ML13158A033

05-Draft Operating Test

ML13158A033
Person / Time
Site:	Grand Gulf
Issue date:	05/16/2013
From:	Garchow S Operations Branch IV
To:	Entergy Operations
laura hurley
References
Download: ML13158A033 (298)

Text

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS1 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1AS1 JPM

Title:

Verify Surveillances Status for 03-1-01-5 Att. I Facility Number: N/A __________

(If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Applicant: ________________________________ Examiner: _________________________________

Performance Time: ________________________ Performance Rating: SAT UNSAT Comments:

Prepared By: Kyle Grillis 2/20/13 Exam Developer Date Ops Review: Robert Brinkman 3/21/2013 st 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Keith Huff / Dustin Hill 3/25/2013 nd 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 2/20/2013 Page 1 of 8

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS1 Verify Surveillances Status for 03-1-01-5 Att. I Setting: Classroom Type: SRO Task: SRO-NO-31 K&A: 2.1.25 (3.9/4.2), 2.1.36 (3.0/4.1), 2.1.40 (2.8/3.9), 2.1.42 (2.5/3.4)

Safety Function: Conduct of Operations Performance: Actual Reference(s): 03-1-01-5, Refueling Handout(s): 03-1-01-5 Att. I, page 1, partially completed and Exerpt from Surveillance Late Date Report sorted by procedure number

1. Manipulations: N/A

1. Critical Steps: 1 Simulator Setup/Required Plant Conditions:

• None Safety Concerns:

• None Task Standard(s):

• Reviews the surveillance Late Date Report sheets provided and identifies 06-OP-1T41-Q-0002 is late/not current.

Revision 0 2/20/2013 Page 2 of 8

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS1 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• Today is 5/09/2013.

• The plant is in Mode 5 for a scheduled refueling outage.

• Preparations are being made for Core Alterations.

• 03-1-01-5 Attachment I, page 1 has been turned over in progress from the previous shift.

Initiating Cue(s):

• You are the Control Room Supervisor. The Shift Manager has directed you to ensure the appropriate surveillance requirements on 03-1-01-5 Att. I, page 1 have been performed prior to performing Core Alterations, per 03-1-01-5 step 5.20. You do not need to recheck the items already completed by the previous shift.

REFER TO 03-1-01-5 ATT. I, PAGE 1 AND THE SURVEILLANCE LATE DATE REPORT SORTED BY PROCEDURE NUMBER, PROVIDED.

Revision 0 2/20/2013 Page 3 of 8

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS1 Verify Surveillance Status for 03-1-01-5 Att. I Notes: (Notes to Evaluator)

• Refer to the Evaluator Copy of the Surveillance Late Date Report sorted by procedure number, but DO NOT allow student to see it.

Task Overview: (Detailed description of task)

• This task is to perform the SRO review of the Surveillance Late Date Report to determine whether surveillances required during Core Alterations are current. One surveillance on the list of surveillances to be verified is past its Tech Spec late date and is, therefore, not current Revision 0 2/20/2013 Page 4 of 8

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS1 Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 03-1-01-5 Att. I, page 1

• Reviews the Surveillance Late Date Report to determine whether surveillances listed on 03-1-01-5 Att. I, page 1 are current or are past their Tech Spec late date.

Standard:

• Reviews the surveillance Late Date Report sheets provided and determines all listed surveillances except 06-OP-1T41-Q-0002 are current by initialing beside them on 03-1-01-5 Att. I, page 1 but does not initial beside 06-OP-1T41-Q-0002.

• Student identifies surveillance 06-OP-1T41-Q-0002-01 as LATE/not current.

Cue: Once the student identifies 06-OP-1T41-Q-0002 is late, if asked how to proceed, tell the student to complete 03-1-01-5 Att. I, signing for all surveillances that are current.

Notes: 06-OP-1T41-Q-0002-01, which satisfies quarterly testing requirements, is a distinct surveillance from 06-OP-1T41-Q-0002-02, which is scheduled only to meet 18 month/2 year requirements. Just because 06-OP-1T41-Q-0002-02 is current on the late Date Report provided, it does not mean the quarterly requirements of 06-OP-1T41-Q-0002-01 are current. The requirement represented by 06-OP-1T41-Q-0002 listed on 03-1-01-5 Att. 1, page 1 is that all requirements of 06-OP-1T41-Q-0002, both attachments -01 and -02 are current.

Another surveillance, 06-OP-1T42-Q-0001-01 has exceeded the conservative late date imposed by the surveillance scheduling program (IAS), but is within the Tech Spec late date and is not late. If the student identifies this surveillance as late (not current), this is not critical and does not constitute failure of the JPM.

SAT / UNSAT Revision 0 2/20/2013 Page 5 of 8

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS1 Task Standard(s):

• Reviews the surveillance Late Date Report sheets provided and identifies 06-OP-1T41-Q-0002 is late/not current.

SAT / UNSAT Remember to record stop time Revision 0 2/20/2013 Page 6 of 8

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS1 Follow-Up Questions & Answers:

Comments:

Revision 0 2/20/2013 Page 7 of 8

Give this page to the student Initial Condition(s):

• Today is 5/09/2013.

• The plant is in Mode 5 for a scheduled refueling outage.

• Preparations are being made for Core Alterations.

• 03-1-01-5 Attachment I, page 1 has been turned over in progress from the previous shift.

Initiating Cue(s):

• You are the Control Room Supervisor. The Shift Manager has directed you to ensure the appropriate surveillance requirements on 03-1-01-5 Att. I, page 1 have been performed prior to performing Core Alterations, per 03-1-01-5 step 5.20. You do not need to recheck the items already completed by the previous shift.

REFER TO 03-1-01-5 ATT. I, PAGE 1 AND THE SURVEILLANCE LATE DATE REPORT SORTED BY PROCEDURE NUMBER, PROVIDED.

All Surveillances ~~~ Sorted by Procedure Number / Late Date ~~~ Wednesday, May 8, 2013 11:17

$$ Dollar Signs denotes Surveillances which have exceeded the NRC Late Date PMRQ # /

WO # / LAST DUE LATE MODE APPL.

FREQ DAYS PROCEDURE / DESCRIPTION STATUS PERFORMED DATES DATES COMMENTS 50019995-01 52465491 02/15/2013 01 15 05/25/2013 06/01/2013 EVALUATOR 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 05/25/2013 06/02/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019995-01 52467128 02/15/2013 01 15 06/07/2013 06/14/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER COPY - **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/07/2013 06/15/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019995-01 52468745 02/15/2013 01 15 06/14/2013 06/21/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/14/2013 06/22/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

DO NOT GIVE TO 50019995-01 52470351 02/15/2013 01 15 06/21/2013 06/28/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/21/2013 06/29/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

STUDENT 50019995-01 52471845 02/15/2013 01 15 06/28/2013 07/05/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/28/2013 07/06/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019996-01 52469217 05/04/2013 15 30 06/04/2013 06/11/2013 06OP1R21-M-0002-01 DIV 1 LOAD SHEDDING & SEQUENCING **MODE APPL. = 1, 2, 3, 4, 5, *,

28 ACTIVE TECH SPEC DATE/TIME = 06/06/2013 06/14/2013 0330 FUNCTIONAL TEST. USE ATTACHMENT 1.

50019998-01 52472103 04/13/2013 02 51 05/13/2013 05/20/2013 06OP1R21-M-0002-02 DIV 2 LOAD SHEDDING & SEQUENCING **MODE APPL. = 1, 2, 3, 4, 5, *,

28 ACTIVE TECH SPEC DATE/TIME = 05/15/2013 05/22/2013 1451 FUNCTIONAL TEST. USE ATTACHMENT 2.

50019999-01 52400916 02/19/2012 22 00 08/21/2013 01/05/2014 06OP1R21-R-0001 ESF DIVISION 3 POWER SUPPLY **MODE APPL. = 1, 2, 3, 4, 5, *,

549 ACTIVE TECH SPEC DATE/TIME = 08/21/2013 01/06/2014 0400 FUNCTIONAL TEST 50020000-01 52400917 02/19/2012 21 00 08/21/2013 01/05/2014 06OP1R21-R-0002 ESF DIVISION 2 POWER SUPPLY **MODE APPL. = 1, 2, 3, 4, 5, *,

549 ACTIVE TECH SPEC DATE/TIME = 08/21/2013 01/06/2014 0300 FUNCTIONAL TEST Current date is past TECH SPEC 50020001-01 52400918 02/19/2012 21 40 08/21/2013 01/05/2014 DIVISION 06OP1R21-R-0003 ESF Late 1 POWER Date, SUPPLY surveillance is LATE **MODE APPL. = 1, 2, 3, 4, 5, *,

549 ACTIVE TECH SPEC DATE/TIME = 08/21/2013 01/06/2014 0340 FUNCTIONAL TEST 50020002-01 52466843 04/25/2013 03 00 05/22/2013 06/01/2013 06OP1T10-M-0001 SECONDARY CONTAINMENT **MODE APPL. = 1, 2, 3, *, , ,

28 ACTIVE TECH SPEC DATE/TIME = 05/24/2013 06/03/2013 1500 PENETRATION ISOLATION MONTHLY CHECK

$$ 00012304-01 52464559 01/13/2013 04 58 04/07/2013 04/28/2013 06OP1T41-Q-0002-01 AUX. BLDG. VENT. SYS. VALVE TEST; **MODE APPL. = 1, 2, 3, 4, , ,

84 ACTIVE TECH SPEC DATE/TIME = 04/14/2013 05/06/2013 2258 USE ATT. 1 UPDATED BY PMRQ 50020004-01, ATT 2 00012305-01 52464543 01/13/2013 04 58 07/07/2014 01/01/2015 06OP1T41-Q-0002-02 AUX. BLDG. VENT. SYS. VALVE TEST; **MODE APPL. = 1, 2, 3, 4, , ,

540 ACTIVE TECH SPEC DATE/TIME = 07/07/2014 11/19/2014 0458 18 MON UPDATES ATT 1, PMRQ 00012304-Upper date is the Indus Asset Suite late01date used for scheduling

$$ 50020005-01 52465748 01/19/2013 18 21 04/13/2013 05/04/2013 06OP1T42-Q-0001-01 FHA VENT. SYSTEM FUNCTIONAL TEST. **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 04/20/2013 05/13/2013 1221 UPDATED BY PMRQ 50020008-01 50020008-01 52465734 01/19/2013 18 21 07/13/2014 01/07/2015 06OP1T42-Q-0001-02 FHA VENT. SYSTEM FUNCTIONAL TEST. **MODE APPL. = 1, 2, 3, 4, 5, ,

540 ACTIVE TECH SPEC DATE/TIME = 07/13/2014 11/25/2014 1821 UPDATES PMRQ 50020005-01 50020009-01 52470798 05/07/2013 13 55 06/04/2013 06/11/2013 06OP1T48-M-0001 STANDYBY GAS TREATMENT SYSTEM 'A' **MODE APPL. = 1, 2, 3, *, , ,

28 ACTIVE TECH SPEC DATE/TIME = 06/09/2013 06/17/2013 0155 10 HOUR RUN UPDATED BY PMRQ 50018741-01 OR PMRQ 50018739-01 Lower date is the actual Tech Spec late date used for Tech Spec compliance / operability. This surveillance is past the conservative scheduling late date, but is within the Tech

• • 1-POWER OPS; 2- STARTUP; 3-HOT SHUTDOWN; 4-COLD SHUTDOWN; 5-REFUEL; 6-CONTROL WITHDRAWN Page 135 of 144 SpecRODS allowed late date, so it is current.

7,8,9 IDENTIFIED B *ASTERISK : 7-CORE ALTERATIONS; 8-POTENTIAL FOR DRAINNG VESSEL; 9-HANDLING IRRADIATED FUEL

All Surveillances ~~~ Sorted by Procedure Number / Late Date ~~~ Wednesday, May 8, 2013 11:17

$$ Dollar Signs denotes Surveillances which have exceeded the NRC Late Date PMRQ # / WO # / LAST DUE LATE MODE APPL.

PROCEDURE / DESCRIPTION FREQ DAYS STATUS PERFORMED DATES DATES COMMENTS 50020010-01 52469218 05/03/2013 17 13 06/02/2013 06/09/2013 06OP1T48-M-0002 STANDYBY GAS TREATMENT SYSTEM 'B' EVALUATOR **MODE APPL. = 1, 2, 3, *, , ,

28 ACTIVE TECH SPEC DATE/TIME = 06/03/2013 06/12/2013 0513 10 HOUR RUN UPDATED BY PMRQ 50018738-01, 06OP1T48-Q-0003-02 and 50018740-01, 06OP1T48-Q-0003-01 50020011-01 52464592 04/11/2013 09 34 05/09/2013 05/16/2013 COPY -

06OP1T48-M-0003 SECONDARY CONTAINMENT INTEGRITY **MODE APPL. = 1, 2, 3, *, , ,

28 AWAIT/C TECH SPEC DATE/TIME = 05/12/2013 05/20/2013 2134 CHECK 50018741-01 52470787 02/07/2013 13 55 05/02/2013 05/23/2013 DO NOT GIVE TO 06OP1T48-Q-0002-01 SBGT "A" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 05/09/2013 06/01/2013 0755 UPDATES PMRQ 50020009-01.

UPDATED BY ATT. 2, PMRQ STUDENT 50018739-01.

50018739-01 52458375 12/07/2012 12 10 05/31/2014 10/13/2014 06OP1T48-Q-0002-02 SBGT "A" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

540 ACTIVE TECH SPEC DATE/TIME = 05/31/2014 10/13/2014 1210 UPDATES PMRQ 50020009-01 &

ATT 1, PMRQ 50018741-01 50018740-01 52462961 04/06/2013 04 00 07/01/2013 07/22/2013 06OP1T48-Q-0003-01 SBGT "B" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 07/07/2013 07/29/2013 2200 UPDATES PMRQ 50020010-01, 06OP1T48-M-0002 50018738-01 52462953 01/06/2013 04 00 06/30/2014 12/25/2014 06OP1T48-Q-0003-02 SBGT "B" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

540 ACTIVE TECH SPEC DATE/TIME = 06/30/2014 11/12/2014 0400 UPDATES PMRQ 50020010-01 50020014-01 52404679 03/05/2012 02 44 09/05/2013 01/20/2014 06OP1T48-R-0002-01 SBGT 'A' LOGIC TEST USE **MODE APPL. = 1, 2, 3, *, , ,

549 ACTIVE TECH SPEC DATE/TIME = 09/05/2013 01/20/2014 0844 ATTACHMENT 1 50020015-01 52364484 03/20/2011 15 44 08/14/2013 12/23/2013 06OP1T48-R-0002-02 SBGT 'A' VACUUM TEST; **WC43 - SCH **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 08/22/2013 01/05/2014 1544 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-02 WC43 - Perform Attachment 2 (50020019-01) eighteen months from performance of attachment 3 on a rotating basis.-

SCH 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-02 (50020019-01) 50020016-01 52283510 06/05/2012 11 52 11/26/2013 04/06/2014 06OP1T48-R-0002-03 SBGT 'A' VACUUM TEST; **WC43 - SCH **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 11/26/2013 04/10/2014 1152 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-03 WC43 - Perform Attachment 3 (50020020-01 eighteen months from performance of attachment 2 on a rotating basis.-

SCH 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-03 (50020020-01 50020018-01 52404680 03/05/2012 23 45 09/05/2013 01/20/2014 06OP1T48-R-0003-01 SBGT 'B' LOGIC TEST; USE **MODE APPL. = 1, 2, 3, *, , ,

549 ACTIVE TECH SPEC DATE/TIME = 09/05/2013 01/21/2014 0545 ATTACHMENT 1 50020019-01 52409813 03/20/2011 02 30 03/19/2014 08/02/2014 06OP1T48-R-0003-02 SBGT 'B' VACUUM TEST; USE **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 03/20/2014 08/04/2014 0230 ATTACHMENT 2. DRAWDOWN TESTING WITH AUX BLDG WC43 - Perform Attachment 2 RAILROAD BAY DOORS 1A310/1A312 CLOSED, RAILROAD eighteen months from performance of BAY CEILING HATCHES INSTALLED, AND RAILROAD BAY attachment 3 on a rotating basis.SCH DOOR 1A319A (EXTERIOR DOOR)OPEN 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0002-02 (50020015-01)

• • 1-POWER OPS; 2- STARTUP; 3-HOT SHUTDOWN; 4-COLD SHUTDOWN; 5-REFUEL; 6-CONTROL RODS WITHDRAWN Page 136 of 144 7,8,9 IDENTIFIED B *ASTERISK : 7-CORE ALTERATIONS; 8-POTENTIAL FOR DRAINNG VESSEL; 9-HANDLING IRRADIATED FUEL

All Surveillances ~~~ Sorted by Procedure Number / Late Date ~~~ Wednesday, May 8, 2013 11:17

$$ Dollar Signs denotes Surveillances which have exceeded the NRC Late Date PMRQ # / WO # / LAST DUE LATE MODE APPL.

PROCEDURE / DESCRIPTION FREQ DAYS STATUS PERFORMED DATES DATES COMMENTS 50020020-01 52423363 06/05/2012 11 52 06/05/2015 10/05/2015 06OP1T48-R-0003-03 SBGT 'B' VACUUM TEST; USE **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 06/05/2015 10/20/2015 1152 ATTACHMENT 3. DRAWDOWN TEST WITH RAILROAD BAY EVALUATOR WC43 - Perform Attachment 3 DOOR 1A319A(EXTERIOR DOOR)CLOSED AND DOORS 1A310 eighteen months from performance of AND 1A312 OPEN. attachment 2 on a rotating basis.-

COPY - .SCH 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0002-03 (50020016-01) 50020021-01 52458383 02/07/2013 17 30 05/01/2013 05/22/2013 06OP1Z51-Q-0001-01 CONTROL ROOM HVAC SYSTEM VALVE DO NOT GIVE TO **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 05/08/2013 05/31/2013 1130 TEST. USE ATTACHMENT 1. UPDATED BY PMRQ 50020022-01 UPDATED BY 06OP1Z51-Q-0001-02, PMRQ 50020022-01.

50020022-01 52354499 07/14/2011 03 45 01/04/2013 07/01/2013 06OP1Z51-Q-0001-02 CONTROL ROOM HVAC SYSTEM STUDENT **MODE APPL. = 1, 2, 3, *, , ,

540 ACTIVE TECH SPEC DATE/TIME = 01/04/2013 05/19/2013 0345 VALVE TEST. USE ATTACHMENT 2. UPDATES PMRQ UPDATES PMRQ 50020021-01 50020021-01 50019642-01 52464553 04/10/2013 17 30 07/04/2013 07/25/2013 06OPSC85-Q-0001 SEISMIC MONITORING SYSTEM **MODE APPL. = 1, 2, 3, 4, 5, ,

84 ACTIVE TECH SPEC DATE/TIME = 0711/2013 08/04/2013 1130 FUNCTIONAL TEST 50019643-01 52456127 03/22/2012 22 35 06/14/2013 07/07/2013 06OPSD17-Q-0008 RADWASTE BLDG VENT RAD MONITOR **MODE APPL. = 1, 2, 3, 4, 5, ,

84 ACTIVE TECH SPEC DATE/TIME = 06/21/2013 07/16/2013 1635 FUNCT. TEST 50019644-01 52465037 01/17/2013 12 27 04/11/2013 05/02/2013 06OPSD17-Q-0018 LIQUID RADWASTE EFFLUENT RADIATION **MODE APPL. = 1, 2, 3, 4, 5, ,

84 ACTIVE TECH SPEC DATE/TIME = 04/18/2013 05/11/2013 0627 MONITOR FUNCTIONAL TEST 50019645-01 52470781 02/10/2013 21 45 05/05/2013 05/26/2013 06OPSP21-Q-0001-01 MAKEUP WATER TREATMENT **MODE APPL. = 1, 2, 3, , , ,

84 ACTIVE TECH SPEC DATE/TIME = 05/12/2013 06/04/2013 1545 QUARTERLY VALVE TEST. USE ATTACHMENT 1 UPDATED BY PMRQ 50019646-01, 06OPSP21-Q-0001-02 50019646-01 52453797 11/12/2012 02 46 05/06/2014 10/31/2014 06OPSP21-Q-0001-02 MAKEUP WATER TREATMENT **MODE APPL. = 1, 2, 3, , , ,

540 ACTIVE TECH SPEC DATE/TIME = 05/06/2014 09/18/2014 0246 QUARTERLY VALVE TEST. 18 MONTH; 6 MONTH GRACE UPDATES PMRQ 50019645-01, 06OPSP21-Q-0001-01 50019647-01 52395431 08/19/2012 06 31 08/19/2013 11/17/2013 06OPSP64-A-0004 FIRE PROTECTION SYSTEM VALVE **MODE APPL. = 1, 2, 3, 4, 5, ,

292 ACTIVE TECH SPEC DATE/TIME = 08/19/2013 11/19/2013 0631 STROKE TEST.

50019653-01 52402981 05/28/2012 14 00 03/16/2013 05/28/2013 06OPSP64-A-0012 ANNUAL YARD FIRE HYDRANT FLOW **MODE APPL. = 1, 2, 3, 4, 5, ,

292 ACTIVE TECH SPEC DATE/TIME = 03/16/2013 05/28/2013 1400 CHECK 50019656-01 52413147 07/08/2012 05 44 04/26/2013 07/08/2013 06OPSP64-A-0046 FIRE PUMPS LOW PRESSURE START **MODE APPL. = ,,,,,,

292 ACTIVE TECH SPEC DATE/TIME = 04/26/2013 07/08/2013 0544 FUNCTIONAL TEST 50018545-01 52470797 04/18/2013 07 00 05/16/2013 05/23/2013 06OPSP64-M-0001-01 FIRE PUMP C003A MONTHLY **MODE APPL. = 1, 2, 3, 4, 5, ,

28 ACTIVE TECH SPEC DATE/TIME = 05/19/2013 05/24/2013 1900 OPERABILITY TEST *ATT 1* USE ATTACHMENT 1 50018545-02 52470799 04/18/2013 07 00 05/16/2013 05/23/2013 06OPSP64-M-0001-02 FIRE PUMP C003B MONTHLY **MODE APPL. = 1, 2, 3, 4, 5, ,

28 ACTIVE TECH SPEC DATE/TIME = 05/19/2013 05/24/2013 1900 OPERABILITY TEST *ATT 2* USE ATTACHMENT 2 50018545-03 52470796 04/18/2013 07 00 05/16/2013 05/23/2013 06OPSP64-M-0001-03 MOTOR DRIVEN FIRE PUMP C002 **MODE APPL. = 1, 2, 3, 4, 5, ,

28 ACTIVE TECH SPEC DATE/TIME = 05/19/2013 05/24/2013 1900 OPERABILITY *ATT 3* USE ATTACHMENT 3 50019658-01 52466841 04/28/2013 14 32 05/26/2013 06/02/2013 06OPSP64-M-0011 FIRE PROTECTION SYSTEM VALVE **MODE APPL. = 1, 2, 3, 4, 5, ,

• • 1-POWER OPS; 2- STARTUP; 3-HOT SHUTDOWN; 4-COLD SHUTDOWN; 5-REFUEL; 6-CONTROL RODS WITHDRAWN Page 137 of 144 7,8,9 IDENTIFIED B *ASTERISK : 7-CORE ALTERATIONS; 8-POTENTIAL FOR DRAINNG VESSEL; 9-HANDLING IRRADIATED FUEL

GRAND GULF NUCLEAR STATION INTEGRATED OPERATING INSTRUCTION 03-1-01-5 Revision: 127 Attachment I Page 1 of 4 BEFORE AND DURING CORE ALTERATIONS The following is a list of surveillance requirements that Must be current before AND during core alterations. This list is in addition to the list for Mode 5 contained in Attachment VII. REFER to Table 1 for those valves that require tracking for operability during Core Alts.

Surveillances that are required for Primary AND Secondary Containment valve operability, Secondary Containment AND SBGT May NOT be required current IF the plant has NOT been critical in past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 06-OP-1T10-M-0001 FW 5/9/13 06-OP-1T48-R-0002 FW 5/9/13 06-OP-1T48-M-0003 FW 5/9/13 06-OP-1G33-Q-0001 FW 5/9/13 06-OP-1B21-R-0006 FW 5/9/13 06-OP-1G41-Q-0001 FW 5/9/13 06-OP-1B21-C-0003

• FW 5/9/13 06-OP-1M41-Q-0001 FW 5/9/13 06-OP-SP21-Q-0001 FW 5/9/13 06-OP-1P11-Q-0001 FW 5/9/13 06-OP-1P45-C-0001

• FW 5/9/13 06-OP-1P52-Q-0001 FW 5/9/13 06-OP-1P45-Q-0002 FW 5/9/13 06-OP-1T41-Q-0002 06-OP-1P60-Q-0001 FW 5/9/13 06-OP-1T42-Q-0001 06-OP-SP66-Q-0001 FW 5/9/13 06-OP-1T48-M-0001 06-OP-1P71-Q-0001 FW 5/9/13 06-OP-1T48-M-0002 06-OP-1E12-Q-0005 FW 5/9/13 06-OP-1T48-R-0003 06-OP-1T48-Q-0002 06-OP-1T48-Q-0003

• Cold shutdown surveillances are current until 90 days after entering Mode 4.

J:\ADM_SRVS\TECH_PUB\REVISION\03\31015.doc

All Surveillances ~~~ Sorted by Procedure Number / Late Date ~~~ Wednesday, May 8, 2013 11:17

$$ Dollar Signs denotes Surveillances which have exceeded the NRC Late Date PMRQ # / WO # / LAST DUE LATE MODE APPL.

PROCEDURE / DESCRIPTION FREQ DAYS STATUS PERFORMED DATES DATES COMMENTS 50019995-01 52465491 02/15/2013 01 15 05/25/2013 06/01/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 05/25/2013 06/02/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019995-01 52467128 02/15/2013 01 15 06/07/2013 06/14/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/07/2013 06/15/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019995-01 52468745 02/15/2013 01 15 06/14/2013 06/21/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/14/2013 06/22/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019995-01 52470351 02/15/2013 01 15 06/21/2013 06/28/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/21/2013 06/29/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019995-01 52471845 02/15/2013 01 15 06/28/2013 07/05/2013 06OP1R20-W-0001-01 PLANT AC & DC ELECTRICAL POWER **MODE APPL. = 1, 2, 3, 4, 5, *,

7 ACTIVE TECH SPEC DATE/TIME = 06/28/2013 07/06/2013 1915 DISTRIBUTION WEEKLY LINEUP; USE ATTACHMENT 1.

50019996-01 52469217 05/04/2013 15 30 06/04/2013 06/11/2013 06OP1R21-M-0002-01 DIV 1 LOAD SHEDDING & SEQUENCING **MODE APPL. = 1, 2, 3, 4, 5, *,

28 ACTIVE TECH SPEC DATE/TIME = 06/06/2013 06/14/2013 0330 FUNCTIONAL TEST. USE ATTACHMENT 1.

50019998-01 52472103 04/13/2013 02 51 05/13/2013 05/20/2013 06OP1R21-M-0002-02 DIV 2 LOAD SHEDDING & SEQUENCING **MODE APPL. = 1, 2, 3, 4, 5, *,

28 ACTIVE TECH SPEC DATE/TIME = 05/15/2013 05/22/2013 1451 FUNCTIONAL TEST. USE ATTACHMENT 2.

50019999-01 52400916 02/19/2012 22 00 08/21/2013 01/05/2014 06OP1R21-R-0001 ESF DIVISION 3 POWER SUPPLY **MODE APPL. = 1, 2, 3, 4, 5, *,

549 ACTIVE TECH SPEC DATE/TIME = 08/21/2013 01/06/2014 0400 FUNCTIONAL TEST 50020000-01 52400917 02/19/2012 21 00 08/21/2013 01/05/2014 06OP1R21-R-0002 ESF DIVISION 2 POWER SUPPLY **MODE APPL. = 1, 2, 3, 4, 5, *,

549 ACTIVE TECH SPEC DATE/TIME = 08/21/2013 01/06/2014 0300 FUNCTIONAL TEST 50020001-01 52400918 02/19/2012 21 40 08/21/2013 01/05/2014 06OP1R21-R-0003 ESF DIVISION 1 POWER SUPPLY **MODE APPL. = 1, 2, 3, 4, 5, *,

549 ACTIVE TECH SPEC DATE/TIME = 08/21/2013 01/06/2014 0340 FUNCTIONAL TEST 50020002-01 52466843 04/25/2013 03 00 05/22/2013 06/01/2013 06OP1T10-M-0001 SECONDARY CONTAINMENT **MODE APPL. = 1, 2, 3, *, , ,

28 ACTIVE TECH SPEC DATE/TIME = 05/24/2013 06/03/2013 1500 PENETRATION ISOLATION MONTHLY CHECK

$$ 00012304-01 52464559 01/13/2013 04 58 04/07/2013 04/28/2013 06OP1T41-Q-0002-01 AUX. BLDG. VENT. SYS. VALVE TEST; **MODE APPL. = 1, 2, 3, 4, , ,

84 ACTIVE TECH SPEC DATE/TIME = 04/14/2013 05/06/2013 2258 USE ATT. 1 UPDATED BY PMRQ 50020004-01, ATT 2 00012305-01 52464543 01/13/2013 04 58 07/07/2014 01/01/2015 06OP1T41-Q-0002-02 AUX. BLDG. VENT. SYS. VALVE TEST; **MODE APPL. = 1, 2, 3, 4, , ,

540 ACTIVE TECH SPEC DATE/TIME = 07/07/2014 11/19/2014 0458 18 MON UPDATES ATT 1, PMRQ 00012304-01

$$ 50020005-01 52465748 01/19/2013 18 21 04/13/2013 05/04/2013 06OP1T42-Q-0001-01 FHA VENT. SYSTEM FUNCTIONAL TEST. **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 04/20/2013 05/13/2013 1221 UPDATED BY PMRQ 50020008-01 50020008-01 52465734 01/19/2013 18 21 07/13/2014 01/07/2015 06OP1T42-Q-0001-02 FHA VENT. SYSTEM FUNCTIONAL TEST. **MODE APPL. = 1, 2, 3, 4, 5, ,

540 ACTIVE TECH SPEC DATE/TIME = 07/13/2014 11/25/2014 1821 UPDATES PMRQ 50020005-01 50020009-01 52470798 05/07/2013 13 55 06/04/2013 06/11/2013 06OP1T48-M-0001 STANDYBY GAS TREATMENT SYSTEM 'A' **MODE APPL. = 1, 2, 3, *, , ,

28 ACTIVE TECH SPEC DATE/TIME = 06/09/2013 06/17/2013 0155 10 HOUR RUN UPDATED BY PMRQ 50018741-01 OR PMRQ 50018739-01

• • 1-POWER OPS; 2- STARTUP; 3-HOT SHUTDOWN; 4-COLD SHUTDOWN; 5-REFUEL; 6-CONTROL RODS WITHDRAWN Page 135 of 144 7,8,9 IDENTIFIED BY *ASTERISK : 7-CORE ALTERATIONS; 8-POTENTIAL FOR DRAINING VESSEL; 9-HANDLING IRRADIATED FUEL

All Surveillances ~~~ Sorted by Procedure Number / Late Date ~~~ Wednesday, May 8, 2013 11:17

$$ Dollar Signs denotes Surveillances which have exceeded the NRC Late Date PMRQ # / WO # / LAST DUE LATE MODE APPL.

PROCEDURE / DESCRIPTION FREQ DAYS STATUS PERFORMED DATES DATES COMMENTS 50020010-01 52469218 05/03/2013 17 13 06/02/2013 06/09/2013 06OP1T48-M-0002 STANDYBY GAS TREATMENT SYSTEM 'B' **MODE APPL. = 1, 2, 3, *, , ,

28 ACTIVE TECH SPEC DATE/TIME = 06/03/2013 06/12/2013 0513 10 HOUR RUN UPDATED BY PMRQ 50018738-01, 06OP1T48-Q-0003-02 and 50018740-01, 06OP1T48-Q-0003-01 50020011-01 52464592 04/11/2013 09 34 05/09/2013 05/16/2013 06OP1T48-M-0003 SECONDARY CONTAINMENT INTEGRITY **MODE APPL. = 1, 2, 3, *, , ,

28 AWAIT/C TECH SPEC DATE/TIME = 05/12/2013 05/20/2013 2134 CHECK 50018741-01 52470787 02/07/2013 13 55 05/02/2013 05/23/2013 06OP1T48-Q-0002-01 SBGT "A" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 05/09/2013 06/01/2013 0755 UPDATES PMRQ 50020009-01.

UPDATED BY ATT. 2, PMRQ 50018739-01.

50018739-01 52458375 12/07/2012 12 10 05/31/2014 10/13/2014 06OP1T48-Q-0002-02 SBGT "A" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

540 ACTIVE TECH SPEC DATE/TIME = 05/31/2014 10/13/2014 1210 UPDATES PMRQ 50020009-01 &

ATT 1, PMRQ 50018741-01 50018740-01 52462961 04/06/2013 04 00 07/01/2013 07/22/2013 06OP1T48-Q-0003-01 SBGT "B" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 07/07/2013 07/29/2013 2200 UPDATES PMRQ 50020010-01, 06OP1T48-M-0002 50018738-01 52462953 01/06/2013 04 00 06/30/2014 12/25/2014 06OP1T48-Q-0003-02 SBGT "B" VALVE TEST AND 10 HR RUN **MODE APPL. = 1, 2, 3, *, , ,

540 ACTIVE TECH SPEC DATE/TIME = 06/30/2014 11/12/2014 0400 UPDATES PMRQ 50020010-01 50020014-01 52404679 03/05/2012 02 44 09/05/2013 01/20/2014 06OP1T48-R-0002-01 SBGT 'A' LOGIC TEST USE **MODE APPL. = 1, 2, 3, *, , ,

549 ACTIVE TECH SPEC DATE/TIME = 09/05/2013 01/20/2014 0844 ATTACHMENT 1 50020015-01 52364484 03/20/2011 15 44 08/14/2013 12/23/2013 06OP1T48-R-0002-02 SBGT 'A' VACUUM TEST; **WC43 - SCH **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 08/22/2013 01/05/2014 1544 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-02 WC43 - Perform Attachment 2 (50020019-01) eighteen months from performance of attachment 3 on a rotating basis.-

SCH 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-02 (50020019-01) 50020016-01 52283510 06/05/2012 11 52 11/26/2013 04/06/2014 06OP1T48-R-0002-03 SBGT 'A' VACUUM TEST; **WC43 - SCH **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 11/26/2013 04/10/2014 1152 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-03 WC43 - Perform Attachment 3 (50020020-01 eighteen months from performance of attachment 2 on a rotating basis.-

SCH 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0003-03 (50020020-01 50020018-01 52404680 03/05/2012 23 45 09/05/2013 01/20/2014 06OP1T48-R-0003-01 SBGT 'B' LOGIC TEST; USE **MODE APPL. = 1, 2, 3, *, , ,

549 ACTIVE TECH SPEC DATE/TIME = 09/05/2013 01/21/2014 0545 ATTACHMENT 1 50020019-01 52409813 03/20/2011 02 30 03/19/2014 08/02/2014 06OP1T48-R-0003-02 SBGT 'B' VACUUM TEST; USE **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 03/20/2014 08/04/2014 0230 ATTACHMENT 2. DRAWDOWN TESTING WITH AUX BLDG WC43 - Perform Attachment 2 RAILROAD BAY DOORS 1A310/1A312 CLOSED, RAILROAD eighteen months from performance of BAY CEILING HATCHES INSTALLED, AND RAILROAD BAY attachment 3 on a rotating basis.SCH DOOR 1A319A (EXTERIOR DOOR)OPEN 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0002-02 (50020015-01)

• • 1-POWER OPS; 2- STARTUP; 3-HOT SHUTDOWN; 4-COLD SHUTDOWN; 5-REFUEL; 6-CONTROL RODS WITHDRAWN Page 136 of 144 7,8,9 IDENTIFIED BY *ASTERISK : 7-CORE ALTERATIONS; 8-POTENTIAL FOR DRAINING VESSEL; 9-HANDLING IRRADIATED FUEL

All Surveillances ~~~ Sorted by Procedure Number / Late Date ~~~ Wednesday, May 8, 2013 11:17

$$ Dollar Signs denotes Surveillances which have exceeded the NRC Late Date PMRQ # / WO # / LAST DUE LATE MODE APPL.

PROCEDURE / DESCRIPTION FREQ DAYS STATUS PERFORMED DATES DATES COMMENTS 50020020-01 52423363 06/05/2012 11 52 06/05/2015 10/05/2015 06OP1T48-R-0003-03 SBGT 'B' VACUUM TEST; USE **MODE APPL. = 1, 2, 3, *, , ,

1095 ACTIVE TECH SPEC DATE/TIME = 06/05/2015 10/20/2015 1152 ATTACHMENT 3. DRAWDOWN TEST WITH RAILROAD BAY WC43 - Perform Attachment 3 DOOR 1A319A(EXTERIOR DOOR)CLOSED AND DOORS 1A310 eighteen months from performance of AND 1A312 OPEN. attachment 2 on a rotating basis.-

.SCH 18 MONTHS FROM PERFORMANCE OF 06OP1T48-R-0002-03 (50020016-01) 50020021-01 52458383 02/07/2013 17 30 05/01/2013 05/22/2013 06OP1Z51-Q-0001-01 CONTROL ROOM HVAC SYSTEM VALVE **MODE APPL. = 1, 2, 3, *, , ,

84 ACTIVE TECH SPEC DATE/TIME = 05/08/2013 05/31/2013 1130 TEST. USE ATTACHMENT 1. UPDATED BY PMRQ 50020022-01 UPDATED BY 06OP1Z51-Q-0001-02, PMRQ 50020022-01.

50020022-01 52354499 07/14/2011 03 45 01/04/2013 07/01/2013 06OP1Z51-Q-0001-02 CONTROL ROOM HVAC SYSTEM **MODE APPL. = 1, 2, 3, *, , ,

540 ACTIVE TECH SPEC DATE/TIME = 01/04/2013 05/19/2013 0345 VALVE TEST. USE ATTACHMENT 2. UPDATES PMRQ UPDATES PMRQ 50020021-01 50020021-01 50019642-01 52464553 04/10/2013 17 30 07/04/2013 07/25/2013 06OPSC85-Q-0001 SEISMIC MONITORING SYSTEM **MODE APPL. = 1, 2, 3, 4, 5, ,

84 ACTIVE TECH SPEC DATE/TIME = 0711/2013 08/04/2013 1130 FUNCTIONAL TEST 50019643-01 52456127 03/22/2012 22 35 06/14/2013 07/07/2013 06OPSD17-Q-0008 RADWASTE BLDG VENT RAD MONITOR **MODE APPL. = 1, 2, 3, 4, 5, ,

84 ACTIVE TECH SPEC DATE/TIME = 06/21/2013 07/16/2013 1635 FUNCT. TEST 50019644-01 52465037 01/17/2013 12 27 04/11/2013 05/02/2013 06OPSD17-Q-0018 LIQUID RADWASTE EFFLUENT RADIATION **MODE APPL. = 1, 2, 3, 4, 5, ,

84 ACTIVE TECH SPEC DATE/TIME = 04/18/2013 05/11/2013 0627 MONITOR FUNCTIONAL TEST 50019645-01 52470781 02/10/2013 21 45 05/05/2013 05/26/2013 06OPSP21-Q-0001-01 MAKEUP WATER TREATMENT **MODE APPL. = 1, 2, 3, , , ,

84 ACTIVE TECH SPEC DATE/TIME = 05/12/2013 06/04/2013 1545 QUARTERLY VALVE TEST. USE ATTACHMENT 1 UPDATED BY PMRQ 50019646-01, 06OPSP21-Q-0001-02 50019646-01 52453797 11/12/2012 02 46 05/06/2014 10/31/2014 06OPSP21-Q-0001-02 MAKEUP WATER TREATMENT **MODE APPL. = 1, 2, 3, , , ,

540 ACTIVE TECH SPEC DATE/TIME = 05/06/2014 09/18/2014 0246 QUARTERLY VALVE TEST. 18 MONTH; 6 MONTH GRACE UPDATES PMRQ 50019645-01, 06OPSP21-Q-0001-01 50019647-01 52395431 08/19/2012 06 31 08/19/2013 11/17/2013 06OPSP64-A-0004 FIRE PROTECTION SYSTEM VALVE **MODE APPL. = 1, 2, 3, 4, 5, ,

292 ACTIVE TECH SPEC DATE/TIME = 08/19/2013 11/19/2013 0631 STROKE TEST.

50019653-01 52402981 05/28/2012 14 00 03/16/2013 05/28/2013 06OPSP64-A-0012 ANNUAL YARD FIRE HYDRANT FLOW **MODE APPL. = 1, 2, 3, 4, 5, ,

292 ACTIVE TECH SPEC DATE/TIME = 03/16/2013 05/28/2013 1400 CHECK 50019656-01 52413147 07/08/2012 05 44 04/26/2013 07/08/2013 06OPSP64-A-0046 FIRE PUMPS LOW PRESSURE START **MODE APPL. = ,,,,,,

292 ACTIVE TECH SPEC DATE/TIME = 04/26/2013 07/08/2013 0544 FUNCTIONAL TEST 50018545-01 52470797 04/18/2013 07 00 05/16/2013 05/23/2013 06OPSP64-M-0001-01 FIRE PUMP C003A MONTHLY **MODE APPL. = 1, 2, 3, 4, 5, ,

28 ACTIVE TECH SPEC DATE/TIME = 05/19/2013 05/24/2013 1900 OPERABILITY TEST *ATT 1* USE ATTACHMENT 1 50018545-02 52470799 04/18/2013 07 00 05/16/2013 05/23/2013 06OPSP64-M-0001-02 FIRE PUMP C003B MONTHLY **MODE APPL. = 1, 2, 3, 4, 5, ,

28 ACTIVE TECH SPEC DATE/TIME = 05/19/2013 05/24/2013 1900 OPERABILITY TEST *ATT 2* USE ATTACHMENT 2 50018545-03 52470796 04/18/2013 07 00 05/16/2013 05/23/2013 06OPSP64-M-0001-03 MOTOR DRIVEN FIRE PUMP C002 **MODE APPL. = 1, 2, 3, 4, 5, ,

28 ACTIVE TECH SPEC DATE/TIME = 05/19/2013 05/24/2013 1900 OPERABILITY *ATT 3* USE ATTACHMENT 3 50019658-01 52466841 04/28/2013 14 32 05/26/2013 06/02/2013 06OPSP64-M-0011 FIRE PROTECTION SYSTEM VALVE **MODE APPL. = 1, 2, 3, 4, 5, ,

28 ACTIVE TECH SPEC DATE/TIME = 05/28/2013 06/05/2013 0232 LINEUP VERIFICATION

• • 1-POWER OPS; 2- STARTUP; 3-HOT SHUTDOWN; 4-COLD SHUTDOWN; 5-REFUEL; 6-CONTROL RODS WITHDRAWN Page 137 of 144 7,8,9 IDENTIFIED BY *ASTERISK : 7-CORE ALTERATIONS; 8-POTENTIAL FOR DRAINING VESSEL; 9-HANDLING IRRADIATED FUEL

All Surveillances ~~~ Sorted by Procedure Number / Late Date ~~~ Wednesday, May 8, 2013 11:17

$$ Dollar Signs denotes Surveillances which have exceeded the NRC Late Date END PAGE

• • 1-POWER OPS; 2- STARTUP; 3-HOT SHUTDOWN; 4-COLD SHUTDOWN; 5-REFUEL; 6-CONTROL RODS WITHDRAWN Page 138 of 144 7,8,9 IDENTIFIED BY *ASTERISK : 7-CORE ALTERATIONS; 8-POTENTIAL FOR DRAINING VESSEL; 9-HANDLING IRRADIATED FUEL

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1AS2 JPM

Title:

Determine Firewatch Requirements_

Facility Number: GJPM-OPS-ADMS95 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 25 min Applicant: ______________________ Examiner: ____________________________

Performance Time: ________________________ Performance Rating: SAT UNSAT Comments:

Prepared By: Kyle Grillis 2/21/13 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Keith nd Huff / Dustin Hill 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 2/21/13 Page 139 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 Determine Fire Watch Requirements Setting: Classroom Type: SRO Task: SRO- NO-035 K&A: Generic 2.1.2: (4.1/4.4); 2.1.8: (3.4/4.1); 2.2.22:

(4.0/4.7);2.1.25: (3.9/4.2); 2.4.25: (3.3/3.7)

Safety Function: Conduct of Operations [10CFR55.45a(12)]

Performance: Actual Reference(s): 02-S-01-17, Control of Limiting Conditions for Operation 02-S-01-27, Operations Philosophy 06-OP-SP64-D-0044 Daily Fire Door Checks TRM 6.2.1, Fire Detection Instrumentation TRM 6.2.8, Fire Rated Assemblies Fire Watch Maps Fire Pre Plan for areas A-17, A-18 UFSAR App. 9A, Fire Hazards Analysis Handout(s): Copy of Tech Specs/TRM Section 6.2 02-S-01-17, Control of Limiting Conditions for Operation 06-OP-SP64-D-0044 Daily Fire Door Checks 02-S-01-27, Operations Philosophy (to show door 1A213 is not a HELB door)

Fire Watch Map for Auxiliary Bldg 119 elevation.

(ATTACHED)

Fire Pre Plan for areas A-17, A-18 (ATTACHED)

UFSAR App. 9A, Fire Hazards Analysis for room 1A220 (ATTACHED)

1. Manipulations: N/A

1. Critical Steps: 3 Simulator Setup/Required Plant Conditions:

• None Safety Concerns:

• None Task Standard(s):

• Candidate determines fire watch requirement for combined inoperability of fire detection instrumentation and fire rated assembly is to establish an hourly fire watch patrol for room 1A220 within one hour.

Candidate may also establish an hourly fire watch patrol for area 1A222 within one hour. This is acceptable but room 1A220 is required as a minimum.

Revision 0 2/21/13 Page 140 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The plant is at rated power.

• Painters are working under an approved work order and have requested to block open door 1A213 for work in Piping Penetration Room 1A220 in Area 9/10, Elevation 119.

• A smoke detector in room 1A220 will be covered [bagged],

P65N528E.

• All other fire protection related equipment and structures are operable.

Initiating Cue(s):

• As CRS, you are directed to determine the Fire Watch requirements associated with this work.

• Use the references provided.

• 1A213 is not a HELB door.

Revision 0 2/21/13 Page 141 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 Determine Fire Watch Requirements Notes: (Notes to Evaluator)

Task Overview: (Detailed description of task)

• The student will determine the required TRM Fire Watch actions for impairing a required fire door and smoke detector.

• The order in which the candidate evaluates the INOP fire door and the INOP smoke detector is not critical.

Revision 0 2/21/13 Page 142 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 Critical tasks are underlined, italicized, and denoted by an (*)

Sequence is not critical.

Step 1: TRM 6.2.1

• Candidate uses provided references to identify the smoke detector to be covered in room 1A220 is for fire detection zone 2-3 and is required operable by TRM 6.2.1 as listed in TRM Table 6.2.1-1 C.2 and determines required TRM action.

Standard: Determines an hourly fire watch patrol for room 1A220 per TRM 6.2.1 Condition A, Action A.1 is required for impairing the subject smoke detector.

Cue: None Notes:

SAT /

UNSAT Step 2: TRM 6.2.8

• Candidate uses provided references to identify door 1A213 to be blocked open is required operable by TRM 6.2.8.

Standard: Determines door 1A213 is a Fire Rated Assembly required by TRM 6.2.8 and will be inoperable.

Cue: None Notes:

SAT / UNSAT Revision 0 2/21/13 Page 143 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 Step 3: TRM 6.2.8

• Candidate uses provided references to determine whether or not an operable fire detection zone will be available to monitor one side of door 1A213 and determines the appropriate TRM action for the combined inoperabilities of Fire Detection Instrumentation in room 1A220 and Fire Rated Assembly door 1A213.

Standard: Determines operable fire detection zone 2-2 exists on one side of door 1A213 and an hourly fire watch patrol will be required to be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for room 1A220.

Cue: If student determines continuous firewatch, cue student to use the firewatch that would require the least demand on manpower.

Notes: Since Fire detection zone 2-2 will be unaffected, TRM 6.2.8 Action A.2.1 is satisfied, so TRM 6.2.8 Action A.1, continuous fire watch, is not required.

Though for TRM 6.2.8 Condition A, either Action A.1 (continuous fire watch) OR Actions A.2.1 and A.2.2 (verifying fire detection on one side of door 1A213 and an hourly fire watch) will satisfy TRM actions, selection of an hourly fire watch patrol versus a continuous fire watch is Operations preference to accommodate unit staffing conditions.

Establishing an hourly fire watch patrol to inspect room 1A220 is required to meet TRM 6.2.1 Action A.1 and that will meet the requirement to establish an hourly fire watch patrol to inspect at least one side of door 1A213 per TRM 6.2.8 Action A.2.2.

It is also acceptable to establish an hourly fire watch in Area 1A222 (west corridor) to monitor one side of Door 1A213. If this approach is taken then hourly Fire Watch would be required in room 1A220 for TRM 6.2.1 and Area 1A222 for TRM 6.2.8.

Student may also identify the smoke detector must be restored operable within 14 days, but this is not critical for this JPM.

The task is complete when the operator identifies the required TRM action, including area and frequency of the proposed fire watch.

SAT / UNSAT Revision 0 2/21/13 Page 144 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 Task Standard(s):

• Candidate determines fire watch requirement for combined inoperability of fire detection instrumentation and fire rated assembly is to establish an hourly fire watch patrol for room 1A220 within one hour. Candidate may also establish an hourly fire watch patrol for area 1A222 within one hour. This is acceptable but room 1A220 is required as a minimum.

SAT / UNSAT Remember to record stop time Revision 0 2/21/13 Page 145 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS2 Follow-Up Questions & Answers:

Comments:

Revision 0 2/21/13 Page 146 of 9

Give this page to the student Initial Condition(s):

• The plant is at rated power.

• Painters are working in under an approved work order and have requested to block open door 1A213 for work in Piping Penetration Room 1A220 in Area 9/10, Elevation 119.

• A smoke detector in room 1A220 will be covered [bagged],

P65N528E.

• All other fire protection related equipment and structures are operable.

Initiating Cue(s):

• As CRS, you are directed to determine the Fire Watch requirements associated with this work.

• Use the references provided.

Give this page to the student JPM Page 148 of 298

Give this page to the student JPM Page 149 of 298

Give this page to the student JPM Page 150 of 298

Give this page to the student This page was redacted.

JPM Page 151 of 298

Give this page to the student This page was redacted.

JPM Page 152 of 298

Give this page to the student JPM Page 153 of 298

Give this page to the student JPM Page 154 of 298

Give this page to the student JPM Page 155 of 298

Give this page to the student JPM Page 156 of 298

Give this page to the student JPM Page 157 of 298

Give this page to the student JPM Page 158 of 298

Give this page to the student JPM Page 159 of 298

Give this page to the student JPM Page 160 of 298

Give this page to the student JPM Page 161 of 298

Give this page to the student JPM Page 162 of 298

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1AS3 JPM

Title:

Tagout Approval___

Facility Number: N/A (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 30 min Applicant: ___________________________ Examiner: ___________________________

Performance Time: ________________________ Performance Rating: SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/6/13 Exam Developer Date Ops Review: Robert Brinkman 3/21/2013 st 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Keith Huff / Dustin Hill 3/25/2013 nd 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 3/6/13 Page 163 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Tagout Approval Setting: Classroom Type: SRO Task: SRO-ADMIN-48, SRO-M&S-5, SRO-NO-16 K&A: 2.2.13 (4.1/4.3), 2.2.15 (3.9/4.3), 2.2.40 (3.4/4.7), 2.2.41 (3.5/3.9)

Safety Function: Equipment Control Performance: Actual Reference(s): EN-OP-102 (Protective and Caution Tagging) 02-S-01-17 (Control of Limiting Conditions for Operation)

UFSAR Table 6.2-49 (Attached) 04-1-01-G33-1 (RWCU SOI)

E-1160-18 (NSSSS Electrical Schematic)

M-1079 (RWCU P&ID)

Technical Specification 3.6.1.3 Handout(s): EN-OP-102 02-S-01-17 (Control of Limiting Conditions for Operation)

E-1160-18 (NSSSS Electrical Schematic)

M-1079 (RWCU P&ID)

UFSAR Table 6.2-49 sheet 8 of 17 (Attached) 04-1-01-G33-1 (RWCU SOI)

Tagout Tags Sheet (Attached)

Technical Specifications

1. Manipulations: N/A

1. Critical Steps: 1 Revision 0 3/6/13 Page 164 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Simulator Setup/Required Plant Conditions:

• None Safety Concerns:

• None Task Standard(s):

• The operator identifies incorrect electrical breaker number is listed for valve 1G33F039 and identifies the correct breaker as 52-151140.

• The operator indentifies the tagout but must also include tagging either test connection valve 1G33F055 or 1G33F056 closed.

Revision 0 3/6/13 Page 165 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The plant is in Mode 3.

• Reactor Water CleanUp System is shut down.

• 1G33F040, RWCU Return Inboard Isolation Valve has failed in the open position.

• A tagout has been prepared to meet Technical Specification Action requirements for the inoperable valve.

• The Auxiliary Building Steam Tunnel is open for work and is accessible in all regards, including radiological and heat stress concerns.

Initiating Cue(s):

• As CRS you are tasked to determine the tagging boundary required to satisfy Tech Spec Action per 02-S-01-17 section 6.11, then, review the tagout to ensure it will satisfy the Tech Spec requirements.

• Restoration/Removal positions/sequences are NOT required at this time.

• Document any identified errors by marking up the tagging forms provided.

Revision 0 3/6/13 Page 166 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Tagout Approval Notes: (Notes to Evaluator)

• None Task Overview: (Detailed description of task)

• The operator will determine the proper tagout to meet Tech Spec Action requirements for INOP valve G33-F039.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: Technical Specification 3.6.1.3 Action A The operator must determine the required Tech Spec Action is to isolate the affected penetration in accordance with TS 3.6.1.3 Action A.1.

Standard: Determines the required action is TS 3.6.1.3 Action A.1.

Cue: None Notes:

SAT / UNSAT Revision 0 3/6/13 Page 167 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Step 2: 02-S-01-17 step 6.11.1 The operator must determine the failed valve is the inboard boundary for the affected penetration and the penetration must be isolated using the outboard valve boundaries for the penetration.

Standard: Determines the appropriate isolation valves for the penetration.

Cue: None Notes: Either Test Connection valve 1G33F055 or 1G33F056 will satisfy the requirement to isolate the outboard test connection flow path for penetration 83, although only 1G33F055 is listed in UFSAR Table 6.2-49, since it is the inboard Test Connection valve.

SAT / UNSAT Revision 0 3/6/13 Page 168 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Step 3: EN-OP-102 step 5.8, 02-S-01-17 steps 6.11.1 and 6.11.4

• The Operator reviews the tagout listing provided and documents the following:

• Corrects breaker number listed for valve 1G33F039 to 52-151140.

• Manual Test Connection valve 1G33F055 and/or 1G33F056 must be added to the tagout and tagged in the CLOSED position.

Standard: Documents corrections.

Cue: None Notes: It is acceptable if the operator lists only 1G33F055 or 1G33F056 or both to be tagged closed.

1G33F039 and 1G33F055 and/or F056 are the minimum components necessary to satisfy Tech Spec actions. If the operator includes other components, this is acceoptable.

The task is complete when the operator determines the adequacy for this Tagout.

SAT / UNSAT Revision 0 3/6/13 Page 169 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Task Standard(s):

• The operator identifies incorrect electrical breaker number is listed for valve 1G33F039 and identifies the correct breaker as 52-151140.

• The operator indentifies the tagout but must also include tagging either test connection valve 1G33F055 or 1G33F056 closed.

SAT / UNSAT Remember to record stop time Revision 0 3/6/13 Page 170 of 9

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS3 Follow-Up Questions & Answers:

Comments:

Revision 0 3/6/13 Page 171 of 9

Give this page to the student Initial Condition(s):

• The plant is in Mode 3.

• Reactor Water CleanUp System is shut down.

• 1G33F040, RWCU Return Inboard Isolation Valve has failed in the open position.

• A tagout has been prepared to meet Technical Specification Action requirements for the inoperable valve.

• The Auxiliary Building Steam Tunnel is open for work and is accessible in all regards, including radiological and heat stress concerns.

Initiating Cue(s):

• As CRS you are tasked to determine the tagging boundary required to satisfy Tech Spec Action per 02-S-01-17 section 6.11, then, review the tagout to ensure it will satisfy the Tech Spec requirements.

• Restoration/Removal positions/sequences are NOT required at this time.

• Document any identified errors by marking up the tagging forms provided.

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV.8 MANAGEMENT MANUAL INFORMATIONAL USE PAGE 6 OF 30 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 TAGOUT COVER SHEET Clearance: __MANUAL____________ Tagout: 1CXX-1 G33-001- - 1G33F040 Component to be worked:

1G33F040 RWCU RTN INBD ISOL VLV

==

Description:==

1G33F040 FAILED IN OPEN POSITION AND CANNOT BE CLOSED THIS TAGOUT IS TO ISOLATE THE AFFECTED PENETRATION FLOWPATH FOR TECH SPEC COMPLIANCE.

Placement Inst:

HANG TAGS IN SEQUENCE LISTED.

Hazards:

HIGH ENERGY SYSTEM.

RWCU PIPING WILL BE EXTREMELY HOT.

Restoration Inst:

ENSURE LCO HAS BEEN CLEARED BEFORE CLEARING THIS TAGOUT Attribute Description Attribute Value HIGH ENERGY SYSTEM CONCERNS YES - SEE TAGOUT HAZARDS TECH SPEC IMPACT? LCO 1-TS-XX-0001 COMPENSATORY ACTIONS REQUIRED? NO SCAFFOLD REQUIRED NO WALKDOWN COMPLETE NO TAGOUT PREPARE ISSUES: NO Work Order Number Description XX35762 1G33F040 FAILED IN OPEN POSITION AND CANNOT BE CLOSED Status Description User Verificat ion Date Prepared Prepared Technical Reviewed Reviewed Approved Approved Tags Verified Tags Verified Hung Hung Removal Approved Removal Approved Tags Verified Tags Verified Removed Removed

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV.8 MANAGEMENT MANUAL INFORMATIONAL USE PAGE 6 OF 30 Protective and Caution Tagging Forms & Checklist

NUCLEAR MANAGEMENT NON-QUALITY RELATED MANUAL EN-OP-102-01 REV. 8 INFORMATIONAL USE PAGE 7 OF 30 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET Clearance: ___MANUAL___________ Tagout: 1CXX-1 G33-001- - 1G33F040 Tag Tag Equipment Place. Place. Rest. Rest. Placemen Seri Type Equipment Description Place Placement 1st 2nd Verif Rest Restoration 1st 2nd t/

al Equipment Location . Configurati Verif Date/Time . Configuratio Verif Verif Removal No. Seq. on Date/Tim Seq. n Date/Tim Date/Tim Tag e e e Notes 1-G33-IBISSW-1G33M610 NORMAL Dange *RWCU RTN CTMT OTBD 0001 1 AFTER r ISOL 1G33F039 CLOSED

• C0A-166 -0C503-1-G33 -CKTBRK-52-163152 Dange

• RWCU RTN CTMT OTBD OFF 0002 ISOL 1G33F039 2 r

• A09-119 -1A219-1-G33-VALVE-1G33F039 RWCU RTN CTMT OTBD Dange

• HANDWHEEL 0003 ISOL 1G33F039 3 r CLOSED

• A08-139 -1A305-AUX STM TNL

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS4 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1AS4JPM

Title:

Review Liquid Radwaste Discharge Permit Facility Number:

N/A __________

(If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Validation Time: 20 Time Critical Alternate Path min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 2/11/13 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Keith nd Huff / Dustin Hill 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 2/11/13 Page 10 of 7

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS4 Review Liquid Radwaste Discharge Permit Setting: Classroom Type: SRO Task: SRO-NO-10 K&A: 2.3.6: 3.1 Safety Function: 9 Performance: Actual Reference(s): 01-S-08-11, Radioactive Discharge Controls 06-CH-SG17-V-0034, Radwaste Release Inop Monitor Pre-Release Analysis OCDM 6.3 Handout(s): LRW Discharge Permit with 06-CH-SG17-V-0034 Att. I completed and 01-S-08-11 Att. I with Parts 1, 2, 3, 4, and 5 completed with errors OCDM 6.3

1. Manipulations: N/A

1. Critical Steps: 1 Simulator Setup/Required Plant Conditions:

None Safety Concerns:

None Task Standard(s):

Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01-S-08-11 and identifies at least 2 of the 3 errors.

Revision 0 2/11/13 Page 11 of 7

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS4 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

The Plant Chemistry technician has presented completed surveillance 06-CH-SG17-V-0034, Radwaste Release Inop Monitor Pre-Release Analysis, including a Batch Liquid Radwaste Discharge Permit, to you for Operations Supervision review and approval.

Initiating Cue(s):

You are the Control Room Supervisor. Perform the review for the Part 5 Operations Supervisor signoff of the Batch Liquid Radwaste Discharge Permit associated with completed surveillance 06-CH-SG17-V-0034 for the recently completed discharge and identify 3 critical deficiencies.

REFER TO THE LRW DISCHARGE PERMIT, PROVIDED.

Revision 0 2/11/13 Page 12 of 7

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS4 Review Liquid Radwaste Discharge Permit Notes: (Notes to Evaluator)

Task Overview: (Detailed description of task)

This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by Operations Supervision following a controlled release of liquid radwaste. Three errors have been introduced somewhere within sections 1 through 5 of the Discharge Permit.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 01-S-08-11

• Reviews the Batch Liquid Radwaste Discharge Permit package provided per the requirements of 01-S-08-11 to determine if the discharge was performed in accordance with the requirements of 01-S-08-11.

Standard: Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01-S-08-11 and identifies at least 2 of the 3 following errors:

In Part 2, the Radiochemist signoff for independent verification required for Effluent Radiation Monitor Inoperable had been N/Ad.

In Part 4, the Shift Manager signoff granting permission to discharge had not been obtained.

In Part 5, the Average Dilution Flow during the discharge was lower than the required minimum dilution flow prescribed in Section 3.

Cue: None Notes: All values recorded in Parts 1, 2, and 3 derive from pages 1 and 2 of the computer generated Liquid Pre-Release Permit Report in 06-CH-SG17-V-0034 Att I SAT / UNSAT Revision 0 2/11/13 Page 13 of 7

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS4 Task Standard(s):

Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01-S-08-11 and identifies at least 2 of the 3 errors.

SAT / UNSAT Remember to record stop time Revision 0 2/11/13 Page 14 of 7

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS4 Follow-Up Questions & Answers:

Comments:

Revision 0 2/11/13 Page 15 of 7

Initial Condition(s):

The Plant Chemistry technician has presented completed surveillance 06-CH-SG17-V-0034, Radwaste Release Inop Monitor Pre-Release Analysis, including a Batch Liquid Radwaste Discharge Permit, to you for Operations Supervision review and approval.

Initiating Cue(s):

You are the Control Room Supervisor. Review the Batch Liquid Radwaste Discharge Permit associated with completed surveillance 06-CH-SG17-V-0034 for the recently completed discharge and identify 3 critical deficiencies.

REFER TO THE LRW DISCHARGE PERMIT, PROVIDED.

DO GULF GRAND NOTNUCLEAR GIVESTATION TO STUDENT ADMINISTRATIVE PROCEDURE EVALUATOR COPY 01-S-08-11 Revision: 113 Attachment I Page 1 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT YY-MM-DD-17 Part 1 Pre-Release Processing Release Number*

Date Today Time 0700 Tank to be released* FDST-A Volume* 28560 gal Tank is isolated. Recirculation started Today / 0100 Date/Time Dilution flow 9900 gpm Radwaste monitor background reading*

• N/A (LCO 1-TS-XX-0073) cpm (Monitor reading is less than 10,800 cpm)

• LRW Rad Monitor is INOP under this LCO Clyde Small _____________________

Operator (Performer)

Asterisked* items above verified Frank Zapp_____________________

Operator (Verifier)

Radwaste monitor background reading verified John Doe #30588 Today / 0400 Operations Supervision /Date/Time Part 2 Pre-Release Analysis 20XX192 Batch Number Sample Date Today Time 0830 Minimum recirculation time is met RC #30471 One Total Suspended Solids (TSS) sample has been collected and analyzed for the month:

Yes X Initials RC #30471 No N/A TSS N/A mg/l (< 30mg/l)

The radioactive liquid from the tank designated above is within the ALARA criteria of 10CFR50 App I as defined by surveillance 06-CH-SG17-P-0041, 06-CH-SG17-V-0034, or 06-CH-SP41-P-0035 and may be released.

Should be Rupert Colada #30007signed, not Radiochemist N/Ad DO NOT GIVE TO STUDENT Independent Verification if Effluent Radiation Monitor Inoperable.

N/A Radiochemist Comments: no limits exceeded

DO NOT GRAND GIVE STATION GULF NUCLEAR TO STUDENT ADMINISTRATIVE PROCEDURE EVALUATOR COPY 01-S-08-11 Revision: 113 Attachment I Page 2 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT Part 3 Monitor Setpoint Calibration Batch Number (from Part 2) 20XX192 Setpoints Adjusted to:

Minimum Blowdown Flow Rate Setpoint (Circ Water Blowdown Flow Setpoint) 2250 gpm Maximum Tank Discharge Flow Rate Setpoint (Liquid Radwaste Effluent Flow Setpoint) 100 gpm Effluent Monitor Alarm Setpoint N/A (LCO 1-TS-XX-0073) cpm (Hi)

Effluent Monitor Trip Setpoint N/A cpm (Hi-Hi)

Micheal Wildfire #30864 / Today I&C Technician Date S. Nugent #30255 / Today Verified Date

• Copies of Pages 1 and 2 of this permit have been placed in the Control Room Setpoint Logbook, and

• The previous Pages 1 and 2 have been removed.

Micheal Wildfire #30864 / Today I&C Technician Date S. Nugent #30255 / Today Should be Verified Date signed, not blank Part 4 Release Authorization DO NOT GIVE TO STUDENT The designated tank may be released provided the discharge and dilution flows meet the setpoint criteria.

/

Shift Manager Date Part 5 Release Valve lineup Verified H. Casey #30114 / D. McCormick #30435 Independent Verification if Radiation Monitor Inop From Step 6.4.2e(2): On the date of release, prior to opening SG17-F355 DRAIN BASIN ISOL VLV, have chemistry verify the Total Suspended Solids analysis for this tank has been completed or is not required.

The Total Suspended Solids analysis for this tank has been completed.

YES Not Required_ Rupert Colada #30007 / Today Radiochemist Date

DO GRANDNOTGULF GIVE NUCLEAR TO STUDENT STATION ADMINISTRATIVE PROCEDURE EVALUATOR COPY 01-S-08-11 Revision: 113 Attachment I Page 3 of 4 Part 5 (cont)

BATCH LIQUID RADWASTE DISCHARGE PERMIT Radiation Monitor Reading Before release N/A cpm Maximum during release N/A cpm Average during release* N/A cpm Tank Level Before 28560 After* 762 Gallons Released* 27798 Average Release Rate (Tank Discharge Rate GPM)* 92.66 Flow Rate Indication During Discharge a) Maximum Radwaste Tank Effluent Flow* 94 gpm If G17 FR-R011, tank discharge flow rate recorder, is inop flow must be estimated at intervals not to exceed every four hours.

N/A / Start Should be greater than N/A / Approx. Middle minimum setpoint 2250 gpm listed in Part N/A / End 3

Flow Time b) Average Dilution Flow* 2000 gpm (appx)

Circulation Water Blowdown Flow, monitor Operable Inoperable Discharge Canal Flow Other dilution water source (specify): N/A If dilution flow monitor is inop, flow must be estimated at intervals not to exceed every four hours.

N/A / Start N/A / Approx. Middle N/A / End Flow Time

DO NOT GIVE TO STUDENT GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE EVALUATOR COPY 01-S-08-11 Revision: 113 Attachment I Page 4 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT LCO No.: N/A DATE AND TIME ELAPSED TIME*

(minutes)

VALVES OPEN VALVES SHUT Today 0930 Today 1430 300 TOTAL 300 Monitor flushed HC#30114 H. Casey #30114 Initials Operator (Performer)

Asterisked* items above verified D. McCormick #30435_______________

Operator(Verifier)

Operations Supv __________________

signoff block Operations Supervision Comments:

Part 6 Post-Release Analysis The post-release analysis is based on actual data recorded during the release Comments:

/

Radiochemist Date

Give this page to the student Initial Condition(s):

The Plant Chemistry technician has presented completed surveillance 06-CH-SG17-V-0034, Radwaste Release Inop Monitor Pre-Release Analysis, including a Batch Liquid Radwaste Discharge Permit, to you for Operations Supervision review and approval.

Initiating Cue(s):

You are the Control Room Supervisor. Review the Batch Liquid Radwaste Discharge Permit associated with completed surveillance 06-CH-SG17-V-0034 for the recently completed discharge and identify 3 critical deficiencies.

REFER TO THE LRW DISCHARGE PERMIT, PROVIDED.

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 1 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT YY-MM-DD-17 Part 1 Pre-Release Processing Release Number*

Date Today Time 0700 Tank to be released* FDST-A Volume* 28560 gal Tank is isolated. Recirculation started Today / 0100 Date/Time Dilution flow 9900 gpm Radwaste monitor background reading*

• N/A (LCO 1-TS-XX-0073) cpm (Monitor reading is less than 10,800 cpm)

• LRW Rad Monitor is INOP under this LCO.

Clyde Small______________________

Operator (Performer)

Asterisked* items above verified Frank Zapp ________________________

Operator (Verifier)

Radwaste monitor background reading verified John Doe #30588 Today / 0400 Operations Supervision /Date/Time Part 2 Pre-Release Analysis 20XX192 Batch Number Sample Date Today Time 0830 Minimum recirculation time is met RC #30471 One Total Suspended Solids (TSS) sample has been collected and analyzed for the month:

Yes X Initials RC #30471 No N/A TSS N/A mg/l (< 30mg/l)

The radioactive liquid from the tank designated above is within the ALARA criteria of 10CFR50 App I as defined by surveillance 06-CH-SG17-P-0041, 06-CH-SG17-V-0034, or 06-CH-SP41-P-0035 and may be released.

Rupert Colada #30007 Radiochemist Independent Verification if Effluent Radiation Monitor Inoperable.

N/A Radiochemist Comments: no limits exceeded

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 2 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT Part 3 Monitor Setpoint Calibration Batch Number (from Part 2) 20XX192 Setpoints Adjusted to:

Minimum Blowdown Flow Rate Setpoint (Circ Water Blowdown Flow Setpoint) 2250 gpm Maximum Tank Discharge Flow Rate Setpoint (Liquid Radwaste Effluent Flow Setpoint) 100 gpm Effluent Monitor Alarm Setpoint N/A (LCO 1-TS-XX-0073) cpm (Hi)

Effluent Monitor Trip Setpoint N/A cpm (Hi-Hi)

Micheal Wildfire #30864 / Today I&C Technician Date S. Nugent #30255 / Today Verified Date

• Copies of Pages 1 and 2 of this permit have been placed in the Control Room Setpoint Logbook, and

• The previous Pages 1 and 2 have been removed.

Micheal Wildfire #30864 / Today I&C Technician Date S. Nugent #30255 / Today Verified Date Part 4 Release Authorization The designated tank may be released provided the discharge and dilution flows meet the setpoint criteria.

/

Shift Manager Date Part 5 Release Valve lineup Verified H. Casey #30114 / D. McCormick #30435 Independent Verification if Radiation Monitor Inop From Step 6.4.2e(2): On the date of release, prior to opening SG17-F355 DRAIN BASIN ISOL VLV, have chemistry verify the Total Suspended Solids analysis for this tank has been completed or is not required.

The Total Suspended Solids analysis for this tank has been completed.

YES Not Required_ Rupert Colada #30007 / Today Radiochemist Date

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 3 of 4 Part 5 (cont)

BATCH LIQUID RADWASTE DISCHARGE PERMIT Radiation Monitor Reading Before release N/A cpm Maximum during release N/A cpm Average during release* N/A cpm Tank Level Before 28560 After* 762 Gallons Released* 27798 Average Release Rate (Tank Discharge Rate GPM)* 92.66 Flow Rate Indication During Discharge a) Maximum Radwaste Tank Effluent Flow* 94 gpm If G17 FR-R011, tank discharge flow rate recorder, is inop flow must be estimated at intervals not to exceed every four hours.

N/A / Start N/A / Approx. Middle N/A / End Flow Time b) Average Dilution Flow* 2000 gpm (appx)

Circulation Water Blowdown Flow, monitor Operable Inoperable Discharge Canal Flow Other dilution water source (specify): N/A If dilution flow monitor is inop, flow must be estimated at intervals not to exceed every four hours.

N/A / Start N/A / Approx. Middle N/A / End Flow Time

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 4 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT LCO No.: N/A DATE AND TIME ELAPSED TIME*

(minutes)

VALVES OPEN VALVES SHUT Today 0930 Today 1430 300 TOTAL 300 Monitor flushed HC#30114 H. Casey #30114 Initials Operator (Performer)

Asterisked* items above verified D. McCormick #30435_______________

Operator(Verifier)

Operations Supervision Comments:

Part 6 Post-Release Analysis The post-release analysis is based on actual data recorded during the release Comments:

/

Radiochemist Date

Facility: GGN GRAND GULF NUCLEAR Work Order Package Unit: 1 Project: 0XXXXXX 01 Priority: 4A W/O Dspln: CHEM Rpt: TIPMC11 Planner: RONEAL O'NEAL RONALD Date: XX/XX/20XX W/O Type: WO W/O

Title:

06CHSG17-V-0034 LIQUID RADW ASTE INOP MONITOR PRE RELEASE Job Type: OD Pkg Type:

W/O Task

Title:

06CHSG17-V-0034 LIQUID RADW ASTE INOP MONITOR PRE RELEASE Task Dspln: CHEM Completed By: Entergy Page 1 of 2 Work Order Task Written To Facility: GGN Unit: 1 Op Sys:

Division: Area: Sys/Cls:

Equipment: Component:

Equip Name:

Work Item: 06CHSG17-V-0034GPRO Eqt. List: Ops Review Reqd: N Equip.Tag: Alt:

UTC: Tbl/Brkdwn: (Past 12 mo)

Catalog ID: UCR: 6 CR Comm Reqd: NOTIFY W ORK CONTROL CENTER VIA PHONE PRIOR TO START OF W ORK Location: .

Cost Centr: NSCC2 Activity: PRSS User Def: F5PPNRMSTK Percentage: 100.000000 Acct No: GL GG1 Equipment Information Q Group: Maintenance Rel:

Safety Class:

Manufacturer: Model Number:

Serial Number:

Work Order Task Instructions

• • • DESCRIPTION***

06CHSG17-V-0034 LIQUID RADW ASTE INOP MONITOR PRE RELEASE

• • • DESCRIPTION END***

• • • W ORK ACTIVITY ***

CHEM CH-SG17-V-0034

• • • W ORK ACTIVITY END ***

Rework/Approval Deficiency Tag No: Loc: Tag Removed:

Rework Job: N Comments:

Task Requirements FAC. REG/REQ VALUE COMMENTS GGN EST. DOSE? 1 GGN RW P SRW P GENERAL RW P DOSE ESTIMATE: 0.001 QC Requirements/Comments NO QC REQUIREMENTS FOR THE W ORK ORDER TASK

Facility:

GGN GRAND GULF NUCLEAR Work Order Package Unit: 1 Project: 0XXXXXX 01 Priority: 4A W/O Dspln: CHEM Rpt: TIPMC11 Planner: RONEAL O'NEAL RONALD Date: XX/XX/20XX W/O Type: WO W/O

Title:

06CHSG17-V-0034 LIQUID RADW ASTE INOP MONITOR PRE RELEASE Job Type: OD Pkg Type:

W/O Task

Title:

06CHSG17-V-0034 LIQUID RADW ASTE INOP MONITOR PRE RELEASE Task Dspln: CHEM Completed By: Entergy Page 2 of 2 References/Document Information Type/Subtype: PRO Number: 06CHSG17-V-0034 Sheet: 0 Title/Desc: 2137 STORAGE LOCATION: 120510090 Image:

Type/Subtype: W O Number: W O-00312975 Sheet:

Title/Desc: 06CHSG17-V-0034 LIQUID RADW ASTE INOP MONITOR PRE RELEASE Image:

Authorization Early Start Date: 20XX-XX-XX Early Finish Date: 20XX-XX-XX Late Start Date: Late Finish Date:

Major Failure/Action Taken Major Failure: Action Taken:

Deficiency Tag Loc: Removed (Y/N):

Deficiency Tag No.:

Completion Comments on Work Performed Comments Date By Type Date Batch 20XX192. Sat. LCO 1-TS-XX-0073 20XX-XX-XX KW ILSON 20XX-XX-XX

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-CH-SG17-V-0034 Revision: 106 RT = B6.61 NON-QA RECORD Attachment I Page 1 of 2 INITIALS NUMBER OF PAGESl DATE Page RELATED DOCUMENT RTYPE B6.61 NUMBER = Ref SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED

Title:

Radwaste Release Inop Radwaste Monitor Pre-Release Analysis Technical Specification: SR 6.11.1.1 for Function 6.11.1-1.A, Table 6.11.1-1 Notes c

& d, LCO 6.3.9 Condition B 1.0 IMPACT STATEMENT 1.1 Performance of this procedure has no impact on plant operation.

2.0 PROCEDURE 2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Permission to begin the test Not Applicable Shift Supervisor/Date 2.3 Performed for LCO # 1-TS-XX-073 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [ ]

All other steps/data Acceptable [ ] Unacceptable [ ]

3.2 TCNs in effect during performance (list): none

3.3 Comments

Batch 20XX192 3.4 Test performed by M. Wildfire Date/Time Today / 0500 4.0 DEFICIENCIES CR Issued #

LCO Entered #

WR Issued #

5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supv/Mgr Date Comments:

CONCURRENCE Chemistry Manager Date

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-CH-SG17-V-0034 Revision: 106 RT = B6.61 NON-QA RECORD Attachment I Page 2 of 2 INITIALS NUMBER OF PAGESl DATE Page RELATED DOCUMENT RTYPE B6.61 NUMBER = Ref DATA SHEET I RADWASTE RELEASE INOP RADWASTE MONITOR PRE-RELEASE ANALYSIS SAFETY RELATED INITIALS

$ 5.2 Tank minimum recirculation of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> met MW 5.3.1.b(1) Sample contains Resin and Chemistry Management Notified MW 5.3.1.b(2) Sample does not contain Resin N/A

$ 5.4.2 First Sample all significant peaks identified MW

$ 5.5.2 Second Sample all significant peaks identified MW

$ 5.6.1 ODCM dose limits are not exceeded. MW 5.6.2 Whole Body Current Limit Chemistry Tank Will Be Decision To Initials Dose Admin. Exceeded Supervision Reprocessed Discharge Limit Notified Documented 2.43E3 1.0E-2 Yes/No Yes/NA Yes/No/NA Yes/NA MW mrem mrem Highest Current Limit Chemistry Tank Will Be Decision To Initials Organ Dose Admin. Exceeded Supervision Reprocessed Discharge Limit Notified Documented 4.19E-3 3.3E-2 Yes/No Yes/NA Yes/No/NA Yes/NA MW mrem mrem

$ 5.8 Composite Sample Saved MW 5.10.3 Unused Permit Record # N/A Deleted MW Comments : Batch 20XX192, no limits exceeded _

____LCO 1-TS-XX-0073 _____________________________________

Reviewed : Micheal Wildfire Date: Today

RETDAS v3.5.0 <GGN> CANBERRA LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20xx192 Release ID: 1 SAMPLE TANKS Release Mode: 2 Batch Status: P Pre-Release Comments:

FDST-A for Discharge (V-34 1st sample)

RELEASE DATA ===================================================

Estimated tank volume to be released (gal).....................28560 Average dilution flow available (gpm)..........................2500 Allocation percentage..........................................100 Dilution flow assigned to permit (gpm).........................2500

NUCLIDE DATA ===================================================

Undiluted Percent Nuclide uCi/ml lO*EC of lO*EC ZN-65 C0-60 RB-88 SB-125 5.71E-07 2.14E-07 7.85E-07 1.79E-07 3.00E-05 5.00E-05 4.00E-03 3.00E-04 4.28E-01 1.90E+OO 1.96E-02 5.97E-02 w

LA-140 6.04E-08 9.00E-05 6.71E-02 Gamma 1.81E-06 H-3 4.67E-03 1.OOE-02 4.67E+Ol FE-55 2.17E-06 1.OOE-03 2.17E-01 Beta 4.67E-03 Total 4.67E-03 Diluted D&EG Concentration: O.OOE+OO D&EG Concentration Limit Not Exceeded Date/Time: xx/xx/20xx xx:xx seekeriD: Retdas Page - 1

RETDAS v3.5.0 <GGN> CANBERRA LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20XX192

RELEASE CALCULATIONS ===========================================

Minimum dilution factor........................................9.88E-01 Min. dilution flowrate setpoint(Circ Water Blowdown Flow)(gpm).2.25E+03 Maximum tank discharge flowrate setpoint(Effluent Flow)(gpm)...1.00E+02

SETPOINT DATA ==================================================

Entered background (cpm).......................................0.OOE+OO Alarm Setpoint (cpm)...........................................NA Trip Setpoint (cpm)............................................NA

--- I&C SETPOINT VOLTAGES =============================================

Minimum blowdown flow trip voltage setpoint (vdc).............1. 720E+OO Desired blowdown flow trip voltage setpoint (vdc).............1.729E+OO Maximum blowdown flow trip voltage setpoint (vdc).............1.737E+OO Minimum tank effluent flow trip voltage setpoint (vdc)........4.950E+OO Desired tank effluent flow trip voltage setpoint (vdc)........4.975E+OO Maximum tank effluent flow trip voltage setpoint (vdc)........5.OOOE+OO Minimum radiation monitor alarm voltage setpoint (vdc)........O.OOOE+OO Desired radiation monitor alarm voltage setpoint (vdc)........0.OOOE+OO Maximum radiation monitor alarm voltage setpoint (vdc)........O.OOOE+OO Minimum radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO Desired radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO Maximum radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO

PERMIT INSTRUCTIONS ============================================

Date/Time: xx/xx/20xx xx:xx seekeriD: Retdas Page - 2

RETDAS v3.5.0 <GGN> CANBERRA LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20XX192

PERMIT DOSE BY ORGAN AND AGE GROUP (mrem) ===============================*

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 5.85E-04 1.66E-03 9.66E-05 1.06E-03 1.47E-04 1.34E-03 O.OOE+OO 8.11E-04

PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ============= QUARTER 3 =======

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 1.11E-02 3.38E-02 8.08E-04 2.19E-02 1.30E-03 2.54E-02 O.OOE+OO 1.56E-02

SITE DOSE LIMIT ANALYSIS ================================================

Age Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Admin. Any Organ ADULT LIVER 3.38E-02 3.75E+OO 9.01E-01 Q3 - Admin. Total Body ADULT 1.56E-02 1.13E+OO 1.39E+00 Q3 - TS Any Organ ADULT LIVER 3.38E-02 S.OOE+OO 6.76E-01 Critical Pathway: Fresh Water Fish - Comm. (FFCM)

Q3 - TS Total Body ADULT 1.56E-02 1.50E+OO 1.04E+OO Critical Pathway: Fresh Water Fish - Comm. (FFCM)

PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ================= 2012 ========

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 2.72E-01 5.74E-01 6.62E-03 3.05E-01 3.38E-02 2.77E-01 O.OOE+OO 3.07E-01

SITE DOSE LIMIT ANALYSIS ================================================

Age Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit 2012 - Admin. Any Organ ADULT LIVER 5.74E-01 7.50E+OO 7.65E+OO 2012 - Admin. Total Body ADULT 3.07E-01 2.25E+OO 1.36E+01 2012 - TS Any Organ ADULT LIVER 5.74E-01 1.00E+01 5.74E+OO Critical Pathway: Fresh Water Fish - Comm. (FFCM) 2012 - TS Total Body ADULT 3.07E-01 3.00E+OO 1.02E+01 Critical Pathway: Fresh Water Fish - Comm. (FFCM)

Date/Time: xx/xx/20xx xx:xx seekeriD: Retdas Page - 3

Analyzed: xx/xx/xx xx:xx:xx by mwildfire SEEKER G A M M A A N A L Y S I S R E S U L T S PS Version 1.8.5 Entergy, Inc Grand Gulf Nuclear Station SAMPLE TANKS Liquid Sample Analysis Sample ID: FDST-A for Discharge (V-34 1st sample)

Sampling Start: 09/04/12 05:55:00 Counting Start: 09/04/12 06:08:30 Sampling Stop: 09/04/12 05:55:00 Decay Time. 2.25E-001 Hrs Buildup Time. O.OOE+OOO Hrs Live Time 1800 Sec Sample Size . . l.OOE+003 ml Real Time . 1801 Sec Collection Efficiency 1.0000 Spc. File . .20120904014.SPC Detector #: 4 (Detector 4)

Energy(keV)= 0.50 + O.SOO*Ch + 7.61E-08*ChA2 + O.OOE+OO*ChA3 09/04/12 FWHM(keV) 0.61 + O.Oll*En + 6.03E-04*EnA2 + 0.00E+00*EnA3 11/17/05 Where En= Sqrt(Energy in keV)

Search Sensitivity: 1.00 I Sigma Multiplier: 1.00 I Search Start/End: 0/4095 PEAK SEARCH RESULTS PK. ENERGY ADDRESS NET/MDA UN- C.L. BKG FWHM

1. (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 1 112.37 223.92 10 10 16 40 0.47 NET< CL 2 175.90 351.08 47 13 19 53 1.28 Wide Pk 3 427.79 855.19 45 11 15 33 0.96 4 463.41 926.48 25 9 13 22 0.93 5 486.72 973.13 20 8 11 20 1.17 6 661.64 1323.14 13 9 13 28 0.58 NET< CL 7 897.79 1795.61 17 9 14 28 0.69 8 1115.39 2230.92 39 8 9 12 1.83 9 1173.28 2346.71 209 15 8 9 1.46 10 1332.58 2665.33 167 14 7 8 1.46 Page 1

Analyzed: xx/xx/xx xx:xx:xx by mwildfire SEEKER L I B R A R Y S E A R C H R E S U L T S Version 2.3.1 Entergy, Inc Grand Gulf Nuclear Station Library File:. .LRWLIB.LIB (LRW Library)

Library Match Resolution. 1.2S I Decay Limit (Halflives) ......8.0 Minimum Score . 0.S0 I Decay Correction. . . . . . . . . . ON

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

LIBRARY SEARCH RESULTS Pk. Energy Net Expected Peaks  % Abn.

No. (keV) Counts Nuclide Net Counts Found Found SCORE FLAG 2 17S.90 47 SB-12S 21 3 of s 60.79 1.11 3 427.79 4S SB-12S 94 3 of s 60.79 1.11 4 463.41 2S ----- SPLIT 11 463.41 16 SB-12S 16 3 of s 60.79 1.11 AutoAdd 12 463.41 9-GS 138 1 of 3 22.44 0.72 AutoAdd s 486.72 20 LA-140 1 of s 31.0S 0.81 7 897.79 17 RB-88 1 of 2 39.62 0.90 8 111S.39 39 ZN-6S 1 of 2 100.00 1.00 NI-6S 1 of 2 38.69 0.39 9 1173.28 209 C0-60 186 2 of 2 100.00 1.so 10 1332.S8 167 C0-60 187 2 of 2 100.00 1.so Page 2

Analyzed: xx/xx/xx xx:xx:xx by mwildfire SEEKER F I N A L A C T I V I T Y R E P 0 R T Version 2.3.1 Entergy, Inc Grand Gulf Nuclear Station SAMPLE TANKS Liquid Sample Analysis Sample ID: FDST-A for Discharge (V-34 1st sample)

Sampling Start: 09/04/12 05:55:00 I Counting Start: 09/04/12 06:08:30 Sampling Stop: 09/04/12 05:55:00 I Decay Time. 2.25e-001 Hrs Buildup Time. . 0.OOe+OOO Hrs I Live Time . . 1800 Sec Sample Size . . . .. 1.00e+003 ml I Real Time . . 1801 Sec Collection Efficiency . . . . 1.0000 I Spectrum File .20120904014.SPC Cr. Level Confidence Interval: 95 % I Det. Limit Confidence Interval: 95 %

Detector #: 4 (Detector 4)

Efficiency File: 1LMBS004.EFF (1 Liter Marinelli Det 4)

Eff=l0A[-5.36E+01 +6.72E+Ol*L +-2.87E+Ol*LA2 +4.04E+00*LA3] 07/21/11 Eff.= EXP[9.73E-01 + -8.82E-01

• En+ O.OOE+OO

• EnA2] Above 290.00 keV Coinc. Sum File: ....1LMBS004.CSF (lLMB DET #4 CSF File)

Library File: ......LRWLIB.LIB (LRW Library)

LSF File: ........LRWLLD.LSF (LRWLLD)

MEASURED or MDA CONCENTRATIONS N L ENERGY E Concentration Critical Halflife L %

Nuclide (keV) T (uCi/ml MDA Level (hrs) D ECL SB-125 427.95 1.79E-07 +- 4.44E-08 1.27E-07 5.82E-08 2.43E+04 0.06 176.29 I.D. . . . . 2.43E+04 463.51 I.D. . . . . . 2.43E+04 LA-140 487.03 6.04E-08 +- 2.56E-08 7.96E-08 3.56E-08 3.07E+02 0.07 RB-88 898.03 7.85E-07 +- 4.28E-07 1.39E-06 6.32E-07 2.97E-01 ZN-65 1115.50 2.14E-07 +- 4.43E-08 1.08E-07 4.64E-08 5.85E+03 0.43 C0-60 Average:x 5.71E-07 +- 3.llE-08 4.62E+04 1.90 6.04E-07 +-1173.23 4.38E-08 5.14E-08 2.18E-08 4.62E+04 5.38E-07 +-1332.51 4.40E-08 5.48E-08 2.30E-08 4.62E+04

. CS-138 462.70 I.D. . 5.37E-01 MDAXE-133 81.00 6.70E-08 3.04E-08 1.27E+02 MDANP-239 106.13 8.08E-08 3.68E-08 5.65E+Ol MDACE-144 133.53 1.61E-07 7.34E-08 6.82E+03 MDAM0-99 140.51 1.99E-08 9.14E-09 6.62E+Ol MDA 2.03E-08 TC-99M 6.62E+Ol 9.30E-09 140.51 MDA 3.13E-08 1.41E-08 7.77E+02 MDACE-141 145.45 1.14E-07 5.17E-08 1.70E+Ol MDARE-188 155.03 5.22E-07 2.36E-07 1.40E+07 MDARA-226 185.99 2.24E-07 1.02E-07 5.42E+01 MDAXE-133M 233.20 2.45E-08 1.11E-08 9.08E+OO MDA 2.llE-07 249.79 XE-135 6.65E+02 9.26E-08 MDACR-51 320.07 3.18E-08 1.42E-08 1.93E+02 MDAI-131 364.48 3.42E-08 1.53E-08 1.38E+Ol ZN-69M 438.63 Page 3

Analyzed: xx/xx/xx xx:xx:xx by mwildfire

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

MEASURED or MDA CONCENTRATIONS

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

N L ENERGY E Concentration Critical Halflife L %

Nuclide (keV) T (uCi/ml MDA Level (hrs) D ECL W-187 479.57 MDA 1.09E-07 4.70E-08 2.39E+01 RU-103 497.08 MDA 3.49E-08 1.54E-08 9.44E+02 I-133 529.50 MDA 2.67E-08 1.11E-08 2.03E+01 BA-140 537.38 MDA 1.07E-07 4.35E-08 3.07E+02 AS-76 559.10 MDA 7.51E-08 3.29E-08 2.63E+01 CS-137 661.62 MDA 4.95E-08 2.20E-08 2.64E+OS ZR-95 724.18 MDA 6.78E-08 2.81E-08 1.55E+03 NB-95 765.82 MDA 3.49E-08 1.47E-08 8.44E+02 CS-134 795.76 MDA 5.22E-08 2.26E-08 1.81E+04 C0-58 810.75 MDA 4.70E-08 2.07E-08 1.70E+03 CS-136 818.50 MDA 4.43E-08 1.93E-08 3.12E+02 MN-54 834.81 MDA 4.93E-08 2.18E-08 7.49E+03 MN-56 846.60 MDA S.OSE-08 2.19E-08 2.58E+OO SC-46 889.26 MDA 5.22E-08 2.30E-08 2.01E+03 AG-llOM 937.48 MDA 1.52E-07 6.65E-08 6.00E+03 I-135 1260.41 MDA 1.44E-07 5.66E-08 6.61E+OO FE-59 1291.56 MDA 7.12E-08 2.57E-08 1.08E+03 NA-24 1368.55 MDA 2.39E-08 7.38E-09 1.50E+01 SR-92 1383.90 MDA 4.82E-08 1.84E-08 2.71E+OO SB-124 1691.04 MDA 7.74E-08 2.79E-08 1.44E+03 MEASURED TOTAL: 1.81E-06 +- 5.73E-07 uCi/ml 2.46E+OO

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

UNKNOWN,SUM or ESCAPE PEAKS

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

PK. ENERGY ADDRESS NET UN- C.L. BKG FWHM

1. (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 1 112.37 223.92 10 10 16 40 0.47 Deleted 4 463.41 926.48 25 9 13 22 0.93 SPLIT 6 661.64 1323.14 13 9 13 28 0.58 Deleted

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

NET/MDA PEAK RESULTS PK. ENERGY ADDRESS NET/MDA UN- C.L. BKG FWHM

1. (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 13 81.00 161.14 29 0 13 36 0.76 14 106.13 211.44 30 0 14 38 0.79 15 133.53 266.28 31 0 14 41 0.82 16 140.51 280.25 32 0 15 44 0.83 17 140.51 280.25 32 0 15 44 0.83 18 145.45 290.14 27 0 12 29 0.84 19 155.03 309.31 29 0 13 36 0.85 20 185.99 371.28 28 0 13 32 0.88 21 233.20 465.77 32 0 15 39 0.93 22 249.79 498.97 28 0 13 30 0.94 23 320.07 639.62 22 0 10 18 1.01 Page 4

Analyzed: xx/xx/xx xx:xx:xx by mwildfire

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

NET/MDA PEAK RESULTS

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

PK. ENERGY ADDRESS NET/MDA UN- C.L. BKG FWHM

1. (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 24 364.48 728.50 25 0 11 23 1.05 25 438.63 876.89 26 0 12 23 1.11 26 479.57 958.82 19 0 8 12 1.15 27 497.08 993.85 22 0 10 16 1.17 28 529.50 1058.73 16 0 7 9 1.19 29 537.38 1074.50 15 0 6 7 1.20 30 559.10 1117.96 22 0 10 18 1.22 31 661.62 1323.10 24 0 11 21 1.30 32 724.18 1448.27 16 0 7 8 1.35 33 765.82 1531.58 17 0 7 10 1.39 34 795.76 1591.49 20 0 9 14 1.41 35 810.75 1621.48 22 0 10 17 1.42 36 818.50 1636.98 21 0 9 15 1.43 37 834.81 1669.61 23 0 10 18 1.44 38 846.60 1693.20 20 0 9 14 1.45 39 889.26 1778.55 23 0 10 18 1.49 40 937.48 1875.02 22 0 10 18 1.52 41 1260.41 2520.99 13 0 5 4 1.77 42 1291.56 2583.29 10 0 4 2 1.80 43 1368.55 2737.28 7 0 2 1 1.86 44 1383.90 2767.98 11 0 4 4 1.87 45 1691.04 3382.20 10 0 3 2 2.10 Page 5

Analyzed: xx/xx/xx xx:xx:xx by mwildfire

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

R E T D A S A N A L Y S I S v2.4.0

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

SAMPLE TANKS Liquid Sample Analysis Nuclide uCi/ml +- uCi/ml Transfer?

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

SB-125 1.79e-07 4.44e-08 YES LA-140 6.04e-08 2.56e-08 YES RB-88 7.85e-07 4.28e-07 YES ZN-65 2.14e-07 4.43e-08 YES C0-60 5.71e-07 3.11e-08 YES TOTAL: 1.81e-06 Page 006

END OF FILE ATTACHMENTS File: 1 Sequence: 99999 Filename: 00xxxxxx-01.pdf Included in report.

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS5 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1AS5JPM

Title:

Emergency Event Classification Facility Number: _______ N/A

___ (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Validation Time: 10 Time Critical 15 min Alternate Path min Applicant: Examiner: _________________________

Performance Time: ________________________ Performance Rating: SAT UNSAT Comments:

Prepared By: Kyle Grillis 2/19/13 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Keith nd Huff 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 2/19/13 Page 8 of 298

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS5 Emergency Event Classification Setting: Classroom Type: SRO Task: SRO-A&E-015 K&A: 2.4.41 - 2.9/4.6 Safety Function: Emergency Procedures/Plan Performance: Actual Reference(s): 10-S-01-1 Handout(s): EAL flow charts from 10-S-01-1 10-S-01-1 (available)

1. Manipulations: N/A

1. Critical Steps: 1 Simulator Setup/Required Plant Conditions:

• None Safety Concerns:

• None Task Standard(s):

• Within 15 minutes, classifies the event as an UNUSUAL EVENT in accordance with EAL HU1.

Revision 0 2/19/13 Page 9 of 298

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS5 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The plant is at rated power.

• You have just validated a notification from the NRC Headquarters Operations Officer (HOO) that a single engine, four passenger plane has taken off from the Vicksburg, MS airport and the pilot intends to crash into a plant structure.

Estimated time of arrival of the aircraft is 19 minutes from now.

Initiating Cue(s):

• Classify the event.

• This JPM is time critical.

Revision 0 2/19/13 Page 10 of 298

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS5 Emergency Event Classification Notes: (Notes to Evaluator)

Task Overview: (Detailed description of task)

• An event classification JPM is required of all licensed SROs not qualified as an Emergency Director in accordance with the Emergency Preparedness Plan.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 10-S-01-1

• Classify the event as an UNSUAL EVENT Standard: EAL HU1 - Unusual Event Cue: None Notes: EALs HU1 (Unusual Event) and HA1 (Alert) discriminate between a small aircraft, like described in this JPM, and a large aircraft with potential for causing significant damage to the plant, which would be specifically communicated as an airliner by the NRC Headquarters Operations Officer and is specifically referenced in alert EAL HA1.

SAT / UNSAT Task Standard(s):

Within 15 minutes, classifies the event as an UNUSUAL EVENT in accordance with EAL HU1.

SAT / UNSAT Remember to record stop time Revision 0 2/19/13 Page 11 of 298

Date of Examination: 5/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1AS5 Follow-Up Questions & Answers:

Comments:

Revision 0 2/19/13 Page 12 of 298

Give this page to the student Initial Condition(s):

• The plant is at rated power.

• You have just validated a notification from the NRC Headquarters Operations Officer (HOO) that a single engine, four passenger plane has taken off from the Vicksburg, MS airport and the pilot intends to crash into a plant structure.

Estimated time of arrival of the aircraft is 19 minutes from now.

Initiating Cue(s):

• Classify the event.

• This JPM is time critical.

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1CR1JPM

Title:

Reset Recirc FCV Runback Facility Number: GJPM-OPS-B3313

___ (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 20 Min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: James nd Mergner 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 03/11/2013 Page 14 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Reset Recirc FCV Runback Setting: Simulator Type: RO Task: CRO-B33(2)-8; CRO-B33(2)-1 K&A: 202001 A4.02 (3.5/3.4) 202002 A4.08 (3.3/3.3)

Safety Function: 1 Performance: Actual Reference(s): 04-1-01-B33-1 (Reactor Recirculation System SOI)

Handout(s): 04-1-01-B33-1 Section 6.6

1. Manipulations: 4

1. Critical Steps: 4 Simulator Setup/Required Plant Conditions:

• Reset Simulator to IC-133 Safety Concerns:

• None Task Standard:

• Actions have been taken to reset Recirc FCVs runback.

Revision 0 03/11/2013 Page 15 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The plant was operating at full power when B Reactor Feed Pump (RFP) tripped.

• A and B Recirc FCVs runback has occurred.

• Reactor Engineering is assessing power distribution, FCBB and thermal limits

• Another reactor operator has the THI watch.

Initiating Cue(s):

• The CRS directs you to reset both the Recirc FCV A and B Runback in accordance with section 6.6 0f SOI 04-1-01-B33-1.

Revision 0 03/11/2013 Page 16 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Reset Recirc FCV Runback Notes: (Notes to Evaluator)

• All controls will be from panel P680 in the Main Control Room.

Task Overview: (Detailed description of task)

• The operator will reset a Recirc FCV runback following a trip of B RFP using plant procedures.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-B33-1 Step 6.6.1 Reactor vessel level is greater than low level alarm setpoint AND/OR Both Feed pumps are reset.

Standard: Verifies that reactor vessel level is greater than the low level alarm setpoint and/or both feed pumps are reset.

Cue: None.

Notes:

SAT / UNSAT Revision 0 03/11/2013 Page 17 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Step 2: 04-1-01-B33-1 Step 6.6.2 a

• USING Recirc Loop A(B) FLO CONT, LOWER signal output until one of the following occurs:

1) % Limiter Error is zero, OR

2) % Servo Error is zero, OR

3) FCV motion is noticed in the CLOSE direction, OR

4) A reduction in associated loop flow is noticed.

Standard: Using the Recirc Loop A(B) Flow Controller, lowers signal output until one of the following occurs:

1) % Limiter Error is zero, OR

2) % Servo Error is zero, OR

3) FCV motion is noticed in the CLOSE direction, OR

4) A reduction in associated loop flow is noticed.

Cue: The CRS give permission to use fast Detent.

Notes: Student may perform actions on A or B FCV first, the order is not required SAT / UNSAT Revision 0 03/11/2013 Page 18 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Step 3: 04-1-01-B33-1 Step 6.6.2 b

• PRESS RECIRC PUMP A(B) CAV INTLK RESET pushbutton.

Standard: Depresses RECIRC PMP A(B) CAV INTLK RESET pusbutton.

Cue: None Notes: The student must depress the reset pushbutton for the valve that was manipulated.

SAT / UNSAT Step 4: 04-1-01-B33-1 Step 6.6.2 c OBSERVE "RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP" annunciator Resets.

Standard: Verifies that the P680-3A-D1(4A1-C4), RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP alarm resets.

Cue: None Notes: The student must verify the alarm resets for the valve that was manipulated.

SAT / UNSAT Step 5: 04-1-01-B33-1 Step 6.6.2 a Revision 0 03/11/2013 Page 19 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1

• USING Recirc Loop A(B) FLO CONT, LOWER signal output until one of the following occurs:

1) % Limiter Error is zero, OR

2) % Servo Error is zero, OR

3) FCV motion is noticed in the CLOSE direction, OR

4) A reduction in associated loop flow is noticed.

Standard: Using the Recirc Loop A(B) Flow Controller, lowers signal output until one of the following occurs:

1) % Limiter Error is zero, OR

2) % Servo Error is zero, OR

3) FCV motion is noticed in the CLOSE direction, OR

4) A reduction in associated loop flow is noticed.

Cue: The CRS give permission to use fast Detent.

Notes: Student performs actions on the other FCV (A or B).

SAT / UNSAT Revision 0 03/11/2013 Page 20 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Step 6: 04-1-01-B33-1 Step 6.6.2 b

• PRESS RECIRC PUMP A(B) CAV INTLK RESET pushbutton.

Standard: Depresses RECIRC PMP A(B) CAV INTLK RESET pusbutton.

Cue: None Notes: The student must depress the reset pushbutton for the valve that was manipulated.

SAT / UNSAT Step 7: 04-1-01-B33-1 Step 6.6.2 c OBSERVE "RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP" annunciator Resets.

Standard: Verifies that the P680-3A-D1(4A1-C4), RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP alarm resets.

Cue: None Notes: The student must verify the alarm resets for the valve that was manipulated.

SAT / UNSAT Revision 0 03/11/2013 Page 21 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Task Standard(s):

Actions have been taken to reset Recirc FCV runback per 04-1-01-B33-1 SOI with both RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP alarms reset.

SAT / UNSAT Remember to record stop time Revision 0 03/11/2013 Page 22 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR1 Follow-Up Questions & Answers:

Comments:

Revision 0 03/11/2013 Page 23 of 298

Give this page to the student Initial Condition(s):

• The plant was operating at full power when B Reactor Feed Pump (RFP) tripped.

• A and B Recirc FCVs runback has occurred.

• Reactor Engineering is assessing power distribution, FCBB and thermal limits

• Another reactor operator has the THI watch.

Initiating Cue(s):

• The CRS directs you to reset both the Recirc FCV A and B Runback in accordance with section 6.6 0f SOI 04-1-01-B33-1.

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1CR2 JPM

Title:

Ali gn Buses 16AB and 17AC to ESF Transformer 21 Facility Number: GLP-OPS-R2734 _________ (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Gabe nd Hargrove 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 02/07/2013 Page 25 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Align Buses 16AB and 17AC to ESF Transformer 21 Setting: Simulator Type: RO Task: CRO-R20/27-003, 004, 010 K&A: 262001: A4.01 - 3.4/3.7; A4.02 - 3.4/3.4 Safety Function: 6 Performance: Actual Reference(s): 04-1-01-R21-16 section 4.3; 04-1-01-R21-17 section 4.3; 05-1-02-I-4 Loss of AC Power Handout(s): 04-1-01-R21-16 section 4.3 04-1-01-R21-17 section 4.3

1. Manipulations: 6

1. Critical Steps: 5 Simulator Setup/Required Plant Conditions:

• Reset Simulator to IC-136

• Run Schedule file GJPM-OPS-2012-1CR2 Safety Concerns:

• None Task Standard:

• ESF buses 16AB and 17AC were aligned to ESF Transformer 21 IAW section 4.3 of 04 01-R21-16 and 04-1-01-R21-17, respectively, and bus 17AC has been re-energized following trip of ESF 21 and failure of Division III Diesel Generator IAW 05-1-02-I-4 section 2.0.

Revision 0 02/07/2013 Page 26 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The plant is at rated power.

• ESF Transformer 21 has undergone preventive maintenance and has been re-energized.

• Bus 16AB is currently aligned to ESF Transformer 12.

• Bus 17AC is currently aligned to ESF Transformer 11.

• All Prerequisites are complete Initiating Cue(s):

• The CRS directs you to re-align buses 16AB and 17AC to be supplied by ESF Transformer 21 in accordance with sections 4.3 of 04-1 R21-16 and 04-1-01-R21-17.

• The prerequisites of sections 4.3.1 of both 04-1-01-R21-16 and 04-1-01-R21-17 have been verified to be met.

• Bus 16AB will be transferred first.

Revision 0 02/07/2013 Page 27 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Align Buses 16AB and 17AC to ESF Transformer 21 Notes: (Notes to Evaluator)

• All controls will be from panels P864, P807 and P601 in the Main Control Room.

Task Overview: (Detailed description of task)

• This task is to align ESF Transformer 21 to supply ESF buses 16AB and 17AC, the normal alignment.

• The fault in this task is when the alignment is completed, ESF 21 supplying ESF buses 16AB and 17AC will trip.

Division 2 Diesel Generator will automatically re-energize buses 16AB, but, Division 3 Diesel Generator will Trip. The candidate will be required to manually re-energize bus 17AC in accordance with Loss of AC Power ONEP 05-1-02-I-4 section 2.0.

Revision 0 02/07/2013 Page 28 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-R21-16 Step 4.3.2 a Ensure ESF XFMR 21 energized up to Bus 16AB Feeder Breaker 152-1614.

1. CHECK CLOSED J5206 FDR to XFMR ST-21

2. CHECK CLOSED 552-2105 Bus 21R FDR FRM SFMR ST-21

3. CHECK indicator 2R25-R603 34.5 kV voltage

4. CHECK CLOSED 552-2104 Bus 21R FDR FRM XFMR ESF 21

5. CHECK CLOSED 152-2901 FDR FRM XFMR ESF 21

6. CHECK ENERGIZED status light ON Standard: Verifies ESF XFMR 21 is energized up to Bus 16AB Feeder Breaker 152-1614 by checking the following:

• Checks indicating lights for disconnect SVC XFMR 21 DISC J5206 indicate closed (P807-3B)

• Checks indicating lights for circuit breaker 552-2105 BUS 21R FDR FM XFMR ST-21 indicate closed (P807-4C)

• Observes indicator 34.5KV BUS 21R VOLTS 2R25-R603 indicates approximately 34.5KV (P807-4B)

• Checks indicating lights for circuit breaker 552-2104 ESF XFMR 21 FDR FM BUS 21R indicate closed (P807-5C)

• Checks indicating lights for circuit breaker 152-2901 BUS 27AC/15AA/16AB FDR FM ESF XFMR 21 indicate closed (P807-5C)

• Checks status light (purple light) ESF XFMR NO. 21 ENERGIZED is on for 152-1614 (P864-2C)

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 29 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Step 2: 04-1-01-R21-16 Step 4.3.2 b

• TURN ON: Sync switch for breaker 152-1614 BUS 16AB FDR FRM XFMR ESF 21 Standard: Turns on Sync Switch for 152-1614 by turning handswitch SYNC CONT FDR 152-1614 clockwise to ON (P864-2C).

Cue: None Notes:

SAT / UNSAT Step 3: 04-1-01-R21-16 Step 4.3.2 c CHECK that the sync scope comes up to 12 oclock +/- 10°.

Standard: Observes sync scope for breaker 152-1614 comes to 12 oclock +/- 10° position P864-2B).

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 30 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Step 4: 04-1-01-R21-16 Step 4.3.2 d

• ATTEMPT to CLOSE 152-1614 Bus 16AB feeder from ESF 21.

Standard: Closes circuit breaker 152-1614 by turning handswitch BUS 16AB FDR FM ESF XFMR 21 (P864-2C) to CLOSE and observing breaker closes, then releases the handswitch.

Cue: None Notes:

SAT / UNSAT Step 5: 04-1-01-R21-16 Step 4.3.2 e If 152-1614 closes and the original feeder breaker Trips, then bus is energized and transfer is complete.

Standard: Checks circuit breaker 152-1611 BUS 16AB FDR FM ESF XFMR 12 opens (P864-2C).

Cue: None Notes: Student does not need to perform steps 4.3.2g through 4.3.2k.

SAT / UNSAT Revision 0 02/07/2013 Page 31 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Step 6: 04-1-01-R21-16 Step 4.3.2 f PLACE sync switch to OFF.

Standard: Turns off Sync Switch for 152-1614 by turning handswitch SYNC CONT FDR 152-1614 counter-clockwise to OFF (P864-2C).

Cue: None Notes: Student does not need to perform steps 4.3.2g through 4.3.2k.

SAT / UNSAT Revision 0 02/07/2013 Page 32 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Step 7: 04-1-01-R21-17 Step 4.3.2 a Ensure ESF XFMR 21 energized up to Bus Feeder Breaker 152-1705.

1. CHECK CLOSED J5206 FDR to XFMR ST-21

2. CHECK CLOSED 552-2105 Bus 21R FDR FRM SFMR ST-21

3. CHECK indicator 2R25-R603 34.5 kV voltage

4. CHECK CLOSED 552-2104 Bus 21R FDR FRM XFMR ESF 21

5. CHECK CLOSED 152-2902 FDR FRM XFMR ESF 21

6. CHECK ENERGIZED status light ON Standard: Verifies ESF XFMR 21 is energized up to Bus 17AC Feeder Breaker 152-1705 by checking the following:

• Checks indicating lights for disconnect SVC XFMR 21 DISC J5206 indicate closed (P807-3B)

• Checks indicating lights for circuit breaker 552-2105 BUS 21R FDR FM XFMR ST-21 indicate closed (P807-4C)

• Observes indicator 34.5KV BUS 21R VOLTS 2R25-R603 indicates approximately 34.5KV (P807-4B)

• Checks indicating lights for circuit breaker 552-2104 ESF XFMR 21 FDR FM BUS 21R indicate closed (P807-5C)

• Checks indicating lights for circuit breaker 152-2902 BUS 25AA/26AB/17AC FDR FM ESF XFMR 21 indicate closed (P807-5C)

• Checks status light (purple light) ESF XFMR NO. 21 ENERGIZED is on for 152-1705 (P601-16C)

Cue: None Notes: Steps 1 - 4 were performed during the 16AB Bus transfer, the student may check them again.

SAT / UNSAT Revision 0 02/07/2013 Page 33 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Step 8: 04-1-01-R21-17 Step 4.3.2 b

• TURN ON: Sync switch for breaker 152-1705 BUS 17AC FDR FRM XFMR ESF 21 Standard: Turns on Sync Switch for 152-1705 by turning handswitch SYNC CONT FDR 152-1705 clockwise to ON (P601-16C).

Cue: None Notes:

SAT / UNSAT Step 9: 04-1-01-R21-17 Step 4.3.2 c CHECK that the sync scope comes up to 12 oclock +/- 10°.

Standard: Observes sync scope for breaker 152-1705 comes to 12 oclock +/- 10° position (P601-16B).

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 34 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Step 10: 04-1-01-R21-17 Step 4.3.2 d

• ATTEMPT to CLOSE 152-1705 BUS 17AC feeder from ESF 21.

Standard: Closes circuit breaker 152-1705 by turning handswitch 17AC FDR FRM ESF XFMR 21 (P601-16C) to CLOSE and observing breaker closes, then releases the handswitch.

Cue: None Notes: After 152-1705 closes, Transformer ESF 21 will trip on Sudden Pressure.

SAT / UNSAT Step 11: 05-1-02-I-4 Step 4.0 Recognizes loss of ESF 21 and resulting loss of power to major buses 16AB and 17AC.

Standard: Candidate diagnoses loss of ESF 21 by loss of power alarms for buses 16AB and 17AC on P864-2A and P601-16A or ESF alarms on P807 Cue: If necessary, cue the candidate to respond to the power loss. As CRS, direct the candidate to take the immediate operator actions of the Loss of AC Power ONEP.

Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 35 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Step 12: 05-1-02-I-4 Step 4.0 Recognizes bus 16AB is re-energized by Division 2 Diesel Generator and 17AC is NOT energized with the Division 3 (HPCS) Diesel Generator Tripped.

Standard: Verifies bus 16AB has been re-energized by Division 2 Diesel Generator by various indications which may include observing bus 16AB undervoltage alarms on P864-2A are slow flashing and/or approximately 4.2 KV indicated on 4.16KV BUS 16AB voltmeter R21R615B (P864-2B). 17AC is de-energized by observing 17AC undervoltage alarms on P601-16A are ON and HPCS DIESEL GEN TRIP alarm is ON.

Cue: If required cue candidate to perform immediate operator actions for the Loss of AC Power ONEP.

Notes:

SAT / UNSAT Step 13: 05-1-02-I-4 Step 2.1

• Re-energizes Bus 17AC by closing an alternate feeder breaker.

Standard: Candidate closes either alternate feeder breaker from ESF 11 (152-1706) or ESF 12 (152-1704)

Cue: When Bus 17AC has been re-energized by an alternate feeder the evaluator will stop the JPM.

Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 36 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Task Standard(s):

• ESF buses 16AB and 17AC were aligned to ESF Transformer 21 IAW section 4.3 of 04 01-R21-16 and 04-1-01-R21-17, respectively, and bus 17AC has been re-energized following trip of ESF 21 and failure of Division III Diesel Generator IAW 05-1-02-I-4 section 2.0.

SAT / UNSAT Remember to record stop time Revision 0 02/07/2013 Page 37 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR2 Follow-Up Questions & Answers:

Comments:

Revision 0 02/07/2013 Page 38 of 298

Give this page to the student Initial Condition(s):

• The plant is at rated power.

• ESF Transformer 21 has undergone preventive maintenance and has been re-energized.

• Bus 16AB is currently aligned to ESF Transformer 12.

• Bus 17AC is currently aligned to ESF Transformer 11.

• All Prerequisites are complete Initiating Cue(s):

• The CRS directs you to re-align buses 16AB and 17AC to be supplied by ESF Transformer 21 in accordance with sections 4.3 of 04-1 R21-16 and 04-1-01-R21-17.

• The prerequisites of sections 4.3.1 of both 04-1-01-R21-16 and 04-1-01-R21-17 have been verified to be met.

• Bus 16AB will be transferred first.

PLANT OPERATIONS MANUAL Volume 06 06-OP-1C11-M-0001 Section 01 Revision: 107 Date:

CONTINUOUS USE SURVEILLANCE PROCEDURE CONTROL ROD OPERABILITY SAFETY RELATED Prepared: / DESKTOP Type of Validation Reviewed:

Technical Approved:

Assistant Operations Manager- Support or Shift List of Effective Pages:

Pages 1-7 Attachment I List of TCNs Incorporated:

Revision TCN 20 None 21 None 22 1,2,3 23 4 24 None 25 5,6 26 7 100-107 None X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: i 06-OP-1C11-M-0001 RPTS FORM REQUIR ED REVIEW PERFORMED PAD 50.59 Evaluation (Check all that apply) (EN-LI-100) (EN-LI-101) 72.48 Evaluation 50.54 Evaluation Transmit applicable Review Form as a (EN-LI-112) (EN-NS-210) separate record along with procedure to PAD Not Required(EN-LI-100 or 01-S-02-3)

Document Control. Process Applicability Excluded Editorial Change ISI/IST Implementation TCN Incorporation or Auto Rev.

Other Process-Number:____________________

PAD Reviewer: ________________________/________

(for PAD Not Required) Signature/Date Cross-Discipline review required? ( ) Yes (Note affected Departments Below)

(X) No Preparer Initials>>>

Department Cross-Discipline Reviews Needed Signoff (signed, electronic, telcon)

Does this directive contain Tech Spec Triggers? ( ) YES (X) NO X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: ii 06-OP-1C11-M-0001 REQUIREMENTS CROSS-REFERENCE LIST Requirement Implemented by Directive Directive Paragraph Number Name Paragraph Number That Implements Requirement Tech Spec 5.5.6

• TRM 7.6.3.3

• Tech Spec SR 3.1.3.3

• Tech Spec SR 3.1.3.5

• GE SIL #226, Att A,Section IV 4.6 GE SIL #538 2.10 HPES Eval 91-011 Recommendation #2 4.10 GNRO 93/00068 93-04-01.IV.S2 *

• Covered by directive as a whole or by various paragraphs of the directive.

NOTE The Equipment Database (EDB) Request statement is applicable only to Volume 06 and 07 maintenance directives.

EDB Change Request generated and the backup documentation available for setpoint and/or calibration data only Yes N/A EDBCR #

Current Revision Statement Revision 107:

• Clarifies that -0.5 kW/ft margin for partially inserted rods does not apply to cells containing declared failed fuel.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: 1 06-OP-1C11-M-0001 1.0 PURPOSE 1.1 To demonstrate the operability of each withdrawn Operable control rod regarding its ability to be inserted WHEN above the low power setpoint of the rod pattern controller by inserting each withdrawn control rod at least one notch at least once per 31 days per Tech Spec SR 3.1.3.3 AND within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> WHEN any control rod is discovered to be stuck concurrent with THERMAL POWER greater than the actual LPSP of the RPC per Tech Spec 3.1.3. Also, that the indicated control rod position changes during the movement.

1.2 To ensure control rod coupling per Tech Spec SR 3.1.3.5 AND full out indication each time a control rod is withdrawn to the "full out" position.

1.3 To establish data regarding CRD mechanism seal degradation.

1.4 Changes required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement Should NOT be deleted.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Control rod movement Must be performed in Individual Drive mode, unless otherwise specified by Reactor Engineering.

2.2 Normal control rod notch movement is performed by notching in one notch AND THEN notching out to the original starting position. As an alternate method, control rod movement May be performed in conjunction with an approved control rod pattern adjustment, sequence exchange, OR scram time testing as long as these control rods are inserted at some point during the rod movement.

2.3 WHENEVER a control rod is being moved, OBSERVE the neutron monitoring instrumentation.

2.4 IF using this test to demonstrate operability of a single component, N/A steps NOT associated with that component AND make a notation on the Data Package Cover Sheet.

2.5 Steps marked with a pound sign (#) are recorded on Data Sheet I.

2.6 For Inop control rods OR those at Position 00, PLACE N/A on Data Sheet I (per Step 5.3.1).

2.7 Steps marked with a dollar sign ($) are required to be completed for Technical Specifications Acceptance Criteria.

2.8 IF procedural steps CANNOT be completed as stated OR IF any other problem develops during this test, NOTIFY Shift Supervision.

2.9 IF any withdrawn control rod fails the Acceptance Criteria, REFER to Tech Spec 3.1.3 for required actions.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: 2 06-OP-1C11-M-0001 2.10 IF during control rod movement, high withdrawal speeds OR high insert stall flows are experienced, this Could be symptoms of a failed CRD cooling water orifice. NOTIFY System Engineering AND ISSUE a WO identifying the concern.

2.11 During the course of this test, IF a control rod is inadvertently notched in two notches, IMMEDIATELY RETURN the rod to its original position AND NOTIFY Reactor Engineering.

2.12 The following alarms AND lights May be encountered during this procedure (all indication is on 1H13-P680):

ALARM/LIGHT LOCATION ACTION INSERT BLOCK 6C Rod Motion Cont WITHDRAWN BLOCK 6C Determine Cause AND Correct INSERT INHIBIT 6C Rod Motion Cont WITHDRAW INHIBIT 6C Determine Cause AND Correct CONT ROD WITHDRAWAL BLOCK 4A2-C5 Determine Cause AND Correct Rx Power has decreased RX PWR LO 4A2-D5 below LPAP 3.0 REQUIRED MATERIAL AND TEST EQUIPMENT 3.1 None X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: 3 06-OP-1C11-M-0001

1. 4.0 PREREQUISITES AND PLANT CONDITIONS 4.1 Power level is above Low Power Setpoint (LPSP) of Rod Pattern Control System.

4.2 Control Rod Drive Hydraulics System is operating in accordance with SOI 04-1-01-C11-1.

4.3 Rod Control and Information System is operating in accordance with SOI 04-1-01-C11-2.

4.4 Reactor Engineering is notified before performance of this test.

4.5 OBTAIN an edit of Control Rod positions, IF the core monitoring computer is available.

4.6 REDUCE core thermal power to the level specified by Reactor Engineering USING recirculation flow reduction. Since power peaking off the control rod tip in combination with axial power shape changes due to rod insertion Can cause power increases that violate PCIOMR, exercising CRDs Should NOT be performed at the preconditioned envelope. For control rods which May cause nodal power to rise above the envelope, core flow Should be reduced as necessary to provide sufficient margin to the envelope. Flow reduction Should give a 0.5 kW/ft margin to the envelope before insertion except for fuel bundle(s) currently under failed fuel monitoring. Refer to section 5.7 of Reference 6.8 for failed fuel monitoring requirements.

4.7 Alternating rod position data is selected via DATA MODE push-button before control rod movement.

1. 4.8 RECORD CRD drive pressure (Must be 240 to 260 psi).

1. 4.9 RECORD rod sequence selected.

4.10 ENTER "As Found" positions on Data Sheet I for all control rods NOT at Position 48 to have those control rods flagged before the start of control rod movement.

4.11 IF procedure is being performed in conjunction with control rod pattern adjustment, sequence exchange, OR scram time testing, THEN ENTER N/A for all control rods that are to be inserted at least one notch during the pattern adjustment, sequence exchange, OR scram time testing.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: 4 06-OP-1C11-M-0001 5.0 INSTRUCTIONS 5.1 OBTAIN Shift Supervisions permission to perform test.

5.1.1 Shift Supervision Should SIGN Section 2.2 to ensure that the page check has been completed AND all pages are included.

5.1.2 Performer to RECORD Test Start Time on Data Package Cover Sheet.

5.2 On 1H13-P680-6C, SELECT individual drive USING DRIVE MODE push-button on the operator's control console.

5.3 PERFORM the following steps for notch movement of each withdrawn control rod:

NOTE The order of selection is unimportant as long as every rod is tested.

Placekeeping for this surveillance Will be accomplished by circle AND slashing steps 5.3.2 through 5.3.7 during performance of the first control rod. Placekeeping for each subsequent control rod Will be accomplished by initialing each step as performed in the data sheet. The data sheet contains an abbreviated version of these instructions for each control rod in the correct sequence. This method has been determined to be an acceptable alternative to the normal circle slash method of placekeeping.

1. 5.3.1 IF a control rod is fully inserted, THEN MARK N/A on Data Sheet I for that control rod.

5.3.2 On 1H13-P680-6C, SELECT a control rod to test.

1. a. HAVE an independent RO, SRO, OR STA VERIFY that the correct control rod is selected.

1. 5.3.3 RECORD "As Found" position.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: 5 06-OP-1C11-M-0001 NOTE USE PDS computer for stall flow (BARS) IF available.

5.3.4 PERFORM the following for the selected control rod:

$# a. For rods at Position 48, OBTAIN withdraw stall flow by DEPRESSING "WITHDRAW" AND "CONT WITHDRAW" push-buttons simultaneously.

HOLD signal until a stable drive pressure of 240 to 260 psi is observed. IF stable drive pressure is NOT 240 to 260, THEN RECORD stable drive pressure in stall flow, next to stall flow. RECORD stall flow for each rod at Position 48.

$# b. NOTCH the selected control rod in one notch.

$# c. RETURN the selected control rod to the original position. VERIFY rod position indication changes for the selected control rod by OBSERVING the rod display module on 1H13-P680.

$# d. IF moving control rod to Position 48, THEN PERFORM a coupling check AND VERIFY Full Out indication. INITIAL on Data Sheet I.

(N/A block IF rod NOT left at Notch 48.)

1. 5.3.5 RECORD "As Left" position.

1. 5.3.6 INITIAL "Performed by" block on Data Sheet I.

1. 5.3.7 HAVE an independent RO, SRO, OR STA VERIFY correct.

5.3.8 AFTER all banked rods are exercised, THEN RAISE recirculation flow to bring core thermal power back to its desired value per 03-1-01-2 under direction of the Shift Supervision.

5.3.9 REPEAT Steps 5.3.1 through 5.3.7 until all partially OR fully withdrawn control rods are exercised one notch AND recorded on Data Sheet I.

5.3.10 OBTAIN an edit of Control Rod positions, IF available, AND THEN COMPARE to original to VERIFY all rods RETURNED to original position.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: 6 06-OP-1C11-M-0001

1. 5.3.11 On local CRD temperature recorder, OBTAIN CRD drive temperatures AND RECORD on Data Sheet II. IF desired, THEN an "All Points" printout May be obtained by PERFORMING the following:

a. ADJUST recorder paper to top of perforation.

b. DEPRESS BURST PRINT key.

c. USE arrow keys AND SELECT ALL POINTS.

d. DEPRESS ENTER key AND REMOVE printout WHEN completed. ROLL DOWN paper into catch tray.

NOTE The paper is NCR paper AND Will mark up WHEN touched AND Does NOT reproduce well. Therefore, readings Must be transferred to Data Sheet II.

e. CIRCLE all temperature readings above 250°F on Data Sheet II.

COMMENT on surveillance cover sheet for system engineer to add CRDM to be trended. (A CR Should be written for all CRDMs above 400°F

$# 5.4 IF procedure is being performed in conjunction with control rod pattern adjustment, sequence exchange, OR scram time testing, THEN ATTACH a copy of the pull sheets to include all control rods that are N/Ad on Data Sheet I. Shift Supervisions signature verifies that all control rods N/Aed on Data Sheet I have been inserted at least one notch per the attached pull sheets. (Otherwise this step May be N/Aed.)

5.5 IF any control rod is immovable before the start of this procedure OR is identified as immovable per Step 5.3.4, THEN STATE this under the "Comments" section on the Data Package Cover Sheet along with a statement that this procedure Must be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of the immovable control rod WHEN above the low power setpoint per TS 3.1.3.

5.6 INFORM Shift Supervision WHEN this test is completed. Shift Supervision's signature is required on Data Package Cover Sheet.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE

Title:

Control Rod Operability No.: Revision: 107 Page: 7 06-OP-1C11-M-0001

6.0 REFERENCES

6.1 SOI 04-1-01-C11-1 6.2 SOI 04-1-01-C11-2 6.3 GGNS Technical Specifications 3.1.3, SR 3.1.3.2, SR 3.1.3.3, SR 3.1.3.5 6.4 GGNS FSAR Section 4.6.3.1.1.5 6.5 Bechtel Schematic E-1165, Rev 7 6.6 IPC - 85/2102 6.7 CR 2003-0218 6.8 EN-RE-205, Fuel Preconditioning (BWR)

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 1 of 31 Model WO# 50286898 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED

Title:

Control Rod Operability Technical Specifications: 3.1.3, SR 3.1.3.3, SR 3.1.3.5 1.0 IMPACT STATEMENT 1.1 Performance of this procedure results in control rods being notched in one notch only AND returned to their original position (only WHEN above the low power setpoint of the RPCS).

Reactor Engineering Must be notified before performing this test.

2.0 PROCEDURE 2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Procedure page checked Super Visor / XX/XX/XXXX Shift Supervision / Date 2.3 Test Start Time / /

Performer / Date / Time 3.0 TEST RESULTS 3.1 Test Completion: (CHECK one in each category.)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [ ]

All other steps/data Acceptable [ ] Unacceptable [ ]

3.2 Comments

3.3 Test performed by Date/Time /

4.0 DEFICIENCIES CR Issued # WR Issued # LCO Entered #

5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supervision Date Comments:

CONCURRENCE Operations Management Date Engineering Review Required X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 2 of 31 Page XRef DATA SHEET I CONTROL ROD OPERABILITY SAFETY RELATED INITIALS 4.0 All prerequisites completed SDR 4.8 CRD drive pressure 257 PSIG SDR 4.9 Sequence selected A SDR Acceptance Criteria: All fully withdrawn control rods Shall be demonstrated operable by inserting each control rod at least one notch AND having the position indication change accordingly.

A coupling check Shall be considered to be satisfactory IF first the control rod can be determined to be fully withdrawn as evidenced by either a digital indication of 48 from either Channel A OR B OR a red LED full out indicator from either Channel A OR B AND THEN the absence of the rod over travel annunciator WHEN attempting to withdraw the rod past the fully withdrawn position.

Control position indication Shall be considered satisfactory IF a digital indication of 48is available from either Channel A OR B whenever a red LED full-out indicator is lit from either Channel A OR B.

CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 20E 61Q 24F 61Q 28G 61Q 32H 61Q 36J 61Q X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 3 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 40K 61Q 44L 61Q 12C 57P 16D 57P 20E 57P 24F 57P 28G 57P 32H 57P 36J 57P 40K 57P 44L 57P X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 4 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 48M 57P 52N 57P 08B 53N 12C 53N 16D 53N 20E 53N 24F 53N 28G 53N X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 5 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 32H 53N 36J 53N 40K 53N 44L 53N 48M 53N 52N 53N 56P 53N 08B 49M X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 6 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 12C 49M 16D 49M 12 20E 49M 24F 49M 28G 49M 32H 49M 12 36J 49M 40K 49M X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 7 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 44L 49M 48M 49M 12 52N 49M 56P 49M 04A 45L 08B 45L 12C 45L 16D 45L X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 8 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 20E 45L 24F 45L 28G 45L 32H 45L 36J 45L 40K 45L 44L 45L 48M 45L X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 9 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 52N 45L 56P 45L 60Q 45L 04A 41K 08B 41K 12C 41K 16D 41K 20E 41K X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 10 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 24F 41K 06 28G 41K 32H 41K 36J 41K 40K 41K 06 44L 41K 48M 41K 52N 41K X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 11 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 56P 41K 60Q 41K 04A 37J 08B 37J 12C 37J 16D 37J 20E 37J 24F 37J X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 12 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 28G 37J 32H 37J 36J 37J 40K 37J 44L 37J 48M 37J 52N 37J 56P 37J X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 13 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 60Q 37J 04A 33H 08B 33H 12C 33H 16D 33H 12 20E 33H 24F 33H 28G 33H X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 14 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 32H 33H 14 36J 33H 40K 33H 44L 33H 48M 33H 12 52N 33H 56P 33H 60Q 33H X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 15 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 04A 29G 08B 29G 12C 29G 16D 29G 20E 29G 24F 29G 28G 29G 32H 29G X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 16 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 36J 29G 40K 29G 44L 29G 48M 29G 52N 29G 56P 29G 60Q 29G 04A 25F X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 17 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 08B 25F 12C 25F 16D 25F 20E 25F 24F 25F 28G 25F 06 32H 25F 36J 25F X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 18 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 40K 25F 06 44L 25F 48M 25F 52N 25F 56P 25F 60Q 25F 04A 21E 08B 21E X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 19 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 12C 21E 16D 21E 20E 21E 24F 21E 28G 21E 32H 21E 36J 21E 40K 21E X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 20 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 44L 21E 48M 21E 52N 21E 56P 21E 60Q 21E 08B 17D 12C 17D X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 21 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 16D 17D 12 20E 17D 24F 17D 28G 17D 32H 17D 12 36J 17D 40K 17D X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 22 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 44L 17D 48M 17D 12 52N 17D 56P 17D 08B 13C 12C 13C 16D 13C X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 23 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 20E 13C 24F 13C 28G 13C 32H 13C 36J 13C 40K 13C 44L 13C X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 24 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 48M 13C 52N 13C 56P 13C 12C 09B 16D 09B 20E 09B 24F 09B X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 25 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 28G 09B 32H 09B 36J 09B 40K 09B 44L 09B 48M 09B 52N 09B X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 26 of 31 Page XRef DATA SHEET I (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD ROD AS WITHDRAW ROD STROKED ROD AS NUMBER SELECTED FOUND STALL COUPLED/ LEFT VERIFIED POSITION FLOW IN ONE OUT ONE FULL OUT POSITION PERFORMER VERIFIER COLUMN ROW CORRECT GPM NOTCH NOTCH INDICATION 5.3.2a 5.3.3 5.3.4a $ 5.3.4b $ 5.3.4c $ 5.3.4d 5.3.5 5.3.6 5.3.7 20E 05A 24F 05A 28G 05A 32H 05A 36J 05A 40K 05A 44L 05A

$ 5.4 All control rods verified inserted at least one notch AND copy of pull sheets attached Shift Supervision X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 27 of 31 Page XRef DATA SHEET II CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD CONTROL ROD NUMBER CRD TEMP NUMBER CRD TEMP POINT ID COL ROW 5.3.11 POINT ID COL ROW 5.3.11 110 04 45 131 12 45 111 04 41 132 12 41 112 04 37 133 12 37 113 04 33 134 12 33 114 04 29 135 12 29 115 04 25 136 12 25 116 04 21 137 12 21 117 08 53 138 12 17 118 08 49 139 12 13 119 08 45 140 12 09 120 08 41 141 16 57 121 08 37 142 16 53 122 08 33 143 16 49 123 08 29 144 16 45 124 08 25 145 16 41 125 08 21 146 16 37 126 08 17 147 16 33 127 08 13 148 16 29 128 12 57 149 16 25 129 12 53 150 16 21 130 12 49 151 16 17 152 16 13 Circle temperature readings above 250°F.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 28 of 31 Page XRef DATA SHEET II (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD CONTROL ROD NUMBER CRD TEMP NUMBER CRD TEMP POINT ID COL ROW 5.3.11 POINT ID COL ROW 5.3.11 153 16 09 214 24 41 154 20 61 215 24 37 155 20 57 216 24 33 156 20 53 217 24 29 157 20 49 218 24 25 158 20 45 219 24 21 159 20 41 220 24 17 160 20 37 221 24 13 161 20 33 222 24 09 162 20 29 223 24 05 163 20 25 224 28 61 164 20 21 225 28 57 165 20 17 226 28 53 166 20 13 227 28 49 167 20 09 228 28 45 168 20 05 229 28 41 169 24 61 230 28 37 210 24 57 231 28 33 211 24 53 232 28 29 212 24 49 233 28 25 213 24 45 234 28 21 Circle temperature readings above 250°F.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 29 of 31 Page XRef DATA SHEET II (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD CONTROL ROD NUMBER CRD TEMP NUMBER CRD TEMP POINT ID COL ROW 5.3.11 POINT ID COL ROW 5.3.11 235 28 17 256 36 53 236 28 13 257 36 49 237 28 09 258 36 45 238 28 05 259 36 41 239 32 61 260 36 37 240 32 57 261 36 33 241 32 53 262 36 29 242 32 49 263 36 25 243 32 45 264 36 21 244 32 41 310 36 17 245 32 37 311 36 13 246 32 33 312 36 09 247 32 29 313 36 05 248 32 25 314 40 61 249 32 21 315 40 57 250 32 17 316 40 53 251 32 13 317 40 49 252 32 09 318 40 45 253 32 05 319 40 41 254 36 61 320 40 37 255 36 57 321 40 33 Circle temperature readings above 250°F.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 30 of 31 Page XRef DATA SHEET II (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD CONTROL ROD NUMBER CRD TEMP NUMBER CRD TEMP POINT ID COL ROW 5.3.11 POINT ID COL ROW 5.3.11 322 40 29 342 44 09 323 40 25 343 44 05 324 40 21 344 48 57 325 40 17 345 48 53 326 40 13 346 48 49 327 40 09 347 48 45 328 40 05 348 48 41 329 44 61 349 48 37 330 44 57 350 48 33 331 44 53 351 48 29 332 44 49 352 48 25 333 44 45 353 48 21 334 44 41 354 48 17 335 44 37 355 48 13 336 44 33 410 48 09 337 44 29 411 52 57 338 44 25 412 52 53 339 44 21 413 52 49 340 44 17 414 52 45 341 44 13 415 52 41 Circle temperature readings above 250°F.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1C11-M-0001 Revision: 107 Attachment I Page 31 of 31 Page XRef DATA SHEET II (Continued)

CONTROL ROD OPERABILITY SAFETY RELATED CONTROL ROD CONTROL ROD NUMBER CRD TEMP NUMBER CRD TEMP POINT ID COL ROW 5.3.11 POINT ID COL ROW 5.3.11 416 52 37 433 56 17 417 52 33 434 56 13 418 52 29 435 60 45 419 52 25 436 60 41 420 52 21 437 60 37 421 52 17 438 60 33 422 52 13 439 60 29 423 52 09 440 60 25 424 56 53 441 60 21 425 56 49 426 56 45 427 56 41 428 56 37 429 56 33 430 56 29 431 56 25 432 56 21 Circle temperature readings above 250°F.

X:\EXAMS\GG\GG-2013-05-RETAKE EXAM\GG-2013-05-DRAFT EXAM\GG-2013-05-DRAFT JPMS\GG-2013-05-DRAFT OPERATING TEST.docx

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1CR3 JPM

Title:

Control Rod Operability Surveillance: One Rod Drift then Stuck Facility Number: GJPM-OPS-C11205_________ (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: James nd Mergner 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 02/07/2013 Page 32 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Control Rod Operability Surveillance: One Rod Drift then Stuck Setting: Simulator Type: RO Task: CRO-C11(1)-05, 10 K&A: 201005: A2.13 - 3.8/3.8 A4.01 - 3.7/3.7 Safety Function: 7 Performance: Actual Reference(s): 06-OP-1C11-M-0001 04-1-01-C11-2 05-1-02-IV-1 Handout(s): 06-OP-1C11-M-0001 (marked up)

1. Manipulations: 10

1. Critical Steps: 8 Simulator Setup/Required Plant Conditions:

• Reset Simulator to IC-23

• On Data Sheet I, enter As found rod positions for rods not at position 48.

• Complete/sign Steps 2.1 and 2.2 on Page 1 of Att. I.

• Ensure Individual drive is selected by using DRIVE MODE pushbutton on the operators control console.

• Run Schedule file GJPM-OPS-2012-1CR3 Safety Concerns:

• None Task Standard:

• All tasks associated with this portion of surveillance 06-OP-1C11-M-0001 have been completed IAW the surveillance.

• Perform immediate actions for Control Rod Drift.

• Reduce Core Flow to 70 mlbm/hr when Control Rod does not reach Position 00 Revision 0 02/07/2013 Page 33 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The CRD System is operating IAW SOI 04-1-01-C11-1.

• RC&IS is operating IAW SOI 04-1-01-C11-2.

• Reactor Engineering has been notified that this test is about to be performed.

• An edit of control rod positions has been obtained.

• As Found positions have been entered on Steps of Data Sheet I for all rods not at notch 48.

• Simulate the presence of all permission/page check signatures, revision check and data stamps.

• This test is not being performed in conjunction with a control rod pattern adjustment or sequence exchange.

• The Shift Supervisor has given permission and signed section 2.2.

• Page check has been completed.

Initiating Cue(s):

• The CRS directs you to start test 06-OP-1C11-M-0001 for Control Rods at position 48 only.

Revision 0 02/07/2013 Page 34 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Control Rod Operability Surveillance: One Rod Drift then Stuck Notes: (Notes to Evaluator)

• All controls will be from panel P680 in the Main Control Room.

Task Overview: (Detailed description of task)

• The purpose of this task is to examine attention to detail in preparing and conducting a routine control rod stroke test.

• During the performance a Control Rod will begin to drift in, the candidate will be required to perform immediate actions for a single control rod drift. The control rod will become stuck at a position other than full in. The candidate will be required to perform immediate actions for a control rod drift that cant be fully inserted which is reduce core flow to 70 Mlbm/hr.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-1C11-M-0001 Step 5.1.2 Performer to sign, date and RECORD Test Start time on Data Package Cover Sheet Standard: Candidate signs, dates and records test start time on page 1 of 31 on Attachment 1.

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 35 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 2: 06-OP-1C11-M-0001 Step 5.2 SELECT individual drive USING DRIVE MODE push-button on the operator's control console.

Standard: At the RC&IS Operator Control Module on panel 1H13-P680-6C, ensures the INDIV DRIVE half of the GANG DRIVE/INDIV DRIVE is selected by verifying the status light above the pushbutton indicates INDIV DRIVE.

Cue: None Notes:

SAT / UNSAT Step 3: 06-OP-1C11-M-0001 Step 5.3.2

• On 1H13-P680-6C, SELECT a control rod to test.

Standard:

• Selects control rod 20-61 by simultaneously depressing the pushbuttons marked 20 and 61 on the RC&IS Operator Control Module.

• Observes the rods notch position appearing on the RC&IS Rod Display Panel.

Cue: If the student request a verification of the correct control rod selected cue the student I understand the request for verification continue with the task.

Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 36 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 4: 06-OP-1C11-M-0001 Step 5.3.3 RECORD "As Found" position.

Standard: Records the notch position of rod 20-61 in the space provided.

Cue: None Notes:

SAT / UNSAT Step 5: 06-OP-1C11-M-0001 Step 5.3.4a OBTAIN withdraw stall flow by DEPRESSING "WITHDRAW" AND "CONT WITHDRAW" push-buttons simultaneously. HOLD signal until a stable drive pressure of 240 to 260 psi is observed. IF stable drive pressure is NOT 240 to 260, THEN RECORD stable drive pressure in stall flow, next to stall flow. RECORD stall flow for each rod at Position 48.

Standard: Depresses"WITHDRAW" AND "CONT WITHDRAW" push-buttons simultaneously and holds, observes drive water pressure and records stall flow using PDS Computer (BARS)

Cue: None Notes: Student should use PDS computer to monitor stall flow using the Process Diagram Misc Control Rod Drive BARS.

SAT / UNSAT Revision 0 02/07/2013 Page 37 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 6: 06-OP-1C11-M-0001 Step 5.3.4b

• NOTCH the selected control rod in one notch.

Standard:

1) Inserts control rod 20-61 one notch by depressing the INSERT control pushbutton on the RC&IS Operator Control Module.

2) Monitors the RC&IS Rod Display Panel to observe that the rods notch position goes down and settles on notch 46.

3) Initials the 'IN' ONE NOTCH block for rod 20-61.

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 38 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 7: 06-OP-1C11-M-0001 Step 5.3.4c

• RETURN the selected control rod to the original position.

VERIFY rod position indication changes for the selected control rod by OBSERVING the rod display module on 1H13-P680.

Standard:

1) Withdraws control rod 20-61 one notch to its original position by depressing the WITHDRAW control pushbutton on the RC&IS Operator Control Module.

2) Monitors the RC&IS Rod Display Panel to observe that the rods notch position goes up and settles on notch 48.

3) Observes the rods red FULL OUT LED next to its position indicating digits energizes.

4) Initials the 'OUT' ONE NOTCH block for rod 20-61.

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 39 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 8: 06-OP-1C11-M-0001 Step 5.3.4d

• PERFORM a coupling check AND VERIFY Full Out indication.

Standard:

1) ATTEMPT to withdraw control rod past position 48 by DEPRESSING the WITHDRAW pushbutton.

2) OBSERVE absence of CONT ROD OVERTRAVEL annunciator (1H13-P680-4A2-E5).

3) RELEASE withdraw pushbutton(s) AND VERIFY the control rod position indication returns to position 48 AND the full out LED is lit.

Cue: None Notes:

SAT / UNSAT Step 9: 06-OP-1C11-M-0001 Step 5.3.5 RECORD "As Left" position Standard: Records the AS LEFT POSITION of rod 20-61 in the space provided.

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 40 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 10: 06-OP-1C11-M-0001 Step 5.3.6 INITIAL "PERFORMER" block on Data Sheet I.

Standard: Initials in the space provided.

Cue: If the student requests a verification per step 5.3.7 cue the student I understand the request for verification continue with the task.

Notes:

SAT / UNSAT Step 11: 06-OP-1C11-M-0001 Step 5.3.9 / 2

• On 1H13-P680-6C, SELECT a control rod to test.

Standard:

• Selects control rod 24-61 by simultaneously depressing the pushbuttons marked 24 and 61 on the RC&IS Operator Control Module.

• Observes the rods notch position appearing on the RC&IS Rod Display Panel.

Cue: If the student request a verification of the correct control rod selected cue the student I understand the request for verification continue with the task.

Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 41 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 12: 06-OP-1C11-M-0001 Step 5.3.3 RECORD "As Found" position.

Standard: Records the notch position of rod 24-61 in the space provided.

Cue:

Notes:

SAT / UNSAT Step 13: 06-OP-1C11-M-0001 Step 5.3.4a OBTAIN withdraw stall flow by DEPRESSING "WITHDRAW" AND "CONT WITHDRAW" push-buttons simultaneously. HOLD signal until a stable drive pressure of 240 to 260 psi is observed. IF stable drive pressure is NOT 240 to 260, THEN RECORD stable drive pressure in stall flow, next to stall flow. RECORD stall flow for each rod at Position 48.

Standard: Depresses "WITHDRAW" AND "CONT WITHDRAW" push-buttons simultaneously and holds, observes drive water pressure and records stall flow using PDS Computer (BARS)

Cue: None Notes: Student should use PDS computer to monitor stall flow using the Process Diagram Misc Control Rod Drive BARS.

SAT / UNSAT Step 14: 06-OP-1C11-M-0001 Step 5.3.4b Revision 0 02/07/2013 Page 42 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3

• NOTCH the selected control rod in one notch.

Standard:

1) Inserts control rod 24-61 one notch by depressing the INSERT control pushbutton on the RC&IS Operator Control Module.

2) Monitors the RC&IS Rod Display Panel to observe that the rods notch position goes down and settles on notch 46.

Cue: None Notes: When control rod 24-61 is moved from position 48 the rod will begin to drift in from auto trigger or manual trigger.

SAT / UNSAT Revision 0 02/07/2013 Page 43 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 15: 05-1-02-IV-1, Step 2.2 Student recognizes and announces drifting control rod.

Standard: Student notifies CRS and recognizes drifting control rod IN by the following indications:

• Observes CONT ROD DRIFT alarm, P680-4A2-E4.

• Observes ROD DRIFT status light

• Observes control rod 24-61 continues to move in.

Cue: If necessary, cue the candidate to respond to drifting control rod. As CRS, direct the candidate to take the immediate operator actions of the Control Rod/Drive Malfunctions ONEP.

Notes:

SAT / UNSAT Step 16: 05-1-02-IV-1 Step 2.2.1

• APPLY continuous insert signal until Control Rod reaches zero.

Standard: Depresses the INSERT pushbutton for selected control rod 24-61.

Cue: None Notes: When control rod 24-61 reaches position 12 the control rod will become stuck and will not be able to be inserted to zero position.

SAT / UNSAT Revision 0 02/07/2013 Page 44 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Step 17: 05-1-02-IV-1 Step 2.2.2 RECOGNIZES Control Rod 24-61 cannot be inserted to zero and notifies CRS.

Standard: Recognizes and notifies CRS Control Rod motion has stopped at position 12 Cue: If necessary, cue the candidate to respond to drifting control rod. As CRS, direct the candidate to take the immediate operator actions of the Control Rod/Drive Malfunctions ONEP.

Notes:

SAT / UNSAT Step 18: 05-1-02-IV-1 Step 2.2.2

• REDUCE core flow to 70Mlbm/hr.

Standard: Reduces core flow using Reactor Recirc FCVs to 70 Mlbm/hr and notifies CRS.

Cue: None Notes: Once core flow has been reduced to 70 Mlbm/hr the evaluator will stop the JPM.

SAT / UNSAT Revision 0 02/07/2013 Page 45 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Task Standard(s):

• All tasks associated with this portion of surveillance 06-OP-1C11-M-0001 have been completed IAW the surveillance.

• Perform immediate actions for Control Rod Drift by applying a continuous insert signal for drifting control rod.

• Perform immediate actions for Control Rod Drift by reducing Core Flow to 70 Mlbm/hr when Control Rod cannot reach Position 00.

SAT / UNSAT Remember to record stop time Revision 0 02/07/2013 Page 46 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR3 Follow-Up Questions & Answers:

Comments:

Revision 0 02/07/2013 Page 47 of 298

Give this page to the student Initial Condition(s):

• The CRD System is operating IAW SOI 04-1-01-C11-1.

• RC&IS is operating IAW SOI 04-1-01-C11-2.

• Reactor Engineering has been notified that this test is about to be performed.

• An edit of control rod positions has been obtained.

• As Found positions have been entered on Steps of Data Sheet I for all rods not at notch 48.

• Simulate the presence of all permission/page check signatures, revision check and data stamps.

• This test is not being performed in conjunction with a control rod pattern adjustment or sequence exchange.

• The Shift Supervisor has given permission and signed section 2.2.

• Page check has been completed.

Initiating Cue(s):

• The CRS directs you to start test 06-OP-1C11-M-0001 for Control Rods at position 48 only.

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1CR4 JPM

Title:

Reactor Feed Pump Startup Facility Number: GJPM-OPS-N2103________

(If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: James nd Mergner 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 02/07/2013 Page 49 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Reactor Feed Pump Startup Setting: Simulator Type: RO Task: CRO-N21-003 K&A: 259001/A4.02 - 3.9/3.7 Safety Function: 2 Performance: Actual Reference(s): 04-1-01-N21-1/4.3 Handout(s) 04-1-01-N21-1 section 4.3

1. Manipulations: 5

1. Critical Steps: 5 Simulator Setup/Required Plant Conditions:

• Reset Simulator to IC-137 Safety Concerns:

• None Task Standard:

• RFPT "A" is started up IAW of SOI 04-1-01-N21-1 Revision 0 02/07/2013 Page 50 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The plant is in STARTUP, approximately 400 psig, with level control via Startup Level Control Valve N21-F513.

• All prerequisites for RFPT A Startup of SOI 04-1-01-N21-1 is complete.

• The RFPT A has been tripped tested.

Initiating Cue(s):

• The CRS directs you to place the first Reactor Feed Pump (RFP A) in service at a discharge pressure of >700 psig.

• All steps through 4.3.2m have been completed

• It is NOT desired to put the second RFPT in Standby at this time.

Revision 0 02/07/2013 Page 51 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Reactor Feed Pump Startup Notes: (Notes to Evaluator)

• All controls will be from panel P680 in the Main Control Room.

Task Overview: (Detailed description of task)

• This task starts the first reactor feed pump to be placed in service. The task is necessary for reactor pressurization to continue during a startup because the discharge head of the condensate booster pumps will only provide sufficient flow at RPV pressures less than 600 psig.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-N21-1 Step 4.3.2n

• DEPRESS the RFPT A TRIP RESET pushbutton to reset turbine AND open high AND low pressure stop valves.

Standard: Depresses the RFPT A TRIP RESET pushbutton on P680 and:

1) Observes its red status light on and its green status light off

2) The MANUAL, RAISE and LOWER pushbuttons backlight on the RFP A CONTROL PANEL energize

3) The RFPT Trip annunciator clears 4 Observes red indication on and green light off on High and Low pressure stop valves Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 52 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Step 2: 04-1-01-N21-1 Step 4.3.2o

• DEPRESS the RFPT A RAISE pushbutton to increase RFPT speed to greater than 100 rpm.

Standard: Depresses the RFPT A RAISE pushbutton RFP A CONTROL PANEL to raise RFPT speed to greater than 100 rpm Cue: None Notes: Due to forward flow through the Feedpump, RFPT speed may already be

>100 rpm. Therefore, this step would not be critical if already above 100 rpm.

SAT / UNSAT Step 3: 04-1-01-N21-1 Step 4.3.2p

• WHEN the RFPT A SPEED AUTO pushbutton begins flashing, THEN DEPRESS the RFPT A SPEED AUTO pushbutton.

Standard: When the SPEED AUTO pushbutton backlight for RFPT A starts flashing, indicating RFPT speed > 100 rpm, depresses the SPEED AUTO pushbutton on the RFP A CONTROL PANEL and observes the following:

(1) OBSERVE the RFPT A MANUAL pushbutton extinguishes.

(2) OBSERVE the RFPT A SPEED AUTO Pushbutton is on.

(3) OBSERVE the RFPT A RAISE AND LOWER pushbuttons remain lit.

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 53 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Step 4: 04-1-01-N21-1 Step 4.3.2q

• OPEN F014A, RFP A DISCH VLV.

Standard: Open N21-F014A by depressing and holding its OPEN pushbutton on P680 until its red light is on and its green light is off Cue: None Notes:

SAT / UNSAT Step 5: 04-1-01-N21-1 Step 4.3.2r

• RAISE RFPT A speed to desired RPM AND discharge pressure using the RFPT A RAISE pushbutton.

Standard: Depress the RAISE pushbutton on the RFPT A CONTROL PANEL to increase RFPT A discharge pressure, as indicated by N21-PI-R612A or equivalent, until it is >700 psig, as indicated by C34-PI-R605 or equivalent Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 54 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Step 6: 04-1-01-N21-1 Step 4.3.2s CHECK CLOSED/CLOSE Reactor Feed Pump A steam line drains on 1H22-P175 AND RETURN handswitches to AUTO after valves are closed.

(1) 1N11-F019A, RFPT A HP IN DR VLV (2) 1N11-F023A, RFPT A HP IN DR VLV (3) 1N11-F018A, RFPT A IP IN DR VLV (4) 1N11-F021A, RFPT A IP IN DR VLV (5) 1N11-F042A, RFPT A IP IN DR VLV (6) 1N33-F021A, RFPT A ABOVE SEAT DR (7) 1N33-F022A, RFPT A ABOVE SEAT DR (8) 1N33-F023A, RFPT A BELOW SEAT DR (9) 1N33-F024A, RFPT A BELOW SEAT DR (10) 1N33-F028A, RFPT A 1ST STAGE DR Standard: Directs a plant operator to check closed the following valves on local Panel 1H22-P175:

(1) 1N11-F019A, RFPT A HP IN DR VLV (2) 1N11-F023A, RFPT A HP IN DR VLV (3) 1N11-F018A, RFPT A IP IN DR VLV (4) 1N11-F021A, RFPT A IP IN DR VLV (5) 1N11-F042A, RFPT A IP IN DR VLV (6) 1N33-F021A, RFPT A ABOVE SEAT DR (7) 1N33-F022A, RFPT A ABOVE SEAT DR (8) 1N33-F023A, RFPT A BELOW SEAT DR (9) 1N33-F024A, RFPT A BELOW SEAT DR (10) 1N33-F028A, RFPT A 1ST STAGE DR Cue: Listed valves are in their required positions.

Notes: Valves listed are also indicated on the P870 panel.

SAT / UNSAT Revision 0 02/07/2013 Page 55 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Task Standard(s):

• RFPT "A" is started up IAW SOI 04-1-01-N21-1 SAT / UNSAT Remember to record stop time Revision 0 02/07/2013 Page 56 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR4 Follow-Up Questions & Answers:

Comments:

Revision 0 02/07/2013 Page 57 of 298

Give this page to the student Initial Condition(s):

• The plant is in STARTUP, approximately 400 psig, with level control via Startup Level Control Valve N21-F513.

• All prerequisites for RFPT A Startup of SOI 04-1-01-N21-1 is complete.

• The RFPT A has been tripped tested.

Initiating Cue(s):

• The CRS directs you to place the first Reactor Feed Pump (RFP A) in service at a discharge pressure of >700 psig.

• All steps through 4.3.2m have been completed

• It is NOT desired to put the second RFPT in Standby at this time.

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1CR5 JPM

Title:

Rapid Restart of RWCU Pumps Facility Number: N/A (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 20 Min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: James nd Mergner 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 02/07/2013 Page 59 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Rapid Restart of RWCU Pumps Setting: Simulator Type: RO Task: CRO-G33/36-001 K&A: 202001: K1.21 2.6/2.6 K3.07 2.9/2.9 A2.04 3.7/3.8 Safety Function: 4 Performance: Actual Reference(s): 05-1-02-I-1, Reactor Scram ONEP Handout(s) 05-1-02-I-1, Reactor Scram ONEP

1. Manipulations: 22

1. Critical Steps: 22 Simulator Setup/Required Plant Conditions:

• Reset Simulator to IC-134

• Run Schedule file GJPM-OPS-2012-1CR5 Safety Concerns:

• None Task Standard:

• RWCU system is restarted per 05-1-02-I-1, Reactor Scram ONEP, Attachment 1.

Revision 0 02/07/2013 Page 60 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• A Reactor Scram has occurred 30 minutes ago.

• Reactor level and pressure are stabilized within normal bands

• An RWCU isolation has occurred

• I&C has installed a JUMPER from BB-33 to BB-32 in 1H13-P623.

• Filter Demins are isolated and being backwashed by a plant operator.

• All prerequisites are complete Initiating Cue(s):

• The CRS directs you to Restart Reactor Water Cleanup System (RWCU)

Per step 3.9 of 05-1-02-I-1, Reactor Scram ONEP.

• RWCU blowdown is NOT desired at this time.

Revision 0 02/07/2013 Page 61 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Rapid Restart of RWCU Pumps Notes: (Notes to Evaluator)

• All controls will be from panels P870 and P680 in the Main Control Room.

Task Overview: (Detailed description of task)

• This task is a manual rapid startup of RWCU following a pump trip/system isolation using the Scram ONEP.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-I-1, Att. 1 Step 1 CLOSE OR CHECK CLOSED the following valves:

• G33-F254 RWCU FLTR/DMIN INL FM RWCU HX 1H13-P870-5C

• G33-F256 RWCU HX INL FM RWCU PMP 1H13-P870-5C

• G33-F001 PMP SUCT DRWL INBD ISOL 1H13-P680 Standard: Checks closed the following valves by observing their red light is off and their green light is on.

• G33-F254 1H13-P870-5C

• G33-F256 1H13-P870-5C

• G33-F001 1H13-P680 Cue: None Notes: All valves listed should be closed SAT / UNSAT Revision 0 02/07/2013 Page 62 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Step 2: 05-1-02-I-1, Att. 1 Step 2

• RESET the isolation by DEPRESSING the NSSSS INBD ISOL RESET AND NSSSS OTBD ISOL RESET pushbuttons on 1H13-P601 Standard: DEPRESSES the NSSSS INBD ISOL RESET AND NSSSS OTBD ISOL RESET pushbuttons on 1H13-P601 Cue: None Notes:

SAT / UNSAT Step 3: 05-1-02-I-1, Att. 1 Step 3.a

• CLOSE the following valves on 1H13-P680

• G33-F101 RPV DR VLV TO RWCU

• G33-F102 RWCU RECIRC A/B SUCT VLV Standard: Closes G33-F101 and F102 on Panel P680 by depressing the CLOSE pushbutton and verifies it closed by observing its green light is on and its red light is off Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 63 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Step 4: 05-1-02-I-1, Att. 1 Step 3.b

• OPEN OR CHECK OPEN the following valves, in order:

• G33-F250 RWCU SPLY TO RWCU HXS 1H13-P870-3C

• G33-F251 RWCU SPLY TO RWCU HXS 1H13-P870-9C

• G33-F252 RWCU HX RTN TO RWCU PMPS 1H13-P870-9C

• G33-F253 RWCU HX RTN TO RWCU PMPS 1H13-P870-3C

• G33-F004 PMP SUCT CTMT OTBD ISOL 1H13-P680

• G33-F054 RWCU PMP DISCH CTMT OTBD ISOL 1H13-P680

• G33-F053 RWCU PMP DISCH CTMT INBD ISOL 1H13-P680

• G33-F255 RWCU FLTR/DMIN INL FM RWCU PMP 1H13-P870-5C

• G33-F044 (THROTTLE OPEN SLOWLY) 1H13-P680 RWCU FLTR DMIN BYP VLV

• G33-F042 RWCU REGEN HX RTN VLV 1H13-P680

• G33-F040 RWCU RTN CTMT INBD ISOL 1H13-P680

• G33-F039 RWCU RTN CTMT OTBD ISOL 1H13-P680 Standard: Opens or checks open the listed valves in order, and verifies it open by observing its red light is on and its green light is off Cue: None Notes: Some valves will only require to be verified open but list must be done in order.

SAT / UNSAT Revision 0 02/07/2013 Page 64 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Step 5: 05-1-02-I-1, Att. 1 Step 3.c

• SLOWLY THROTTLE OPEN G33-F102 RWCU RECIRC A/B SUCT VLV.

Standard: Slowly throttles OPEN G33-F102 RWCU RECIRC A/B SUCT VLV by depressing the JOG OPEN pushbutton to pressurize RWCU piping to reactor pressure. RWCU pressure Can be observed on pressure indicator G33-PI-R600 REGEN HX IN PRESS on 1H13-P680. Verfies G33-F102 is full open by its red light on and green light off.

Cue: None Notes: System pressure and reactor should not have much delta to reduce time to re-pressurize system.

SAT / UNSAT Step 6: 05-1-02-I-1, Att. 1 Step 3.d

• OPEN G33-F101 RPV DR VLV TO RWCU.

Standard: Opens G33-F101 by depressing the OPEN pushbutton to and verifies the valve is full open as indicated by its red light on and its green light off Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 65 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Step 7: 05-1-02-I-1, Att. 1 Step 5.a

• CLOSE G33-F044, RWCU FLTR DMIN BYP VLV.

Standard: Closes G33-F044 by depressing the CLOSE pushbutton, and verifies it closed by observing its green light is on and its red light is off Cue: None Notes:

SAT / UNSAT Step 8: 05-1-02-I-1, Att. 1 Step 5.b(1)

• DEPRESS the RWCU PMP A(B) STOP pushbutton.

Standard: Depresses the STOP pushbutton for the RWCU PMP A(B) on the P680 panel to reset the trip logic.

Cue: If student asks which pump is preferred to start first, inform the student that A pump should be started first.

Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 66 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Step 9: 05-1-02-I-1, Att. 1 Step 5.b(2)

• START RWCU PMP A(B).

Standard: Starts RWCU pump A by depressing the START pushbutton on the P680 panel and observes the green light is off and its red light is on Cue: None Notes:

SAT / UNSAT Step 10: 05-1-02-I-1, Att. 1 Step 5.c

• THROTTLE OPEN G33-F044, RWCU FLTR DMIN BYP VLV Standard: Throttles open G33-F044, RWCU FLTR DMIN BYP VLV to achieve flow of greater than 90 gpm but less than 300 gpm as indicated on FI-R609, RWCU INL FLO.

Cue: None Notes: Should observe zero flow on RWCU Filter Demins A & B on 1H13-P680-11B.

SAT / UNSAT Step 11: 05-1-02-I-1, Att. 1 Step 6 (1)

Revision 0 02/07/2013 Page 67 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5

• DEPRESS the RWCU PMP B(A) STOP pushbutton Standard: Depresses the STOP pushbutton for the RWCU PMP B on the P680 panel to reset the trip logic.

Cue: None Notes:

SAT / UNSAT Step 12: 05-1-02-I-1, Att. 1 Step 6 (2)

• START RWCU PMP B(A).

Standard: Starts RWCU pump B by depressing the START pushbutton on the P680 panel and observes the green light is off and its red light is on Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 68 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Step 13: 05-1-02-I-1, Att. 1 Step 6 (3)

• THROTTLE OPEN G33-F044, RWCU FLTR DMIN BYP VLV Standard: Throttles open G33-F044, RWCU FLTR DMIN BYP VLV to achieve flow of 300-500 gpm as indicated on G33-FI-R609, RWCU INL FLO.

Cue: None Notes:

SAT / UNSAT Step 14: 05-1-02-I-1, Att. 1 Step 7 CHECK temperature Point 5 (NON-REGEN HT EX OUTLET TEMP)

Standard: Checks temperature Point 5 (NON-REGEN HT EX OUTLET TEMP) on Panel P680 temperature selector to be <

140°F Cue: If student request, cue that another operator will contact I&C to have jumpers removed.

Notes: RWCU blowdown is NOT desired.

SAT / UNSAT Revision 0 02/07/2013 Page 69 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Task Standard(s):

• RWCU system is restarted per 05-1-02-I-1, Reactor Scram ONEP, Attachment 1.

SAT / UNSAT Remember to record stop time Revision 0 02/07/2013 Page 70 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR5 Follow-Up Questions & Answers:

Comments:

Revision 0 02/07/2013 Page 71 of 298

Give this page to the student Initial Condition(s):

• A Reactor Scram has occurred 30 minutes ago.

• Reactor level and pressure are stabilized within normal bands

• An RWCU isolation has occurred

• I&C has installed a JUMPER from BB-33 to BB-32 in 1H13-P623.

• Filter Demins are isolated and being backwashed by a plant operator.

• All prerequisites are complete Initiating Cue(s):

• The CRS directs you to Restart Reactor Water Cleanup System (RWCU)

Per step 3.9 of 05-1-02-I-1, Reactor Scram ONEP.

• RWCU blowdown is NOT desired at this time.

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1CR6 JPM

Title:

Align CCW to FPCCU Heat Exchanger A Facility Number: GJPM-OPS-P4202_______ (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Gabe nd Hargrove 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 02/07/2013 Page 73 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Align CCW to FPCCU Heat Exchanger A Setting: Simulator Type: RO Task: CRO-P42-003, CRO-P42-005 K&A: 400000: K1.02 3.2/3.4 A4.01 3.1/3.0 Safety Function: 8 Performance: Actual Reference(s): 04-1-01-P42-1 04-1-02-1H13-P870-2A-B1 04-1-01-R21-1 Handout(s) 04-1-01-P42-1 section 4.2 & 6.3 04-1-01-R21-1 section 4.2

1. Manipulations: 7

1. Critical Steps: 6 Simulator Setup/Required Plant Conditions:

• Reset Simulator to IC-138

• Run Schedule file GJPM-OPS-2012-1CR6 Safety Concerns:

• None Task Standard:

• SSW B is aligned to FPCCU Heat Exchanger B in accordance with 04-1-01-P42-1 section 6.3.

Revision 0 02/07/2013 Page 74 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The Inadequate Decay Heat Removal ONEP has been entered due to Spent Fuel Pool temperature.

• CCW Cooling to both FPHXs is Out of Service due to restoration following maintenance.

• Another operator is monitoring CCW Head Tank level and temperatures.

Initiating Cue(s):

• The CRS directs you to place CCW in service to only the A FPCCU Heat Exchanger in accordance with 04-1-01-P42-1 section 4.2.

• The prerequisites of section 4.2.1 have been verified to be met.

Revision 0 02/07/2013 Page 75 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Align CCW to FPCCU Heat Exchanger A Notes: (Notes to Evaluator)

• All controls will be from panel P870 in the Main Control Room.

Task Overview: (Detailed description of task)

• This task is to align CCW to Fuel Pool Cooling and Cleanup (FPCCU) Heat Exchanger A.

• The fault in this task is the failure of the Division 1 CCW to FPCCU Heat Exchangers flow circuit, which is simulated to fail to a low flow condition. This causes CCW to FPCCU Heat Exchangers inlet and outlet valves, P42F105 and P42F205, to automatically close when the operator releases their handswitches and they spring return to the AUTO position.

• The operator will then be redirected to align SSW B to the B FPCCU Heat Exchanger. This will require initiation of SSW B and alignment of Division 2 valves to FPCCU B Heat Exchanger.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-P42-1 Step 3.4 Place CCW DIV1 MOV TEST switch to TEST Standard: Places CCW DIV1 MOV TEST switch to TEST by verifying alarm P870-2A-D1 (CCW DIV 1 MOVS IN TEST MODE) and status light on P870-2B (CCW D1 MOV IN TEST STATUS).

Cue: None Notes: Candidate may not perform this step due to ONEP entry.

SAT / UNSAT Revision 0 02/07/2013 Page 76 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Step 2: 04-1-01-P42-1 Step 4.2.2 b (1)

• OPEN OR VERIFY OPEN F028A, FPHX A Inlet valve Standard: OPENS F028A, FPHX A Inlet valve, using respective handswitch CLG WTR INL TO FPHX A [P870-2C], ensuring red light on and green light off.

Cue: None Notes:

SAT / UNSAT Step 3: 04-1-01-P42-1 Step 4.2.2 b (1)

• OPEN OR VERIFY OPEN F032A, FPHX A Outlet valve Standard: OPENS F032A, FPHX A Outlet valve, using respective handswitch CLG WTR OUTL FM FPHX A [P870-2C], ensuring red light on and green light off.

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 77 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Step 4: 04-1-01-P42-1 Step 4.2.2 b (2)

• OPEN F105 AND F205 by SIMULTANEOUSLY HOLDING Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C]

AND CCW RTN FM FPHX A/B [2C], to the OPEN position until alarm Clears (1H13-P870 Section 2A Grid B-1).

Standard: OPENS F105 AND F205 by SIMULTANEOUSLY HOLDING Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C] AND CCW RTN FM FPHX A/B [2C], to the OPEN position until alarm Clears (1H13-P870 Section 2A Grid B-1). Recognizes and reports F105 and F205 reached fully open but the FPCCU Hx A low flow alarm did not clear, and F105 and F205 stroked closed when their hand switches were released. The operator should report the FPCCU Hx B low flow alarm (1H13-P870 Section 8A) did clear when the valves were open but came back in when the valves automatically closed.

Cue: After report of F105 and F205 unable to stay open, The CRS directs you to manually initiate SSW B using the hard card and align SSW B to FPCCU Heat Exchanger B in accordance with 04-1-01-P42 section 6.3.

Notes: A sensed low flow condition prevents opening F105 and F205 if F028A and F032A are OPEN. To allow the opening of F105 and F205, their handswitches must be held to the OPEN position until the low flow condition clears for the Division 1 flow circuit.

In this JPM, the low flow condition will not clear in the Division 1 circuit, and the valves will automatically close when their handswitches are released (spring return to NORMAL). The Division 2 CCW to FPCCU Heat Exchangers flow circuit is unaffected, so the Div 2 low CCW to FPCCU Hx flow alarm will clear when P42F105 and P42F205 are both opened.

The candidate may close P42F028A and P42F032A before proceeding to the next step, but this is not necessary.

SAT / UNSAT Revision 0 02/07/2013 Page 78 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Step 5: 04-1-01-P41-1 Attachment VIII

• PRESS Both SSW Div 2 MAN INIT pushbuttons.

Standard: Initiates SSW B by simultaneously depressing both SSW Div 2 MAN INIT pushbuttons on P870-7C.

Cue: None Notes:

SAT / UNSAT Step 6: 04-1-01-P42-1 Step 6.3.3 a SHUTDOWN Div II LSS per SOI 04-1-01-R21-1 Standard: Refers to SOI 04-1-01-R21-1 and request a plant operator to shutdown Division 2 Load Shedding and Sequencing panel accordance with 04-1-01-R21-1 step 4.2 Cue: When the simulator operator has inserted trigger 25 as indicated by receipt of alarm P864-2A-H1, report back as the local operator that the Div 2 LSS Panel has been shutdown per the SOI.

Notes: When requested to shutdown Division 2 Load Shedding and Sequencing Panel, insert trigger 25.

SAT / UNSAT Revision 0 02/07/2013 Page 79 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Step 7: 04-1-01-P42-1 Step 6.3.3 b CLOSE OR CHECK CLOSED the following valves:

• P42-F028B

• P42-F203

• P42-F032B

• P42-F204 Standard: Checks close the following valve on H13P870 sections 2C and 8C by verifying red light off and green light on:

• P42F028B

• P42F032B

• P42F203

• P42F204 Cue: None Notes:

SAT / UNSAT Step 8: 04-1-01-P42-1 Step 6.3.3 c

• OPEN P42-F200B Standard: Opens P42F200B, FPHX B Inlet valve, using its respective handswitch SSW B INL TO FPHX B [8C] by verifying red light on and green light off.

Cue: None Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 80 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Step 9: 04-1-01-P42-1 Step 6.3.3 d

• OPEN P42-F201B Standard: Opens P42F201B, FPHX B Outlet valve, using its respective handswitch SSW B OUTL FM FPHX B [8C] by verifying red light on and green light off. The operator should report B FPCCU Hx low flow alarm clears.

Cue: When the candidate has opened P42 F200B and F201B, the evaluator will end the JPM Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 81 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Task Standard(s):

• SSW B is aligned to FPCCU Heat Exchanger B in accordance with 04-1-01-P42-1 section 6.3.

SAT / UNSAT Remember to record stop time Revision 0 02/07/2013 Page 82 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR6 Follow-Up Questions & Answers:

Comments:

Revision 0 02/07/2013 Page 83 of 298

Give this page to the student Initial Condition(s):

• The Inadequate Decay Heat Removal ONEP has been entered due to Spent Fuel Pool temperature.

• CCW Cooling to both FPHXs is Out of Service due to restoration following maintenance.

• Another operator is monitoring CCW Head Tank level and temperatures.

Initiating Cue(s):

• The CRS directs you to place CCW in service to only the A FPCCU Heat Exchanger in accordance with 04-1-01-P42-1 section 4.2.

• The prerequisites of section 4.2.1 have been verified to be met.

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1CR7 JPM

Title:

Emergency Depressurization using ADS/SRVs Facility Number: N/A_______

(If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 5 Min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Gabe nd Hargrove 3/25/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/25/2013 Project Lead or Exam Team Lead Date Revision 0 02/07/2013 Page 85 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 Emergency Depressurization using ADS/SRVs Setting: Simulator Type: RO Task: CRO-B21-010 K&A: 218000: K6.06 3.4/3.6 A1.04 4.1/4.2 A2.05 3.4/3.6 A4.01 4.4/4.1 A4.10 3.8/3.8 Safety Function: 3 Performance: Actual Reference(s): 05-S-01-EP-2 Handout(s) None

1. Manipulations: 9

1. Critical Steps: 8 Simulator Setup/Required Plant Conditions:

• Reset Simulator to IC-135

• Run Schedule file GJPM-OPS-2012-1CR7 Safety Concerns:

• None Task Standard:

• Opens 8 ADS/SRVs using Division 2 Handswitches on the P631 panel.

Revision 0 02/07/2013 Page 86 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• A transient has occurred causing the CRS to direct actions from EP-2.

• ESF bus 16AB is de-energized due to an electrical fault.

Initiating Cue(s):

• The CRS directs you to Open 8 ADS/SRVs for Emergency Depressurization.

Revision 0 02/07/2013 Page 87 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 Emergency Depressurization using ADS/SRVs Notes: (Notes to Evaluator)

• All controls will be from panels P601 and P631 in the Main Control Room.

Task Overview: (Detailed description of task)

• This task is to emergency depressurize the reactor by opening 8 ADS/SRVs.

• The fault in this task is a failure of the Division 1 DC Battery bus. This causes a failure of the P601 SRV handswitches which control the Div. 1 ADS/SRV solenoids.

• With 16AB de-energized the Manual Initiation for ADS will not work due to no Div 2 ECCS pumps running.

• The operator will then be redirected to use the Div. 2 solenoids to achieve SRV opening.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-S-01-EP-2, Step ED-4 OPEN 8 ADS/SRVs Standard: Places control switch for 8 ADS/SRVs to the open position on P601.

Cue: None Notes: When candidate places the handswitch for B21-F051A to the open position 11DA DC BUS will trip causing valves to fail closed and the Handswitches on P601 to become inoperable with loss of indication.

SAT / UNSAT Revision 0 02/07/2013 Page 88 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 Step 2: 05-S-01-EP-2, Step ED-4 RECOGNIZE failure of valves to Open Standard: RECOGNIZE failure of valves to Open by observing the Red light does not illuminate and reports to CRS.

Cue: The CRS directs you to Emergency Depressurize the Reactor by using the Division 2 SRV solenoids/handswitches.

Notes:

SAT / UNSAT Step 3: 05-S-01-EP-2, Step ED-4

• OPEN 8 ADS/SRVs Standard: Places control switch for 8 ADS/SRVs to the open position on P631 and verifies the red light is on and the green light is off.

Cue: None Notes: The candidate may use non-ADS valves for a total of 8 SRVs.

Each individual valve can be considered a critical task to achieve 8 valves open.

SAT / UNSAT Revision 0 02/07/2013 Page 89 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 Step 4: 05-S-01-EP-2, Step ED-4 Verify reactor pressure is lowering.

Standard: Observes Reactor pressure is lowering by using pressure indication on P601 or P680.

Cue: When 8 ADS/SRVs are open and reactor pressure is lowering the evaluator will stop the JPM.

Notes:

SAT / UNSAT Revision 0 02/07/2013 Page 90 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 Task Standard(s):

Opens 8 ADS/SRVs using Division 2 Handswitches on the P631 panel.

SAT / UNSAT Remember to record stop time Revision 0 02/07/2013 Page 91 of 298

Date of Examination: 05/06/2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1CR7 Follow-Up Questions & Answers:

Comments:

Revision 0 02/07/2013 Page 92 of 298

Give this page to the student Initial Condition(s):

• A transient has occurred causing the CRS to direct actions from EP-2.

• ESF bus 16AB is de-energized due to an electrical fault.

Initiating Cue(s):

• The CRS directs you to Open 8 ADS/SRVs for Emergency Depressurization.

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1PS1 JPM

Title:

Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Facility Number: GJPM-OPS-C6103 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 20 min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: James nd Mergner 3/26/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/26/2013 Project Lead or Exam Team Lead Date Revision 0 3/16/2013 Page 94 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Setting: Plant Type: NLO Task: NOB-ADMIN-024 CRO-ADMIN-008 CRO-C61-001 K&A: 295016 AA1.07: 4.2/4.3 AK2.02: 4.0/4.1 2.1.30: 4.4/4.0 Safety Function: 7 Performance: Simulate Reference(s): 05-1-02-II-1, Attachment III Handout(s): 05-1-02-II-1

1. Manipulations: 10

1. Critical Steps: 10 Simulator Setup/Required Plant Conditions:

• Control building - Division 1 switchgear room is accessible Safety Concerns:

• Wear appropriate personal protective equipment.

• Don't forget ALARA

• No climbing. Point up or down while you explain what you are going to do.

• DO NOT operate plant equipment Task Standard(s):

• Attachment III of 05-1-02-II-1 is complete.

Revision 0 3/16/2013 Page 95 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• The plant has been scrammed.

• A fire exists in the Main Control Room.

• The Control Room Supervisor has evacuated the Main Control Room and established control of the plant at the Remote Shutdown Panels.

• Remote Shutdown Panel (RSD) room locker is open.

Initiating Cue(s):

• The CRS directs you to complete the handswitch lineup per Attachment III of 05-1-02-II-1 step 3.2.5 a.

Revision 0 3/16/2013 Page 96 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Notes: (Notes to Evaluator)

• Panels may be operated in any order. The sequencing is NOT CRITICAL.

• This JPM is considered a Low Power JPM due to the requirement to scram the plant prior to manning the Remote Shutdown Panels.

• This JPM is an Abnormal Operating Procedure outside of the CAA.

Task Overview: (Detailed description of task)

• This task is to align the Alternate Shutdown Panels in the Division 1 switchgear room of the Control Building per 05-1-02-II-1 Attachment III separating the Main Control Room from the Division I equipment for safe shutdown in the event of a fire or security event in the Main Control Room.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-II-1 Attachment III a OBTAIN key from RSD room locker Standard: Obtains the key to the locked switch cover for C61-HSS-M150 key from the RSD locker.

Cue: You have the KEY.

Notes: The key is located in the Locker in the Division 2 Remote Shutdown Room. Once the candidate identifies where the key is located this is sufficient.

1H22-P152 Control Building Area 25A 111 ft elevation Order of completion of panels is NOT critical.

SAT / UNSAT Revision 0 3/16/2013 Page 97 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Step 2: 05-1-02-II-1 Attachment III a

• PLACE Transfer Switch for Lockout Transfer Relay C61-HSS-M150 at 1H22-P152 (Area 25A, El. 111) to ON position.

Standard: Simulates opening locked box over C61-HSS-M150 and placing transfer switch to the ON position.

Cue: Switch is in the ON position.

Notes: 1H22-P152 Control Building Area 25A 111 ft elevation Order of completion of panels is NOT critical.

SAT / UNSAT Step 3: 05-1-02-II-1 Attachment III b OBSERVE that Lockout Transfer Relays R1 through R36 trip to LOCKOUT position.

Standard: Indicates the location of relays R1 through R36 and position when in LOCKOUT.

Cue: Lockout Transfer Relays R1 through R36 are in the LOCKOUT position.

Notes: 1H22-P152 Control Building Area 25A 111 ft elevation SAT / UNSAT Revision 0 3/16/2013 Page 98 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Step 4: 05-1-02-II-1 Attachment III c

• PLACE the following handswitches at 1H22-P299 (Area 25A, Elev 111') to LOCAL position

• C61-HSS-M512 (ESF XFMR NO. 12 152-1511)

• C61-HSS-M514 (ESF XFMR NO. 21 152-1501/ESF XFMR NO.

11 152-1514)

• C61-HSS-M516 (BUS 15AA FDR FM DG 11/152-1508)

• C61-HSS-M518 (SSW SYSTEM BOUNDARY VALVE)

• C61-HSS-M520 (SSW PMP HSE VENT SYS)

• C61-HSS-M513 (4.16 KV BUS 15AA)

• C61-HSS-M515 (4.16 KV BUS 15AA)

• C61-HSS-M517 (480V POWER DIST IC FDR TO 15BA6 and 15BA5)

• C61-HSS-M519 (SFGD SWGR-BTRY RM EXH FAN A)

Standard: Simulates placing the above handswitches to LOCAL.

Cue: Handswitches are in LOCAL Notes: 1H22-P299 Control Building Area 25A 111 ft elevation SAT / UNSAT Revision 0 3/16/2013 Page 99 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Step 5: 05-1-02-II-1 Attachment III d PLACE OR VERIFY each component on panel 1H22-P299 is in the desired position.

Component DESIRED POSITION *

• Q1P41-F016A-A, 1C61-HSS-M570 Closed

• Q1Y47-C001A-A, 1C61-HSS-M572 Indication Available (Running IF SSW A Pump runni

• 152-1507, 1C61-HSS-M565 Closed

• 152-1513, 1C61-HSS-M566 Closed

• 152-1512, 1C61-HSS-M567 Closed

• 152-1504, 1C61-HSS-M568 Closed

• 480V LCC 15BA5, 1C61-HSS-M569 Closed

• Q1Y47-F002A-A As Required (Open IF Y47-C001A running)

• Q1Y47-F003A-A As Required (Close on high SSW A Pumphouse tem

• Q1Y47-F001A-A As Required (Open IF Y47-C001A running)

• Q1Z77-F036A-A As Required (Opens on high temperature)

• Q1Z77-C001A-A Running (Red Light ON)

• This is normal indication with no isolation OR initiation signal with plant at power Standard: Verifies indications and compares to desired position.

Cue: As indicated Notes: 1H22-P299 Control Building Area 25A 111 ft elevation SAT / UNSAT Revision 0 3/16/2013 Page 100 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Step 6: 05-1-02-II-1 Attachment III e NOTIFY RSD SRO of any component NOT in desired position on panel 1H22-P299.

Standard: Notifies RSD SRO of any component not in desired position on panel 1H22-P299.

Cue: Acknowledge any report. Leave as is.

Notes: 1H22-P299 Control Building Area 25A 111 ft elevation SAT / UNSAT Task Standard(s):

Attachment III of 05-1-02-II-1 is complete.

SAT / UNSAT Remember to record stop time Revision 0 3/16/2013 Page 101 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS1 Follow-Up Questions & Answers:

Comments:

Revision 0 3/16/2013 Page 102 of 298

Give this page to the student Initial Condition(s):

• The plant has been scrammed.

• A fire exists in the Main Control Room.

• The Control Room Supervisor has evacuated the Main Control Room and established control of the plant at the Remote Shutdown Panels.

• Remote Shutdown Panel (RSD) room locker is open.

Initiating Cue(s):

• The CRS directs you to complete the handswitch lineup per Attachment III of 05-1-02-II-1 step 3.2.5 a.

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1PS2 JPM

Title:

Reset Undervoltage Lockouts on BOP Buses Facility Number: GJPM-OPS-R2108 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 20 min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: James nd Mergner 3/26/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/26/2013 Project Lead or Exam Team Lead Date Revision 0 3/16/2013 Page 104 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 Reset Undervoltage Lockouts on BOP Buses Setting: Plant (Inside CAA)

Type: NLO Task: NOB-R21-008 K&A: 262001 A2.11: 3.2/3.6 295003 AA1.01: 3.7/3.8 2.1.30: 4.4/4.0 Safety Function: 6 Performance: Simulate Reference(s): ONEP 05-1-02-I-4 section 3.3.12e Handout(s): ONEP 05-1-02-I-4 section 3.3.12e

1. Manipulations: 6

1. Critical Steps: 6 Simulator Setup/Required Plant Conditions:

• Turbine Building elevations 113 and 133 Safety Concerns:

• Wear appropriate personal protective equipment.

• Don't forget ALARA

• No climbing. Point up or down while you explain what you are going to do.

• DO NOT operate plant equipment Task Standard(s):

• Bus 13AD and 12HE bus undervoltage lockout devices are reset.

Revision 0 3/16/2013 Page 105 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• BOP Transformer 11B locked out on Sudden Pressure and deenergized 34.5 KV Bus 12R.

• BOP Buses 12HE and 13AD lost power.

• Control room operators have reenergized bus 12HE and bus 13AD from alternate feeders powered by BOP Transformers 12A and 12B per Loss of AC Power ONEP.

• Major loads powered from these buses cannot be restored until bus under voltage lockout devices are reset at the busses.

Initiating Cue(s):

• The CRS directs you to reset all bus under voltage lockout devices on bus 12HE and bus 13AD.

Revision 0 3/16/2013 Page 106 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 Reset Undervoltage Lockouts on BOP Buses Notes: (Notes to Evaluator)

• Bus 13AD and 12HE may be restored in any order. Bus order is not critical.

• Bus undervoltage lockout devices may be reset in any order.

BUV device order is not critical.

• The operator must be able to recognize the difference between a BUV and an overcurrent lockout device and should not attempt to reset an overcurrent lockout device for this task.

• There is no specific procedure for this task; it is considered a skill of the craft.

Task Overview: (Detailed description of task)

• This task is to reset bus undervoltage lockout devices on affected bus auxiliary panels after bus reenergization. This task is performed to allow large electrical loads to be restarted on affected buses.

GGNS plant scram on February 11, 2005 required this task to be performed.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-I-4 3.3.12 e Locate 4.16KV bus 13AD.

Standard: Locates bus 13AD in the electrical switchgear room in area 4 elevation 133 of the turbine building.

Cue: None Notes:

SAT / UNSAT Revision 0 3/16/2013 Page 107 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 Step 2: 05-1-02-I-4 3.3.12 e

• Reset bus undervoltage lockout devices on bus auxiliary cubicle.

• Relay 186 BV-1 reset.

• Relay 186 BV-2 reset.

• Relay 186 BV-3 reset.

• Relay 186 BV-4 reset.

Standard: Rotates handle of bus undervoltage device clockwise until it clicks vertical.

Cue: As each BUV device handle is rotated, cue the operator that the handle clicks vertical.

Notes: BUV Relays have Red and White labels under them.

SAT / UNSAT Step 3: 05-1-02-I-4 3.3.12 e Observes white continuity light is on.

Standard: Operator locates and observes white continuity light is on.

Cue: White light is on.

Notes: White light comes on, located above TEST SWITCH 786 BV-1, when the last BUV device is reset SAT / UNSAT Revision 0 3/16/2013 Page 108 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 Step 4: 05-1-02-I-4 3.3.12 e Locate 6.9KV bus 12HE.

Standard: Locates bus 12HE in the electrical switchgear room in area 4 elevation 113 of the turbine building.

Cue: None Notes:

SAT / UNSAT Step 5: 05-1-02-I-4 3.3.12 e

• Reset bus undervoltage lockout devices on bus auxiliary cubicle.

• Relay 286BV-1 reset.

• Relay 286BV-2 reset.

Standard: Rotates handle of bus undervoltage device clockwise until it clicks vertical.

Cue: As each BUV device handle is rotated, cue the operator that the handle clicks vertical.

Notes: BUV Relays have Red and White labels under them.

SAT / UNSAT Revision 0 3/16/2013 Page 109 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 Step 6: 05-1-02-I-4 3.3.12 e Observes white continuity light is on.

Standard: Operator observes white continuity light is on.

Cue: White light is on.

Notes: White light comes on when the last BUV device is reset.

SAT / UNSAT Task Standard(s):

Bus 13AD and 12HE bus undervoltage lockout devices are reset.

SAT / UNSAT Remember to record stop time Revision 0 3/16/2013 Page 110 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS2 Follow-Up Questions & Answers:

Comments:

Revision 0 3/16/2013 Page 111 of 298

Give this page to the student Initial Condition(s):

• BOP Transformer 11B locked out on Sudden Pressure and de-energized 34.5 KV Bus 12R.

• BOP Buses 12HE and 13AD lost power.

• Control room operators have reenergized bus 12HE and bus 13AD from alternate feeders powered by BOP Transformers 12A and 12B per Loss of AC Power ONEP.

• Major loads powered from these buses cannot be restored until bus under voltage lockout devices are reset at the busses.

Initiating Cue(s):

• You have been directed to reset all bus under voltage lockout devices on bus 12HE and bus 13AD.

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 GGNS 2012-1 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2012-1PS3 JPM

Title:

Align Fire Water to LPCS per EP Attachment 26 Facility Number: GJPM-OPS-EOP26B (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 20 min Applicant: ________________________________ Examiner:

Performance Time: ________________________ Performance Rating:

SAT UNSAT Comments:

Prepared By: Kyle Grillis 3/21/2013 Exam Developer Date Ops Review: Robert st Brinkman 3/21/2013 1 Validation by Ops Rep or Ops Validation Crew Date Validated By: Gabe nd Hargrove 3/26/2013 2 Validation by Ops Validation Crew Date Approved By: Steve Reeves 3/26/2013 Project Lead or Exam Team Lead Date Revision 0 3/16/2013 Page 113 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Align Fire Water to LPCS per EP Attachment 26 Setting: Plant (Inside CAA)

Type: NLO Task: AON-P64-025 K&A: 286000 A1.05:3.2/3.2 295031: EA1.08 3.8/3.9; 2.1.30: 4.4/4.0 2.4.35 3.8/4.0 Safety Function: 2 Performance: Simulate Reference(s): 05-S-01-EP-1 Attachment 26 Handout(s): 05-S-01-EP-1 Attachment 26

1. Manipulations: 6

1. Critical Steps: 6 Simulator Setup/Required Plant Conditions:

• Auxiliary Building 119 elev., Areas 9/10 are accessible with radiation levels ALARA Safety Concerns:

• Wear appropriate personal protective equipment.

• Don't forget ALARA

• No climbing. Point up or down while you explain what you are going to do.

• DO NOT operate plant equipment Task Standard(s):

• Fire Water has been aligned to LPCS, pathway 3, in accordance with 05-S-01-EP-1, Attachment 26.

Revision 0 3/16/2013 Page 114 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Name: ___________________________ Time Start: _______ Time Stop: _______

Initial Condition(s):

• A LOCA has occurred.

• The reactor is shutdown with RPV level still lowering

• The SRO with the Command Function is implementing EP-2 actions Initiating Cue(s):

• The CRS directs you to obtain 05-S-01-EP-1 Attachment 26 Injection into RPV with Fire Protection Water System beginning at step 2.3 and align Fire Water for injection through LPCS.

• A ladder and extra fire hoses are being dispatched to the area.

• A spanner wrench has been obtained.

Revision 0 3/16/2013 Page 115 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Align Fire Water to LPCS per EP Attachment 26 Notes: (Notes to Evaluator)

• Fire hoses and nozzles are not to be disturbed during task performance.

• The only portion of the sequence that is critical is that the fire hose is connected before either the fire hose station valve or the pair of injection line test connection valves is opened.

Task Overview: (Detailed description of task)

• This task simulates routing and connecting fire hoses from hose stations to test connections on ECCS injection piping in the Auxiliary Building.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-S-01-EP-1 Attachment 26 Locate a copy of EP Attachment 26 Standard: Operator describes location of the dedicated copy of Attachment 26 in a box on top of the Control Room Emergency Locker Cue: When the operator describes the location of the box containing EP attachments, hand the operator the JPM copy of Attachment 26.

Notes:

SAT / UNSAT Revision 0 3/16/2013 Page 116 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Step 2: 05-S-01-EP-1 Attachment 26 Step 2.3.3 a LOCATE HOSE STATION 14B (Area 9 El 119 Outside switchgear room)

Standard: Locates hose station 14B (Area 9 EL. 119 outside of switchgear room).

Cue: None.

Notes:

SAT / UNSAT Step 3: 05-S-01-EP-1 Attachment 26 Step 2.3.3 b

• REMOVE nozzle from existing hose.

Standard: Describes removal of the nozzle from the hose on Hose Station 14B using common technique for right hand threads.

Cue: The nozzle is removed.

Notes:

SAT / UNSAT Revision 0 3/16/2013 Page 117 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Step 4: 05-S-01-EP-1 Attachment 26 Step 2.3.3 c

• ROUTE hose to the piping penetration room, Area 9/10.

Standard: Describes routing the hose from hose station 14B into the room.

Cue: The hose is in place.

Notes: Room 1A220 SAT / UNSAT Step 5: 05-S-01-EP-1 Attachment 26 Step 2.3.3 d

• CONNECT hose to RPV fill connection 1E21-F013/F014, located in the piping penetration room, Area 9/10.

Standard: Describes connecting the hose from hose station 14 into the room and connecting it to the special fitting at 1E21-F014 using common technique for right handed threads.

Cue: The hose is connected.

Notes:

SAT / UNSAT Revision 0 3/16/2013 Page 118 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Step 6: 05-S-01-EP-1 Attachment 26 Step 2.3.3 e

• SLOWLY OPEN Hose Station 14B isolation valve SP64-FA13B.

Standard: Describes slowly opening Hose Station 14B isolation valve SP64-FA13B by turning the handle counter-clockwise.

Cue: The hose is pressurized and you feel resistance in the counter-clockwise direction.

Notes:

SAT / UNSAT Step 7: 05-S-01-EP-1 Attachment 26 Step 2.3.3 f

• SLOWLY OPEN fill connection 1E21-F013, located in the piping penetration room, Area 9.

Standard: Describes slowly opening fill connection 1E21-F013 by turning the valve handle counter-clockwise.

Cue: You feel resistance in the counter-clockwise direction.

Notes:

SAT / UNSAT Revision 0 3/16/2013 Page 119 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Step 8: 05-S-01-EP-1 Attachment 26 Step 2.3.3 g

• SLOWLY OPEN fill connection 1E21-F014, located in the piping penetration room, Area 9.

Standard: Describes slowly opening fill connection 1E21-F014 by turning the valve handle counter-clockwise.

Cue: You feel resistance in the counter-clockwise direction.

Notes:

SAT / UNSAT Task Standard(s):

• Fire Water has been aligned to LPCS, pathway 3, in accordance with 05-S-1-EP-1, Attachment 26.

SAT / UNSAT Remember to record stop time Revision 0 3/16/2013 Page 120 of 298

Date of Examination: 05-06-2013 Operating Test Number: LOT 2012-1 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2012-1PS3 Follow-Up Questions & Answers:

Comments:

Revision 0 3/16/2013 Page 121 of 298

Give this page to the student Initial Condition(s):

• A LOCA has occurred.

• The reactor is shutdown with RPV level still lowering

• The SRO with the Command Function is implementing EP-2 actions Initiating Cue(s):

• The CRS directs you to obtain 05-S-01-EP-1 Attachment 26 Injection into RPV with Fire Protection Water System beginning at step 2.3 and align Fire Water for injection through LPCS.

• A ladder and extra fire hoses are being dispatched to the area.

• A spanner wrench has been obtained.

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Page 1 of 3 Facility: Grand Gulf Nuclear Station Scenario No.: 1 Op-Test No.: LOT-2012-1 Examiners: ____________________________ Operators: _____________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

Surveillance 06-OP-1B33-Q-0003-01 Reactor Recirc System Quarterly Valve Test.

1B33F019 RW Process Sampling Outboard Isolation Valve failure to reopen during stroke testing.

Component Cooling Water temperature control valve fails partially closed, requiring isolating CCW to RWCU and power reduction.

Jet pumps 5/6 failure Loss of Offsite Power followed by an unisolable LOCA in the Drywell.

Div 2 Load Shedding and Sequencing system failure.

RHR A logic power failure (LPCS available by manual action).

Emergency Depressurization required due to low reactor water level.

Initial Conditions: Plant is operating at 100% power.

Inoperable Equipment: Division 3 AOT in progress with High Pressure Core Spray system and Division 3 Diesel Generator unavailable Turnover:

• Plant is in steady state operation at 100% power.

• The Division 3 AOT in progress with High Pressure Core Spray system and Division 3 Diesel Generator out of service for maintenance. Division 3 is scheduled to remain unavailable for the next 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />.

• Following shift briefing, perform 06-OP-1B33-Q-0003, Attachment 1, Reactor Recirc System Quarterly Valve Test.

Scenario Notes:

This is a new scenario.

Validation Time (60-90 min): 80 min Revision 0 4/02/13

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Page 2 of 3 Event Malf. No. Event Type Event No. Description Reactor Recirc System Quarterly Valve Test (06-OP-1B33-Q-1 N (ATC) 0003, Attachment 1).

1B33F019 RW Process Sampling Outboard Isolation Valve C (ATC) failure to reopen during stroke testing (06-OP-1B33-Q-0003, 2 b33f019_i TS (CRS) Alarm Response Instruction 04-1-02-1H13-P601-19A-G3, TS 3.6.5.3, TR SR 6.4.1.5).

A (CREW) Component Cooling Water temperature control valve fails 3 p42R016 R(ATC) partially closed, requiring isolating CCW to RWCU and power C (ATC) reduction (05-1-02-V-1 Loss of Component Cooling Water).

A (CREW) Jet pumps 5/6 rams head failure (05-1-02-III-6 Jet Pump 4 rr011c C (ATC) Anomalies, 05-1-02-III-3 Reduction in Recirculation System TS (CRS) Flow Rate, TS 3.4.3).

Loss of Offsite Power followed by an unisolable LOCA in the Drywell (EP-2 RPV Control, EP-3 Containment Control, 05 02-I-1 Reactor Scram, 05-1-02-I-2 Turbine and Generator Trips, 05-1-02-I-4 Loss of AC Power).

r21135 When reactor water level lowers to between -160 (TAF) and 5 M(CREW) -191, the crew opens 8 SRVs and observes lowering pressure rr063a trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized) Criterion is to open at least seven SRVs before RPV level drops to -217.

Rapid Depressurization with the BPVs satisfies this critical task.

I(BOP) Div 2 Load Shedding and Sequencing system failure (Alarm 6 r21218 Response Instruction 04-1-02-1H13-P864-2A-H1).

RHR A logic power failure (LPCS available by manual action)

When drywell pressure exceeds 1.39 psig or reactor water level is below -150.3, the crew recognizes Division 1 ECCS fails to automatically initiate and indication of RHR A Logic Power Failure and manually starts LPCS pump using its P601 hand switch. (Criterion is to align LPCS for injection by manually starting LPCS pump on P601 prior to Emergency Depressurization.)

7 r21220 I(ATC/BOP)

AND/OR Align RHR A for injection by manually starting RHR A pump and opening 1E12F053A RHR A Shutdown Cooling Return to Feedwater on P601 or opening 1E12F042A RHR A INJ SHUTOFF VLV on Div 1 Remote Shutdown Panel (Criterion is to align RHR A for injection prior to going below 125 psig during Emergency Depressurization.)

Revision 0 4/02/13

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Page 3 of 3 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

• Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 1 Abnormal Events 2 Reactivity Manipulations 1 Total Malfunctions 7 Instrument/Component Failures 5 EP Entries (Requiring substantive action) 1 Major Transients 1 EP Contingencies 1 Tech Spec Calls 2 Critical Tasks 2 Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 1 of 21 Simulator Setup:

A. Initialization

1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).

2. Startup the simulator using Simulator Instructors Job Aid section 6.3.

Note:

Prior to running the Schedule File, ensure no Event Files are Open. If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load

3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.

4. Set the Simulator to IC-141and perform switch check (Using Quick Reset in Director).

5. Click on Open in the Schedule window and Open Schedule File 2012-1 scenario 1.sch (in the Schedule Directory)

6. In Schedule window, click on the Stopped red block. The red block will change to a green arrow and indicate the scenario is active (Running).

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 2 of 21

7. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

8. Take the simulator out of freeze.

9. Log on to all simulator PDS and SPDS computers.

10. Verify or perform the following:

• IC-141

• Power approximately 100%

• Ensure the BOC movement sequence available at the P680.

• Advance all chart recorders and ensure all pens inking properly.

• Ensure APRM recorders are displaying APRM trend mode.

• Clear any graphs and trends off of SPDS.

• Place HPCS Jockey Pump handswitch to STOP on 1H13P601

• Place HPCS OOSVC switch to INOP on 1H13P601

• Place Red Tags on the following on 1H13P601:

o HPCS Pump handswitch o HPCS Jockey Pump handswitch o 17AC Feeder Breaker from DG13, 152-1701

11. Run through any alarms and ensure alarms are on. (Note: On T-Rex, to verify alarms are ON, the indicator will indicate Alarms On).

12. Place the simulator in Freeze.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 3 of 21 B. File loaded verification:

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 4 of 21 Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 5 of 21 Crew Turnover:

B. Assign the candidates crew positions.

C. Turnover the following conditions:

Power 100%

Pressure 1021 psig BOC EOOS YELLOW Work Week Division 3

• Plant is in steady state operation at 100% power.

• The Division 3 AOT in progress with High Pressure Core Spray system and Division 3 Diesel Generator out of service for maintenance. Division 3 is scheduled to remain unavailable for the next 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />.

Planned Evolutions this shift:

• Following shift briefing, perform 06-OP-1B33-Q-0003, Attachment 1, Reactor Recirc System Quarterly Valve Test.

• Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

D. Allow the crew to perform pre-shift brief and review procedures for planned evolutions.

E. Bring the crew into the Simulator, place the simulator is in RUN.

F. Allow the crew to walk down panels.

G. When the crew assumes the shift begin Scenario Activities.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 6 of 21 SCENARIO ACTIVITIES:

• Start SBT report and any other required recording devices (Video recording not allowed for NRC exams).

Reactor Recirc System Quarterly Valve Test (06-OP-1B33-Q-0003, Attachment 1):

• The crew will perform Reactor Recirc System Quarterly Valve Test (06-OP-1B33-Q-0003, Attachment 1).

• When requested to isolate the Containment Sample Panel by closing manual valve 1P33F856, wait 1 minute, then respond as Plant Chemistry that 1P33F856 has been closed.

• When 1B33F019 is closed, its breaker will trip (Auto Event 2).

• If requested to check breaker 52-163141 for 1B33F019, wait 5 minutes, then as the building operator report the breaker is tripped. If requested to investigate as Electrical Maintenance, report a WO and tagout will be required for troubleshooting before attempting to reset the breaker.

• When the CRS enters LCO 3.6.5.3 Condition A and potential LCO for continuous reactor conductivity monitoring per TR SR 6.4.1.5, and any briefs are complete, at the Lead Evaluators discretion, insert remote function p42R016 by triggering Event 3 to cause Component Cooling Water temperature control valve 1P44F501 to fail partially closed.

Component Cooling Water temperature control valve 1P44F501 fails partially closed

• The crew will respond using 05-1-02-V-1 Loss of Component Cooling Water for a partial loss.

• The crew will trip RWCU pumps:

• If sent to investigate locally, as the building operator report CCW temperature controller 1P44R016 is indicating 100% demand output, but CCW temperature control valve 1P44F501 looks like it is mostly closed or may be oscillating, although it is hard to see since it is high in the overhead.

• When directed as the building operator to close 1P42F103, CCW to RWCU Non Regenerative Heat Exchangers, trigger event 11 to insert remote function p42037.

• The crew will reduce core flow to 70 mlbm/hr.

• After the crew has reduced core flow to 70 mlbm/hr, the severity of the temperature control valve failure will reduce (Auto Event 25) to ensure Reactor Recirc Pump temperatures stop rising (temperatures will fall).

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 7 of 21 Then report as the building operator that CCW temperature control valve 1P44F501 has opened and looks like it is attempting to control.

• If asked for OPRM 1,3, and 4 status from back panels (OPRM 2 is modeled on backpanels), as booth operator inform the operator OPRM 1, 3, and 4 are enabled (not bypassed).

• When power has been reduced and Reactor Recirc Pump temperatures have been addressed, at the Lead Evaluators discretion, insert malfunction rr011c by triggering Event 4 to cause failure of Jet Pumps 5/6.

Jet Pumps 5/6 Failure:

• The crew will respond using ONEPs 05-1-02-III-6 Jet Pump Anomalies, 05-1-02-III-3 Reduction in Recirculation System Flow Rate.

• If requested to perform 06-RE-1B33-D-0001, as Reactor Engineering after approximately 5 minutes report the surveillance failed for Jet Pumps 5 and 6.

• When the CRS enters LCO 3.4.3 Condition A, and any transient briefs are complete, at the Lead Evaluators discretion, insert malfunction rr012b by triggering Event 5 to cause Loss of Offsite Power followed by LOCA.

Loss of Offsite Power followed by an unisolable LOCA in the Drywell:

• A loss of offsite power will occur when event 5 is triggered. A small Recirc Loop A suction line will occur 1 minute later. Division 2 LSS will fail upon the loss of offsite power. RHR A Logic Power Failure will occur after the LOCA when drywell pressure rises to 1.39 psig (Auto Event 7)

• The crew will take actions per EP-2 RPV Control, EP-3 Containment Control, 05 02-I-1 Reactor Scram, 05-1-02-I-2 Turbine and Generator Trips, and 05-1-02-I-4 Loss of AC Power:

• If contacted regarding restoration of offsite power, as the system dispatcher report the cause has not been determined and you estimate it will take at least one hour to restore one offsite source once the cause is determined.

• Regarding Division 2 LSS:

o If directed to investigate Division 2 LSS panel failure, wait 5 minutes, then report as the building operator that there appears to be a loss of power to the Division 2 LSS panel. If sent to check breakers 72-11E70 and 72-11B24, wait 5 minutes, then report 72-11B24 is tripped. If directed to reclose 72-11B24, wait 1 minute, then report 72-11B24 will not reset.

o If directed to investigate Division 2 DG not starting, wait 5 minutes, then report as the building operator that Division 2 DG has no alarms and indicates it is in standby.

• Regarding RHR A Logic Power Failure, if directed to check breaker 72-11A38, wait 5 minutes, then as the building operator report 72-11A38 is tripped. If directed to reclose 72-11 A38, wait 1 minute, then report 72-11 A38 will not reset.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 8 of 21 Termination:

• When reactor water level has been restored and stabilized in the -30 to 30 level band, or as directed by Lead Evaluator:

o Take the simulator to Freeze and turn horns off.

o Stop and save the SBT report and any other recording devices.

o Instruct the crew to not erase any markings or talk about the scenario until after follow-up questions are asked.

Critical Tasks:

When reactor water level lowers to between -160 (TAF) and

-191, the crew opens 8 SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized)

Criterion is to open at least seven SRVs before RPV level drops to -217. Rapid Depressurization with the BPVs satisfies this critical task.

When drywell pressure exceeds 1.39 psig or reactor water level is below -150.3, the crew recognizes Division 1 ECCS fails to automatically initiate and indication of RHR A Logic Power Failure and manually starts LPCS pump using its P601 hand switch AND/OR align RHR A for injection. Criterion is to align LPCS for injection (by manually starting LPCS pump on P601) prior to Emergency Depressurization AND/OR align RHR A for injection (by manually starting RHR A pump and opening 1E12F053A RHR A Shutdown Cooling Return to Feedwater on P601) prior to going below 125 psig during Emergency Depressurization.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 9 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 1 Event

Description:

06-OP-1B33-Q-0003-01 Reactor Recirc System Quarterly Valve Test TIME Position Applicants Actions or Behavior Directs ATC to perform 06-OP-1B33-Q-0003-01 Reactor Recirc System CRS Quarterly Valve Test.

Begins performing 06-OP-1B33-Q-0003-01 Reactor Recirc System Quarterly ATC Valve Test, as directed.

Peer checks ATC actions for 06-OP-1B33-Q-0003-01 Reactor Recirc System BOP Quarterly Valve Test Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 10 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 2 Event

Description:

1B33F019 RW Process Sampling Outboard Isolation Valve failure to reopen during stroke testing TIME Position Applicants Actions or Behavior

• Recognizes and reports 1B33F019 failure when attempting to reopen it.

• Suspends performing surveillance at that point and requests directions ATC from CRS.

(Note: The green closed position indication light above the 1H13P680 hand switch for 1B33F019 will remain lit after the breaker for 1B33F019 trips, because it is fed by an independent 120 VAC power panel breaker.)

Responds to annunciator 04-1-02-1H13-P601-19A-G3 RX INBD ISOL SYS OOSVC:

BOP

• Refers to Alarm Response Instruction

• Identifies circuit for 1B33F019 is an input to this alarm

• Dispatches building operator to check breaker 52-163141

• Directs suspending surveillance 06-OP-1B33-Q-0003-01. (Not expected to direct completing surveillance as a partial, including returning MOV Test switches to Normal due to scenario progression).

• Enters LCO for TS 3.6.5.3 Condition A one inoperable automatic CRS isolation valve in a penetration f.

• May enter Potential LCO for TR SR 6.4.1.5 for one reactor water continuous Conductivity Monitor sample paths (Recirc System) isolated. (This is not required for TS compliance for first TS call by CRS for this scenario).

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 11 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 3 Event

Description:

Component Cooling Water temperature control valve 1P44F501 fails partially closed TIME Position Applicants Actions or Behavior ATC Recognizes and reports CCW temperature rising based on PDS trend.

Responds to annunciator 1H13-P870-5A-D1, CCW HX OUTL TEMP HI.

• Verifies adequate Plant Service Water flow to the plant by verifying normal PSW supply header pressure ~25-30 psig on 1H13P854 and BOP stable PSW makeup flow on 1H13P870 (or PDS) and notifies CRS.

• Dispatches operator to check 1P44F501, CCW Temperature Control Valve, and temperature controller 1P44R016 for proper operation.

Enters 05-1-02-V-1, Loss of Component Cooling Water for partial loss (due to CCW temperature high, NOT degraded CCW flow/pressure):

• Directs ATC to monitor CCW heat exchanger outlet temperature and RWCU non-regenerative heat exchanger outlet (RWCU Filter Demin inlet) temperature.

CRS

• Directs ATC to secure RWCU pumps (once determined rate of RWCU non-regenerative heat exchanger outlet temperature rise does not allow time to place RCWU filters in hold before F/D would automatically isolate, 140°F).

• Directs BOP to monitor Reactor Recirc pump temperatures.

• Monitors CCW heat exchanger outlet temperature and RWCU non-regenerative heat exchanger outlet temperatures. Notifies CRS of values and trends.

ATC

• Trips RWCU pumps A and B on 1H13P680, as directed.

• Sends building operator to close 1P42F103, RWCU HX ISOL VLV.

Responds to annunciator 1H13-P680-3A-A8, RECIRC PMP/MTR A/B TEMP HI.

• Monitors Reactor Recirc pump temperatures on PDS and/or BOP 1H13P614. Determines no metal temperatures are near their alarm setpoints, only high cooling water temperatures.

• Notifies CRS of values and trends.

Following tripping RWCU pumps, when Reactor Recirc pump temperatures CRS continue to rise, directs ATC to lower power by reducing core flow using Reactor Recirc FCVs in fast detent to 70 mlbm/hr.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 12 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 3 (Cont.)

Event

Description:

Component Cooling Water temperature control valve 1P44F501 fails partially closed

• Reduces core flow to 70 mlbm/hr using Reactor Recirc FCVs A/B, as ATC directed.

• Plots point of operation in OPRM Enabled Region of Power/Flow map.

Following power reduction, continues to monitor and reports Reactor Recirc BOP temperatures lowering.

Enters 05-1-02-III-3, Reduction in Recirculation System Flow Rate:

• Directs ATC to monitor for Thermal Hydraulic Instability, concurrent duties allowed.

CRS

• Directs BOP to verify at least 3 OPRMs are enabled (not bypassed).

May pursue continuing power reduction based on CCW temperature trend (depends on timing of crew actions), but temperatures will trend down before additional power reduction is required.

Monitors APRMs, LPRMs, SRM Period meters, and OPRM PDS trends on ATC 1H13P680 for Thermal Hydraulic Instability with no .concurrent duties until reactor conditions are stable.

BOP Verifies OPRMs are enabled on PDS and/or back panel PRNM cabinets.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 13 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 4 Event

Description:

Jet pumps 5/6 rams head failure Recognizes and reports step change reduction in power indicated on 1H13P680:

• MWe loss ATC

• APRM trends

• Feedwater flow reduction

• Reactor water level perturbation Diagnoses jet pump failure as indicated by on 1H13P680:

• Reduced total core flow

• Recirc Loop A and B elevated drive flows ATC

• Calibrated Jet Pump A flow less than calibrated Jet Pump B, C, and D flows

• Reduced Core dp Checks individual Jet Pump dp on 1H13P619.

BOP Recognizes and reports Jet Pumps 5 and 6 dps less than other Jet Pump dps.

Enters 05-1-02-III-6, Jet Pump Anomalies:

• Directs ATC to determine actual total core flow and plot point of operation on Power/Flow map CRS

• Directs Reactor Engineering to perform 06-RE-1B33-D-0001, Jet Pump Functional Test, and to verify thermal limits are met.

Re-enters 05-1-02-III-3 Reduction in Recirculation System Flow Rate:

Determines actual core flow per 05-1-02-III-6, Jet Pump Anomalies (by doubling the indicated flow for calibrated jet pump A and subtracting that from indicated core flow twice).

Plots and reports point of operation on the Power/Flow Map ATC

• Depending on precise degree of previous core flow reduction to 70 mlbm/hr, may plot in OPRM Enabled Region of Power/Flow map, on the line between OPRM Enabled Region and Controlled Entry Region, or in Controlled Entry Region.

If operation is reported in or on the line of the Controlled Entry Region of the CRS Power/Flow map, directs inserting CRAM rods until the Controlled Entry Region is exited.

If CRAM rod insertion is required:

BOP

• Inserts CRAM rods as directed until operation is in the OPRM Trip Enabled Region of the Power/Flow Map.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 14 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 4 (Cont.)

Event

Description:

Jet pumps 5/6 rams head failure If CRAM rod insertion is required:

• Peer checks control rod movement while continuing to monitor for ATC THI..

• Plots point of operation on Power/Flow Map.

• Reports exiting Controlled Entry Region.

Enters TS 3.4.3 Condition A.

Makes notifications for entering TS 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shutdown statement.

CRS Begins reviewing 03-1-01-2, Power Operations for commencing plant shutdown.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 15 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 5 Event

Description:

Loss of Offsite Power followed by an unisolable LOCA in the Drywell TIME Position Applicants Actions or Behavior BOP Recognizes and reports loss of switchyard/offsite power.

Recognizes and reports reactor scram:

• Places Reactor Mode Switch to shutdown

• Verifies all control rods fully inserted (indicated on RPIS channel 1after ATC Div 1 DG restores power to bus 15AA) and power approximately 0%

• Recognizes and reports reactor water level reduced due to loss of Condensate/Feedwater

• Recognizes and reports Main Turbine tripped and MSIVs closed Enters the following procedures (simultaneously):

• EP-2, RPV Control

• 05-1-02-I-1, Reactor Scram CRS

• 05-1-02-I-2, Turbine and Generator Trips

• 05-1-02-I-4, Loss of AC Power Check Recognizes and reports Reactor Water Level Low, Level 2.

ATC

• Verifies RCIC initiated and injecting (HPCS system tagged OOSVC).

Checks Division 1, 2, and 3 Diesel Generators have energized their respective buses. Recognizes and reports bus 16AB de-energized and Division 2 LSS failure.

• Dispatches operator to investigate failure of Div 2 LSS.

BOP

• Verifies SSW A aligned to Div 1 DG on 1H13P870. (SSW C will align to Div 3 DG and HPCS but may not be verified since HPCS and Div 3 DG are red tagged OOSVC)

• Verifies isolations for Level 2 on 1H13P870.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 16 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 5 (Cont.)

Event

Description:

Loss of Offsite Power followed by an unisolable LOCA in the Drywell From EP-2, RPV Control:

• Directs verify initiations and isolations for Reactor Level 2 CRS

• Directs ATC establish a level band of +30 to -30 in using RCIC

• Directs BOP establish a pressure band of 800 -1060 psig using SRVs Recognize and report indications of a LOCA in the Drywell as indicated by rising drywell pressure and temperature (P680-5A-C3, DRWL PRESS HI/LO; CREW P680-5A-C2, DRWL PRESS HI HI; Low Pressure ECCS initiations due to 1.39 psig in the drywell).

Verifies Low Pressure ECCS initiations for Drywell Pressure High:

• Recognizes Div 1 and Div 2 ECCS initiations occurred on 1H13P601(white lights above ECCS Manual Initiation push buttons lit)

• Recognizes no low pressure ECCS systems automatically align for injection on 1H13P601.

• Recognizes and reports RHR A Logic Power Failure as indicated by RHR A OOSVC alarm and logic power failure status light on 1H13P601.

Manually starts LPCS pump using its 1H13P601 hand switch and reports LPCS aligned for injection ATC/

• Recognizes and reports RHR A available for injection from 1H13P601 via 1E12F053A, RHR A SHUTDN CLG RTN TO FW BOP When drywell pressure exceeds 1.39 psig or reactor water level is below -

150.3, the crew recognizes Division 1 ECCS fails to automatically initiate and indication of RHR A Logic Power Failure and manually starts LPCS pump using its P601 hand switch. (Criterion is to align LPCS for injection by manually starting LPCS pump on P601 prior to Emergency Depressurization.)

AND/OR Align RHR A for injection by manually starting RHR A pump and opening 1E12F053A RHR A Shutdown Cooling Return to Feedwater on P601 or opening 1E12F042A RHR A INJ SHUTOFF VLV on Div 1 Remote Shutdown Panel (Criterion is to align RHR A for injection prior to going below 125 psig during Emergency Depressurization.)

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 17 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 5 (Cont.)

Event

Description:

Loss of Offsite Power followed by an unisolable LOCA in the Drywell Enter EP-3 and re-enter EP-2 Direct actions of EP-2:

• Verify initiations and isolations for Drywell Pressure 1.39 psig.

• Enter the Alternate Level Control procedure of EP-2.

CRS

• Inhibit ADS

• Maximize CRD for flow.

Addresses all legs of EP-3

• Directs verifying Div 1 Drywell and Containment hydrogen analyzers are operating and starting Div 1 Drywell/Containment Hydrogen Igniters When directed, maximize CRD A for flow (only CRD A pump is available due to bus 16AB de-energized).

• Re-energize 15B42 on P864

• Start the CRD A Aux Oil Pump ATC

• Start the CRD A Pump

• Although there are other actions per the procedure, only these listed will accomplish anything with scram sealed in and loss of offsite power.

Update the CRS with reactor water level as it continues to lower.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 18 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 5 (Cont.)

Event

Description:

Loss of Offsite Power followed by an unisolable LOCA in the Drywell TIME Position Applicants Actions or Behavior When directed, Inhibit ADS by placing both ADS inhibit switches to INHIBIT.

BOP Dispatch operators to recover out of service water injection sources.

Evaluate and deliver ECCS Status Report to the CRS (hard card).

• Provides frequent reports of reactor water level and trend.

ATC

• Reports level at Top of Active Fuel when level trends offscale low on wide range recorders on 1H13P601.

Verifies Div 1 Drywell/Containment Hydrogen Analyzers are operating and BOP starts Div 1 Drywell/Containment Hydrogen Igniters on 1H13P870 Directs aligning EP-2 Table 2 systems for injection when determined level cannot be restored to nominal band, 30 to +30:

CRS

• Directs ATC to initiate Standby Liquid Control System A

• Calls Maintenance/OSC for Fire Water to be connected for injection per Attachment 26 via HPCS and RHR C pathways.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 19 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 5 (Cont.)

Event

Description:

Loss of Offsite Power followed by an unisolable LOCA in the Drywell TIME Position Applicants Actions or Behavior When directed to initiate SBLC A, use 04-1-01-C41-1, Standby Liquid Control System, Attachment VI (Initiation of Standby Liquid Control hard card):

• Insert keys and turn SBLC Pmp A pump key switch to START.

• Verify system initiation by observing the following:

o F004A SQUIB valves fired:

White SQUIB valve ready light OFF Annunciator SLC SYS A OOSVC (P601-19A-H1)

Amber status light SQUIB A LOSS CONT or PWR LOSS is ON.

ATC/ o C41-F001A tank outlet valve is open.

o SBLC Pump A running.

o RWCU Isolated G33-F004 Closed o Verify SBLC A is injecting into the RPV by observing the following:

SBLC pump discharge pressure exceeds reactor pressure.

SBLC tank level lowering.

When reactor water level reaches -160 and before -191, enter Emergency Depressurization leg of EP-2, RPV Control

• Verify Suppression Pool level is above 10.5

• Direct the BOP to open 8 ADS/SRVs CRS When reactor water level lowers to between -160 (TAF) and

-191, the crew opens 8 SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized) Criterion is to open at least seven SRVs before RPV level drops to -217.

BOP When directed, Opens at least 7 ADS valves on 1H13P601.

Revision 0 4/02/13

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 20 of 21 Op-Test No: 2012-1 Scenario No: 1 Event No: 5 (Cont.)

Event

Description:

Loss of Offsite Power followed by an unisolable LOCA in the Drywell TIME Position Applicants Actions or Behavior When reactor pressure lowers to <500 psig, directs injection with RHR A by manually starting RHR A Pump on 1H13P601 or on Div 1 Remote Shutdown Panel and opening either:

CRS 1E12F053A, RHR A SHUTDN CLG RTN TO FW from 1H13P601, or 1E12F042A, RHR A INJ SHUTOFF VLV from Div 1 Remote Shutdown Panel As directed, injects with RHR A by manually starting RHR A Pump on 1H13P601 or on Div 1 Remote Shutdown Panel and opening either:

ATC/

1E12F053A, RHR A SHUTDN CLG RTN TO FW from 1H13P601, or BOP 1E12F042A, RHR A INJ SHUTOFF VLV from Div 1 Remote Shutdown Panel

• Monitors for LPCS and/or RHR A injection and ensures level is re-established above TAF.

ATC

• Controls LPCS and/or RHR A injection by operating injection valves or cycling pumps to restore and control reactor water level -30 to +30 on wide range level instrumentation.

Revision 0 4/02/13

Give this page to the CRS Turnover the following conditions:

Power 100%

BOC EOOS YELLOW Work Week Division 3

• Plant is in steady state operation at 100% power.

• The Division 3 AOT in progress with High Pressure Core Spray system and Division 3 Diesel Generator out of service for maintenance. Division 3 is scheduled to remain unavailable for the next 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />.

Planned Evolutions this shift:

• Following shift briefing, perform 06-OP-1B33-Q-0003, Attachment 1, Reactor Recirc System Quarterly Valve Test.

• Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

Revision 0 4/02/12 Page 20 of 21

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Page 1 of 3 Facility: Grand Gulf Nuclear Station Scenario No.: 2 Op-Test No.: LOT-2012-1 Examiners: ____________________________ Operators: _____________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

• Remove Heater Drain Pump A from service.

• Heater Drain Pump B trip when Heater Drain Pump A is secured.

• RPS/NSSSS pressure trip unit B21N678C fails high.

• Reactor Recirc Pump B trip.

• Condenser boot seal leak, slow loss of vacuum

• Manual scram, hydraulic block ATWS, power greater than 5%, Condenser boot seal tear, rapid loss of vacuum.

• Standby Liquid Control suction valves failure to open

• Wide range level indication Channel A fails as-is Initial Conditions: Plant is operating at 83.5% power.

Inoperable Equipment: None Turnover:

• Power has been reduced to 83.5% per 03-1-01-2 Att. VIII, Temporary Downpower, to remove Heater Drain Pump A from service for an emergent maintenance window scheduled for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• Following shift briefing, secure Heater Drain Pump A per 04-1-01-N23-1 section 4.6.

Scenario Notes:

This is a new scenario.

Validation Time (60-90 min): 85 min Revision 0 04/01/12

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Page 2 of 3 Event Malf. No. Event Type Event No. Description Remove Heater Drain Pump A from service (04-1-01-N23-1 1 N (ATC) section 4.6).

Heater Drain Pump B trip when Heater Drain Pump A is C (ATC) secured (Alarm Response Instruction 04-1-02-1H13-P680-1A-2 fw231b R(ATC) A8, 05-1-02-V-5 Loss of Feedwater Heating, 05-1-02-III-3 Reduction in Recirculation System Flow Rate).

RPS/NSSSS pressure trip unit B21N678C fails high (Alarm ptb21n078c I (ATC) Response Instructions 04-1-02-1H13-P680-5A-B2/7A-A2/4A2-3

_a TS (CRS) D4, Section Procedure 17-S-06-5 Technical Specification Instrumentation Loop Logic, TS 3.3.1.1, TS 3.3.6.1).

C (ATC) Reactor Recirc Pump B trip (Alarm Response Instructions 04-4 rr012b A(CREW) 1-02-1H13-P680-3A-B10, 05-1-02-III-3 Reduction in TS (CRS) Recirculation System Flow Rate, TS 3.4.1, TR 3.4.1).

C (ATC) Condenser boot seal leak, slow loss of vacuum (05-1-02-V-8 5 fw163c A(CREW) Loss of Condenser Vacuum)

Manual Scram, hydraulic block ATWS, power > 5%,

Condenser boot seal tear, rapid loss of vacuum, level/power control (05-1-02-V-8 Loss of Condenser Vacuum, 05-1-02-I-1 Reactor Scram, 05-1-02-I-2 Turbine and Generator Trips, EP-2A ATWS RPV Control, EP-3 Containment Control)

Entry into EP2A step L8 (when Suppression Pool temperature >110°F). Crew terminates and prevents all injection except boron, CRD, and RCIC per 02-S 27 Operations Philosophy. Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criterion is to give the highest priority to terminate and prevent all injection except boron, CRD, and RCIC until reaching criteria specified in EP2A step L8.

fw264c M (CREW) 6 c11164 Criteria specified in EP2A step L-9 are satisfied. Crew restores injection using Condensate/Feedwater as evidenced by feedwater flow to RPV or RPV level trend. Criterion is to give the highest priority to reinitiate injection flow and establish the appropriate level band.

Hydraulic block ATWS occurs. Crew directs installation of EP Attachments 18, 19, and 20 and control rods are inserted by manual scram and/or normal rod insertion. Criteria is to give the highest priority, along with level and pressure control, to insert control rods by manual scram and/or normal rod insertion following installation of EP Attachments 18 and 19 (20 for normal rod insertion).

c41329 lo-7 C(BOP) Standby Liquid Control suction valves failure to open 1c41f031_r 1c41f031_g 8 rr041a I(ATC) Wide range level indication Channel A fails as-is Revision 0 04/01/12

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Page 3 of 3 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

• Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 1 Abnormal Events 2 Reactivity Manipulations 1 Total Malfunctions 7 Instrument/Component Failures 6 EP Entries (Requiring substantive action) 2 Major Transients 1 EP Contingencies 1 Tech Spec Calls 2 Critical Tasks 3 Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 1 of 22 Simulator Setup:

C. Initialization

13. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).

14. Startup the simulator using Simulator Instructors Job Aid section 6.3.

Note:

Prior to running the Schedule File, ensure no Event Files are Open. If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load

15. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.

16. Set the Simulator to IC-142 and perform switch check (Using Quick Reset in Director).

17. Click on Open in the Schedule window and Open Schedule File 2012-1 scenario 2.sch (in the Schedule Directory)

18. In Schedule window, click on the Stopped red block. The red block will change to a green arrow and indicate the scenario is active (Running).

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 2 of 22

19. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

20. Take the simulator out of freeze.

21. Log on to all simulator PDS and SPDS computers.

22. Verify or perform the following:

• IC-142

• Power approximately 83.5%

• Ensure the BOC rod movement sequence available at the P680.

• Advance all chart recorders and ensure all pens inking properly.

• Clear any graphs and trends off of SPDS.

• Ensure APRM recorders are displaying APRM trend mode.

• Placed marked up copy of 03-1-01-2 Power Operations, Att. VIII, Temporary Downpower on CRS desk.

23. Run through any alarms and ensure alarms are on. (Note: On T-Rex, to verify alarms are ON, the indicator will indicate Alarms On).

24. Place the simulator in Freeze.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 3 of 22 D. File loaded verification:

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 4 of 22 Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 5 of 22 Crew Turnover:

H. Assign the candidates crew positions.

I. Turnover the following conditions:

Power 83.5%

BOC EOOS GREEN Work Week Division 1 Power has been reduced to 83.5% per 03-1-01-2 Att. VIII, Temporary Downpower, to remove Heater Drain Pump A from service for emergent maintenance on the pump seal, which is scheduled for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned Evolutions this shift:

• Remove Heater Drain Pump A from operation per SOI 04-1-01-N23-1 section 4.6.

• Maintain power level approximately 84% until Heater Drain Pump B has been returned to operation.

• Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

J. Allow the crew to perform pre-shift brief and review procedures for planned evolutions.

K. Bring the crew into the Simulator, place the simulator is in RUN.

L. Allow the crew to walk down panels.

M. When the crew assumes the shift begin Scenario Activities.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 6 of 22 SCENARIO ACTIVITIES:

• Start SBT report and any other required recording devices (Video recording not allowed for NRC exams).

Shut down Heater Drain Pump A:

• The crew will secure Heater Drain Pump A using 04-1-01-N23-1 section 4.6 (Heater Drain Pump Shutdown).

• 5 seconds after Heater Drain Pump A is secured, Heater Drain Pump B will trip (Auto Event 2).

Heater Drain Pump B trip

• The crew will respond using 05-1-02-V-5, Loss of Feedwater Heating, and ARI P680-1A-A8.

• Enter 05-1-02-V-5, Loss of Feedwater Heating:

• The crew will reduce core flow to 70 mlbm/hr per 05-1-02-V-5 and to gain margin for Reactor Feed Pump suction pressure (satisfies ARI immediate action to reduce power to 79%).

• The crew will enter 05-1-02-III-3, Reduction in Recirculation System Flow Rate, and assign monitoring for thermal hydraulic instability due to operation in the OPRM Trip Enabled region of the Power/Flow map.

• The crew will observe feed water temperature and plot point of operation in Region I of the Feedwater Temperature vs. Power curve (no further action required).

• If directed to investigate, report as the building operator and/or Electrical Maintenance that HDP B breaker 152-1408 is tripped on timed overcurrent but there is no indication of a fault at HDP B itself.

• When power has been reduced and feedwater temperature has been addressed, at the Lead Evaluators discretion, insert malfunction ptb21N078c_a by triggering Event 3 to cause RPS Reactor Pressure transmitter C to fail upscale.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 7 of 22 RPS Reactor Pressure trip unit 1B21N678C failure high (half scram):

• The crew will respond using ARIs P680-5A-B2, P680-7A-A2, and P601-19A-G3.

• When asked by the operator responding to upper control room panel 1H13-P693, inform him the red trip light on Reactor Pressure master trip unit 1B21N678C is on, its gross fail LED is on, and its meter is indicating upscale. Also, inform him Reactor Pressure slave trip unit 1B21N679C red trip light is on and its gross fail light is on.

• If asked to investigate as I&C, wait 5 minutes and report the same information given above, and say you will initiate a work request.

• When the CRS enters LCO 3.3.1.1 Condition A and LCO 3.3.6.1 Condition A, and any transient briefs are complete, at the Lead Evaluators discretion, insert malfunction rr012b by triggering Event 4 to cause Reactor Recirc Pump B to trip.

Reactor Recirc Pump B to trip:

• The crew will take actions per 05-1-02-III-3, Reduction in Recirc System Flow Rate:

• Assign operator to monitor for thermal hydraulic instability with no concurrent duty until feedwater temperature stabilizes.

• Immediately initiate action to exit the Controlled Entry Region by raising core flow or by inserting control rods.

o If consulted, as Reactor Engineering recommend raising total core flow to a target of 56 mlbm/hr using Reactor Recirc Loop A to exit the Controlled Entry Region.

o If requested by operator checking APRM/OPRMs at control room back panels, inform him OPRMs are operating with no faults.

o If contacted as I&C or Work Management to implement single loop setpoints per TR 3.4.1, respond that a work task will be issued and setpoints should be implemented within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• The ATC will close Reactor Recirc Pump B Discharge Valve 1B33F067B on P680 and, after 5 minutes, reopen it.

• When the CRS has addressed LCO 3.4.1 and TR3.4.1, and any transient briefs are complete, at the Lead Evaluators discretion, insert malfunction fw163c by triggering Event 5 to cause a main condenser vacuum leak.

Main Condenser Vacuum Leak:

• The crew will enter 05-1-02-V-8, Loss of Condenser Vacuum.

• When it becomes apparent that the main turbine low condenser vacuum trip set point will be reached, the crew will initiate a reactor scram.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 8 of 22

• If sent as the local operator to investigate the cause for loss of vacuum, acknowledge the order but do not report back a cause. If the control room makes subsequent contact, tell them you are still investigating.

• When the manual scram is inserted, the vacuum leak severity will increase, Auto Event 6. Vacuum will lower to the main bypass valve trip setpoint, but severity will reduce as vacuum lowers, Auto Event 25, so that vacuum will remain above the MSIV closure setpoint.

ATWS:

• The crew will respond to a high power ATWS and closure of Main Bypass Valves due to low condenser vacuum.

• The crew will implement Level/Power Control due to Suppression Pool Temperature above 110°F.

• The severity of the vacuum leak will automatically reduce to maintain condenser vacuum above the MSIV isolation setpoint (Auto Event 25).

• Standby Liquid Control will not inject due to failure of the pump suction valves 1C41F001A/B to open (partially simulated by Auto Events 20 and 21).

• Wide Range Reactor Water Level indication Channel A will fail as-is during the transient (Auto Event 8).

• (Do NOT install EP Attachment 18 or 20 until the CRS has directed lowering water level in accordance with EP-2A step L8.

Install other EP Attachments as directed).

Termination:

• Once the crew has begun control rod insertion and is maintaining the reactor within established level and pressure bands, and as directed by the lead evaluator,

• Take the simulator to Freeze and turn horns off.

• Stop and save the SBT report and any other recording devices.

• Instruct the crew to not erase any markings or talk about the scenario until after follow-up questions are asked.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 9 of 22 Critical Tasks:

Entry into EP2A step L8. Crew terminates and prevents all injection except boron, CRD, and RCIC per 02-S-01-27 Operations Philosophy. Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criterion is to give the highest priority to terminate and prevent all injection except boron, CRD, and RCIC until reaching criteria specified in EP2A step L8.

Criteria specified in EP2A step L-9 are satisfied. Crew restores injection using Condensate/Feedwater as evidenced by feedwater flow to RPV or RPV level trend.

Criterion is to give the highest priority to reinitiate injection flow and establish the appropriate level band.

Hydraulic block ATWS occurs. Crew directs installation of EP Attachments 18, 19, and 20 and control rods are inserted by manual scram and/or normal rod insertion.

Criteria is to give the highest priority, along with level and pressure control, to insert control rods by manual scram and/or normal rod insertion following installation of EP Attachments 18 and 19 (20 for normal rod insertion).

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 10 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 1 Event

Description:

Shut Down Heater Drain Pump A TIME Position Applicants Actions or Behavior Directs the ATC to secure Heater Drain Pump A using 04-1-01-N23-1, Heater CRS Vents and System section 4.6 (Heater Drain Pump Shutdown)

Note: Brief was performed prior to the crew assuming the watch.

Shut down Heater Drain Pump A as follows:

• JOG CLOSED N23-F051A, HTR DR PMP A DISCH VLV on 1H13-P680.

o Responds to 1H13-P680-1A-D8, HTR DRN TK LVL HI in ATC accordance with the ARI (normal alarm when closing 1N23F051A(B))

• STOP HTR DR PMP A on 1H13-P680 Note: 5 seconds after Heater Drain Pump A is s stopped, Heater Drain Pump B will trip.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 11 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 2 Event

Description:

Heater Drain Pump B trip TIME Position Applicants Actions or Behavior ATC Recognize and report annunciator P680-1A-A8, HTR DR PMP B TRIP.

Enters 05-1-02-V-5, Loss of Feedwater Heating and:

CRS

• Directs ATC to lower core flow to 70mlbm/hr using Recirc FCVs in fast detent.

Lowers power by closing the Recirc FCVs A & B using loop flow controllers B33K603A & B in fast detent to 70 mlbm/hr total core flow on P680-3B.

ATC

• Reports OPRM Trip Enabled Region of the Power/Flow Map has been entered (<~72 mlbm/hr core flow)

Enters 05-1-02-III-3, Loss of Feedwater Heating and:

CRS

• Directs ATC to monitor for Thermal hydraulic Instability.

Monitors neutron instrumentation and alarms on 1H13P680 and OPRMs on ATC PDS for Thermal hydraulic Instability with no concurrent duties until reactor conditions have stabilized.

Perform Alarm Response Instruction 04-1-02-1H13-P680-1A-A8 and:

• Monitors Feed Pump suction pressure on PI-R611A(B).

• Verifies power has been reduced to 79%.

• Check that feed pump suction pressure stabilizes greater than 300 psig.

• Check that the Condensate System is not in run-out condition.

BOP

• Check on N23 process computer diagram (N23-N079) that heater drain tank level is being maintained at approximately 29" by the dump valves.

• Refers to ONEP 05-1-02-V-5, Loss of Feedwater Heating and:

o Checks feedwater temperature is in Region I of the Feedwater Temperature vs. Power curve (no further action necessary).

• CLOSES N23-F051B, HTR DR PMP B DISCH VLV on 1H13-P680.

Dispatches operator and Electrical Maintenance to investigate cause of HDP B CRS trip.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 12 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 3 Event

Description:

RPS Reactor Pressure master trip unit 1B21N678C failure high:

TIME Position Applicants Actions or Behavior Recognizes and reports a Division 1 Reactor Pressure High trip signal to RPS has produced a Division 1 half scram, as indicated by:

• Annunciator P680-5A-B2, RX PRESS HI

• Annunciator P680-7A-A2, RX SCRAM TRIP ATC

• Observing Division 1 scram solenoid valve white lights off.

• Annunciator P680-4A2-D4, HCU TROUBLE Checks RPS Reactor Pressure trip unit status on upper control room panels 1H13P691 and 1H13P693.

BOP

• (Following information provided by booth operator) Reports to CRS that 1B21N678C indicates 1100psig and in trip status.

Performs ARI 04-1-02-1H13-P680-4A2-D4:

• Depresses HCU FAULT push button to identify affected HCUs (04-21,04-45, 28-05, 28-61will be indicated due to Div 1 half scram)

ATC

• Depresses ACKN HCU FAULT push button on 1H13P680

• Sends operator to verify fault indication is due to power loss from Div 1 half scram and not due to low pressure or water in instrument block by observing local red power available LEDs for CRD HCUs 04-21,04-45, 28-05, 28-61 are not illuminated.

Directs I&C to investigate trip unit 1B21N678C status.

Reviews P&ID and/or other reference material to determine channel C of RPS and NSSSS(SDC) Reactor Pressure High trip functions are inoperable.

Enters TS 3.3.1.1 Condition A and TS 3.3.6.1 Condition A for RPS and NSSSS(SDC) Reactor Pressure High trip functions (require placing channel or CRS trip system in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

Briefs crew on failure status, inability to reset half scram, compensatory action to monitor HCUs 04-21,04-45, 28-05, 28-61 for faults. May enter TR 3.1.5 Conditions A and B for CRD HCUs 04-21,04-45, 28-05, 28-61 accumulator alarm instrumentation (depending on scenario timing and progression to next event).

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 13 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 4 Event

Description:

Reactor Recirc Pump B Trip Recognizes and reports Reactor Recirc Pump B has tripped off.

ATC

• As indicated by annunciator P680-3A-B10, RECIRC PMP B OVERLD/TRIP CRS Enters 05-1-02-III-3, Reduction in Recirculation System Flow Rate.

Reports Entry into the Controlled Entry Region of the power to flow map.

ATC Establishes THI watch without concurrent duties.

CRS Directs the BOP to Close the B33-F067B (Recirc Pump B discharge valve).

BOP Shuts B33-F067B (P680-3C).

Checks OPRMs are operable by operate status with no faults indicated (OPRM BOP 2 is modeled on back panels; status of other OPRMs will be obtained from the booth operator).

Consults Reactor Engineering for recommended method of exiting the Controlled Entry Region of the Power/Flow Map CRS Initiate actions to exit the Controlled Entry Region by opening Recirc FCV A (recommended by Reactor Engineering) or by inserting control rods.

Conducts reactivity brief for unplanned power change.

Exits the Controlled Entry Region by opening Recirc FCV A as directed by the BOP CRS.

Once the Controlled Entry Region is exited, direct the following actions (per the Reduction in Recirc ONEP subsequent actions):

• Ensure the operating Recirc Loop flow is <44,600gpm.

• Re-open B33-F067B after it is closed for 5 minutes.

• Open the Recirc B FCV to the maximum position.

CRS

• Per TS 3.4.1, TR 3.4.1 and Reduction in Recirc ONEP, determine and inform the Work Management / I&C / Reactor Engineering that Single Loop setpoints must to be established within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from the time single loop operation was entered and surveillance 06-RE-1J11-V-0001 must be performed.

The CRS may not have time to address each of these actions since the scenario will move forward once the Restricted Region is exited and need for single loop setpoints is identified per the requirements of TS 3.4.1, TR 3.4.1.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 14 of 22 Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 15 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 5 Event

Description:

Main Condenser Boot Seal Leak TIME Position Applicants Actions or Behavior Recognizes and reports lowering vacuum to the CRS.

• As indicated by annunciator P680-4A2-E3, OG PNL P845 TROUBLE ATC and lowering condenser vacuum indications on P680 and PDS.

• The BOP operator will also note increased offgas flow.

Enters 05-1-02-V-8, Loss of Condenser Vacuum ONEP.

Carryout steps of the ONEP to determine the cause of Loss of Condenser Vacuum.

• Assigns BOP to monitor LP Condenser Vacuum (critical parameter)

• Verify SJAE has not malfunctioned

• Check that offgas flow is not obstructed (this is determined not to be the cause by the increased offgas flow rate)

• Check that Seal Steam is operating properly CRS

• Send a local operator to check for condenser inleakage

• Check Circ Water system for proper operation

• Check Condenser Vacuum Breaker valves are closed

• Send a local operator to ensure Condenser Vacuum Breaker valves have adequate seal water When it is apparent that the Condenser Low Vacuum trip set point will be reached, direct the ATC to insert a Manual Scram before the Main Turbine trip at 21Hg condenser vacuum.

When directed:

• Verify SJAE has not malfunctioned by checking the SJAE lineup on the P680-10C (the A SJAE valves should all be open).

ATC

• Check that Seal Steam is operating properly by checking for normal indications on the P680-10B for normal SS indications.

• Check Circ Water system for proper operation by checking that both Circ Water pumps are running on the P680-10C.

When directed, check Condenser Vacuum Breaker valves are closed on the BOP P870-6C.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 16 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 6 Event

Description:

Main Condenser Boot Seal Failure / Loss of Vacuum / ATWS TIME Position Applicants Actions or Behavior When apparent condenser vacuum cannot be maintained above 21Hg as ATC directed by the CRS, places the Mode Switch in SHUTDOWN.

Provides a scram report:

• Reactor Mode SW in SHUTDOWN.

• All Rods are NOT Inserted (Hydraulic Block ATWS).

• Reactor power is above 5% (Value depends when data taken).

ATC

• Reactor water level and trend.

• Reactor pressure and trend.

• Feedwater is available but RFPTs may trip on low vacuum.

• Bypass valves and MSIVs are available but may close on low vacuum.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 17 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 6 (cont.) / 7 Event

Description:

Main Condenser Boot Seal Failure / Loss of Vacuum / ATWS Failure of Standby Liquid Control suction valves 1C41F001A/B to open TIME Position Applicants Actions or Behavior Enter SCRAM ONEP and EP-2A, ATWS RPV CONTROL Direct actions of EP-2A, ATWS RPV CONTROL steps 1 - 4:

Directs ATC to Verify Recirc Pump A transferred to LFMG.

CRS Directs ATC to Verify ARI/RPT initiation.

Directs BOP to inhibit ADS.

Directs BOP to Override HPCS injection.

Verify Recirc Pump A transferred to LFMG.

ATC Verify/Initiate ARI/RPT.

Inhibits ADS.

• Place ADS A and ADS B keylock switches to INHIBIT Override HPCS injection.

BOP

• Place the HPCS pump handswitch to the STOP position.

• Place the E22-F004, HPCS injection valve, handswitch to the CLOSE position.

Enter EP-2A step L-7 and direct the ATC to establish level band -70 to -130 on Startup Level Control and direct BOP to initiate and override low pressure ECCS.

CRS Enter EP-2A step Q-4. (SLC will not inject, Attachment 28 is required)

Enter EP-2A step P-4 and direct the BOP to establish a pressure band 800 -

1060 psig using IPC and BCV Manual Jack.

Call for EP Attachments 8, 12, 18, 19, 20, and 28.

Event 7 After placing SLC A/B key switches to start, reports failure of SLC suction BOP valves to open (Auto Event 7).

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 18 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 6 (cont.) / 8 Event

Description:

Main Condenser Boot Seal Failure / Loss of Vacuum / ATWS Wide Range Reactor Water Level Indication Channel A Fail As-Is TIME Position Applicants Actions or Behavior When reactor water level falls to -75 inches, wide range water level indication Event 8 on PDS will fail as-is, remaining at the current value (Auto Event 8). The ATC will then disregard this channel when controlling level and will report the failure ATC to the CRS.

Line up Feed and Condensate systems for Startup Level Control using 04 01-N21-1, Feedwater System attachment VII, Transferring to Startup Level Control hard card.

• If two Feed pumps are running, trip one.

• Close N21-F009A and N21-F009B.

• Open N21-F001, N21-F010A, and N21-F010B.

• Verify Closed N21-F513, N21-F510, N21-F040.

• If no Feed pumps are in operation, start one.

o Ensure RFPT A(B) controls Manual pushbutton is backlit.

ATC o Verify AC lube oil pump is running o Open N21-F014A(B) o Depress the TRIP RESET pushbutton o Depress the RAISE pushbutton to establish Feed pump discharge pressure above reactor pressure by approx. 250 psig.

• Open/Verify Open N21-F014A or N21-F014B

• Maintain reactor level in Auto or Manual using the Startup level controller or Manually using N21-F040 or N21-F009A(B).

Feed the reactor using the Startup Level Controller to maintain reactor level within the set level band (-70 to -130).

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 19 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 6 (cont.)

Event

Description:

Main Condenser Boot Seal Failure / Loss of Vacuum / ATWS TIME Position Applicants Actions or Behavior Initiates Div 1 and 2 ECCS and overrides LPCS and LPCI A/B/C on 1H13P601:

• Arms and depresses LPCS/RHR A MAN INIT and RHR B/RHR C MAN INIT pushbuttons.

• Places handswitches for LPCS, RHR A, RHR B, and RHR C pumps to BOP stop.

• Places handswitches for injection MOVs 1E21F005, 1E12F042A, 1E12F042B, and 1E12F042C to close.

• Verifies amber override alarms for LPCS, RHR A, RHR B, and RHR C pump and injection MOV annunciate and seal in.

Recognize and report that Main Bypass Valves have closed by:

• Bypass Stop Valve position indication lights indicate green/closed on 1H13P680

• Bypass Control Valve indicate 0% on position indication meters on 1H13P680 CREW

• Annunciator P601-19A(18A)-B6, LO-LO SET PT SEALED IN

• Rising reactor pressure

• Open SRVs Direct the BOP to manually control reactor pressure in the band of 800 to 1060 psig using SRVs. May direct pressure band of 450 to 600 psig in anticipation of MSIV closure on low condenser vacuum (although vacuum is programmed CRS to remain above the MSIV trip setpoint in this scenario).

Direct the BOP to lineup RHR A and B for Suppression Pool Cooling using 04-1-01-E12-1, Residual Heat Removal System attachment VI, Maximizing Suppression Pool Cooling hard card.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 20 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 6 (cont.)

Event

Description:

Main Condenser Boot Seal Failure / Loss of Vacuum / ATWS TIME Position Applicants Actions or Behavior Open and Close SRVs as required to maintain reactor pressure within the established band. (This will be a continuing action for the remainder of the scenario)

When directed to lineup RHR A and B for Suppression Pool Cooling:

• Ensure SSW is in service by observing the following:

o SSW A(B) Pump running o P41-F001A(B), SSW PMP A(B) DISCH VLV is Open BOP o P41-F005A(B), SSW LOOP A(B) RTN TO CLG TWR is Open o P41-F014A(B), SSW INL TO RHR HX A(B) OUTL VLV is Open o P41-F006A(B), SSW PMP RECIRC VLV is closed

• Verify Open E12-F003A(B), RHR HX OUTL VLV

• Start RHR PMP A(B)

• Open E12-F024A(B), RHR TEST RTN TO SUPP POOL Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 21 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 6 (cont.)

Event

Description:

Main Condenser Boot Seal Failure / Loss of Vacuum / ATWS TIME Position Applicants Actions or Behavior When Suppression Pool Temperature reaches 110F Enter EP-2A step L-8 and direct the following:

• ATC: Terminate and prevent Feedwater by Closing the Startup Level Control valve, N21-F040, N21-F009A, and N21-F009B.

• BOP: If not already performed, terminate and prevent high pressure and low pressure ECCS injection by ensuring ECCS is initiated and overriding LPCS, RHR A/B/C, HPCS pump off and injection valve shut.

Allow level to lower until:

• Power is below 5%

OR

• Level drops to -167 (Compensated Fuel Zone)

OR CRS

• All SRVs stay closed and DW pressure stays below 1.23 psig Establish a new level band of -191 to level lowered from above Entry into EP2A step L8. Crew terminates and prevents all injection except boron, CRD, and RCIC per 02-S-01-27 Operations Philosophy.

Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criterion is to give the highest priority to terminate and prevent all injection except boron, CRD, and RCIC until reaching criteria specified in EP2A step L8.

Criteria specified in EP2A step L-9 are satisfied. Crew restores injection using Condensate/Feedwater as evidenced by feedwater flow to RPV or RPV level trend. Criterion is to give the highest priority to reinitiate injection flow and establish the appropriate level band.

ATC Reestablish Feedwater to maintain level within the new level band.

Revision 0 04/01/12

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 22 of 22 Op-Test No: 2012-1 Scenario No: 2 Event No: 6 (cont.)

Event

Description:

Main Condenser Boot Seal Failure / Loss of Vacuum / ATWS TIME Position Applicants Actions or Behavior CRS Directs BOP to maximize CRD flow.

BOP Maximizes CRD for flow: 04-1-01-C11-1 Att.

• Places CRD SYS FLO CONT C11-R600 in MANUAL.

• Using CRD SYS FLOW CONT C11-R600, fully opens C11-F002A(B),

CRD FLO CONT VLV.

• Fully opens C11-F003, CRD DRIVE WTR PRESS CONT VLV CRS When Attachments 18, 19, and 20 are reported installed, directs ATC to reset scram and BOP to maximize CRD drive water pressure.

Hydraulic block ATWS occurs. Crew directs installation of EP Attachments 18, 19, and 20 and control rods are inserted by manual scram and/or normal rod insertion. Criteria is to give the highest priority, along with level and pressure control, to insert control rods by manual scram and/or normal rod insertion following installation of EP Attachments 18 and 19 (20 for normal rod insertion).

ATC Resets RPS A by placing RPS Div 1 & 3 or 2 & 4 Reset switches to RESET on P680.

BOP Maximizes CRD drive water pressure by fully closing C11-F003, CRD DRIVE WTR PRESS CONT VLV on P601 BOP/ Inserts Control Rods by scramming rods using RPS scram arm/depress ATC pushbuttons and/or by selecting control rods on RC&IS and depressing IN TIMER SKIP or INSERT pushbutton on P680.

Revision 0 04/01/12

Give this page to the CRS Turnover the following conditions:

Power 83.5%

BOC EOOS GREEN Work Week Division 1 Power has been reduced to 83.5% per 03-1-01-2 Att. VIII, Temporary Downpower, to remove Heater Drain Pump A from service for emergent maintenance on the pump seal, which is scheduled for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned Evolutions this shift:

• Remove Heater Drain Pump A from operation per SOI 04-1-01-N23-1 section 4.6.

• Maintain power level approximately 84% until Heater Drain Pump B has been returned to operation.

• Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

Revision 0 4/01/12 Page 22 of 22