Text

Initial Exam 2009-302 Draft Administrative JPMs
	ML100830095
Person / Time
Site:	Watts Bar
Issue date:	02/11/2010
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/09-302
	Download: ML100830095 (265)
	v • d • e

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DRAFT ADMINISTRATIVE JPMS CONTENTS:

~aft ADMIN JPMs Location of Electronic Files:

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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 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 X- - - Simulate

References:

OPDP-10, "License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions ," Rev. 1 Task Number: RO-119-PAI-2.07-001

Title:

Maintain active NRC License Task Standard: Candidate determines the correct status of each of the three Reactor Operator licenses. Operator A and C are active, Operator B is Inactive 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

WATTS BAR NUCLEAR PLANT A.1-1 RO/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. Three Reactor Operators have the following history:

2. All three 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 3 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:

License was active on October 1, 2009.

10102/09 Worked 0700-1900 shift as Unit 1 OAG.

10103/09 Worked 0700-1900 shift as Unit 1 OAG.

(

\

10104/09 Worked 0700-1900 shift in the Ta in Office.

10105/09 Worked 0700-1900 shift as Unit 1 OAG.

10106/09 Worked 0700-1900 shift as Unit 1 OAG.

11/14/09 Worked 1900-0700 shift as Unit 1 OAG.

11/17/09 Worked 1900-0700 shift as Unit 1 GRO.

License was active on October 1, 2009.

10101/09 Worked 0700-1900 shift as Unit 1 OAG.

10102/09 Worked 0700-1900 shift in the Ta in Office.

10103/09 Worked 0700-1900 shift as Unit 1 GRO.

10105/09 Worked 0700-1900 shift as Unit 1 OAG.

10/14/09 Worked 1900-0700 shift as Unit 1 OAG.

11/02/09 Worked 0700-1900 shift in the Ta in Office.

License was inactive on October 1, 2009.

10/5/09 thru 10109/09 worked 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the Unit 1 OAG and com leted all re uirements for license reactivation.

11/12/09 Worked 0700-1900 shift as Unit 1 OAG.

11/13/09 Worked 0700-1900 shift as Unit 1 OAG.

11/15/09 Worked 0700-1900 shift as Unit 1 OAG.

11/16/09 Worked 1900-0700 shift as Unit 1 OAG.

11/21/09 Worked 1900-0700 shift as Unit 1 OAG.

INITIATING CUES:

1. You are to determine if each of the Reactor Operators is eligible to work the Unit 10Ae 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 SAT/UNSAT START TIME: _ __

STEP 1.: Determine the Active I Inactive status of Operator A license. - SAT

- UNSAT STANDARD:

Candidate determines the license is Active because the operator worked the required 5 twelve hour shifts in a license position during the previous quarter.

COMMENTS:

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

- SAT STANDARD: - UNSAT Candidate determines the license is Inactive because the operator did not work the required 5 twelve hour shifts in a license position during the previous quarter.

COMMENTS:

PAGE 4 OF 6

WATTS BAR NUCLEAR PLANT A.1-1 RO/SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3.: Determine the Active / Inactive status of Operator C license. SAT STANDARD: UNSAT Candidate 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.

COMMENTS:

END OF TASK STOP TIME _ __

PAGE 5 OF 6

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. Three Reactor Operators have the following history:

2. All three 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 3 has worked any shift since 12/01/09.

4. Activellnactive 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 OAe.

OAC.

10103/09 Worked 0700-1900 shift as Unit 1 OAe.

OAC.

10104/09 Worked 0700-1900 shift in the Tagging Office.

10105/09 Worked 0700-1900 shift as Unit 1 OAe.

OAC.

, 10106/09 Worked 0700-1900 shift as Unit 1 OAe.

OAC.

I

," 11/14/09 Worked 1900-0700 shift as Unit 1 OAe.

OAC.

11/17/09 Worked 1900-0700 shift as Unit 1 CRO.

eRO.

Operator 8 License was active on October 1, 2009 .

10101/09 Worked 0700-1900 shift as Unit 1 OAC.

OAe.

10102/09 Worked 0700-1900 shift in the Tagging Office.

10103/09 Worked 0700-1900 shift as Unit 1 CRO.

eRO.

I.*... 10105/09 Worked 0700-1900 shift as Unit 1 OAe.

OAC.

.,F~~,

!~'./ \ . ,.... . . ..' .......

10/14/09

'" ... , 11/02/09 Worked 1900-0700 shift as Unit 1 OAe.

OAC.

Worked 0700-1900 shift in the Tagging Office.

Operator C License was inactive on October 1, 2009.

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I/:~; ;!if~;~.;*. . 10/5/09 thru 10109/09 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 10/5/09 completed all requirements for license reactivation.

OAe and

}.{1~~~i****

~*,l '., . .* 11/12/09 Worked 0700-1900 shift as Unit 1 OAe.

OAC.

Ir;;ii;;"i:~~~ 11/13/09 Worked 0700-1900 shift as Unit 1 OAe.

OAC.

t~~:~~ i'~~~

11/15/09 Worked 0700-1900 shift as Unit 1 OAe.

OAC.

I, 11/16/09 Worked 1900-0700 shift as Unit 1 OAe.

OAC.

I'~~\:;~/,!t l;,!A'?. . . . . .,. 11/21/09 i.**..* Worked 1900-0700 shift as Unit 1 OAC.

OAe.

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.

TITLE OPDP-10 rmJ License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Rev. 0001 Page 1 of 20 Quality Related o Yes DNa 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 20f20 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-1 0-1.

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 License Limited 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 10CFR55.53 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. 10CFR55.53(e)

4. NUREG-1262 - Preface; pages 71-80

5. NUREG-1021 - ES-605

6. Technical Specification j

/

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 Cl 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 6 of 20 3.2.4 INSTRUCTIONS (continued)

D. Technical Specifications / 10CFR50 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 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Pa~e 7of20 Page 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 liceriseeare 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 fora 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 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 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 SRO 0 RO 0 (check one)

B. 40 Hours on Shift

Attach copy of Operating Log for each shift.

C. Tour of Plant (Check box below when complete) o AppendixA D. Shift Turnover

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 12 of 20 Appendix A (P~ge 2 of 7)

Return to Active Status Checklist Licensee 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-Iicensed 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 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 License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 13 of 20 Appendix A (Page 3 of 7)

Return to Active Status Checklist Operations Training Manager To:

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: / /

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.

Date: _ _ / _ _ / _ _

Licensee cc: Operations Manager Training File 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 Page 14 of 20 Appendix A (Page 4 of 7)

Return to Active Status Checklist (Completed ONCE per Reactivation)

NAME:

Licensee 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 (Shift Manager)

Review Control Room Logs Radiological Conditions in the plant Significant Modifications and major maintenance activities.

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, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 15 of 20 Appendix A (Page 5 of 7)

Return to Active Status Checklist BFN Tour Checklist 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 License Status Maintenance, OPDP-10 Department Reactivation and Proficiency for Rev. 0001 Procedure Non-Licensed Positions Page 16 of 20 Appendix A (Page 6 of 7)

Return to Active Status Checklist SQN Tour Checklist 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 DI Building

(

Diesel Generator Building All Levels of Control Building Outside Areas, including CCW Building, New Makeup DI Building and Switchyard ERCW Structure 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 17 of 20 Appendix A (Page 7 of 7)

Return to Active Status Checklist WBN Tour Checklist 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 M!3keup 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 Pase Appendix B (Page 1 of 2)

Activation of SRO License Limited to Fuel Handling Licensed IndividuallEIN 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 10CFRSO.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 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 20 of 20 Appendix C (Page 1 of 1)

Active Licensed Maintenance for Off-Shift Personnel Quarterly On-Shift Time Documentation NAME:

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 A.1-2 RO Perform RCS Deboration Calculation PA(';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: . NIA 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 -

xX In-Plant Perform x

-X

Simulate

References:

SOI-62.04, "cvcs Purification System," Rev. 53 TI-59, "Boron Tables," Rev. 7 Task Number: RO-062-TI-59-001

Title:

Perform boron concentration change calculations.

( Task Standard: 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."

Validation Time: 10 minutes Time Critical: Yes - - No X

===============================================================

Applicant: Time Start:

NAME SSN __

Time Finish: - -_-

Performance Rating: SAT UNSAT Performance Time Examiner: -----------------------.1

.1_ _-

NAME SIGNATURE DATE

===============================================================

COMMENTS PAr,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 Cs 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 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 ~ OF 7

WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam I STEP/STANDARD SAT/UNSAT START TIME: _ __

STEP 1: [1] INDICATE Mixed Bed for which this calculation is being SAT performed (CHECK ONLY ONE.)

UNSAT

_ _ _ _ OR Mixed Bed B --------

Mixed Bed A -------- _ _ __

STANDARD:

From INITIAL CONDITIONS, the applicant checks Mixed Bed A.

COMMENTS:

(

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:

QT

- V Cf= Cae 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)

PAGE40F 7

WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT STEP 2: [2] RECORD current RCS Temperature: - SAT

- UNSAT STANDARD:

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 CRITICAL using TI-59 (first page of App D through App N, as STEP appropriate.)

- SAT

( STANDARD: UNSAT Applicant locates TI-59, and selects Appendix L, and records 87813.5 as the RCS volume.

COMMENTS:

PAGE 5 OF 7

WATTS BAR NUCLEAR PLANT A.1-2 RO Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT STEP 4: [4] PERFORM the following calculation to estimate time in CRITICAL service: STEP

-In ( _ _,ppml----Ppm) SAT

-In (Cf/C o ) V ppml----Ppm) _ _ gals Time=----- =----------- UNSAT Q _ _ _ _ _gpm Time = minutes STANDARD:

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

SOI-62.04 WBN CVCS PURIFICATION SYSTEM Revision 53 1

Page 77 of 85 APPENDIX B Page 1 of 1 RCS DEBORATION CALCULATION

[1] INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY ON'7) (Fnwtt l"iNI (i_It",S)

Mixed Bed A V OR Mixed Bed B 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:

2I

- 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 D through App N, as appropriate.)

B7I"~.fRCS Volume

[4] PERFORM the following calculation to estimate time in service:

-In (Cf/C o) V -In (Kppm/$&ppm) ~fI!'

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

Q IZO

_~--'=- .gpm

_---'----'-_~gpm Time = 77. I minutes ~11.w 75 -Ie SO

[5] RECORD Mixed Bed Run times for which this Calculation is being lVI_leS performed (Times can be obtained from Attachment 1 for the associated demin).

1 234 5 6 7 8 Run time Total time Initials

\{F"

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 CB 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 the CVCS mixed bed demineralizer 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.

501-62.04 WBN CVCS PURIFICATION SYSTEM Revision 53 1

Page 77 of 85 APPENDIX B Page 1 of 1 RCS DEBORA TION CALCULATION

[1] INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY ONE.)

Mixed Bed A - _- __ -_ - OR Mixed Bed B 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 = 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 (Cf/C o) V -In ( _ _ppm/_ppm) _ _ _ 9 als Time=----- =------------

Q _ _ _ _ _9 pm 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 2 3 4 5 6 7 8 Run time Total time Initials

WBN Boron Tables TI-59 Unit 1 Rev. 0007 Page 89 of 105 Appendix L (Page 1 of 8)

Boron Tables For ReS At 575°F 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

( *********************************************************************************

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 1::\

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

Alternate Path: None Facility JPM. #: 3-0T-JPM ADA 1.6 KIA Rating(s): 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2)

Task Standard: 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 Classroom x Perform x Simulate

References:

1-SI-0-11, "Estimated Critical Position," Rev 14 WCAP-16880-P, NuPOP for WBN Unit 1, Cycle 9 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 Task Number: SRO-085-SI-0-11-001 Applicable for: RO 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 PAr,F ? OF 1~

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 CB 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 CB 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.

\

PA(';F ~ OF 1 ~

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __

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: CRITICAL STEP A. All Rods Out (ARO) Critical Cb: _ _ ppm.

SAT B. Differential Boron Worth (DBW) at the ARO Critical Cb:

__ pcm/ppm. UNSAT STANDARD:

ERRORS TO BE IDENTIFIED:

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 (i.e. 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 vCllue of 254.3 was inserted in the Inserted Rod Worth blank.

COMMENTS:

PAGE 5 OF 13

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

UNSAT STANDARD:

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

COMMENTS:

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

A. RECORD the ARO Critical Cb inferred by the Sub-Critical UNSAT Rod Worth Measurement from PET-107:

Inferred ARO Cb = ppm STANDARD:

From the INITIAL CONDITIONS, the applicant determines that the correct value of 1700 was entered.

COMMENTS:

PAGE 6 OF 13

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: [5] IF performing a pull-to-critical, THEN PERFORM the following CRITICAL sUb-steps: STEP B. CALCULATE the critical boron concentration at the ECP SAT as follows:

UNSAT EGG Gb = Inferred ARO Gb + (Inserted Rod Worth DBW)

EGG Gb = ppm + ppm _pcm/ppm (Step 6.5[5]A ) (Step 6.5[3]) (Step 6.5[1]B)

EGG Gb = ___ppm for Bank 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: [6] VERIFY ECP is above the Control Bank Insertion Limits in SAT the COLR (Acceptance Criteria 5.1A).

UNSAT STANDARD:

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

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD sAT/UNsAT STEP 7: [7] IF applicable, THEN VERIFY ECP is below the Negative SAT MTC Withdrawal Limit from Step 6.4[2] D (Acceptance Criteria 5.1 B). UNSAT STANDARD:

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.

NOTE TO EVALUATOR: JPM steps8 through 13 are all associated with 0-51-0-11 Step

( 8.

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

UNSAT 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

WATTS BAR NUCLEAR PLANT A.1-2 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: [8] CALCULATE, AND RECORD the UPPER and LOWER SAT Acceptance Bands:

UNSAT 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 SAT Acceptance Bands:

UNSAT 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 STANDARD:

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

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 750 pcm Limit from NuPOP Table 7-30:

Step 6.5[3] + 750 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 Control 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 500 pcm Limit from NuPOP Table 7-30:

Step 6.5[3] - 500 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:

PAGE 10 OF 13

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

UNSAT 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 STANDARD:

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

STANDARD:

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

COMMENTS:

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 SAT/UNSAT STEP 14: [10] OBTAIN review of calculations and results by task qualified CRITICAL individual. An STA or SRO may also perform this review. STEP STANDARD: SAT Applicant states that the package contains errors and must be returned to UNSAT 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

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 CB is 2870 ppm.

3. CurrentRCS temperature is 557°F.

4. Unit startup will be via control rods.

5. PET 107 performance data predicts ARO Critical CB 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.

KE'i KE'f' WBN Estimated Critical Position 1-51-0-11 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: rfE(l.~fL ~ shPu.ld b-<.-

\.Y & J ". - ltDCf~

All Rods Out (ARO) Critical Cb : .4e-z.. ppm. ffrYl

)

&Differential Boron Worth (DBW) at the ARO Critical Cb :

".~O pcm/ppm. (E2.t(ot< 1 ~o1.l1J be.. -~ ) ..........-

~ RECORD the desired Control Bank D 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:

=IS4.'

Inserted Rod Worth pcm IF performing a dilute-ta-critical, dilute-to-critical, THEN

( CALCULATE the critical boron concentration at the ECP as follows:

EGG Gb = ARO Gb + (Inserted Rod Worth DBW)

EGG Gb = ppm + _ _ _ _ _ pcm + _ _ pcm/ppm (Step 6.5[1]A) (Step 6.5[3]) (Step 6.5[1]B)

EGG Gb = _ _ _ ppm for Bank D at _ _ _ steps

& IF performing a pull-to-critical, THEN PERFORM the following sUb-steps:

~ RECORD the ARO Critical Cb inferred by the Sub-Critical

~ Rod Worth Measurement from PET-107:

Inferred ARO Cb = 17DO ppm KEY

KE.y WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 26 of 69 Data Package: Page __ of __ Date _ __

6.5 ECP Hand Calculation Following a Refueling Outage (continued)

~ CALCULATE the critical boron concentration at the ECP

~sfollows:

EGG Gb = Inferred ARO Gb + (Inserted Rod Worth + DBW) (eIl.~" \fa.t",,-

~ ~L1.()£c'IJ. 10<:.-

EGC Gb = 170() ppm + Z. 5"+.'$ pcm + ~ pcm/ppm _ ~. \~)

(Step 6.5[5]A ) (Step 6.5[3]) (Step 6.5[1 ]B)

~

EGG Gb = 11+\ ppm for Bank D at 11,0 steps

~ VERIFY ECP is above the Control Bank Insertion Limits in the

~ COLR (Acceptance Criteria 5.1A).

& ,..IIF F 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.

~ CALCULATE, AND RECORD the UPPER and LOWER

~ Acceptance Bands:

~ DETERMINE the Upper 1000 pcm Limit from NuPOP

~able7-30:

Step 6.5[3] - 1000 pcm = -74t. pcm Bank C at Zz.& steps & Bank D at ~6 steps

~ DETERMINE the Lower 1000 pcm Limit from NuPOP

~ Table 7-30: .

Step 6.5[3] + 1000 pcm = 1!2l pcm Bank C at ,,, '2... steps & Bank D at # steps KE'1

KE WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Pa e 27 of 69 Data Package: Page _ _ of _ _ Date _ __

6.5 ECP Hand Calculation Following a Refueling Outage (continued)

~ DETERMINE the Upper 750 pcm Limit from NuPOP Table l:5( 7-30:

Step 6.5[3] - 750 pcm = -41S' pcm Bank C at ~2.e steps & Bank D at ZZS steps

~ DETERMINE the Lower 750 pcm Limit from NuPOP Table

\...:)l7-30:

Step 6.5[3] + 750 pcm =~ pcm Bank C at '81. steps & Bank D at ~ steps

~."""\ DETERMINE the Upper 500 pcm Limit from NuPOP Table

\.:S(J-30:

Step 6.5[3] - 500 pcm =-~ pcm Bank C at US steps & Bank D at ZZ8 steps

~ 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 Be. steps

~ RECORD the following:

~. Date of calculation: ..... / .... / ......

B. - -:-~

Time of calculation:.... -

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

~OBTAIN review of calculations and results by task qualified VindiVidual. An STA or SRO may also perform this review.

Ke~1 1<

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

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 Cs 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 Cs 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.

WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 25 of 69 Data Package: Page _I_ of -4 Date ~

6.5 ECP Hand Calculation Following a Refueling Outage

~ RECORD the following from NuPOP Table 4-8:

~ All Rods Out (ARO) Critical Cb: 14-~ 2.. ppm.

~ Differential Boron Worth (DBW) at the ARO Critical Cb:

- b. '2.0 pcm/ppm.

RECORD the desired Control Bank D rod position for initial criticality (i.e. ECP):

ECP = {to 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 = 254-.:3 pcm

~ IF 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 + _ _ _ _ _ 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 N/A

~ IF performing a pull-to-critical, THEN PERFORM the following sub-steps: li:tJ

~ RECORD the ARO Critical Cb inferred by the Sub-Critical Rod Worth Measurement from PET-107:

Inferred ARO Cb = {7 00 ppm

WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 26 of 69 Data Package: Page ~ of 4- Date ~

6.5 ECP Hand Calculation Following a Refueling Outage (continued)

" CALCULATE the critical boron concentration at the ECP as follows:

ECC Cb = Inferred ARO C b + (Inserted Rod Worth DBW) 1703 ppm + 2.. 54 ..3 pcm + ~. 2. pcm/ppm (Step 6.5[5]A ) (Step 6.5[3]) (Step 6.5[1 ]B) 1141 ppm for Bank 0 at I C, () 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:

~ DETERMINE the Upper 1000 pcm Limit from NuPOP Table 7-30:

Step 6.5[3] - 1000 pcm = 7 4-" pcm Bank C at 2. z..g steps & Bank 0 at 22.8 steps

~ DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30:

Step 6.5[3] + 1000 pcm = [2 sLIt-- pcm Bank Cat {" 2.. steps & Bank 0 at 4" steps

WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 27 of 69 Data Package: Page ~ of 4- Date ~

6.5 ECP Hand Calculation Following a Refueling Outage (continued)

~ DETERMINE the Upper 750 pcm Limit from NuPOP Table

~7-30:

Step 6.5[3] - 750 pcm =- 4'( 5 pcm Bank C at ze. g steps & Bank D at 2 ~ g steps DETERMINE the Lower 750 pcm Limit from NuPOP Table 7-30:

Step 6.5[3] + 750 pcm = l~a+ pcm Bank C at J~ 2. steps & Bank D at " ~ steps

~ DETERMINE the Upper 500 pcm Limit from NuPOP Table 7-30:

Step 6.5[3] - 500 pcm =-2.45 pcm

(

Bank C at 2Z ~ steps & Bank D at 2.e. g steps

~ DETERMINE the Lower 500 pcm Limit from NuPOP Table

~7-30:

Step 6.5[3] + 500 pcm =15+ pcm Bank C at 2c4 steps & Bank D at ~<;? steps

~ RECORD the following:

A. Date of calculation: "" /.!dJ t.I'y, B. Time of calculation:~ :).....A.

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

[1 0] OBTAI N 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 4 of A- Date -

6.5 ECP Hand Calculation Following a Refueling Outage (continued)

[11] OBTAIN SM/US review and approval of ECP.

SM/US

(

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 2of69 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 4of69 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 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 (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 2

SR 3.1.7.1 1,21 2 ,3 (1) withKeff:2:: 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 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.

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-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 (Le., 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 (i1T) for ICRR monitoring may be adjusted at the discretion of the Test Director (minimum of 10 seconds or at least 1000 counts/i1T 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/STA.

(

WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 90f69 Data Package: Page _ _ of _ _ Date _ _ __

4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions

[1] RECORD start date and time on Surveillance Task Sheet.

NOTES

1) 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.

2) The use of BEACON is the other primary method.

3) Hand calculations may also be performed as a backup method.

[2] IF REACTW or REACTINWare to be used, THEN OBTAIN PC with REACTWand/or REACTINW software installed in accordance with Release Memorandums.

[3] 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.

NOTE Reference 2.1.1 contains guidance in performing the CIPS adjustment.

[4] IF an adjustment to the ECC is desired to account for CIPS effects, THEN PERFORM the following. OTHERWISE, MARK this step N/A.

A. INTEGRATE the Actual to Predicted Axial Offset differences over the cycle life.

L JMO

d BU =- - - -%

MWD/MTU

WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 10 of 69 Data Package: Page _ __ _ of _ ___ Date _ _ __

4.1 Preliminary Actions (continued)

B. DETERMINE the increase in HZP reactivity from Figure 2.

~pCIPS = pcm C. 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.

~CbCIPS = ~pCIPS /IDBWI = /1 ____

NOTE 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:

1. 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.

2. At 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.

3. At MOL at 800 ppm and 18% B-10, an RCS cooldown to Mode 5 results in Significant RCS makeup due to shrinkage.

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

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-SI-0-11 Unit 1 Rev. 0014 Page 12 of 69 Data Package: Page _ _ of __ Date _ _ __

6.0 PERFORMANCE 6.1 Sections to be Performed

[1] ENSURE Precautions and Limitations in Section 3.0 have been reviewed.

[2] ENSURE Prerequisite Actions in Section 4.0 have been met.

NOTES

1) 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.

2) Use of Zero Power method is discouraged when the startup burnup is 3 EFPD greater than the previous startup's burnup.

[3] INDICATE sections to be performed:

( A. Section 6.2, REACTW/REACTINW ECP Calculation Using Previous At-Power Data. 0 B. Section 6.3, REACTW/REACTINW ECP Calculation Using Previous Zero Power Data. 0 C. Section 6.4, ECP Hand Calculation Using Previous At-Power Data. 0 D. Section 6.5, ECP Hand Calculation Following a Refueling Outage. 0 E. Section 6.6, ECP Calculation USing BEACON General 3D Calc. 0 F. Section 6.7, ECP Calculation Using BEACON ECC 0 G. Section 6.8, Detector Reliability and/or Base Count Rate Determination. 0 H. Section 6.9, ICRR Monitoring. 0 I. Section 6.10, Critical Data Evaluation. 0

[4] PERFORM selected section(s).

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: %. 0

Input last 10 days' at power' power history. 0

Input Sm effective worth (See TI-55). 0

(,

C. Core average burnup: MWD/MTU.

D. Boron Concentration (C b): ppm.

E. Bank D Position: steps.

F. Delta Flux (D>: %.

G. Weighted Average Delta Flux (D>: %

(Reactor Trip Report or NuPOP Table 7-28)

H. Shutdown Date and Time: - - I - I ----

Length of time since plant shutdown: _ _ _ _ hrs.

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. D
2. Equilibrium Xe and 1- use STEADY STATE Tables D Equilibrium Rx Power for Xe %
3. Input Xe and I - use TI-54 (NIX Tables) D
% of Full Power Equilibrium concentration for Xe %
% of Full Power Equilibrium concentration for I %
4. Use Xe and I - from LAST Xenon Run D
% 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-10 concentration changes, then the expected boron concentration at startup used as input into REACTINW in the following step should subtract the value(s) for ~Cb CIPS and ~Cb 8-10 recorded in Steps 4.1 [4]
and 4.1 [5], respectively. The ~Cb CIPS and ,1.C b8-10 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 REACTWor REACTINW ECC program, AND PRINT the output file.
W8N Estimated Critical Position 1-SI-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 5.18).
[7] COMPLETE required entries on the REACTW output data sheets.
[8] RECORD 1000 pcm lower limit:
Bank D at steps.
Bank Cat steps.
[9] ATTACH computer printouts to Data Package.
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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 REACTW.or REACTI NW output.
L1C b REACTW + +
ECC Cb = 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
(
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\. Page 17 of 69 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 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 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: - ___ - -%. D
Input last 10 days 'at power' power history. D
Input Sm effective worth (See TI-55). D C. Core average burnup: ____ MWD/MTU.
D. Boron Concentration (C b): ____ ppm.
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6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
E. Bank D Position: ____ steps.
F. Delta Flux (8<1>>: _ _ _%.
G. Weighted Average Delta Flux (8<1>>: %.
(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. 0
( 2. Equilibrium Xe and 1- use STEADY STATE 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 forXe %
% 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.
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6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
[3] RUN REACTWor 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.
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6.3 REACTW/REACTINW ECP Calculation Using Previous Zero Power Data (continued)
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
(
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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: - - 1 - 1 ----
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 (~>: %.
( 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 L1C bCIPS and L1C b8-10 recorded in Steps 4.1 [4]C and 4.1 [5], respectively. The L1CbCIPS and L1Cb 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
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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 Gb = LiGbNuPOP + LiGbCIPS + LiG bB- 1O EGG Gb = ppm + ppm + ppm (NuPOP) (Step 4.1 [4]G) (Step 4.1 [5])
(
EGG Gb = 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
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6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
B. Lower 1000 pcm limit:
Step 6.4[5] + 1000 pcm = pcm.
Bank Cat steps & Bank D at steps C. Upper 750 pcm limit:
Step 6.4[5] - 750 pcm = pcm.
Bank Cat steps & Bank D at steps D. Lower 750 pcm limit:
Step 6.4[5] + 750 pcm = pcm.
Bank Cat steps & Bank D at steps E. Upper 500 pcm threshold:
(
Step 6.4[5] - 500 pcm = pcm.
Bank Cat steps & Bank D at steps F. Lower 500 pcm threshold:
Step 6.4[5] + 500 pcm = pcm.
Bank Cat steps & Bank D 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]D (Acceptance Criteria 5.18).
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6.4 ECP Hand Calculation Using Previous At-Power Data (continued)
[11] RECORD the following:
A. Date of calculation: _1_1_
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
(
(
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6.5 ECP Hand Calculation Following a Refueling Outage
[1] RECORD the following from NuPOP Table 4-8:
A. All Rods Out (ARO) Critical Cb: ppm.
B. Differential Boron Worth (DBW) at the ARO Critical Cb:
_ _ _ pcm/ppm.
[2] RECORD the desired Control Bank D rod position for initial criticality (i.e. ECP):
ECP = steps
[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
[4] IF performing a dilute-to-critical, THEN
( CALCULATE the critical boron concentration at the ECP as follows:
EGG Gb = + (Inserted Rod Worth DBW)
EGG Gb = ppm + _ _ _ _ _ pcm + __ pcm/ppm (Step 6.5[1]A) (Step 6.5[3]) (Step 6.5[1]B)
EGG Gb = ppm for Bank 0 at steps
[5] IF performing a pull-to-critical, THEN PERFORM the following sub-steps:
A. RECORD the ARO Critical Cb inferred by the Sub-Critical Rod Worth Measurement from PET-107:
Inferred ARO Cb = ppm
(
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6.5 ECP Hand Calculation Following a Refueling Outage (continued)
B. CALCULATE the critical boron concentration at the ECP as follows:
EGG Gb = Inferred ARO Gb + (Inserted Rod Worth DBW)
EGG Gb = ppm + _ _ _ _ _ pcm + __ pcm/ppm (Step 6.5[5]A ) (Step 6.5[3]) (Step 6.5[1]B)
EGG Gb = _ _ _ ppm for Bank 0 at _ _ _ steps
[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 6.4[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 = pcm Bank C at _ _ _ steps & Bank 0 at _ _ _ steps B. DETERMINE the Lower 1000 pcm Limit from NuPOP Table 7-30:
Step 6.5[3] + 1000 pcm = pcm Bank C at _ _ _ steps & Bank 0 at _ _ _ steps
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6.5 ECP Hand Calculation Following a Refueling Outage (continued)
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 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 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 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
[9] RECORD the following:
A. Date of calculation: _1_1_
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.
[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
(
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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 (actual)
Tin: (actual)
Burnup: MWD/MTU (actual)
K eft: (calculated)
Boron: ppm (actual)
D Bank: steps (actual)
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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 (ca Icu lated)
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 llC bCIPS and llCbB-10 recorded in Steps 4.1 [4]C and 4.1 [5] , respectively. The llC bCIPS and llC bB-1o 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 eft" 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.
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6.6 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)
K eft: (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:
+ +
ECC C b = ppm + ppm + ppm (Step 6.6[3]B) (Step 4.1 [4]C) (Step 4.1 [5])
_ _ _ ppm
(
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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:
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:
K eft: (calculated)
D Bank: o steps (defined)
C Bank: steps (COLR)
B Bank: steps (COLR)
A Bank: 228 steps (defined)
(
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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)
(
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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, KeffRef, 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:
K Ref Desired K = eff 1_ K Ref. ( Limit )
eff 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.
(
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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,
( Keftef, 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:
K Ref
CBr 7;1 eff -K DesIred K = Keff +;18
eff CBr 1- K Ref. ( Limit )
eff 100000 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.
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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, Kettef, 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 Kel and the BI
( applicable values from Table 3 according to the following equation:
K Ref
3;1 -K DesIred K = Keff eBI +;14. eff eff eBI 1_ K Ref. ( Limit )
eff 100000 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.
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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: - - - -
(
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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
(
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6.7 ECP Calculation using BEACON ECC NOTE 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.
WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 40 of 69 Data Package: Page _ __ __
_ of _ _ Date _ _ __
6.7 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 "E-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.
(
WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 41 of 69 Data Package: Page __ of __ Date _ __
6.7 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 BEACON 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:
r---------------~
~--------------~
Model Input File:
~--------------~
r---------------~
Summary Results File:
r---------------~
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.
WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 42 of 69 Data Package: Page __ of __ Date _ _ __
6.7 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: f---------j hr Time Step: hr Number of Steps: L - -_ _ _ _ _ _----'
{
[2.9] IF the reactor startup will be performed via a "pull-to-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 "dilute-to-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 ~ 500 pcm,
~ 750 pcm, and ~ 1000 pcm bands.
[2.11] ENTER the appropriate "Acceptance Band Bias" on the "Band Options" tab.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 43 of 69 Data Package: Page _ _ of __ Date _ _ __
6.7 ECP Calculation using BEACON ECC (continued)
[2.12] RECORD what was selected:
Acceptance Band Search: 0 Rods o 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 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: 0 Full Core o Quarter/Eighth Core louse Ala Correction
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 44 of 69 Data Package: Page __ of __ Date _ _ __
6.7 ECP Calculation using BEACON ECC (continued)
[2.17] VERIFY the "Use Depleted B-10" box is not selected on the "Core Conditions" tab.
NOTE 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 ilCb8-10 recorded in Step 4.1 [5]. The ilCb8-10 value will be added back in later.
[2.18] IF "Rods vs, Time" was sele-cted 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 1-51-0-11 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: f-f --
-lj 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 (C b)
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 46 of 69 Data Package: Page _ _ of _ _ Date _ __
6.7, ECP Calculation using BEACON ECC (continued)
[3.2] RECORD the i1Cb8-10 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 i1C b8-10 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).
(
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 47 of 69 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 C at steps & Bank D at steps B. Lower 1000 pcm Limit Bank Cat steps & Bank D at steps C. Upper 750 pcm Limit Bank Cat steps & Bank D at steps D. Lower 750 pcm Limit Bank C at steps & Bank D at steps E. Upper 500 pcm Threshold Bank Cat 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 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 1-51-0-11 Unit 1 Rev. 0014 Page 48 of 69 Data Package: Page _ _ of _ _ Date _ __
6.8 Detector Reliability and/or Base Count Rate Determination NOTE Section 6.8 must be performed prior to initiating ICRR monitoring.
[1 ] RECORD N-131 Count Rate (CR) _ _ _ _ _ cps
[2] MULTIPLY Step 6.8[1] by 10(1/2) _ _ _ _ _
10(1/2)_'--_ cps
[3] MULTIPLY Step 6.8[1] by 10(-1/2) _ _ _ _ _ cps
[4] 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 S.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.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 49 of 69 Data Package: Page _._ of _ _ Date _ _ __
6.8 Detector Reliability and/or Base Count Rate Determination (continued)
CAUTION 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:
Yes No N/A ABOVE the Control Bank Insertion Limits o o (Acceptance Criteria 5.1.A)
BELOW the Negative MTC Withdraw Limit in NOB 0 o o 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.
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 all ICRR monitoring and will be repeated numerous times.
2) When the ScalarlTimer is used, the count period (ilT) may be adjusted at the discretion of the Test Director (minimum of 10 seconds and at least 1000 counts/ilT 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 Pag_e 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 j)
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.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014
( Page 54 of 69 Data Package: Page _ _ of _ _ Date _ __
6.10 Critical Data Evaluation
[1] RECORD the following critical data, AND EVALUATE against the ECp.4 A. Date and time for ECP: - _1_1- I_ -__
I - -- .__-
8. Date and time of criticality: _1_1_ __:__
C. Core average temperature: _ _ _ oF.
D. Control bank position: _ _ _ steps.
E. Cb: ppm.
[2] VERIFY the elapsed time from Step 6.9[1] to Step 6.10[1]8 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).
(
WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014
( Page 55 of 69 Data Package: Page _ _ of _ _ Date _ __
7.0 POST PERFORMANCE ACTIVITY
[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 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 paneI1-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 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 1-51-0-11 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 1-51-0-11 Unit 1 Rev. 0014 Page 57 of 69 Appendix A (Page 1 of 6)
ICRR Monitoring Data Package: Page _ _ of _ _ Date _ _ __
ICRR Monitoring Using Shutdown Monitor 11M Display SOURCE RANGE CHANNEL: N-131, and N-132 ITEM:
Bank ID & ICRR [11M] ICRR [11M]
Time Position Channel Channel Initial UNITS: (Steps) N-131 N-132
(
Reviewed by:
(
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Pa~e 58 of 69 Page Appendix A (Page 2 of 6)
ICRR Monitoring ICRR Monitoring Using Shutdown Monitor 11M Display VS. ROD POSITION SOURCE RANGE CHANNEL: N-131, and N-132 Sank Sank Position ICRR [11M] ICRR [11M]
10 (Steps) Channel N-131 Channel N-132 Initial
";> " u; CSA 50 CSA 100 CSAlS 150/34 CSAlS 200/84 CSS/C 134/18 CSS/C 184/68 CSC/D 118/2 CSCID 168/52
( CSCID CSO CSO CSO CSO CSO CSO Reviewed By:
(
WBN Estimated Critical Position 1-81-0-11 Unit 1 Rev. 0014 Page 59 of 69 Appendix A (Page 3 of 6)
ICRR Monitoring Data Package: Page _ _ of _ _ Date _ _ __
ICRR MONITORING USING COUNT RATE METER SOURCE RANGE CHANNEL: N-131 0, or N-132 0 Bank Count Rate Base Count Rate Bank Position (C i) (Co) ICRR [Co/Ci] Initial 10 (Steps) [CountslL1T] (cps)
Initial Co CBA 50 CBA 100 CBAlB 150/34 CBAlB 200/84 CBB/C 134/18
( CBB/C 184/68 CBC/O 118/2 CBC/D 168/52 CBC/D CBO CBO CBO CBO CBO CBO Reviewed By:

~-----

~------

WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 60 of 69 Appendix A (Page 4 of 6)
ICRR Monitoring Data Package: Page _ _ of _ _ _ _ __
Date ____
ICRR MONITORING USING SCALAR TIMER SOURCE RANGE CHANNEL: N-131 0, or N-132 0 Count Count Rate Bank Base Bank Period (C i) ICRR Position Counts Count Rate (Co) 10 [L'lT] [CountslL'lT] [CO/C i] Initial (Steps) (cps)
(sec) (cps)
Initial L'lT and Co
,:: ;i CBA 50 CBA 100 CBAlB 150/34 CBAlB 200/84 CBB/C 134/18
(
CBB/C 184/68 CBCID 118/2 CBCID 168/52 CBC/O CBO CBO CBO CBO CBO Reviewed By:
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 61 of 69 Appendix A (Page 5 of 6)
ICRR Monitoring 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;) ICRR RATE (Co)
UNITS: [COUNTS/(LlT)l [Co/C;l INITIAL (CPS)
(CPS)
INITIAL LlT AND Co
(
Reviewed By:
(
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014
( Page 62 of 69 Appendix A (Page 6 of 6)
ICRR Monitoring 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: PERIOD ICRR COUNTS INITIAL UNITS: (~T) [COUNTS/(~T)] RATE (Co) [CO/C i ]
(SEC) (CPS) (CPS)
INITIAL ~T AND Co . . /
/.
(
Reviewed By:
(
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014
(
Page 63 of 69 Appendix B (Page 1 of 3)
Predicted ICRRs Data Package: Page _ _ of _ _ Date _ _ __
Table 1 ROD POSITIONS AT CRITICALITY (ROD SEARCH)
(Step 6.6[8]A) (Step 6.6[8]8) (Step 6.6[8]C)
Condition Kel ef Limit Desired K C 8ank o 8ank (pcm) (steps) (steps)
Rod Insertion Limit (Step 6.6[6]8) 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]8) 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 Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014
(
Page 64 of 69 Appendix B (Page 2 of 3)
Predicted ICRRs Table 2 ROD POSITIONS AT 8-Fold (ROD SEARCH)
(Step 6.6[9]A) (Step 6.6[9]B) (Step 6.6[9]C)
Condition Kett ef Limit Desired K C Bank D Bank (pcm) (steps) (steps)
Rod Insertion Limit (Step 6.6[6]B) 0 Lower 1000 pcm Limit (Step 6.6[1]D) -1000 Lower 750 pcm Limit (Step 6.6[1]D) -750 Lower 500 pcm Threshold (Step 6.6[1]D) -500 Estimated Critical (Step 6.6[1]D) 0 Condition
( All Rods Out (Step 6.6[7]B) 0 Upper 500 pcm Threshold (Step 6.6[1]D) 500 Upper 750 pcm Limit (Step 6.6[1]D) 750 Upper 1000 pcm Limit (Step 6.6[1]D) 1000 Performed By:
Reviewed By:
I
\.
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 65 of 69 Appendix B (Page 3 of 3)
Predicted ICRRs Table 3 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)
Condition K"lef Limit Desired K C Bank D Bank (pcm) (steps) (steps)
Rod Insertion Limit (Step 6.6[6]B) 0 Lower 1000 pcm Limit (Step 6.6[1]D) -1000 Lower 750 pcm Limit (Step 6.6[1]D) -750 Lower 500 pcm Threshold (Step 6.6[1 ]D) -500 Estimated Critical (Step 6.6[1]D) 0 Condition All Rods Out (Step 6.6[7]B) 0 Upper 500 pcm Threshold (Step 6.6[1 ]D) 500 Upper 750 pcm Limit (Step 6.6[1]D) 750 Upper 1000 pcm Limit (Step 6.6[1]D) 1000 Performed By:
Reviewed By:
(
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 66 of 69 Appendix C (Page 1 of 1)
BEACON ECC Data Package: Page _ _ of _ _ Date _ __
Time Since D Bank Cb ~CbB-10 ECCC b Calendar Date Input Model Position and Time (ppm) (ppm) (ppm)
(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 Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014
( Page 67 of 69 Figure 1 (Page 1 of 1)
ICCR VS Control Bank Position 2 52 102 152 202 CBD 68 118 168 218 CBC 34 84 134 184 CBB 0 50 100 150 200 CBl!.
1.1 1
0_9 0_8
( 0_7 0_6 gj u
1-1 0_5 0_4 0_3 0_2 0_1 0
0 50 100 150 200 250 300 350 400 450 500 550 600 Total Rod. Steps CONTROL BANK POSITION, Steps (Assuming Bank Overlap)
\ Performed By: Reviewed By:
WBN Estimated Critical Position 1-SI-0-11 Unit 1 Rev. 0014 Page 68 of 69 Figure 2 (Page 1 of 1)
CIPS Adjustment 1000?-~------~--------~--------~--~~~~------~~--~~-,
900 800 700 600
~121
~
( .j.l
.pol 500
.pol
.j.l I:)
tI$
Q) 400 t:'ti MO 200 100 o~--------+---------+---------+---------+---------~------~
O~--------+---------+---------+---------+---------~------~
o 10000 20000 30000 40000 50000 60000 Absolute Value [ I DAO d BU] (%
MWD/MTU)
WBN Estimated Critical Position 1-51-0-11 Unit 1 Rev. 0014 Page 69 of 69 Source Notes (Page 1 of 1)
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 SOER 88-002 Recommendation 6 3 withdrawal to allow neutron level stabilization and the use of the Audio Count Rate Speaker.
Premature Criticality Events During SOER 88-002 Rec. 7 4 Reactor Startup.
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam A.2-1 RO Perform 1~SI-0-2A-O~, "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 EVALUATION SHEET Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three."
Alternate Path: N/A Facility JPM #: 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 xX Classroom Perform xX Simulate
References:
1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Rev.
30.
Task Number: RO-113-GEN-004
Title:
Perform surveillance tests.
Task Standard: 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.
Validation Time: minutes Time Critical: Yes --
No X
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: - - -
Performance Rating: SAT UNSAT Performance Time Examiner: _ _ _ _ _ _ _ _ _ _ __

- - - - - -_____~/__

~/ __--

NAME SIGNATURE DATE
===============================================================
COMMENTS PAGE20F17
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 ~ OF 17
-" WATTS BAR-1UCLEAR PLANT A.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:
I>,~< ~~~Y.c
~~~y'c ".
. >>\\';~";'"
>>\';~',;,
~\'. <1w~\~
'!"'~\; <1w~'\~ !,~.
!,~~
Type Eyent Inserted .R~mp Initial F:i l1l1al
.' ',i'" Delay' al ,.**.
Value,
.'., Type I>,? ..",'
pi-1-,2a 05150 s9 #1 stm hdr eh 1 0 00:00:00 00:00:00 00:00:00 1055 1074.1 pi-1-2b 05150 s9 #1 stm hdr eh 2 0 00:00:00 00:00:00 00:00:00 1055 1074.1 pi-1-5 05150 s9 #1 main stm hdr 0 00:00:00 00:00:00 00:00:00 1100 1074.1 1i-3-55 05050 s9 #2 level ind 0 00:00:00 00:00:00 00:00:00 30 37.8133 1i-68-335a 05350 res przr Ivl(m-4) 0 00:00:00 00:00:00 00:00:00 32 27.1232 1i-63-52 09030 sis rwst level ind 0 00:00:00 00:00:00 00:00:00 90 98.1359
6. Place simulator in RUN and acknowledge any alarms.
7. Place simulator in FREEZE until Examiner cue is given.
PAGE 4 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __
EXAMINERS CUE: Provide a marked-up copy of 1-SI-0-2A-03 to applicant. The !ollowing 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 SAT 3 data collection and determine if Acceptance Criteria are
( met. UNSAT Perform Data 1-M-2 1-U-2-230A 0
0

200,000 Sheet 3 of 3 Pnl 0-L-20S CST A Level OR gallons 1-SI-0-2-00 T15M/708 1-U-2-230B 0 gallons "CST Level" STANDARD:
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
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT STEP 2. PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference CRITICAL 4 data collection and determine if Acceptance Criteria are STEP met.
SAT 1-PI-1-2A psig SG 1 Press 1-PI-1-28 psig UNSAT 1-PI-1-5 psig 1-PI-1-9A psig SG 2 Press 1-PI-1-98 Operable, psig ContactSRO 1-PI-1-12 Channel psig to 4 1-M-4 Check,and 1-PI-1-20A psig consult Tech MCOs90 Specs.
SG 3 Press 1-PI-1-20B psig psig
\-------1 1-PI-1-23 psig 1-PI-1-27A psig SG 4 Press 1-PI-1-27B psig f-------\
1-PI-1-30 psig STANDARD:
( Applicant obtains current readings for SG Pressure and records them on 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 60F 17
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference CRITICAL 5 data collection and determine if Acceptance Criteria are STEP met.
SAT 1-U-3-42 %
SG 1 Level 1-U-3-39 f-------I
% UNSAT 1-U-3-38 %
1-U-3-55 %
Operable at SG 2 Level 1-U-3-52 :2:32% NR [for %
Contact SRO 1-U-3-51 OPERABLE % to 5 1-M-4 loops],
1-U-3-97 % consult Tech Channel Specs.
SG 3 Level 1-U-3-94 Check, and %
f-------I MCD s:: 6.0%
l-U-3-93 %
1-Ll-3-110 %
SG 4 Level 1-Ll-3-107 %
1-Ll-3-106 %
STANDARD:
Applicant obtains current readings for SG Level and records them on the
( data sheet, and determines that SG 3 Level channel 1-L/-3-55 is NOT within MCD is within:::;; 6.0%.
EXAMINER'S CUE:
If asked about 1-U-3-55 indication, acknowiedge 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
WATTS BAR NUCLEAR PLANT A.2-1 RO
( Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 8 data collection and determine if Acceptance Criteria are SAT met.
UNSAT Operable, Channel Check, and MCD SR Neutron value is plus or minus 1-NI-92-131A 1/2 decade Contact Mon CH I
[O.3CR1<CR2 SRO to 8 1-M-4 <3.0CR1]. CPS(2) consult f--------
--. j Tech Spec Reading should be the s.
SR Neutron average value l-NI-92-132A Mon CH" observed over a 30 second period' STANDARD:
Applicant determines that the Source Range Monitors are Operable and within the MCD tolerance.
COMMENTS:
(
(
PAGE 8 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference CRITICAL 9 data collection and determine if Acceptance Criteria are STEP met.
SAT 1-Ll-68-339A % Contact Operable, less than or f -
--1 i SRO 9 1-M-4 PZR Level 1-Ll-68-335A equal t080%, % to consult UNSAT Channel Check, and 1-U-68-320 MCD :;; 6.0% Tech Spec
% s.
STANDARD:
Applicant obtains current readings for PZR Level and records them on the data sheet, determines that PZR level channel 1-LJ-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
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference SAT 10 data collection and determine if Acceptance Criteria are met. UNSAT 1-PI-68-340A psig Operable Contact 1-PI-68-334 channel check, psig SRO 10 1-M-5 PZR Press greater than or equal to consult 1-PI-68-323 to 2214psig and psig Tech Spec MCO:s 55 psig. s 1-P 1-68-322 psig STANDARD:
Applicant enters data and determines that all PZR Pressure channels meet acceptance criteria.
COMMENTS:
(
(
PAGE 10 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 RO
( Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT STEP 7: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference SAT 15 data collection and determine if Acceptance Criteria are met. UNSAT RCP 1 234 RCS Loops RCP Status ON 0 0 0 0 1,2,3,4 OFFO 0 DO 1-HS-68-8AA Two loops operable; (1) Contact RCP 1 1-HS-68-8BA two loops in operation SROto 15 1-M-5 1-HS-68-31AA if capable of rod consult RCP2 (1) 1-HS-68-31 SA vvithdrawal (one loop if Tech Spec NOT) s.
1-HS-68-50AA (1)
RCP3 1-HS-68-50SA 1-HS-68-73AA (1)
RCP4 1-HS-68-738A STANDARD:
Applicant enters data for the Reps and determines that acceptance criteria are met.
COMMENTS:
PAGE 11 OF 17
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 SAT 16 data collection and determine if Acceptance Criteria are met. UNSAT Ref Location Description Instrument # T S Limit Data Acc NOT Met RWSTto RHR 1-FCV-63-1 OPEN 0 EGCS Suction (1-HS-63-1A) CLOSED 0 16 1-M-6 OPEN SI Pumps to CL 1, 1-FCV-63-22 OPEN 0 2,3,4 (1-HS-63-22A) CLOSED 0 Shunt BKR 1A1-A OFF 0 cl2E1 1-BKR-63-1A ON 0 Contact SRO to At least one OR consult Breaker breaker OFF OFF 0 1-BKR-63-1 B Tech Specs.
480V Rx 1A1-Ac110A ON 0 MOV Boards Shunt BKR 1B1-B OFF 0 c!2F2 1-BKR-63-22A ON 0 At least one OR Breaker breaker OFF OFF 0 1-BKR-63-22B 1B1-B c!11D ON 0 STANDARD:
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:
f PAGE 12 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference CRITICAL 17 data collection and determine if Acceptance Criteria STEP are met.
SAT
% UNSAT
% Contact SRO to f-------
f---
-t--

j-

-t---------
---jj--- --
-Ii consult Tech f - -_ _'X-j0 Specs f----------%-j Specs STANDARD:
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-Ll-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
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT 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 0 CL Accum 1 Outlet (1-HS-63-118A) CLOSED 0 1-FCV-63-98 Valves OPEN 0 CL Accum 2 Outlet Contact SRO to (1-HS-63-98A) Open-when Pzr CLOSED 0 18 1-M-6 consult 1-FCV-63-80 pressure OPEN 0 CL Accum 3 Outlet Tech Specs.
(1-HS-63-80A) >1000 psig. CLOSED 0 1-FCV-63-67 OPEN 0 CL Accum 4 Outlet (1-HS-63-67A) CLOSED 0 STANDARD:
Applicant enters data and determines that all valves are in their required positions and meet acceptance criteria.
COMMENTS:
(
PAGE 14 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 RO Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT STEP 11: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 4, Reference SAT 19 data collection and determine if Acceptance Criteria are met. UNSAT Ref Location Description Instrument # T S Limit Data Acc NOT Met CLAccum 1 1-U-63-129 gal Lvi 1-U-63-1 '19 gal Check operability CLAccum 2 l-U '109 gal by acceptable Lvi l-LHn-99 gal deviation berNeen redundant level and CLAcclIm3 'i-U-53-S9 gal pressure channels Lvi when pressurizer
'I-U-63-S1 gal pressure is above
'I-U-53-S2 gal '1000 psig If CLAccum4 deviation limit is Lv! i-U-63-60 gal
'19 '1-lvl-6 exceeded, l-P!-63-128 psig determine the CLAccum 1 channel inoper-able Press 1-PI-63-126 psig AND record only 1-PI-63-'J08 psig the operable CLAccum2 channeL This Press 1-PI-63-106 ;c6'1O and s;660 psig psrg channel check is and MCD S;30 NOT a technical CLAccum 3 1-PI-63-S8 psig n pSig specification Press 'j-PI-63-86 psig re-quirement CLAccum4 1-PI-63-62 psig
( Press i-Pi-63-6'! psig STANDARD:
Applicant enters data and determines that all Cold Leg accumulator level and pressure channels meet acceptance criteria.
COMMENTS:
(
\
PAGE 15 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 RO
(
Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 4, Reference SAT 20 data collection and determine if Acceptance Criteria are met. UNSAT l-PDI-30-42 0 Operable, Ctmnnel or Point P1000A 0 psig (2)
Check, and MCD of l-PDI-30-43 0 the following:
'I-M-6 or or Point Pl001A 0 MCD $ '1.0 psig (Ind) t--_-'-ps--"i 9_'2-j) Contact SRO to f--_--'--ps---=ig=--'2-i) 20 CNTMT Press ICS 1-PDI-30-44 0 consult Tech Specs MCD $ 0,8 psig or Point P1002A 0 (mixed) psig (2) 1-PDI-30-45 0 rvlCD $ 05 psig or Point P1003A 0 (computer) psig (2)
STANDARD:
Applicant enters data and determines that all channels meet acceptance criteria.
COMMENTS:
(
STOP TIME _ __
PAGE 16 OF 17
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.
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.
Added 1-FI-90-400 for Shield Building Flow 32 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 oTe, +,
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 TACF 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 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.
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. RCW and 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 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 Ref Freq MODES SR p3.3.1.1-5 2(1),3(2).(3) 2,3,4,5,6 B S 4 (2),(3), 5(2),(3)
SR p3.3.2.1-1.c 1,2,3 1,2,3 20 S SR p3.3.2.1-1.d 1,2,3(4) 1,2,3 10 S SR p3.3.2.1-1.e 1,2,3(4) 1,2,3 4 S
( SR p3.3.2.1-2.c 1,2,3 1,2,3 20 S SR p3.3.2.1-3.b.(3) 1,2,3 1,2,3 20 S SR p3.3.2.1-4.c 1,2(5),3(5) 1,2,3 20 S SR p3.3.2.1-4.d.(1) 1, 2(5), 3(4),(5) 1,2,3 4 S 3(5),(6) 4 SR p3.3.2.1-4.d.(2) 3 S SR p3.3.2.1-5.b 1,2(7), 3(7) 1,2,3 5 S SR p3.3.2.1-6.b 1,2,3 1,2,3 5 S SR p3.3.2.1-7.b 1,2,3,4 1,2,3,4 17 S SR p3.3.2.1-B.b.(1) 1,2,3 1,2,3 10 S SR p3.3.2.1-B.b.(2) 1,2,3 1,2,3 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.
(1) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(2) With RTBs closed and Rod Control System capable of rod withdrawal.
(3) With RTBs open. In this condition, source range function does NOT provide reactor trip but does provide indication.
(4) Above P-11 (Pressurizer Pressure) interlock.
(5) Except when all MSIVs are closed & deactivated.
(6) 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.
(7) Except when all MFIVs, MFRVs, and their bypass valves are closed and deactivated or isolated by a closed manual valve.
(8) 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,fo 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,fo 3 3 5 S SR p3.5.1.1 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,fo 1,2,3,4 1,2,3,4 21 S SR p3.6.11.1,fo 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,fo 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.
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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 Freq REQUIREMENTS MODES T8R p3.1.2.1 1,2,3 1,2,3 65 8 T8R p3.6.1.1. 1,2,3,4 1,2,3,4 24 8 T8R p3.6.2.1 1,2,3,4 1,2,3,4 23 8 T8R p3.6.2.3 1,2,3,4 1,2,3,4 23 8 T8R p3.7.5.1 All All 65 8 TR p3.6.1 Action B.1.1 1,2,3,4 1,2,3,4 24 1&8 TR p3.6.1 Action 8.1.2 1,2,3,4 1,2,3,4 24 1 TR p3.6.1 Action 8.1.3 1,2,3,4 1,2,3,4 24 1&8 TR p3.6.1 Action C.1.1 1,2,3,4 1,2,3,4 24 1&8 TR p3.6.1 Action C.1.2 1,2,3,4 1,2,3,4 24 1 TR p3.6.2 Action A.1 1,2,3,4 1,2,3,4 24 4
( The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSO) is used instead of the Tech Spec value.
D. Performance of this Instruction satisfies the following Offsite Dose Calculation Manual Surveillance Requirements (OSRs):
ODCM SURVEILLANCE APPLICABLE MODES PERFORMANCE MODES Ref Freq REQUIREMENTS 08R p2.1.2-3J AII(2O) AII(2O) 59 0 08R p2.1.2-4.e All All 59 0 (20) Both Unit 1 and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement.
E. Fulfillment of special conditions will initiate the following requirements:
SURVEILLANCE REQUIREMENTS APPLICABLE MODES PERFORMANCE MODES Ref Freq TR p3.6.1 Action A.1 1,2,3,4 1,2,3,4 24 8
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WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Pag_e 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.
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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.
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WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 11 of 39 2~ 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.
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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.
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WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page PaQe 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. (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-5.
E. 1-45W-605-242, Electrical Tech Spec Compliance Tables.
F. 1-45W-605-243, Electrical Tech Spec Compliance Tables.
G. SQPER930138, Generic Applicability to Watts Bar Steam Generator PressurefTemperature Limitations SON LeO 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.
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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_ __ of _ __
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.
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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.
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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 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.
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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 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.
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WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 20 of 39 Date-__ of _ __
-_- Page _ __ of ---
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.
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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
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WBN 1900 - 0700 1-SI-0-2A-03
/ Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Pa_ge 22 of 39 Data Sheet 1 (Page 1 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page_ _ __ of _ _ __
I Ref I Location ! Description ! Instrument # T S Limit Data Acc NOT Met 1-M-2 Perform Data 1-U-2-230A D
~ 200,000 Sheet 3 of 3 PnI0-L-209 CST A Level OR gallons 1-SI-0-2-00 T15M/708 1-U-2-230B D
. gallons "CST Level" 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 Contact SRO 1-PI-1-12 Channel psig to 4 1-M-4 Check,and 1-PI-1-20A psig consult Tech MCD:::; 90 Specs.
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-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 %
Contact SRO 1-U-3-51 OPERABLE % to 5 1-M-4 loops],
1-U-3-97 % consult Tech Channel Specs.
SG 3 Level 1-U-3-94 Check, and %
MCD :::;6.0%
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 Peliormer's SRO's "Acc not Met" column initiated. Initials Initials
( 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 _ _ __ of - - - -
Ref Acc NOT Location Description Instrument # T S Limit Data Met Operable, Channel Check, and MCO SR Neutron value is plus or minus 1-NI-92-131A Contact Mon CH I 1/2 decade
[0.3CR1 <CR2 SRO to S 1-M-4 <3.0CR1]. 1.. CPS(2) consult Tech Spec Reading should be the s.
SR Neutron average value 1-N 1-92-132A Mon CHI/ observed over a 30 second period A. CPS(2) 1-L/-6S-339A % Contact Operable, less than or SRO 1-L/-6S-335A equal toSO%,
9 1-M-4 PZR Level % to consult Channel Check, and Tech Spec 1-L/-6S-320 MCO::; 6.0%
% s.
( 1-PI~6S-340A psig Operable Contact 1-PI-6S-334 channel check, psig SRO 10 1-M-5 PZR Press greater than or equal to consult 1-PI-6S-323 to 2214psig and psig Tech Spec MCO::; 55 psig. s 1-PI-6S-322 psig RCP1 2 3 4 RCS Loops RCP Status ON 0 0 0 0 1,2,3,4 OFF 0 0 0 0 1-HS-6S-SAA Two loops operable; (1) Contact RCP 1 1-HS-6S-SSA two loops in operation SROto 15 1-M-5 1-HS-6S-31AA if capable of rod consult (1)
RCP2 withdrawal (one loop if Tech Spec 1-H S-6S-31 SA NOT) s.
1-HS-6S-50AA (1)
RCP 3 1-HS-6S-50SA 1-HS-6S-73AA (1)
RCP4 1-HS-6S-73SA (1) Loop status is to be written in data space {Operable (OJ, 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 Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 24 of 39 Data Sheet 1 (Page 3 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page_ _ __ of Ref Location Description Instrument # T S Limit Data Acc NOT Met RWSTto RHR 1-FCV-63-1 OPEN ~
ECCS Suction (1-HS-63-1A) CLOSED 0 16 1-M-6 OPEN SI Pumps to CL 1, 1-FCV-63-22 OPEN lit lit' 2,3,4 (1-HS-63-22A) CLOSED 0 Shunt BKR 1A1-A OFF [M'"
c/2E1 1-BKR-63-1A ON 0 Contact SRO to At least one OR consult Breaker 1-BKR-63-1 B breaker OFF OFF ~ Tech Specs.
480V Rx 1A1-A c/10A ON 0 MOV Boards Shunt BKR 1B1-B OFF ~
c/2F2 1-BKR-63-22A ON 0 At least one OR Breaker breaker OFF OFF ijY' 1-BKR-63-22B 1B1-B c/11D ON 0 1-Ll-63-180 %
Operable, CNTMT 1-Ll-63-181 Channel check, %
( Sump Level 1-Ll-63-182 and %
MCD ::::6.0% Contact SRO to 1-Ll-63-183 %
17 1-M-6 consult Tech 1-Ll-63-50 % Specs Operable, 1-Ll-63-51 Channel check, %
RWST Level 1-Ll-63-52 and MCD %
7.0%
1-Ll-63-53 %
1-FCV-63-118 OPEN 0 CL Accum 1 Outlet (1-HS-63-118A) CLOSED 0 1-FCV-63-98 Valves OPEN 0 CL Accum 2 Outlet Contact SRO to (1-HS-63-98A) Open-when Pzr CLOSED 0 18 1-M-6 consult 1-FCV-63-80 pressure OPEN 0 CL Accum 3 Outlet Tech Specs.
(1-HS-63-80A) >1000 psig. CLOSED 0 1-FCV-63-67 OPEN 0 CL Accum 4 Outlet (1-HS-63-67A) CLOSED 0 Initials INDICATE acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials
( Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 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 Date _ _ __ Page_ _ __ of -_ _ __
Ref Location Description Instrument # T S Limit Data Acc NOT Met CLAccum 1 1-U-63-129 gal Lvi 1-U-63-119 ~ 7630 and ::;8000 gal gal and MCD ::; 96 Check operability CLAccum 2 1-U-63-109 gal by acceptable gal. Chemistry is to Lvi 1-U-63-99 be notified to gal deviation between perform 1-SI-63-6 redundant level and CLAccum 3 1-U-63-89 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if tank gal pressure channels Lvi level is increased ~ when pressurizer 1-U-63-81 gal 75 gal and tank NOT pressure is above CLAccum 4 1-U-63-82 filled from RWST.(l) gal 1000 psig. If deviation limit is Lvi 1-U-63-60 gal 19 1-M-6 exceeded, 1-PI-63-128 psig determine the CLAccum 1 channel inoper-able Press 1-PI-63-126 psig AND record only the operable
( CLAccum 2 1-PI-63-108 psig channel. This Press ~61 0 and ::;660 psig 1-PI-63-106 psig channel check is and MCD::; 30 1-PI-63-88 psig (1) psig NOT a technical CLAccum 3 specification Press 1-PI-63-86 psig re-quirement.
CLAccum 4 1-PI-63-62 psig Press 1-PI-63-61 psig 1-PDI-30-42 ~ Operable, Channel or Point P1 OOOA 0 0 psig (2)
Check, and MCD of 1-PDI-30-43 5t" the following:
or Point P1 001A 0 (!) psig (2) 1-M-6 or MCD::; 1.0 psig (Ind) Contact SRO to 20 CNTMT Press ICS 1-PDI-30-44 I!f' MCD ::; 0.8 psig consult Tech Specs or Point P1002A 0 (mixed) C) psig (2) 1-PDI-30-45 uY' MCD ::; 0.5 psig 0
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 acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials
( Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 26 of 39 Data Sheet 1 (Page 5 of 15)
Mode 3 Surveillance Log: 1900-0700 Date Page of Ref Location Description Instrument # T S Limit Data Acc NOT Met CNTMT-ANN 1-PDI-30-133 0 L1P between -0.07
.21 1-M-9 or L1P and 0.27 psid psid(2) 1-PDI-30-30C 0 More negative than or 1-PDI-30-126 " H20(4) equal value on 1-M-9 Annulus L1P Attachment 1 " H20(1) 1-PDI-30-127 and MCD:5 0.7 "H 2O " H20(4) Contact SRO to consult point Y2203A 0 Tech Specs.
22 or ICS Shield N/A-used for 1-M-9 Building Flow 1-FI-90-400 0 Attachment 1 or Data Sheet 3y(3) 0 SCFM Tech Spec Acceptance value from Attachment 1 " H20(4)
( (1) 1-PDI-30-126 and 1-PDI-30-127 have a range of 0 -10" H 20 and indicate negative pressure relative to atmosphere (e.g. an indication of 6" H2 0 is more negative than negative 5.5" H2 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) NfA 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 Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 27 of 39 Data Sheet 1 (Page 6 of 15)
Mode 3 Surveillance Log: 1900-0700 Ret Location Description Instrument # TS Limit Data Acc NOT Met 23 1-M-10 Ice Cndnsr Door 1-XI-61-187 Operable, all doors (--1) Contact SRO to consult Status Position closed, and Channel Tech Specs and perform Monitoring Check data sheet 23.
System 24 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 (1) group operable. 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 acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 28 of 39 Data Sheet 1 (Page 7 of 15)
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 EL 776 EL 756 Group 7(1)(2) 144 3 Group 4(1)(2) 145 18 Group 1(1)(2) 146 32 147 4 148 19 149 33 150 5 151 20 152 34 1 1 1 Two Highest Temps Two Highest Temps Two Highest Temps 2 2 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 EL 776 EL 756 Group 8(1)(2) 159 8 Group 5(1)(2) 160 23 Group 2(1)(2) 161 36 165 9 166 24 167 37 183 10 184 25 185 38
( Two Highest Temps 1
Two Highest Temps 1
Two Highest Temps 1
2 2 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 EL 776 EL 756 Group 9(1)(2) 174 13 Group 6(1)(2) 175 28 Group 3(1)(2) 176 41 177 14 178 29 179 42 180 15 181 30 N/A N/A N/A 1 1 1 Two Highest Temps Two Highest Temps Two Highest Temps 2 2 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 TOTAL OF MEAN ICE BED OPTIMUM MEAN ICE PERFORMER TOTALS+ 18 TEMP (3) REVIEWER INITIALS SUMS 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 Performer's SRO's "Acc not Met" column initiated. Initials Initials
( Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 29 of 39 Data Sheet 1 (Page 8 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page_ _ _ ___ of - - - -
Ref Location Description Instrument # T 5 Limit Data Acc NOT Met 1-RM-90-106A 0 or If monitor aligned to point R1012A 0 cpm Lower Containment is 1-RM-90-1068 0 inoperable, the other or monitor is to be re-point R1013A 0 Operable and cpm aligned using Lower and 1-RM-90-112A 0 Channel Check SOI-90.02. If both 0-M-12 or Upper CNTMT 25 or monitors are inoper-ICS Gas and point R1015A 0 cpm able, SRO is to be Particulate notified, 1-SI-68-32 1-RM-90-1128 0 is to be performed, or and Chemistry Count-point R1016A 0 cpm room is to be notified 1-RR-90-106 (-,j) to perform 1-SI-90-25.
Operable 1-RR-90-112 (,j)
( 0-RM-90-102 or 0
0-M-12 or Spend Fuel Pit point R9011A 0 Operable and mr/hr Contact SRO to consult 26 ICS Area 0-RM-90-103 0 Channel Check Tech Specs or point R9012A 0 mr/hr 0-RM-90-125 0 or point R1025A 0 cpm 0-RM-90-126 0 Contact SRO to consult 0-M-12or Operable and 27 MeR Intake or Tech Specs. See ICS Channel Check point R1026A 0 cpm Section 6.1 K.
0-RR-90-125 (,j) 0-RR-90-126 (\)
Initials indicate ace met OR action in Performer's SRO's "Ace not Met" column initiated. Initials Initials Remarks:
(
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 30 of 39 Data Sheet 1 (Page 9 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page _ _ __ of of -_ _ __
Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-RM-90-123 0 Operable and O-M-12 or CCS HxA Out Contact SRO. See 28 or Channel Check ICS Liquid Section 6.1 K.
point R1023A 0 (Info Only-T.S. N/A) cpm 1-RM-90-130A 0 Contact SRO to consult or Tech Specs. See CNTMT AUX BLDG point R1027A 0 cpm Section 6.1 K. IF both Purge Air Exh Operable and 29 A2U1713 or monitors inoperable, Radiation Channel Check ICS 1-RM-90-131A 0 suspend purge flow Monitor or immediately per ODCM point R1028A 0 table 1.1.2-6.a cpm
(
Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials 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_ _ __ of _ _ __
Ref Location Description Instrument # T S Limit Data Acc NOT Met Unit 1 Shield Bldg Exhaust AEB 729 1-SMPL-90-801 Operable Tritium Flow Rate Monitor (-I) If Tritium flow rate measuring device Unit 2 Shield is inoperable, SRO Bldg Exhaust AEB 729 2-SMPL-90-801 Operable and Chemistry are 59 Tritium Flow to be notified.
Rate Monitor (-I) Initiate WO and Aux Bldg and record number in Fuel Handling remarks section.
AUX BLDG Exhaust Tritium O-SMPL-90-800 Operable 786 Flow Rate Monitor (-I)
Completed or in progress for the required
( 67 N/A 1-SI-O-10(1) N/A Tech Specs per performance N/A 1-SI-O-10 frequency interval 0 (-I)
(1)
Conditional performance cannot be substituted for periodic performance.
Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 32 of 39 Data Sheet 1 (Page 11 of 15)
Mode 3 Surveillance Log: 1900-0700 Date Date-_ _ __ Page_ _ __ of _ _ __
of Ref Location LI Description DescriQtion Instrument T S Limit Data Acc NOT Met Control Building Buildi'!9 NORMAL LIMITS Control Room South Wall 0-TI-30-5219 ::; 80°F of Readings on this el755 page may be taken in Control Room across from any order.
0-TI-30-5220 ::; 80°F OF 1-M-9 el755 Next to 480V SO BO In all sections of Ref 0-TI-30-5201 ::; 104°F OF Transformer 1A2-A el 772 65, use of Fluke 52 Next to 480V SO BO digital thermometer or 0-TI-30-5202 ::; 104°F OF Transformer 1B 1-B el 772 equivalent is Next to 480V Rx MOV acceptable for 0-TI-30-5203 ::; 83°F OF Bd 1A2-A el 772 temperature Behind 125V Vital Batt indicators not present 0-TI-30-5204 ::; 83°F OF or inoperable.
Charger 6-S el 772 Next to 480V Rx MOV 0-TI-30-5205 ::; 83°F OF Bd 2A2-A el 772 Next to 480V SO BO
( 65 Transformer 2A2-A el 772 0-TI-30-5206 ::; 104°F OF Next to 480V SO BO 0-TI-30-5207 ::; 104°F OF Transformer 2B2-B el 772 Contact SRO to Next to 480V Rx MOV consult Technical 0-TI-30-5208 ::; 83°F OF Bd 2B2-B el 772 Requirements section 3.7.5.1. SRO should U1 Mech Equip Rm el772 0-TI-30-5209 ::; 91°F OF evaluate normal AND SO BO Rm U1 behind stairs abnormal limits.
0-TI-30-521 0 ::; 85°F OF S-A3 el757 Perform Data Sheets SO BO Rm U2 behind stairs 65 of 1-SI-0-2-00 0-TI-30-5211 ::; 85°F OF S-A13 el 757 "Out of Limit Hourly Refuel Floor U 1 beside Aux Temperature" .
0-TI-30-5212 ::; 104°F OF Boration Makeup Tank el757 Computer room at center of 0-TI-30-5226 ::; 74°F OF the room el 708 Aux Instrument Room el 708 0-TI-30-5233 ::; 90°F OF Initials indicate ace met OR action in Performer's SRO's "Ace not Met" column initiated. Initials Initials
\ Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 33 of 39 Data Sheet 1 (Page 12 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page_ _ __ of - - - -
Ref Location I Description Instrument # T S Limit Data Acc NOT Met Auxiliary Building Normal Limits U1 outside supply fan room Readings on this 0-TI-30-5213 ~ 104°F OF el737 page may be taken South steam vault room U1 in any order.
0-TI-30-5228 ;::: 50°F of el730 In all sections of Ref North steam vault room U1 65, use of Fluke 52 0-TI-30-5227 ;::: 50°F of el730 digital thermometer Between UHI Accumulators or equivalent is 0-TI-30-5218 ~ 92°F of acceptable for el729 temperature U1 across from AFW pumps indicators not 0-TI-30-5214 ~ 104°F present or el713 of inoperable.
U1 outside AFW pump room Contact SRO to
( doorel692 0-TI-30-5215 ~ 104°F of consult Technical Requirements U2 near Boric Acid section 3.7.5.1. SRO 65 con-centrate filter vault 0-TI-30-5216 ~ 104°F should evaluate el692 OF normal AND abnormal limits.
Perform Data Sheets 65 of 1-SI Next to 0-L-629 el 676 0-TI-30-5217 ~ 104°F 2-00 "Out of Limit Hourly OF Temperature".
U1 Blender Station South Contact SRO to 1-TI-62-240 ;::: 63°F consult Technical Wall el713 of Requirements section 3.1.1.1 &Ior 3.1.2.1 Perform Behind BAT A el713 1-TI-62-239 ;::: 63°F Data of Sheet 65 of 1-SI 2-00 "Out of Limit Behind BAT B el 713 2-TI-62-239 ;::: 63°F Hourly OF Temperature".
Initials indicate acc ace met OR action in Performer's SRO's "Acc not Met" column initiated.
"Ace Initials Initials
( Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Pa~e 34 of 39 Page Data Sheet 1 (Page 13 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page _ _ __ of - - - -
Ref Location I Description Instrument # T S Limit Data Acc NOT Met Outside Normal Limits 1A-A DIG Rm near DIG set Readings on this page may be 0-Tf-30-5229 ~ 50°F OF el742 taken in any order.
18-8 DIG Rm near DIG set 0-Tf-30-5230 ~ 50°F OF In all sections of Ref 65, use of el742 Fluke 52 digital thermometer or 2A-A DIG Rm near DIG set equivalent is acceptable for 0-Tf-30-5231 ~ 50°F OF el742 temperature indicators not 28-8 DIG Rm near DIG set present or inoperable.
0-Tf-30-5232 ~ 50°F OF el742 28-8 DIG Rm on wall by Contact SRO to consult Technical 65 0-TI-30-5221 ~ 104°F Requirements section 3.7.5.1.
bat-tery charger el 742 OF SRO should evaluate normal AND abnormal limits. Perform Next to 480V Diesel Aux Data Sheet 65 of 1-SI-O-2-00 "Out 0-TI-30-5222 ~ 104°F 8d 281-8 e1760.5 of Limit Hourly Temperature".
OF C-S DIG temp only taken IF C-S
( C-S DIG Rm on wall near DIG TI-36 ~ 50°F DIG declared Operable. NIA if NOT operable Perform Data setel742 Sheet 65 of 1-SI-O-2-00 "Out of OF Limit Hourly Temperature" Pumpin Station (IPS)
NORMAL LIMITS Next to 480V IPS bd &
0-TI-30-5223 ~ 50°F &
trans-former (A bus) el 711 OF
~ 104°F In 8 train ERCW pump rm Contact SRO to consult 0-TI-30-5224 ~ 120°F OF el741 Technical Requirements Next to 480V IPS bd & section 3.7.5.1. SRO should 65 0-TI-30-5225 ~ 104°F OF evaluate normal AND trans-former (8 bus) el 711 Mech Equip Rm A near ERCW abnormal limits. Perform Data
~ 50°F & Sheet 65 of 1-SI-0-2-00 "Out
& HPFP instru sense lines 0-TI-30-5245
~ 104°F OF of Limit Hourly Temperature".
el722 Mech Equip Rm 8 near ERCW
~ 50°F &
& HPFP instru sense lines 0-TI-30-5246
~ 104°F OF el722 Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials
/
Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 35 of 39 Data Sheet 1 (Page 14 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page_ _ __ of _ _ __
Ref Location I Description Instrument # T S Limit Data Acc NOT Met Outside Notify SRO of need to evaluate DIG Various DIG Electrical Bd. See following Bkrs & HS in See following 66 operability using Data Sheet 66 of Rooms table required position table 1-SI-0-2-00 LOCATION Bkr& HS in BKR NOMENCLATURE 480V Diesel HS POSITION UNID Required POSITION Auxiliary Bd. Position?
DG 1A-A RM EXH FAN 1 PULL 1-BKR-30-447 I DYES 1A1-A C/2B ON (1-FAN-30-447) STANDBY 1-HS-30-447C DNO DG 1A-A RM GEN/PNL VENT FAN DYES 1A1-A C/4D ON N/A 1-BKR-30-491 (1-FAN-30-491) DNO DG 1A-A ELEC BOARD ROOM EXH 1-BKR-30-459 I DYES 1A1-A C/4E ON P-AUTO FAN (1-FAN-30-459) 1-HS-30-459C DNO DG 1A-A RM EXH FAN 2 1-BKR-30-451 I DYES 1A2-A C/2B ON P-AUTO (1-FAN-30-451 ) 1-HS-30-451C DNO DG 2A-A RM EXH FAN 1 PULL 2-BKR-30-448 I DYES 2A1-A C/2B ON (2-FAN-30-448) STANDBY 2-HS-30-448C DNO
( DG 2A-A ROOM GEN/PANEL VENT 2A1-A C/4D ON N/A 2-BKR-30-492 DYES FAN (2-FAN-30-492) DNO DG 2A-A ELEC BOARD ROOM EXH 2-BKR-30-460 I DYES 2A1-A C/4E ON P-AUTO FAN (2-FAN-30-460) 2-HS-30-460C DNO DG 2A-A RM EXH FAN 2 2-BKR-30-452 I DYES 2A2-A C/2B ON P-AUTO (2-FAN-30-452) 2-HS-30-452C DNO DG 1B-B ROOM EXH FAN 1 PULL 1-BKR-30-449 I DYES 1B1-B C/2B ON (1-FAN-30-449) STANDBY 1-HS-30-449C DNO DG 1B-B RM GEN/PNL VENT FAN DYES 1B1-B C/4D ON N/A 1-BKR-30-493 (1-FAN-30-493) DNO DG 1B-B ELEC BOARD ROOM EXH 1-BKR-30-461 I DYES 1B1-B C/4E ON P-AUTO FAN (1-FAN-30-461) 1-HS-30-461 C DNO DG 1B-B ROOM EXH FAN 2 1-BKR-30-453 I DYES 1B2-B C/2B ON P-AUTO (1-FAN 453) 1-HS-30-453C DNO DG 2B-B ROOM EXH FAN 1 PULL 2-BKR-30-450 I DYES 2B1-B C/2B ON (2-FAN-30-450) STANDBY 2-HS-30-450C DNO DG 2B-B ROOM GEN/PNL VENT FAN DYES 2B1-B C/4D ON N/A 2-BKR-30-494 (2-FAN-30-494) DNO DG 2B-B ELEC BOARD ROOM EXH 2-BKR-30-462 I DYES 2B1-B C/4E ON P-AUTO FAN (2-FAN-30-462) 2-HS-30-462C DNO DG 2B-B RM EXH FAN 2 2-BKR-30-454 I DYES 2B2-B C/2B ON P-AUTO (2-FAN-30-454) 2-HS-30-454C DNO Initials indicate ace met OR action in Performer's SRO's "Ace not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03
( Unit 1 Shift And Daily Surveillance Log Rev. 0030
\
Mode Three Page 37 of 39 Data Sheet 2 (Page 1 of 1)
Inoperable Components Date- - - - 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 0 Inoperable Ice Condenser Inlet Door Monitoring System Data Sheet 23 0 Inoperable Ice Bed Monitoring System Data Sheet 24 0 Inoperable Unit 1 Shield Building Stack Flow Monitor Data Sheet 37 0 Inoperable Diffuser Discharge Effluent Flow Monitor Data Sheet 38 0 Inoperable CVES Flow Monitor Data Sheet 45 0 Inoperable Auxiliary Building Stack Flow Monitor Data Sheet 51 0 Inoperable Liquid Radwaste Effluent Line Flow Monitor Data Sheet 55 0 Inoperable Condensate Demin Effluent Flow Monitor Data Sheet 58 0
( Inoperable SGBD to CTBD Flow Monitor Data Sheet 60 0 Inoperable Service Building Stack Flow Monitor Data Sheet 62 0 ICS Data Sheet 63 0 Out Of Limit Hourly Temperature Data Sheet 65 0 Periodic Temperature Check from DG Bldg Roof Data Sheet 66 0 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 ~P TIS Limit (IN WC) FLOW ICS Point Y2203A ~P 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.
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 EVALUATION SHEET Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three."
Alternate Path: N/A Facility JPM #: 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:
1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three," Rev.
30.
Task Number: RO-113-GEN-004
Title:
Perform surveillance tests.
Task Standard: Applicant reviews data collected for Data Sheet 1, pages 1 through 4 of 1-SI 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.
Validation Time: 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 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 required actions.
PAGE 3 OF 17
WATTS BAR JUCLEAR PLANT A.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:
I'.,*\'*~;
';'~' Key>Key~ , ,: '" .
",,**,*":I~
,',.. ""'.,{~'.\;,::,
".' ...,',',;.,....... '.,1.~*.\.;.:' . Type Event Delay ,Inserted Ramp ",'" Initial Final Value pi-1-2a 05150 sg #1 stm hdr eh 1 0 00:00:00 00:00:00 00:00:00 1055 1074.1 pi-1-2b 05150 sg #1 stm hdr eh 2 0 00:00:00 00:00:00 00:00:00 1055 1074.1 pi-1-5 05150 sg #1 main stm hdr 0 00:00:00 00:00:00 00:00:00 1100 1074.1 1i-3-55 05050 sg #2 level ind 0 00:00:00 00:00:00 00:00:00 30 37.8133 li-68-335a 05350 res przr Ivl(m-4) 0 00:00:00 00:00:00 00:00:00 32 27.1232 li-63-52 09030 sis rwst level ind 0 00:00:00 00:00:00 00:00:00 90 98.1359
6. Place simulator in RUN and acknowledge any alarms.
7. Place simulator in FREEZE until Examiner cue is given.
PAGE 4 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT 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 SAT 3 data collection and determine if Acceptance Criteria are met. UNSAT 1-M-2 1-Ll-2-230A 0 Perform Data
~ 200,000 Sheet 3 of 3 Pnl 0-L-209 CST A Level OR gallons 1-SI-0-2-00 T15MI708 1-Ll-2-230B 0 gallons "CST Level" STANDARD:
Applicant determines that 1-U-2-230A reading, approximately 390,000 gallons, is within acceptance criteria.
COMMENTS:
PAGE 5 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2. PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 1, Reference CRITICAL 4 data collection and determine if Acceptance Criteria are STEP met.
SAT 1-PI-1-2A psig SG 1 Press 1-PI-1-2B psig UNSAT 1-PI-1-5 psig 1-PI-1-9A psig SG 2 Press 1-PI-1-9B Operable, psig Contact SRO 1-PI-1-12 Channel psig 4 1-M-4 Check, and to 1-PI-1-20A psig consult Tech MCD s: 90 Specs.
SG3 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 f----------1 1-PI-1-30 psig STANDARD:
( Applicant determines that SG 1 Pressure channeI1-PI-1-5 is NOT within MCD of 90 psig. The applicant CIRCLES the 1100 psig value for 1-PI-1-5, 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
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT STEP 3: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 1, Reference CRITICAL 5 data collection and determine if Acceptance Criteria are STEP met.
SAT 1-Ll-3-42 %
SG 1 Level 1-Ll-3-39 f---------j
% UNSAT 1-Ll-3-38 %
1-Ll-3-55 %
Operable at SG 2 Level 1-Ll-3-52 2: 32% NR [for %
Contact SRO 1-Ll-3-51 OPERABLE % to 5 1-M-4 loops].
1-Ll-3-97 % consult Tech Channel Specs.
SG 3 Level 1-Ll-3-94 Check, and %
f---------j MCDs6.0%
1-Ll-3-93 %
1-Ll-3-110 %
SG4 Level 1-U-3-107 %
1-U-3-106 %
STANDARD:
Applicant determines that SG 3 Level channel 1-Ll-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 16, Condition A - Restore channel within 30 days.
COMMENTS:
PAGE 7 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference 8 data collection and determine if Acceptance Criteria are SAT met.
UNSAT Operable, Channel Check, and MCD SR Neutron value is plus or minus 1-NI-92-131A 1/2 decade Contact Mon CH I
[O.3CR1<CR2 SRO to 8 1-M-4 <3.0CR1]. CPS(2) consult f --
r -----

j j Tech Spec Reading should be the s.

SR Neutron average value 1-NI-92-132A Mon CH II observed over a 30 second period STANDARD:
Applicant determines that the Source Range Monitors are Operable and within the MCD tolerance.
COMMENTS:
(
PAGE 8 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO
(
Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 2, Reference CRITICAL 9 data collection and determine if Acceptance Criteria are STEP met.
SAT 1-Ll-68-339A % Contact Operable, less than or 1-----------1 SRO 9 1-M-4 PZR Level 1-Ll-68-335A equal t080%, % to consult UNSAT Channel Check, and 1-Ll-68-320 MCD 5: 6.0% Tech Spec
% s.
STANDARD:
Applicant determines that PZR Level channel 1-U-68-335A is NOT within MCD (::; 6.0%). The applicant CIRCLES the value for 1-Ll-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 16, Condition A - 30 days.
COMMENTS:
PAGE 9 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 2, Reference SAT 10 data collection and determine if Acceptance Criteria are met. UNSAT 1-PI-68-340A psig Operable Contact 1-PI-68-334 channel check, psig SRO 10 1-M-5 PZR Press greater than or equal to consult 1-PI-68-323 to 2214psig and psig Tech Spec MCDs 55 psig. s 1-PI-68-322 psig STANDARD:
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
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 2, Reference SAT 15 data collection and determine if Acceptance Criteria are met. UNSAT RCP 1 2 3 4 RCS Loops RCP Status ON 0 0 0 0 1,2,3,4 OFF 0 0 0 0 1-HS-68-8AA Two loops operable; {ll Contact RCP 1 1-HS-68-8BA two loops in operation SROto 15 1-M-5 1-HS-68-31AA if capable of rod consult RCP2 (1) 1-HS-68-31BA withdrawal (one loop if Tech Spec NOT) s.
1-H S-68-50AA (1)
RCP3 1-HS-68-50BA 1-HS-68-73AA (1)
RCP4 1-HS-68-73BA STANDARD:
Applicant determines that acceptance criteria are met.
COMMENTS:
PAGE 11 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference SAT 16 data collection and determine if Acceptance Criteria are met. UNSAT Ref Location Description Instrument # T S Limit Data Acc NOT Met RWSTto RHR 1-FCV-63-1 OPEN 0 ECCS Suction (1-HS-63-1A) CLOSED 0 16 1-M-6 OPEN SI Pumps to CL 1, 1-FCV-63-22 OPEN 0 2,3,4 (1-HS-63-22A) CLOSED 0 Shunt BKR 1A1-A OFF D cl2E1 1-BKR-63-1A ON D Contact SRO to At least one OR consult Breaker breaker OFF OFF D 1-BKR-63-1 B Tech Specs, 480V Rx 1A1-Ac/10A ON D MOV Boards Shunt BKR 1B1-B OFF D c/2F2 1-BKR-63-22A ON D At least one OR Breaker breaker OFF OFF D 1-BKR-63-22B 1B1-Bc/11D ON D STANDARD:
Applicant determines that all acceptance criteria are met for 1-FCV-63-1
( and 1-FCV-63-22.
EXAMINER'S CUE:
Local information will be marked on the Data Sheet provided to the applicant, as indicated in the INITIAL CONDITIONS.
COMMENTS:
(
PAGE 12 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 3, Reference . CRITICAL 17 data collection and determine if Acceptance Criteria STEP are met.
SAT
% UNSAT
% Contact SRO to f ---
r -----------------
t1- --
--++ --
---i---
-i----
c--,---- ------ - j consult Tech 1--_ _% Specs 1 - - - - - - -0/,---\0 1
STANDARD:
Applicant determines that CNTMT SUMP channels meet acceptance criteria.
Applicant determines that 1-Ll-63-53 RWST Level channel does NOT meet l acceptance criteria, and requires that a Work Order be written. The
\.
applicant CIRCLES the value for 1-Ll-63-53. This channel is NOT a PAM designated channel.
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
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT 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 0 CL Accum 1 Outlet (1-HS-63-118A) CLOSED 0 1-FCV-63-98 Valves OPEN 0 CL Accum 2 Outlet Contact SRO to
( 1-HS-63-98A) Open-when Pzr CLOSED 0 18 1-M-6 consult 1-FCV-63-80 pressure OPEN 0 CL Accum 3 Outlet Tech Specs.
(1-HS-63-80A) >1000 psig. CLOSED 0 1-FCV-63-67 OPEN 0 CL Accum 4 Outlet (1-HS-63-67A) CLOSED 0 STANDARD:
Applicant determines that all valves are in their required positions and meet acceptance criteria.
COMMENTS:
PAGE 14 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11: PERFORM 1-SI-O-2A-03, Data Sheet 1, Page 4, Reference SAT 19 data collection and determine if Acceptance Criteria are met. UNSAT Ref Location Description Instrument # T S Limit Data AccNOTMet CLAccum 1 1-LJ-63-129 gal Lvi 'J -LJ-63-1 '19 gal Check operability CLAccum2 1-U-63-109 gal by acceptable Lvi 1-U-63-99 gal deviation between redundant level and CLAccum 3 l-U-63-89 gal pressure channels Lvi when pressurizer
'I-U-63-81 gal pressure is above
'I-U-63-82 gal '1000 psig If CLAccum4 deviation limit is Lvi 1-U-63-60 gal
'19 '1-lvl-6 exceeded, l-PI-63-'128 psig determine the CLAccum 1 channeJ inoper-abJe Press l-PI-63-126 psig AND record only l-PI-63-'108 psig the operable CLAccum 2 channel. This Press ~6'IO and ~660 psig 1-PI-63-106 psig channel check is and MCD ~30 l-PI-63-88 psig (ll psig NOT a technical CLAccum 3 specification Press 'I-PI-63-86 psig re-quirement CLAccum4 1-PI-63-62 psig
( Press l-PI-63-6'J psig STANDARD:
Applicant determines that all Cold Leg accumulator level and pressure channels meet acceptance criteria.
COMMENTS:
PAGE 15 OF 17
WATTS BAR NUCLEAR PLANT A.2-1 SRO Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12: PERFORM 1-SI-0-2A-03, Data Sheet 1, Page 4, Reference SAT 20 data collection and determine if Acceptance Criteria are met. UNSAT 1-PDI-30-42 0 Operable, Channel or Point P1000A 0 psig (2)
Check, and MCD of 1-PDI-30-43 0 tt-.e following:
1-M-6 or or Point P1001A 0 MCD s 1.0 psig (Ind) '2i f--_-'-PS....;:i9_\2-1 f--_-'-PS-"i _ -ji Contact SRO to 20 CNTMT Press ICS 1-PDI-30-44 0 consult Teer, Specs MCD s: O.S psig or Point P1002A 0 (mixed) psig (2) 1-PDI-30-45 0 MCD s: 0.5 psig or Point P1003A 0 (computer) psig (2]
STANDARD:
Applicant determines that all channels meet acceptance criteria.
COMMENTS:
(
STOP TIME _ __
PAGE 16 OF 17
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 required actions.
(
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 8y: Scot Newell Approved 8y: 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.
Added 1-FI-90-400 for Shield Building Flow 32 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 T ACF 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 4 of 39 Table of Contents (continued)
Data Sheet 2: Inoperable Components ........................................................................... 37 Attachment 1: Determining Annulus ~P 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 ilP Channel Checks:
a. Annulus to Atmospheric ilP Channel Check.
( b. Annulus to Containment ilP 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. RCW and 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 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 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 Ref Freq MODES SR p3.3.1.1-5 2(1),3(2).(3) 2,3,4,5,6 B S 4(2).(3), 5(2).(3)
SR p3.3.2.1-1.c 1,2,3 1,2,3 20 S SR p3.3.2.1-1.d 1,2,3(4) 1,2,3 10 S SR p3.3.2.1-1.e 1,2,3(4) 1,2,3 4 S SR p3.3.2.1-2.c 1,2,3 1,2,3 20 S SR p3.3.2.1-3.b.(3) 1,2,3 1,2,3 20 S SR p3.3.2.1-4.c 1,2(5),3(5) 1,2,3 20 S SR p3.3.2.1-4.d.(1) 1,2(5),3(4),(5) 1,2,3 4 S 3(5),(6)
SR p3,3.2.1-4.d.(2) 3 4 S SR p3.3.2.1-5.b 1 ,2(7), 3(7) 1,2,3 5 S SR p3.3.2.1-6.b 1,2,3 1,2,3 5 S SR p3.3.2.1-7.b 1,2,3,4 1,2,3,4 17 S SR p3.3.2.1-B.b.(1) 1,2,3 1,2,3 10 S SR p3.3.2.1-B,b.(2) 1,2,3 1,2,3 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.
(1) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(2) With RTBs closed and Rod Control System capable of rod withdrawal.
(3) With RTBs open. In this condition, source range function does NOT provide reactor trip but does provide indication.
(4) Above P-11 (Pressurizer Pressure) interlock.
(5) Except when all MSIVs are closed & deactivated.
(6) 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.
(7) Except when all MFIVs, MFRVs, and their bypass valves are closed and deactivated or isolated by a closed manual valve.
(8) 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 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 p3.6.11.10T0 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 p3.6.15.10T0 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 Freq REQUIREMENTS MODES T8R p3.1.2.1 1,2,3 1,2,3 65 8 T8R p3.6.1.1 '" 1,2,3,4 1 ,2,3,4 24 8 T8R p3.6.2.1 1,2,3,4 1,2,3,4 23 8 T8R p3.6.2.3 1,2,3,4 1,2,3,4 23 8 T8R p3.7.5.1 All All 65 8 TR p3.6.1 Action B.1.1 1,2,3,4 1,2,3,4 24 1&8 TR p3.6.1 Action B.1.2 1,2,3,4 1,2,3,4 24 1 TR p3.6.1 Action B.1.3 1,2,3,4 1,2,3,4 24 1&8 TR p3.6.1 Action C.1.1 1,2,3,4 1,2,3,4 24 1&8 TR p3.6.1 Action C.1.2 1,2,3,4 1,2,3,4 24 1 TR p3.6.2 Action A.1 1,2,3,4 1,2,3,4 24 4
( The more conservative Tech Spec Operability Limit provided by the applicable Setpoint and Scaling document (SSO) is used instead of the Tech Spec value.
D. Performance of this Instruction satisfies the following Offsite Dose Calculation Manual Surveillance Requirements (OSRs):
ODCM SURVEILLANCE APPLICABLE MODES PERFORMANCE MODES Ref Freq REQUIREMENTS 08R p2.1.2-3.f AII(2O) AII(2O) 59 0 08R p2.1.2-4.e All All 59 0 (20) Both Unit 1 and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement.
E. Fulfillment of special conditions will initiate the following requirements:
SURVEILLANCE REQUIREMENTS APPLICABLE MODES PERFORMANCE MODES Ref Freq TR p3.6.1 Action A.1 1,2,3,4 1,2,3,4 24 8
(
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. 1-001-90-2, Steam Generator Blowdown Release B. 1-001-90-25, Condenser Vacuum Exhaust Release.
(
C. 1-SI-63-6, Cold Leg Accumulators Boron Determination.
O. 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, NPOES 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
( Page 12 of 39 Mode Three 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. (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-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 14 of 39 Date_ __ Page_ __ of - - -
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
[1J OBTAIN SM/Unit SRO approval on the Surveillance Task Sheet to perform this Instruction.
(
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Pa~e 15 of 39 Page 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 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 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 _ __ of _ __
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.
(
(
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 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 22 of 39 Data Sheet 1 (Page 1 of 15)
Mode 3 Surveillance Log: 1900-0700 Date\~ Page_--,-__
Page_---'-__ of IS I Ref I Location I Description I Instrument # T S Limit Data Acc NOT Met Perform Data 1-M-2 1-U-2-230A 0
200,000 3'\°lOOO Sheet 3 of 3 PnI0-L-209 CST A Level OR gallons 1-SI-0-2-00 T15M1708 1-U-2-230B 0 gallons "CST Level" 1-PI-1-2A lOSt> psig SG 1 Press 1-PI-1-2B 10Sb psig 1-PI-1-5 llc;t) psig 1-PI-1-9A (010 psig SG 2 Press 1-PI-1-9B Operable, 1070 psig Contact SRO Channel 1-M-4 1-PI-1-12 Check, and IO~o psig to 4
1-PI-1-20A psig consult Tech MCD:::; 90 (070 Specs.
SG 3 Press 1-PI-1-20B psig lOG:,O psig
( 1-PI-1-23 1070 psig 1-PI-1-27A ID70 psig SG 4 Press 1-PI-1-27B I 07D psig 1-PI-1-30 {070 psig SG 1 Level 1-U-3-42 1-U-3-39 3'
3'1 1-U-3-38 36 %
1-U-3-55 Operable at ~Cf %
SG 2 Level 1-U-3-52 ;:: 32% NR [for OPERABLE 3a
~a %
Contact SRO 5 1-M-4 1-U-3-51 loops],
38 % to consult Tech 1-U-3-97 Channel 31 %
Specs.
SG 3 Level 1-U-3-94 Check, and MCD:::;6.0%
':51 %
1-U-3-93 31 %
1-U-3-110 .3"1 %
SG 4 Level 1-U-3-107 3Cf %
1-U-3-106 3~ %
Initials INDICATE acc met OR action in SRO's "Acc not Met" column initiated. Initials 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-'-~1\
Date-r~
Page Z of Is
~
Ref Acc NOT Location Description Instrument # T S Limit Data Met Operable, Channel Check, and MCD SR Neutron value is plus or minus 1-NI-92-131A Contact Mon CH I 1/2 decade
[0.3CR1<CR2 SROto 8 1-M-4 CPS(2) consult
<3.0CR1]. 1- Tech Spec Reading should be the s.
SR Neutron average value 1-N 1-92-132A Mon CH" observed over a CPS(2) 30 second period Z.
1-L/-68-339A ~fp
~(p % Contact Operable, less than or SRO 1-L/-68-335A equal to80%,
9 1-M-4 PZR Level ChannelCheck,and 3Z % to consult Tech Spec 1-L/-68-320 MCD :5:6.0%
zt; 2t; % s.
( 1-PI-68-340A ZZG, ~ psig Operable Contact 1-PI-68-334 channel check, Z2.I~ psig SRO 10 1-M-5 PZR Press greater than or equal to consult 1-PI-68-323 to 2214psig and ZZz..o psig Tech Spec MCD:5: 55 psig. s 1-PI-68-322 Zz.~O psig RCP 1 234 RCS Loops 1,2,3,4 RCP Status ON~
ON~
OFF D D D D 1-HS-68-8AA Two loops operable; Contact RCP 1 1-HS-68-8BA two loops in operation -e- (1)
SROto 15 1-M-5 1-HS-68-31AA if capable of rod consult (1)
RCP2 withdrawal (one loop if Tech Spec 1-HS-68-31 BA NOT) 1Z. s.
1-H S-68-50AA (1)
RCP3 1-HS-68-50BA IZ-1-HS-68-73AA (1)
RCP4 1-HS-68-73BA ~
(1) Loop status is to be written in data space (Operable (O), 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 SRO's "Acc not Met" column initiated. Initials
( Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 24 of 39 Data Sheet 1 (Page 3 of 15)
Mode 3 Surveillance Log: 1900-0700 Dat~~
Date(~ (
Page 3 of IS Ref Location Description Instrument # T S Limit Data Acc NOT Met RWSTto RHR 1-FCV-63-1 OPEN [p""
[p" ECCS Suction (1-HS-63-1 A) CLOSED 0 16 1-M-6 OPEN SI Pumps to CL 1, 1-FCV-63-22 OPEN IB'"
IB""
2,3,4 (1-HS-63-22A) CLOSED 0 Shunt BKR 1A1-A OFF c/2E1 1-BKR-63-1A At least one ON g" Contact SRO to OR consult Breaker breaker OFF OFF I:ir'"
I:ir" 1-BKR-63-1B Tech Specs.
480V Rx 1A1-A c/10A ON 0 MOV
~
Boards Shunt BKR 1B1-B OFF c/2F2 1-BKR-63-22A ON At least one OR Breaker 1-BKR-63-22B breaker OFF OFF W 1 B1-B c/11D ON 0 1-U-63-180 0 %
Operable, CNTMT 1-U-63-181 Channel check, 0 %
( Sump Level 1-U-63-182 and 0 %
MCD :0;6.0% Contact SRO to 1-M-6 1-U-63-183 0 %
consult Tech 17 1-U-63-50 Operable, 9e, % Specs 1-U-63-51 Channel check, <3lP %
RWST Level and MCD 1-U-63-52
0;7.0%
~~ %
1-U-63-53 ~O %
CL Accum 1 Outlet 1-FCV-63-118 OPEN !B'
!B'""
(1-HS-63-118A) CLOSED 0 1-FCV-63-98 Valves OPEN riV I:iY CL Accum 2 Outlet (1-HS-63-98A) Open-when Pzr CLOSED 0 Contact SRO to 18 1-M-6 consult 1-FCV-63-80 pressure OPEN [R'" Tech Specs.
CL Accum 3 Outlet >1000 psig.
(1-HS-63-80A) CLOSED 0 1-FCV-63-67 OPEN r1V CL Accum 4 Outlet (1-HS-63-67A) CLOSED 0 Initials INDICATE acc me! OR action in SRO's "Acc not Met" column initiated. Initials
( Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Pa~e 25 of 39 Page Data Sheet 1 (Page 4 of 15)
Mode 3 Surveillance Log: 1900-0700 Date~ Page 4 of Ie I~- -
of_.....:/'---_
Ref Location Description Instrument # T S Limit Data Acc NOT Met CLAccum 1 1-U-63-129 18\~ gal Lvi 1-U-63-119 ~ 7630 and :s;8000 gal 18l.00
."l8l. Check operability gal and MCD :s; 96 CLAccum 2 1-U-63-109 "18,0 gal by acceptable gal. Chemistry is to Lvi 1-U-63-99 be notified to 7e,S- gal deviation between redundant level and perform 1-SI-63-6 1-U-63-89 7gto gal CLAccum 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if tank 19l0 pressure channels Lvi 1-U-63-81 level is increased ~ when pressurizer 71(10 gal 75 gal and tank NOT pressure is above 1-U-63-82 filled from RWST.(l) gal 1000 psig. If CLAccum 4 lifO
"'lilO deviation limit is Lvi 1-U-63-60 19 1-M-6 7g'10 19'10 gal exceeded, i-PI-63-128 psig determine the CLAccum 1 ~2.o channel inoper-able Press i-PI-63-i26 ~3S" psig AND record only
( CLAccum 2 1-PI-63-108 ~ psig the operable channel. This Press ~610 and :s;660 psig 1-PI-63-106 ~~S' psig channel check is and MCD:S; 30 i-PI-63-88 psig (1) NOT a technical CLAccum 3 fL,g> psig tog> specification Press 1-PI-63-86 ~ -zt;;
~-z.~ psig re-quirement.
CLAccum 4 1-PI-63-62 {q30 psig Press i-PI-63-61 ~6l:> psig 1-PDI-30-42 ~ Operable, Channel or Point Pi OOOA 0 Check, and MCD of 0 psig (2) i-PDI-30-43 !iV' the following:
i-M-6 or or Point Pi 001A 0 MCD:s; 1.0 psig (Ind) 0 psig (2)
Contact SRO to 20 CNTMT Press ICS i-PDI-30-44 ~ MCD :s; 0.8 psig consult Tech Specs or Point Pi 002A 0 (mixed) 0 psig (2) i-PDI-30-45 [!(" MCD :s; 0.5 psig or Point Pi 003A 0 (computer) 0 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 Performer's SRO's "Acc not Met" column initiated. Initials Initials
(, Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 26 of 39 Data Sheet 1 (Page 5 of 15)
Mode 3 Surveillance Log: 1900-0700 Date Page of Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-POI-30-133 0 CNTMT-ANN llP between -0.07 21 1-M-9 or llP and 0.27 psid psid(2) 1-PDI-30-30C 0 More negative than or 1-PDI-30-126 " H20(4) equal value on 1-M-9 Annulus llP Attachment 1 " H20(1) 1-PDI-30-127 and MCD ~ 0.7 "H 2O " H20(4) Contact SRO to consult point Y2203A 0 Tech Specs.
22 or ICS Shield N/A-used for 1-FI-90-400 0 1-M-9 Building Flow Attachment 1 or Data Sheet 37(3) 0 SCFM Tech Spec Acceptance value from Attachment 1 " H20(4)
(1 ) 1-PDI-30-126 and 1-PDI-30-127 have a range of 0 -10" H2 0 and indicate negative pressure relative to atmosphere (e.g. an
( indication of 6" H2 0 is more negative than negative 5.5" H2 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 LlP 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 Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
(
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 27 of 39 Data Sheet 1 (Page 6 of 15)
Mode 3 Surveillance Log: 1900-0700 Ret Location Description Instrument # TS Limit Data Acc NOT Met 23 1-M-1O Ice Cndnsr Door 1-XI-61-187 Operable, all doors (..J) Contact SRO to consult Status Position closed, and Channel Tech Specs and perform Monitoring Check data sheet 23.
System 24 1-M-1O Ice Bed 1-TR-61-138 Operable, :s; 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 (1) group operable. Sheet 24 of 1-SI-O-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 LeO 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 Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 28 of 39 Data Sheet 1 (Page 7 of 15)
Mode 3 Surveillance Log: 1900-0700 Date----- Page_ _ __ of 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 EL 776 EL 756 Group 7(1)(2) 144 3 Group 4(1)(2) 145 18 Group 1(1)(2) 146 32 147 4 148 19 149 33 150 5 151 20 152 34 1 1 1 Two Highest Temps Two Highest Temps Two Highest Temps 2 2 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 EL 776 EL 756 Group 8(1)(2) 159 8 Group 5(1)(2) 160 23 . Group 2(1)(2) 161 36 165 9 166 24 167 37 183 10 184 25 185 38
( Two Highest Temps 1
Two Highest Temps 1
Two Highest Temps 1
2 2 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 EL 776 EL 756 Group 9(1)(2) 174 13 Group 6(1)(2) 175 28 Group 3(1)(2) 176 41 177 14 178 29 179 42 180 15 181 30 N/A N/A N/A 1 1 1 Two Highest Temps Two Highest Temps Two Highest Temps 2 2 2 Sum of 1 and 2 Sum of 1 and 2 Sum of 1 and 2 TOTAL OF MEAN ICE BED OPTIMUM MEAN ICE PERFORMER TOTALS + 18 TEMP (3) REVIEWER INITIALS SUMS 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 Performer's SRO's "Ace not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 29 of 39 Data Sheet 1 (Page 8 of 15)
Mode 3 Surveillance Log: 1900-0700 Date- - - - Page_ _ __ of _ _ __
Ref Location Description Instrument # T S Limit Data Ace NOT Met 1-RM-90-106A 0 or point R1012A 0 If monitor aligned to cpm Lower Containment is 1-RM-90-106B 0 inoperable, the other or monitor is to be re-point R1013A 0 Operable and cpm aligned using Lower and 1-RM-90-112A 0 Channel Check SOI-90.02. If both 0-M-12 or Upper CNTMT 25 or monitors are inoper-ICS Gas and point R1015A 0 cpm able, SRO is to be Particulate notified,1-SI-68-32 1-RM-90-112B 0 is to be performed, or and Chemistry Count-point R1016A 0 cpm room is to be notified 1-RR-90-106 (>/) to perform 1-SI-90-25.
Operable 1-RR-90-112 (>/)
0-RM-90-102 0
( or 0-M-12 or Spend Fuel Pit point R9011A 0 Operable and mr/hr Contact SRO to consult 26 ICS Area 0-RM-90-103 0 Channel Check Tech Specs or point R9012A 0 mr/hr 0-RM-90-125 0 or point R1 025A 0 cpm 0-RM-90-126 0 Contact SRO to consult 0-M-12 or Operable and 27 MCR Intake or Tech Specs. See ICS Channel Check point R1026A 0 cpm Section 6.1 K.
0-RR-90-125 (>/)
0-RR-90-126 (>/)
Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
(
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 30 of 39 Data Sheet 1 (Page 9 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page_ _ __ of -_ _ __
Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-RM-90-123 0 Operable and O-M-12 or CCS HxA Out Contact SRO. See 28 or Channel Check ICS Liquid Section 6.1 K.
point R1023A 0 (Info Only-T.S. N/A) cpm 1-RM-90-130A 0 Contact SRO to consult or Tech Specs. See CNTMT AUX BLDG point R1027A 0 cpm Section 6.1K. IF both Purge Air Exh Operable and 29 A2U/713 or monitors inoperable, Radiation Channel Check ICS 1-RM-90-131A 0 suspend purge flow Monitor or immediately per ODCM point R1028A 0 table 1.1.2-6.a cpm
(
Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
(
WBN 1900., 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three PaJle 31 of 39 Page Data Sheet 1 (Page 10 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ ____ __ Page_ _ __ ___
of ___ __
Ref Location Description Instrument # T S Limit Data Acc NOT Met Unit 1 Shield Bldg Exhaust AEB 729 1-SM PL 801 Operable Tritium Flow Rate Monitor (>I) If Tritium flow rate measuring device Unit 2 Shield is inoperable, SRO Bldg Exhaust AEB 729 2-SMPL-90-801 Operable and Chemistry are 59 Tritium Flow to be notified.
Rate Monitor ('1/)
Initiate WO and Aux Bldg and record number in Fuel Handling remarks section.
AUX BLDG Exhaust Tritium 0-SMPL-90-800 Operable 786 Flow Rate Monitor ('1/)
Completed or in progress for the required
( 67 N/A 1-SI-0-10(1) N/A Tech Specs per performance N/A 1-SI-0-10 frequency interval 0 ('1/)
(1)
Conditional performance cannot be substituted for periodic performance.
Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
(
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 32 of 39 Data Sheet 1 (Page 11 of 15)
Mode 3 Surveillance Log: 1900-0700 Date-_ _ __ Page_ _ __ of _ _ __
Ref Location I Description Instrument T S Limit Data Acc NOT Met Control Building NORMAL LIMITS Control Room South Wall 0-TI-30-5219 ::; 80°F OF Readings on this el755 page may be taken in Control Room across from any order.
0-TI-30-5220 ::; 80°F OF 1-M-9 el755 Next to 480V SO BO In all sections of Ref 0-TI-30-5201 ::; 104°F OF Transformer 1A2-A el772 65, use of Fluke 52 Next to 480V SO BO digital thermometer or 0-TI-30-5202 ::; 104°F OF Transformer 1 B 1-B el 772 equivalent is Next to 480V Rx MOV acceptable for 0-TI-30-5203 ::; 83°F OF Bd 1A2-A el 772 temperature Behind 125V Vital Batt indicators not present 0-TI-30-5204 ::; 83°F OF or inoperable.
Charger 6-S el 772 Next to 480V Rx MOV 0-TI-30-5205 ::; 83°F OF Bd 2A2-A el 772 Next to 480V SO BO
( 65 Transformer 2A2-A el 772 0-TI-30-5206 ::; 104°F OF Next to 480V SO BO 0-TI-30-5207 ::;104°F OF Transformer 2B2-B el 772 Contact SRO to Next to 480V Rx MOV consult Technical 0-TI-30-5208 ::; 83°F OF Bd 2B2-B el 772 Requirements section 3.7.5.1. SRO should U1 Mech Equip Rm el772 0-TI-30-5209 ::; 91°F OF evaluate normal AND SO BO Rm U1 behind stairs abnormal limits.
0-TI-30-521 0 ::;85°F OF S-A3 el757 Perform Data Sheets SO BO Rm U2 behind stairs 65 of 1-SI-0-2-00 0-TI-30-5211 ::; 85°F OF S-A13 el757 "Out of Limit Hourly Refuel Floor U1 beside Aux Temperature" .
0-TI-30-5212 ::; 104°F OF Boration Makeup MakeLlP_ Tank el 757 Computer room at center of 0-TI-30-5226 ::; 74°F OF the room el 708 Aux Instrument Room el 708 0-TI-30-5233 ::; 90°F OF Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030 Mode Three Page 33 of 39 Data Sheet 1 (Page 12 of 15)
Mode 3 Surveillance Log: 1900-0700 Date- - - - Page_ _ __ of - - - -
Ref Location .l Description Instrument # T S Limit Data Acc NOT Met Auxiliary Building Normal Limits U1 outside supply fan room Readings on this 0-TI-30-5213 :::; 104°F of el737 page may be taken in any order.
South steam vault room U1 0-TI-30-5228 ;::: 50°F of el730 In all sections of Ref North steam vault room U1 65, use of Fluke 52 0-TI-30-5227 ~ 50°F of el730 digital thermometer Between UHI Accumulators or equivalent is 0-TI-30-5218 :::; 92°F OF acceptable for el729 temperature U1 across from AFW pumps indicators not 0-TI-30-5214 :::; 104°F present or el713 of inoperable.
U1 outside AFW pump room Contact SRO to 0-TI-30-5215 :::; 104°F of door el692 consult Technical Requirements U2 near Boric Acid section 3.7.5.1. SRO 65 con-centrate filter vault 0-TI-30-5216 :::; 104°F should evaluate el692 of normal AND abnormal limits.
Perform Data Sheets 65 of 1-SI Next to 0-L-629 el 676 0-TI-30-5217 :::; 104°F 2-00 "Out of Limit Hourly of Temperature".
U 1 Blender Station South Contact SRO to 1-TI-62-240 ;::: 63°F consult Technical Wall el713 of Requirements section 3.1.1.1 &/or 3.1.2.1 Perform Behind BAT A el713 1-TI-62-239 ~ 63°F Data of Sheet 65 of 1-SI 2-00 "Out of Limit Behind BAT B el 713 2-TI-62-239 ;::: 63°F Hourly of Temperature".
Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials qemarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 34 of 39 Data Sheet 1 (Page 13 of 15)
Mode 3 Surveillance Log: 1900-0700 Date-_ _ __ Page_ _ __ of _ _ __
of Ref Location I Description Instrument # T S Limit Data Acc NOT Met Outside Normal Limits 1A-A DIG Rm near DIG set Readings on this page may be 0-TI-30-5229 ~ 50°F of el742 taken in any order.
1B-B DIG Rm near DIG set 0-TI-30-5230 ~ 50°F In all sections of Ref 65, use of el742 of Fluke 52 digital thermometer or 2A-A DIG Rm near DIG set equivalent is acceptable for 0-TI-30-5231 ~ 50°F of el742 temperature indicators not 2B-B DIG Rm near DIG set present or inoperable.
0-TI-30-5232 ~ 50°F of el742 2B-8 DIG Rm on wall by Contact SRO to consult Technical 65 0-TI-30-5221 ~ 104°F Requirements section 3.7.5.1.
bat-tery_
bat-tery charger el 742 OF SRO should evaluate normal AND abnormal limits. Perform Next to 480V Diesel Aux Data Sheet 65 of 1-SI-O-2-00 "Out 0-TI-30-5222 ~ 104°F 8d 281-8 el 760.5 of Limit Hourly Temperature".
of C-S DIG temp only taken IF C-S
( C-S DIG Rm on wall near DIG TI-36 DIG declared Operable. NIA if
~ 50°F NOT operable Perform Data setel742 Sheet 65 of 1-SI-O-2-00 "Out of of Hourl~ Temperature" Limit Hourly Tem~erature" Pumpin Station JIPS) (IPS)
NORMAL LIMITS Next to 480V IPS bd &
0-TI-30-5223 ~ 50°F &
trans-former (A bus) el 711 of
~ 104°F In 8 train ERCW pump rm Contact SRO to consult 0-TI-30-5224 ~ 120°F of Technical Requirements el741 Next to 480V IPS bd & section 3.7.5.1. SRO should 65 0-TI-30-5225 ~ 104°F of evaluate normal AND trans-former (8 bus) el 711 Mech Equip Rm A near ERCW abnormal limits. Perform Data
~ 50°F & Sheet 65 of 1-SI-0-2-00 "Out
& HPFP instru sense lines 0-TI-30-5245
~ 104°F of of Limit Hourly Temperature".
el722 Mech Equip Rm 8 near ERCW
~ 50°F &
& HPFP instru sense lines 0-TI-30-5246
~ 104°F of el722 Initials indicate acc met OR action in Performer's SRO's "Acc not Met" column initiated. Initials Initials
(, Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 35 of 39 Data Sheet 1 (Page 14 of 15)
Mode 3 Surveillance Log: 1900-0700 Date_ _ __ Page _ _ _--'- of - - - -
Ref Location I Description Instrument # T S Limit Data Acc NOT Met Outside Notify SRO of need to evaluate DIG Various DIG Electrical Bd. See following Bkrs & HS in See following 66 operability using Data Sheet 66 of Rooms table required position table 1-SI-O-2-00 LOCATION Bkr & HS in BKR NOMENCLATURE 480V Diesel HS POSITION UNID Required POSITION Auxiliary Bd. Position?
DG 1A-A RM EXH FAN 1 PULL 1-BKR-30-447 I DYES 1A1-A C/2B ON (1-FAN-30-447) STANDBY 1-HS-30-447C DNO DG 1A-A RM GEN/PNL VENT FAN DYES 1A1-A C/4D ON N/A 1-BKR-30-491 (1-FAN-30-491 ) DNO DG 1A-A ELEC BOARD ROOM EXH 1-BKR-30-459 I DYES 1A1-A C/4E ON P-AUTO FAN (1-FAN-30-459) 1-HS-30-459C DNO DG 1A-A RM EXH FAN 2 1-BKR-30-451 I DYES 1A2-A C/2B ON P-AUTO (1-FAN-30-451 ) 1-HS-30-451 C DNO DG 2A-A RM EXH FAN 1 PULL 2-BKR-30-448 I DYES 2A1-A C/2B ON (2-FAN-30-448) STANDBY 2-HS-30-448C DNO
( DG 2A-A ROOM GEN/PANEL VENT FAN (2-FAN-30-492) 2A1-A C/4D ON N/A 2-BKR-30-492 DYES DNO DG 2A-A ELEC BOARD ROOM EXH 2-BKR-30-460 I DYES 2A1-A C/4E ON P-AUTO FAN (2-FAN-30-460) 2-HS-30-460C DNO DG 2A-A RM EXH FAN 2 2-BKR-30-452 I DYES 2A2-A C/2B ON P-AUTO (2-FAN-30-452) 2-HS-30-452C DNO DG 1B-B ROOM EXH FAN 1 PULL 1-BKR-30-449 I DYES 1B1-B C/2B ON (1-FAN-30-449) STANDBY 1-HS-30-449C DNO DG 1B-B RM GEN/PNL VENT FAN DYES 1B1-B C/4D ON N/A 1-BKR-30-493 (1-FAN-30-493) DNO DG 1B-B ELEC BOARD ROOM EXH 1-BKR-30-461 I DYES 1B1-B C/4E ON P-AUTO FAN (1-FAN-30-461) 1-HS-30-461C DNO DG 1B-B ROOM EXH FAN 2 1-BKR-30-453 I DYES 1B2-B C/2B ON P-AUTO (1-FAN-30-453) 1-HS-30-453C DNO DG 2B-B ROOM EXH FAN 1 PULL 2-BKR-30-450 I DYES 2B1-B C/2B ON (2-FAN-30-450) STANDBY 2-HS-30-450C DNO DG 2B-B ROOM GEN/PNL VENT FAN DYES 2B1-B C/4D ON N/A 2-BKR-30-494 (2-FAN-30-494) DNO DG 2B-B ELEC BOARD ROOM EXH 2-BKR-30-462 I DYES 2B1-B C/4E ON P-AUTO FAN (2-FAN-30-462) 2-HS-30-462C DNO DG 2B-B RM EXH FAN 2 2-BKR-30-454 I DYES 2B2-B C/2B ON P-AUTO (2-FAN-30-454) 2-HS-30-454C DNO Initials indicate acc met OR action in Performer's SRO's "Ace not Met" column initiated. Initials Initials Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 36 of 39 Data Sheet 1 (Page 15 of 15)
Mode 3 Surveillance Log: 1900-0700
(
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Page 37 of 39 Data Sheet 2 (Page 1 of 1)
Inoperable Components Date- - - - 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-S/-0-2-00 are to be performed and attached to this package:
INOPERABLE COMPONENT 1-SI-0-2-00 DATA SHEET CST Level Data Sheet 3 0 Inoperable Ice Condenser Inlet Door Monitoring System Data Sheet 23 0 Inoperable Ice Bed Monitoring System Data Sheet 24 0 Inoperable Unit 1 Shield Building Stack Flow Monitor Data Sheet 37 0 Inoperable Diffuser Discharge Effluent Flow Monitor Data Sheet 38 0 Inoperable CVES Flow Monitor Data Sheet 45 0 Inoperable Auxiliary Building Stack Flow Monitor Data Sheet 51 0 Inoperable Liquid Radwaste Effluent Line Flow Monitor Data Sheet 55 0 Inoperable Condensate Demin Effluent Flow Monitor Data Sheet 58 0
( Inoperable SGBD to CTBD Flow Monitor Data Sheet 60 0 Inoperable Service Building Stack Flow Monitor Data Sheet 62 0 ICS Data Sheet 63 0 Out Of Limit Hourly Temperature Data Sheet 65 0 Periodic Temperature Check from DG Bldg Roof Data Sheet 66 0 INITIALS Remarks:
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0030
( Mode Three Pa_ge 38 of 39 Page 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 ilP TIS Limit (IN WC) FLOW ICS Point Y2203A ilP 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-O-2-00 to determine shield building flow.
2) If flow reading is between two values, use next higher flow value.
WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam A.3 RO/SRO Determine Potential Total Dose for Valve Alignment.
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PA~F 1 OF Q
WATTS BAR NUCLEAR PLANT A.3 RO/SRO Nov. 2009 NRC Exam EVALUATION SHEET Determine Potential Total Dose For Valve Alignment.
Alternate Path: NIA Facility JPM #: JPMRADMIN A.3 KIA Rating(s): 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2/3.7 Task Standard: 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-5.01-001 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
(
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.
(
PAr,F ~ OF q
WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD SAT/UNSAT
(
START TIME: _ __
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 thru all transit areas. Allowable values are
+0%, -10%.
STEP 1: Calculate exposure during transit thru the sample room and CRITICAL penetration room to the valve and return. STEP STANDARD: SAT Sample Room (500mr/hr)(0.5 min)(2)(hr/60min) =8.33 mr UNSAT Pen Room to STEP (0.5 in)(2)(120mr/hr)(hr/60min) =2 mr OFF PAD Hot Spot (45sec)(2)(min/60sec)2S00mr/hr)(hr/60min) =70 mr
(
Past BIT (3min)(2)(SOOmr/hr)(hr/60min) =80 mr Transit to valve (7min)(2)(325mr/hr)(hr/60min) =75.83 mr Operate valve (19min)(325mr/hr)(hr/60min) = 102.9 mr COMMENTS:
PAGE 4 OF 9
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 CRITICAL task. STEP STANDARD: SAT Individual doses received are added up. UNSAT 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 50F 9
WATTS BAR NUCLEAR PLANT A3 RO/SRO STEP/STANDARD SATIUNSAT STEP 3. Applicant calculates his/her total estimated exposure. CRITICAL STEP STANDARD:
SAT Total dose calculated in previous step is added to applicant's total dose for the year: ' UNSAT 715 mr (total dose to date) + 339 mr (minimum total dose for this job [-10%
margin]) = 1054 mrem.
Acceptable range of answer 1045 to 1065 mrem.
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 CRITICAL job is performed. Applicant notifies supervisor of findings, STEP stating that admin dose limit will be exceeded.
SAT STANDARD:
UNSAT 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
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 (SOOmr/hr)(O.S min)(2)(hr/60min) 2 mr back Pen Room to STEP (O.S in )(2)( 120mr/hr)(hr/60min) 8.33 mr or 8 mr OFF PAD and back Hot Spot and back (4Ssec)(2)(min/60sec)2800mr/hr)(hr/60min) 70 mr Past BIT and back (3min)(2)(800mr/hr)(hr/60min) 80 mr Transit to valve and (7min)(2)(32Smr/hr)(hr/60min) 75.83 mr or 76 mr back Operate valve ( 19min)(32Smr/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 70F 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.
(
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:
(
(
APPLICANT CUE SHEET
~(RETURN TO EXAMINER UPON COMPLETION OF TASK)
__
J -'.' . . , '
?
5 a..m pl c. I,OCl m vC.c ,.. ,:)a.m pIe. lZoom DOD ("
~ ~ 'M' ,,' I f .ut~ ~------o,. t_
500 mr/hr gen area E -.- _~'. .** .
tt::::;:;=:::::==-
j **
'lAO,......~
1000 mr/hr general area
120mr/hr
~genera[
...~
~ i s.o.P
'--_ _ _ _ _......... :::;:c::::::c::c::::!.;...i..--:....-.J
~:
.=c:::z::::::!.;,.J,,_:...-.1 *. _ _
l:
~:.* ...--------=-""T-~..-------~~~~--+
~----~~=-g~~~-----------
-.-__ -"'f2L::""'ra~_lI__----_:_~
s.o.P .......- - - - -..... ....
.... ~
~...'-'
~.~.~:----------~~-
-------.~-~~~--~
, Gro..n
325 mr/hr _______ ': 1:FCV-63-11 "
2800mr/hr
'l.f- Ct"\ lt66 mrihr Ii~~~t.*~~~~!~genrer_ala_re~a~~~ ~~"~~I!"~
o Hot Spot general area
~:
Boron j".i~/A .,
ran/(-->
~~~ .......-
~~~""-~
> :.~::::~ :': '. 0 2100 [J Yolu.me confrol td."1<
loop NO.4
PAGE1 OF 7 WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam A.4-SRO CLASSIFY THE EVENT AND DETERMINE PAR.
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PAGE 2 OF 7 WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam EVALUATION SHEET' Classify the Event and determine PAR.
Alternate Path: N/A Facility JPM #: New KIA Rating(s): 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)
Task Standard: 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 Classroom X Perform X Simulate
(
References:
EPIP-1 "Emergency Plan Classification Flowpath," Rev. 30; EPIP-5 "GENERAL EMERGENCY," Rev. 37 Task Number: SRO-113-EPIP-001 Applicable for: RO SRO X Validation Time: 15 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 3 OF 7 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.
(
(
PAGE 4 OF 7 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. AOI-6, "Small Reactor Coolant System Leak" has been implemented.
( 4. The operators are attempting to identify the source of the leak.
INITIATING CUES:
1. The US has informed you, the SED, of the leak.
2. The operators have not identified the leak source but, AOI-6 is in progress at this time.
3. Using the following parameters provided, classify the event according to the EPIPs and determine what, if any, Protective Action Recommendations are required.
a. PZR level is 58% and dropping at a rate of 0.5% per minute.
b. Charging flow is 140 gpm.
c. Letdown flow is 0 gpm.
d. Containment pressure is +0.2 psid and steady.
e. Containment Sump level is not increasing.
f. RHR Pipe Break White Lights have just illuminated.
g. Auxiliary Building Vent 0-RM-90-101 B is increasing.
h. Several Area Rad Monitors on EI 692 and 713 are in Hi Rad.
i. Chemistry reports a step rise in the RCS activity to 410 IJCi/gm dose
( equivalent Iodine 131.
PAGE 5 OF 7 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," Fission Product Barrier Matrix."
SAT Applicant determines that they have met the conditions of:
1.1.2 Loss, "RCS sample activity is greater than 300 J,JCi/gm dose equivalent 1131" UNSAT 1.2.2 Potential Loss, "Non Isolatable RCS leak exceeding the capacity of one charging 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.
NOTE TO EXAMINER:
RECORD time that declaration was made:- - - -
COMMENTS:
STEP 2: Refers to EPIP-5, "GENERAL EMERGENCY."
SAT STANDARD: EPIP-5, GENERAL EMERGENCY, is referred to for determining PAR.
UNSAT COMMENTS:
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PAGE 6 OF 7 WATTS BAR NUCLEAR PLANT A.4-1 SRO Nov. 2009 NRC Exam STEP 3: [STEP 1] IF the onsite emergency centers are not staffed, - SAT 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 - UNSAT 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: Per the INITIATING CUES, the applicant DOES NOT need to address this step.
COMMENTS:
STEP 4: [STEP 2] IF the TSC has not been activated, THEN CRITICAL
a. INITIATE Appendix A and B, Initial Notification Form for STEP GENERAL EMERGENCY and Protective Action Recommendations.
STANDARD: Applicant refers to Appendix A, and then accurately - SAT completes Appendix B by selecting RECOMMENDATION 2.
- UNSAT
. NOTE TO EVALUATOR: Underlined portion is the critical part.
CUE: Provide the applicant with the following data from the 46 meter MET TOWER: Wind speed is 10 mph from 180°.
COMMENTS:
i
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TIME STOP: _ __
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:
5. A Unit 1 shutdown was initiated prior to reaching the Tech Spec limit for RCS activity being elevated and increasing.
6. After starting the shutdown, indications of a primary system leak developed.
7. AOI-6, "Small Reactor Coolant System Leak" has been implemented.
8. The operators are attempting to identify the source of the leak.
INITIATING CUES:
( 4. The US has informed you, the SED, of the leak.
5. The operators have not identified the leak source but, AOI-6 is in progress at this time.
6. Using the following parameters provided, classify the event according to the EPIPs and determine what, if any, Protective Action Recommendations are required.
a. PZR level is 58% and dropping at a rate of 0.5% per minute.
b. Charging flow is 140 gpm.
c. Letdown flow is 0 gpm.
d. Containment pressure is +0.2 psid and steady.
e. Containment Sump level is not increasing.
f. RHR Pipe Break White Lights have j~st illuminated.
g. Auxiliary Building Vent 0-RM-90-1 01 B is increasing.
h. Several Area Rad Monitors on EI 692 and 713 are in Hi Rad.
i. Chemistry reports a step rise in the RCS activity to 410 J-ICilgm dose equivalent Iodine 131.
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rr======;J EPIP-I KBf Revision 31 Page 7 of 47 FISSION PRODUCT BARRIER MATRIX 1.1 Fuel Clad 1.2 1.3 RCS Containment 1 SYSTEM DEGRADATION 2.1 Loss of Instrumentation 2.6 RCS Identified Leakage 2.2
')
_.j 2.4
~
Loss of Function/Communication Failure of Reactor Protection Fuel Clad Degradation 2.7 2.8 2.9 Uncontrolled Cool Down Turbine Failure Technical Specification 2
2.5 RCS Unidentified Leakage 2.10 Safety Limit LOSS OF POWER 3.1 Loss of AC (Power Ops) 3.2 3.3 Loss of AC (Shutdown)
Loss of DC 3 HAZARDS and SED JUDGMENT 4.1 Fire 4.3 Flammable Gas 4.5 Control Room Evacuation
( 4.2 Explosion Table 4-1 Figure 4-A 4.4 Toxic Gas Table 4-2 Figure 4-8 4.6 4.7 Security SED Judgment Table 4-3 4
DESTRUCTIVE PHENOMENON 5.1 Earthquake 5.4 River Level High 5.2 5.3 Tornado Aircraft/Projectile Crash Table 5-1 5.5 5.6 River Level Low Watercraft Crash Figure 5-A 5
SHUTDOWN SYSTEM DEGRADATION 6.1 Loss of Shutdown Systems 6.2 6.3 Loss of AC (Shutdown)
Loss of DC (Shutdown) 6 RADIOLOGICAL 7.1 Gaseous Effluent 7.3 Radiation Levels 7.2 Liquid Effluent Table 7-1 Figure 7-A 7.4 Fuel Handling Table 7-2 7
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EPIP-I
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-OR-
-OR-RCS Leak results in Non Isolatable RCS Leak Loss of subcooling Exceeding The Capacity of
<<65°F Indicated), One Charging Pump (CCP)
[85°F ADVj In the Normal Charging Alignment.
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3. Steam Generator T-=u:..:::b:.:::e:....:R....:.u::.r:....::.::.:....:=---_
T-=u:..::b-=e.....:R....:.u:::.c....::.=..:....:=--_ _ _- I
-OR- LOSS SGTR that results in a Not Applicable
4. safety injection actuation
. LOSS OR Not Applicable VALID RVLlS level <33%
(No RCP running)
-OR-
5. Containment Radiation Monitors VALID RVLlS level Not Applicable LOSS <33%
VALID reading increase Not Applicable (No RCP Running) of Greater Than:
74 R/hr On 1-RE-90-271 -OR-and 272 OR 59 R/hr On 1-RE-90-273 and 274 instruction note 5. Site Eme Director Ju ment
-OR- Any condition that, in the Judgment of the SM/S~D, Indicates Loss or Potential Loss of the RCS Barner
6. Site Eme Director Ju ment Com Ie to the Conditions Listed Above.
Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the Fuel Clad Barrier Com arable to the Conditions Listed Above.
EPIP-1 EPIP-!
Revision 3! 31 Page9Bof47 Modes: 1, 2, 3, 4 INSTRUCTIONS F Not Applicable Containment (FR-Z.1) Red I NOTE A condition is considered to be MET if, in the OR S judgment of the Site Emergency Director, the Actions of FR-C.1 (Red Path) S condition will be MET imminently (i.e., within 1 to 2 are INEFFECTIVE (i.e.: core hours, in the absence of a viable success path)
TC TCs trendi The classification shall be made a soon as this 0 detenmination is made 1\
-OR-Containment Pressure/H Pressure/ en____________;
~~~~------------~
~-L~~~
1. In the matrix to the left, review the INITIATING p CONDITIONS in all columns and identify which, Potential L~~~ R if any, INITIATING CONDITIONS are MET.
Containment Hydrogen 0 Circle these CONDITIONS.
Increases to >4% by volume D OR U
2. For each of the three barriers, identify if any Pressure >2.8 PSIG (Phase C LOSS or Potential LOSS INITIATING B) with < One full train of CONDITIONS have been MET. T Containment s
3. If a CSF is listed as an INITIATING B
-OR- CONDITION; the respective status tree A
3. Containment Isolation Status criteria will be monitored and used to R r---------------------;
. LOSS p S determine the EVENT classification for the R
Modes listed on the classification flowchart.
Containment Isolation is Not Applicable I Incomplete (when required) E
( AND a Release Path to the
4. Compare the barrier losses and potential losses to the EVENTS below and make the R fimnmAnt Exists Environment appropriate declaration.
-OR- l\l
5. Containment Radiation Monitors are temperature A sensitive and can be affected by temperature T induced currents. Following a rapid increase or RUPTURED S/G is also Unexplained VALID increase R decrease in containment temperature, testing has FAULTED outside CNTMT in area or ventilation RAD shown rad monitors to give unreliable indication I
OR monitors in areas adjacent to for up to 2 minutes. X Prolonged (>4 Hours) CNTMT (with LOCA in Secondary Side release progress) U outside CNTMT from a S/G with a SGTL > TIS Limits EVENTS
-OR- UNUSUAL EVENT nificant Radioactivi~~~~~----------;
Loss or Potential LOSS of Any LOSS or Potential Containment Barrier LOSS of Fuel Clad barrier Not Applicable VALID Reading increase of Greater Than:
108 Rlhr on 1-RE-90-271 and 1-RE-90-272 Any LOSS or Potential LOSS of RCS barrier 86 Rlhr on 1-RE-90-273 and 1-RE-90-274 ee instruction note
-OR-
6. Site Emergency Director Judgment SITE AREA EMERGENCY Any condition that, in the Judgment of the SM/SED, Indicates
( Loss or Potential Loss of the CNTMT Barrier Comparable to LOSS or Potential LOSS of the Conditions Listed Above. any two barriers
(..E'f KEf Ke-I
~I---W--B-N--~-----G-E-N-E-R-A-L-E-M--ER-G-E-N-C-Y----~I-E--P-I-P---5~!
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APPENDIX A (P age 1 0 f 1)
TVA INITIAL NOTIFCATION FORM FOR GENERAL EMERGENCY
1. 0 This is a Drill o This is an Actual Event - Repeat - This is an Actual Event
2. This is ,
Watts Bar has declared a GENERAL EMERGENCY affecting Unit 1
3. EAL Designator(s): 1.1.2 L t 1.2.:2. PL. 1.3.Z.L-t
4. Brief Description of the Event: ~~ Ot.d-i.,ck c.o(\ta.~ V\4e..V1tr ~ruJu ~ +k-C4pa.,-~ hj l:> F c nt: ~~ h,~ ~s. ~If~ I-y (Dr U --\tll~
5. Radiological Conditions: (Check one under both Airborne and Liquid column.)
Airborne Releases Offsite Liguid Releases Offsite o Minor releases within federally approved limits 1
o Minor releases within federally approved limits 1
o Releases above federally approved limits 1
o Releases above federally approved limits 1
E Release information not known M.Release information not known
( 'Tech Specs) . ( 1Tech Specs)
6. Event Declared: Time: ~ON Date: Tod.c..y
7. The Meteorological Conditions are: (Use 46 meter data from the Met Tower)
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Wind Direction is FROM: leo degrees Wind Speed: LO m.p.h
8. Provide Protective Action Recommendation: (Check either 1, 2 or 3, and mark wind direction.)
o Recommendation 1
.EVACUATE LISTED SECTORS R WIND FROM 0 R ~Recommendation 2 E (Mark) E =>EVACUATE LISTED SECTORS (2 mile Radius and 10 miles downwind) (2 mile radius and 5 mile downwind)
C C
.SHELTER remainder of 10 mile EPZ. =>SHELTER remainder of 10 mile EPZ.
.CONSIDER issuance of Potassium Iodide in =>CONSIDER issuance of Potassium accordance with the State Plan. 1 2 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
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A-1, B-1, C-1, 0-1, 171-230 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 o Recommendation 3
.SHELTER 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 Date this information was provided. Time: ~O..N Date To~_
Action: When notification complete, FAX form as prescribed in this instruction.
Key PAGE 13 of 17 REVISION 37 Kef
Ke-j
( WBN GENERAL EMERGENCY I EPIP-si 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
Modify protective actions based on available
+-------------------~
plant and field monitoring information.
Locate and evaluate localized hot spots.
Is there a short term controlled release whereas near plant areas cannot be evacuated before plume arrival?
(see Note 2) At or beyond
( 5 miles, is the ~
YES Projected OR \. ~~
Measured Dose greate~ - - - ,
than Table 1 limits?
RECOMMENDATION 3 YES SHELTER 10 mile EPZ RECOMMENDATION 1 RECOMMENDATION 2 EVACUATE 2 miles radius EVACUATE 2 miles radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of SHELTER remainder of 10 mile EPZ 10 mile EPZ 1 1 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
EPIP-1 Revision 31 Page 7 of 47 FISSION PRODUCT BARRIER MATRIX (Modes 1-4) 1.1 Fuel Clad 1.2 1.3 RCS Containment 1 SYSTEM DEGRADATION 2.1 Loss of Instrumentation 2.6 RCS Identified Leakage 2.2 2.3 2.4 2.5 Loss of Function/Communication Failure of Reactor Protection Fuel Clad Degradation RCS Unidentified Leakage 2.7 2.8 2.9 2.10 Uncontrolled Cool Down Turbine Failure Technical Specification Safety Limit 2
LOSS OF POWER 3.1 Loss of A C (Power Ops) 3.2 3.3 Loss of AC (Shutdown)
Loss of DC 3 HAZARDS and SED JUDGMENT 4.1 Fire 4.3 Flammable Gas 4.5 Control Room Evacuation
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4.2 Explosion Table 4-1 Figure 4-A 4.4 Toxic Gas Table 4-2 Figure 4-3 4.6 4.7 Security SED Judgment Table 4-3 4
DESTRUCTIVE PHENOMENON 5.1 Earthquake 5.4 River Level High 5.2 5.3 Tornado Aircraft/Projectile Crash Table 5-1 5.5 5.6 River Level Low Watercraft Crash Figure 5-A 5
SHUTDOWN SYSTEM DEGRADATION 6.1 Loss of Shutdown Systems 6.2 6.3 Loss of AC (Shutdown)
Loss of DC (Shutdown) 6 RADIOLOGICAL 7.1 Gaseous Effluent 7.3 Radiation Levels 7.2 Liquid Effluent Table 7-1 Figure 7-A 7.4 Fuel Handling Table 7-2 7
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EPIP-I Revision 31
( Page 8 of 47 ODCM: Offsite Dose Calculation Manual.
UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY and OR<\NGE PATH: Monitoring of one or more CSFs by FR-O which indicates GENERAL EMERGENCY: (see SED Judgment 47).
that the CSF(s) is under severe challenge.
BOMB: An explosive device (See EXPLOSION).
PROJECTILE: An object ejected, thrown, or launched towards a plant CIVIL DISTURBANCE: A group of twenty (20) or more persons violently protesting station operations or activities at the site. structure. The source of the projectile may be onsite or offsite. Damage is CREDIBLE SITE-SPECIFIC -The determination is made by WBN sufficient to cause concem regarding the integrity of the affected structure or the senior plant management through use of information found in the operability or reliability of safety equipment contained therein.
Safeguards Contingency Plan. PROTECTED AREA: Encompasses all owner controlled areas within the CRITICAL-SAFETY FUNCTIO:-.I (CSFs): A plant safety function security protected area fence as shown on Figure 4-A.
required to prevent significant release of core radioactivity to the RED PATH: Monitoring of one or more CSFs by the FR-O which indicates environment. There are six CSFs: Sub-criticality, Core Cooling, Heat that the CSF(s) is under extreme challenge; prompt operator action is required.
Sink, Pressurized Thermal Shock, Integrity (Containment) and Inventory RUPTURED: (Steam Generator) Existence of primary to secondary leakage of a magnitude greater than chargmg pump capacity.
(RCS)
SABOTAGE: Deliberate damage, misalignment, or mis-operation of plant EVENT: Assessment of an EVENT commences when recognition is equipment with the intent to render the equipment inoperable.
made that one or more of the conditions associated with the event exist.
SIGNIFICAl'IT TRUiSIENT: An UNPLANNED event involving one or Implicit in this definition is the need for timely assessment, i.e. within 15 more of the following: (1) An automatic turbine run back > 15% thermal minutes.
reactor power; (2) Electrical load rejection> 25% full electrical load; (3)
EXCLUSION AREA BOUl'I'DARY (EAB): The demarcation of the Reactor Trip or (4) Safety Injection System Activation.
area surrounding the WBN units in which postulated FSAR accidents will SITE PERIMETER: Encompasses all owner controlled areas in the not result in population doses exceeding the criteria of 10 CFR Part 100.
immediate site environs as shown on Figures 4-Aand 7-A.
Refer to Figure 7-A.
STRIKE ACTION: A work stoppage within the PROTECTED AREA by a EXPLOSION: A rapid, violent, unconfined combustion, or a catastrophic body of workers to enforce compliance with demands made on TVA. The failure of pressurized equipment that imparts energy of sufficient force to STRlKE ACTION must threaten to interrupt normal plant operatIOns.
potentially damage permanent structures required for safe operation.
TOXIC GAS: A gas that is dangerous to life or limb by reason of inhalation or EXTORTION: An attempt to cause an action at the station by threat of skin contact (e.g., chlorine).
force.
UNPLANNED: An event or action that is not the expected result of normal FAULTED: (Steam Generator) Existence of secondary side leakage (i.e.,
operations, testing, or maintenance. Events that result in corrective or steam or feed line break) that results in an uncontrolled decrease in steam mitigative actions being taken in accordance with abnormal or emergency generator pressure or the steam generator being completely depressurized.
proc~dures procedures are UNPLANNED.
FIRE: Combustion characterized by heat and light. Source of smoke such UNPLANNED: (With specific regard to radioactivity releases) A release of as slipping drive belts or overheated electrical components do not constitute radioactivity is UNPLANNED if the release has not been authorized by a fires. Observation of flame is preferred but is NOT required if large Discharge Permit (DP). Implicit in this definition are unintentional releases, quantities of smoke and heat are observed.
unmonitored releases, or planned releases that exceed a conditIOn condition speCified specified on
( FLA~L'L\BLE GAS: Combustible gases maintained at concentrations less than the LOWER EXPLOSIVE LIMIT (LEL) will not explode due the DP, e.g., alarm setpoints, minimum dilution flow, minimum release times, maximum release rates, andlor discharge of incorrect tank.
tImes, to ignition.
VALID: An indication or report or condition is considered to be VALID when HOSTAGE: A person(s) held as leverage against the station to ensure it is conclusively verified by (I) an instrument channel check, or (2) indications that demands will be met by the station. on related or redundant indicators, or (3) by direct observation by plant HOSTILE ACTION: An act toward a nuclear power plant or its personnel. Implicit in this definition is the need for timely assessment, i.e.,
personnel that includes the use of violent force to destroy equipment, take within 15 minutes.
hostaaes, andlor intimidates the licensee to achieve an end. ThiS mcludes VISIBLE DAMAGE: Damage to equipment that is readily observable attack by air, land, or water; using guns, explosives, projectiles, vehicles, or without measurements, testing, or analyses. Damage is sufficient enough to other devices used to deliver destructive force. Other acts that satisfY the cause concern regarding the continued operability or reliability of affected overall intent may be included. HOSTILE ACTION should NOT be safety structure, system, or component. Example damage includes: .
construed to include acts of civil disobedience or felonious acts that are not deformation due to heat or impact, denting, penetration, rupture, cracking, part of a concerted attack on the nuclear power plant. Non-terrorism-based andlor paint blistering. Surface blemishes (e.g., paint chipping, scratches)
EALs should be used to address such activities, (e.g., violent acts between should NOT be included.
individuals in the owner controlled area.)
VITAL AREA: Is any area within the PROTECTED AREA which contains HOSTILE FORCE: Individual(s) involved with a HOSTILE ACTION. failure: destruction, or release of equipment, systems, devices, or material, the failure, One or more individuals who are engaged in a determined assault, overtly which could directly or indirectly endanger the public health and safety by or by stealth and deception, equipped with suitable weapons capable of exposure to radiation.
killing, maiming, or causing destruction.
Il'IEFFECTIVE: The specified restoration action(s) does not result in a reduction in the level of severity of the RED PATH condition within 15 minutes from identification of the Core Cooling CSF Status Tree RED PATH. A reduction in the level of severity is an improvement in the applicable parameters, e.g., Increasing Trend in Reactor Vessel Water Level (Full RVLIS) andlor Decreasing Trend on Core Thermocouple Temperatures.
I:-.IITIA TI:-.IG CONDITIONS: Plant Parameters, radiation monitor readings or personnel observations that identifY an Event for purposes of Emergency Plan Classification.
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I:\,TRUSION/INTRUDER: Suspected hostile individual present in a protected area without authorization.
EPIP-I Revision 31 Page 9A of47 Potentia Pressurized Thermal Shock Red (FR-P.1)
OR Heat Sink Red (FR-H.1)
RHR
-OR-
-OR-Level Potential L Potential LOSS RCS Leak results in Non Isolatable RCS Leak RCS sample activity is Loss of subcooling Exceeding The Capacity of Greater Than 300 ~Ci/gm Not applicable
. lent iodine-131 dose uivalent <<65°F Indicated), One Charging Pump (CCP)
[85°F ADVj In the Normal Charging Alignment.
-OR-OR RCS Leakage Results In Into E-1
-OR-( Stearn Generator Tube
3. Steam R Ru
-OR- ----~~~~~--~
r---~~~--------~
LOSS SGTR that results in a
4. safety injection actuation LOSS OR Not Applicable VALID RVLlS level <33% into E-3 (No RCP running)
-OR-
-OR- 4. Reactor Vessel Water Level

~~----------~

r---~r-~~~----~
LOSS
5. Containment Radiation Monitors VALID RVLlS level LOSS <33%
VALID reading increase Not Applicable (No RCP Running) of Greater Than:
74 R/hr On 1-RE-90-271 -OR-and 272 OR 59 R/hr On 1-RE-90-273 and 274
5. Site EmErne Director Ju Jud ment
-OR- Any condition that.
that, in the Judgment of the SM/SED Indicates Loss or Potential Loss of the RCS Barrier'
6. Site E Erne en Director Jud mentrnent Ie to the Conditions Listed Above.
ble An~
Any condition that, in the Judgment of the SM/SED, SM/SED Indicates Loss or Potential Loss of the Fuel Clad '
Barrier C rable to the Conditions Listed Above.
arable
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EPIP-!
Revision 31 Paae 98 of47 Modes: 1, 2, 3, 4 INSTRUCTIONS F Not Applicable Containment (FR-Z.1) Red I NOTE: A condition is considered to be MET if, in the OR S judgment of the Site Emergency Director, the Actions of FR-C.1 (Red Path) condition will be MET imminently (i.e, within 1 to 2 S are INEFFECTIVE (i.e.: core hours, in the absence of a viable success path ).
trendin TCs trendi The classification shall be made a soon as this 0 determination is made.
N
-OR-
2. Containment Press Pressu 1. In the matrix to the left, review the INITIATING p LOSS CONDITIONS in all columns and identify which, R if any, INITIATING CONDITIONS are MET.
Rapid unexplained decrease Containment Hydrogen 0 Circle these CONDITIONS.
following initial increase Increases to >4% by volume D OR OR U
2. For each of the three barriers, identify if any Containment pressure or Pressure >2.8 PSIG (Phase C LOSS or Potential LOSS INITIATING Sump level Not increasing B) with < One full train of T CONDITIONS have been MET.
Containment s
3. If a CSF is listed as an INITIATING B CONDITION; the respective status tree A
3. criteria will be monitored and used to R LOSS determine the EVENT classification for the R Modes listed on the classification flowchart.
Containment Isolation is I Incomplete (when required) E
4. Compare the barrier losses and potential
( AND.a Release Path to the ent nt Exists losses to the EVENTS below and make the appropriate declaration.
R M
5. Containment Radiation Monitors are temperature A sensitive and can be affected by temperature T induced currents. Following a rapid increase or RUPTURED S/G is also Unexplained VALID increase R decrease in containment temperature, testing has FAULTED outside CNTMT in area or ventilation RAD shown rad monitors to give unreliable indication I OR monitors in areas adjacent to for up to 2 minutes. X Prolonged (>4 Hours) CNTMT (with LOCA in Secondary Side release progress) U outside CNTMT from a S/G 1
with a SGTL > T/S Limits EVENTS
-OR- UNUSUAL EVENT nificant Radioacti in Containment
~-------------------; Any LOSS or Potential Loss Q!Potential LOSS of Potential LOSS Containment Barrier LOSS of Fuel Clad barrier Not Applicable VALID Reading increase of Greater Than:
108 R/hr on 1-RE-90-271 and 1-RE-90-272 Any LOSS Q! Potential LOSS of RCS barrier 86 Rlhr on 1-RE-90-273 and 1-RE-90-274 instruction note
-OR-
6. Site Emergency Director Judgment SITE AREA EMERGENCY GENERAL EMERGENCY Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the CNTMT Barrier Comparable to LOSS Q! Potential LOSS of LOSS of any two barriers the Conditions Listed Above. any two barriers and Potential LOSS of third barrier
WBN GENERAL EMERGENCY I EPIP-SI APPENDIX A (P age aJle 1 0 f 1)
TVA INITIAL NOTIFCATION FORM FOR GENERAL EMERGENCY
1. o This is a Drill o This is an Actual Event - Repeat - This is an Actual Event
2. This is ,
Watts Bar has declared a GENERAL EMERGENCY affecting Unit 1
3. EAL Designator(s):
4. Brief Description of the Event:
5. Radiological Conditions: (Check one under both Airborne and Liquid column.)
Airborne Releases Offsite Liquid Releases Offsite o Minor releases within federally approved limits 1
o Minor releases within federally approved limits 1
o Releases above federally approved limits 1
o Releases above federally approved limits 1
o Release information not known o Release information not known
( 1Tech Specs) ( 1Tech Specs)
6. Event Declared: Time: Date:
7. The Meteorological Conditions are: (Use 46 meter data from the Met Tower)
(
Wind Direction is FROM: degrees Wind Speed: m.p.h
8. Provide Protective Action Recommendation: (Check either 1, 2 or 3, and mark wind direction.)
o Recommendation 1
=>EVACUATE LISTED SECTORS R WIND FROM 0 R o Recommendation 2
=>EVACUATE LISTED SECTORS E (Mark) E (2 mile Radius and 10 miles downwind) (2 mile radius and 5 mile downwind)
C C
=>SHELTER remainder of 10 mile EPZ. =>SHELTER remainder of 10 mile EPZ.
=>CONSIDER issuance of Potassium Iodide in =>CONSIDER issuance of Potassium accordance with the State Plan. 1 2 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, D-2, -4, -5, -6, -7, -8, -9 C-7, D-2, -4, -5 A-1, B-1, C-1, 0-1,69-110 A-1, B-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 , B-1, C-1 , 0-1, 111-170 A-1, B-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, B-1, C-1, 0-1, 171-230 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, D-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, D-4,-9 C-2, -4, -5, -7, -8, D-4 o Recommendation 3
=>SHELTER 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 Date this information was provided. Time: Date
Action: When notification complete, FAX form as prescribed in this instruction.
PAGE 13 of 17 REVISION 37
WBN GENERAL EMERGENCY !I EPIP-SI 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
Modify protective actions based on available I+-------------------~
plant and field monitoring information.
Locate and evaluate localized hot spots.
Is there a short term controlled release whereas near NO plant areas cannot be evacuated before plume arrival?
(see Note 2) At or beyond 5 miles, is the
( YES Projected OR NO Measured Dose greater )-----,
than Table 1 limits?
RECOMMENDATION 3 SHELTER 10 mile EPZ RECOMMENDATION 1 RECOMMENDATION 2 1
EVACUATE 2 miles radius EVACUATE 2 miles radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of SHELTER remainder of 10 mile EPZ 10 mile EPZ 1 1 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

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