-0700 Date Page __ ' __ I Ref I Location I Description I Instrument
T 5 Limit Data 1-M-2 1-U-2-230A IZ( 3 PnI0-L-209 CST A Level OR 2: 200,000 3tfO, ()()(!) T15M/708 1-U-2-230B 0 gallons gallons 1-PI-1-2A
/040 psig SG 1 Press 1-PI-1-2B IOflo psig 1-PI-1-5 1140 psig 1-PI-1-9A 10 So psig SG 2 Press 1-PI-1-9B Operable, /080 psig 1-PI-1-12 Channel 10eo psig 4 1-M-4 Check, and 1-PI-1-20A MCD:s; 90 1070 psig SG 3 Press 1-PI-1-20B psig /0"0 psig 1-PI-1-23 1010 psig 1-PI-1-27A lOla psig SG 4 Press 1-PI-1-27B psig 1-PI-1-30 1040 psig 1-U-3-42 3t> % SG 1 Level 1-U-3-39 % 1-U-3-38 8C) % 1-U-3-55 Operable at ao % SG 2 Level 1-U-3-52 32% NR [for 10 % 5 1-M-4 Remarks: 1-U-3-51 OPERABLE loops], 1-U-3-97 Channel SG 3 Level 1-U-3-94 Check, and 1-U-3-93 MCD:s;6.0%
1-U-3-110 SG 4 Level 1-U-3-107 1-U-3-106 Initials INDICATE acc met OR action in "Acc not Met" column initiated.
+0 3S 38 38 .36 58 % % % % % % % Performer's Initials of It; Acc NOT Met Perform Data Sheet 3 of 1-SI-0-2-00 "CST Level" Contact SRO to consult Tech Specs. Contact SRO to consult Tech Specs. SRO's Initials Ref 8 9 10 15 ) Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 2 of 15) 1-SI-0-2A-03 Rev. 0030 Page 23 of 39 Mode 3 Surveillance Log: 1900-0700 ,
-Location Description Instrument # T S Limit Operable, Channel Check, and MCD SR Neutron 1-NI-92-131A value is plus or minus Mon CH I 1/2 decade [0.3CR1<CR2 1-M-4 <3.0CR1].
Reading should be the SR Neutron 1-NI-92-132A average value Mon CH II observed over a 30 second period 1-Ll-6S-339A Operable, less than or 1-M-4 PZR Level 1-Ll-6S-335A equal toSO%, Channel Check, and 1-Ll-68-320 MCD:s: 6.0% 1-PI-6S-340A Operable 1-PI-68-334 channel check, 1-M-5 PZR Press greater than or equal 1-PI-6S-323 to 2214psig and 1-PI-6S-322 MCD:S: 55 psig. RCS Loops RCP Status 1,2,3,4 1-HS-68-SAA Two loops operable; RCP 1 1-HS-6S-SBA two loops in operation 1-M-5 1-HS-6S-31AA if capable of rod RCP2 withdrawal (one loop if 1-HS-6S-31BA NOT) RCP3 1-HS-6S-50AA 1-HS-68-50BA RCP4 1-HS-6S-73AA 1-HS-6S-73BA (1) Loop status is to be written in data space (Operable (0), Running (R), or INOP). (2) See 1-SI-0-2-00 Ref. 8 if indication is less than 0.2 CPS. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Data Z CPS(2) Z CPS(2) % 3+/- % 21 % "J,.Z(PC;-
psig 2.:zes psig UZO psig "J Z 3 D psig RCP1 2 3 4 ON OFF 0 0 0 0 Aeo " (1) 12. (1) (1) R (1) Performer's Initials -Acc NOT Met Contact SROto consult Tech Spec s. Contact SRO to consult Tech Spec s. Contact SRO to consult Tech Spec s Contact SROto consult Tech Spec s. SRO's Initials Ref 8 9 10 15 ) Remarks: WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 23 of 39 Data Sheet 1 (Page 2 of 15) Mode 3 Surveillance Log: 1900-0700 Date Page I Location Description Instrument
T S Limit Operable, Channel Check, and MCD SR Neutron 1-NI-92-131A value is plus or minus Mon CH I 1/2 decade [0.3CR1<CR2 1-M-4 <3.0CR1].
Reading should be the SR Neutron 1-NI-92-132A average value Mon CH II observed over a 30 second period 1-Ll-68-339A Operable, less than or 1-L 1-68-335A equal t080%, 1-M-4 PZR Level Channel Check, and 1-Ll-68-320 MCD 6.0% 1-PI-68-340A Operable 1-PI-68-334 channel check, 1-M-5 PZR Press greater than or equal 1-PI-68-323 to 2214psig and 1-PI-68-322 55 psig. RCS Loops RCP Status 1,2,3,4 1-HS-68-8AA Two loops operable; RCP 1 1-HS-68-8BA two loops in operation 1-M-5 1-HS-68-31AA if capable of rod RCP 2 withdrawal (one loop if 1-HS-68-31 BA NOT) RCP 3 1-HS-68-50AA 1-HS-68-50BA RCP4 1-HS-68-73AA 1-HS-68-73BA (1) Loop status is to be written in data space (Operable (0), Running (R), or INOP). (2) See 1-SI-0-2-00 Ref. 8 if indication is less than 0.2 CPS. Initials INDICATE ace met OR action in "Ace not Met" column initiated.
'].. of Data Z CPS(2) Z CPS(2)
% 3+ % 21 % Z.Z(PC> psig Z-z.tS psig UZO psig psig RCP1 2 3 4 ON OFF D D D D " jl. (1) 12. (1) (1) R (1) Performer's Initials Acc NOT Met Contact SRO to consult Tech Spec s. Contact SRO to consult Tech Spec s. Contact SRO to consult Tech Spec s Contact SROto consult Tech Spec s. SRO's Initials Ref 16 17 18 Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three . Data Sheet 1 (Page 3 of 15) 1-SI-0-2A-03 Rev. 0030 Page 24 of 39 Mode 3 Surveillance Log: 1900-0700 Date 1041 Page 3 of IS: Location 1-M-6 480V Rx MOV Boards 1-M-6 1-M-6 Description Instrument
T 5 Limit RWSTto RHR 1-FCV-63-1 ECCS Suction (1-HS-63-1A)
OPEN SI Pumps to CL 1, 1-FCV-63-22 2,3,4 (1-HS-63-22A)
Shunt BKR 1A1-A c/2E1 1-BKR-63-1 A At least one OR breaker OFF Breaker 1-BKR-63-1 B 1A1-A c/10A Shunt BKR 1B1-B c/2F2 1-BKR-63-22A At least one OR breaker OFF Breaker 1-BKR-63-22B 1B1-B c/11D 1-LJ-63-180 Operable, CNTMT 1-LJ-63-181 Channel check, Sump Level 1-LJ-63-182 and 1-LJ-63-183 MCD:s;6.0%
1-LJ-63-50 Operable, 1-LJ-63-51 Channel check, RWST Level and MCD 1-LJ-63-52 1-LJ-63-53
S;7.0% CL Accum 1 Outlet 1-FCV-63-118 ( 1-HS-63-118A)
CL Accum 2 Outlet 1-FCV-63-98 Valves (1-HS-63-98A)
Open-when Pzr pressure CL Accum 3 Outlet 1-FCV-63-80 (1-HS-63-80A)
>1000 psig. CL Accum 4 Outlet 1-FCV-63-67 (1-HS-63-67A)
Initials INDICATE ace met OR action in "Ace not Met" column initiated.
Data Acc NOT Met OPEN Iir CLOSED 0 OPEN [j( CLOSED 0 OFF 0 Contact SRO to ON t!r [B"""" consult OFF Tech Specs. ON 0 OFF 0 ON OFF ON 0 0 % 0 % 0 % 0 % Contact SRO to consult Tech ge % Specs % % 9' % OPEN CLOSED 0 OPEN CLOSED 0 Contact SRO to consult OPEN Tech Specs. CLOSED 0 OPEN Iif' CLOSED 0 e.o Performer's . Initials SRO's Initials Ref 16 17 18 ) Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 3 of 15) 1-SI-0-2A-03 Rev. 0030 Page 24 of 39 Mode 3 Surveillance Log: 1900-0700 Date 104.( Page __ 3 __ of IS: Location 1-M-6 480V Rx MOV Boards 1-M-6 1-M-6 Description Instrument
T S Limit RWSTto RHR 1-FCV-63-1 ECCS Suction (1-HS-63-1A)
OPEN SI Pumps to CL 1, 1-FCV-63-22 2,3,4 (1-HS-63-22A)
Shunt BKR 1A1-A c/2E1 1-BKR-63-1A At least one OR breaker OFF Breaker 1-BKR-63-1 B 1A1-A c/10A Shunt BKR 1 B 1-B c/2F2 1-BKR-63-22A At least one OR breaker OFF Breaker 1-BKR-63-22B 1 B1-B c/11D 1-U-63-180 Operable, CNTMT 1-U-63-181 Channel check, Sump Level 1-U-63-182 and 1-U-63-183 MCD :::;6.0% 1-U-63-50 Operable, 1-U-63-51 Channel check, RWST Level and MCD 1-U-63-52 1-U-63-53
7.0% CL Accum 1 Outlet 1-FCV-63-118 ( 1-HS-63-118A)
CL Accum 2 Outlet 1-FCV-63-98 Valves (1-HS-63-98A)
Open-when Pzr pressure CL Accum 3 Outlet 1-FCV-63-80 (1-HS-63-80A)
>1000 psig. CL Accum 4 Outlet 1-FCV-63-67 (1-HS-63-67A)
Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met OPEN 1M"" CLOSED D OPEN err CLOSED D OFF D ON [!f" Contact SRO to [B"'"" consult OFF Tech Specs. ON D OFF D ON OFF ON D 0 % 0 % 0 % 0 % Contact SRO to consult Tech 98 % Specs % % 99 % OPEN [)!( CLOSED D OPEN I!(" CLOSED D Contact SRO to ff consult OPEN Tech Specs. CLOSED D OPEN [i( CLOSED D A120 Performer's Initials SRO's Initials
) Ref 19 20 L WBN Unit 1 Date Location Description CLAccum 1 Lvi CLAccum 2 Lvi CLAccum 3 Lvi CLAccum 4 1-M-6 Lvi CL Accum 1 Press CLAccum 2 Press CLAccum 3 Press CLAccum 4 Press 1-M-6 or CNTMT Press ICS 1900 -0700 1-SI-0-2A-03 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 25 of 39 Data Sheet 1 (Page 4 of 15) Mode 3 Surveillance Log: 1900-0700 Page 4-Instrument
T 5 Limit Data 1-Ll-63-129 78tO gal 1-Ll-63-119 7630 and ::::;8000 781 0 gal 1-Ll-63-109 gal and MCD ::::; 96 781S gal gal. Chemistry is to 1-Ll-63-99 be notified to gal perform 1-SI-63-6 1-Ll-63-89 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if tank 7810 gal 1-Ll-63-81 level is increased 7(310 gal 75 gal and tank NOT 1-Ll-63-82 filled from RWST. (1) 791D gal 1-Ll-63-60 7810 gal 1-PI-63-128 64 0 psig 1-PI-63-126 psig 1-PI-63-108 (O/fo psig 1-PI-63-106 0 and ::::;660 psig h tfD psig and MCD::::; 30 1-PI-63-88 psig (1) psig 1-PI-63-86 (P30 psig 1-PI-63-62
/P40 psig 1-PI-63-61
",30 psig 1-PD 1-30-42 IH"" Operable, Channel or Point P1 OOOA 0 Check, and MCD of " psig (2) 1-PDI-30-43 iii"" the following:
or Point P1 001A 0 MCD::::; 1.0 psig (Ind) 0 psig (2) 1-PDI-30-44
[j)"'" MCD ::::; 0.8 psig or Point P1 002A 0 (mixed) <:5 psig (2) 1-PD 1-30-45 Ir" MCD::::; 0.5 psig () or Point P1 003A 0 (computer) psig (2) (1) When Pzr pressure greater than 1000 psig. (2) Instrument used for data is to be checked. POI is preferred instrument.
Initials INDICATE ace met OR action in "Ace not Met" column initiated.
ARJ> Performer's Initials 1 Remarks: of Acc NOT Met Check operability by acceptable deviation between redundant level and pressure channels when pressurizer pressure is above 1000 psig. If deviation limit is exceeded, determine the channel inoper-able AND record only the operable channel. This channel check is NOT a technical specification re-quirement.
Contact SRO to consult Tech Specs SRO's Initials Ref 19 ) 20 WBN Unit 1 Date Location Description CL Accum 1 Lvi CL Accum 2 Lvi CLAccum 3 Lvi CLAccum 4 1-M-6 Lvi CLAccum 1 Press CLAccum 2 Press CL Accum 3 Press CLAccum 4 Press 1-M-6 or CNTMT Press ICS 1900 -0700 1-SI-0-2A-03 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 25 of 39 Data Sheet 1 (Page 4 of 15) Mode 3 Surveillance Log: 1900-0700 Page_--l+'---_
Instrument
T 5 Limit Data 1-Ll-63-129 78tO gal 1-Ll-63-119
>

7630 and 78/0 gal 1-Ll-63-109 gal and MCD 96 78K gal gal. Chemistry is to 1-Ll-63-99 be notified to gal perform 1-S 1-63-6 1-Ll-63-89 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if tank '7810 gal 1-Ll-63-81 level is increased
>

7810 gal 75 gal and tank NOT 1-Ll-63-82 filled from RWST. (1) 7f31D gal 1-Ll-63-60 7810 gal 1-PI-63-128 psig 1-PI-63-126 psig 1-PI-63-108
(;'40 psig 1-PI-63-106
>

610 and psig and MCD 30 htfO psig 1-PI-63-88 psig (1) 6;,40 psig 1-PI-63-86 psig 1-PI-63-62 (P40 psig 1-PI-63-61
&'30 psig 1-PDI-30-42 Operable, Channel or Point P1 OOOA D Check, and MCD of 6 psig (2) 1-PDI-30-43 Ii!" the following:
or Point P1 001A D MCD 1.0 psig (Ind) 0 psig (2) 1-PDI-30-44
[jf'"" MCD 0.8 psig or Point P1 002A D (mixed) (5 psig (2) 1-PDI-30-45 rr MCD 0.5 psig 0 or Point P1 003A D (computer) psig (2) (1) When Pzr pressure greater than 1000 psig. (2) Instrument used for data is to be checked. POI is preferred instrument.
Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials \ Remarks: I of Acc NOT Met Check operability by acceptable deviation between redundant level and pressure channels when pressurizer pressure is above 1000 psig. If deviation limit is exceeded, determine the channel inoper-able AND record only the operable channel. This channel check is NOT a technical specification re-quirement.
Contact SRO to consult Tech Specs SRO's Initials
) Ref 21 I WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Date Description CNTMT-ANN 1-M-9 ,1.P 1-M-9 I Annulus ,1.P Mode Three Page 26 of 39 Data Sheet 1 (Page 5 of 15) Mode 3 Surveillance Log: 1900-0700 Page Instrument
T S limit 1-PDI-30-133 D ,1.P between -0.07 or and 0.27 psid 1-PDI-30-30C D 1-PDI-30-126 More negative than or equal value on Attachment 1 " H 2 0(1) 1-PD 1-30-127 and MCD < 0.7 "H 2 O point Y2203A D Data psid(2) " H 2 0(4) " H 2 0(4) of I Acc NOT Met Contact SRO to consult Tech Specs. 22 I ICS Shield or N/A-used for 1-M-9 Building Flow 1-FI-90-400 or D Attachment 1 Data Sheet 37(3) D SCFM Tech Spec Acceptance value from Attachment 1 " H 2 0(4) (1) 1-PDI-30-126 and 1-PDI-30-127 have a range of 0 -10" H 2 0 and indicate negative pressure relative to atmosphere (e.g. an indication of 6" H 2 0 is more negative than negative 5.5" H 2 0) (2) 1-PDI-30-30C on 1-L-10 may be substituted for 1-PDI-30-133 to check Tech Spec compliance.
(3) Perform data sheet 37 of 1-SI-0-2-00 to determine shield building flow if ICS point and 1-FI-90-400 are unavailable whenever shield building exhaust stack has flow. This flow is required in order to determine Tech Spec value for Annulus Ll.P on Attachment 1 . (4) N/A during venting operations.
required annulus entries, or Aux Bldg isolations not exceeding 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration.
Remarks: Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials Ref 21 22 WBN Unit 1 Date 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 5 of 15) 1-SI-0-2A-03 Rev. 0030 Page 26 of 39 Mode 3 Surveillance Log: 1900-0700 Page of Location Description Instrument
T 5 Limit Data Acc NOT Met CNTMT-ANN 1-PDI-30-133 D L1P between -0.07 1-M-9 L1P or and 0.27 psid 1-PDI-30-30C D psid(2) 1-PDI-30-126 More negative than or equal value on " H 2 0(4) 1-M-9 Annulus L1P Attachment 1 " H 2 0(1) 1-PDI-30-127 and MCD 0.7 "H 2 O " H 2 0(4) Contact SRO to consult point Y2203A D Tech Specs. ICS Shield or N/A-used for 1-M-9 Building Flow 1-FI-90-400 D Attachment 1 or Data Sheet 37(3) D SCFM Tech Spec Acceptance value from " H 2 0(4) Attachment 1 (1) 1-PDI-30-126 and 1-PDI-30-127 have a range of 0 -10" H 2 0 and indicate negative pressure relative to atmosphere (e.g. an indication of 6" H 2 0 is more negative than negative 5.5" H 2 0) (2) 1-PDI-30-30C on 1-L-10 may be substituted for 1-PDI-30-133 to check Tech Spec compliance.
(3) Perform data sheet 37 of 1-SI-0-2-00 to determine shield building flow if ICS point and 1-FI-90-400 are unavailable whenever shield building exhaust stack has flow. This flow is required in order to determine Tech Spec value for Annulus L'>P on Attachment
1. (4) N/A during venting operations, required annulus entries, or Aux Bldg isolations not exceeding 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration.
Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials Remarks:
) WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 6 of 15) 1-SI-0-2A-03 Rev. 0030 Page 27 of 39 Mode 3 Surveillance Log: 1900-0700 Ret Location Description Instrument
TS Limit Data Acc NOT Met 23 24 Remarks: 1-M-10 Ice Cndnsr Door 1-XI-61-187 Operable, all doors C..J) Contact SRO to consult Status Position closed, and Channel Tech Specs and perform Monitoring Check data sheet 23. System 1-M-10 Ice Bed 1-TR-61-138 Operable, ::;; 25.2°F, Table If 1-TR-61-138 and Local Temperature ChannelCheck,and below Ice Cond Temp Monitoring minimum of two monitoring panel are System RTDs per inoperable, perform Data group operable.
(1) Sheet 24 of 1-SI-0-2-00 "Inoperable Ice Bed Monitoring System" (1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded.
All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. (2) Fulfills LCO 3.6.12 Action B.1 or TR 3.6.2 Action A.1, when maximum ice bed temp 25.2°F once every four hours. (3) Fulfills TR 3.6.1 Action B.1.2 and/or Action C.1.2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE ace met OR action in "Ace not Me!" column initiated.
Performer's Initials SRO's Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 6 of 15) 1-SI-0-2A-03 Rev. 0030 Page 27 of 39 Mode 3 Surveillance Log: 1900-0700 Ret Location Description Instrument
TS Limit Data Acc NOT Met 23 24 Remarks: 1-M-10 Ice Cndnsr Door 1-XI-61-187 Operable, all doors (-I) Contact SRO to consult Status Position closed, and Channel Tech Specs and perform Monitoring Check data sheet 23. System 1-M-10 Ice Bed 1-TR-61-138 Operable, ::; 25.2°F, Table If 1-TR-61-138 and Local Temperature ChannelCheck,and below Ice Cond Temp Monitoring minimum of two monitoring panel are System RTDs per inoperable, perform Data group operable.
(1) Sheet 24 of 1-SI-0-2-00 "Inoperable Ice Bed Monitoring System" (1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded.
All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. (2) Fulfills LCO 3.6.12 Action B.1 or TR 3.6.2 Action A.1, when maximum ice bed temp s; 25.2°F once every four hours. (3) Fulfills TR 3.6.1 Action B.1.2 and/or Action C.1.2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 7 of 15) 1-SI-0-2A-03 Rev. 0030 Page 28 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page. ___ _ of ___ _ TE PT Data TE PT Data TE PT Data 138 1 139 16 N/A N/A N/A 141 2 142 17 143 31 EL 801 144 3 EL 776 145 18 EL 756 146 32 Group 7(1)(2) Group 4(1)(2) Group 1(1)(2) 147 4 148 19 149 33 150 5 151 20 152 34 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 153 6 154 21 155 35 156 7 157 22 N/A N/A N/A EL 801 159 8 EL 776 160 23 EL 756 161 36 Group 8(1)(2) Group 5(1)(2) Group 2(1)(2) 165 9 166 24 167 37 183 10 184 25 185 38 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 168 11 169 26 170 39 171 12 172 27 173 40 EL 801 174 13 EL 776 175 28 EL 756 176 41 Group 9(1)(2) Group 6(1)(2) Group 3(1)(2) 177 14 178 29 179 42 180 15 181 30 N/A N/A N/A 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 TOTAL OF TOTALS+ 18 MEAN ICE BED OPTIMUM MEAN ICE PERFORMER REVIEWER INITIALS SUMS TEMP (3) BED TEMP INITIALS +18 15°F TO 20°F ---------(1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded.
All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. (2) Fulfills LCO 3.6.12 Action B.1 or TR 3.6.2 Action A.1, when maximum ice bed temp <; 25.2°F once every four hours. (3) Fulfills TR 3.6.1 Action B.1.2 and/or Action C.1.2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 7 of 15) 1-SI-0-2A-03 Rev. 0030 Page 28 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page ___ _ of ___ _ TE PT Data TE PT Data TE PT Data 138 1 139 16 N/A N/A N/A 141 2 142 17 143 31 EL 801 144 3 EL 776 145 18 EL 756 146 32 Group 7(1)(2) Group 4(1)(2) Group 1 (1)(2) 147 4 148 19 149 33 150 5 151 20 152 34 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 153 6 154 21 155 35 156 7 157 22 N/A N/A N/A EL 801 159 8 EL 776 160 23 EL 756 161 36 Group 8(1)(2) Group 5(1)(2) Group 2(1)(2) 165 9 166 24 167 37 183 10 184 25 185 38 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 168 11 169 26 170 39 171 12 172 27 173 40 EL 801 174 13 EL 776 175 28 EL 756 176 41 Group 9(1)(2) Group 6(1)(2) Group 3(1)(2) 177 14 178 29 179 42 180 15 181 30 N/A N/A N/A 1 1 1 Two Highest Temps 2 Two Highest Temps 2 Two Highest Temps 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 TOTAL OF TOTALS+ 18 MEAN ICE BED OPTIMUM MEAN ICE PERFORMER REVIEWER INITIALS SUMS TEMP (3) BED TEMP INITIALS +18 15°F TO 20°F (1) At least two RTDs are to be verified operable per group and two highest readings from each group recorded.
All readings should be recorded to one decimal position and should NOT be rounded. If 1-TR-61-138 is inoperable, MIG is to be notified to perform IMI-15 once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to fulfill TR 3.6.1 Action A.11. (2) Fulfills LCO 3.6.12 Action B.1 or TR 3.6.2 Action A.1, when maximum ice bed temp ,s; 25.2°F once every four hours. (3) Fulfills TR 3.6.1 Action B.1.2 and/or Action C.1.2, when required by INOP Ice Bed Temp Monitoring System. Initials INDICATE acc met OR action in "Acc not Met" column initiated.
Performer's Initials SRO's Initials Ref 25 )" 26 27 Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 8 of 15) 1-SI-0-2A-03 Rev. 0030 Page 29 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ___ _ Location 0-M-12 or ICS 0-M-12 or ICS 0-M-12 or ICS Description Instrument # T S Limit 1-RM-90-106A 0 or point R1012A 0 1-RM-90-106B 0 or point R1013A 0 Operable and Lower and Channel Check UpperCNTMT 1-RM-90-112A 0 Gas and or Particulate point R1015A 0 1-RM-90-112B 0 or point R1016A 0 1-RR-90-106 1-RR-90-112 Operable 0-RM-90-102 0 or Spend Fuel Pit point R9011A 0 Operable and Area 0-RM-90-1 03 0 Channel Check or point R9012A 0 0-RM-90-125 0 or point R1025A 0 0-RM-90-126 0 Operable and MCR Intake or Channel Check point R1026A 0 0-RR-90-125 0-RR-90-126 Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met If monitor aligned to cpm Lower Containment is inoperable, the other monitor is to be re-cpm aligned using SOI-90.02.
If both monitors are inoper-cpm able, SRO is to be notified, 1-SI-68-32 is to be performed, and Chemistry Count-cpm room is to be notified to perform 1-SI-90-25. mr/hr Contact SRO to consult Tech Specs mr/hr cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. Performer's SRO's Initials Initials Ref 25 J , 26 27 Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 8 of 15) 1-SI-0-2A-03 Rev. 0030 Page 29 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ____ _ Location 0-M-12 or ICS 0-M-12 or ICS 0-M-12 or ICS Description Instrument
T 5 Limit 1-RM-90-106A 0 or point R1012A 0 1-RM-90-106B 0 or point R1013A 0 Operable and Lower and Upper CNTMT 1-RM-90-112A 0 Channel Check Gas and or Particulate point R1 015A 0 1-RM-90-112B 0 or point R1016A 0 1-RR-90-106 1-RR-90-112 Operable 0-RM-90-102 0 or Spend Fuel Pit point R9011A 0 Operable and Area 0-RM-90-103 0 Channel Check or point R9012A 0 0-RM-90-125 0 or point R1025A 0 0-RM-90-126 0 Operable and MCR Intake or Channel Check point R1 026A 0 0-RR-90-125 0-RR-90-126 Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met If monitor aligned to cpm Lower Containment is inoperable, the other monitor is to be re-cpm aligned using 501-90.02.
If both monitors are inoper-cpm able, SRO is to be notified, 1-51-68-32 is to be performed, and Chemistry Count-cpm room is to be notified (-I) to perform 1-SI-90-25.
(-I) mr/hr Contact SRO to consult Tech Specs mr/hr cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. (-I) (-I) Performer's SRO's Initials Initials WBN Unit 1 ) Date Ref Location O-M-12 or 28 ICS AUX BLDG 29 A2U/713 or ICS Remarks: 1900 -0700 . Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 9 of 15) 1-SI-0-2A-03 Rev. 0030 Page 30 of 39 Mode 3 Surveillance Log: 1900-0700

Page of ___ _ Description Instrument

T S Limit CCS HxA Out 1-RM-90-123 0 Operable and Liquid or Channel Check point R1023A 0 (Info Only-T.S.
N/A) 1-RM-90-130A 0 CNTMT or Purge Air Exh point R1027A 0 Operable and Radiation Channel Check Monitor 1-RM-90-131A 0 or point R1028A 0 Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Ace NOT Met Contact SRO. See Section 6.1 K. cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. I F both monitors inoperable, suspend purge flow immediately per ODCM cpm table 1.1.2-6.a Performer's SRO's Initials Initials WBN Unit 1 Date Ref Location O-M-12 or 28 ICS AUX BLDG 29 A2U/713 or ICS Remarks: 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 9 of 15) 1-SI-0-2A-03 Rev. 0030 Page 30 of 39 Mode 3 Surveillance Log: 1900-0700

Page ___ _ of ----Description Instrument

T 5 Limit CCS HxA Out 1-RM-90-123 D Operable and Liquid or Channel Check point R1023A D (Info Only-T.S.
N/A) 1-RM-90-130A D CNTMT or Purge Air Exh point R1027A D Operable and Radiation Channel Check Monitor 1-RM-90-131A D or point R1028A D Initials indicate acc met OR action in "Acc not Met" column initiated.
Data Acc NOT Met Contact SRO. See Section 6.1 K. cpm Contact SRO to consult Tech Specs. See cpm Section 6.1 K. I F both monitors inoperable, suspend purge flow immediately per ODCM cpm table 1.1.2-6.a Performer's Initials SRO's Initials Ref 59 , 67 ) I Remarks: WBN Unit 1 Date Location AEB 729 AEB 729 AUX BLDG 786 N/A 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 10 of 15) 1-SI-0-2A-03 Rev. 0030 Page 31 of 39 Mode 3 Surveillance Log: 1900-0700

Page ___ _ Description Instrument

T 5 Limit Data Unit 1 Shield Bldg Exhaust 1-SMPL-90-801 Operable Tritium Flow Rate Monitor Cy) Unit 2 Shield Bldg Exhaust Tritium Flow 2-SMPL-90-801 Operable Rate Monitor Cy) Aux Bldg and Fuel Handling Exhaust Tritium 0-SMPL-90-800 Operable Flow Rate Monitor (,f) Completed or in progress for the Tech Specs per required 1-SI-0-10(1)
N/A performance 1-SI-0-10 frequency interval 0 (,f) (1) Conditional performance cannot be substituted for periodic performance.
Initials indicate ace met OR action in "Ace not Met" column initiated.
Performer's Initials of ___ _ Acc NOT Met If Tritium flow rate measuring device is inoperable, SRO and Chemistry are to be notified.
Initiate WO and record number in remarks section. N/A SRO's Initials Ref 59 , 67 1 ! l Remarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 10 of 15) 1-SI-0-2A-03 Rev. 0030 Page 31 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page ___ _ Location Description Instrument
T S Limit Data Unit 1 Shield AEB 729 Bldg Exhaust 1-SMPL-90-801 Operable Tritium Flow Rate Monitor (-/) Unit 2 Shield Bldg Exhaust AEB 729 Tritium Flow 2-SMPL-90-801 Operable Rate Monitor (-/) Aux Bldg and AUX BLDG Fuel Handling Exhaust Tritium O-SM PL 800 Operable (1) 786 Flow Rate Monitor Tech Specs per N/A 1-SI-0-10(1)
N/A 1-SI-0-10 Conditional performance cannot be substituted for periodic performance.
Initials indicate acc met OR action in "Acc not Met" column initiated.
(-/) Completed or in progress for the required performance frequency interval D (-/) Performer's Initials of ----Acc NOT Met If Tritium flow rate measuring device is inoperable, SRO and Chemistry are to be notified.
Initiate WO and record number in remarks section. N/A SRO's Initials Ref I \ 65 WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 11 of 15) 1-SI-0-2A-03 Rev. 0030 Page 32 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ___ _ Location I Description I Instrument I T S Limit I Data I Acc NOT Met Control Building NORMAL LIMITS Control Room South Wall 0-TI-30-5219 el755 Control Room across from 0-TI-30-5220 1-M-9 el 755 Next to 480V SO BO 0-TI-30-5201 Transformer 1A2-A e1772 Next to 480V SO BO 0-TI-30-5202 Transformer 1 B 1-B el 772 Next to 480V Rx MOV 0-TI-30-5203 Bd 1A2-A el 772 Behind 125V Vital Batt 0-TI-30-5204 Charger 6-S el 772 Next to 480V Rx MOV 0-TI-30-5205 Bd 2A2-A el 772 Next to 480V SO BO 0-TI-30-5206 Transformer 2A2-A el 772 Next to 480V SO BO 0-TI-30-5207 Transformer 2B2-B el 772 Next to 480V Rx MOV 0-TI-30-5208 Bd 2B2-B el 772 U1 Mech Equip Rm el772 0-TI-30-5209 SO BO Rm U1 behind stairs 0-TI-30-521 0 S-A3 el757 SO BO Rm U2 behind stairs 0-TI-30-5211 S-A13 el757 Refuel Floor U1 beside Aux 0-TI-30-5212 Boration Makeup Tank el 757 Computer room at center of 0-TI-30-5226 the room el 708 Aux Instrument Room el 708 0-TI-30-5233 Initials indicate acc met OR action in "Acc not Met" column initiated.
80°F of Readings on this page may be taken in

::; 80°F of any order. In all sections of Ref :::; 104°F OF 65, use of Fluke 52 digital thermometer or :::; 104°F OF equivalent is acceptable for :::; 83°F OF temperature indicators not present :::; 83°F OF or inoperable.
83°F OF

::; 104°F OF :::; 104°F OF Contact SRO to consult Technical
83°F OF Requirements section 3.7.5.1. SRO should

::; 91°F OF evaluate normal ANO abnormal limits. :::; 85°F OF Perform Oata Sheets 65 of 1-SI-0-2-00
85°F OF "Out of Limit Hourly Temperature".
104°F OF

::; 74°F OF :::; 90°F OF Performer's SRO's Initials Initials Ref \ 65 ! rmarks: WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 11 of 15) 1-SI-0-2A-03 Rev. 0030 Page 32 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Page of ____ _ Location I Description Instrument T S Limit Data Acc NOT Met Control Building NORMAL LIMITS Control Room South Wall 0-TI-30-5219 el755 Control Room across from 1-M-9 el 755 0-TI-30-5220 Next to 480V SO BO 0-TI-30-5201 Transformer 1A2-A el 772 Next to 480V SO BO 0-TI-30-5202 Transformer 1 B1-B el 772 Next to 480V Rx MOV 0-TI-30-5203 Bd 1A2-A el 772 Behind 125V Vital Batt 0-TI-30-5204 Charger 6-S el 772 Next to 480V Rx MOV 0-TI-30-5205 Bd 2A2-A el 772 Next to 480V SO BO 0-TI-30-5206 Transformer 2A2-A el 772 Next to 480V SO BO 0-TI-30-5207 Transformer 2B2-B el 772 Next to 480V Rx MOV 0-TI-30-5208 Bd 2B2-B el 772 U1 Mech Equip Rm el 772 0-TI-30-5209 SO BO Rm U1 behind stairs 0-TI-30-521 0 S-A3 el 757 SO BO Rm U2 behind stairs 0-TI-30-5211 S-A13 el757 Refuel Floor U1 beside Aux 0-TI-30-5212 Boration Makeup Tank el 757 Computer room at center of 0-TI-30-5226 the room el 708 Aux Instrument Room el708 0-TI-30-5233 Initials indicate ace met OR action in "Ace not Met" column initiated.
s; 80°F Readings on this OF page may be taken in :s; 80°F OF any order. :s; 104°F In all sections of Ref of 65, use of Fluke 52 :s; 104°F digital thermometer or OF equivalent is :s; 83°F acceptable for OF temperature
s; 83°F indicators not present OF or inoperable.
s; 83°F OF :s; 104°F OF :s; 104°F OF Contact SRO to :s; 83°F consult Technical OF Requirements section :s; 91°F 3.7.5.1. SRO should OF evaluate normal AND :s; 85°F abnormal limits. OF Perform Data Sheets :s; 85°F 65 of 1-SI-0-2-00 OF "Out of Limit Hourly :s; 104°F Temperature".
OF :s; 74°F OF :s; 90°F OF Performer's SRO's Initials Initials Ref 65 WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 12 of 15) 1-SI-0-2A-03 Rev. 0030 Page 33 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Location I Description U1 outside supply fan room el737 South steam vault room U1 el730 North steam vault room U1 el730 Between UHI Accumulators el729 U1 across from AFW pumps el713 U1 outside AFW pump room doorel692 U2 near Boric Acid con-centrate filter vault el692 Next to 0-L-629 el 676 U 1 Blender Station South Wall el713 Behind BAT A el 713 Behind BAT B el713 -Instrument
T S Limit Auxiliary Building Normal Limits 0-TI-30-5213 0-TI-30-5228 0-TI-30-5227 0-TI-30-5218 0-TI-30-5214 0-0-TI-30-5216 0-TI-30-5217 1-TI-62-240 1-TI-62-239 2-TI-62-239 Initials indicate acc met OR action in "Acc not Met" column initiated.
S 104°F z 50°F ;::0: 50°F S 92°F S 104°F S 104°F S 104°F S 104°F z 63°F z 63°F z 63°F Page of ___ _ Data Acc NOT Met Readings on this of page may be taken in any order. OF In all sections of Ref 65, use of Fluke 52 of digital thermometer or equivalent is of acceptable for temperature indicators not present or of inoperable.
Contact SRO to of consult Technical Requirements section 3.7.5.1; SRO should evaluate of normal AND abnormal limits. Perform Data Sheets 65 of 1-SI-0-2-00 "Out of Limit Hourly of Temperature".
Contact SRO to consult Technical of Requirements section 1.1.1 &Ior 3.1.2.1 Perform Data of Sheet 65 of 1-SI-0-2-00 "Out of Limit Hourly of Temperature".
Performer's I SRO's Initials Initials Ref I 65 WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 12 of 15) 1-SI-0-2A-03 Rev. 0030 Page 33 of 39 Mode 3 Surveillance Log: 1900-0700 Date ___ _ Location I Description U1 outside supply fan room el737 South steam vault room U1 el730 North steam vault room U1 el730 Between UHI Accumulators el729 U1 across from AFW pumps el713 U1 outside AFW pump room doorel692 U2 near Boric Acid con-centrate filter vault el692 Next to 0-L-629 el 676 U 1 Blender Station South Wall el713 Behind BAT A el713 Behind BAT B el713 Instrument
T 5 Limit Auxiliary Building Normal Limits 0-TI-30-5213 0-TI-30-5228 0-TI-30-5227 0-TI-30-5218 0-TI-30-5214 0-0-TI-30-5216 0-TI-30-5217 1-TI-62-240 1-TI-62-239 2-TI-62-239 Initials indicate acc met OR action in "Acc not Met" column initiated.
104°F ;

: 50°F ;:: 50°F :::; 92°F :::; 104°F :::; 104°F :::; 104°F :::; 104°F ;:: 63°F ;:: 63°F ;:: 63°F Page of ___ _ Data Acc NOT Met Readings on this OF page may be taken in any order. of In all sections of Ref 65, use of Fluke 52 of digital thermometer or equivalent is OF acceptable for temperature indicators not present or of inoperable.
Contact SRO to of consult Technical Requirements section 3.7.5.1. SRO should evaluate OF normal AND abnormal limits. Perform Data Sheets 65 of 1-SI-0-2-00 "Out of Limit Hourly of Temperature".
Contact SRO to consult Technical of Requirements section 1.1.1 &Ior 3.1.2.1 Perform Data of Sheet 65 of 1-SI-0-2-00 "Out of Limit Hourly of Temperature".
Performer's SRO's Initials Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 13 of 15) 1-SI-0-2A-03 Rev. 0030 Page 34 of 39 Mode 3 Surveillance Log: 1900-0700 Ref 65 \ ) 65 Date ___ _ Location I Description Instrument # T S Limit Outside Normal Limits 1A-A DIG Rm near DIG set 0-TI-30-5229
50°F el742 1 B-B DIG Rm near DIG set el742 0-TI-30-5230
50°F 2A-A DIG Rm near DIG set 0-TI-30-5231
50°F el742 2B-B DIG Rm near DIG set 0-TI-30-5232
50°F el742 2B-B DIG Rm on wall by bat-tery charger el 742 0-TI-30-5221 104°F Next to 480V Diesel Aux Bd 2B1-B e1760.5 0-TI-30-5222 104°F C-S DIG Rm on wall near DIG TI-36 set el742 ;

: 50°F Pumpin! Station (IPS) Next to 480V IPS bd & NORMAL LIMITS trans-former (A bus) el 711 0-TI-30-5223
50°F & < 104°F In B train ERCW pump rm el741 0-TI-30-5224
s; 120°F Next to 480V IPS bd & 0-TI-30-5225
s; 104°F trans-former (B bus) el 711 Mech Equip Rm A near ERCW ;:: 50°F & & HPFP instru sense lines 0-TI-30-5245 el722 104°F Mech Equip Rm B near ERCW ;:: 50°F & & HPFP instru sense lines 0-TI-30-5246 el722 104°F --------------Initials indicate ace met OR action in "Ace not Met" column initiated.
'rmarks: Page of __ _ Data Acc NOT Met Readings on this page may be OF taken in any order. OF In all sections of Ref 65, use of I Fluke 52 digital thermometer or equivalent is acceptable for of temperature indicators not present or inoperable.
I of Contact SRO to consult Technical of Requirements section 3.7.5.1. I SRO should evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-0-2-00 "Out I of of Limit Hourly Temperature".
C-S DIG temp only taken IF C-S DIG declared Operable.
NIA if NOT operable Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourlv Temperature" of Contact SRO to consult I of Technical Requirements I section 3.7.5.1. SRO should of evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourly Temperature".
-Performer's SRO's Initials Initials WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 13 of 15) 1-SI-0-2A-03 Rev. 0030 Page 34 of 39 Mode 3 Surveillance Log: 1900-0700 Ref 65 ) 65 Date ___ _ Location I Description Instrument
T S Limit Outside Normal Limits 1A-A DIG Rm near DIG set 0-TI-30-5229
50°F el742 1 B-B DIG Rm near DIG set 0-TI-30-5230
50°F el742 2A-A DIG Rm near DIG set 0-TI-30-5231
50°F el742 2B-B DIG Rm near DIG set 0-TI-30-5232
50°F el742 2B-B DIG Rm on wall by bat-tery charger el 742 0-TI-30-5221
104°F Next to 480V Diesel Aux Bd 2B1-B el 760.5 0-TI-30-5222
104°F C-S DIG Rm on wall near DIG set el742 TI-36 ;

:: 50°F Pumpin Station (IPS) Next to 480V IPS bd & NORMAL LIMITS trans-former (A bus) el 711 0-TI-30-5223
50°F & < 104°F In B train ERCW pump rm 0-TI-30-5224
120°F el741 Next to 480V IPS bd & 0-TI-30-5225
104°F trans-former (B bus) el 711 Mech Equip Rm A near ERCW ;

:: 50°F & & HPFP instru sense lines 0-TI-30-5245 el722 ::; 104°F Mech Equip Rm B near ERCW ;::: 50°F & & HPFP instru sense lines 0-TI-30-5246 el722 ::; 104°F Initials indicate ace met OR action in "Ace not Met" column initiated.
'rmarks: Page of ___ _ Data Acc NOT Met Readings on this page may be of taken in any order. In all sections of Ref 65, use of of Fluke 52 digital thermometer or equivalent is acceptable for of temperature indicators not present or inoperable.
of Contact SRO to consult Technical of Requirements section 3.7.5.1. SRO should evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourly Temperature".
C-S DIG temp only taken IF C-S DIG declared Operable.
NIA if NOT operable Perform Data Sheet 65 of 1-SI-0-2-00 "Out of of Limit Hourlv Temperature" of Contact SRO to consult OF Technical Requirements section 3.7.5.1. SRO should of evaluate normal AND abnormal limits. Perform Data Sheet 65 of 1-SI-0-2-00 "Out OF of Limit Hourly Temperature".
of Performer's SRO's Initials Initials WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Date ___ _ Ref Location I Description Various DIG Electrical Bd. 66 Rooms NOMENCLATURE DG 1A-A RM EXH FAN 1 (1-FAN-30-447)
DG 1A-A RM GEN/PNL VENT FAN (1-FAN-30-491)
DG 1A-A ELEC BOARD ROOM EXH FAN (1-FAN-30-459)
DG 1A-A RM EXH FAN 2 (1-FAN-30-451)
DG 2A-A RM EXH FAN 1 (2-FAN-30-448) 2A-A ROOM GEN/PANEL VENT N (2-FAN-30-492) llG 2A-A ELEC BOARD ROOM EXH FAN (2-FAN-30-460)
DG 2A-A RM EXH FAN 2 (2-FAN-30-452)
DG 1 B-B ROOM EXH FAN 1 (1-FAN-30-449)
DG 1 B-B RM GEN/PNL VENT FAN (1-FAN-30-493)
DG 1 B-B ELEC BOARD ROOM EXH FAN (1-FAN-30-461)
DG 1 B-B ROOM EXH FAN 2 (1-FAN-30-453)
DG 2B-B ROOM EXH FAN 1 (2-FAN-30-450)
DG 2B-B ROOM GEN/PNL VENT FAN (2-FAN-30-494 ) DG 2B-B ELEC BOARD ROOM EXH FAN (2-FAN-30-462)
DG 2B-B RM EXH FAN 2 (2-FAN-30-454 ) qemarks: ] Mode Three Data Sheet 1 (Page 14 of 15) Page 35 of 39 Mode 3 Surveillance Log: 1900-0700 Instrument
T S Limit Outside See following Bkrs & HS in table required position LOCATION BKR 480V Diesel POSITION Auxiliary Bd. 1A1-A C/2B ON 1A1-A C/4D ON 1A1-A C/4E ON 1A2-A C/2B ON 2A1-A C/2B ON 2A1-A C/4D ON 2A1-A C/4E ON 2A2-A C/2B ON 1B1-BC/2B ON 1 B1-B C/4D ON 1B1-B C/4E ON 1B2-B C/2B ON 2B1-B C/2B ON 2B1-B C/4D ON 2B1-B C/4E ON 2B2-B C/2B ON Initials indicate ace met OR action in "Ace not Met" column initiated.
Page of ____ _ Data Acc NOT Met See following NotifySRO of need to evaluateD/G table operability using Data Sheet 66 of 1-SI-0-2-00 Bkr& HS in HS POSITION UNID Required Position?
PULL 1-BKR-30-447 I DYES STANDBY 1-HS-30-447C D NO N/A 1-BKR-30-491 DYES D NO P-AUTO 1-BKR-30-459 I DYES 1-H S-30-459C DNO P-AUTO 1-BKR-30-451 I DYES 1-HS-30-451 C D NO PULL 2-BKR-30-448 I DYES STANDBY 2-HS-30-448C D NO N/A 2-BKR-30-492 DYES D NO P-AUTO 2-BKR-30-460 I DYES 2-HS-30-460C DNO P-AUTO 2-BKR-30-452 I DYES 2-HS-30-452C D NO PULL 1-BKR-30-449 I DYES STANDBY 1-HS-30-449C D NO N/A 1-BKR-30-493 DYES D NO P-AUTO 1-BKR-30-461 I DYES 1-HS-30-461 C DNO P-AUTO 1-BKR-30-453 I DYES 1-HS-30-453C D NO PULL 2-BKR-30-450 I DYES STANDBY 2-HS-30-450C D NO N/A 2-BKR-30-494 DYES D NO P-AUTO 2-BKR-30-462 I DYES 2-HS-30-462C DNO P-AUTO 2-BKR-30-454 I DYES 2-HS-30-454C D NO Performer's SRO's Initials Initials WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 ) Date ___ _ Ref Location I Description 66 Various DIG Electrical Bd. Rooms NOMENCLATURE DG 1A-A RM EXH FAN 1 (1-FAN-30-447)
DG 1A-A RM GEN/PNL VENT FAN (1-FAN-30-491)
DG 1A-A ELEC BOARD ROOM EXH FAN (1-FAN-30-459)
DG 1A-A RM EXH FAN 2 (1-FAN-30-451 ) DG 2A-A RM EXH FAN 1 (2-FAN-30-448)
OG 2A-A ROOM GEN/PANEL VENT '}A.N (2-FAN-30-492)
DG 2A-A ELEC BOARD ROOM EXH FAN (2-FAN-30-460)
DG 2A-A RM EXH FAN 2 (2-FAN-30-452)
DG 1 B-B ROOM EXH FAN 1 (1-FAN-30-449)
DG 1 B-B RM GEN/PNL VENT FAN (1-FAN-30-493)
DG 1 B-B ELEC BOARD ROOM EXH FAN (1-FAN-30-461)
DG 1 B-B ROOM EXH FAN 2 (1-FAN-30-453)
DG 2B-B ROOM EXH FAN 1 (2-FAN-30-450)
DG 2B-B ROOM GEN/PNL VENT FAN (2-FAN-30-494)
DG 2B-B ELEC BOARD ROOM EXH FAN (2-FAN-30-462)
DG 2B-B RM EXH FAN 2 (2-FAN-30-454 ) qemarks: 1 Mode Three Data Sheet 1 (Page 14 of 15) Page 35 of 39 Mode 3 Surveillance Log: 1900-0700 Instrument
T S Limit Outside See following Bkrs & HS in table required position LOCATION BKR 480V Diesel POSITION Auxiliary Bd. 1A1-A C/2B ON 1A1-A C/4D ON 1A1-A C/4E ON 1A2-A C/2B ON 2A1-A C/2B ON 2A1-A C/4D ON 2A1-A C/4E ON 2A2-A C/2B ON 1B1-BC/2B ON 1 B1-B C/4D ON 1B1-BC/4E ON 1 B2-B C/2B ON 2B1-B C/2B ON 2B1-B C/4D ON 2B1-B C/4E ON 2B2-B C/2B ON Initials indicate acc met OR action in "Acc not Met" column initiated.
Page of ___ _ Data Acc NOT Met See following Notify SRO of need to evaluate DIG operability using Data Sheet 66 of table 1-SI-0-2-00 Bkr& HS in HS POSITION UNID Required Position?
PULL 1-BKR-30-447 I DYES STANDBY 1-HS-30-447C D NO N/A 1-BKR-30-491 DYES D NO P-AUTO 1-BKR-30-459 I DYES 1-HS-30-459C D NO P-AUTO 1-BKR-30-451 I DYES 1-HS-30-451 C D NO PULL 2-BKR-30-448 I DYES STANDBY 2-HS-30-448C D NO N/A 2-BKR-30-492 DYES D NO P-AUTO 2-BKR-30-460 I DYES 2 -H S-30-460C D NO P-AUTO 2-BKR-30-452 I DYES 2-HS-30-452C D NO PULL 1-BKR-30-449 I DYES STANDBY 1-HS-30-449C D NO N/A 1-BKR-30-493 DYES D NO P-AUTO 1-BKR-30-461 I DYES 1-HS-30-461 C D NO P-AUTO 1-BKR-30-453 I DYES 1-HS-30-453C D NO PULL 2-BKR-30-450 I DYES STANDBY 2-HS-30-450C D NO N/A 2-BKR-30-494 DYES D NO P-AUTO 2-BKR-30-462 I DYES 2-HS-30-462C D NO P-AUTO 2-BKR-30-454 I DYES 2-HS-30-454C D NO Peliormer's SRO's Initials Initials WBN Unit 1 ) ) 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 15 of 15) 1-SI-0-2A-03 Rev. 0030 Page 36 of 39 Mode 3 Surveillance Log: 1900-0700 WBN Unit 1 ) 1900 -0700 Shift And Daily Surveillance Log Mode Three Data Sheet 1 (Page 15 of 15) 1-SI-0-2A-03 Rev. 0030 Page 36 of 39 Mode 3 Surveillance Log: 1900-0700
) ,/ WBN 1900 -0700 Unit 1 Shift And Daily Surveillance Log Date __ _ Mode Three Data Sheet 2 (Page 1 of 1) Inoperable Components 1-SI-0-2A-03 Rev. 0030 Page 37 of 39 ----Page __ _ of ----IF any of the following components are inoperable (when required OPERABLE) during the 1900 -0700 shift, THEN the applicable Data Sheets from 1-SI-0-2-00 are to be performed and attached to this package: INOPERABLE COMPONENT CST Level Inoperable Ice Condenser Inlet Door Monitoring Inoperable Ice Bed Monitoring System Inoperable Unit 1 Shield Building Stack Flow Monitor Inoperable Diffuser Discharge Effluent Flow Monitor Inoperable CVES Flow Monitor Inoperable Auxiliary Building Stack Flow Monitor Inoperable Liquid Radwaste Effluent Line Flow Monitor Inoperable Condensate Demin Effluent Flow Monitor Inoperable SGBD to CTBD Flow Monitor Inoperable Service Building Stack Flow Monitor ICS Out Of Limit Hourly Temperature Periodic Temperature Check from DG Bldg Roof Remarks: 1-51-0-2-00 DATA SHEET Data Sheet 3 0 Data Sheet 23 0 Data Sheet 24 0 Data Sheet 37 0 Data Sheet 38 0 Data Sheet 45 0 Data Sheet 51 0 Data Sheet 55 0 Data Sheet 58 0 Data Sheet 60 0 Data Sheet 62 0 Data Sheet 63 0 Data Sheet 65 0 Data Sheet 66 0 INITIALS ) WBN 1900 -0700 Unit 1 Shift And Daily Surveillance Log Date. ___ _ Mode Three Data Sheet 2 (Page 1 of 1) Inoperable Components 1-SI-0-2A-03 Rev. 0030 Page 37 of 39 Page, ___ _ of ----IF any of the following components are inoperable (when required OPERABLE) during the 1900 -0700 shift, THEN the applicable Data Sheets from 1-SI-0-2-00 are to be performed and attached to this package: INOPERABLE COMPONENT 1-51-0-2-00 DATA SHEET CST Level Data Sheet 3 D Inoperable Ice Condenser Inlet Door Monitoring System Data Sheet 23 D Inoperable Ice Bed Monitoring System Data Sheet 24 D Inoperable Unit 1 Shield Building Stack Flow Monitor Data Sheet 37 D Inoperable Diffuser Discharge Effluent Flow Monitor Data Sheet 38 D Inoperable CVES Flow Monitor Data Sheet 45 D Inoperable Auxiliary Building Stack Flow Monitor Data Sheet 51 D Inoperable Liquid Radwaste Effluent Line Flow Monitor Data Sheet 55 D Inoperable Condensate Demin Effluent Flow Monitor Data Sheet 58 D Inoperable SGBD to CTBD Flow Monitor Data Sheet 60 D Inoperable Service Building Stack Flow Monitor Data Sheet 62 D ICS Data Sheet 63 D Out Of Limit Hourly Temperature Data Sheet 65 D Periodic Temperature Check from DG Bldg Roof Data Sheet 66 D INITIALS Remarks:
) WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 38 of 39 Attachment 1 (Page 1 of 1) Determining Annulus AP TIS Limit SHIELD VENT STACK ADJUSTED Annulus SHIELD VENT STACK ADJUSTED Annulus FLOW ICS Point Y2203A aP TIS Limit (IN WC) FLOW ICS Point Y2203A aP TIS Limit (IN WC) (SCFM)) (SCFM) 0 -S.SO 14S00 -S.80 SOO -S.SO 1S000 -S.82 1000 -S.SO 1SS00 -S.84 1S00 --S.SO 16000 -S.86 2000 -S.S1 16S00 -S.88 2S00 -S.S1 17000 -S.91 3000 -S.S2 17S00 -S.93 3S00 -S.S2 18000 -S.95 4000 -S.S3 18S00 -S,98 4S00 -S.S3 19000 -6.01 SOOO -S.S4 19S00 -6.03 SSOO -S.SS 20000 -6.06 6000 -S.SS 20S00 -6.09 6S00 -S.S6 21000 -6.12 7000 -S.S7 21S00 -6.14 7S00 -S.S8 22000 -6.17 8000 -S.S9 22S00 -6.20 8S00 -S.61 23000 -6.24 9000 -S.62 23S00 -6.27 9S00 -S.63 24000 -6.30 10000 -S.6S 24S00 -6.33 10S00 -S.66 2S000 -6.37 11000 2SS00 -6.40 11S00 -S.69 26000 -6.44 12000 -S.71 26S00 -6.47 12S00 -S.72 27000 -6.S1 13000 -S.74 27S00 -6.SS 13S00 -S.76 28000 -6.S8 ) 14000 -S.78 NOTES 1) Shield Bldg Vent Stack Flow reading to be taken from ICS log pt Y2203A or 1-FI-90-400.
IF ICS point and flow indicator are unavailable, perform Data Sheet 37 of 1-SI-0-2-00 to determine shield building flow. 2) .If flow reading is between two values, use next higher flow value. I J WBN 1900 -0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 38 of 39 Attachment 1 (Page 1 of 1) Determining Annulus AP TIS Limit SHIELD VENT STACK ADJUSTED Annulus SHIELD VENT STACK ADJUSTED Annulus FLOW ICS Point Y2203A aP TIS Limit (IN WC) FLOW ICS Point Y2203A aP TIS Limit (IN WC) (SCFM)) (SCFM) 0 -5.50 14500 -5.80 500 -5.50 15000 -5.82 1000 -5.50 15500 -5.84 1500 -5.50 16000 -5.86 2000 -5.51 16500 -5.88 2500 -5.51 17000 -5.91 3000 -5.52 17500 -5.93 3500 -5.52 18000 -5.95 4000 -5.53 18500 -5.98 4500 -5.53 19000 -6.01 5000 -5.54 19500 -6.03 5500 -5.55 20000 -6.06 6000 -5.55 20500 -6.09 6500 -5.56 21000 -6.12 7000 -5.57 21500 -6.14 7500 -5.58 22000 -6.17 8000 -5.59 22500 -6.20 8500 -5.61 23000 -6.24 9000 -5.62 23500 -6.27 9500 -5.63 24000 -6.30 10000 -5.65 24500 -6.33 10500 -5.66 25000 -6.37 11000 -5.67 25500 -6.40 11500 -5.69 26000 -6.44 12000 -5.71 26500 -6.47 12500 -5.72 27000 -6.51 13000 -5.74 27500 -6.55 13500 -5.76 28000 -6.58 , 14000 -5.78 NOTES 1) Shield Bldg Vent Stack Flow reading to be taken from ICS log pt Y2203A or 1-FI-90-400.
IF ICS point and flow indicator are unavailable, perform Data Sheet 37 of 1-SI-0-2-00 to determine shield building flow. 2) If flow reading is between two values, use next higher flow value.
WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Source Notes (Page 1 of 1) 1-SI-0-2A-03 Rev. 0030 Page 39 of 39 Requirements Statement Source Document See 1-SI-0-2-00 "Shift and Daily Surveillance Log Master" Implementing Statement*
WBN Unit 1 1900 -0700 Shift And Daily Surveillance Log Mode Three Source Notes (Page 1 of 1) 1-SI-0-2A-03 Rev. 0030 Page 39 of 39 Requirements Statement Source Document See 1-SI-0-2-00 "Shift and Daily Surveillance Log Master" Implementing Statement
) WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam / A.3 RO/SRO Determine Potential Total Dose for Valve Alignment.
1 ()F q WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam I A.3 RO/SRO Determine Potential Total Dose for Valve Alignment.
1 nF Q Task: Alternate Path: Facility JPM #: KIA Rating(s):
Task Standard:
WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam EVALUATION SHEET Determine Potential Total Dose For Valve Alignment.
NIA JPMRADMIN A.3 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2/3.7 Determine total dose which will occur while aligning 1-FCV-63-11, and based on that determination, state whether the administrative dose limit will be exceeded.
Preferred Evaluation Location:
Preferred Evaluation Method: Simulator
\
References:
/ Task Number: x Validation Time: Classroom x AUO-119-SSP-5.01-001 10 minutes Perform x Simulate Applicable for: RO X SRO x Time Critical:
Yes No X ===========================================================================
Applicant:
Time Start: NAME SSN Time Finish: Performance Rating: SAT UNSAT Performance Time Examiner:
__________________________
__
NAME SIGNATURE DATE ===========================================================================
COMMENTS PAr,F? OF Q Alternate Path: Facility JPM #: KIA Rating(s):
Task Standard:
WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam EVALUATION SHEET Determine Potential Total Dose For Valve Alignment.
NIA JPMRADMIN A.3 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2/3.7 Determine total dose which will occur while aligning 1-FCV-63-11, and based on that determination, state whether the administrative dose limit will be exceeded.
Preferred Evaluation Location:
Preferred Evaluation Method: Simulator x Classroom x Perform x Simulate )
References:
Task Number

AUO-119-SSP-S.01-001 Applicable for: RO X SRO x Validation Time: 10 minutes Time Critical:
Yes No X ===========================================================================
Applicant:
Time Start: NAME SSN Time Finish: Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE ===========================================================================
COMMENTS PAl-:F ? OF <l
) WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam ENSURE the applicant has a copy of the survey map for elevation 713' areas of interest.
DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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:
A survey map is available for elevation 713' of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.
RADCON personnel are currently unavailable to provide assistance. ) INITIATING CUES: You have been directed to perform the alignment of 1-FCV-63-11.
Your total dose for the year to date is 715 mr. Calculate your estimated total dose to perform this job using the attached survey map. Determine if you can perform this job without exceeding your administrative dose limit. Show all work. PAr,F OF q WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam ENSURE the applicant has a copy of the survey map for elevation 713' areas of interest.
DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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:
A survey map is available for elevation 713' of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.
RADCON personnel are currently unavailable to provide assistance. ) INITIATING CUES: You have been directed to perform the alignment of 1-FCV-63-11.
Your total dose for the year to date is 715 mr. Calculate your estimated total dose to perform this job using the attached survey map. Determine if you can perform this job without exceeding your administrative dose limit. Show all work.
':\ OF q
') WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD START TIME: __ _ SAT/UNSAT NOTE TO EVALUATOR:
If the applicant asks if this is a planned special exposure, respond that the applicant should read initiating cues. Examinee must calculate 2 way travel time through all transit areas. Allowable values are +0%, -10%. STEP 1: Calculate exposure during transitthrough the sample room and penetration room to the valve and return. STANDARD:
Sample Room Pen Room to STEP OFF PAD Hot Spot Past BIT Transit to valve Operate valve COMMENTS:
(500mr/hr)(O.5 min)(2)(hr/60min)
=
(0.5 in)(2)(120mr/hr)(hr/60min)
= :iirit (45sec)(2)(min/60sec)(2800mr/hr)(hr/60min)
= rJtirif (3min)(2)(800mr/hr)(hr/60min)
= SOmr (7min )(2)(325mr/hr)(hr/60min)
= 1S'ISJImr (19min)(325mr/hr)(hr/60min)
=
PAGE 4 OF 9 CRITICAL STEP SAT UNSAT ') WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD START TIME: __ _ SATIUNSAT NOTE TO EVALUATOR:
If the applicant asks if this is a planned special exposure, respond that the applicant should read initiating cues. Examinee must calculate 2 way travel time through all transit areas. Allowable values are +0%, -10%. STEP 1: Calculate exposure during transitthrough the sample room and penetration room to the valve and return. STANDARD:
Sample Room Pen Room to STEP OFF PAD Hot Spot Past BIT Transit to valve Operate valve COMMENTS:
(500mr/hr)(O.5 min)(2)(hr/60min)
= 8.33 mr (0.5 in)(2)(120mr/hr)(hr/60min)
= 2 mr (45sec)(2)(min/60sec)(2800mr/hr)(hr/60min)
= 70 mr (3min)(2)(800mr/hr)(hr/60min)
= 80 mr (7min)(2)(325mr/hr)(hr/60min)
= 75.83 mr (19min)(325mr/hr)(hr/60min)
= 102.9 mr PAGE 4 OF 9 CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD SAT/UNSAT ) NOTE to examiner -Some rounding of numbers is allowed as long as the examinee follows sound mathematical standards.
The acceptable total is 305.154 to 339.03 mrem. (-10% +O%) STEP 2: Calculate the total exposure received while performing the task. STANDARD:
Individual doses received are added up. 8.33 mr + 2 mr + 70 mr + 80 mr + 75.83 mr + 102.9 mr = 339.06mr.
Rounding values 8 + 2+ 70 +80 +76 + 103 = 339 mr Acceptable Range -
Step is critical to avoid exceeding dose limits. ) COMMENTS:
PAGE 5 OF 9 CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD SAT/UNSAT ) NOTE to examiner -Some rounding of numbers is allowed as long as the examinee follows sound mathematical standards.
The acceptable total is 305.154 to 339.03 mrem. (-10% +0%) STEP 2: Calculate the total exposure received while performing the task. STANDARD:
Individual doses received are added up. 8.33 mr + 2 mr + 70 mr + 80 mr + 75.83 mr + 102.9 mr = 339.06mr.
Rounding values 8 + 2+ 70 +80 +76 + 103 = 339 mr Acceptable Range -330-350 mrem Step is critical to avoid exceeding dose limits. ) COMMENTS:
PAGE 5 OF 9 CRITICAL STEP SAT UNSAT WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD
/ STEP 3. Applicant calculates his/her total estimated exposure.
STANDARD:
Total dose calculated in previous step is added to applicant's total dose for the year: 715 mr (total dose to date) + 339 mr (minimum total dose for this job [-10% margin]) = 1054 mrem. Acceptable range of answer ItA:"'A'iW1!II Critical step to calculate dose accurately in order to avoid exceeding dose limits. COMMENTS:
STEP 4: Applicant determines admin dose limit will be exceeded if the A job is performed.
Applicant notifies supervisor of findings, stating that admin dose limit will be exceeded.
STANDARD:
Admin dose limit for the year is 1000 mrem. Potential dose received is 330 to 350 mrem. Total is 1045 to 1065 mrem, __ Evaluator cue: When notified of applicant's findings, acknowledge report using repeat back, and state that this JPM is completed.
Have applicant turn in all paperwork
& calculations.
COMMENTS:
STOP TIME --.;...' __ PAGE 6 OF 9 SAT/UNSAT CRITICAL STEP SAT UNSAT CRITICAL STEP SAT UNSAT STEP 3. STANDARD:
WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD Applicant calculates his/her total estimated exposure.
Total dose calculated in previous step is added to applicant's total dose for the year: 715 mr (total dose to date) + 339 mr (minimum total dose for this job [-10% margin]) = 1054 mrem. Acceptable range of answer 1045 to1 065 mrem. Critical step to calculate dose accurately in order to avoid exceeding dose limits. COMMENTS: ) STEP 4: STANDARD:
Applicant determines admin dose limit will be exceeded if the job is performed.
Applicant notifies supervisor of findings, stating that admin dose limit will be exceeded.
Admin dose limit for the year is 1000 mrem. Potential dose received is 330 to 350 mrem. Total is 1045 to 1065 mrem, exceeding admin limit. Evaluator cue: When notified of applicant's findings, acknowledge report using repeat back, and state that this JPM is completed.
Have applicant turn in all paperwork
& calculations.
COMMENTS:
STOP TIME --.:... __ PAGE 6 OF 9 SATIUNSAT CRITICAL STEP SAT UNSAT CRITICAL STEP SAT UNSAT KEY DO NOT HAND TO APPLICANT SURVEY DATA: ). 1-FCV 63-11 is shown on the Survey map.
Travel time from the sample room door thru the sample room is 30 seconds.
Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.
Travel time from the step off pad past the Hot Spot to the lower radiation area around the BIT is 45 seconds due to obstructions in the area.
Travel time from the BIT area into the piping area is 180 seconds.
Travel time thru the piping area to the valve is 420 seconds.
Estimated time at valve is 19 minutes.
General Area Dose rates are listed on the survey map. RESULTS: Sample Room and (500mr/hr)(O.5 min)(2)(hr/60min) 8.33 mr or 8 mr back Pen Room to STEP (0.5 in)(2)(120mr/hr)(hr/60min) 2 mr OFF PAD and back Hot Spot and back (45sec )(2)( min/60sec
)(2S00mr/hr)(hr/60min 70 mr ) Past BIT and back (3min)(2)(SOOmr/hr)(hr/60min) 80 mr Transit to valve and (7min)(2)(325mr/hr)(hr/60min) 75.83 mr or 76 mr back Operate valve (19min)(325mr/hr)(hr/60min) 102.9 mr or 103 mr Accept 330-t0350 mr as dose expected to perform task. When added to current dose for the year of 715mr, the administrative dose limit of 1000 mrem WILL BE EXCEEDED (total 1045-1065 mrem). PAGE 7 OF 9 KEY DO NOT HAND TO APPLICANT SURVEY DATA: ). 1-FCV 63-11 is shown on the Survey map.
Travel time from the sample room door thru the sample room is 30 seconds.
Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.
Travel time from the step off pad past the Hot Spot to the lower radiation area around the BIT is 45 seconds due to obstructions in the area.
Travel time from the BIT area into the piping area is 180 seconds.
Travel time thru the piping area to the valve is 420 seconds.
Estimated time at valve is 19 minutes.
General Area Dose rates are listed on the survey map. RESULTS: Sample Room and (500mr/hr)(0.5 min)(2)(hr/60min) 8.33 mr or 8 mr back Pen Room to STEP (0.5 in)(2)(120mr/hr)(hr/60min) 2 mr OFF PAD and back Hot Spot and back (45sec )(2)( min/60sec
)(2S00mr/hr)(hr/60min 70 mr ) \ Past BIT and back (3min)(2)(SOOmr/hr)(hr/60min) 80 mr .' Transit to valve and (7min)(2)(325mr/hr)(hr/60min) 75.83 mr or 76 mr back Operate valve (19min)(325mr/hr)(hr/60min) 102.9 mr or 103 mr Accept 330-t0350 mr as dose expected to perform task. When added to current dose for the year of 715 mr, the administrative dose limit of 1000 mrem WILL BE EXCEEDED (total 1045-1065 mrem). PAGE 7 OF 9
) APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:
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:
A survey map is available for elevation 713' of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.
RADCON personnel are currently unavailable to provide assistance.
INITIATING CUES: You have been directed to perform the alignment of 1-FCV-63-11.
Your total dose for the year to date is 715 mr. Calculate your estimated total dose to perform this job using the attached survey map. Determine if you can perform this job without exceeding your administrative dose limit. Show all work. A.3-1 RO/SRO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:
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:
A survey map is available for elevation 713' of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.
RADCON personnel are currently unavailable to provide assistance.
INITIATING CUES: You have been directed to perform the alignment of 1-FCV-63-11.
Your total dose for the year to date is 715 mr. Calculate your estimated total dose to perform this job using the attached survey map. Determine if you can perform this job without exceeding your administrative dose limit. Show all work. A.3-1 RO/SRO
) APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) SURVEY DATA:
1-FCV 63-11 is shown on the Survey map.
Travel time from the sample room door thru the sample room is 30 seconds.
Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.
Travel time from the step off pad past the Hot Spot to the lower radi.ation area around the BIT is 45 seconds due to obstructions in the area.
Travel time from the BIT area into the piping area is 180 seconds.
Travel time thru the piping area to the valve is 420 seconds . * -Estimated time at valve is 19 minutes.
General Area Dose rates are listed on the survey map. RESULTS: A.3-1 RO/SRO APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) \ ; SURVEY DATA:
1-FCV 63-11 is shown on the Survey map.
Travel time from the sample room door thru the sample room is 30 seconds.
Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.
Travel time from the step off pad past the Hot Spot to the lower radiation area around the BIT is 45 seconds due to obstructions in the area.
Travel time from the BIT area into the piping area is 180 seconds.
Travel time thru the piping area to the valve is 420 seconds.
Estimated time at valve is 19 minutes.
General Area Dose rates are listed on the survey map. RESULTS: A.3-1 RO/SRO APPLICANT CUE SHEET 5 \? (RETURN TO EXAMINER UPON COMPLETION OF TASK) a..rT'I P c:. ('00 m 1.)00 . ,:)(l.M P Ie. Q.oom Doo (" (. ::2)=* 4;f ,J I' -x,L"x L , / 120 mr/hr general -area \, 500 mr/hr gen area 1000 mr/hr general area r:""9 ** P. 'f ED 6:'A J -.;: .. , 8
t 1 I << I., ; _. S.O.P " ' **
Gra.n 9a .
.. a66 mrlhr , . . . \-) :1 0 2aoo mr/hr Hot Spot general area Boron in .. ! of a. nit, [] 210* LOOP NO.4 [] Volume confrol tdfJII. Qe Ej'B ""ct;:" , * " a IA : ... ., ** , ' .. ,'. '. " .::
.. . . i.. [ APPLICANT CUE SHEET S \? ",(RETURN TO EXAMINER UPON COMPLETION OF TASK) Q.Y()p Co , .... oOr'l'\ Voo(, .:)o..Mpk Q,oom Doo(' ....-__ .....
J I'IU'L.. 'J!' '" I r .(A L----=), \ -/ 120 mrlhr 'general area \, , o , 0 0 0 .--..,.-..----.
2800 mr/hr 500 mr/hr gen area 1000 mr/hr general area f -.-. . Hot Spot general area Boron ranJ< --->
[] t. oop NO.4 t* * * *f : Volume confrol tdnx :. lp, ...*.
C ., ** :' " [
) WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam ) *A.4-SRO CLASSIFY THE EVENT AND DETERMINE PAR. N e.e, d 10 derfe,v m '>'1. & h DW we.. WJ II J D -JpaN\ P;:JOA 1 of 9 WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam ) A.4-SRO CLASSIFY THE EVENT AND DETERMINE PAR. Nee,.cl % de--/-e,vm'Y1.v h DW we-w)/! dD -JpaN\
1 of 9
) Task: Alternate Path: Facility JPM #: KIA Rating(s):
Task Standard:
WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam EVALUATION SHEET Classify the Event and determine PAR. N/A Modified 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.
[2.5/3.3] (CFR: 41.10/43.5/45.11) . 2.4.41 Knowledge of the emergency action level thresholds and classifications.
[2.9/4.6] (CFR: 41.10/43.5/45.11)
The event is classified as a GENERAL EMERGENCY based on "Loss of Any Two Barriers and Potential Loss of Third Barrier" within 15 minutes of starting the evaluation.
Protective Action Recommendation determined is Recommendation
2. Preferred Evaluation Location:
Preferred Evaluation Method: Simulator
References:
Task Number: Validation Time: Classroom X Perform X Simulate EPIP-1 "Emergency Plan Classification Flowpath," Rev. 30; EPIP-5 "GENERAL EMERGENCY," Rev. 37 SRO-113-EPIP-001 Applicable for: RO SRO X 15 minutes Time Critical:
Yes X No ===========================================================================
Applicant:
Time Start: NAME SSN Time Finish: ___ _ Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE ===================================================================================
COMMENTS P::me 2 of 9 Alternate Path: Facility JPM#: KIA Rating(s):
Task Standard:
WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam EVALUATION SHEET Classify the Event and determine PAR. N/A Modified 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.
[2.5/3.3] (CFR: 41.10/43.5/45.11) 2.4.41 Knowledge of the emergency action level thresholds and classifications.
[2.9/4.6] (CFR: 41.10/43.5/45.11)
The event is classified as a GENERAL EMERGENCY based on "Loss of Any Two Barriers and Potential Loss of Third Barrier" within 15 minutes of starting the evaluation.
Protective Action Recommendation determined is Recommendation
2. Preferred Evaluation Location:
Preferred Evaluation Method: Simulator
References:
Task Number: Validation Time: Classroom X Perform X Simulate EPIP-1 "Emergency Plan Classification Flowpath," Rev. 30; EPIP-5 "GENERAL EMERGENCY," Rev. 37 SRO-113-EPIP-001 Applicable for: RO SRO X 15 minutes Time Critical:
Yes X No ---------------------------------------------------------------------------

Applicant:
Time Start: NAME SSN Time Finish: ___ _ Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE ===================================================================================
COMMENTS 2 of 9 WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam ) THIS JPM IS PERFORMED IN A CLASSROOM SETTING. REQUIRED MATERIALS:
EPIP-1 through EPIP-5 Tools/Equipment/Procedures Needed: Copies of the WBN EPIPs for each applicant.
PRoe 3 of 9 ') WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam THIS JPM IS PERFORMED IN A CLASSROOM SETTING. REQUIRED MATERIALS:
EPIP-1 through EPIP-5 Tools/Equipment/Procedures Needed: Copies of the WBN EPIPs for each applicant.
PAne 3 of 9
) WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:
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. A Unit 1 shutdown was initiated prior to reaching the Tech Spec limit for RCS activity being elevated and increasing.
2. After starting the shutdown, indications of a primary system leak developed.
3. A safety injection was manually initiated during the performance of AOI-6, "Small Reactor Coolant System Leak" due to a imminent loss of pressurizer level with charging flow at 150 gpm and letdown isolated.
4. The operators are performing actions of E-O, "Reactor Trip or Safety Injection." INITIATING CUES: 1. The US has informed you, the SED, of the leak. 2. Using the following parameters, classify the event according to the EPIPs, determine what, if any, Protective Action Recommendations are required, and complete any required appendices.
a. Containment pressure is +0.11 psid and steady. b. Containment Sump level is not increasing.
c. RHR Pipe Break White Lights have just illuminated.
d. Auxiliary Building Vent 0-RM-90-1 01 B is increasing.
e. Several Area Rad Monitors on EI 692 and 713 are in Hi Rad. f. Chemistry reports a step rise in the RCS activity to 410 JJCi/gm dose equivalent Iodine 131. 3. This JPM is a Time Critical JPM.
4 of 9 WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:
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. A Unit 1 shutdown was initiated prior to reaching the Tech Spec limit for RCS activity being elevated and increasing.
2. After starting the shutdown, indications of a primary system leak developed.
3. A safety injection was manually initiated during the performance of AOI-6, "Small Reactor Coolant System Leak" due to a imminent loss of pressurizer level with charging flow at 150 gpm and letdown isolated. ) 4. The operators are performing actions of E-O, "Reactor Trip or Safety Injection." INITIATING CUES: 1. The US has informed you, the SED, of the leak. 2. Using the following parameters, classify the event according to the EPIPs, determine what, if any, Protective Action Recommendations are required, and complete any required appendices.
a. Containment pressure is +0.11 psid and steady. b. Containment Sump level is not increasing. . c. RHR Pipe Break White Lights have just illuminated.
d. Auxiliary Building Vent 0-RM-90-1 01 B is increasing.
e. Several Area Rad Monitors on EI 692 and 713 are in Hi Rad. f. Chemistry reports a step rise in the RCS activity to 410 dose equivalent Iodine 131. 3. This JPM is a Time Critical JPM. P::lOP. 4 of 9
) WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam . START TIME: __ _ STEP 1: Refers to EPIP-1 to determine level of event. STANDARD:
CRITICAL STEP Applicant refers to EPIP-1, Section 1, and "Fission Product Barrier Matrix." Applicant determines that they have met the conditions of:
9..... /H./2.**.,.0//
..** /. ..*..*** " .n .**. M./.9/". Based on "Emergency Class Criteria", the applicant determines the need to declare a General Emergency, based on Loss of two barriers and )1 potential loss of the third barrier. Criteria to meet the critical step is for the EALs to be correctly identified and the declaration made within 15 minutes. NOTE TO EXAMINER:
RECORD time that declaration was made: ___ _ COMMENTS:
P;me 5 of 9 SAT UNSAT ) WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam START TIME: __ _ STEP 1: Refers to EPIP-1 to determine level of event. CRITICAL STANDARD:
STEP Applicant refers to EPIP-1, Section 1, and "Fission Product Barrier Matrix." Applicant determines that they have met the conditions of: 1.1.2 Loss, "RCS sample activity is greater than 300 j.JCilgm dose. equivalent 1131" 1.2.2 Potential Loss, "Non Isolatable RCS leak exceeding the capacity of one chargrng pump in the normal charging alignment" 1.3.2 Loss, "Containment pressure or sump level not increasing with a LOCA in progress" Based on "Emergency Class Criteria", the applicant determines the need to declare a General Emergency, based on Loss of two barriers and ) potential loss of the third barrier. Criteria to meet the critical step is for the EALs to be correctly identified and the declaration made within 15 minutes. NOTE TO EXAMINER:
RECORD time that declaration was made: ----COMMENTS:
PRoe 5 of 9 SAT UNSAT STEP 2: STANDARD:
COMMENTS:
WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam Implements EPIP-5, "GENERAL EMERGENCY." EPIP-5, GENERAL EMERGENCY, is implemented.
The following steps are from EPIP-5 STEP 3: [1] IF the onsite emergency centers are not staffed, THEN DIRECT Shift Personnel to activate the Emergency Paging System (EPS) to staff the Technical Support Center (TSC) and Operations Support Center (OSC). Shift Personnel should confirm activation and provide the 20 minute printed report to the SM for review. a. IF the EPS system fails, call the ODS, ringdown or (5-751-1700) and DIRECT him to activate the EPS. b. IF the above methods of activating the EPS fail, THEN DIRECT Shift Personnel to use the Watts Bar Nuclear Plant Emergency Response Call-List to staff the TSC and OSC. (This list is located in the EPS Manual near the terminal.)
STANDARD:
Shift Personnel are directed to activate the Emergency Paging System (EPS) CUE: When directed state "Emergency paging to be activated." COMMENTS:
PAne 6 of 9 SAT UNSAT SAT UNSAT ) STEP 2: STANDARD:
COMMENTS:
WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam Implements EPIP-5, "GENERAL EMERGENCY." EPIP-5, GENERAL EMERGENCY, is implemented.
The following steps are from EPIP-5 STEP 3: [1] IF the onsite emergency centers are not staffed, THEN DIRECT Shift Personnel to activate the Emergency Paging System (EPS) to staff the Technical Support Center (TSC) and Operations Support Center (OS C). Shift Personnel should confirm activation and provide the 20 minute printed report to the SM for review. a. IF the EPS system fails, call the ODS, ringdown or (5-751-1700) and DIRECT him to activate the EPS. b. IF the above methods of activating the EPS fail, THEN DIRECT Shift Personnel to use the Watts Bar Nuclear Plant Emergency Response Call-List to staff the TSC and OSC. (This list is located in the EPS Manual near the terminal.)
STANDARD:
Shift Personnel are directed to activate the Emergency Paging System (EPS) CUE: When directed state "Emergency paging to be activated." COMMENTS:
PRne 6 of 9 SAT -UNSAT -SAT -UNSAT -
STEP 4: STANDARD:
WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam [2] IF the TSC has not been activated, THEN a. INITIATE Appendix A and B, Initial Notification Form for GENERAL EMERGENCY and Protective Action Recommendations.
NOTE TO EVALUATOR:
Appendix A information required to satisfy the critical step is as identified on the attached key and listed below. o Classification of General Emergency o EAL Designators 1.1.2(L), 1.2.2(P), 1.3.2(L) o Recommedation 2 o Wind direction from 171-230 oAffected Sectors A-1 ,B-1 ,C-1 ,0-1, A-2,-3, B-2,-4, and C-2 CUE: Provide the applicant with the following data from the 46 meter MET TOWER: Wind speed is 10 mph from 180°. )\ COMMENTS:
P80A 7 of 9 CRITICAL STEP SAT UNSAT STEP 4: WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam [2] IF the TSC has not been activated, THEN a. INITIATE Appendix A and 8, Initial Notification Form for GENERAL EMERGENCY and Protective Action Recommendations.
STANDARD:
Applicant completes Appendix A and Appendix 8, determines Recommendation
2. NOTE TO EVALUATOR:
Appendix A information required to satisfy the critical step is as identified on the attached key and listed below. o Classification of General Emergency o EAL Designators 1.1.2(L), 1.2.2(P), 1.3.2(L) o Recommedation 2 oWind direction from 171-230 oAffected Sectors A-1 ,B-1 ,C-1 ,0-1, A-2,-3, B-2,-4, and C-2 CUE: Provide the applicant with the following data from the 46 meter MET TOWER: Wind speed is 10 mph from 180°. ) COMMENTS:
P::Jnp. 7 of 9 CRITICAL STEP SAT UNSAT
/1 ) STEP 5: WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam b. NOTIFY the ODS direct by ODS Ring-down or by USING 5-751-1700 or 5-751-2495; and 1) PROVIDE the information from Appendix A. STANDARD:
Applicant provides the information to the ODS. Criteria to meet the critical step is for the ODS to be provided the information within 10 minutes after the declaration is made. NOTE TO EXAMINER:
RECORD time that ODS is notified:
___ _ COMMENTS:
End ofJPM TIME STOP: __ _ P::IClA 8 of 9 CRITICAL STEP SAT UNSAT ) STEP 5: WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam b. NOTIFY the ODS direct by ODS Ring-down or by USING 5-751-1700 or 5-751-2495; and 1) PROVIDE the information from Appendix A. STANDARD:
Applicant provides the information to the ODS. Criteria to meet the critical step is for the ODS to be provided the information within 10 minutes after the declaration is made. NOTE TO EXAMINER:
RECORD time that ODS is notified:
___ _ COMMENTS:
End of JPM TIME STOP: __ _ P;:)oe 8 of 9 CRITICAL STEP SAT UNSAT
t.a \L\d. ,MH t 0\\4""" la..;i, LA-\ -:?
WBN GENERAL EMERGENCY
! EPIP-S! APPENDIX A ,--::J.-* -** TVA INITIAL NOTIFCATION FORM FOR GENERAL EMERGENCY
1.
is a Orill o This is an Actual Event -Repeat -This is an Actual Event 2. This is'ru.rte " , W ov..' L 0 JJI, Watts Bar has declared EMERGENCY ffecting Unit 1 (I(:f&C\I;tA' if 3. EAL Designator(s):(l.l.l(C.)
(.'2, l.3,2(0) IN J "-4. Brief Description of the Event: LQC-A hi de. t!..a", +A 'NM t"N1 VV ,1"!:j 14; toY 5 .. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liguid Releases Offsite t\ u.yl. Minor releases within federally approved limits Minor releases within federally approved limits' Releases above federally approved limits 1* 0 Releases above federally approved limits 1 Release information not known e.i\", Release information not known }, 1 1 ( Tech Specs) ( Tech Specs) \ ---;'\ Q "1; "d k" \ 6. Event Declared:
Time: I yw'\ e.. Oate: I} 7. The Meteorological Conditions are: (Use 46 meter data from the Met Tower) Wind Oirection is FROM: degrees Wind Speed: 111 m.p.h 8. Provide Protective Action Recommendation: (Check either 1,2 or 3, and mark wind direction.)
* --o Recommendation 1 R WIND FROM ° R )
LISTED SECTORS E (Mark) E E LISTED SECTORS (2 mile Radius and 10 miles downwind)
C C (2 mile radius and 5 mile downwind)
TER remainder of 10 mile EPZ.
remainder of 10 mile EPZ.
issuance of Potassium Iodide in 1 issuance of Potassium accordance with the State Plan. 2 Iodide in accordance with the State Plan. A-1, 8-1, C-1, 0-1, 26-68 A-1, 8-1, C-1, 0-1, C-7, D-2, 4, -5 A-1, 8-1, C-1, 0-1,69-110 A-1, 8-1; C-1, 0-1, A-3, -4, D-2, -3, 4, -5, -6, -7, -8, -9 A-3, D-2, 4, -5 A-1, 8-1, C-1, 0-1, 111-170 A-1, 8-1, C-1, 0-1, A-2, -3, -4, -5, -6, -7, D-2, -3, -5, -6 A-2 -3, D-2 -5 A-1, 8-1, C-1, 0-1, A-1, 8-1, C-1, 0-1, ) A-2, -3, -5, -6, -7, B-2, -3, -4, -5, C-2 A-2 -3 B-2 -4. C-2. A-1, 8-1, C-1, 0-1, 231-270 . A-1, 8-1, C-1, 0-1, B-2, -3, 4, -5, C-2, -3,
-4, C-2 A-1, 8-1, C-1, 0-1, 271-325 A-1, 8-1, C-1, 0-1, B-2, -3, C-2, -3, -4, -5, -6, -11 B-2, C-2, -4, -5, A-1, 8-1, C-1, 0-1, 326-25 A-1, 8-1, C-1, 0-1, C-2, -4, -5, -6, -7, -8, -9, -10, -11, D-4,-9 C-2, 4, -5, -7, -8, D-4 o Recommendation 3
TER all sectors.
issuance of Potassium Iodide in accordance with the State Plan. 9. Please repeat the information you have received to ensure accuracy.
I .... 10. Time and Oate this information was provided.
Time: '
Oate "d\A-k." ....-*Action: When notification complete, FAX form as prescribed in this instruction.
PAGE 13 of 17 REVISION 37 .r
-, t" pv i1t::R> WBN ! GENERAL EMERGENCY
! EPIP-S! APPENDIX A (Page 1 of 1) TV A INITIAL NOTIFCATION FORM FOR GENERAL EMERGENCY
1. [3"'This is a Orill D This is an Actual Event -Repeat -This is an Actual Event 2. This " , IN 0""\ L C!JJJI, h(.. Watts Bar has declared EMERGENCY ffecting Unit 1 N'..vl-if 3. EAL oesignator(s):L[l.2.(L.) t * '1 ,?.lP) l.3,2(0) IN Ii-"-4. Brief Oescription of the Event: h; de. L()N C:-N1 vv/1/j H-; R t.s J\t.,ti " ; t:J 5. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liguid Releases Offsite Minor releases with in federally approved Ii mils Minor releases within federally approved limits' Releases above federally approved limits 1. D Releases above federally approved limits 1 Release information not known E.ih.. Release information not known ( 1Tech Specs) ( 1Tech Specs) ------'\ '" \'d4k" \ 6. Event Oeclared:
Time: I\""') e. Oate: 7. The Meteorological Conditions are: (Use 46 meter data from the Met Tower) Wind Oirection is FROM: I BO degrees Wind Speed: 10 m.p.h 8. Provide Protective Action Recommendation: (Check either 1, 2 or 3, and mark wind direction.)
* ---D Recommendation 1 R WIND FROM 0 R ) =>EVACUATE LISTED SECTORS E (Mark) E =>cVACUA I E LISTED SECTORS (2 mile Radius and 10 miles downwind)
C C (2 mile radius and 5 mile downwind)
=>SHEL TER remainder of 10 mile EPZ. =>SHEL TER remainder of 10 mile EPZ. =>CONSIDER issuance of Potassium Iodide in 1 2 =>CONSIDER issuance of Potassium accordance with the State Plan. Iodide in accordance with the State Plan. A-1, B-1, C-1, 0-1, 26-68 A-1, B-1, C-1, 0-1, C-7, -9, 0-2, -4, -5, -6, -7, -8, -9 C-7, 0-2, -4, -5 A-1, B-1, C-1, 0-1,69-110 A-1, B-1, C-1, 0-1, A-3, -4, 0-2, -3, -4, -5, -6, -7, -8, -9 A-3, 0-2, -4, -5 A-1, B-1, C-1, 0-1, 111-170 A-1, B-1, C-1, 0-1, A-2, -3, -4, -5, -6, -7,0-2, -3, -5, -6 A-2 -3, 0-2 -5 A-1, B-1, C-1, 0-1, Q71-230 A-1, B-1, C-1, 0-1, ) A-2, -3, -5, -6, -7, B-2, -3, -4, -5, C-2 A-2 -3 B-2 -4. C-2 A-1, B-1, C-1, 0-1, 231-270 A-1, B-1, C-1, 0-1, B-2, -3, -4, -5, C-2, -3, B-2, -4, C-2 A-1, B-1, C-1, 0-1, 271-325 A-1, B-1, C-1, 0-1, B-2, -3, C-2, -3, -4, -5, -6, -11 B-2, C-2, -4, -5, A-1, B-1, C-1, 0-1, 326-25 A-1, B-1, C-1, 0-1, C-2, -4, -5, -6, -7, -8, -9, -10, -11,0-4,-9 C-2, -4, -5, -7, -8, 0-4 D Recommendation 3 =>SHEL TER all sectors. =>CONSIDER issuance of Potassium Iodide in accordance with the State Plan. 9. Please repeat the information you have received to ensure accuracy.
10. Time and Oate this information was provided.
Time: \
Oate " d\/t -Ie " /' *Action: When notification complete, FAX form as prescribed in this instruction.
PAGE 13 of 17 REVISION 37 WBN GENERAL EMERGENCY
! EPIP-S! APPENDIX B (Page 1 of 1) PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer is NO. Note 2: A short term release is defined as "a release that does not exceed a 15 minute duration".
GENERAL EMERGENCY DECLARED CONTINUE ASSESSMENT I t Modify protective actions based on available 4 plant and field monitoring information.
'" Is there a . short term controlled release whereas near plant areas cannot be evacuated before plume arrival? (see Note 2) YES RECOMMENDATION 3 SHELTER 10 mile EPZ RECOMMENDATION 1 EVACUATE 2 miles radius and 10 miles downwind AND SHELTER remainder of 10 mile EPZ 1
Locate and evaluate localized hot spots. NO -==;> At . or beyond 5 miles, is the Projected OR NO --==> Measured Dose greater than Table 1 limits? YES tv RECOMMENDATION 2 EVACUATE 2 miles radius and 5 miles downwind AND SHELTER remainder of 10 mile EPZ TABLE 1 Protective Action Guides (PAG) TYPE LIMIT Measured 3.9 E-6 micro Cilcc of Iodine 131 or 1 REM per hour External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE PAGE 14 of 17 REVISION 37 WBN GENERAL EMERGENCY
! EPIP-5! APPENDIX B (Page 1 of 1) PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer is NO. Note 2: A short term release is defined as "a release that does not exceed a 15 minute duration".
GENERAL EMERGENCY DECLARED CONTINUE ASSESSMENT 1+----------- Modify protective actions based on available plant and field monitoring information.
Is there a short term controlled release whereas near plant areas cannot be evacuated before plume arrival? (see Note 2) YES RECOMMENDATION 3 SHELTER 10 mile EPZ RECOMMENDATION 1 EVACUATE 2 miles radius and 10 miles downwind AND SHELTER remainder of 10 mile EPZ 1 -Locate and evaluate localized hot spots. NO At or beyond 5 miles, is the Projected OR NO -==> Measured Dose greater than Table 1 limits? YES RECOMMENDATION 2 EVACUATE 2 miles radius and 5 miles downwind AND SHELTER remainder of 10 mile EPZ TABLE 1 Protective Action Guides (PAG) TYPE LIMIT Measured 3.9 E-6 micro Ci/cc of Iodine 131 or 1 REM per hour External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE PAGE 14 of 17 REVISION 37
) APPLICANT HANDOUT SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed forthis JPM, incluqing any required communications.
I will provide initiating cues and reports on other actions when airected 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. A Unit 1 shutdown was initiated prior to reaching the Tech Spec limit for RCS activity being elevated and increasing
.. 2. After starting the shutdown, indications of a primary system leak developed.
3. A safety injection was manually initiated during the performance of AOI-6, "Small Reactor Coolant System Leak" due to a imminent loss of pressurizer level with charging flow at 150 gpm and letdown isolated.
4. The operators are performing actions of E-O, "Reactor Trip or Safety Injection." INITIATING CUES: 1. The US has informed you, the SED, of the leak. 2. Using the following parameters, classify the event according to the EPIPs, determine what, if any, Protective Action Recommendations are required, and complete any required appendices.
a. Containment pressure is +0.11 psid and steady. b. Containment Sump level is not increasing.
c. RHR Pipe Break White Lights have just illuminated.
d. Auxiliary Building*
Vent 0-RM-90-1 01 B is increasing.
e. Several Area Rad Monitors on EI 692 and 713 are in Hi Rad. f. Chemistry reports a step rise in the RCS activity to 410 IJCi/gm dose equivalent Iodine 131. 3. This JPM is a Time Critical JPM. A.4-SRO APPLICANT HANDOUT SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:
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. A Unit 1 shutdown was initiated prior to reaching the Tech Spec limit for RCS activity being elevated and increasing.
2. After starting the shutdown, indications of a primary system leak developed.
3. A safety injection was manually initiated during the performance of AOI-6, "Small Reactor Coolant System Leak" due to a imminent loss of pressurizer level with charging flow at 150 gpm and letdown isolated.
4. The operators are performing actions of E-O, "Reactor Trip or Safety Injection." \ INITIATING CUES: 1. The US has informed you, the SED, of the leak. 2. Using the following parameters, classify the event according to the EPIPs, determine what, if any, Protective Action Recommendations are required, and complete any required appendices.
a. Containment pressure is +0.11 psid and steady. b. Containment Sump level is not increasing.
c. RHR Pipe Break White Lights have just illuminated.
d. Auxiliary Building Vent 0-RM-90-1 01 B is increasing.
e. Several Area Rad Monitors on EI 692 and 713 are in Hi Rad. f. Chemistry reports a step rise in the RCS activity to 410 IJCilgm dose equivalent Iodine 131. 3. This JPM is a Time Critical JPM. A.4-SRO

ML100830118

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