ML101940034
| ML101940034 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/25/2010 |
| From: | NRC Region 4 |
| To: | |
| References | |
| 50-416/10-301 | |
| Download: ML101940034 (98) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 06/28/2010 Examination Level: RO X SRO Operating Test Number: 6/10 Administrative Topic Type Describe activity to be performed (see Note) Code*
Perform 06-OP-1R20-W-0001-02, Attachment II of weekly AC/DC Lineup for ESF 21 Transformer Retest GJPM-OPS-ADMR91.00 Conduct of Operations S; N K/A 2.1.20: 4.6 Review Cooldown Record GJPM-OPS-ADMR92.00 Conduct of Operations R; N K/A2.1.25: 3.9 Determine Tagging Requirements & Prepare Tagout Tags Sheet for SRV B21-F047L Equipment Control R; M GJPM-OPS-ADMR93.00 K/A 2.2.13: 4.1 N/A Radiation Control Primary Containment Water Level Determination EOP Attachment 29 Emergency Procedures/Plan R; M GJPM-OPS-ADMR94.00 K/A 2.4.21: 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
Revision 1 4/14/2010
ES-301 Administrative Topics Outline Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 06/28/2010 Examination Level: RO SRO X Operating Test Number: 6/10 Administrative Topic Type Describe activity to be performed (see Note) Code*
Determine Fire Watch Requirements GJPM-OPS-ADMS95.00 Conduct of Operations R; N K/A 2.1.2: 4.4 Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available GJPM-OPS-ADMS96.00 Conduct of Operations R; M K/A2.1.25: 4.2 Determine LCO Actions and Initiate a Manual LCO Tracking Report Equipment Control R; M GJPM-OPS-ADMS97.00 K/A 2.2.22: 4.7 Determine Protective Action Recommendations GJPM-OPS-ADMS88.00 Radiation Control R; M K/A 2.3.13: 3.8 Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable GJPM-OPS-EAL27.00 Emergency Procedures/Plan R; M K/A 2.4.41: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
Revision 1 4/14/2010
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 6/28/2010 Exam Level: RO X SRO-I SRO-U Operating Test No.: 6/10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function
- a. 201005/201001/295022 Operate CRD System/RCIS to Achieve S; L; M; A 1 Criticality and Commence Reactor Heatup
- b. 295030/223001 Raise Suppression Pool Level using HPCS S; M; A 5
- c. 217000 Restore RCIC to Standby following Steam Supply S; M 2 Isolation
- d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal S; L; M 4 Stratification
- e. 262001 Align Buses 16AB and 17AC to ESF Transformer S; M; A 6
- g. 400000 Align CCW to FPCCU Heat Exchanger A S; N; A 8
- h. 21272000 Perform Area Radiation Monitor Functional Test S; N 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. 295016 Perform Remote Shutdown Panel Area Actions for Security E; N 7 Code Orange
- j. 295015 EP Attachment 22 - Locally Scram Control Rods R; E; D 1
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator 5/6/2010
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 6/28/2010 Exam Level: RO SRO-I X SRO-U Operating Test No.: 6/10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function
- a. 201005/201001/295022 Operate CRD System/RCIS to Achieve S; L; M; A 1 Criticality and Commence Reactor Heatup
- b. 295030/223001 Raise Suppression Pool Level using HPCS S; M; A 5
- c. 217000 Restore RCIC to Standby following Steam Supply S; M 2 Isolation
- d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal S; L; M 4 Stratification
- e. 262001 Align Buses 16AB and 17AC to ESF Transformer 21 S; M; A 6
- g. 400000 Align CCW to FPCCU Heat Exchanger A S; N; A 8
- h. N/A In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. 295016 Perform Remote Shutdown Panel Area Actions for Security E; N 7 Code Orange
- j. 295015 EP Attachment 22 - Locally Scram Control Rods R; E; D 1
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator 5/6/2010
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 06/28/2010 Exam Level: RO SRO-I SRO-U Operating Test No.: BACKUP JPMS Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function
- a. 201005 Control Rod Operability Surveillance S; M; A 1/7
- b. 223002 Isolate Division 2 Valves following Failure to Auto Isolate S; N 5 c.
d.
e.
f.
g.
h.
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. 263000 Battery Charger Startup D 6 j.
k.
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator 5/6/2010
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR91 Revision: 00 Page: 1 of 1 JOB PERFORMANCE Rtype:
MEASURE QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE:
Perform 06-OP-1R20-W-0001-02, Attachment II of weekly AC/DC Lineup for ESF 21 Transformer Retest New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: NA REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 11/17/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/17/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR91 Revision: 00 Page: 2 of 2 JOB PERFORMANCE MEASURE Task: Perform 06-OP-1R20-W-0001-02 Setting: Classroom Type: RO Task: CRO-R20/27-008 K&A: Generic 2.1.20- 4.6/4.6; 2.1.31: 4.6/4.3 Safety Function: NA; 10CFR55.45a (12)]
Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 06-OP-1R20-W-0001 Plant AC and DC Electrical Power Distribution Weekly Lineup Tech Spec 3.8.1 Handout(s): 06-OP-1R20-W-0001 Plant AC and DC Electrical Power Distribution Weekly Lineup, Attachment II
- Manipulations: N/A
- Critical Steps: 1 Group : N/A Simulator Setup/Required Plant Conditions:
- Reset to any IC with the normal electrical distribution alignment
- Insert override ao_1r25r603 at severity 5
- Place a Condition Identification (CI) Tag on 1H13P807 beside bus 11R voltmeter R25R603 stating Bus 11R potential xfmr 1XRPT1 is damaged, R25R603 reading is inaccurate Safety Concerns:
- None THIS IS AN ADMINISTRATIVE JPM.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR91 Revision: 00 Page: 3 of 3 JOB PERFORMANCE MEASURE Initial Condition(s):
- The Plant is at rated power.
- ESF Transformer 21 has just been re-energized and placed into its normal alignment following maintenance.
Initiating Cue(s):
- You have been directed to perform 06-OP-1R20-W-0001 Attachment II as a retest for ESF Transformer 21. Use the marked-up partial surveillance data package provided.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR91 Revision: 00 Page: 4 of 4 JOB PERFORMANCE MEASURE Task: Perform 06-OP-1R20-W-0001-02 Notes:
- 1. None Task Overview:
This task is to perform the data collection for the surveillance used to verify the Offsite and On-Site Power sources required to satisfy Surveillance Requirement SR3.8.1.1 in order to restore ESF Transformer 21 operable following maintenance.
Note : Critical steps are underlined, italicized, and denoted by an (*).
Sequence is not critical.
- Record data using 06-OP-1R20-W-0001 Attachment II.
Standard: Candidate records data using 06-OP-1R20-W-0001 Attachment II.
The candidate will conduct a breaker lineup verification and use the Voltmeter Selector switches to determine and record phase voltages on buses 11R and 21R and INC VOLTAGE (4160 volts) for the individual bus feeder voltages on pages 2 and 3.
The candidate should note the CI tag for bus 11R voltmeter, determine those readings cannot be obtained, and make a notation to this effect in the comments section on the surveillance Data Package Cover Sheet, which may be done later when completing the Data Package Cover Sheet. The candidate should determine the bus 11R voltage reading is not required for Tech Spec acceptance criteria in accordance with Note (1) on page 3 of the surveillance data package.
For the 4160V buses, to obtain the INC VOLTAGE they will go to each Incoming Transformer Feeder circuit breaker on H13-P864 and H13-P601 section 16C and select the listed feeder SYNC SWITCH to the ON position to read Incoming Voltage. It is critical that the candidate turns OFF each Sync Switch after taking the appropriate reading before turning the next SYNC switch ON.
Cue: None.
Notes: Refer to evaluators copy of 06-OP-1R20-W-0001 Attachment II where Critical items are highlighted.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR91 Revision: 00 Page: 5 of 5 JOB PERFORMANCE MEASURE Completes the surveillance Data Package Cover Sheet.
Standard: The operator checks Partial Procedure Completed, Tech Spec Acceptance Criteria Acceptable, All Other Steps/Data Unacceptable (due to not being able to obtain bus 11R readings), and signs and dates Performed by on the Data Package Cover Sheet. If not done earlier, the candidate should make a notation in the comments section that bus 11R voltage could not be obtained due to the equipment problem listed on the CI Tag. The critical portions of this step are the performers signature, date, time and Tech Spec Acceptance Criteria is checked as Acceptable.
Cue: End of JPM.
Notes: .
Task Standard(s):
Readings for Surveillance 06-OP-1R20-W-0001 Attachment II have been obtained and documented on the surveillance data sheets and the surveillance Data Package Cover Sheet has been completed by the test performer.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR91 Revision: 00 Page: 6 of 6 JOB PERFORMANCE MEASURE Task: Perform 06-OP-1R20-W-0001-02 Follow-Up Questions & Answers:
Comments:
Do NOT give this page to the student CONTINUOUS USE GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-OP-1R20-W-0001 Revision 106 RT = B6.61 NON-QA RECORD Attachment II Page 1 of 4 INITIALS NUMBER OF PAGES DATE Model WO# 50289936 RELATED DOCUMENT RTYPE B6.61 NUMBER = XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED
Title:
Plant AC and DC Electrical Power Distribution Weekly Lineup Technical Specifications: SR 3.8.1.1 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 2.2 Permission to begin the test /
Shift Supervisor / Date 2.3 Radiation Protection Review N/A RWP # N/A 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 Inop Electrical Equipment (include LCO #)
3.3 Comments
3.4 Test performed by Date/Time /
4.0 DEFICIENCIES CR Issued #
LCO Entered # WR Issued #
5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]
Shift Supv./Mgr. Date Comments:
CONCURRENCE Operations Management Date
Do NOT give this page to the student DATA SHEET I PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED (Step 5.2.2) Div 1, 2 & 3 Offsite Feeders OFFSITE ENERGIZED VOLTAGE RECORDED FREQUENCY RECORDED INITIALS FEEDER INDICATOR VOLTAGE INDICATOR FREQUENCY YES/NO (LOCATION) (ACCEPTANCE (LOCATION) (ACCEPTANCE CRITERIA) CRITERIA)
BAXTER 500 kV FREQ.
$ WILSON
- JACKSON kV SR27-SR-R600 Hz DISPATCHER (H13-P807)
$ FRANKLIN * (496-525kV)*** or Pine Bluff (57-61.8Hz)
Dispatcher
- x 27.64 152-1511 = kV 115kV LINE 152-1611 (120.75-
$ PORT GIBSON
- 152-1704 112.13) kV
- To determine status of offsite feeders, contact load dispatcher. Ensure that the feeders are independently energized from the grid, such that the loss of one feeder would not result in the loss of another.
Return Sync switch to OFF after taking reading.
- Allowable Value of minimum voltage is >491 kV for operability of Offsite Feeders.
This value is based on analysis of the Class 1E ESF buses and includes an allowance for instrument uncertainty associated with the voltage measurement in the switchyard.
Extended operation beyond the normal continuous operating limits should be evaluated and caution should be taken when starting large loads under these conditions.
Do NOT give this page to the student CONTINUOUS USE GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 106 Attachment II Page 3 of 4 Page RTYPE B6.61 XRef DATA SHEET I (Continued)
PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED RECORDED VOLTAGE REQUIRED ACTUAL INSTRUMENT ACCEPTANCE BREAKER POSITION POSITION INITIALS COMMENTS (LOCATION) CRITERIA Service Transformer 11 - Bus 11R to ESF 15AA, 16AB & 17AC 34.5kV Bus A-B = (1)
$ 552-1105 Closed 11R Volts B-C = (1) 1R25-EI-R603 C-A = (1)
$ 552-1104 Closed (H13-P807-1B) (31.05-37.95kV)
Bkr 152-1514
- Inc Voltage (3952-4576)
Bkr 152-1601 *
$ 152-1901 Closed Inc Voltage (3952-4576)
Bkr 152-1706 *
$ 152-1902 Closed Inc Voltage (3952-4576)
- Note: For these breakers verify voltage is available to the ESF Bus by placing the Sync switch on 1H13-P864 or 1H13-P601 for the designated breaker to ON and recording incoming voltage. Return Sync switch to OFF after taking reading.
(1) Voltage indication from 1R25-EI-R603 is not required to meet Tech Spec acceptance criteria. Voltage indication is met by acceptable incoming voltage for breakers 152-1514, 152-1601, and 152-1706.
J:\ADM_SRVS\TECH_PUB\REVISION\O\OR20W01.A2
Do NOT give this page to the student CONTINUOUS USE GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 106 Attachment II Page 4 of 4 Page RTYPE B6.61 XRef DATA SHEET I (Continued)
PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED (Step 5.2.2)
RECORDED VOLTAGE REQUIRED ACTUAL INSTRUMENT ACCEPTANCE BREAKER POSITION POSITION INITIALS COMMENTS (LOCATION) CRITERIA Service Transformer 21 - Bus 21R to ESF 15AA, 16AB & 17AC 34.5kV Bus A-B =
(1)
$ 552-2105 Closed 21R Volt B-C =
(1) 2R25-EI-R603 C-A =
(1)
$ 552-2104 Closed (H13-P807-4B) (31.05-37.95kV)
Bkr 152-1501
- Inc Voltage (3952-4576)
Bkr 152-1614 *
$ 152-2901 Closed Inc Voltage (3952-4576)
Bkr 152-1705 *
$ 152-2902 Closed Inc Voltage (3952-4576) 115 kV Line to ESF 15AA, 16AB & 17AC
$ J3885 Closed N/A N/A Bkr 152-1511
- Inc Voltage (3952-4576)
Bkr 152-1611 *
$ 152-1903 Closed Inc Voltage (3952-4576)
Bkr 152-1704 *
$ 152-1904 Closed Inc Voltage (3952-4576)
- Note: For these breakers verify voltage is available to the ESF Bus by placing the Sync switch on 1H13-P864 or 1H13-P601 for the designated breaker to ON and recording incoming voltage. Return Sync switch to OFF after taking reading.
(1) Voltage indication from 2R25-EI-R603 for Bus 21R is not required to meet Tech Spec acceptance criteria. Voltage indication is met by acceptable incoming voltage for breakers 152-1501, 152-1614, and 152-1705.
REFERENCE TECHNICAL SPECIFICATION REQUIRED ACCEPTANCE CRITERIA ACTION(S) IF ACCEPTANCE CRITERIA NOT MET FOR:
SR 3.8.1.1 - Mode 1, 2, 3 - LCO 3.8.1 - Condition A, C, D two of the above circuits between the offsite transmission network and the onsite Class 1E distribution system are Operable; correct breaker lineup and power available.
J:\ADM_SRVS\TECH_PUB\REVISION\O\OR20W01.A2
Give this page to the student Perform 06-OP-1R20-W-0001-02 Initial Condition(s):
- The Plant is at rated power.
- ESF Transformer 21 has just been re-energized and placed into its normal alignment following maintenance.
Initiating Cue(s):
- You have been directed to perform 06-OP-1R20-W-0001 Attachment II as a retest for ESF Transformer 21. Use the marked-up partial surveillance data package provided.
Give this page to the student Give this page to the student Give this page to the student Give this page to the student ENTERGY NUCLEAR Number: GJPM-OPS-ADMR92 Revision: 00 Page: 1 of 1 JOB PERFORMANCE Rtype:
MEASURE QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE:
Review Cooldown Record New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: NA REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 11/17/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/15/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR92 Revision: 00 Page: 2 of 2 JOB PERFORMANCE MEASURE Task: Review Cooldown Record Setting: Classroom Type: RO Task: CRO-ADMIN-007 K&A: Generic 2.1.25: 3.9/4.2; 2.1.23: 4.3/4.4 Safety Function: NA; 10CFR55.45a (12)]
Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 03-1-01-3 Plant Shutdown Tech Spec 3.4.11 RCS P/T Limits w/ Figure 3.4.11-1 RCS P/T Limit Curve for the current point in service life Handout(s): 03-1-01-3 Attachment III with temperature data (ATTACHED)
Technical Specifications
- Manipulations: N/A
- Critical Steps: 1 Group : N/A Simulator Setup/Required Plant Conditions:
- None Safety Concerns:
- None THIS IS AN ADMINISTRATIVE JPM.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR92 Revision: 00 Page: 3 of 3 JOB PERFORMANCE MEASURE Initial Condition(s):
- The Plant is in Mode 3.
- Plant cooldown is in progress for a planned shutdown.
- A non-licensed operator has collected cooldown data using 03-1-01-3 Attachment III, but no reviews have been performed yet.
Initiating Cue(s):
- You have been directed to review the cooldown data recorded by the non-licensed operator as the Reactor Operator in accordance with 03-1-01-3 to determine whether any limits have been exceeded.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR92 Revision: 00 Page: 4 of 4 JOB PERFORMANCE MEASURE Task: Review Cooldown Record Notes:
- 1. None Task Overview:
The candidate will review cooldown data recorded on 03-1-01-3 Attachment III and identify the administrative limit of 90°F has been exceeded.
Note : Critical steps are underlined, italicized, and denoted by an (*).
- Reviews temperature data on 03-1-01-3 Attachment III and determines the Administrative Limit of 90°F has been exceeded.
Standard: The operator determines the hourly temperature change for the data provided on 03-1-01-3 Attachment III page 1 for each parameter. The operator identifies the Administrative Limit of 90°F/hr has been exceeded for R643 Pt. 4, Bottom Drain between time 0800 (385°F) and 0900 (288°F), but the Tech Spec limit of 100°F/hr has not been exceeded. The operator compares the readings for Head Flange Temperature, Shell Flange Temperature and Reactor Pressure against the Minimum Reactor Vessel Metal Temperature vs. Reactor Vessel Pressure curve, TS Figure 3.4.11-1, and determines all temperatures are to the right of curve B and are, thus, within limits.
Cue: none.
Notes: 385°F minus 288°F = 97°F in one hour .
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR92 Revision: 00 Page: 5 of 5 JOB PERFORMANCE MEASURE Completes the Reactor Operator review signoff on the cooldown record data sheet, 03-1-01-3 Attachment III page 1.
Standard: The operator checks Tech Spec Acceptance Criteria Acceptable, Admin Limit Criteria Unacceptable, and signs and dates Review performed by on 03-1-01-3 Attachment III page 1.
Cue: End of JPM.
Notes: .
Task Standard(s):
Review the cooldown record data sheet for plant shut down in accordance with 03-1-01-3 and Tech Spec 3.4.11 and identify the Administrative cooldown rate limit has been exceeded.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR92 Revision: 00 Page: 6 of 6 JOB PERFORMANCE MEASURE Task: Review Cooldown Record Follow-Up Questions & Answers:
Comments:
Give this page to the student Review Cooldown Record Initial Condition(s):
- The Plant is in Mode 3.
- Plant cooldown is in progress for a planned shutdown.
- A non-licensed operator has collected cooldown data using 03-1-01-3 Attachment III, but no reviews have been performed yet.
Initiating Cue(s):
- You have been directed to review the cooldown data recorded by the non-licensed operator as the Reactor Operator in accordance with 03-1-01-3 to determine whether any limits have been exceeded.
Give this page to the student GRAND GULF NUCLEAR STATION INTEGRATED OPERATING INSTRUCTION 03-1-01-3 Revision: XX Attachment III Page 1 of 3 DATA SHEET I PLANT SHUTDOWN HEATUP/COOLDOWN DATA SHEETS SAFETY RELATED SHEET 1 of 1 Record Every 30 Minutes; Recorder 1B21-R643 suggested for temps, if not available, PDS may be used.
Date REACTOR VESSEL TEMPERATURES PRESSURE 6 / XX / XX R643 R643 Pt.2 R643 Pt.3 R643 Pt.4 R643 R643 TEMPS MEET TS Pt.1 BOTTOM SHELL BOTTOM Pt.5 Pt.6 CURVE per INITIALS HEAD HEAD FLANGE DRAIN RECIRC RECIRC REACTOR SR3.4.11.1**
TIME FLANGE A SUCT B SUCT PRESSURE Y/N PERF VERIF*
07 30** 429 296 413 412 371 369 180 08 00** 407 258 390 385 342 341 110 08 30** 377 240 359 337 313 313 81 09 00** 348 223 331 288 283 286 49 09 30** 329 201 313 263 269 271 34 10 00** 308 175 295 246 250 252 21 10 30** 290 161 279 230 234 235 12
- Tech Spec Acceptance Criteria: *Verifier to evaluate every 60-minute segment to ensure H/U, C/D limits (< 100°F/Hr) are not exceeded.
- Every 30 minutes compare head flange temperature, shell flange temperature and reactor pressure to ensure reactor metal temperature vs. reactor pressure is to the right of the curve as required in Tech Spec SR 3.4.11.1.
Tech Spec Acceptance Criteria: Acceptable [ ] Unacceptable [ ] Admin Limit Criteria ( 90°F/HR): Acceptable [ ] Unacceptable [ ]
Review performed by / /
(Reactor Operator) Date Time DEFICIENCIES: CR Issued # LCO Entered #
APPROVAL: Shift Supv/Mgr Date
Give this page to the student GRAND GULF NUCLEAR STATION INTEGRATED OPERATING INSTRUCTION 03-1-01-3 Revision: 117 Attachment III Page 3 of 3 DATA SHEET II PLANT SHUTDOWN HEATUP/COOLDOWN DATA SHEETS SAFETY RELATED CAUTION Exceeding 100°F/hr is a violation of Tech Specs Check Recorder Point Used:
Recirc A Recirc B Bottom Head Drain Maintain the Heatup or Cooldown Rate less than the slope of the curve.
(Administrative limit of 90 degree F/hr.)
600 TEMPERATURE (20 °F increments) 500 400 300 200 100 0
0 1 2 3 4 5 6 7 8 ELASPED TIME (HOURS)
ENTER TIME (tic marks are 15 minute increments)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR93 Revision: 00 Page: 1 of 14 JOB PERFORMANCE Rtype:
MEASURE QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE:
ADMINISTRATIVE JPM Determine Tagging Requirements and Prepare a Tagout Tags Sheet for SRV B21-F047L New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 10/29/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/15/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR93 Revision: 00 Page: 2 of 14 JOB PERFORMANCE MEASURE Task: Determine Tagging Requirements and Prepare a Tagout Tags Sheet for SRV B21-F047L Setting: Classroom Type: RO Task: CRO-ADMIN-005 K&A: Generic 2.2.13: 4.1/4.3 Safety Function: NA Time Required: 45 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): EN-OP-102, EN-OP-102-1, Drawings M1077E; E1161-04,11,12,14,17; E0300 fuse sort page 1, panel sort pages 20; 23 Technical Specifications 3.3.5.1, 3.3.6.5, 3.4.4 Handout(s): Completed Work Impact Statement, partially completed Tagout Request Form, completed Tagout Cover Sheet, completed Tagout Tags Sheet, Dwgs M1077E; E1161-01, 04 , 11, 12, 14, 17; E0300 Technical Specifications
- Manipulations: N/A
- Critical Steps: 1 Group : N/A Simulator Setup/Required Plant Conditions:
- None Safety Concerns:
- None THIS IS AN ADMINISTRATIVE JPM.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR93 Revision: 00 Page: 3 of 14 JOB PERFORMANCE MEASURE Initial Condition(s):
- The Plant is in Mode 4.
- Electrical Maintenance is to rework the wiring connections for 1B21F505P and 1B21F506P, Pilot Solenoid Valves for SRV 1B21F047L locally, at the SRV.
- The work will require electrical isolation only. The air supply portion of the system will not be breached.
- The next sequential tag serial number is 01.
Initiating Cue(s):
- You have been directed to prepare a Tagout Tags Sheet using Attachment 9.3 of procedure EN-OP-102 for electrical isolation of 1B21F505P and 1B21F506P.
Use the drawings and forms provided.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR93 Revision: 00 Page: 4 of 14 JOB PERFORMANCE MEASURE Task: Determine Tagging Requirements and Prepare a Tagout Tags Sheet for SRV B21-F047L Notes:
- 1. None Task Overview:
Prepare a tag out in preparation for locally reworking the wiring connections for 1B21F505P and 1B21F506P, Pilot Solenoid Valves for SRV 1B21F047L.
Note : Critical steps are underlined, italicized, and denoted by an (*)
- COMPLETE Attachment 9.3 of procedure EN-OP-102-01, documenting the required components and their required positions for the tagout. (Tagging sequence and tag type are not critical.)
Standard: The operator prepares the Attachment as indicated on the attached key by an asterisk (*) in the tag serial number field. Order listed on the sheet is NOT critical. Critical Item is must have the four fuses removed.
Cue:
Notes: See attached Evaluator Key Task Standard(s):
Correctly prepare a Tagout Tags Sheet (EN-OP-102 Attachment 9.3) in preparation for locally reworking the wiring connections for 1B21F505P and 1B21F506P, Pilot Solenoid Valves for SRV 1B21F047L in accordance with EN-OP-102.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR93 Revision: 00 Page: 5 of 14 JOB PERFORMANCE MEASURE Task: Determine Tagging Requirements and Prepare a Tagout Tags Sheet for SRV B21-F047L Follow-Up Questions & Answers:
Comments:
DO NOT GIVE THIS PAGE TO THE STUDENT NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENT MANUAL INFORMATIONAL USE PAGE 7 OF 25 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________ TAGOUT: ________________
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/R Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif emoval No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes XXX1 Danger 1B21M605P 1 OFF ADS VALVE 1B21-F047L COA-166-0C504
-1H13P601 XXX2 Danger 1B21M606P 1 OFF ADS VALVE 1B21-F047L COA-166-0C504
-1H13P631 XXX3 Danger 1-B21 FUSE -1B21F11A 2 REMOVED
- 1H13-P628 BAY A FUSE
- 21 ON TERMINAL BOARD D FOR 1B21F047L (B21CF11A)
COA-189 XXX4 Danger 1-B21 FUSE -1B21F12A 2 REMOVED
- 1H13-P628 BAY A FUSE
- 22 ON TERMINAL BOARD D FOR 1B21F047L (B21CF12A)
COA-189 Page 6 of 14
DO NOT GIVE THIS PAGE TO THE STUDENT NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENT MANUAL INFORMATIONAL USE PAGE 7 OF 25 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________ TAGOUT: ________________
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/R Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif emoval No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes XXX5 Danger 1-B21 FUSE -1B21F11B 2 REMOVED
- 1H13-P631BAY A FUSE
- 21 ON TERMINAL BOARD D FOR 1B21F047L (B21CF11B)
COA-166 XXX6 Danger 1-B21 FUSE -1B21F12B 2 REMOVED
- 1H13-P631 BAY A FUSE
- 22 ON TERMINAL BOARD D FOR 1B21F047L (B21CF12B)
COA-166 Page 7 of 14
Determine Tagging Requirements and Prepare a Tagout Tags Sheet for SRV B21-F047L Give this page to the student Initial Condition(s):
- The Plant is in Mode 4.
- Electrical Maintenance is to rework the wiring connections for 1B21F505P and 1B21F506P, Pilot Solenoid Valves for SRV 1B21F047L locally, at the SRV.
- The work will require electrical isolation only. The air supply portion of the system will not be breached.
- The next sequential tag serial number is 01.
Initiating Cue(s):
- You have been directed to prepare a Tagout Tags Sheet using Attachment 9.3 of procedure EN-OP-102 for electrical isolation of 1B21F505P and 1B21F506P.
Use the drawings and forms provided.
Page 8 of 14
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT INFORMATIONAL USE PAGE 6 OF 25 MANUAL Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 TAGOUT COVER SHEET Clearance: __MANUAL____________ Tagout: _____________________
Component to be worked: B21-F505P, B21-F506P B21-F047L Solenoid Valves DRYWELL 166
==
Description:==
ELECTRICALLY ISOLATE 1B21F047L IN ORDER TO REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P AND 1B21F506P Placement Inst:
This tagout de-energize solenoid valves for SRV 1B21F047L.
References:
M1077E; E1161-01, 04, 11, 12, 14, 17; E0300 fuse sort page 1, panel sort pages 20; 23 Hazards: NONE Restoration Inst:
Post-maintenance testing and recovery method required; SRV click test.
Attribute Description Attribute Value High Energy System Concerns NO Tech Spec Impact? Enter EOS# or None NONE IN MODE 4/5 Compensatory Actions Req? NO Locked Components? NO Fire Protection Impairment? NO Equip Drain / Vent rig required? NO Scaffold Required? NO Is an LCO start time required? NO Tech Spec Impact on System Restoration? NO Component Deviation Required? NO 50.59 Screening Attached N/A Crew Assigned Walk down Yes Walk down complete?
Reason this tag was created? Scheduled work Tagout prepare issues: No issues Work Order Number Description XXXXXX REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P AND 1B21F506P Status Description User Verification Date Prepared Prepared Technical Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed Page 9 of 14
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT MANUAL INFORMATIONAL USE PAGE 7 OF 25 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________ TAGOUT: ________________
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/R Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif emoval No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes Page 10 of 14
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT MANUAL INFORMATIONAL USE PAGE 7 OF 25 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________ TAGOUT: ________________
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/R Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif emoval No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes Page 11 of 14
Give this page to the student NUCLEAR QUALITY RELATED EN-WM-105 REV.XX MANAGEMENT INFORMATIONAL USE PAGE xx OF 48 MANUAL ATTACHMENT 9.2 IMPACT TEMPLATE Sheet 1 of 1
____________________/___________ ____________________/___________
PLANNER DATE REVIEWER DATE WORK SCOPE:
REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P AND 1B21F506P.
COMPONENT MODE: ( ) INSV ( X )OOSV ( ) AVAILABLE PLANT MODES & CONDITIONS:
Plant MUST BE IN Mode 4 or 5. 1B21F505P and 1B21F506P must be electrically isolated.
EFFECTS ON ASSOCIATED SYSTEM AND COMPONENTS:
SRV 1B21F047L will not be capable of being opened electrically, either manually or automatically.
PRE-MAINTENANCE ACTIVITIES:
None POST-MAINTENANCE ACTIVITIES:
None DOES THE ACTIVITY HAVE THE POTENTIAL TO SCRAM/TRIP THE PLANT: ( ) YES ( X ) NO SECURITY/FIRE/CONTROL ROOM ENVELOPE BARRIER BREACH: ( ) YES ( X ) NO RPS AFFECTED: ( ) YES ( X ) NO ESF/EFSAS AFFECTED: ( X ) YES ( ) NO ALARMS/COMPUTER POINTS AFFECTED (IF YES, LIST ON ATTACHED SHEET) ( ) YES ( X ) NO Page 12 of 14
Give this page to the student NUCLEAR QUALITY RELATED EN-WM-105 REV.XX MANAGEMENT INFORMATIONAL USE PAGE xx OF XX MANUAL ATTACHMENT 9.3 OPERATIONAL IMPACT TEMPLATE Sheet 1 of 1 OPERATIONAL IMPACT
____________________/___________ ____________________/___________
SRO DATE REVIEWER DATE TECHNICAL SPECIFICATIONS:
NONE IN MODE 4 OR 5 LIMITING CONDITIONS FOR OPERATIONS:
NONE IN MODE 4 OR 5 REACTIVITY IMPACT (REQUIRED):
NONE POTENTIAL SYSTEM/COMPONENT EFFECTS:
This work only affects capability of one SRV, 1B21F047L.
ACTUAL OR POTENTIAL MEASURE OR CONTINGENCY ACTION REQUIRED:
At least two SRVs must be operable in Mode 4 and in Mode 5 until the RPV head is removed.
Page 13 of 14
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT INFORMATIONAL USE PAGE 14 OF 25 MANUAL Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.10 TAGOUT REQUEST Tagout Request Instructions The Tagging Requestor is responsible for providing detailed information on the work scope/condition and should recommend boundaries to provide for equipment and personnel safety.
Work Order # Task # Mark # Requester Ext. /
Pager XXXXXX 1 Smith 555
- 1. Provide a detailed description of the maintenance activity and the reference drawing numbers:
REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P AND 1B21F506P. M1077E; E1161-01,04,11,12,14,17; E0300 fuse sort pg 1, panel sort pgs 20; 23
- 2. If known, provide a previous Clearance/Tagout number which provides the required protection:
Fluid systems:
Yes No Valve Work Air- Back Seat Yes No Water- MOV Open Closed Steam-Oil-Test & Maintenance Tag
- 3. Fluid Components To Be Tagged and Required Position:
Isolation Valves (Any Gags, Brakes, or Flanges required):
Drain/Vent Valves:
Special Instructions:
Need solenoid valves electrically isolated
- 4. Electrical Components To Be Tagged and Required Position:
Yes No Control Switches:
Breakers:
Tag on Breaker Tag to be moved to Door Fuses/Leads to Pulled/Lifted:
Grounds/Ground Locations:
Special Instructions:
Click test required for retest.
Page 14 of 14
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR94 Revision: 0 Page: 1 of 1 JOB PERFORMANCE Rtype:
MEASURE QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE:
Primary Containment Water Level Determination EOP Attachment 29 New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: NA REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 11/9/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/15/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR94 Revision: 0 Page: 2 of 2 JOB PERFORMANCE MEASURE Task: Primary Containment Water Level Determination Setting: Classroom Type: RO Task: CRO-EP-029 K&A: 295029 EA2.01: 3.9/3.9; EA2.03: 3.4/3.5; Generic 2.4.21: 4.0/4.6; 2.1.25: 3.9/4.2; 2.1.20: 4.6/4.6 Safety Function: Containment Integrity [10CFR55.45a (4)]
Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 05-S-01-EP-1, Attachment 29 Handout(s): None
- Manipulations: N/A
- Critical Steps: 4 Group : N/A Simulator Setup/Required Plant Conditions:
- None Safety Concerns:
- None THIS IS AN ADMINISTRATIVE JPM.
Initial Condition(s):
- A LOCA has occurred.
- Suppression Pool water level indication is offscale high.
- RCIC is shut down with suction aligned to the Suppression Pool.
Initiating Cue(s):
- Determine Primary Containment water level IAW EP Attachment 29.
- Use the attached images for current plant indications.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR94 Revision: 0 Page: 3 of 3 JOB PERFORMANCE MEASURE Task: Primary Containment Water Level Determination Notes:
- 1. None Task Overview:
Using EP Attachment 29 and the attached images to obtain RCIC Suction Pressure and Containment Pressure, determine Primary Containment Water Level from the Delta Pressure to Ctmt Level Conversion Table, EP Attachment 29 Table 1.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR94 Revision: 0 Page: 4 of 4 JOB PERFORMANCE MEASURE Task: Primary Containment Water Level Determination Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- DETERMINES RCIC Pump Suction Pressure indicated on E51-R604 is 15 psig.
Standard: The operator determines RCIC Pump Suction Pressure indicated on E51-R604 from image 1 is 15 psig and records it on EP Attachment 29 step 2.4.
Cue: none.
Notes:
- DETERMINES Containment Pressure indicated on SPDS is 2.2 psig.
Standard: The operator determines Containment Pressure indicated on the SPDS display from image 2 is 2.2 psig and records it on EP Attachment 29 step 2.5.
Cue: none.
Notes:
- DETERMINES Delta Pressure to be 12.8 psig by subtracting Containment Pressure from RCIC Pump Suction Pressure.
Standard: The operator determines Delta Pressure to be 12.8 psig by subtracting Containment Pressure recorded in step 2.5 from RCIC Pump Suction Pressure recorded in step 2.4 and records it in step 2.6.
Cue: none.
Notes:
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR94 Revision: 0 Page: 5 of 5 JOB PERFORMANCE MEASURE
- DETERMINES Primary Containment water level to be 35.5 feet.
Standard: The operator determines Primary Containment water level using EP Attachment 29 Table 1 by moving down the Delta Pressure whole number column to 12 and then to the right to the 0.8, Tenths of Pound Delta Pressure column, which lists Containment Level as 35.5 feet.
Cue: End of task.
Notes: EP Attachment 29 provides the following example:
IF delta pressure obtained in Step 2.6 was 14.2 psig, THEN determine CTMT level by going down the left hand column to 14 and then across to the 0.2 column. This example results in containment level of 38.8 ft.
Task Standard(s):
Determine Containment Water level using Containment pressure and RCIC Suction pressure and 05-S-01-EP-1 Attachment 29.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR Number: GJPM-OPS-ADMR94 Revision: 0 Page: 6 of 6 JOB PERFORMANCE MEASURE Task: Primary Containment Water Level Determination Follow-Up Questions & Answers:
Comments:
Primary Containment Water Level Determination Give this page to the student Initial Condition(s):
- A LOCA has occurred.
- Suppression Pool water level indication is offscale high.
- RCIC is shut down with suction aligned to the Suppression Pool.
Initiating Cue(s):
Determine Primary Containment water level IAW EP Attachment 29.
Use the attached images for current plant indications.
Page 7 of 7
Image 1 - SPDS Display- Give this page to the student Page 8 of 8
Image 2 - 1H13P601- Give this page to the student Page 9 of 9
GRAND GULF Number: GJPM-OPS-ADMS88 NUCLEAR STATION Revision: 00 Page: 1 of 7 Rtype:
JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING
- LESSON PLAN TITLE:
Determine Protective Action Recommendation New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: NA REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 11/17/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/19/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
GJPM-SRO-A&E45.00 Page 1 of 7
GRAND GULF Number: GJPM-OPS-ADMS88 NUCLEAR STATION Revision: 00 Page: 2 of 7 JOB PERFORMANCE MEASURE Task : Determine Protective Action Recommendation Setting: Classroom Type: SRO Task: SRO-A& E-041 K&A: Generic 2.3.13: 3.8; 2.4.29: 4.0; 2.4.40: 4.5; 2.4.44: 4.4 Safety Function: Administrative Time Required: 15 minutes Time Critical: No Faulted: No Performance: Perform Reference(s): 10-S-01-1, Activation of the Emergency Plan (Section 6.1.6k) 10-S-01-12,Radiological Assessment and Protective Action Recommendations (Section 6.2)
Handout(s): 10-S-01-1, Activation of the Emergency Plan 10-S-01-12, Radiological Assessment and Protective Action Recommendations 2-mile Emergency Planning Zone Map (a copy is located at Shift Managers desk in the simulator)
- Manipulations: N/A
- Critical Steps: 1 Group #: N/A Simulator Setup/Required Plant Conditions: None.
Safety Concerns: None.
Equipment Needed: None.
THIS IS AN ADMINISTRATIVE JPM.
GJPM-SRO-A&E45.00 Page 2 of 7
GRAND GULF Number: GJPM-OPS-ADMS88 NUCLEAR STATION Revision: 00 Page: 3 of 7 JOB PERFORMANCE MEASURE Initial Condition(s):
- The Emergency Plan has been entered and a General Emergency declared.
- An uncontrolled offsite radioactive release is occurring.
- The On-Shift Chemist has performed Dose Calculations and projected the following exposures:
Site Boundary 1.5 Rem TEDE 7.5 Rem CDE Thyroid 5 Miles from the plant 0.2 Rem TEDE 5.1 Rem CDE Thyroid 10 Miles from the plant 0.03 Rem TEDE 0.12 Rem CDE Thyroid
- Wind direction is from 225 degrees to 45 degrees.
- NO abnormal weather conditions exist.
Initiating Cue(s):
- You are the Emergency Director.
- Determine the Protective Action Recommendations, if any, to be made to State and Local Agencies for the offsite public, identifying the affected downwind sectors.
GJPM-SRO-A&E45.00 Page 3 of 7
GRAND GULF Number: GJPM-OPS-ADMS88 NUCLEAR STATION Revision: 00 Page: 4 of 7 JOB PERFORMANCE MEASURE Task : Determine Protective Action Recommendation Notes
- 1. This is an Administrative Job Performance Measure.
Task Overview: This task is to determine based on plant conditions during an emergency the recommendations for protective measures for offsite persons and emergency response personnel. This will involve understanding of radiological conditions and applying the Emergency Plan Procedures to the situation and determining protective actions.
Tasks: Critical steps are underlined, italicized, and denoted by (*).
- Using 10-S-01-1 section 6.1.4k OR 10-S-01-12 section 6.2, make a Protective Action Recommendation for the State and Local Agencies based on radiological conditions.
Standard: Candidate uses references to determine the EXTENDED PAR is applicable, which requires evacuating 2 miles All Sectors and 10 miles Downwind Sectors (B, C, D) and Shelter the remainder of the 10 mile Emergency Planning Zone. Additionally a recommendation to consider use of Potassium Iodide in accordance with State Plans should be made. The affected sectors are B, C, D. The Ad Hoc PAR should not be made since dose projections at 10 miles are well below the Ad Hoc limit.
Cue: None Notes: If needed use a followup question to determine the Down Wind Sectors.
GJPM-SRO-A&E45.00 Page 4 of 7
GRAND GULF Number: GJPM-OPS-ADMS88 NUCLEAR STATION Revision: 00 Page: 5 of 7 JOB PERFORMANCE MEASURE Task Standard(s):
Recommends EXTENDED PAR: evacuation of all sectors within a 2-mile radius, evacuation of sectors B, C, D within a 10-mile radius, and use of Potassium Iodide in accordance with State Plans in accordance with 10-S-01-1 and 10-S-01-12.
Name: __________________________________ Time Start: _______ Time Stop: _______
GJPM-SRO-A&E45.00 Page 5 of 7
GRAND GULF Number: GJPM-OPS-ADMS88 NUCLEAR STATION Revision: 00 Page: 6 of 7 JOB PERFORMANCE MEASURE Task : Determine Protective Action Recommendation Follow-Up Questions & Answers:
Comments:
GJPM-SRO-A&E45.00 Page 6 of 7
Give this page to the student Determine Protective Action Recommendation Initial Condition(s):
- The Emergency Plan has been entered and a General Emergency declared.
- An uncontrolled offsite radioactive release is occurring.
- The On-Shift Chemist has performed Dose Calculations and projected the following exposures:
Site Boundary 1.5 Rem TEDE 7.5 Rem CDE Thyroid 5 Miles from the plant 0.2 Rem TEDE 5.1 Rem CDE Thyroid 10 Miles from the plant 0.03 Rem TEDE 0.12 Rem CDE Thyroid
- Wind direction is from 225 degrees to 45 degrees.
- NO abnormal weather conditions exist.
Initiating Cue(s):
- You are the Emergency Director.
- Determine the Protective Action Recommendations, if any, to be made to State and Local Agencies for the offsite public, identifying the affected downwind sectors.
GJPM-SRO-A&E45.00 Page 7 of 7
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS95 Revision: 00 Page: 1 of 9 JOB PERFORMANCE Rtype:
MEASURE QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE:
Determine Fire Watch Requirements New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: NA REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 11/17/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/19/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS95 Revision: 00 Page: 2 of 9 JOB PERFORMANCE MEASURE Task : Determine Fire Watch Requirements Setting: Classroom Type: SRO Task: SRO-NO-035 K&A: Generic 2.1.2: 4.4; 2.1.8: 4.1; 2.2.22: 4.7;2.1.25: 4.2; 2.4.25: 3.7 Safety Function: N/A [10CFR55.45a (12)]
Time Required: 20 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 02-S-01-17, Control of Limiting Conditions for Operation 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 UFSAR App. 9A, Fire Hazards Analysis E-1800 Handout(s): Copy of Tech Specs/TRM 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)
UFSAR App. 9A, Fire Hazards Analysis for room 1A220 (ATTACHED)
E-1800
- Manipulations: N/A
- Critical Steps: 3 Group : N/A Simulator Setup/Required Plant Conditions:
- None Safety Concerns:
- None THIS IS AN ADMINISTRATIVE JPM.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS95 Revision: 00 Page: 3 of 9 JOB PERFORMANCE MEASURE 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, P65N528E.
- All other fire protection related equipment and structures are operable.
Initiating Cue(s):
- Determine the Fire Watch requirements associated with this work.
- Use the references provided.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS95 Revision: 00 Page: 4 of 9 JOB PERFORMANCE MEASURE Task : Determine Fire Watch Requirements Notes:
- 1. None Task Overview:
The student will use references to determine TRM LCO requirements for inoperable required fire detection instrumentation and an inoperable fire rated assembly.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS95 Revision: 00 Page: 5 of 9 JOB PERFORMANCE MEASURE Task : Determine Fire Watch Requirements Tasks : Critical steps are underlined, italicized, and denoted by an (*).
Sequence is not critical.
- Determines Fire Detection Instrumentation required by TRM 6.2.1 will be inoperable Standard: 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. Candidate determines entry into TRM 6.2.1 Condition A, Action A.1 is required for the work.
Cue: none Notes:
- Determines door1A213 is a Fire Rated Assembly required by TRM 6.2.8 and will be inoperable.
Standard: Candidate uses provided references to identify the door to be blocked open is required operable by TRM 6.2.8. Candidate determines entry into TRM 6.2.8 Condition A is required for the work.
Cue: none Notes:
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS95 Revision: 00 Page: 6 of 9 JOB PERFORMANCE MEASURE
- Determines appropriate action for the combination of Fire Detection Instrumentation and Fire Rated Assembly inoperable is to establish an hourly fire watch patrol to inspect room 1A220.
Standard: Candidate determines fire detection instrumentation on at least one side of door 1A213 is operable, zone 2-2, per TRM Action A.2.1. Candidate determines establishing an hourly fire watch patrol to inspect room 1A220 is required to meet TRM 6.2.1 Action A.1 and that this 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.
Candidate identifies he would establish an hourly fire watch patrol to inspect room 1A219.
NOTE: Though for TRM 6.2.8 Condition A, either Action A.1 (continuous firewatch) OR Actions A.2.1 and A.2.2 (verifying fire detection on one side of door 1A213 and an hourly firewatch) will satisfy TRM actions, selection of an hourly firewatch patrol versus a continuous firewatch is Operations preference to accommodate staffing conditions.
1A222 is acceptable as an additional area, but NOT required. 1A220 MUST be hourly fire watch to satisfy 6.2.1 condition A.
Cue: end of JPM Notes:
Task Standard(s):
Candidate identifies he would establish an hourly fire watch patrol to inspect room 1A220 in accordance with TRM 6.2.1 and TRM 6.2.8.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS95 Revision: 00 Page: 7 of 9 JOB PERFORMANCE MEASURE Task : Determine Fire Watch Requirements Follow-Up Questions & Answers:
Comments:
Give this page to the student Determine Fire Watch Requirements 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, P65N528E.
- All other fire protection related equipment and structures are operable.
Initiating Cue(s):
- Determine the Fire Watch requirements associated with this work.
- Use the references provided.
JPM Page 8 of 9
Give this page to the student The reference pages have been redacted due to providing specific equipment location information.
JPM Page 9 of 9
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS96 Revision: 00 Page: 1 of 7 JOB PERFORMANCE Rtype:
MEASURE QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE:
Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: NA REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 11/20/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/16/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS96 Revision: 00 Page: 2 of 7 JOB PERFORMANCE MEASURE Task : Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available Setting: Classroom Type: SRO Task: SRO-ADMIN-054 K&A: Generic 2.1.25: 4.2; 2.1.1: 4.2; 2.2.17: 3.8 Safety Function: N/A [10CFR55.45a (12)]
Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 01-S-18-6, Risk Assessment of Maintenance Activities Handout(s): 01-S-18-6, Risk Assessment of Maintenance Activities
- Manipulations: N/A
- Critical Steps: 1 Group : N/A Simulator Setup/Required Plant Conditions:
- None Safety Concerns:
- None THIS IS AN ADMINISTRATIVE JPM.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS96 Revision: 00 Page: 3 of 7 JOB PERFORMANCE MEASURE Initial Condition(s):
- The plant is at 70% power.
- A Severe Thunderstorm Watch has just been issued for Claiborne County, MS.
- Heater Drain Pump A is red tagged out of service for preventive maintenance.
- Standby Service Water Pump C is red tagged out of service for preventive maintenance.
- The EOOS computer program is not available.
- All other equipment and structures are operable.
Initiating Cue(s):
- Determine the Plant Safety Index risk color manually in accordance with 01-S-18-6, provided.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS96 Revision: 00 Page: 4 of 7 JOB PERFORMANCE MEASURE Task : Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available Notes:
- 1. None Task Overview:
The candidate will determine the Plant Safety Index risk color for the given plant conditions using 01-S-18-6 Attachment IV.
Note: Critical steps are underlined, italicized, and denoted by an (*)
- Determines the Plant Safety Index risk color using 01-S-18-6 Attachment IV.
Standard: Candidate performs a manual quantitative analysis in accordance with 01-S-18-6 step 6.5.2a. Candidate reviews the listed systems on 01-S-18-6 Attachment IV page 1 and determines SSW C is listed and the associated risk color for SSW C out of service is Yellow. Candidate determines Heater Drain Pumps are not a listed system, so only one listed system, SSW C, is affected. Therefore he can determine risk level without the aid of the PSA group as specified in the note at the top of 01-S-18-6 Attachment IV.
Candidate reviews the listed environmental conditions on 01-S-18-6 Attachment IV page 2 and determines for a Severe Thunderstorm Watch there is NO risk impact and the note at the top of page 1 still applies. The candidate determines risk color for this combination of Level 1 equipment out of service and environmental conditions is YELLOW.
Note: Candidate should perform a qualitative risk analysis using 01-S-18-6 Attachment V, but this is not critical since no missile barriers are out of service, thus the risk color is unchanged.
Cue: none Notes:
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS96 Revision: 00 Page: 5 of 7 JOB PERFORMANCE MEASURE Task Standard(s):
Determines the Plant Safety Index risk color is YELLOW in accordance with 01-S-18-6.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS96 Revision: 00 Page: 6 of 7 JOB PERFORMANCE MEASURE Task : Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available Follow-Up Questions & Answers:
Comments:
Give this page to the student Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available Initial Condition(s):
- The plant is at 70% power.
- A Severe Thunderstorm Watch has just been issued for Claiborne County, MS.
- Heater Drain Pump A is red tagged out of service for preventive maintenance.
- Standby Service Water Pump C is red tagged out of service for preventive maintenance.
- The EOOS computer program is not available.
- All other equipment and structures are operable.
Initiating Cue(s):
- Determine the Plant Safety Index risk color manually in accordance with 01-S-18-6, provided.
JPM Page 7 of 7
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS97 Revision: 00 Page: 1 of 16 JOB PERFORMANCE Rtype:
MEASURE QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING
- LESSON PLAN TITLE:
Determine LCO Actions and Initiate a Manual LCO Tracking Report New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: NA REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )
Prepared By: Kyle Grillis 11/20/09
- Preparer Date Ops Review++: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Validated By: M. Rasch 3/19/2010 Training Representative Date Approved By:
+
Discipline Training Supervisor Date Approval Date:*
- Indexing Information
- The requirements of the Training Material Checklist have been met.
+
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++
Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS97 Revision: 00 Page: 2 of 16 JOB PERFORMANCE MEASURE Task: Determine LCO Actions and Initiate a Manual LCO Tracking Report Setting: Classroom Type: SRO Task: SRO-ADMIN-038; SRO-NO-030 K&A: Generic 2.2.22: 4.7; 2.2.23: 4.6; 2.2.15: 4.3; 2.2.40: 4.7; 2.2.41: 3.9 Safety Function: N/A [10CFR55.45a (12)]
Time Required: 30 minutes Time Critical: No Faulted: No Performance: Simulate Reference(s): GGNS Tech Specs 3.5.1 02-S-01-17, Control of Limiting Conditions for Operations; Drawings M1077E; E1161-04,11,12,14,17; E0300 fuse sort page 1, panel sort pages 20; 23 Handout(s): Completed Work Impact Statement, partially completed Tagout Request Form, completed Tagout Cover Sheet, Blank copy of Tagout Tags Sheet, Dwgs M1077E; E1161-04,11,12,14,17; E0300 02-S-01-17, Control of Limiting Conditions for Operations Technical Specifications
- Manipulations: N/A
- Critical Steps: 9 Group #: N/A Simulator Setup/Required Plant Conditions: None.
Safety Concerns: None Equipment Needed: None THIS IS AN ADMINISTRATIVE JPM.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS97 Revision: 00 Page: 3 of 16 JOB PERFORMANCE MEASURE Initial Condition(s):
- The Plant is in Mode 3.
- Electrical Maintenance is to rework the wiring connections for 1B21F505P and 1B21F506P, Pilot Solenoid Valves for SRV 1B21F047L locally, at the SRV.
- The work will require electrical isolation only. The air supply portion of the system will NOT be breached.
- A protective clearance has been prepared for the work.
- The next sequential LCO number is 7777.
Initiating Cue(s):
- You have been directed to prepare an LCO using Attachment I of procedure 02-S 17 to allow installation of the protective clearance, attached.
Use the drawings and blank LCO Tracking Report provided.
The LCO start time will begin when you complete the LCO Tracking Report.
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS97 Revision: 00 Page: 4 of 16 JOB PERFORMANCE MEASURE Task: Determine LCO Actions and Initiate a Manual LCO Tracking Report Notes
- 1. This is an Administrative JPM.
Task Overview: This task is to determine actions to be taken and generate the eSOMS LCO for the conditions.
Tasks: Critical tasks are underlined, italicized, and denoted by (*).
- Review the tagout and determines the ADS and Relief functions for ADS/SRV 1B21-F047L are INOPERABLE.
Standard: The candidate reviews the tagout and determines the Division 1 & 2 trip systems for ADS and Relief functions for ADS/SRV 1B21-F047L will be de-energized.
Cue: None Notes:
- Identifies Technical Specifications 3.5.1 Condition E is the bounding LCO.
Standard: The candidate determines the applicable Technical Specifications are TS 3.5.1 Condition E and TS 3.4.4 is a potential LCOTR. Of those, the candidate determines TS 3.5.1 Condition E is the most limiting and bounds the others for the given situation.
Cue:
INFORM THE CANDIDATE TO COMPLETE ONLY THE LCO TRACKING REPORT FOR THE ACTUAL LCO TS 3.5.1.
Notes:
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS97 Revision: 00 Page: 5 of 16 JOB PERFORMANCE MEASURE
- Initiates a manual LCO Tracking Report.
Standard: The candidate completes the initiation sections of an LCO Tracking Report, 02-S-01-17 Attachment 1 in accordance with 02-S-01-17 section 6.10 with Critical items as follows: Highlighted on KEY.
- The System or Component and Initiating Condition fields should accurately represent the inoperable equipment and/or function.
- As a minimum TS 3.5.1 Condition E should be listed in the TS/TRM/ODCM NO. and Condition fields.
- In the Required Action and Completion Time fields, Required Action E, Restore the ADS Valve to Operable status, 14 Days , should be reflected.
The following Non-Critical fields should be completed:
- Date and time
- The LCO number will be M-1-TS-10-7777 in accordance with step 6.10.2 and the next sequential number of 7777 given in the initial conditions.
- Mode (3)
- WO NO. and Other Document & NO. fields should be blank since no WO or Clearance number are provided.
- Station Management Notified should be N/A. No Duty Manager notification is required. No other department notification is required.
- LCO 3.0.6 Entered and Evaluated for Loss of Safety Function should both be N/A. (not a support system; no support systems cued as INOP)
- The candidate should sign as Shift Supervisor.
Tech Spec 3.4.4 Condition A & required actions A.1 and A.2 may be listed, but clearly identified as having no completion time.
Tech Spec 3.3.5.1 and 3.3.6.5 may be referenced as Potential LCOs, but no required actions apply.
Cue: If asked, inform the candidate the WO and Clearance numbers are not finalized yet. Also, if contacted as Duty Manager, simply acknowledge receipt of information conveyed.
Notes:
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS97 Revision: 00 Page: 6 of 16 JOB PERFORMANCE MEASURE Task Standard(s):
A manual LCOTR form has been completed in accordance with 02-S-01-17 identifying entry into Tech Spec 3.5.1 Conditions E for SRV 1B21F047L inoperable.
Name: ________________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR Number: GJPM-OPS-ADMS97 Revision: 00 Page: 7 of 16 JOB PERFORMANCE MEASURE Task: Determine LCO Actions and Initiate a Manual LCO Tracking Report Follow-Up Questions & Answers:
Comments:
GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE 02-S-01-17 Revision: 118 Attachment I Page 1 of 1 DO NOT GIVE THIS PAGE TO STUDENT KEY LCOTR NO. M-1 -TS-10-7777 DATE todays date TIME current time MODE 1 2 3 4 5 SYSTEM OR COMPONENT 1B21-F047L TS/TRM/ODCM NO. WO NO. OTHER DOCUMENT & NO.
TS 3.5.1 Xxx610 INITIATING CONDITION ADS SRV B21-F047L out of service to rework electrical connections at B21-F505P & F506P Wording does not have to be exact.
CONDITION REQUIRED ACTION COMPLETION TIME E Restore ADS Valve to operable status. 14 Days Other Department required Notified Y / N/A STATION MANAGEMENT NOTIFIED Y / N/A to perform Action:
LCO 3.0.6 ENTERED Y / N/A EVALUATED FOR LOSS OF SAFETY FUNCTION Y / N/A SHIFT SUPERVISOR SHIFT MANAGER Student signature RECURRING ACTION VERIFICATION DATE 0700-1900 1900-0700 LCO RESTORED DATE/TIME COMMENTS/CORRECTIVE ACTION SHIFT SUPERVISOR SHIFT MANAGER This form may be discarded after all information has been entered in the eSOMS LCO Tracking System
Give this page to the student Determine LCO Actions and Initiate a Manual LCO Tracking Report Initial Condition(s):
- The Plant is in Mode 3.
- Electrical Maintenance is to rework the wiring connections for 1B21F505P and 1B21F506P, Pilot Solenoid Valves for SRV 1B21F047L locally, at the SRV.
- The work will require electrical isolation only. The air supply portion of the system will NOT be breached.
- A protective clearance has been prepared for the work.
- The next sequential LCO number is 7777.
Initiating Cue(s):
- You have been directed to prepare an LCO using Attachment I of procedure 02-S 17 to allow installation of the protective clearance, attached.
Use the drawings and blank LCO Tracking Report provided.
The LCO start time will begin when you complete the LCO Tracking Report.
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT MANUAL INFORMATIONAL USE PAGE 6 OF 25 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 TAGOUT COVER SHEET Clearance: __MANUAL____________ Tagout: ___1-C17-B21-XXX__________________
Component to be worked: B21-F505P/B21-F506P B21-F047L Solenoid Valve DRYWELL 166
==
Description:==
ELECTRICALLY ISOLATE 1B21F047L IN ORDER TO REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P & 1B21F506P Placement Inst:
This tagout de-energize solenoid valves for SRV 1B21F047L.
References:
M1077E; E1161-04,11, 12,14, 17, E0300 fuse sort page 1, panel sort page 20 & 23 Hazards: NONE Restoration Inst:
Post-maintenance testing and recovery method required; SRV click test.
Attribute Description Attribute Value High Energy System Concerns NO Tech Spec Impact? Enter EOS# or None YES Compensatory Actions Req? NO Locked Components? NO Fire Protection Impairment? NO Equip Drain / Vent rig required? NO Scaffold Required? NO Is an LCO start time required? NO Tech Spec Impact on System Restoration? NO Component Deviation Required? NO 50.59 Screening Attached N/A Crew Assigned Walk down Yes Walk down complete?
Reason this tag was created? Scheduled work Tagout prepare issues: No issues Work Order Number Description XXX610 REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P & 1B21F506P Status Description User Verification Date Prepared Prepared Technical Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT MANUAL INFORMATIONAL USE PAGE 7 OF 25 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________ TAGOUT: ___1-C17-B21-XXX _____________
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/R Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif emoval No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes XXX1 Danger 1B21M605P 1 OFF ADS VALVE 1B21-F047L COA-166-0C504
-1H13P601 XXX2 Danger 1B21M606P 1 OFF ADS VALVE 1B21-F047L COA-166-0C504
-1H13P631 XXX3 Danger 1-B21 FUSE -1B21F11A 2 REMOVED
- 1H13-P628 BAY A FUSE
- 21 ON TERMINAL BOARD D FOR 1B21F047L (B21CF11A)
COA-189 XXX4 Danger 1-B21 FUSE -1B21F12A 2 REMOVED
- 1H13-P628 BAY A FUSE
- 22 ON TERMINAL BOARD D FOR 1B21F047L (B21CF12A)
COA-189
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT MANUAL INFORMATIONAL USE PAGE 7 OF 25 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________ TAGOUT: ____1-C17-B21-XXX ____________
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/R Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif emoval No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes XXX5 Danger 1-B21 FUSE -1B21F11B 2 REMOVED
- 1H13-P631BAY A FUSE
- 21 ON TERMINAL BOARD D FOR 1B21F047L (B21CF11B)
COA-166 XXX6 Danger 1-B21 FUSE -1B21F12B 2 REMOVED
- 1H13-P631 BAY A FUSE
- 22 ON TERMINAL BOARD D FOR 1B21F047L (B21CF12B)
COA-166
Give this page to the student NUCLEAR QUALITY RELATED EN-WM-105 REV.XX MANAGEMENT INFORMATIONAL USE PAGE xx OF 48 MANUAL ATTACHMENT 9.2 IMPACT TEMPLATE Sheet 1 of 1
____________________/___________ ____________________/___________
PLANNER DATE REVIEWER DATE WORK SCOPE:
REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P &
1B21F506P.
COMPONENT MODE: ( ) INSV ( X )OOSV ( ) AVAILABLE PLANT MODES & CONDITIONS:
Plant MUST BE IN Mode 3. 1B21F505P and 1B21F506P must be electrically isolated.
EFFECTS ON ASSOCIATED SYSTEM AND COMPONENTS:
SRV 1B21F047L will not be capable of being opened electrically, either manually or automatically.
PRE-MAINTENANCE ACTIVITIES:
None POST-MAINTENANCE ACTIVITIES:
None DOES THE ACTIVITY HAVE THE POTENTIAL TO SCRAM/TRIP THE PLANT: ( ) YES ( X ) NO SECURITY/FIRE/CONTROL ROOM ENVELOPE BARRIER BREACH: ( ) YES ( X ) NO RPS AFFECTED: ( ) YES ( X ) NO ESF/EFSAS AFFECTED: ( X ) YES ( ) NO ALARMS/COMPUTER POINTS AFFECTED (IF YES, LIST ON ATTACHED SHEET) ( ) YES ( X ) NO
Give this page to the student NUCLEAR QUALITY RELATED EN-WM-105 REV.XX MANAGEMENT INFORMATIONAL USE PAGE xx OF XX MANUAL ATTACHMENT 9.3 OPERATIONAL IMPACT TEMPLATE Sheet 1 of 1 OPERATIONAL IMPACT
____________________/___________ ____________________/___________
SRO DATE REVIEWER DATE TECHNICAL SPECIFICATIONS:
LIMITING CONDITIONS FOR OPERATIONS:
REACTIVITY IMPACT (REQUIRED):
NONE POTENTIAL SYSTEM/COMPONENT EFFECTS:
This work only affects capability of one SRV, 1B21F047L.
ACTUAL OR POTENTIAL MEASURE OR CONTINGENCY ACTION REQUIRED:
Give this page to the student NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. XX MANAGEMENT INFORMATIONAL USE PAGE 14 OF 25 MANUAL Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.10 TAGOUT REQUEST Tagout Request Instructions The Tagging Requestor is responsible for providing detailed information on the work scope/condition and should recommend boundaries to provide for equipment and personnel safety.
Work Order # Task # Mark # Requester Ext. / Pager XXX610 1 Smith 555
- 1. Provide a detailed description of the maintenance activity and the reference drawing numbers:
REWORK WIRING CONNECTIONS AT SOLENOID VALVES 1B21F505P & 1B21F506P. Ref.
M1077E; E1161-04,11,12,14, 17, E0300 fuse sort pg 1, panel sort pg 20 & 23
- 2. If known, provide a previous Clearance/Tagout number which provides the required protection:
Fluid systems:
Yes No Valve Work Air- Back Seat Yes No Water- MOV Open Closed Steam-Oil-Test & Maintenance Tag
- 3. Fluid Components To Be Tagged and Required Position:
Isolation Valves (Any Gags, Brakes, or Flanges required):
Drain/Vent Valves:
Special Instructions:
Need solenoid valves electrically isolated
- 4. Electrical Components To Be Tagged and Required Position:
Yes No Control Switches:
Breakers:
Tag on Breaker Tag to be moved to Door Fuses/Leads to Pulled/Lifted:
1B21F11A; F12A; F11B; F12B Grounds/Ground Locations:
Special Instructions:
Click test required for retest.
Give this page to the student XX
GRAND GULF Number: GJPM-OPS-EAL27 NUCLEAR STATION Revision: 00 Page: 1 of 7 Rtype:
JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING
- LESSON PLAN TITLE:
DETERMINE ENTRY INTO SITE EMERGENCY PLAN AND COMPLETE INITIAL NOTIFICATION FORMS APPROXIMATE TIME REQUIRED: 15 Minutes for declaration 5 minutes for form completion PREREQUISITES: NONE SUPPORTING LESSONS: NONE New Material Minor Revision Major Revision REASON FOR REVISION:
New JPM; Modified JPM REVIEW / APPROVAL (Print Name): Electronic Approval (TEAR # )
Prepared By: M. Rasch 1/26/2010 Preparer Date Reviewed By: R. Thompson 4/20/2010 Technical Reviewer (e.g., SME, line management) Date Instructional Adequacy Determined By: W. Ryder 4/20/2010 ITPL (Rev 0); Qualified Instructor (All other revisions) Date Approved By:
++
Discipline Training Supervisor Date Effective Date:
- Date
++
Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on the Training Development Review Worksheet FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable ANO PNPS CNPS RBS ECH VY GGNS WF3 IPEC WPO JAF
- Indexing Information Page 1 of 7
GRAND GULF Number: GJPM-OPS-EAL27 NUCLEAR STATION Revision: 00 Page: 2 of 7 Rtype:
JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Task: Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Setting: Classroom Type: SRO Task: SRO-A&E-015; SRO-A&E-003 K&A: Generic 2.4.41: 4.6; 2.4.30: 4.1; 2.4.40: 4.5 Safety Function: N/A Time Required: 15 minutes for declaration of EAL Classification 5 minutes for completion of Notification Form Time Critical: YES, EAL CLASSIFICATION ONLY Faulted: No Performance: Perform Reference(s): 10-S-01-1 Handout(s): 10-S-01-1; EAL Flow Chart Forms EPP 06-01 and EPP 01-06
- Manipulations: N/A
- Critical Steps: 2 Group #: N/A ADMINISTRATIVE JPM Simulator Setup/Required Plant Conditions: None.
Safety Concerns: None.
Equipment Needed: None.
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GRAND GULF Number: GJPM-OPS-EAL27 NUCLEAR STATION Revision: 00 Page: 3 of 7 Rtype:
JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Task: Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Initial Condition(s):
- The plant has experienced a transient.
Initiating Cue(s):
- You are the Shift Manager.
- A tornado offsite in Claiborne County caused damage to the Entergy Transmission Lines resulting in a loss of the Baxter Wilson and Franklin 500 KV Transmission Lines and Port Gibson 115 KV Transmission Line 15 minutes ago.
- Division 2 Diesel Generator is in Maintenance and disassembled.
- Divisions 1 and 3 Diesel Generators are operating carrying their respective busses.
- The Reactor Scrammed upon the loss of offsite power.
- All Control Rods are fully inserted.
- All other systems are functioning as designed.
- Classify this event and complete any initial notification forms that are required.
Use Current time for time of Shutdown.
No Meteorological Data is available.
No Release is in progress.
This is a TIME CRITICAL JPM.
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GRAND GULF Number: GJPM-OPS-EAL27 NUCLEAR STATION Revision: 00 Page: 4 of 7 Rtype:
JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Task: Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Notes
- 1. This is an Administrative JPM.
- 2. This is an activity performed by an SRO as Emergency Director per the GGNS Emergency Plan Procedures.
Task Overview: This task is to use the Emergency Plan Procedure and Off Normal Event Procedures for classification of plant conditions per the Emergency Action Levels and complete the Initial Notification forms for contact of State and Local Agencies. This is a TIME CRITICAL JPM based on the requirements of 10 CFR50 Appendix E IV.D.3.
Tasks: Critical tasks are underlined, italicized, and denoted by (*).
This is a TIME CRITICAL JPM.
Identify that Division 2 bus 16AB is de-energized and that only Division 1 Diesel Generator powering bus 15AA prevents a Station Blackout.
Standard: Candidate determines that a single failure of Division 1 Diesel Generator will result in a Station Blackout.
Cue: None Notes: All offsite transmission lines out of service means the station is relying on Diesel Generators for ESF buses.
Station Blackout is defined as a loss of power to both 15AA and16AB. A loss of Division 1 Diesel Generator would result in the loss of power to 15AA and thus a Station Blackout.
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GRAND GULF Number: GJPM-OPS-EAL27 NUCLEAR STATION Revision: 00 Page: 5 of 7 Rtype:
JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials
- Classify the event as an ALERT.
Standard: Candidate uses 10-S-01-1 Attachments I and II Initiating Conditions SA1 to classify the event as an ALERT.
Cue: None Notes: CLASSIFICATION of the EAL is the TIME CRITICAL portion of the JPM.
- Complete the Initial Notification form for contact of State and Local Agencies. (SEE Attached form for critical information.)
Standard: Candidate completes Initial Notification form.
Cue: None Notes: TIME to Complete the Notification form is NOT TIME CRITICAL.
Task Standard(s):
ALERT is declared per EAL SA1 and Initial Notification Form is completed.
Name: __________________________________ Time Start: _______ Time Stop: _______
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GRAND GULF Number: GJPM-OPS-EAL27 NUCLEAR STATION Revision: 00 Page: 6 of 7 Rtype:
JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Task: Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Follow-Up Questions & Answers:
Comments:
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Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Give this page to the student Initial Condition(s):
- The plant has experienced a transient.
Initiating Cue(s):
- You are the Shift Manager.
- A tornado offsite in Claiborne County caused damage to the Entergy Transmission Lines resulting in a loss of the Baxter Wilson and Franklin 500 KV Transmission Lines and Port Gibson 115 KV Transmission Line 15 minutes ago.
- Division 2 Diesel Generator is in Maintenance and disassembled.
- Divisions 1 and 3 Diesel Generators are operating carrying their respective busses.
- The Reactor Scrammed upon the loss of offsite power.
- All Control Rods are fully inserted.
- All other systems are functioning as designed.
- Classify this event and complete any initial notification forms that are required.
Use Current time for time of Shutdown.
No Meteorological Data is available.
No Release is in progress.
This is a TIME CRITICAL JPM.
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