Text

302 Final JPMs
	ML090270042
Person / Time
Site:	Brunswick
Issue date:	11/10/2008
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-324/08-302, 50-325/08-302
	Download: ML090270042 (222)
	v • d • e

Final Submittal (Blue Paper)

FINAL JPMS

1. ADMINISTRATIVE JPMs

2. IN-PLANT JPMs

3. SIMULATOR JPMs (CONTROL ROOM)

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE A-1A-R LESSON TITLE: Determine SRM/IRM Overlap Per GP-02.

LESSON NUMBER: LOT-OJT-JP-307-A03 REVISION NO: 0

Determine SRM/IRM Overlap Per GP-02.

SAFETY CONSIDERATIONS:

None.

E&

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL NOT be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

3. Task standards (Le. pass/fail criteria) for each JPM step are ITALICIZED below that step.

Read the following to trainee.

TASK CONDITIONS:

1. Unit One (1) startup is being performed per OGP-02.

2. Initial (pre-startup) SRM and IRM readings were recorded as follows:

SRM Channel Reading IRM Channel Reading*

A 100 CPS A 3%

B 150 CPS B 2%

C 150 CPS C 4%

D 100 CPS D 5%

E 8%

F 6%

G 3%

H 5%

LOT-OJT-JP-307-A03 Page 2 of 9 REV. 0

Determine SRM/IRM Overlap Per GP-02.

3. Current SRM and IRM readings are as follows:

SRM Channel Reading IRM Channel Reading*

A 2 X 105 CPS A 11%

B 9 X 104CPS B 14%

C 4X 105 CPS C 16%

D 3 X 105 CPS D 10%

E 15%

F 18%

G 14%

H 17%

AIIIRM Readings taken on Range One From the Bar Graph Recorder (0-125%)

INITIATING CUE:

You are directed to determine if proper SRM/IRM overlap exists in accordance with GP-02.

It is NOT desired to use the highest reading IRM (pre-startup) for overlap criteria for allIRMs.

LOT-OJT-JP-307-A03 Page 3 of 9 REV. 0

Determine SRMIIRM Overlap Per GP-02.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain a current revision of OGP-02.

Current Revision of OGP-02 obtained and verified, if applicable.

SAT/UNSAT*

Step 2 - Determine SRM/IRM overlap criteria is not met for IRM A and D based on not reading 10% of scale.

Determined that SRMIIRM overlap criteria is not met for IRM A and D based on not reading 10% of scale.

- CRITICAL STEP** SAT/UNSAT*

Step 3 - Determine SRM/IRM overlap criteria is not met for IRM E based on not reading double the initial reading.

Determined that SRMIIRM overlap criteria is not met for IRM E based on not reading double the initial reading.

- CRITICAL STEP ** SAT/UNSAT*

LOT-OJT-JP-307 -A03 Page 4 of 9 REV. 0

Determine SRM/IRM Overlap Per GP-02.

Step 4 - Determine GP-02 requires the Reactor Engineer be notified and Technical Specification LeO 3.3.1.1 be referenced.

Determined that GP-02 requires the Reactor Engineer be notified and Technical Specification 3.3. 1. 1 be referenced.

SAT/UNSAT*

Comments required for any step evaluated as UNSAT.

LOT-OJT-JP-307 -A03 Page 5 of 9 REV. 0

Determine SRMIIRM Overlap Per GP-02.

Time Required for Completion: ~ Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate l Actual Unit:

Setting: Control Room Simulator__ (Not applicable to In-Plant JPMs)

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee:

SSN: - - - - - - - - - -

JPM: Pass ___ Fail --

Remedial Training Required: Yes No _ _

Yes No -----

Comments:

Comments reviewed with Student Evaluator Signature: Date: _________

LOT-OJT-JP-307-A03 Page 7of9 REV. 0

TASK CONDITIONS:

1. Unit One startup is being performed per OGP-02.

2. Initial (pre-startup) SRM and IRM readings were recorded as follows:

SRM Channel Reading IRM Channel Reading*

A 100 CPS A 3%

B 150 CPS B 2%

C 150 CPS C 4%

D 100 CPS D 5%

E 8%

F 6%

G 3%

H 5%

3. Current SRM and IRM readings are as follows:

SRM Channel Reading IRM Channel Reading*

A 2 X 105 CPS A 11%

B 9 X 104CPS B 14%

C 4 X 105 CPS C 16%

D 3 X 105 CPS D 10%

E 15%

F 18%

G 14%

H 17%

AIIIRM Readings taken on Range One From the Bar Graph Recorder (0-125%)

INITIATING CUE:

You are directed to determine if proper SRMIIRM overlap exists in accordance with GP-02.

It is NOT desired to use the highest reading IRM (pre-startup) for overlap criteria for allIRMs.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE A-1A-S LESSON TITLE: Evaluate Core Spray System Operability Test Data LESSON NUMBER: LOT-ADM-JP-018-A01 REVISION NO: 0

Evaluate Core Spray System Operability Test Data.

SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.

2. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.

3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

4. Obtain copy of OPT-07.2.4a and fill out Attachment 1 up to Unit SCO review. Under General Comments, Exceptions, and Corrective Actions fill in None.

5. Fill out Attachment 2 for Core Spray Pump 1A Test Information. Data should be within acceptance range with exception of:

Incorrectly determine pump DP and record that value. Use numbers that when correctly subtracted place pump DP below the acceptance and required action range value.

Fill out one vibration (1 W A) as greater than maximum acceptance value but less than required action - in alert range.

6. Fill out Attachment 3 for Unit 1 Core Spray Loop A Valve Test Information Sheet. All data filled out should fall within acceptance range with the exception of:

1-E21-F005A stoke open time should be filled out as greater than maximum value, but less than limiting value.

1-E21-F031A stroke close time should be filled out as less than minimum value.

7. Provide filled out Attachments 1,2, & 3 and Acceptance Criteria from OPT-07.2.4a to examinee. Provide examinee an entire copy of OPT-07.2.4a if requested (examiner should have available copy for each examinee).

8. Task standards (Le. pass/fail criteria) for each JPM step are ITALICIZED below the step.

LOT-ADM-J P-O 18-AO 1 Page 2 of 8 REV. 0

Evaluate Core Spray System Operability Test Data.

Read the following to trainee.

TASK CONDITIONS:

1. OPT-07.2.4a, Core Spray System Operability Test - Loop A, has just been completed on Unit One for Core Spray Loop 1A by an operator.

2. The test was performed to satisfy the QUARTERLY frequency requirement.

3. Stem verifications and Leakage walkdown were not performed.

4. The operator who completed the test has determined all acceptance criteria are met with no exceptions as certified on Attachment 1.

5. The operator who completed the test has requested a peer check of the data that was recorded on Attachments 2 and 3 to ensure all acceptance criteria are met.

6. Another operator is checking the remainder of the procedure, other than Attachments 2 and 3 for satisfactory completion.

INITIATING CUE:

You are directed to evaluate the data recorded in OPT-07.2.4a, Attachments 2 and 3, against the acceptance criteria of the test. Report any exceptions to satisfactory performance, and if required, any corrective action required by OPT-07.2.4a.

LOT-ADM-JP-018-A01 Page 3 of 8 REV. 0

Evaluate Core Spray System Operability Test Data.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain a current revision of OPT-02.4.7a.

Current Revision of OPT-02. 7.4a obtained.

SAT/UNSAT*

Step 2 - Evaluate data in the completed Attachments 2 and 3 and identify the following DEFICIENCIES and CORRECTIVE ACTIONS.

a. Identify that Pump DP is incorrectly calculated and that actual DP is outside acceptance range and in required action range.

Identified that Pump DP psid is outside acceptance range and in required action range

Declared Core Spray pump 1A INOPERABLE per the guidance of Acceptance Criteria step 6.1.5

- CRITICAL STEP ** SAT/UNSAT*

b. Identify that Pump vibration position 1W A is in the alert range.

Identified that Pump vibration position 1W A is in the alert range

Determine testing frequency shall be doubled per the guidance of Acceptance Criteria step 6. 1.4

- CRITICAL STEP ** SAT/UNSAT*

LOT-ADM-JP-018-A01 Page 4 of 8 REV. 0

Evaluate Core Spray System Operability Test Data.

c. Identify that Valve 1-E21-F005A is outside acceptance range but within limiting time for opening.

Identified that Valve 1-E21-F005A is outside acceptance range but within limiting time for opening.

Immediately retest or Declare 1-E21-F005A INOPERABLE per the guidance of Acceptance Criteria step 6.2.1.2

- CRITICAL STEP ** SAT/UNSAT*

d. Identify that Valve 1-E21-F031 A is outside (less than) minimum acceptance range for closing.

Identify that Valve 1-E21-F031A is outside (less than) minimum acceptance range for closing.

Declare 1-E21-F031A INOPERABLE per the guidance of Acceptance Criteria step 6.2.1.3

- CRITICAL STEP ** SATIUNSAT*

Comments required for any step evaluated as UNSAT.

LOT-ADM-JP-018-A01 Page 5 of 8 REV. 0

Evaluate Core Spray System Operability Test Data.

RELATED TASKS:

2090038201, Perform Core Spray System Operability Test Per PT-07.2.4a (07.2.4b)

KIA REFERENCE AND IMPORTANCE RATING:

GEN 2.1.32 3.8/4.0 Ability to explain and apply system limits and precautions.

REFERENCES:

OPT-07.2.4a TOOLS AND EQUIPMENT:

None.

ADMINISTRATIVE CATEGORY (from NUREG 1123):

Admin - Equipment Control LOT-ADM-JP-018-A01 Page 6 of 8 REV. 0

Evaluate Core Spray System Operability Test Data.

Validation Time: ~ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual L Unit: _1_

Setting: Control Room Simulator__ (N/A for Admin or In-Plant JPMs)

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X IIII1 ] n 111111111 ] ]111 n1111l1li11111 I Ii EVALUATION Trainee: _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass - - Fail - -

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure as Authorized Copy?: Yes No _ __

Comments:

Comments reviewed with Student Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

LOT-ADM-JP-018-A01 Page 7 of 8 REV. 0

TASK CONDITIONS:

1. OPT-07.2.4a, Core Spray System Operability Test - Loop A, has just been completed on Unit One for Core Spray Loop 1A by an operator.

2. The test was performed to satisfy the QUARTERLY frequency requirement.

3. Stem verifications and Leakage walkdown were not performed.

4. The operator who completed the test has determined all acceptance criteria are met with no exceptions as certified on Attachment 1.

5. The operator who completed the test has requested a peer check of the data that was recorded on Attachments 2 and 3 to ensure all acceptance criteria are met.

6. Another operator is checking the remainder of the procedure, other than Attachments 2 and 3 for satisfactory completion.

INITIATING CUE:

You are directed to evaluate the data recorded in OPT-07.2.4a, Attachments 2 and 3, against the acceptance criteria of the test. Report any exceptions to satisfactory performance, and if required, any corrective action required by OPT-07.2.4a.

BRUNSWICK NUCLEAR PLANT c

Continuous Use DATE COrPLETED To ;~ FREQUENCY:

UNIT % PWR /(JOE?riWE '1 J~ A. Once every 92 days SUPERVISOR :! . 0" e B. Stem verification - each refueling NOT to REAj)ON FOR TEST (check one or more): exceed two years

_V_ Routine f surveillance C. Leakage walkdown - at least once per 24

_W/O# _ _ _ _ _ _ _ _ _ _ _ __ months

_ Other (explain)_ _ _ _ _ _ _ _ _ __ D. Stroking/timing E21-F015A- each refueling outage E. Comprehensive Pump Test (CPT) every 2 years PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT o

OPT-07.2.4a CORE SPRA Y SYSTEM OPERABILITY TEST - LOOP A REVISION 58 1 OPT-07.2.4a Rev. 58 Page 1 of 361

1.0 PURPOSE 1.1 This test is performed to determine the operability of the Core Spray System A Loop. The test conforms to the requirements specified in Technical Specifications 5.5.6 to perform testing in accordance with ASME OM-Code. This test satisfies Technical Specification surveillance's SR 3.5.1.6 and 3.5.2.5 (for the Core Spray Pump). Performance of Valve Remote Position indicator Verification satisfies the requirements of SR 3.3.3.1.3. This test satisfies a portion of SRs 3.5.1.12 and 3.5.2.7 related to response time testing for Core Spray Pump A and E21-F005A.

1.2 This test also satisfies Technical Specification 5.5.2 for leak tightness inspection every 24 months.

1.3 The following test quantities shall be measured, calculated, or observed and recorded as applicable:

1.3.1 Valve stem travel or disk movement 1.3.2 Proper operation of the valve remote position indicator (RPI) 1.3.3 Time required for valve stroke 1.3.4 Pump inlet pressure 1.3.5 Pump discharge pressure 1.3.6 Pump vibration velocity 1.3.7 Pump flow rate 1.3.8 Pump lubricant level 1.3.9 Pump differential pressure (calculated) 1OPT-07 .2.4a Rev. 58 Page 2 of 361

2.0 REFERENCES

2.1 Technical Specifications 2.2 FSAR, Section 6.3 2.3 1(2)OP-18, Core Spray System Operating Procedure 2.4 1(2)OP-51, DC Electrical System Operating Procedure 2.5 001-01.08, Control of Equipment and System Status 2.6 Technical Requirements Manual (TRM) 2.7 OSD-18, Core Spray System Description 2.8 NUREG-1482, Revision 1, Guidelines for Inservice Testing at Nuclear Power Plahts 2.9 ASME OM Code-2001, Code for Operation and Maintenance of Nuclear Power Plants through ASME OMb Code-2003 Addenda 2.10 NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs 2.11 OENP-17, Pump and Valve Inservice Testing (1ST) 2.12 OENP-16.1, 1ST Pump and Valve Data IR131 2.13 EC 46949, 2-E21-F004A1B and F005A1B Motor Pinion Gear Ratio Change &

Compiling Core Spray Surveillance Requirements 2.14 EER 90-0315, Vibration Program for 1A and 2A Core Spray Pumps IRISI 2.15 Response to NRC Bulletin 88-04, Potential Safety Related Pump Loss 2.16 0-25024, Sheet 2, Core Spray System, Unit 1 2.17 0-02524, Sheet 2, Core Spray System, Unit 2 1OPT-07.2.4a Rev. 58 Page 3 of 361

2.0 REFERENCES

2.18 ESR 97-00508, ECCS Response Time Testing Methods 2.19 10 CFR 50.67, Accident Source Term 2.20 Second Request for Additional Information, Brunswick Steam Electric Plant, Units 1 and 2 Response to Generic Letter 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves" 2.21 EGR-NGGC-0010, System and Component Trending Program and System Libraries 2.22 OENP-23, Predictive Maintenance Program 2.23 RFJ-14, Refueling Justification for Stroking E21-F015A1B.

2.24 OAP-54, Plant Leak Management 2.25 Brunswick Steam Electric Plant Units 1 and 2, Issuance of Amendment RE:

Alternative Source Term (License Amendments 221 and 246, dated May 30, 2002) 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Attachments 2 and 3 must be reviewed by the 1ST group.

3.2 Water from the suppression pool should not be injected into the reactor vessel during the performance of this test.

3.3 The following annunciators may alarm during the performance of this test:

3.3.1 CORE SPRA Y OR RHR PUMPS RUNNING (A-03 2-1).

3.3.2 CORE SPRAY LOOPA SYS PRESS LOW (A-01 2-10).

3.4 Vibration velocity testing is required only during Comprehensive Pump Tests (CPT). When required, vibration velocity readings shall be taken at the test positions specified on the data sheet. Since there are multiple test points, ensure that the probe is located on the correct bearing (see Attachment 5) and in the correct direction as specified in the test position number.

IOPT-07.2.4a Rev. 58 Page 4 of 36 I

3.0 PRECAUTIONS AND LIMITATIONS 3.5 For taking vibration readings, the probe shall be securely mounted at each test position. The probe must be in firm contact with the bearing housing when taking data.

3.6 When taking readings to be recorded on Attachment 2, the indicator/pointer fluctuation should be reduced to a minimum. A valve upstream of the gauge may be throttled to reduce fluctuation. Care should be taken to ensure proper communication between the gauge and main flow path.

3.7 Suitable test gauges may be used in place of any installed instrument. If used, the full-scale range of each analog instrument should be three times the reference value or less, with adequate range to prevent damage during use. Use of alternate test gauges requires recording the test gauge identification number, test gauge calibration date, and test gauge calibration due date.

3.8 Some steps of this test require independent verification.

3.9 An Operator should be stationed to monitor system piping for excessive motion and/or water hammer when a Core Spray Pump is started. The susceptible piping includes Core Spray discharge piping located in the overhead of the 50' elevation of the Reactor Building.

3.10 When opening system drain/vent valves, proper radiological control procedures shall be observed.

3.11 Core Spray Loop A shall be declared inoperable from the beginning of Valve Testing, Section 7.7, to when valve stroking is complete AND the CORE SPRAY LOOPA SYS PRESS LOW(A-01 2-10) is cleared.

3.12 During system venting, air is not expected in the system. Should air be found, initiate a W/O and notify the System Engineer. Presence of air in the system does not make the system inoperable but does imply component degradation at some point that must be addressed. The test may continue provided air can be removed from the system via the normal venting process.

3.13 The Comprehensive Pump Test (CPT) Acceptance Criteria is only applicable when performing a Comprehensive Pump Test. The Quarterly pump test Acceptance Criteria is only applicable when performing a Quarterly Test.

1OPT-07.2.4a Rev. 58 Page 5 of 361

4.0 PREREQUISITES 4.1 No other testing or maintenance is in progress that will adversely affect the performance of this test.

4.2 The Core Spray System (Loop A) is in standby per 1(2)OP-18.

4.3 The station battery chargers are in operation per 1(2)OP-51.

4.4 IF a leakage walkdown is required, THEN OAP-054 Alternative Source Term (AST) Combined Leakage Log value has been recorded on Attachment 4.

4.5 If Comprehensive Pump Testing is required, a temporary 0-30 psig digital pressure gauge, with an accuracy within 0.1 %, is installed at A Core Spray Pump suction at E21-PI-R001A INSTRUMENT DRAIN VALVE, E21-PI-R001 A-6.

5.0 SPECIAL TOOLS AND EQUIPMENT 5.1 Confirm that no active corrective maintenance W/O exists on the following installed instruments. If any active W/O exists, operability of the instrument must be resolved and recorded in the General Comments and Recommendations section before the instrument may be used.

Instrument W/R-W/O W/R-W/O#

5.1.1 E21-PT-N001A yes/@>

5.1.2 E21-FT-N003A yes/@

5.1.3 E21-PI-R600A yes/(§)

5.1.4 E21-FI-R601A yes/@

5.1.5 E21-PI-2651 yes/~

5.1.6 E21-PI-7119A yes/&

5.1.7 E21-PI-ROO 1A yes/ey I OPT-07.2.4a Rev. 58 Page 6 of 36 I

5.0 SPECIAL TOOLS AND EQUIPMENT 5.2 If CPT is required, a digital 0-30 psig pressure gauge, with an accuracy within 0.1%, is installed at E21-PI-R001A INSTRUMENT DRAIN VALVE, E21-PI-R001A-6. If used, note:

5.2.1 ID number

/J~

5.2.2 Calibration date A/~

5.2.3 Calibration due date ,,/~

5.3 Suitable test gauges may be used to obtain data in place of any installed instrument. If used, note:

5.3.1 ID number 5.3.2 Range of instrument 5.3.3 Calibration date 5.3.4 Calibration due date 5.3.5 Parameter measured 5.4 A stopwatch with the following data recorded below:

5.4.1 Stopwatch identification number. ~t;Vlcf7 5.4.2 Stopwatch calibration date. 10/, log 5.4.3 Stopwatch calibration due date. "/,! 0' 5.5 If a CPT is performed, Predictive Maintenance personnel will provide the vibration monitoring instrument used for data collection. Record the required data below:

5.5.1 Vibration monitor identification number.

5.5.2 Transducer identification number. It/~

5.5.3 Vibration monitor/transducer calibration date. n I,...

5.5.4 Vibration monitor/transducer calibration due date.

5.6 Vent and drain rig 5.7 Tubing, valves, and fittings to install test gauges (as required).

5.8 Ladder for vibration readings, if required 1OPT-07.2.4a Rev. 58 Page 7 of 361

6.0 ACCEPTANCE CRITERIA This test may be considered satisfactory when the following criteria are met:

6.1 Pump Tests NOTE: Acceptance Criteria 6.1.1 includes allowances for a number of items (such as flow diversion through the minimum flow valve, cracks, and the vent hole).

Meeting the values shown assure that CS can provide 4100 gpm to the vessel with 113 psid between the Suppression Pool and the vessel as required by Technical Specifications.

6.1.1 CORE SPRA Y PUMP A operation develops a recirculation flow rate of 4700 gpm or greater against a system head of greater than or equal to 260 psig. (SR 3.5.1.6, SR 3.5.2.5) 6.1.2 CORE SPRA Y PUMP A discharge pressure increases to greater than or equal to 300 psig within 5 seconds of control switch operation.

(SR 3.5.1.12, SR 3.5.2.7) 6.1.3 The pump test data shall be compared to the allowable ranges identified in Test Information Attachment 2.

6.1.4 If deviations fall within the ALERT RANGE of Attachment 2, the frequency of testing shall be doubled until the cause of the deviation is determined and corrected and either the existing reference values reverified or a new set of reference values established per IST8-6200.

6.1.5 If the deviations fall within the REQUIRED ACTION RANGE of Attachment 2, the pump shall be declared inoperable and not returned to service until the condition has been corrected.

6.1.6 When completed test results show deviations greater than the allowable ACCEPTANCE VALUE RANGE, the instruments involved may be recalibrated and the test rerun. However, this shall not preclude declaring the pump inoperable as required.

IOPT-07.2.4a Rev. 58 Page 8 of 36 I

6.0 ACCEPTANCE CRITERIA 6.2 Valve Tests NOTE: Stroke time shall be measured from the time the control switch is repositioned to the time the valve is fully stroked by light indication.

Deviations from this standard method of testing will be specified in the procedure.

6.2.1 Valve Stroke Time

1. Measured stroke times shall be within the ACCEPTABLE RANGE as specified by the minimum and maximum stroke times shown on Attachment 3.

2. For tests where the measured stroke time of a valve exceeds the maximum ACCEPTABLE stroke time but does not exceed the LIMITING stroke time, the valve shall be immediately retested or declared INOPERABLE.

a. If a valve is retested, and the measured stroke time is within the ACCEPTABLE RANGE, the valve may be declared OPERABLE. A Condition Report (CR) shall be generated to ensure the OM Code requirement associated with the evaluation is completed by Engineering.

b. If a valve is retested and the measured stroke time falls outside the ACCEPTABLE RANGE, a Tracking LCO shall be generated to track the time agreed upon by the Shift Superintendent and BESS in accordance with 001-01.08.

Otherwise, declare the valve INOPERABLE and meet the requirements of all applicable Technical Specifications.

3. For tests where the measured stroke time of the valve is less than the minimum ACCEPTABLE stroke time, exceeds the LIMITING stroke time or the valve disc or stem fail to exhibit the required change of position, the valve shall immediately be declared INOPERABLE.

4. For Core Spray Injection Valves, E21-F004A and E21-F005A, the measured opening stroke time shall be less than or equal to 23.8 seconds to satisfy Core Spray Loop A response time requirements. (SR 3.5.1.12, SR 3.5.2.7).

I OPT-07.2.4a Rev. 58 Page 9 of 36 I

6.0 ACCEPTANCE CRITERIA 6.2.2 Valve Full-Stroke Exercise Full-stroke exercise requirements shall be satisfied by completely cycling a valve from the closed position to the open position and back to the closed position or from the open position to the closed position and back to the open position.

6.2.3 Valve Remote Position Indicator (RPI) Verification At a refueling frequency (not to exceed 2 years), each RPI Verification identified on Attachment 3 shall be observed to verify that the valve position is accurately indicated in both the open and closed positions by the indicating lights on the RTGB when the valve stem or mechanical position indicator has stopped moving. RPI verification satisfies the requirements of SR 3.3.3.1.3.

6.2.4 Check Valve Exercising

1. Check valve exercising to the full open position shall be satisfied by demonstrating the ability to pass maximum accident condition flow.

2. Check valve exercising to the partial open position shall be satisfied by demonstrating the ability to pass sustained flow.

3. Check valve exercising to the closed position shall be considered satisfactory by demonstrating the ability to establish a differential pressure across the valve seat, or by verifying the absence of flow under pressure while venting the upstream side of the valve seat with pressure on the downstream side.

6.3 Leak Tightness Examination 6.3.1 Identified leakage is recorded on Attachment 4, Leak Identification Data Sheet, and a Work Request (WR) is initiated for any leakage with the exception of packing and gasket leakage less than 5 drops per minute (dpm). The WR shall state that identified leakage is required to be corrected or minimized as required by TS 5.5.2.

6.3.2 For 'through-wall' or 'through-weld' leakage, a Nuclear Condition Report (NCR) is initiated to assess structural integrity of the affected component.

IOPT-07.2.4a Rev. 58 Page 10 of 361

6.0 ACCEPTANCE CRITERIA 6.3.3 The following applicable actions are taken when the combined leakage total (AST Combined Leakage Log value plus leakage from components shown on Attachment 6) is greater than 0 gpm:

1. If the combined leakage is determined to be less than or equal to 1 gallon per minute (gpm), the normal work management process (PRI 3) for correcting leakage is implemented.

2. If the combined leakage is determined to be greater than 1 gpm and less than or equal to 20 gpm, the initiated WR should be identified as PRI 2 to expedite corrective actions to eliminate or reduce identified leakage as soon as plant conditions allow.

3. If the combined leakage is greater than 20 gpm, the initiated WR should be identified as PRI 2 to expedite corrective actions to eliminate or reduce identified leakage as soon as plant conditions allow. A Nuclear Condition Report (NCR) is initiated to have Engineering assess the impact to the AST (10CFR50.67) analysis.

1OPT-07.2.4a Rev. 58 Page 11 of 361

7.0 PROCEDURAL STEPS Initials 7.1 OBTAIN permission from the Unit SCO to perform this test, J()

AND ENSURE LCO requirements have been reviewed in Unit seo accordance with 001-01.08.

7.2 ENSURE all prerequisites listed in Section 4.0 are met.

7.3 CONFIRM required data has been recorded in Section 5.0.

7.4 NOTIFY Maintenance the pumps are being tested so they can observe the pump run, if desired.

NOTE: A leakage walkdown is required to be performed each 24 months per TS 5.5.2.b.

7.5 IF a leakage walkdown is required of CORE SPRA Y LOOP A during the performance of this procedure, THEN PREPARE to perform a system walkdown to identify system leaks.

7.6 IF CPT is required, THEN ENSURE a 0-30 psig digital pressure gauge is installed at E21-PI-R001A INSTRUMENT DRAIN VALVE, E21-PI-R001A-6.

1OPT-07.2.4a Rev. 58 Page 12 of 361

7.0 PROCEDURAL STEPS Initials 7.7 Valve Testing NOTE: Those steps associated with valve remote position indicator (RPI) verification are performed each refueling, not to exceed 2 years, or after maintenance which affects RPI performance. IF RPI verification is NOT required for this test, THEN N/A may be entered in the Initials.

NOTE: Steps 7.7.1 through 7.7.3.2 are required to be performed only during refueling outages in an effort to prevent voiding Core Spray piping during power operations. IF these steps are NOT required for this test, THEN NA may be entered where appropriate.

C6re SpraYL6C>p.ASh~11 ;lje}d~.0f~;~CJirtOperable from the beginning of Valve Testing to whenvalVe s~r6king\is'pornriletejAND the GORE SPRAY LOOP A SYS PRESS LOW (A-Ot2~10) iStc:lear~d., ... .

7.7.1 IF performing during a refueling outage, THEN ENSURE Core Spray FULL FLOW TEST BYP VL V, E21-F015A, is closed.

7.7.2 IF performing during a refueling outage, THEN OPEN Core Spray FULL FLOW TEST BYP VLV, E21-F015A.

1. CONFIRM Core Spray FULL FLOW TEST BYP VL V, E21-F015A, valve stem travels to the open position when indicating lights indicate open, AND RECORD remote position indicator results on Attachment 3.

7.7.3 IF performing during a refueling outage, THEN CLOSE Core Spray FULL FLOW TEST BYP VL V, E21-F015A, AND RECORD valve stroke time and full-stroke exercise on Attachment 3.

1. CONFIRM Core Spray FULL FLOW TEST BYP VL V, E21-F015A, valve stem travels to the closed position when indicating lights indicate closed, AND RECORD remote position indicator results on Attachment 3.

1 OPT-07.2.4a Rev. 58 Page 13 of 361

7.0 PROCEDURAL STEPS Initials

2. IF entrance into this procedure was necessary only to 11/~

perform stroking and timing of E21-F015A, THEN GO TO AND PERFORM Section 7.8 AND applicable steps of Section 7.10.

7.7.4 ENSURE Core Spray OUTBOARD INJECTION VL V, -J5 E21-F004A, is open.

7.7.5 CLOSE Core Spray OUTBOARD INJECTION VL V, :J3 E21-F004A, AND RECORD valve stroke time on Attachment 3.

1. CONFIRM Core Spray OUTBOARD INJECTION VL V,

).5 E21-F004A, valve stem travels to the closed position when indicating lights indicate closed, AND RECORD remote position indicator results on Attachment 3.

7.7.6 ENSURE Core Spray INBOARD INJECTION VL V, JS E21-F005A, is closed.

7.7.7 OPEN Core Spray INBOARD INJECTION VL V, :rs E21-F005A, AND RECORD valve stroke time on Attachment 3.

1. CONFIRM Core Spray INBOARD INJECTION VL V, n E21-F005A, valve stem travels to the open position when indicating lights indicate open, AND RECORD remote position indicator results on Attachment 3.

7.7.8 CLOSE Core Spray INBOARD INJECTION VL V, n E21-F005A, AND RECORD valve stroke time and full-stroke exercise on Attachment 3.

1. CONFIRM Core Spray INBOARD INJECTION VLV, JS E21-F005A, valve stem travels to the closed position when indicating lights indicate closed, AND RECORD remote position indicator results on Attachment 3.

1OPT-07.2.4a Rev. 58 Page 14 of 361

7.0 PROCEDURAL STEPS Initials 7.7.9 OPEN Core Spray OUTBOARD INJECTION VL V, J5 E21-F004A, AND RECORD valve stroke time and full-stroke exercise on Attachment 3.

1. CONFIRM Core Spray OUTBOARD INJECTION VL V, 'J5 E21-F004A, valve stem travels to the open position when indicating lights indicate open, AND RECORD remote position indicator results on Attachment 3.

7.7.10 ENSURE Core Spray TORUS SUCTION VL V, D E21-F001A, is open.

7.7.11 CLOSE Core Spray TORUS SUCTION VL V, Is E21-F001A, AND RECORD valve stroke time on Attachment 3.

1. CONFIRM Core Spray TORUS SUCTION VL V, J.5 E21-F001A, valve stem travels to the closed position when indicating lights indicate closed, AND RECORD remote position indicator results on Attachment 3.

7.7.12 OPEN Core Spray TORUS SUCTION VL V, J"S E21-F001A, AND RECORD the valve stroke time and fUll-stroke exercise on Attachment 3.

1. CONFIRM Core Spray TORUS SUCTION VL V, J>

E21-F001A, valve stem travels to the open position when indicating lights indicate open, AND RECORD remote position indicator results on Attachment 3.

7.7.13 ENSURE Core Spray MIN FLOW BYPASS VL V, :JS E21-F031A, is open.

7.7.14 CLOSE Core Spray MIN FLOW BYPASS VL V, J.S E21-F031A, AND RECORD valve stroke time on Attachment 3.

1. CONFIRM Core Spray MIN FLOW BYPASS VL V, :r.S E21-F031A, valve stem travels to the closed position when indicating lights indicate closed, AND RECORD remote position indicator results on Attachment 3.

1OPT-07.2.4a Rev. 58 Page 15 of 361

7.0 PROCEDURAL STEPS Initials 7.7.15 OPEN Core Spray MIN FLOW BYPASS VL V, E21-F031A, AND RECORD valve stroke time and full-stroke exercise on Attachment 3.

1. CONFIRM Core Spray MIN FLOW BYPASS VL V, T5 E21-F031A, valve stem travels to the open position when indicating lights indicate open, AND RECORD remote position indicator results on Attachment 3.

NOTE: A higher pressure indication on E21-PI-R600A than on E21-PI-R001A confirms CORE SPRA Y PUMP DISCHARGE CHECK VAL VE, E21-F003A, is in the closed position.

7.7.16 CONFIRM CORE SPRA Y PUMP DISCHARGE CHECK VALVE, E21-F003A, is in the closed position AND RECORD position on Attachment 3.

7.8 Filling and Venting Core Spray Loop A NOTE: IF air is observed in the discharge piping, a W/R should be prepared to correct any problems.

7.8.1 IF the keepfill station for CORE SPRA Y LOOP A is available, THEN PERFORM the following:

1. ENSURE that a vent and drain rig is attached to CORE SPRA Y DIVISION I LINE VENT VAL VE, E21-V23.

2. THROTTLE OPEN CORE SPRA Y DIVISION I LINE VENT VALVE, E21-V23, until a solid stream of water issues from the vent line, THEN CLOSE E21-V23.

NOTE: Observation of a solid stream of water from CORE SPRA Y DIVISION I LINE VENT VALVE, E21-V23, confirms KEEPFILL STATION CHECK VALVES, E21-F029A and E21-F030A go to the partial open position.

3. CONFIRM KEEPFILL STA TlON CHECK VALVES, E21-F029A and E21-F030A, go to the partial open position AND RECORD position on Attachment 3.

1OPT-07.2.4a Rev. 58 Page 16 of 361

7.0 PROCEDURAL STEPS Initials CAUTION Failure tofolldwSteps1.R;2, 1'JhroughV,ajt:8 in thJ3?order specifiedhiay caus~Jhe KEEPFlbLBEitlEF VALVE,E21~Fb24A, t91iftand'damage theseatoU\EEPFltL .

STATION. PRESSURE CONTROL VALVE,E21-PCV-F026A .

.. ,;:.~.'. ..... . . . . . . . . ..

7.8.2 IF it is desired to use the KEEPFILL STA TlON E21-PCV-F026A BYPASS VALVE, E21-F028A, OR the valve is already open, THEN PERFORM the following:

1. ENSURE that a vent and drain rig is attached to CORE SPRA Y DIVISION I LINE VENT VAL VE, E21-V23.

2. ENSURE KEEPFILL STA TlON E21-PCV-F026A DOWNSTREAM ISOLATION VALVE, E21-F027A, is closed.

3. IF necessary, THROTTLE OPEN KEEPFILL STATION E21-PCV-F026A BYPASS VALVE, E21-F028A

4. THROTTLE OPEN CORE SPRA Y DIVISION I LINE VENT VALVE, E21-V23, until a solid stream of water issues from the vent line, THEN CLOSE E21-V23.

NOTE: Observation of a solid stream of water from CORE SPRA Y DIVISION I LINE VENT VALVE, E21-V23, confirms KEEPFILL STA TlON CHECK VALVES, E21-F029A and E21-F030A go to the partial open position.

5. CONFIRM KEEPFILL STA TlON CHECK VALVES, E21-F029A and E21-F030A, go to the partial open position AND RECORD position on Attachment 3.

6. CLOSE KEEPFILL STA TlON E21-PCV-F026A MIca BYPASS VALVE, E21-F028A. IndVer.

1 OPT-07.2.4a Rev. 58 Page 17 of 361

7.0 PROCEDURAL STEPS Initials

7. THROTTLE OPEN CORE SPRA Y DIVISION I LINE VENT VALVE, E21-V23, until CORE SPRAY PUMP A AL DISCHARGE PRESSURE INDICA TOR, E21-PI-R600A (Panel H12-P601), indicates 40 to 70 psig, THEN CLOSE E21-V23.

8. SLOWLY OPEN KEEPFILL STA TlON lib/co E21-PCV-F026A DOWNSTREAM ISOLA TlON Ind.ver.

VALVE, E21-F027A.

7.8.3 IF required, REMOVE the vent and drain rig from the CORE SPRA Y DIVISION I LINE VENT VALVE, E21-V23.

7.8.4 CONFIRM CORE SPRA Y LOOP A SYS PRESS LOW (A-01 2-10) is cleared.

7.9 Pump Testing 7.9.1 IF Quarterly testing is to be performed, THEN ~

OBSERVE CORE SPRA Y PUMP A suction pressure (stopped), as indicated on E21-PI-R001A, AND RECORD on Attachment 2.

7.9.2 IF Comprehensive Pump Testing is to be performed, THEN PERFORM the following:

1. OPEN E21-PI-R001A INSTRUMENT DRAIN VALVE, ~

E21-PI-ROO1A-6.

2. OBSERVE CORE SPRA Y PUMP A suction pressure n/I\.

(stopped), as indicated on temporary gauge, AND RECORD on Attachment 2.

1OPT-07.2.4a Rev. 58 Page 18 of 361

7.0 PROCEDURAL STEPS Initials

'CAUTION"

/ ,~ ,

Do NOT crossiconnec~ the Nuclear~~Ci Conventjorji:if'Servjc~Water headers. by

',siniulta~e~usly opening NUC SWTOVITALfjIEAl)IER VL V,SW-V117, and CONV,SW

'TOVITJfk-HIEAOIER VLV, SW-V1,11. ' '. . ,

7.9.3 ENSURE one of the following valves is open:

1. NUC SWTO VITAL HIEADIER VLV, SW-V117 T5 OR

2. CONV SWTO VITAL HEADER VLV, SW-V111.

7.9.4 ENSURE VITAL HEADERXTIE VLV, SW-V118, is open.

7.9.5 ENSURE WELL WATER TO VITAL HEADER VALVE, J3 SW-V141, is closed.

7.9.6 STATION an operator to monitor system piping for 'Z5 excessive motion and water hammer when a Core Spray pump is started.

7.9.7 ENSURE proper CORE SPRA Y PUMP A lubricant TI level.

1 OPT-07.2.4a Rev. 58 Page 19 of 361

7.0 PROCEDURAL STEPS Initials NOTE: The following step requires that the time interval from pump start to discharge pressure at 300 psig be measured with a stopwatch. It may be advisable to place a temporary non-destructive mark on the pressure indicator at 300 psig to assist in timing.

CAUTION Operation of tneCore

, ~ .' ,

S~ray F?urnp inthe h:linimum flow mode should be minimized.

~ '> *, " , . " , ,

7.9.8 START CORE SPRA Y PUMP A while monitoring pump discharge pressure on E21-PI-R600A, AND CONFIRM pressure increases to greater than or equal to 300 psig in less than or equal to 5.0 seconds.

Response Time fu sec.

7.9.9 RECORD the time that CORE SPRA Y PUMP A was 75 started.

Time 1.i!9fl 7.9.10 ENSURE the following:

1. CORE SPRA Y DIVISION I ROOM COOLER FAN has .;:5 started.

2. SERVICE WATER OUTLET VALVE, SW-V128, is open.

-=0-7.9.11 THROTTLE OPEN Core Spray FULL FLOW TEST J)

BYP VL V, E21-F015A, to obtain greater than or equal to 4700 gpm as indicated on E21-FI-R601A.

7.9.12 WHEN flow is greater than 603 gpm, CONFIRM that J3 the Core Spray MIN FLOW BYPASS VL V, E21-F031A, closes.

IR131 7.9.13 CONFIRM CORE SPRA Y PUMP A discharge 'J3 pressure is greater than or equal to 260 psig, as indicated on E21-PI-R600A.

1OPT-07.2.4a 1 Rev. 58 Page 20 of 361

7.0 PROCEDURAL STEPS Initials NOTE: A higher pressure indication on E21-PI-R600A than on E21-PI-2651 confirms KEEPFILL STATION CHECK VALVES, E21-F030A or E21-F029A, goes to the closed position. If indication on E21-PI-2651 is "pegged", then proceed to Step 7.9.15. If test is satisfactory, then N/A Step 7.9.15.

NOTE: Operability of the keep-fill check valves is performed as a pair. If the check valves cannot be determined to be closed, then a W/R shall be written to repair or replace both E21-F030A and E21-F029A.

7.9.14 CONFIRM KEEPFILL STATION CHECK VALVES, E21-F030A or E21-F029A, goes to the closed position, AND RECORD on Attachment 3.

NOTE: Confirming the absence of flow under pressure while venting at E21-PI-2651 INSTRUMENT DRAIN VALVE, E21-IV-786, satisfies reverse exercising requirements for KEEPFILL STATION CHECK VALVES, E21-F030A and/or E21-F029A. This does NOT imply that drainage will not be present.

7.9.15 IF test conditions in Step 7.9.14 cannot be met, THEN PERFORM the following steps to satisfy exercising KEEPFILL STATION CHECK VALVES, E21-F030A and/or E21-F029A, to the closed position:

1. CONNECT hose at E21-PI-2651 INSTRUMENT DRAIN VALVE, E21-IV-786, AND ROUTE to floor drain.

2. CLOSE KEEPFILL STA TlON E21-PCV-F026A UPSTREAM ISOLA TlON VALVE, E21-F025A.

3. ENSURE CORE SPRA Y LOOP A KEEPFILL ISOLATION VALVE, TD-V13, is closed.

4. OPEN E21-PI-2651 INSTRUMENT DRAIN VALVE, E21-IV-786, AND ALLOW piping to drain for a minimum of 3 minutes.

5. CONFIRM the absence of pressurized flow from drain hose AND RECORD KEEPFILL STA TlON CHECK VALVES, E21-F030A and/or E21-F029A go to the closed position on Attachment 3.

1 OPT-07.2.4a Rev. 58 Page 21 of 361

7.0 PROCEDURAL STEPS Initials

6. CLOSE E21-PI-2651 INSTRUMENT DRAIN / 'V',

VALVE, E21-IV-786. IndVer.

CAUTION Dam~me to the XEEPFILL STA Tl0N PRESSURE CONTROL VAL VEl E21-PCV-F026A, mciy occur if it. is placed in service too rapidly.

7. SLOWLY OPEN KEEPFILL STA TlON /~'"

E21-PCV-F026A UPSTREAM ISOLA TlON Ind.Ver.

VALVE, E21-F025A.

7.9.16 SLOWLY OPEN E21-PI-7119A INSTRUMENT ISOLATION VALVE, E21-V5000.

NOTE: The Core Spray Pump shall be operated under conditions as stable as the system permits prior to recording test data.

7.9.17 THROTTLE Core Spray FULL FLOW TEST BYP VLV, J3 E21-F015A, to obtain 4700 gpm as indicated on E21-FI-R601A.

7.9.18 IF the Quarterly test is being performed, THEN PERFORM the following:

1. OBSERVE CORE SPRA Y PUMP A suction pressure n (running), as indicated on E21-PI-R001A, AND RECORD on Attachment 2.

2. OBSERVE CORE SPRA Y PUMP A discharge J:S pressure, as indicated on E21-PI-7119A, AND RECORD on Attachment 2.

3. CALCULATE Core Spray Pump differential pressure, T5 AND RECORD in Quarterly Pump DP on Attachment 2.

4. RECORD CORE SPRA Y PUMP A System flow, as n indicated on FLOW INDICATOR E21-FI-R601A, on Attachment 2.

1 OPT-07.2.4a Rev. 58 Page 22 of 361

7.0 PROCEDURAL STEPS Initials 7.9.19 IF Comprehensive Pump Testing is being performed, THEN PERFORM the following:

I\~

1. OBSERVE CORE SPRA Y PUMP A suction pressure (running), as indicated on temporary gauge, AND RECORD on Attachment 2.

2. OBSERVE CORE SPRA Y PUMP A discharge ...1'"

pressure, as indicated on E21-PI-7119A, AND RECORD on Attachment 2.

3. CALCULATE Core Spray Pump differential pressure, ~~

AND RECORD in CPT Pump DP on Attachment 2.

4. OBSERVE CORE SPRA Y PUMP A System flow, as ,.,/~

indicated on FLOW INDICATOR E21-FI-R601A, AND RECORD on Attachment 2.

MEASURE CORE SPRA Y PUMP A vibration velocity

"./et 5.

(in/sec peak) at the test positions indicated, AND RECORD on Attachment 2.

7.9.20 ENSURE proper lubricant level AND RECORD on Attachment 2.

NOTE: Flow indication of at least 5000 gpm on FLOW INDICATOR E21-FI-R601A confirms CORE SPRA Y PUMP A DISCHARGE CHECK VAL VE, E21-F003A, goes to the full open position.

7.9.21 THROTTLE Core Spray FULL FLOW TEST BYP VL V, E21-F015A, to obtain 5000 gpm as indicated on E21-FI-R601A.

7.9.22 CONFIRM CORE SPRA Y PUMP A DISCHARGE CHECK VALVE, E21-F003A, fully opens AND RECORD on Attachment 3.

NOTE: A leakage walkdown is required to be performed at least once per 24 months per TS 5.5.2.

7.9.23 IF required, PERFORM a leakage walkdown of the components identified on Attachment 6, AND RECORD leakage on Attachment 4, Leak Identification Data Sheet.

1OPT-07.2.4a Rev. 58 Page 23 of 361

7.0 PROCEDURAL STEPS Initials 7.9.24 CLOSE E21-PI-7119A INSTRUMENT ISOLATION ,4e1 CO VALVE, E21-V5000. IndVer.

7.9.25 IF CPT was performed, THEN CLOSE E21-PI-ROO1A 1 'Y',,-

INSTRUMENT DRAIN VALVE, E21-PI-ROO1A-6. IndVer.

7.9.26 CLOSE Core Spray FULL FLOW TEST BYP J3 VLV, E21-F015A.

7.9.27 WHEN CORE SPRA Y LOOP A flow is less than 603 gpm, ENSURE that Core Spray MIN FLOW BYPASS VL V, E21-F031A, opens.

7.9.28 STOP CORE SPRA Y PUMP A AND RECORD the T...s time.

Time 12,,.2, s' 7.9.29 CONFIRM the following:

1. CORE SPRA Y DIVISION I ROOM COOLER FAN is T5 off.

2. SERVICE WATER OUTLET VALVE, SW-V12B, is :J5 closed.

7.9.30 IF required, ENSURE the following valves are closed:

1. NUC SW TO VITAL HEADER VLV, SW-V117 -:IS 1116 IndVer.

2. CONV SWTO VITAL HEADER VLV, SW-V111 --r51Ai$

IndVer.

7.9.31 CALCULATE CORE SPRA Y PUMP A run time. n I a,,~~ I ~f) i) = 2.,L 7.9.28 7.9.9 1OPT-07.2.4a Rev. 58 Page 24 of 361

7.0 PROCEDURAL STEPS Initials 7.9.32 IF required to relieve high system pressure condition or ensure the system is filled and vented, THEN PERFORM the following

1. ENSURE a vent and drain rig is attached to CORE n/"

SPRA Y DIVISION I LINE VENT VAL VE, E21- V23.

2. THROTTLE OPEN CORE SPRA Y DIVISION I LINE ~~

VENT VALVE, E21-V23, until a solid stream of water issues from the vent line, THEN CLOSE E21-V23.

3. IF required, REMOVE the vent and drain rig from "'I, CORE SPRAY DIVISION I LINE VENT VALVE, E21-V23.

7.10 System Restoration 7.10.1 ALIGN valves as specified in Table 1. T5 NOTE: Independent verification is required for valve lineup.

TABLE 1 SYSTEM VERIFICATION LINEUP SHEET REQUIRED INITIALS VALVE NO. DESCRIPTION POSITION IND. VER.

E21-FOO1A Core Spray Pump A Suppression Pool Suction Valve OPEN J3/,%

E21-FOO4A Core Spray Outboard Injection Valve OPEN JJ/~

E21-FOO5A Core Spray Inboard Injection Valve CLOSED "DIAO E21-F031A Core Spray Minimum Flow Bypass Valve OPEN j1/A-a E21-F015A Core Spray Test Bypass Valve CLOSED J5 I /J6 E21-V23 Core Spray Division I Line Vent Valve CLOSED 'J)/M 7.10.2 IF installed, REMOVE drain hose installed at E21-PI-2651, INSTRUMENT DRAIN VALVE, E21-IV-786.

7.10.3 IF CPT was performed, THEN REMOVE the temporary gauge at E21-PI-R001A INSTRUMENT DRAIN VALVE, E21-PI-R001A-6.

1OPT-07.2.4a Rev. 58 Page 25 of 361

7.0 PROCEDURAL STEPS Initials 7.10.4 IF necessary, REMOVE the temporary mark on w~

pressure indicator E21-PI-R600A.

7.10.5 ENSURE the required information has been recorded on the cover page.

7.10.6 NOTIFY the Unit sea when this test is complete or found to be unsatisfactory.

1OPT-07.2.4a Rev. 58 Page 26 of 361

ATTACHMENT 1 Page 1 of 1 Certification and Review Form General Comments and Recommendations _ _ _~ft_O::....:.....c-£~_ _ _ _ _ _ __

Initials Name (Print)

Performed by: ""IS "T-::,_ 5 ... r+L..

A6 A_ ~J1 cO Exceptions to satisfactory performance _--=-,.".....;;...o,oa~cJ..;;;;;>,,_ _ _ _ _ _ _ _ _ __

Corrective action required _ _ _......h---"'Qo&...&..DL,..D""'_=---------------

NOTE: Pump test data shall be analyzed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after completion of this PT.

SCQ review/approval of the PT satisfies this ASME Code requirement.

Test procedure has been satisfactorily completed:

Unit SCQ: _ _ _ _ _ _ _ _ _ _ _ _ __

Signature Date Test procedure has NOT been satisfactorily completed:

Unit SCQ: _ _ _ _ _ _ _ _ _ _ _ _ __

Signature Date Test has been reviewed by:

Shift Superintendent _ _ _ _ _ _ _ _ _ _ __

Signature Date 1 OPT-07.2.4a Rev. 58 Page 27 of 361

ATTACHMENT 2 Page 1 of 2 Unit 1 Core Spray Pump A Test Information Data Sheet

1. The lubricant level (pump running) is normal.

2. Calculate pump dP as follows:

Pump discharge pressure - suction pressure (run) = pump dP

"5. 0 S.O = .;J?O. 0 NOTE

Pump vibration measurement is required only during CPT. Vibration is measured at the test point marked on the pump for the correct bearing number and direction as indicated by the Test Position number as follows

- the number indicates the bearing number from Attachment 5

- for position, N=North, S=South, E=East, W=West

- for direction, A=Axial, H=Horizontal, V=Vertical NOTE: Reference values for pump suction and discharge pressures are provided for determining the suitability of alternate test gauges, if used.

UNIT 1 CORE SPRAY PUMP A TEST DATA REQUIRED ACTUAL REFERENCE ACCEPTANCE ALERT RANGE ACTION RANGE TEST PARAMETER VALUE VALUE VALUE RANGE LOW HIGH LOW HIGH Suction Press.

(Stopped) psig Suction Press.

'.0 6.0 4.0 4 to 8 N/A N/A N/A N/A N/A

<4 N/A

>8 N/A (Running) psig S:O Discharge Press. Psig 290.0 N/A N/A N/A N/A N/A

Z,,~ 0 Quarterly Pump DP 290.9 261.9 to 319.9 N/A N/A < 261.9 > 319.9 psid ;1')0*0 CPT Pump DP psid 290.9 270.6 to 299.6 261.9 N/A < 261.9 > 299.6 n/" to

<270.6 Flow Rate gpm Vibration-vel (in/s

".,00 4,700 0.133 N/A oto 0.325 N/A N/A N/A

> 0.325 N/A N/A N/A

> 0.700 peak) Position 1S H to

. I) 0 0.700 Vibration-vel (in/s 0.195 oto 0.325 N/A > 0.325 N/A > 0.700 peak) Position 1W A to

.3Q{' 0.700 Vibration-vel (in/s 0.144 oto 0.325 N/A > 0.325 N/A > 0.700 peak) Position 1W H

./ ~S to 0.700 Performed By (Signature) _---lJL.O.:::..L.---:.-A"'---...::::S"--'-=.t1---'-YL-'--.:::....-_

Reviewed, 1ST Group (Signature) _ _ _ _ _ _ _ _ Date _ _ __

1 OPT-07.2.4a Rev. 58 Page 28 of 361

ATTACHMENT 2 Page 2 of2 Unit 2 Core Spray Pump A Test Information Data Sheet

1. The lubricant level (pump running) is normal.

2. Calculate pump dP as follows:

Pump discharge pressure - suction pressure (run) = pump dP

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

NOTE: Pump vibration measurement is required only during CPT. Vibration is measured at the test point marked on the pump for the correct bearing number and direction as indicated by the Test Position number as follows:

the number indicates the bearing number from Attachment 5 for position, N=North, S=South, E=East, W=West for direction, A=Axial, H=Horizontal, V=Vertical NOTE: Reference values for pump suction and discharge pressures are provided for determining the suitability of alternate test gauges, if used.

UNIT 2 CORE SPRAY PUMP A TEST DATA REQUIRED ACTION ACTUAL REFERENCE ACCEPTANCE ALERT RANGE RANGE TEST PARAMETER VALUE VALUE VALUE RANGE LOW HIGH LOW HIGH Suction Press. 6.0 4 to 8 N/A N/A <4 >8 (Stopped) psig Suction Press. 4.0 N/A N/A N/A N/A N/A (Running) psig Discharge Press. Psig 290.0 N/A N/A N/A N/A N/A Quarterly Pump DP 283.1 260.0 to 311.4 N/A N/A < 260.0 > 311.4 psid CPT Pump DP psid 283.1 263.3 to 291.5 260.0 to N/A < 260.0 > 291.5

<263.3 Flow Rate gpm 4,700 N/A N/A N/A N/A N/A Vibration-vel (in/s 0.230 oto 0.325 N/A > 0.325 N/A > 0.700 peak) Position 1S H to 0.700 Vibration-vel (in/s 0.212 oto 0.325 N/A > 0.325 N/A > 0.700 peak) Position 1W A to 0.700 Vibration-vel (in/s 0.156 oto 0.325 N/A > 0.325 N/A > 0.700 peak) Position 1W H to 0.700 Performed By (Signature) Date ____ Time _ __

Reviewed, 1ST Group (Signature) _ _ _ _ _ _ _ _ Date _ _ __

\ OPT-07.2.4a Rev. 58 Page 29 of 36\

ATTACHMENT 3 Page 1 of 2 Unit 1 C S Svstem(Loop A) Valve Test Inf, tion Sheet Valve Number Stroke Remote Position Stroke Stroke Time Acceptance Direction Indication (Initials) Time Test Criteria (Seconds) Fail- FulI- Check Stem Ind. (sec) Acceptable Range Ref. Safe Stroke Valve Valve Lights Minimum Maximum Limiting Stroke Test Exercise Exercise SATI

(?-) (.;) <<) Time (Initials) (Initials) (Initials) UNSAT 1-E21-F015A OPEN .../" "'/1- N/A N/A N/A N/A N/A N/A N/A N/A SR7 1-E21-F015A CLOSED 3). os 35.90 48.50 52.70 42.20 N/A "I1 N/A ~

1-E21-F004A CLOSED la. tlQ 9.85 13.33 14.49 11.59 N/A N/A N/A SKI 1-E21-F005A OPEN

I. 01 10.01 13.55 14.73 11.78 N/A N/A N/A s¥ 1-E21-F005A CLOSED 10. II 9.88 13.36 14.53 11.62 N/A ~ N/A sM"

" . 'I~ S~

1-E21-F004A OPEN 9.99 13.51 14.69 11.75 N/A -r~ N/A 1-E21-F001A CLOSED )S.O~ 68.51 92.69 100.75 80.60 N/A N/A N/A sFt 1-E21-F001A OPEN iO .(0 72.73 98.39 106.95 85.56 N/A TI N/A SA-I 1-E21-F031A CLOSED

10. "0 11.00 14.80 16.10 12.90 N/A N/A N/A SIP, 1-E21-F031A OPEN ,/ Jt 13.00 12.30 16.50 18.00 14.40 N/A -:1"5 N/A slPf 1-E21-F003A CLOSED N/A N/A N/A N/A N/A N/A N/A N/A N/A TI sAf"'

1-E21-F029A PART N/A N/A N/A N/A N/A N/A N/A N/A N/A OPEN n S~

1-E21-F030A PART N/A N/A N/A N/A N/A N/A N/A N/A N/A OPEN n strr 1-E21-F029A CLOSED N/A N/A N/A N/A N/A N/A N/A N/A N/A -:r-5 S~

1-E21-F030A CLOSED N/A N/A N/A N/A N/A N/A N/A N/A N/A fS ,s~"'-

1-E21-F003A OPEN N/A N/A N/A N/A N/A N/A N/A N/A N/A 73 .5l/-r NOTE: Spaces next to valve numbers shall be filled in with an appropriate entry, initials, or N/A.

II Performed by (signature) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date _ _ _ _ _ _ _ _ _ __

Performed by (signature) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date _ _ _ _ _ _ _ _ _ __

Reviewed, 1ST Group (signature) Date IOPT-07.2.4a Rev. 58 Page 30 of 361

ATTACHMENT 3 Page 2 of2 Valve Number Stroke Remote Position Stroke Stroke Time Acceptance Direction Indication (Initials) Time Test Criteria (Seconds) Fail- Full- Check Stem Ind. (sec) Acceptable RanQe Ref. Safe Stroke Valve Valve Lights Minimum Maximum Limiting Stroke Test Exercise Exercise SATI

(~) (::;) (:::;) Time (Initials) (Initials) (Initials) UNSAT 2-E21-F015A OPEN N/A N/A N/A N/A N/A N/A N/A N/A 2-E21-F015A CLOSED 36.30 49.10 53.30 42.70 N/A N/A 2-E21-F004A CLOSED 9.38 12.70 13.80 11.04 N/A N/A N/A 2-E21-F005A OPEN 10.20 13.80 15.00 12.00 N/A N/A N/A 2-E21-F005A CLOSED 10.30 13.94 15.15 12.12 N/A N/A 2-E21-F004A OPEN 9.61 13.01 14.14 11.31 N/A N/A 2-E21-F001A CLOSED 70.00 94.60 102.90 82.34 N/A N/A N/A 2-E21-F001A OPEN 67.20 90.80 98.70 79.03 N/A N/A 2-E21-F031A CLOSED 12.20 16.40 17.90 14.33 N/A N/A N/A 2-E21-F031A OPEN 13.10 17.70 19.20 15.41 N/A N/A 2-E21-F003A CLOSED N/A N/A N/A N/A N/A N/A N/A N/A N/A 2-E21-F029A PART N/A N/A N/A N/A N/A N/A N/A N/A N/A OPEN 2-E21-F030A PART N/A N/A N/A N/A N/A N/A N/A N/A N/A OPEN 2-E21-F029A CLOSED N/A N/A N/A N/A N/A N/A N/A N/A N/A 2-E21-F030A CLOSED N/A N/A N/A N/A N/A N/A N/A N/A N/A 2-E21-F003A OPEN N/A N/A N/A N/A N/A N/A N/A N/A N/A NOTE: Spaces next to valve numbers shall be filled in with an appropriate entry, initials, or N/A.

~

Performed by (signature) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date _ _ _ _ _ _ _ _ _ __

Reviewed, 1ST Grou Date OPT-07.2.4a Rev. 58 Page 31 of 36

ATTACHMENT 4 Page 1 of 1 Leak Identification Data Sheet NOTE: For packing and gaskets, a WR is required to be initiated and documented if leakage exceeds 5 dpm.

NOTE: Each WRIWO listed is required to state that identified leakage is to be corrected or minimized as required by TS 5.5.2.

SYSTEM: Core Spray System A Loop Unit _ _ _ __

Leaka~e Component Nature of Leak Rate WRIWO#

Sum of Identified Leakage:

AST Combined Leakage Log value from OAP-054: +

Total: =

1 Conversion Factor: (dpm x 1.6 x 10-3) + 60 =gpm Examination Performed by: _ _ _ _ _ _-.:1_ _ _ _ _ _ _ _ Date _ __

(Signature) (Print Name)

Examination Performed by: _ _ _ _ _ _ _.1_ _ _ _ _ _ _ _ Date _ __

(Signature) (Print Name) 1OPT-07.2.4a Rev. 58 Page 32 of 361

ATTACHMENT 5 Page 1 of 1 Core Spray Pump Pump Vibration Test Position Numbers (Bearing Numbers) 1 1-------1 <,...----------- 2 1 OPT-07.2.4a Rev. 58 Page 33 of 361

ATTACHMENT 6 Page 1 of 2 Leakage Inspection Boundary NOTE: Because of drawing limitations, instrumentation lines connected to boundaries are not shown. The leakage inspection boundary for instrumentation lines extends to and includes the last instrument root valve before the instrument.

NOTE: The Suppression Chamber is NOT required to be examined. It is shown for clarification only 5~ ;- f!j f~ c: 71------1-----,

FllttA' t I'Of3A Y5t I t----l lI-illA Y55 ....:r F015A fOO3At;;y i R12QA YOY fQ~1A fQ10A r----'-.V ~p FOUl<

'OZA

\/1 roOM ~

I OPT-07.2.4a Rev. 58 Pa~~ 34 of 36-1

ATTACHMENT 6 Page 2 of2 Leakage Inspection Guidance When performing leakage inspections for T5 5.5.2, the following guidance should be followed to the extent practical.

1. The leakage inspection should be conducted by examining the accessible exposed surfaces for evidence of leakage.

2. For insulated components or components whose external surfaces are inaccessible for direct inspection, the leakage inspection should be performed on surrounding areas (i.e. floors or equipment surfaces located under the component) for evidence of leakage or other areas to which leakage may be channeled.

3. For vertical surfaces, the inspection of the lowest elevation where leakage may be detected should be performed.

4. For ALARA, a leakage inspection using remote visual equipment or the use of an installed leakage detection system to identify leakage is acceptable.

1 OPT-07 .2.4a Rev. 58 Page 35 of 361

REVISION

SUMMARY

Revision 58 incorporates upgrade of ASME OM Code to 2001 with 2003 Addenda; incorporates Comprehensive Pump Test criteria; incorporates check valve testing of E21-F003A close and E21-F029A130A part open.

Revision 57 incorporates PRR214582 (CaRR 207570-14) and PRR20653 (CaRR 207575-16) program changes to perform a Leakage Walkdown in accordance with TS 5.5.2. Changes include documenting leakage as required for Alternate Source Term (License Amendments 221 and 246 dated May 30, 2002).

Revision 56 adds Step 7.8.33 to vent system as required.

Revision 55 incorporated EC63657 by changing pump flow rate from 4626 to 4700 gpm (steps 6.1.1 and 7.8.10), adding a new step (7.8.23) to increase flow to 5000 gpm, changing Note prior to new step (7.8.23) to 5000 gpm, remove the statement inside the

"( )" in Step 2.13, and changed the 1ST pump psid value to 260.

Revision 54 makes an editorial correction to add the Tech Spec reference to Section 6.3 per NAS Observation 69604 (This reference is already listed in the Purpose Section).

Revision 53 revises the stroke time acceptance criteria for 1-E21-F004A and 1-E21-F005A to reflect the gear ratio change incorporated lAW EC 51210/54126.

Revision 52 makes editorial corrections to update the cover page and word processing format and makes changes to reflect EC 46949, Rev 2, re-evaluation of CS injection valve and pump performance requirements.

Revision 51 revises the stroke time acceptance criteria for 2-E21-F004A and 2-E21-F005A to reflect the gear ratio change incorporated lAW EC 46949/EC 50010.

Revision 50 adds "if performing during a refueling outage" to clarify required testing associated with stroking E21-F015A.

Revision 49 updates stroke time data for 2-E21-F005A iaw the 1ST program; added frequency of each refueling outage for stroking/timing E21-F015A; added NOTES/step informing operators E21-F015A is required to be stroked/timed during refuel outages only and routes procedure users to applicable sections if test is being performed only to test E21-F015A Revision 48 removes reference to specific vibration instrument, IRD Model 890, and replaces with generic reference; Add P&L and caution identifying Core Spray Loop A is inop during valve stroking and until the Loop A low pressure alarm clears.

Revision 47 revises purpose to include Tech Spec Section 5.5.2.a and adds Precaution and Limitations regarding actions if air is found in the system during testing.

1 OPT-07.2.4a Rev. 58 Page 36 of 361

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE A-1B-R/S LESSON TITLE: Evaluate Reactor Water Level Instruments using Caution 1 LESSON NUMBER:

REVISION NO: 0

Evaluate Reactor Water Level Instrumentation using Caution 1 SAFETY CONSIDERATIONS:

None.

IUl 7 II1II1 I II 1 I nunlll l111B RIll IIHUlI II I I 17 EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

3. Task standards (Le. pass/fail criteria) for each JPM step are ITALICIZED below the step.

Page 2 REV. 0

Evaluate Reactor Water Level Instrumentation using Caution 1 Read the following to trainee.

TASK CONDITIONS:

Condition 1 Condition 2 Condition 3 Page 3 REV. 0

Evaluate Reactor Water Level Instrumentation using Caution 1 Condition 4 Condition 5 INITIATING CUE:

Using CAUTION 1 (Unit Two) and the indications provided in:

Condition 1, determine if level instruments N004A1B/C are available or unavailable for use in determining reactor water level.

Condition 2, determine if level instruments N026A1B are available or unavailable for use in determining reactor water level.

Condition 3, determine if level instruments N036/N037 are available or unavailable for use in determining reactor water level.

Condition 4, determine if reactor water level is currently above or below TAF.

Condition 5, determine if reactor water level is currently above or below LL-4.

Provide answer sheet to the examiner upon completion of tasks.

Page 4 REV. 0

Evaluate Reactor Water Level Instrumentation using Caution 1 PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Using the Narrow Range Level Instruments section of CAUTION 1, plot the given parameters of Condition 1 to determine availability of N004A/S/C.

Plot and determine that Condition 1 parameters plot in the UNSAFE Reactor Saturation Limit Curve; plot and determine that*

plot and determine that _ _ .

- CRITICAL STEP** SAT/UNSAT*

Step 2 - Using the Wide Range Level Instruments section of CAUTION 1, plot the given parameters of Condition 2 to determine availability of N026A/S.

Identify that RB 50ft Temperature is above 140F, therefore

- CRITICAL STEP** SAT/UNSAT*

Step 3 - Using the Fuel Zone Level Instruments section of CAUTION 1, plot the given parameters of Condition 3 to determine availability of N036/37.

Plot and determine that Condition 3 parameters in the UNSAFE region of the Reactor Saturation Limit Curve; determine that since it is reading above -130 inches, determine that since it is reading below -130 inches.

- CRITICAL STEP** SAT/UNSAT*

Page 5 REV. 0

Evaluate Reactor Water Level Instrumentation using Caution 1 Step 4 - Using the TAF Determination section of CAUTION 1, plot the given parameters of Condition 4 to determine if reactor water level is above or below TAF.

Plot the parameters of Condition 4 and determine that

- CRITICAL STEP** SAT/UNSAT*

Step 5 - Using the LL-4 Determination section of CAUTION 1, plot the given parameters of Condition 5 to determine if reactor water level is above or below LL-4.

Plot the parameters of Condition 5 and determine that

- CRITICAL STEP** SATIUNSAT*

Comments required for any step evaluated as UNSAT.

Page 6 REV. 0

Evaluate Reactor Water Level Instrumentation using Caution 1 RELATED TASKS:

KIA REFERENCE AND IMPORTANCE RATING:

GEN 2.1.25 3.9/4.2 Ability to interpret reference materials, such as graphs, curves, tables, etc.

REFERENCES:

Unit 2 CAUTION 1 TOOLS AND EQUIPMENT:

None.

ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2, Supp. 1.):

Admin - Conduct of Operations Page 7 REV. 0

Evaluate Reactor Water Level Instrumentation using Caution 1 Time Required for Completion: ~ Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit:

Setting: Control Room Simulator__ ( Not applicable to In-Plant JPMs )

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X I IIilIU 1m u IHHUI?

EVALUATION Trainee:

SSN:

JPM: Pass ____ Fail ____

Remedial Training Required: Yes No ____

Did Trainee Verify Procedure Current?: Yes No _____

Comments:

Comments reviewed with Student Evaluator Signature: ______________________ Date: _______

Page 8 REV. 0

TASK CONDITIONS:

Condition 1 Condition 2 Reactor Water Level 5 inches Reactor Water Level 15 inches Reactor Pressure 950 1258-1 210F 1258-3 225F 1258-2 215F 1258-2 207F 150F Condition 3 Reactor Water Level Reactor Water Level Reactor Pressure 1258-1 Condition 4

-40 inches 600 220F OFF Condition 5 INITIATING CUE:

Using CAUTION 1 (Unit Two) and the indications provided in:

Condition 1, determine if level instruments N004A1B/C are available or unavailable for use in determining reactor water level.

Condition 2, determine if level instruments N026A/B are available or unavailable for use in determining reactor water level.

Condition 3, determine if level instruments N036/N037 are available or unavailable for use in determining reactor water level.

Condition 4, determine if reactor water level is currently above or below TAF.

Condition 5, determine if reactor water level is currently above or below LL-4.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE A-2-R LESSON TITLE: Determination of Drywell Volumetric Average Temperature Per OPT-16.2 LESSON NUMBER: LOT-OJT-JP-201-D09 REVISION NO: 2

Determination of Drywell Volumetric Average Temperature SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. This JPM is performed in the simulator.

2. Ensure all simulator computer screens are OFF prior to commencing JPM

3. Reset the simulator to IC-11.

4. Input the following point values into CAC-TR-4426-1A11 B/2A12B

Div 2A (Channel 3) -5823 40.0

Div 2A (Channel 4) -5824 185.5

Div 1A (Channel 4) -5822 185.5

Div 2B (Channel 1) -5802 174.1

Div 1B (Channel 2) -5803 168.3

Div 2B (Channel 2) -5804 162.6

Div 1B (Channel 3) -5805 139.3

Div 2B (Channel 3) -5806 136.8

Div 1B (Channel 4) -5807 133.5

Div 2B (Channel 4) -5808 40.0

Div 1B (Channel 5) -5808 124.5

Div 1A (Channel 4) -5808 121.6

Div 2B (Channel 6) -5808 119.2

Div 1A (Channel 5) -5817 88.7

Div 1A (Channel 6) -5818 40.0

Div 2A (Channel 5) -5819 88.7

Div 2A (Channel 6) -5820 88.7

5. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

6. The trainee will need a calculator to perform this JPM.

7. The trainee will be given a copy of OPT-16.2.

8. Task standards (Le. pass/fail criteria) for each JPM step are ITALICIZED below the step.

LOT-OJT-JP-201-D09 Page 2 of 11

Determination of Drywell Volumetric Average Temperature Read the following to trainee.

TASK CONDITIONS:

1. Drywell air RTDs CAC-TE-1258-8, CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable due to erratic indication.

2. An LCO has been established that requires the performance of OPT-16.2, Drywell Volumetric Average Temperature, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3. The CAC-TY-4426-1 and 2 Microprocessors could not be physically accessed due to work in the back panel area.

4. The Process Computer is not available due to maintenance activities.

5. ERFIS is temporarily off-line.

6. This is the 15th day of the month.

7. You have been granted permission by the Unit SCO to perform this test.

INITIATING CUE:

You have been directed by the Unit SCO to perform OPT-16.2, Drywell Volumetric Average Temperature.

When the test is complete, determine if the test acceptance criteria has been met.

Report the test results to the examiner.

LOT-OJT-JP-20 1-D09 Page 3 of 11

Determination of Drywell Volumetric Average Temperature PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain drywell temperature readings for the locations listed in step 7.2.1 Records the following readings:

4426-2A Channel 3 - INOP 4426-2A Channel 4 - 185.5 (+Q.1) 4426-1A Channel 4 - 185.5 (+Q.1)

SAT/UNSAT*

Step 2 - Add step 7.2.1 recorded temperatures and record in step 7.2.2 185.5 (+Q.1) and 185.5 (+Q.1) added totaling 371.0 (+Q.2) and documented in step 7.2.2 SATIUNSAT*

Step 3 - Divide total obtained in step 7.2.2 by the number of temperatures used 371.0 (+Q.2) divided by 2 equaling 185.5 (!0.1) and documented in step 7.2.3

- CRITICAL STEP** SAT/UNSAT*

Step 4 - Obtain drywell temperature readings for the locations listed in step 7.3.1 Records the following readings:

4426-28 Channel 1 - 174.1 (+Q.1) 4426-18 Channel 2 - 168.3 (+Q.1) 4426-28 Channel 2 - 162.6 (+Q.1)

SAT/UNSAT*

LOT-OJT-JP-201-D09 Page 4 of 11

Determination of Drywell Volumetric Average Temperature Step 5 - Add step 7.3.1 recorded temperatures and record in step 7.3.2 174.1 (+Q.1), 168.3 (+Q.1) and 162.6 (+Q.1) added totaling 505.0 (+Q.3) and documented in step 7.3.2 SAT/UNSAT*

Step 6 - Divide total obtained in step 7.3.2 by the number of temperatures used 505.0 (+Q.3) divided by 3 equaling 168.3 (+/-0.1) and documented in step 7.3.3

- CRITICAL STEP** SAT/UNSAT*

Step 7 - Obtain drywell temperature readings for the locations listed in step 7.4.1 Records the following readings:

4426-18 Channe/3 - 139.3 (+Q.1) 4426-28 Channel 3 - 136.8 (+Q.1) 4426-18 Channel 4 - 133.5 (+Q.1) 4426-28 Channel 4 - INOP SAT/UNSAT*

Step 8 - Add step 7.4.1 recorded temperatures and record in step 7.4.2 139.3 (+Q.1), 136.8 (+Q.1) and 133.5 (+Q.1) added totaling 409.6 (+Q.3) and documented in step 7.4.2 SAT/UNSAT*

Step 9 - Divide total obtained in step 7.4.2 by the number of temperatures used 409.6 (+Q.3) divided by 3 equaling 136.5 (+/-0.1) and documented in step 7.4.3

- CRITICAL STEP** SAT/UNSAT*

LOT-OJT-J P-20 1-D09 Page 5 of 11

Determination of Drywell Volumetric Average Temperature Step 10- Obtain drywell temperature readings for the locations listed in step 7.5.1 Records the following readings:

4426-18 Channel 5 - 124.5 (+Q.1) 4426-1A Channel 3 - 121.6 (+Q.1) 4426-28 Channel 6 - 119.2 (+Q. 1)

SAT/UNSAT*

Step 11 - Add step 7.5.1 recorded temperatures and record in step 7.5.2 124.5 (+Q.1), 121.6 (+Q.1) and 119.2 (+Q.1) added totaling 365.3 (+Q.3) and documented in step 7.5.2 SAT/UNSAT*

Step 12 - Divide total obtained in step 7.5.2 by the number of temperatures used 365.3 (+Q.3) divided by 3 equaling 121.8 (:!:.O.1) and documented in step 7.5.3

- CRITICAL STEP** SAT/UNSAT*

Step 13 - Obtain drywell temperature readings for the locations listed in step 7.6.1 Records the following readings:

4426-1A Channel 5 - 88.7 (+Q.1) 4426-1 A Channel 6 - INOP 4426-2A Channel 5 - 88.7 (+Q.1) 4426-2A Channel 6 - 88.7 (+Q.1)

SAT/UNSAT*

Step 14 - Add step 7.6.1 recorded temperatures and record in step 7.6.2 88.7 (+Q.1), 88.7 (+Q.1) and 88.7 (+Q.1) added totaling 266.1 (+Q.3) and documented in step 7.6.2 SAT/UNSAT*

LOT-OJT-J P-20 1-D09 Page 6 of 11

Determination of Drywell Volumetric Average Temperature Step 15 - Divide total obtained in step 7.6.2 by the number of temperatures used 266.1 (+Q.3) divided by 3 equaling 88.7 (:!:.O.1) and documented in step 7.6.3

- CRITICAL STEP** SAT/UNSAT*

Step 16 - Transfer average readings documented in steps 7.2.3,7.3.3,7.4.3,7.5.3 and 7.6.3 into step 7.7.1 188.5 (+Q.1), 168.3 (+Q.1), 136.5 (+Q.1), 121.8 (+Q.1), and 88.7 (+Q.1) transferred into step 7.7. 1 SAT/UNSAT*

Step 17 - Multiply each reading in 7.7.1 by the designated factor and document in step 7.7.1 9.3 (+Q.1), 15.1 (+Q.1), 54.6 (+Q.1), 46.3 (+Q.1), and 7.1 (+Q.1) documented in step 7.7.1

- CRITICAL STEP** SAT/UNSAT*

Step 18 - Add weighted averages in step 7.7.1 and document as TOTAL in step 7.7.1.6 9.3 (+Q.1), 15.1 (+Q.1), 54.6 (+Q.1), 46.3 (+Q.1), and 7.1 (+Q.1) added totaling 132.5 (:!:.O.5) and documented in step 7.7.1

- CRITICAL STEP** SATIUNSAT*

LOT-OJT-J P-20 1-D09 Page 7 of 11

Determination of Drywell Volumetric Average Temperature Step 19 - Record computer point C074 value in step 7.7.2 Step 7.7.2 marked NIA due to unavailability SAT/UNSAT*

Step 20 - Perform steps 7.7.3 and 7.7.4 Step 7.7.3 and 7.7.4 marked NIA (not required)

SAT/UNSAT*

Step 21 - Perform step 7.7.5 Cover page information verified complete SAT/UNSAT*

Step 22 - Determine whether the test is SAT or UNSAT based on the cue sheet instructions Applicant determines the test is SAT because calculated Orywel/ Avg Air Temp (132.5 :!O.5) is less than 150F (acceptance criteria)

- CRITICAL STEP** SAT/UNSAT*

Step 23 - Perform step 7.7.6 Unit SeQ notified test is complete SATIUNSAT*

Comments required for any step evaluated as UNSAT.

LOT-OJT-JP-201-D09 . Page 8 of 11

Determination of Drywell Volumetric Average Temperature LIST OF REFERENCES RELATED TASKS:

223*206*81 *01 KIA REFERENCE AND IMPORTANCE RATING:

GEN 2.2.12 3.7/4.1 Knowledge of Surveillance Procedures

REFERENCES:

OPT-16.2 Drywell Volumetric Average Temperature TOOLS AND EQUIPMENT:

Calculator ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2. Supplement 1):

Admin - Equipment Control LOT-OJT-J P-20 1-009 Page 9 of 11

Determination of Drywell Volumetric Average Temperature Time Required for Completion: 20 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit: 2 Setting: Control Room Simulator__ (Not applicable to In-Plant JPMs)

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee: _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass _ _ Fail Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure as Authorized Copy?: Yes _ _ No - - -

(Each Student should verify one JPM per evaluation set.)

Comments:

Comments reviewed with Student Evaluator Signature: Date: _ _ _ __

LOT-OJT-JP-201-D09 Page 10 of 11

TASK CONDITIONS:

1. Drywell air RTDs CAC-TE-1258-8, CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable due to erratic indication.

2. An LCa has been established that requires the performance of OPT-16.2, Drywell Volumetric Average Temperature, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3. The CAC-TY-4426-1 and 2 Microprocessors could not be physically accessed due to work in the back panel area.

4. The Process Computer is not available due to maintenance activities.

5. ERFIS is temporarily off-line.

6. This is the 15th day of the month.

7. You have been granted permission by the Unit sca to perform this test.

INITIATING CUE:

You have been directed by the Unit sca to perform OPT-16.2, Drywell Volumetric Average Temperature.

When the test is complete, determine if the test acceptance criteria has been met.

Report the test results to the examiner.

BRUNSWICK NUCLEAR PLANT c

Continuous Use DATE COMPLETED _.L.l1 Q..a.J~C\~V

_ _ _-::--:--:-_ FREQUENCY:

UNIT ~ % PWR (tJO r GMWE q )".a Once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when at least one SPTMS SUPERVISOR.---':-"'-J..;... _________

....;D~se air RTD is inoperable in each division of SPTMS REASON FOR TEST (check one or more): and the unit is in Mode 1, 2, or 3.

_ Routine surveillance

=z WO#

Other (-ex-p-Ia-in-)-tc':"'"""'""f)-.3-.-b~-----

PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT o

OPT-16.2 DRYWELL VOLUMETRIC AVERAGE TEMPERATURE REVISION 34 IOPT-16.2 Rev. 34 Page 1 of 121

1.0 PURPOSE 1.1 This test is performed to determine the operability of the drywell in conformance with the requirements specified in Technical Specification SR 3.6.1.4.1.

1.2 This test involves averaging air temperatures within the drywell.

2.0 REFERENCES

2.1 Technical Specifications 2.2 FSAR, Section 6.2 2.3 System Description SD-24, Containment Atmosphere Control System 2.4 EER 93-578 (SPTMS Air RTD Divisions/Channels Defined) 2.5 2SP-95-208, Temperature Measurement for SPTMS RTD 2.6 ESR 98-00387, Rev. 0, TS Change to ContainmentlDrywell Air Temperature Requirements 3.0 PREREQUISITES None Applicable 4.0 PRECAUTIONS AND LIMITATIONS None Applicable 5.0 SPECIAL TOOLS AND EQUIPMENT Calculator 6.0 ACCEPTANCE CRITERIA This test may be considered satisfactory when the drywell volumetric average temperature is less than or equal to 150°F.

IOPT-16.2 Rev. 34 Page 2 of 121

7.0 PROCEDURAL STEPS Initials 7.1 OBTAIN permission from Unit Senior Control Operator (SCO) to perform this test.

NOTE: Figure 1 may be used as a worksheet but is NOT required to be retained with this PT.

NOTE: All temperatures used in this procedure should be rounded off to the nearest tenth of a degree.

NOTE: Primary containment temperatures may be obtained from the CAC-TY-4426-1 (2) microprocessor per OP-24, Operator Interface With The SPTMS Microprocessors, from the recorders in the Control Room, from ERFIS display screens 740 and 745 of the Validation Menu; or as a backup method, the designated process computer pOints may be used.

Microprocessor pOint values may also be obtained by I&C manually taking temperature measurements of SPTMS RTDs.

NOTE: Technical Specifications requires at least one operable temperature detector in each channel for each location.

IOPT-16.2 Rev. 34 Page 3 of 121

7.0 PROCEDURAL STEPS Initials 7.2 90' Elevation And Above 7.2.1 OBTAIN drywell temperature for the locations listed below AND RECORD in the spaces provided.

Recorder/ERFIS Display SPTMS CHAN PPC 4426-2A Channel 3 _ __ (5823) _ _ II N/A 4426-2A Channel 4 - - - (5824) _ _ II N/A 4426-1 A Channel 4 _ __ (5822) _ _ I N/A 7.2.2 ADD the recorded temperatures AND RECORD the total in the following space:

_ _ _ _ _ _ _ _ _ _ - Recorder/ERFIS display total

_ _ _ _ _ _ _ _ _ _ - SPTMS total 7.2.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 90' elevation and above in the following space:

- - - - - _ ..... _ - - - - - - = - - - - - -

total no. of temperatures average IOPT-16.2 Rev. 34 Page 4 of 121

7.0 PROCEDURAL STEPS Initials 7.3 Between 70' And 80' Elevation 7.3.1 OBTAIN drywell temperatures for the locations listed below AND RECORD in the spaces provided.

Recorder/ERFIS Display SPTMS CHAN PPC 4426-2B Channel 1 (5802)_ _ II W109 _ _ _ __

4426-1 B Channel 2 _ __ (5803) _ _ I F148 _ _ _ __

4426-2B Channel 2 _ __ (5804) _ _ II W110 _ _ _ __

NOTE: Notify BESS duty manager if any temperatures between 70' and 80' elevation exceed 240°F.

7.3.2 ADD the recorded temperatures AND RECORD the total in the following spaces:

_ _ _ _ _ _ _ _ _ - Recorder/ERFIS display total

_ _ _ _ _ _ _ _ _ - SPTMS total

_ _ _ _ _ _ _ _ _ - PPC total 7.3.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 70' - 80' elevation in the following space:

+------ =- - - - - -

total no. of temperatures average IOPT-16.2 Rev. 34 Page 5 of 121

7.0 PROCEDURAL STEPS Initials 7.4 Between 28' And 45' Elevation 7.4.1 OBTAIN drywell temperatures for the locations listed below AND RECORD in the spaces provided.

Recorder/ERFIS Display SPTMS CHAN PPC 4426-1BChanne13 (5805) I F149 4426-2B Channel 3 (5806) II W085 4426-1 B Channel 4 (5807) I F150 4426-2B Channel 4 (5808) II W086 7.4.2 ADD the recorded temperatures AND RECORD the total in the following spaces:

_ _ _ _ _ _ _ _ _ - Recorder/ERFIS display total

_ _ _ _ _ _ _ _ _ - SPTMS total

_ _ _ _ _ _ _ _ _ - PPC total 7.4.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 28' - 45' elevation in the following space:

_ _ _ _ _ "T" _ _ _ _ _ _ _ = _ _ _ __

total no. of temperatures average 7.5 Between 10' And 23' Elevation 7.5.1 OBTAIN drywell temperatures for the locations listed below AND RECORD in the spaces provided.

Recorder/ERFIS Display SPTMS CHAN PPC 4426-1 B Channel 5 _ __ (5809) _ _ F151 _ _ _ __

4426-1A Channel 3 _ __ (5812) _ _ W105 _ _ _ __

4426-2B Channel 6 - - - (5813) _ _ II W088 _ _ _ __

IOPT-16.2 Rev. 34 Page 6 of 121

7.0 PROCEDURAL STEPS Initials 7.5.2 ADD the recorded temperatures AND RECORD the total in the following spaces:

_ _ _ _ _ _ _ _ _ - Recorder/ERFIS display total

_ _ _ _ _ _ _ _ _ - SPTMS total

- PPC total 7.5.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 10' - 23' elevation in the following space:

+--------=--------

total no. of temperatures average 7.6 Below 5' Elevation 7.6.1 OBTAIN primary containment temperatures for the locations listed below AND RECORD in the spaces provided.

Recorder/ERFIS Display SPTMS CHAN 4426-1A Channel 5 _ __ (5817)_ _ I W106 _________

4426-1A Channel 6 _ __ (5818) _ _ W107 _________

4426-2A Channel 5 _ __ (5819) _ _ II W115 _________

4426-2A Channel 6 _ __ (5820) _ _ II W116 _________

CAUTION Ifmicropro¢~ssorj~ Use.d tdXo~fain data,fairure to rest6remode selectbr switoh' to the ERFIS (J'J()~MAJi).positiqnWill.eause lass of SPTMSindications on the ERFIS C~>Iltrol Room dJS'pl~Ys~.* . .

7.6.2 ADD the recorded temperatures AND RECORD the total in the following spaces:

_ _ _ _ _ _ _ _ _ - Recorder/ERFIS display total

_ _ _ _ _ _ _ _ _ - SPTMS total

_ _ _ _ _ _ _ _ _ - PPC total IOPT-16.2 Rev. 34 Page 7 of 121

7.0 PROCEDURAL STEPS Initials 7.6.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the below 5' elevation in the following space:

+ ------- =-----

total no. of temperatures average NOTE: The total in Step 7.7.1.6 is the volumetric average temperature for the drywell. If this temperature is greater than 150°F, actions should be taken as required by Technical Specification SR 3.6.1.4.1.

7.7 Volumetric Average 7.7.1 DETERMINE the volumetric average temperature by performing the following calculations:

1. Average above 90' elevation x 0.05 =_ _ __

Step 7.2.3

2. Average 70' - 80' elevation x 0.09 =_ _ __

Step 7.3.3

3. Average 28' - 45' elevation x 0.40 =_ _ __

Step 7.4.3

4. Average 10' - 23' elevation x 0.38 =_ _ __

Step 7.5.3

5. Average below 5' elevation x 0.08 =____

Step 7.6.3

6. Total _ _ _ _ _ _ _ _ _ _ _ __

Steps 7.7.1.1 through 7.7.1.5 IOPT-16.2 Rev. 34 Page 8 of 121

7.0 PROCEDURAL STEPS Initials NOTE: Computer point C074 may only be used to satisfy EQP concerns and may NOT be used to satisfy Technical Specifications.

7.7.2 RECORD computer point C074 value (for information).

C074 _ _ _ __

NOTE: Performance of Steps 7.7.3 and 7.7.4 is only required once a month (perform on the first day of the month).

7.7.3 SUBTRACT the value obtained in Step 7.7.2 from the value obtained in Step 7.7.1.6.

=

Step 7.7.1.6 Step 7.7.2 Difference 7.7.4 IF the absolute value of the difference obtained in Step 7.7.3 is greater than 10°F, THEN ENSURE that Unit SCQ is informed of the discrepancies in the computer point reading (EQP concern).

7.7.5 ENSURE required information has been recorded on the cover page.

7.7.6 NOTIFY Unit SCQ when this test is complete or found to be unsatisfactory.

IOPT-16.2 Rev. 34 Page 9 of 121

ATTACHMENT 1 Page 1 of 1 Certification and Review Form General Comments and Recommendations _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Initials Name (Print)

Performed by:

Exceptions to satisfactory performance _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Corrective action required _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Test procedure has been satisfactorily completed:

Unit SCD: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Signature Date Test procedure has NOT been satisfactorily completed:

Unit SCD: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Signature Date Test has b.een reviewed by:

Shift Superintendent: _ _ _ _ _ _ _ _ _ _ _ __

Signature Date IOPT-16.2 Rev. 34 Page 10 of 121

FIGURE 1 Page 1 of 1 Containment Temperature Worksheet TIME 4426-2A (Channel 3)-5823 _ _ _ 0.05 4426-2A (Channel 4)-5824 4426-1A (Channel 4)-5822 4426-2B (Channel 1)-5802 4426-1 B (Channel 2)-5803 _ _ _ 0.09 4426-2B (Channel 2)-5804 4426-1 B (Channel 3)-5805 4426-2B (Channel 3)-5806 4426-1B (Channel 4)-5807 _ _ _ 0.40 4426-2B (Channel 4)-5808 4426-1 B (Channel 5)-5809 4426-1A (Channel 3)-5812 _ _ _ 0.38 4426-2B (Channel 6)-5813 4426-1A (Channel 5)-5817 4426-1A (Channel 6)-5818 _ _ _ 0.08 4426-2A (Channel 5)-5819 4426-2A (Channel 6)-5820 AVERAGE TEMPERATURE 1 OPT-16.2 I Rev. 34 ------- Page 11 of 121

REVISION

SUMMARY

Revision 34 restores 2CAC-TE-1258-20 (4426-2A [channel 6]-5820) that was temporarily removed lAW EC 63061.

Revision 33 incorporates temporary change EC 63061 which temporarily disables temperature indication 2CAC-TE-1258-20 (4426-2A [channel 6]-5820).

Revision 32- Removes the Unit Specific items and associated notes that were added per Temporary Plant Modification ESR 99-00485. Temperature Sensor 2-CAC-TE-1258-22 has been repaired during the refuel outage. This revision also revises terminology for PassPort Implementation.

Revision 31 - This revision removes the notes that specified equivalencies during implementation of ESRs 97-00125 and 97-00051, and changed points A, B, C, D, E, &

F to channel 1, 2, 3, 4, 5, & 6.

IOPT-16.2 Rev. 34 Page 12 of 121

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE A-2-S LESSON TITLE: Evaluate a Clearance Request - CRD Pump 2A.

LESSON NUMBER: LOT-OJT-JP-201-E01 REVISION NO: 01

Evaluate a Clearance Request - 2A CRD Pump.

SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable prints 0-02516 SH1A & 18, 0-02538 SH2, LL-09113 SH32, and Attachments 2

& 4 of OPS-NGGC-1301 WILL be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

3. The attached forms from OPS-NGGC-1301 are intended to provide a guide to the evaluator and are NOT to be given to the examinee. Attachments 2 & 4 of OPS-NGGC-130 1 should be filled out using actual copies of forms from OPS-NGGC-1301 and given to the examinee.

4. The evaluator should have available copies of valve lineups from 20P-08 & 21 to support performance of JPM if the examinee asks for them.

5. Task standards (Le. pass/fail criteria) for each JPM step are ITALICIZED below the step.

I l1li I I I II VI F IV II II l1li1111 'l1li 1111 Read the following to trainee.

TASK CONDITIONS:

1. You are an operator in the Work Control Center. Passport is not available for use.

2. Maintenance has prepared a Clearance Request to place CRO Pump 2A under clearance for scheduled work. CRO Pump 28 will be running.

3. This clearance is to allow maintenance to perform two WOs.

a. The first WO is to allow maintenance to sample lube oil on CRO Pump 2A motor bearings and speed changer, and to inspect the seal cooling water lines (requires breaking flanges on cooling water lines at the pump).

b. The second WO is to lift the pump so the pump feet can be honed due to high vibration (requires breaking flanges at the pump).

INITIATING CUE:

The WCC SRO directs you to evaluate the attached Clearance Request Form (Attachment 2 of OPS-NGGC-1301) and proposed Clearance Checklist (Attachment 4 of OPS-NGGC-1301) and determine the adequacy of the clearance boundary, and inform him if the proposed clearance is adequate.

LOT-ADM-JP-201-E01 Page 2 of 12 Rev. 01

Evaluate a Clearance Request - 2A CRD Pump.

ATTACHMENT 2 Sheet 1 of 1 Clearance Request Form To be completed by the Requestor. (Please print.)

A. Name Mechanic Supervisor Ext. No. 0000 Work Group Z73 (Mechanical Maintenance) Date: Yesterday B. (1) Unit #--L (2) System # 2-C12 (3) Equipment to be cleared 2-C12-C001A. CRD Pump 2A C. Clearance Specifications Fluid Boundary System Depressurized and Drained Power Supply breaker racked out/off D. Reference drawings and procedures (attach list if necessary) 0-02516 SH1A & 1B, 0-02538 SH2, LL-09113 SH32, 20P-08, 20P-21 E. Special requests, precautions, and prerequisites Need SS Waiver of 2 isolation valve requirement F. Date/Time Needed Today / ASAP or Event LOT-ADM-J P-20 1-EO 1 Page 3 of 12 Rev. 01

Evaluate a Clearance Request - 2A CRD Pump.

ATTACHMENT 4 Sheet 1 of 1 Operations Clearance Checklist Clearance No. Admin JPM Page _1_ of _1_

Checklist Type: Hang INT NAME (PRINT) INT NAME (PRINT)

Independent Verification Required? YES If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed. Verified By By 1 Hang CIT 1 INFTAH RTGB Control Switch 2-C12-CS-Z4A 2 Hang Red 2 RACOR Motor Feeder 2-E3-AI2 3 Hang Red 3 CLOLOC Discharge Valve 2-C12-F014A 4 Hang Red 4 CLOLOC Recirc Valve 2-C12-F015A 5 Hang Red 5 CLOLOC Suction Valve 2-C12-F013A 6 Hang Red 6 Closed Cooling Inlet Valve 2-RCC-V295 7 Hang Red 7 Closed Cooling Outlet Valve 2-RCC-V7 8 Hang CIT 8 Closed Pump Drain Valve 2-C12-V45 9 Hang Red 9 Open Casing Vent Valve 2-C12-F1 09A LOT-ADM-JP-201-E01 Page 4 of 12 Rev. 01

Evaluate a Clearance Request - 2A CRD Pump.

PERFORMANCE CHECKLIST NOTE: Steps are listed in a logical order, but may be performed in any order.

Step 1 - May obtain a current revision of OPS-NGGC-1301.

Current Revision of OPS-NGGC-1301 obtained.

SAT/UNSAT*

Step 2 - Evaluates CIT INFTAH Tag for the RTGB Control Switch 2-C12-CS-Z4A.

Determines no deficiencies for the info tag.

SAT/UNSAT*

Step 3 - Evaluates Red RACOR Tag for the Motor Feeder 2-E3-AI2.

Identifies deficiency for the breaker number, which should be 2-E3-AJ2.

- CRITICAL STEP ** SAT/UNSAT*

Step 4 - Evaluates Red CLOLOC Tag for the Discharge Valve 2-C12-F014A.

Determines no deficiencies for the locked closed tag.

SAT/UNSAT*

Step 5 - Evaluates Red CLOLOC Tag for the Recirc Valve 2-C12-F015A.

Determines no deficiencies for the locked closed tag.

SAT/UNSAT*

Step 6 - Evaluates Red CLOLOC Tag for the Suction Valve 2-C12-F013A.

Determines no deficiencies for the locked closed tag.

SAT/UNSAT*

Step 7 - Evaluates Red Closed Tag for the Cooling Inlet Valve 2-RCC-V295.

Identifies wrong valve listed, Valve should be 2-RCC-V294.

- CRITICAL STEP ** SAT/UNSAT*

LOT-ADM-JP-201-E01 Page 5 of 12 Rev. 01

Evaluate a Clearance Request - 2A CRD Pump.

Step 8 - Evaluates Red Closed Tag for the Cooling Outlet Valve 2-RCC-V7.

Identifies wrong valve listed, Valve should be 2-RCC-VB.

- CRITICAL STEP ** SAT/UNSAT*

Step 9 - Evaluates CIT Closed Tag for the Pump Drain Valve 2-C12-V45.

Determines the tag should be a RED tag and the valve position should be OPEN.

- CRITICAL STEP ** SATIUNSAT*

Step 10 - Evaluates Red Open Tag for the Casing Vent Valve 2-C12-F109A.

Determines no deficiencies for the open tag.

SAT/UNSAT*

Step 11 - Identify the positive seal line isolation valve not included in boundary request.

Determine positive seal pressure valve (2-C12-F017) should be added.

(Red Closed Tag sequenced anywhere after the breaker but before the Drain Valve).

- CRITICAL STEP ** SAT/UNSAT*

Step 12 - Evaluates Sequence of the steps of the clearance.

Determines no deficiencies for the sequence.

SAT/UNSAT*

Step 13 - Inform WCC SRO of results._

WCC SRO informed that the clearance is UNSAT as written for the following reasons:

Feed breaker ID#

Incorrect RCC inlet valve listed

Incorrect outlet valve listed

Incorrect drain valve tag type and position

Positive seal pressure valve not listed SAT/UNSAT*

LOT-ADM-JP-201-E01 Page 6 of 12 Rev. 01

Evaluate a Clearance Request - 2A CRD Pump.

Corrected Clearance Seq Action Type Tagld Position Equipment/Component Completed. Verified By By Hang CIT INFTAH RTGB Control Switch 2-C12-CS-Z4A Motor Feeder 2-E3-AI2 2 Hang Red 2 RACOR 3 Hang Red 3 CLOLOC Discharge Valve 2-C12-F014A 4 Hang Red 4 CLOLOC Recirc Valve 2-C12-F015A 5 Hang Red 5 CLOLOC Suction Valve 2-C12-F013A Cooling Inlet Valve 2-RCC-V295 6 Hang Red 6 Closed 7 Hang Red 7 Closed I III CIT I lIB Closed Pump Drain Valve 2-C12-V45 9 Hang 9 III 10 Hang Red 10 Open Casing Vent Valve 2-C12-F109A LOT-ADM-JP-201-E01 Page 7 of 12 Rev. 01

Evaluate a Clearance Request - 2A CRD Pump.

RELATED TASKS:

2990208301, Develop A Clearance Per OPS-NGGC-1301 KIA REFERENCE AND IMPORTANCE RATING:

Generic 2.2.13 4.1/4.3 Knowledge of tagging and clearance procedures

REFERENCES:

OPS-NGGC-1301 TOOLS AND EQUIPMENT:

Referenced prints and OP lineups.

ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2. Supp. 1):

Admin - Equipment Control LOT-ADM-JP-201-E01 Page 8 of 12 Rev. 01

Evaluate a Clearance Request - 2A CRD Pump.

Time Required for Completion: ~ Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit: 2 Setting: Control Room X Simulator__ ( Not applicable to In-Plant JPMs )

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass _ _ Fail Remedial Training Required: Yes No Did Trainee Verify Procedure Revision?: Yes No _ __

( Each Student should verify one JPM per evaluation set. )

Comments:

Comments reviewed with Student Evaluator Signature: Date: _ _ _ _ __

LOT-ADM-JP-201-E01 Page 9 of 12 Rev. 01

TASK CONDITIONS:

1) You are an operator in the Work Control Center. Passport is not available for use.

2) Maintenance has prepared a Clearance Request to place CRD Pump 2A under clearance for scheduled work. CRD Pump 2B will be running.

3) This clearance is to allow maintenance to perform two WOs.

a) The first WO is to allow maintenance to sample lube oil on CRD Pump 2A motor bearings and speed changer, and to inspect the seal cooling water lines (requires breaking flanges on cooling water lines at the pump).

b) The second WO is to lift the pump so the pump feet can be honed due to high vibration (requires breaking flanges at the pump).

INITIATING CUE:

The WCC SRO directs you to evaluate the attached Clearance Request Form (Attachment 2 of OPS-NGGC-1301) and proposed Clearance Checklist (Attachment 4 of OPS-NGGC-1301) and determine the adequacy of the clearance boundary, and inform him if the proposed clearance is adequate.

ATTACHMENT 2 Sheet 1 of 1 Clearance Request Form To be completed by the Requestor. (Please print.)

A. Name Mechanic Supervisor Ext. No. 0000 Work Group Z73 (Mechanical Maintenance) Date: Yesterday B. (1 ) Unit# ....L (4) System # 2-C12 (5) Equipment to be cleared 2-C12-C001A. CRD Pump 2A C. Clearance Specifications Fluid Boundary System Depressurized and Drained Power Supply breaker racked out/off D. Reference drawings and procedures (attach list if necessary) 0-02516 SH1A & 1B, 0-02538 SH2, LL-09113 SH32, 20P-08, 20P-21 E. Special requests, precautions, and prerequisites Need SS Waiver of 2 isolation valve requirement F. Date/Time Needed Today / ASAP or Event -------------------

ATTACHMENT 4 Sheet 1 of 1 Operations Clearance Checklist Clearance No. Admin JPM Page _1_ of _1_

Checklist Type: Hang INT NAME (PRINT) INT NAME (PRINT)

Independent Verification Required? YES If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed. Verified By By 1 Hang CIT 1 INFTAH RTGB Control Switch 2-C12-CS-Z4A 2 Hang Red 2 RACOR Motor Feeder 2-E3-AI2 3 Hang Red 3 CLOLOC Discharge Valve 2-C12-F014A 4 Hang Red 4 CLOLOC Recirc Valve 2-C12-F015A 5 Hang Red 5 CLOLOC Suction Valve 2-C12-F013A 6 Hang Red 6 Closed Cooling Inlet Valve 2-RCC-V295 7 Hang Red 7 Closed Cooling Outlet Valve 2-RCC-V7 8 Hang CIT 8 Closed Pump Drain Valve 2-C12-V45 9 Hang Red 9 Open Casing Vent Valve 2-C12-F109A

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE A-3-RlS LESSON TITLE: Determine Stay Time limitations for performing work in a High Radiation Area LESSON NUMBER:

REVISION NO: 01

SAFETY CONSIDERATIONS:

None.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.

2. Task standards (Le. pass/fail criteria) for each JPM step are ITALICIZED below each step.

TASK CONDITIONS:

Two workers will be performing a lube check and coupling alignment on the Unit Two (2)

RWCU Pump 2A.

Worker #1 has accumulated 600 mrem this year.

Worker #2 has accumulated 670 mrem this year.

The elevator is out of service The following times for each worker have been estimated for performance of the job.

1. Traversing Southeast stairwell 20' - 50' Rx Bldg 6 minutes

2. Staging time in access area directly outside the RWCU room 15 minutes

3. Staging time in area directly inside room access door 15 minutes

4. Work time at the "A" RWCU pump 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

5. Following completion of the job, an additional 25 mrem per worker will be received during de-staging activities and transit back to the maintenance shop.

INITIATING CUE:

Using the information above and the provided radiological survey using best ALARA practices:

1. Determine the total dose accumulated for both workers. (assume the same task times for both workers)

2. Determine if any Brunswick Administrative dose limitations will be exceeded.

PERFORMANCE CHECKLIST NOTE: Provide the examinee the attached survey map. Each substep is a CRITICAL STEP.

Step 1 - Determines dose for each worker as follows:

a. Traversing SE stairwell 20' - 50' Rx Bldg (SE is the lowest dose stairwell)

(6 min) O. 1 Hr X 5 mrlhr = .5 mrem

~re Estimate 0.5 mrem dose accumulation **CRITICAL f;iK**

SAT/UNSAT

b. Staging time in access area directly outside the RWCU room (15 min) 0.25 Hr X 20 mrlhr =5 mrem

~11fJ Estimate 5 mrem dose accumulation. **CRITICAL T~**

SAT/UNSAT

c. Staging time in area directly inside room access door (15 min) 0.25 Hr X 80 mrlhr =20 mrem

~;tf Estimate 5 mrem dose accumulation. **CRITICAL .;iK**

SAT/UNSAT

d. Work time at the '~" RWCU pump 1.5 Hrs X 200 mrlhr =300 mrem

{;riP Estimate 300 millirem dose accumulation. **CRITICAL ~**

SAT/UNSAT

e. An additional 25 mr will be accumulated once the job is done for de-staging activities.

Total = 0.5 + 5 + 20 + 300 + 25 are;: ** CRITICAL STEP**

,,'1- <.

SAT/UNSAT 0

Step 2 - Determines that neither worker would exceed the Brunswick administrative limit of 2 REM per calendar year if the estimated do e were accumulated.

Worker #1 600 mr + 350.5 mr = mr << 2R limit)

Worker #2 670 mr + 350.5 mr = O. mr << 2R limit)

- CRITICAL STEP**

SAT/UNSAT Comments

KIA REFERENCE AND IMPORTANCE RATING:

2.3.7 Ability to comply with radiation work permit requirements during normal and abnormal conditions

REFERENCES:

TOOLS AND EQUIPMENT:

Calculator.

SAFETY FUNCTION (from NUREG 1123):

A.3 Radiation Control Validation Time: 15 Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 1 Setting: Control Room Simulator__ (N/A for Admin or In-Plant JPMs)

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION JPM: Pass - - Fail _ _

TASK CONDITIONS:

Two workers will be performing a lube check and coupling alignment on the Unit Two (2)

RWCU Pump 2A.

Worker #1 has accumulated 600 mrem this year.

Worker #2 has accumulated 670 mrem this year.

The elevator is out of service The following times for each worker have been estimated for performance of the job.

1. Traversing Southeast stairwell 20' - 50' Rx Bldg 6 minutes

2. Staging time in access area directly outside the RWCU room 15 minutes

3. Staging time in area directly inside room access door 15 minutes

4. Work titTle at the "A" RWCU pump 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

5. Following completion of the job, an additional 25 mrem per worker will be received during de-staging activities and transit back to the maintenance shop.

INITIATING CUE:

Using the information above and the provided radiological survey using best ALARA practices:

Determine the total dose accumulated for both workers. (assume the same task times for both workers)

Determine if any Brunswick Administrative dose limitations will be exceeded.

BRUNSWICK NUCLEAR PLANT RADIOLOGICAL SURVEY SURVEY NO DATE: /oJ 0..7 TIME: O'loo INST. TYPE DOSE RATE H {., ..t.-. -f.d,-

CONTAMINATION

~O 010 ~O orO SURVEYOR g~(1 J'aoe.s SERIAL NO. Ill'] ~

SIGNATURE

~.~ If" FACTOR INST/SN REVIEWED A:/!.t 1t.r~

RXPOWER H2 SCFM 100 3f{

EFF.

BKGD.

CPM CPM UNIT_2_ BLDG ~ EL ~ AREA ~ A-/6 12. vJc l.I( Pi /11Y RWP NO. _..:.../.!.../.....!I.(-=/;....::;5:.t...-_---!()lL.cf-'1-.._

COMPONENT OR TAG ~. WRIJO - - - - - - - - - -

WORK PERFORMED U'!:!(1. L fLb-t... r..Ll_ c./C. .,J... ('Q.v{- I~ t2l. l TJb ~ . . +- SMEAR RESULTS IN DPM/100 CM2 B=BETA IN mRAD/HRl100CM 2

~/rO M=CPM/MASLIN CV

~ 1111111111 (f) 1 RWCU 16100 [IDIf~ NO.

,2 RESULTS

.2S"r arm

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3 ~ar

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n~~o A PUMP BPUMP @ :-

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I V~LCTANK DRAINUNE GJ

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MEZZANINE \

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1 I

1:::.. INDICATES ELECTRICAL OUTLETS RA -RADIATION AREA CA -CONTAMINATION AREA

\

HRA -HIGH RADIATION AREA HCA -HIGH CONTAMINATION AREA DOSE RATES IN mRlHR LHRA -LOCKED HIGH RADIATION AREA M -AIRBORNE AREA o

RCA -RADIATION CONTROL AREA - ROPE BOUNDARY n -NEUTRON (mRem/Hr)

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE A-4-S LESSON TITLE: Classify An Emergency Per PEP-02.1.

LESSON NUMBER: SOT-OJT-JP-301-A1S REVISION NO: 0

Classify An Emergency Per PEP-02.1.

SAFETY CONSIDERATIONS:

None.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

3. The evaluator may provide the examinee with a copy of PEP-02.1 (including flowchart) if desired.

4. Task standards (Le. pass/fail criteria) for each JPM step are ITALICIZED below the step.

SOT-OJT-JP-301-A15 Page 2 REV. 0

Classify An Emergency Per PEP-02.1.

Read the following to trainee.

TASK CONDITIONS:

1. Unit Two was operating at 100% power with DG4 under clearance. SJAE monitors were slowly rising and E&RC was notified to obtain a reactor coolant sample.

2. The following sequence of events occurs (ASSUME all automatic actions that should occur have occurred unless otherwise specified):

Time Event Description Exceeded EAL Number Highest Current Classification( s) Exeeded Classification and EAL number 1200 E&RC reports results of reactor coolant sample at 5.2 J..lCi/gm 1-131 dose equivalent 1230 Seismic event occurs and is verified to be at a magnitude of 0.12g on seismic instrumentation 1245 Off-site power is lost. DG3 fails to start automatically or manually 1255 DG3 is successfully started and tied to E3 1305 HPCI steam line break occurs in the HPCI room as indicated by high room temperature and radiation level and high steam line flow.

Attempts to isolate the HPCI system are unsuccessful - Assume any E-bus crosstie actions are unsuccessful 1320 E&RC reports results of reactor coolant sample at 330 J..lCi/gm 1-131 dose equivalent.

SOT-OJT-JP-301-A 15 Page 3 REV. 0

Classify An Emergency Per PEP-02.1.

INITIATING CUE:

You are directed to classify the event per PEP-02.1.

For each time listed state the following:

Exceeded Classification(s)

Associated EAL number(s)

Current Highest EAL Classification and associated EAL number(s)

SOT-OJT-J P-30 1-A15 Page 4 REV. 0

Classify An Emergency Per PEP-02.1.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain a current revision of PEP-02.1.

Current Revision of PEP-02. 1 obtained.

SAT/UNSAT*

Step 2 - (Time 1200).

Determine Exceeded Classification and associated EAL number o Unusual Event - 03.01.01

Determine Highest Current Classification and EAL Number(s) o Unusual Event - 03.01.01

- CRITICAL STEP ** SAT/UNSAT*

Step 3 - (Time 1230).

Determine Exceeded Classification and associated EAL number o Alert - 14.02.01

Determine Highest Current Classification and EAL Number(s) o Alert- 14.02.01

- CRITICAL STEP ** SAT/UNSAT*

Step 4 - (Time 1245).

Determine Exceeded Classification and associated EAL number o Alert - 06.02.02

Determine Highest Current Classification and EAL Number(s) o Alert - 06.02.02 and 14.02.01

- CRITICAL STEP ** SAT/UNSAT*

SOT-OJT-JP-301-A 15 Page 5 REV. 0

Classify An Emergency Per PEP-02.1.

Step 5 - (Time 1255)

Determine Exceeded Classification and associated EAL number o Unusual Event- 06.01.01

Determine Highest Current Classification and EAL Number(s) o Alert- 14.02.01

- CRITICAL STEP ** SAT/UNSAT*

Step 6 - (Time 1305)

Determine Exceeded Classification and associated EAL number o Site Area Emergency- 02.03.01 and 12.03.01 o General (Possible) - 12.04.01 (not a required call at this time)

Determine Highest Current Classification and EAL Number(s) o Site Area Emergency- 02.03.01 and 12.03.01 o General (Possible) - 12.04.01 (not a required call at this time)

- CRITICAL STEP ** SAT/UNSAT*

Step 7 - (Time 1320)

Determine Exceeded Classification and associated EAL number o General Emergency- 12.04.01 o Alert - 03.02.01

Determine Highest Current Classification and EAL Number(s) o General Emergency- 12.04.01

- CRITICAL STEP ** SAT/UNSAT*

Comments required for any step evaluated as UNSAT.

SOT-OJT-JP-301-A 15 Page 6 REV. 0

Classify An Emergency Per PEP-02.1.

Answer Key Time Event Description Exceeded EAL Number(s) Highest Current Classification( s) Exeeded Classification and EAL number(s) 1200 E&RC reports results of reactor coolant sample at 5.2 ~Ci/gm 1-131 Unusual Event 03.01.01 Unusual Event dose equivalent 03.01.01 1230 Seismic event occurs and is verified to be at a magnitude of 0.12g on seismic Alert 14.02.01 Alert instrumentation 14.02.01 1245 Off-site power is lost. DG3 fails to Alert start automatically or manually Alert 06.02.02 14.02.01 06.02.02 1255 DG3 is successfully started and tied to Alert E3 Unusual Event 06.01.01 14.02.01 1305 HPCI steam line break occurs in the Site Area HPCI room as indicated by high room Site Area 02.03.01 02.03.01 temperature and radiation level and Emergency 12.03.01 12.03.01 high steam line flow. Attempts to isolate the HPCI system are Possible 12.04.01 Possible unsuccessful - Assume any E-bus General General crosstie actions are unsuccessful 12.04.01 1320 E&RC reports results of reactor coolant sample at 330 ~Cilgm 1-131 General 12.04.01 General dose equivalent. Emergency 12.04.01 Alert 03.02.01 SOT-OJT-JP-30 1-A15 Page 7 REV. 0

Classify An Emergency Per PEP-02.1.

RELATED TASKS:

Perform actions of Site Emergency Coordinator following declaration of a General Emergency KIA REFERENCE AND IMPORTANCE RATING:

GEN 2.4.29 3.1/4.4 Knowledge of the Emergency Plan

REFERENCES:

OPEP-02.1, Rev 50 TOOLS AND EQUIPMENT:

None.

ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2., Supp.1):

Admin - Emergency Procedures / Plan SOT-OJT-JP-301-A 15 Page 8 REV. 0

Classify An Emergency Per PEP-02.1.

Time Required for Completion: ~ Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit:

Setting: Control Room Simulator__ ( Not applicable to In-Plant JPMs )

Time Critical: Yes No ~ Time Limit N/A Alternate Path: Yes No ~

EVALUATION Trainee: ------------------------- SSN: ----------------

JPM: Pass Fail _ _

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure Current?: Yes ____ No _ _

Comments:

Comments reviewed with Student Evaluator Signature: Date:- - - -

SOT-OJT-JP-301-A15 Page 9 REV. 0

TASK CONDITIONS:

1. Unit Two was operating at 100% power with DG4 under clearance. SJAE monitors were slowly rising and E&RC was notified to obtain a reactor coolant sample.

2. The following sequence of events occurs (ASSUME all automatic actions that should occur have occurred unless otherwise specified):

Time Event Description Exceeded EAL Number Highest Current Classification( s) Exeeded Classification and EAL number 1200 E&RC reports results of reactor coolant sample at 5.2 /-LCi/gm 1-131 dose equivalent 1230 Seismic event occurs and is verified to be at a magnitude of 0.12g on seismic instrumentation 1245 Off-site power is lost. DG3 fails to start automatically or manually 1255 DG3 is successfully sarted and tied to E3 1305 HPCI steam line break occurs in the HPCI room as indicated by high room temperature and radiation level and high steam line flow.

Attempts to isolate the HPCI system are unsuccessful - Assume any E-bus crosstie actions are unsuccessful 1320 E&RC reports results of reactor coolant sample at 330 /-LCi/gm 1-131 dose equivalent.

INITIATING CUE:

You are directed to classify the event per PEP-02.1.

For each time listed state the following:

Exceeded Classification( s)

Associated EAL number(s)

Current Highest EAL Classification and associated EAL number

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT P-1 LESSON TITLE: Alternate Coolant Injection - EOP-LEP Coolant Injection with SLC Pumps Aligned To Demineralized Water LESSON NUMBER: AOT-OJT-JP-300-J10 REVISION NO: 04

Alternate Coolant Injection - EOP-LEP-01 Coolant Injection with SLC Pumps Aligned To Demineralized Water SAFETY CONSIDERATIONS:

1. Radiological hazards.

2. Operating equipment hazards.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be supplied to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee.

3. The task standard (Le. pass fail criteria) is italicized.

4. This JPM may be performed on either Unit, as selected by the evaluator.

Read the following to the trainee TASK CONDITIONS:

1. This JPM will be performed on Unit __ . (Designated by the evaluator)

2. The SLC system and the Demineralized Water system are operable and accessible.

3. Reactor pressure is below the upper range of the SLC pump discharge pressure (0-1380 psig).

4. EOP-01 has directed control operators to enter LEP-01 to restore and/or maintain RPV level above TAF.

5. All control rods are fully inserted.

INITIATING CUE:

You are the Reactor Building AO. You are directed by the Control Operator (with SCO approval) to perform the Auxiliary Operator actions associated with aligning Unit SLC using Demineralized Water per LEP-01, Section 1 and inform the control room when you have completed the actions.

AOT-OJT-JP-300-J10 Page 2 of9 Rev. 04

Alternate Coolant Injection - EOP-LEP-01 Coolant Injection with SLC Pumps Aligned To Demineralized Water PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Determines that EOP-01-LEP-01, Section 1, Step 4 is the starting point and proceed to the Reactor Building 80' elevation.

Procedure is obtained.

SAT/UNSAT*

Start Time: _ _ _ __

Step 2 - Unlock and close SLC storage tank outlet isolation valve, C41-F001 .

C41-F001 unlocked and manually closed (Step 4a).

- CRITICAL STEP** SAT/UNSAT*

Step 3 - Obtain pipe wrench and Demin water to SLC Jumper hose from 80' LEP Toolbox.

Jumper and pipe wrench is obtained.

- CRITICAL STEP** SAT/UNSAT*

AOT-OJT-JP-300-J 10 Page 3 of 9 Rev. 04

Alternate Coolant Injection - EOP-LEP-01 Coolant Injection with SLC Pumps Aligned To Demineralized Water Step 4 - Connect one end of the demin water to SLC jumper hose to the threaded connection at the SLC Demineralized Water Supply Isolation Valve, C41-V5000.

Jumper is connected to threaded connection at V5000 (Step 4b).

- CRITICAL STEP** SAT/UNSAT*

Step 5 - Connect the other end of the demin water to SLC jumper hose to the threaded connection upstream of the SLC Test Tank Outlet Demineralized Water Supply Isolation Valve, C41-F014.

Jumper is connected to threaded connection at F014 (Step 4c).

- CRITICAL STEP** SAT/UNSAT*

Step 6 - Open the SLC Demin Water Supply Isolation Valve, C41-V5000.

C41-V5000 manually opened, at 80' Rx Bldg (Step 4d).

- CRITICAL STEP** SAT/UNSAT*

AOT-OJT-JP-300-J10 Page 40f9 Rev. 04

Alternate Coolant Injection - EOP-LEP-01 Coolant Injection with SLC Pumps Aligned To Demineralized Water Step 7 - Unlock and open SLC Test Tank Outlet Demineralized Water Supply Isolation Valve, C41-F014.

C41-F014 unlocked and manually opened, at 80' Rx Bldg above SLC test tank. (Step 4e)

- CRITICAL STEP** SAT/UNSAT*

Step 8 - Contact the control room to start the SLC pumps.

Control room informed that SLC is aligned to demineralized water and that the pumps can be started. (Step 7)

SAT/UNSAT*

TIME STOP: _ _ _ __

Comments required for any step evaluated as UNSAT.

AOT -OJT-J P-300-J 10 Page 5 of 9 Rev. 04

Alternate Coolant Injection - EOP-LEP-01 Coolant Injection with SLC Pumps Aligned To Demineralized Water RELATED TASKS:

200071 8504 Perform Alternate Coolant Injection With SLC Pumps Per EOP-LEP-01.

KIA REFERENCE AND IMPORTANCE RATING:

295031 EA1.08 3.8/3.9 Ability to operate alternate injection systems.

REFERENCES:

1. EOP-01-LEP-01, Alternate Coolant Injection, Section 1.

TOOLS AND EQUIPMENT:

1. 1 LEP Toolbox Key

2. Pipe wrench

3. Demineralized water to SLC jumper hose SAFETY FUNCTION (from NUREG 1123, Rev. 2)

Safety Function 2, Reactor Water Inventory Control REASON FOR REVISION:

SLC modification is now common to both Units.

AOT-OJT-JP-300-J 10 Page 6 of 9 Rev. 04

Alternate Coolant Injection - EOP-LEP-01 Coolant Injection with SLC Pumps Aligned To Demineralized Water Validation Time: 12 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual Unit:

Setting: Control Room Simulator In-Plant Time Critical: Yes No Time Limit N/A Alternate Path: Yes No EVALUATION Trainee: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass Fail _ _

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure?: Yes No _ __

( Each Student should verify one JPM per evaluation set)

Comments:

Comments Reviewed With Trainee Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date: _ _ _ _ _ __

AOT-OJT-JP-300-J10 Page 7 of 9 Rev. 04

TASK CONDITIONS:

1. This JPM will be performed on Unit __ . (Designated by the evaluator)

2. The SLC system and the Demineralized Water system are operable and accessible.

3. Reactor pressure is below the upper range of the SLC pump discharge pressure (0-1380 psig).

4. EOP-01 has directed control operators to enter LEP-01 to restore and/or maintain RPV level above TAF.

5. All control rods are fully inserted.

INITIATING CUE:

You are the Reactor Building AO. You are directed by the Control Operator (with SCO approval) to perform the Auxiliary Operator actions associated with aligning Unit SLC using Demineralized Water per LEP-01, Section 1 and inform the control room when you have completed the actions.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN PLANT P-2A LESSON TITLE: STOP AND PREPARE DG4 FOR START PER OASSD-02 with failed breaker (DG OPERATOR ACTIONS)

LESSON NUMBER: AOT-OJT-JP-304-24 REVISION NO: o

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure SAFETY CONSIDERATIONS:

1. Hearing protection, hardhat, and safety glasses.

2. Simulate all actions including communications.

3. Practice ALARA at all times while simulating actions.

4. Standard electrical precautions when working around energized electrical equipment.

EVALUATOR NOTES: (Do not read to performer)

1. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

2. The task standard (Le. pass fail criteria) is italicized.

3. START LOCATION: Begin this JPM at the DG4 Control Panel H57. Access/Egress is NOT evaluated because this JPM starts at and is performed at the DG4 Control Panel H57.

4. PROVIDE A COPY: OASSD-02, Section E, is to be provided to the student (marked up to the starting location).

5. Location of the ASSD Bag: 23' Elevation (between the cable spread room and the breezeway), opposite wall (South wall) from the elevator to the control room.

6. TIME CRITICAL - BASIS FOR TIME: This JPM is a time critical JPM. The critical time is a fraction of the analysis time to establish Suppression Pool Cooling within 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Based on all the other actions that are required to be performed within this time frame, the critical time established for this JPM is 15 minutes.

AOT-OJT-J P-304-24 Page 2 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure Read the following to the JPM performer.

TASK CONDITIONS:

1. This is a time critical JPM.

2. A Control Room fire has resulted in Control Room Evacuation.

3. OASSD-02 has been entered and is being performed.

4. You are the Diesel Generator Operator.

5. ASSD equipment is distributed and ASSD communications are established.

6. You have your ASSD equipment bag and the following keys:

Fifteen (15) T112 keys, one (1) CO key, thirty-four (34) GE-75 keys

7. You have completed OASSD-02, Section E, up through and including step 1.14.

INITIATING CUE:

You are directed to remove DG4 from service and prepare DG4 for a start per OASSD-02, Section E, step 1.15 through step 1.17.

AOT-OJT-JP-304-24 Page 3 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Comments required for any step evaluated UNSAT.

START TIME: _ _ __

PROIVIPT: Providelndication~asnecessarytbtheexal11inee: . ..... . ,. . . . ..' . . . ..'

Initial conditions vJillspow the DG4 outputpreaker cl'oseCl; GREENlIGH:r:OFF, .

RED L1GHTON.: ...**.*. . .... . ....... ...>' ...,.

Step 1 - Trip the generator circuit breaker.

Places the Generator Circuit Breaker to open. (Step 1. 15. 1)

- CRITICAL STEP**SAT/UNSAT*

PR0MPT*:Aftertlle generator circuifbreaker is tripped reportDG4 oi.ltputS~eaker0pen;i GREEN LIGt:lTON, RED LIGHT OFIF. . .

Step 2 - Stop DG4 using the EMERGENCY STOP pushbutton.

Depresses DG4 EMERGENCY STOP pushbutton. (Step 1.15.2)

- CRITICAL STEP**SAT/UNSAT*

PROMPT: When DG4 EMERGENCY STOP pushbutton is pressed,il1dicate,pGjs offby

., showillgUNIT AVAILABLE white light off. Equipment noisegoe§ a.Way. .

AOT-OJT-J P-304-24 Page 4 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure Step 3 - Place six (6) keylock NORMAL/LOCAL switches in LOCAL.

Inserts key into switch and rotates switch to LOCAL position. (Step 1.15.3)

Accomplished for each of six (6) switches in the same row.

Separate key is used for each switch.

- CRITICAL STEP**SAT/UNSAT*

PROMPT:'Wtlellakeylock switch ,has a GE75 key inserted (simulated)"andlsJ9!ated tothe/,

LOQAL position, indi¢atetne keylock switch in. LOqAL. If thekeyi~~n0tsimulatea to oeinsertedthekeylockswitch remains in the NORMAL position (wc>n't move),;

NOTE< Adfft'erent GE75 key is \0 be used for each switch. If aswit~h is"~la~.edin LOCA~

qnd'the performer indicates they would remove the k~yfo of:}erate,'tpellext switcn;~~

ind iCate they are unable to remove the key from the switchWnlle intha LOCAL ',\

. '.P9~ition. "

Step 4 - Place seventh (ih) keylock NORMAL/LOCAL switch in LOCAL, located in the row above the six keylock switches just operated.

Inserts key into switch and rotates switch to LOCAL position. (Step 1.15.4)

Separate key is used for switch.

- CRITICAL STEP**SAT/UNSAT*

NOTE: Thereare'sevEm keStiock J\lCikMAULOClff. sWitctlesfocatedoQ Di~.~el Generator 4 control panel.Sixof these are located in a row. The seventh swif&R IS located in

(;;.m~ row above the~ix switche~~Thesixswitches in a row must be placed in

,',' <*t~Cf\l...befpre pl~cingJh~~seventh,~switGh; ill LQ.9A4.. ' ,

AOT-OJT-J P-304-24 Page 5 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure Step 5 -Inform Emergency Switchgear Operator DG Bldg that DG4 is removed from service.

Informs Emergency Switchgear Operator DG Bldg that DG4 is removed from service. (Step 1.15.5)

- CRITICAL STEP**SAT/UNSAT*

I PROMPT: Roleplaycornrnunications\C3,&.l;mergencySWitchgear OperatorIRG~ldg,"

Step 6 - At MCC DGD Compt D59 (Row G3), place NORMAL/LOCAL switch in LOCAL.

At MCC DGD Campt D59: Inserts key into NORMAULOCAL switch and rotates switch to LOCAL position (Step 1.16.1.1)

- CRITICAL STEP**SATlUNSAT*

PRC:>MPT: When key inserted (T112) and NORMAL/LOCAL switch is rotated to the LOCAL .

(i' pOpition, indicate the switch in L O C A L . ' .

Step 7 - At MCC DGD Compt D59 (Row G3), place START/STOP control switch in START for DG CELL 4 EXHAUST FAN 2-VA-H-EF-DG.

At MCC DGD Campt D59: Rotates START/LOCAL switch to START.

(Step 1.16.1.2)

- CRITICAL STEP**SAT/UNSAT*

PROMPT'~ .. Y"henthe STAF{T/STOP.control switch is rotated to START, inqicate switch'ih i **** *,$;,{ART.lndicategreerl'light;off"Jed lighton. ,', ". ,

Step 8 - At MCC DGD Compt EF7 (Row G2), place SW TO JKT WTR CLR SPLY ISOL VLV, 1-SW-V682 in OFF.

At MCC DGD Campt EF7: Breaker placed in OFF. (Step 1.16.1.3)

SAT/UNSAT*

IPROMPT:Wbeoa$ked infQrrn.theeXarnil)ee the breakeris'inOFF, '

AOT-OJT-J P-304-24 Page 6 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure Step 9 - At 480V Substation E8 trip the following breakers:

Row Compt Breaker Open B3 AZ6 MCC2XH D2 A03 MCC1XK E2 AO? MCC2XM E4 A09 MCC 2CB F3 A12 Emerg. 120/208V AC Distr Pnl 2E8-HG3 (Step 1.16.2)

- CRITICAL STEP**SAT/UNSAT*

PROMPT: VVbeni~~ch breaker is tripped; indicate to the exainineethat there isa greenop'en inqicating;flagon the br,eaker. >" ... 'c/ ..... .'

Step 10 - At 480V Substation E8 Compt FN2 (Row A 1): Places NORMALILOCAL keylock switch to LOCAL.

EB Compt FN2 (Row A1): NORMAULOCAL switch in LOCAL. (Step 1.16.3.1)

- CRITICAL STEP**SAT/UNSAT*

PROMPT: When key is inserted and NaRMALlLO¢A~swltchi~Jotated to the LOGj\L. "*..**.

.. .;;\ : position; indicate the switch in LOCAL. . .." '. . . . . . . ".

Step 11 - At 480V Substation E8 Compt AZ5 (Row B2): Verifies E8 480V SUB MAIN BREAKER.

EB Compt AZ5 (Row 82): EB 4BOV SUB MAIN BREAKER open flag verified.

SAT/UNSAT*

PROMPT: Indicate 6reakeris08EN{bYiind~rltingth~.ttheJe isa green open indicating flag.

',~(~~~,,; :::.~"" , ~ '>, / .': //'c/;"/ /,_'" // ' '

N~E~"\' .This starts the alternate path portion of having to 6Id~e;the break~LIQcall~.

Step 12 - At 480V Substation E8 Compt FN2 (Row A 1): Places local ASSD control switch to close.

EB Compt FN2 (Row A1): local ASSD control switch is closed. (Step 1.16.3.2)

SAT/UNSAT*

PRO'MPT: ASSDcontr6IsWit69.~mComptFN2is placed in close indicate that the~reaker*

":< ... .:' gr~en ,'open fli:lg;Is~till'~v:idenf.:., ..' '.

AOT-OJT-J P-304-24 Page 7 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure Step 13 - At 480V Substation E8 Compt AZ5 (Row B2): Close the breaker by pulling down the manual close lever.

EB Compt FN2 (Row 82): Breaker closed by pulling down on the manual close lever. (Step 1.16.3.3)

- CRITICAL STEP**SAT1UNSAT*

PROMPT: Indi.Ctate breakerclosed after pulling down the manual close lever; red closed indicating flag. ..' ..... .***

Step 14 - Inform Emergency Switchgear Operator DG Bldg that DG4 is ready to be started.

Emergency Switchgear operator DG Bldg Operator informed DG4 is ready to be started. (Step 1. 17)

SAT/UNSAT*

1PROMPT: ROleplay commu nications. as. *ErnergencySwitchgearQpera!br DGBldg. '. . '1 TERMINATING CUE: When DG4is ready to be started and the Emergency Switchgear Operator DG .Bldg is;inforrn~dth~s JPM.:is complete. " .l, STOP TIME: _ _ _ __

Time Critical Time - 15 minutes.

AOT-OJT-J P-304-24 Page 8 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure RELATED TASKS:

2006118504, Perform actions associated with Alternate Safe Shutdown as the Unit 1(2)

DG Operator per OASSD-02.

KIA REFERENCE AND IMPORTANCE RATING:

295003 AA 1.02 Ability to operate and/or monitor the following as they apply to Partial or Complete Loss of AC Power: Emergency Generators (4.2/4.3)

REFERENCES:

OASSD-02, Section E.

TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev 2.):

6 (Electrical)

REASON FOR REVISION:

Modified JPM to add alternate path.

Formatted to have Prompts after steps they apply to AOT-OJT-JP-304-24 Page 9 of 11 Rev. 0

STOP AND PREPARE DG4 FOR START PER OASSD-02 with breaker failure Time Required for Completion: 15 Minutes (approximate).

Time Taken: Minutes II II II' 11111 II APPLICABLE METHOD OF TESTING Performance: Simulate x Actual Unit: 2 Setting: Control Room Simulator _ (Not applicable to In-Plant JPMs)

Time Critical: Yes x No Time Limit 15 Minutes Alternate Path: Yes x No III III I I'll EVALUATION Performer: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass Fail _ _ __

Remedial Training Required: Yes No _ _

Did Performer Verify Procedure? Yes _ _ No _ __

(Each Student should verify one JPM per evaluation set)

III III Comments:

Comments reviewed with Student Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date: _ _ _ __

AOT-OJT-J P-304-24 Page 10 of 11 Rev. 0

TASK CONDITIONS:

1. This is a time critical JPM.

2. A Control Room fire has resulted in Control Room Evacuation.

3. OASSD-02 has been entered and is being performed.

4. You are the Diesel Generator Operator.

5. ASSD equipment is distributed and ASSD communications are established.

6. You have your ASSD equipment bag and the following keys:

Fifteen (15) T112 keys, one (1) CO key, thirty-four (34) GE-75 keys

7. You have completed OASSD-02, Section E, up through and including step 1.14.

INITIATING CUE:

You are directed to remove DG4 from service and prepare DG4 for a start per OASSD-02, Section E, step 1.15 through step 1.17.

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT P-3 LESSON TITLE: Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation LESSON NUMBER: LOT -OJT -JP-302-E07 REVISION NO: 04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation SAFETY CONSIDERATIONS:

1. Operating equipment and energized electrical equipment hazards.

2. Hearing protection is required in this area when equipment is operating.

3. Safety Glasses, Hard Hat, and approved footwear must be worn while in the area of this JPM.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the performer, once it is demonstrated he/she knows the correct procedure.

2. The task standard (Le. pass fail criteria) is italicized.

3. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

LOT-OJT-JP-302-E07 Page 2 of 10 Rev.04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation Read the following to the JPM performer.

TASK CONDITIONS:

1. The Shift Superintendent has made the determination that Control Room evacuation is required.

2. All immediate actions associated with AOP-32, Plant Shutdown from Outside Control Room, are complete.

3. Remote shutdown equipment has been distributed and communication between the Remote Shutdown Stations is established.

4. All NORMAL/LOCAL switches have been placed in LOCAL in accordance with Attachments 1 through 4, Remote Shutdown Panel Initial Switch Alignment.

5. The RHRSW System is accessible and in standby lAW OP-43.

6. Station 4 (Diesel Building Operator) is available for actions required by this procedure.

7. This JPM will be performed on Unit ___ '

INITIATING CUE:

You are directed by the Unit SCO to perform Station 2 (Reactor Building Operator) actions, including Remote Shutdown Panel (Station 1) actions, associated with placing the 'B' Loop RHRSW System in operation per OAOP-32, Step 3.2.11.2.

Inform the Unit SCO when all required actions have been completed.

LOT-OJT-JP-302-E07 Page 3 of 10 Rev.04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtains copy of AOP-32 and determines starting point of Step 3.2.11.2 Obtains copy of AOP-32.

SAT/UNSAT*

TIME START _ _ __

Step 2 - OPEN SW-V105, NUCLEAR SERVICE WATER SUPPLY VALVE, at MCC 1(2) XB Compartment DM1, Row H3.

SW-V105 is opened. (Step 2a)

- CRITICAL STEP**SAT/UNSAT*

Step 3 - CLOSE SW-V141, WELL WATER SUPPLY VALVE, at the Remote Shutdown Panel.

SW-V141 is verified closed. (Step 2b)

SAT/UNSAT*

Step 4 - CLOSE SW-V143, WELL WATER SUPPLY VALVE, at the Remote Shutdown Panel.

SW-V143 is verified closed. (Step 2b)

SAT/UNSAT*

LOT-OJT-JP-302-E07 Page 4 of 10 Rev.04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation Step 5 - OPEN or VERIFY OPEN E11-F002B, RHR HEAT EXCHANGER 'B' SERVICE WATER DISCHARGE VALVE, at MCC 1(2) XB Compartment DN9, Row G4.

E11-F002B is verified opened. (Step 2c)

SATIUNSAT*

Step 6 - Contact Station 4 (Diesel Generator Operator) and direct starting both unit NSW pumps.

Both affected unit NSW pumps are started. (Step 2d)

- CRITICAL STEP**SAT/UNSAT*

Step 7 - Contact the Station 4 (Diesel Generator Operator) and direct starting the '8' or 'D' RHR Service Water Booster Pump.

The B or D RHR SW Booster Pump is started. (Step 2e)

- CRITICAL STEP**SATIUNSAT*

LOT-OJT-JP-302-E07 Page 5 of 10 Rev.04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation Step 8 - THROTTLE OPEN E11-F068B, RHR HEAT EXCHANGER 'B' SERVICE WATER DISCHARGE VALVE, at MCC 1(2) XB Compartment DN1, Row K4, until amperage on the running RHR Service Water Booster Pump reaches 80 amps.

E11-F0688 is throttled open until pump amperage reaches 80 amps. (Step 2g)

- CRITICAL STEP**SAT/UNSAT*

Step 9 - OPEN SW-V117, NUCLEAR SERVICE WATER TO VITAL HEADER VALVE, at MCC 1(2) XB Compartment DP2, Row G2.

SW-V117 is opened. (Step 2h)

- CRITICAL STEP**SAT/UNSAT*

Step 10 -Notify the Unit SCO that the RHR Service Water System is in operation.

The Unit seo is notified.

SAT/UNSAT*

LOT-OJT-J P-302-E07 Page 6 of 10 Rev.04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation TIME COMPLETED _ _ _ __

LOT-OJT-JP-302-E07 Page 7 of 10 Rev.04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation LIST OF REFERENCES RELATED TASKS:

2006048504 Perform MCC Operator Actions For Placing Suppression Pool Cooling In Service Per ASSD-02 or AOP-32.

KIA REFERENCE AND IMPORTANCE RATING:

295026 EA1.01 4.1/4.1 Ability to operate and/or monitor the following as they apply to Suppression Pool High Water Temperature: Suppression Pool Cooling

REFERENCES:

AOP-32, Plant Shutdown from Outside Control Room - Rev 45 TOOLS AND EQUIPMENT:

Equipment from the Remote Shutdown Equipment Locker.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

Safety Function 5 - Containment Integrity REASON FOR REVISION:

Procedure changes.

LOT-OJT-J P-302-E07 Page 8 of 10 Rev.04

Control Room Evacuation lAW AOP-32, Placing the RHR Service Water System in Operation Validated Time:~ Minutes (approximate).

II APPLICABLE METHOD OF TESTING Performance: Simulate -..:L Actual Unit:

Setting: Control Room Simulator _ (Not applicable to In-Plant JPMs)

Time Critical: Yes No ..:::L Time Limit N/A Alternate Path: Yes No ..:::L EVALUATION Performer:

JPM: Pass - - Fail _ _

Remedial Training Required: Yes No _ _

Did Performer Verify Procedure? Yes ___ No ____

(Each Student should verify one JPM per evaluation set)

Comments:

Comments reviewed with Student Evaluator Signature: ______________________________ Date:

LOT-OJT-JP-302-E07 Page 9 of 10 Rev.04

TASK CONDITIONS:

1. The Shift Superintendent has made the determination that Control Room evacuation is required.

2. All immediate actions associated with AOP-32, Plant Shutdown from Outside Control Room, are complete.

3. Remote shutdown equipment has been distributed and communication between the Remote Shutdown Stations is established.

4. All NORMAL/LOCAL switches have been placed in LOCAL in accordance with Attachments 1 through 4, Remote Shutdown Panel Initial Switch Alignment.

5. The RHRSW System is accessible and in standby lAW OP-43.

6. Station 4 (Diesel Building Operator) is available for actions required by this procedure.

7. This JPM will be performed on Unit _ __

INITIATING CUE:

You are directed by the Unit SCO to perform Station 2 (Reactor Building Operator) actions, including Remote Shutdown Panel (Station 1) actions, associated with placing the '8' Loop RHRSW System in operation per OAOP-32, Step 3.2.11.2.

Inform the Unit SCO when all required actions have been completed.

Page 10 of 10

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR 8-1 LESSON TITLE: Emergency Equalization Around MSIV's - using the Hard Card.

LESSON NUMBER: LOT-SIM-JP-025-A01 REVISION NO: 2

Emergency Equalization Around MSIV's - using the Hard Card.

SIMULATOR SETUP:

Recommended Initial Conditions IC-11, 100% Power, BOC Required Plant Conditions Perform a MANUAL Scram carry out EOP-01-RSP initial operator actions. Close the MSIVs, Trip the SJAEs, RFPs and OPEN the condenser vacuum breakers to reduce vacuum to <10". After this is done place the MSIV control switches to OPEN.

Triggers Malfunctions Overrides Remotes MS_VMS5005D MVD-V5005 MN STM DRN HDR Isolation Open MS IAGP1 BYP LO COND VACUUM GP1 TRIP BYP LOT-SIM-JP-02S-A01 Page 2 of 9 Rev. 2

Emergency Equalization Around MSIV's - using the Hard Card.

SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL NOT be provided to the performer.

2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

Read the following to the JPM performer.

TASK CONDITIONS:

1. A scram and Group 1 Isolation have occurred.

2. No fuel failure or steam line breaks have occurred.

3. The Main Condenser is available as a heat sink.

4. The Unit SCQ has anticipated that Emergency Depressurization may be required.

INITIATING CUE:

You are directed to perform the control operator actions associated with emergency equalization around the MSIVs, and open MSIVs when pressure is ~ 200 psid, using the Hard Card.

You are to inform the Unit SCQ when the actions to equalize and open the MSIVs per the Hard Card are complete.

LOT-SIM-JP-025-A01 Page 3 of 9 Rev. 2

Emergency Equalization Around MSIV's - using the Hard Card.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain "Hard Card" for MSIV equalization.

"Hard Card" obtained for MSIV equalization.

SAT/UNSAT*

TIME START _ _ _ __

Step 2 - Ensure the condenser vacuum bypass switches in bypass position.

Vacuum bypass switches placed in bypass.

. SAT/UNSAT*

Step 3 - Place all MSIV control switches in the CLOSE position.

AI/ MSIV control switches, B21-F022A, B, C & 0, B21-F028A, B, C & 0, placed in CLOSE position.

. SAT/UNSAT*

Step 4 - Reset Group 1 Isolation.

Group 1 Isolation reset switches, A72-S32 and S33, on P601, are depressed and White lights are ON.

SAT/UNSAT*

Step 5 - Open Outboard MSIVs.

Outboard MSIV control switches, B21-F028A, B21-F028B, B21-F028C, B21-F0280, placed in OPEN and MSIVs are OPEN.

- CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-025-A01 Page 4 of 9 Rev. 2

Emergency Equalization Around MSIV's - using the Hard Card.

Step 6 - Open MS-F020.

Verify MSL Drain Isolation Valve, MS-F020, is open.

SAT/UNSAT*

Step 7 - Open B21-F019.

MSL Outboard Drain Isolation Valve, B21-F019, is open.

- CRITICAL STEP ** SAT/UNSAT*

Step 8 - Close MS-V28.

Steam Supply to MSR's, SJAE's, RFP's, MS-V28, indicates full closed.

- CRITICAL STEP ** SAT/UNSAT*

Step 9 - Close MVD-F021.

Verify Common drain line orifice Bypass Valve to Condenser, MVD-F021, closed.

SAT/UNSAT*

Step 10 - Open B21-F016.

MSL Inboard Drain Isolation Valve, B21-F016, open.

- CRITICAL STEP ** SAT/UNSAT*

Step 11 - Open MS-F038 A, B, C, D.

MSL Orifice Bypass Valve, MS-F038A, B, C, and D, open to increase steam line pressure.

- CRITICAL STEP ** SAT/UNSAT*

Step 12 - Ensure steam line pressure is increasing downstream of Outboard MSIVs.

Steam line pressure rising as indicated on Main Steam Pressure AlB indications on XU-1.

SAT/UNSAT*

LOT-SIM-JP-025-A01 Page 5 of 9 Rev. 2

Emergency Equalization Around MSIV's - using the Hard Card.

Step 13 - Close MS-V46, V47, V48, V49 and V35.

Verify MSL drain valves, MS-V46, MS-V47, MS-V48, & MS-V49 and V35, are closed.

SAT/UNSAT*

Step 14 - When.::. 200 psid across the valves, open Inboard MSIVs.

Inboard MSIVs B21-F022A, B, C & 0 are open after.::. 200 psid.

- CRITICAL STEP ** SAT/UNSAT*

Step 15 - Open MVD-F021.

MVO-F021 indicates open.

SAT/UNSAT*

Step 16 - Direct AO to open MVD-V5005.

MVO-V5005 is open.

SAT/UNSAT*

Time completed: _ _ _ __

LOT-SIM-JP-025-A01 Page 6 of 9 Rev. 2

Emergency Equalization Around MSIV's - using the Hard Card.

LIST OF REFERENCES RELATED TASKS:

239201 8401 Equalize Around And Open Main Steam Isolation Valves Per Hot Startup OP-2S.

KIA REFERENCE AND IMPORTANCE RATING:

239001 A4.01 4.2/4.0 Ability to manually operate and or monitor in the Control Room: MSIVs

REFERENCES:

EOP-01-RVCP, Reactor Vessel Control Procedure Hard Card for Emergency MSIV equalization and reopening (S/1032)

TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev .2) 4 - Heat Removal from the Reactor Core (Main and Reheat Steam System)

REASON FOR REVISION:

Formatting and comment incorporation LOT-SIM-JP-025-A01 Page 7 of 9 Rev. 2

Emergency Equalization Around MSIV's - using the Hard Card.

Validation Time: --1L Minutes (approximate).

Inn nHlIL III APPLICABLE METHOD OF TESTING Performance: Simulate Actual -..2L Unit: ..L Setting: Control Room Simulator -..2L In-Plant:

Time Critical: Yes No X Time Limit Alternate Path: Yes No X EVALUATION Performer:

JPM: Pass - - Fail _ _

Remedial Training Required: Yes No _ _

Did Performer Verify Procedure? Yes No _ _

(Each Student should verify one JPM per evaluation set)

Comments:

Comments reviewed with Student Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

LOT-SIM-JP-025-A01 Page 8 of 9 Rev. 2

TASK CONDITIONS:

1. A scram and Group 1 Isolation have occurred.

2. No fuel failure or steam line breaks have occurred.

3. The Main Condenser is available as a heat sink.

4. The Unit SCQ has anticipated that Emergency Depressurization may be required.

INITIATING CUE:

You are directed to perform the control operator actions associated with emergency equalization around the MSIVs, and open MSIVs when pressure is ~ 200 psid, using the Hard Card.

You are to inform the Unit SCQ when the actions to equalize and open the MSIVs per the Hard Card are complete.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR S-2 LESSON TITLE: Vent the Orywell per OP-1 0 wi Stack Rad Monitor Increase >50%

LESSON NUMBER: LOT-SIM-JP-010-A02 REVISION NO: 3

Vent the Drywell per OP-1 0 wi Stack Rad Monitor Increase >50%

SIMULATOR SETUP:

A. Initial Conditions:

1. Recommended Initial Conditions IC 11 Rx. Pwr. 100%

Core Age BOC

2. Required Plant Conditions Drywell Pressure above 0.5 psig SLOWLY rising or stable, AND below 1.7 psig.

B. Malfunctions None required C. Overrides Meters Event Pane Tag Title Value Activate Deactivate I (ramp rate) Time (sec) Time (sec) 13/5min E1 XU-3 G5B02G15 Main Stack Radiation OSEC N/A Trigger 1 Q6225LGT CAC-V23 Green Lamp =False D. Special Instructions Secure Drywell Coolers 2C and 2D Fans 1 and 2 and allow drywell pressure to rise to

~0.6 psig as indicated on CAC-PI-2685-1 on XU-51, then restart Drywell Coolers 2D Fan 2 and allow Drywell pressure to stabilize. Override Drywell Cooler 2C Fans 1 and 2 and Drywell Cooler 2D Fan 1 control switches OFF.

LOT-SIM-JP-010-A02 Page 2 of 12 Rev.3

Vent the Drywell per OP-1 0 w/ Stack Rad Monitor Increase >50%

SAFETY CONSIDERATIONS:

NONE EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee, once it is demonstrated he/she knows the correct procedure.

2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. The Unit is operating at full power.

2. Drywell pressure is above normal due to a partial loss of Drywell Cooling.

3. AOP-14.0 has been entered.

4. Standby Gas Treatment System is in the Standby Alignment.

5. The plant stack radiation monitor is in service and CAC-CS-5519, CAC Purge Vent Isolation Override is in OFF.

6. Temporary suppression chamber to drywell vacuum breaker monitoring is in service.

7. Immediate Drywell venting is required.

INITIATING CUE:

The Unit SCO directs you to vent the Drywell via Standby Gas Treatment, and to inform him when drywell pressure has been reduced below 0.5 psig.

LOT-SI M-JP-01 0-A02 Page 3 of 12 Rev.3

Vent the Drywell per OP-1 0 wi Stack Rad Monitor Increase >50%

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain current revision of OP-1 0, Section 8.2.

Current revision of OP-10, Section 8.2 is obtained.

SAT/UNSAT*

Time Started: _ _ __

Step 2 - Record D12-RR-R6008, STACK RAD MONITOR, digital point display.

Value for D12-RR-R600B recorded in OP-10. (Step 8.2.2.1)

. SATIUNSAT*

Step 3 - Add 0.17 to the value to obtain the logarithmic equivalent of a 50% increase in stack radiation monitor reading and record result.

Value recorded in OP-10 of initial reading + 0.17 (1.06 + 0.17 = 1.23)

(Step 8.2.2.2 and 8.2.2.4)

SAT/UNSAT*

Step 4 - Monitor Stack Rad Monitor, D12-RM-R6008, for increase in activity during venting.

D12-RM-R600B periodically monitored. (Step 8.2.2.5).

SATIUNSAT*

LOT-SIM-JP-010-A02 Page 4 of 12 Rev.3

Vent the Drywell per OP-1 0 wI Stack Rad Monitor Increase >50%

Step 5 - CLOSE REACTOR BUILDING SBGT TRAIN 2A INLET VALVE, VA-2D-BFV-RB.

VA-2D-BFV-RB indicates fully closed. (Step 8.2.2.8)

- CRITICAL STEP ** SATIUNSAT*

Step 6 - CLOSE REACTOR BUILDING SBGT 2B INLET VALVE, VA-2H-BFV-RB.

VA-2H-BFV-RB indicates fully closed. (Step 8.2.2.9)

- CRITICAL STEP ** SAT/UNSAT*

Step 7 - OPEN SBGT DW SUeT DAMPER, VA-2F-BFV-RB.

VA-2F-BFV-RB, indicates open. (Step 8.2.2.10)

- CRITICAL STEP ** SAT/UNSAT*

Step 8 - OPEN SUPP POOL PURGE EXH VLV, CAC-V172 CAC-V172 indicates full open. (Step 8.2.2. 11a)

NAISAT/UNSAT*

Step 9 - OPEN TORUS PURGE EXHAUST VLV, CAC-V22.

CAC-V22 indicates full open. (Step 8.2.2.11 b)

NAISAT/UNSAT*

LOT-SIM-JP-010-A02 Page 5 of 12 Rev.3

Vent the Drywell per OP-10 wI Stack Rad Monitor Increase >50%

Step 10 - CLOSE SUPP POOL PURGE EXH VLV, CAC-V172.

CAC-V172 indicates full closed (Step 8.2.2.12a)

NAISAT/UNSAT*

Step 11 - Close TORUS PURGE EXHAUST VLV, CAC-V22.

CAC-V22 indicates full closed (Step 8.2.2.12b)

NAISAT/UNSAT*

Step 12 - OPEN DW PURGE EXH VALVE, CAC-V9.

CAC-V9 indicates full open. (Step 8.2.2. 13a)

- CRITICAL STEP ** SAT/UNSAT*

Step 13 - OPEN DW PURGE EXH VALVE, CAC-V23.

CAC-V23 indicates full open. (Step 8.2.2. 13b)

- CRITICAL STEP ** SAT/UNSAT*

Step 14 - OPEN DW HEAD PURGE EXH VLV, CAC-V49.

CAC-V49 indicates full open. (Step 8.2.2. 13c)

SAT/UNSAT*

LOT-SIM-JP-010-A02 Page 6 of 12 Rev.3

Vent the Drywell per OP-1 0 wI Stack Rad Monitor Increase >50%

Step 15 - OPEN OW HEAD PURGE EXH VLV, CAC-V50.

CAC-V50 indicates full open. (Step 8.2.2. 13d)

SAT/UNSAT*

Step 16 - Monitor Main Stack Rad Monitor and determine reading has risen by >50%.

Determines Main Stack Rad Monitor reading has risen by>. 17 (50%).

- CRITICAL STEP ** SAT/UNSAT*

Step 17 - CLOSE OW PURGE EXH VLV, CAC-V23.

CAC-V23 indicates full closed. (Step 8.2.2. 14a)

- CRITICAL STEP ** SAT/UNSAT*

Step 18 - CLOSE DRYWELL PURGE EXH VALVE, CAC-V9.

CAC-V9 indicates full closed. (Step 8.2.2. 14b)

- CRITICAL STEP ** SATIUNSAT*

Step 19 - ENSURE OW HEAD PURGE EXH VLV, CAC-V49, IS CLOSED.

CAC-V49 indicates full closed. (Step 8.2.2. 14c)

- CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-010-A02 Page 7 of 12 Rev.3

Vent the Drywell per OP-10 wI Stack Rad Monitor Increase >50%

Step 20 - ENSURE DW HEAD PURGE EXH VLV, CAC-V50, IS CLOSED.

CAC-V50 indicates full closed. (Step 8.2.2. 14d)

- CRITICAL STEP ** SAT/UNSAT*

Step 21 - CLOSE SBGT DW SUCT DAMPER, VA-2F-BFV-RB.

VA-2F-BFV-RB indicates full closed. (Step 8.2.2.15)

- CRITICAL STEP ** SAT/UNSAT*

Step 22 - OPEN SBGT TRAIN 2B REACTOR BUILDING SUCTION VALVE, VA-2H-BFV-RB.

VA-2H-BFV-RB indicates full open. (Step 8.2.2.16)

SAT/UNSAT*

Step 23 - OPEN SBGT TRAIN 2A REACTOR BUILDING SUCTION VALVE, VA-2D-BFV-RB.

VA-2D-BFV-RB indicates full open. (Step 8.2.2.17)

SAT/UNSAT*

Step 24 - Confirm all suppression chamber to drywell vacuum breakers are closed.

All Suppression Chamber to Drywell vacuum breakers verified closed.

(Step 8.2.2.18)

SAT/UNSAT*

LOT-SIM-JP-010-A02 Page 8 of 12 Rev.3

Vent the Drywell per QP-1 0 wI Stack Rad Monitor Increase >50%

Step 25 - Notify E&RC to sample containment.

E&RC notified. . (Step 8.2.2.7b)

SATIUNSAT*

Step 26 - Notify E&RC to perform E&RC 2020, Noble Gas Instantaneous Release Rate Determination ..

E&RC notified. (Step 8.2.2.7c)

SATIUNSAT*

Step 27 - Inform Unit SCQ venting is secured due to increase of 50% in Main Stack Rad Monitor reading.

Unit SCQ is informed venting is secured due to increase of 50% in Main Stack

. Rad Monitor reading.

SAT/UNSAT*

Comments required for any step evaluated as UNSAT.

Time completed: _ _ __

LQT-SIM-JP-010-A02 Page 9 of 12 Rev.3

Vent the Drywell per OP-1 0 wi Stack Rad Monitor Increase >50%

LIST OF REFERENCES RELATED TASKS:

261 00881 01, Perform Normal Primary Containment Venting.

KlA REFERENCE AND IMPORTANCE RATING:

261000 A4.04 3.3/3.4, Ability to manually operate and monitor Primary Containment Pressure.

REFERENCES:

20P-10, Sect. 8.2 Rev 65 TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev 2):

Safety Function 9, Radioactivity Release REASON FOR REVISION:

Formatting and incorporation of comments LOT-SIM-JP-010-A02 Page 10 of 12 Rev.3

Vent the Drywell per OP-1 0 wI Stack Rad Monitor Increase >50%

Time Required for Completion: --.1L Minutes (approximate).

111111 un mI nnm APPLICABLE METHOD OF TESTING Performance: Simulate Actual ./ Unit:

Setting: Control Room ./ Simulator ./ (Not applicable to In-Plant JPMs)

Time Critical: Yes No ./ Time Limit N/A Alternate Path: Yes No EVALUATION Trainee: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass _ _ Fail --

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure?: Yes _ _ No _ __

(Each Student should verify one JPM per evaluation set)

Comments:

Comments reviewed with Student Evaluator Signature: Date: _ _ _ _ _ __

LOT-SIM-JP-010-A02 Page 11 of 12 Rev.3

TASK CONDITIONS:

1. The Unit is operating at full power.

2. Drywell pressure is above normal due to a partial loss of Drywell Cooling.

3. AOP-14.0 has been entered.

4. Standby Gas Treatment System is in the Standby Alignment.

5. The plant stack radiation monitor is in service and CAC-CS-5519, CAC Purge Vent Isolation Override is in OFF.

6. Temporary suppression chamber to drywell vacuum breaker monitoring is in service.

7. Immediate Drywell venting is required.

INITIATING CUE:

The Unit SCO directs you to vent the Drywell via Standby Gas Treatment, and to inform him when drywell pressure has been reduced below 0.5 psig.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR S-3 LESSON TITLE: Recovery From Recirculation Pump Runback - Speed Control Failure LESSON NUMBER: LOT-SIM-JP-002-A06 REVISION NO: 2

Recovery From Recirculation Pump Runback - Speed control Failure SIMULATOR SETUP Initial Conditions

1. Recommended Initial Conditions IC 13 Rx. Pwr. 100%

Core Age MOC

2. Required Plant Conditions Recirculation Pumps at Limiter #1 and in the Scram Avoidance Region of OENP-24, Thermal Limitations Map. OPRM Trip Enabled annunciator in ALARM.

Malfunctions Event System Tag Title Value Activate Deactivate (ramp rate) Time (sec) Time (sec)

A RC RC024F Recirc Pump A Runback To Limiter #1 N/A OSEC 30 SEC A RC RC025F Recirc Pump B Runback To Limiter #1 N/A OSEC 30 SEC Overrides Pots Event Pane Tag Title Value Activate Deactivate I (ramp rate) Time (sec) Time (sec)

E1* P603 P2740A11 Recirc Pump B Speed Control 1/120 SEC OSEC N/A E2 P603 P2739A11 Recirc Pump A Speed Control 1/120 SEC OSEC N/A

Set Trigger E1 Conditional; K2716A = Reset

- Set Trigger E2 Conditional; K2711 PS8 =Reset Special Instructions Initiate malfunctions and allow plant conditions to stabilize. Verify Operation is in the SCRAM AVOIDANCE REGION.

LOT-SIM-JP-002-A06 Page 2 of 9 Rev. 02

Recovery From Recirculation Pump Runback - Speed control Failure SAFETY CONSIDERATIONS:

NONE EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee. When the trainee has identified the proper procedure and section to be used a working copy of the procedure WILL be given to the trainee.

2. If this is the first set of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee.

3. When the first Recirc Pump is reset the pump speed will increase. The operator should lock the scoop tube per immediate actions of AOP-03.0. If speeds are within 20%, no further action is required, otherwise the Recirculation Pump must be shutdown.

Read the following to the trainee TASK CONDITIONS:

1. Recirculation Pumps A and B have run back and the cause has been corrected.

2. Another operator is available and will monitor Nuclear Instrumentation.

INITIATING CUE:

You are directed by the Unit seo to reset the Recirculation Pump runback signals to allow Reactor Recirculation flow to be raised. Inform the Unit seo when the runback signals have been reset.

LOT-Sl M-JP-002-A06 Page 3 of 9 Rev. 02

Recovery From Recirculation Pump Runback - Speed control Failure PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain current revision of OP-02, Section 8.3.

Current revision of OP-02, Section 8.3 obtained and verified if applicable.

SAT/UNSAT*

Time Start: _ _ _ _ _ __

Step 2 - Adjust potentiometer on Recirc Pump A Speed Control until the percent speed demand signal decreases below the runback limit.

Speed demand of Recirc Pump A is reduced until the speed demand is less than or equal to the runback limit.

- CRITICAL STEP ** SAT/UNSAT*

Step 3 - Depress the Recirc Runback reset push button for Recirc Pump A.

Runback is reset without uncontrolled rise in pump flow.

- CRITICAL STEP ** SAT/UNSAT*

Step 4 - Adjust potentiometer on Recirc Pump B Speed Control until the speed demand signal decreases below the runback limit.

Speed demand of Recirc Pump B is reduced until the speed demand is less than or equal to the runback limit.

- CRITICAL STEP ** SAT/UNSAT*

LOT-S IM-J P-002-A06 Page 4 of 9 Rev. 02

Step 5 - Depress the Recirc Runback reset push button for Recirc Pump B.

Runback is reset.

- CRITICAL STEP ** SAT/UNSAT*

Step 6 - Lock the Recirc Pump scoop tube to terminate the uncontrolled rise in pump speed.

Scoop tube for Recirc Pump is locked, pump speed stops rising before violating mismatch criteria.

- CRITICAL STEP ** SAT/UNSAT*

Step 7 - Determine Recirc Pump speed mismatch.

Recirc Pump speeds are verified to be within allowable limits (~7.5 Mlbslhr)

OR Recirc Pump speeds are verified to be outside of allowable limits SAT/UNSAT*

LOT-SIM-JP-002-A06 Page 5 of 9 Rev. 02

Recovery From Recirculation Pump Runback - Speed control Failure Step 8 - Inform Unit sea of pump speed mismatch.

Unit sea informed of pump speed mismatch.

SAT/UNSAT*

Comments required for any step evaluated as UNSAT.

Time Completed: _ _ _ _ _ __

LOT-S IM-JP-002-A06 Page 6 of9 Rev. 02

Recovery From Recirculation Pump Runback - Speed control Failure RELATED TASKS:

2020158401 Respond To A Recirc Pump Flow Control Failure Rising Per AOP-03.0.

KIA REFERENCE AND IMPORTANCE RATING:

295014 AA 1.02 3.6/3.8.

Ability to operate/monitor Recirc Flow Control System As It Applies To Inadvertent Reactivity Addition.

REFERENCES:

20P-02, Section 8.3 OAOP-03.0, Positive Reactivity Addition TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev. 2)

Safety Function 1, Reactivity Control (Recirculation Flow Control System)

REASON FOR REVISION:

LOT-S IM-J P-002-A06 Page 7 of 9 Rev. 02

Recovery From Recirculation Pump Runback - Speed control Failure Time required for Completion: 15 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: _2_

Setting: Control Room Simulator 1 (Not applicable to In-Plant JPMs)

Time Critical: Yes No -.lL Time Limit N/A Alternate Path: Yes X No EVALUATION Trainee:

JPM: Pass - - Fail _ _

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure Revision? Yes No ____

(Each Student should verify one JPM per evaluation set.)

Comments:

Comments Reviewed With Trainee Evaluator Signature: ____________________________ Date: ____________

LOT-SI M-JP-002-A06 Page 8 of 9 Rev. 02

TASK CONDITIONS:

1. Recirculation Pumps A and B have run back and the cause has been corrected.

2. Another operator is available and will monitor Nuclear Instrumentation.

INITIATING CUE:

You are directed by the Unit SeQ to reset the Recirculation Pump runback signals to allow Reactor Recirculation flow to be raised. Inform the Unit SeQ when the runback signals have been reset.

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR S-4 LESSON TITLE: HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

LESSON NUMBER: LOT-SIM-JP-019-14 REVISION NO: 0

HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

SIMULATOR SETUP Recommended Initial Conditions IC-11 100%, BOC Event Triggers E1 - Activates all malfunctions/overrides when prompted by evaluator Malfunctions A, ES040F, HPCI Fail To Auto Start A, ES053F - E41-F002 Fail To Auto Close A, ES054F - E41-F003 Fail To Auto Close E1, ES047F - HPCI Stm Brk HPCI Room, 1%,0 SEC Overrides Lamps E1, P601, Q1112SWL, Auto Isol Sig A White, ON E1, P601, Q1111 SWL, Auto Isol Sig B White, ON Alarms E1, P601, ZA135, HPClisol Trip Sig A, ON E1, P601, ZA145, HPClisol Trip Sig B , ON E1, P601, ZA152, HPCI Turb Exh Diaph Press Hi, On Special Instructions

1. Scram the Reactor and close MSIV's

2. Perform scram immediate actions

3. Ensure RPV level is stable and >LL2 LOT-SIM-JP-019-14 Page 2 of 9 REV. 0

HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

SAFETY CONSIDERATIONS:

None.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL NOT be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. The reactor has scrammed due to MSIV closure.

2. RPV water level is stable.

3. HPCI is not required for RPV level control.

INITIATING CUE:

You are directed by the Unit SCQ to start HPCI for pressure control to lower pressure to 800 psig per the Hard Card and inform the Unit SCQ when the actions are complete.

LQT-SIM-JP-019-14 Page 3 of 9 REV. 0

HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain Hard Card for HPCI Injection In EOPs.

Hard Card for HPC//njection obtained.

SAT/UNSAT*

Time Started: _ _ _ __

Initial Reactor Pressure: _ _ _ __

Step 2 - Ensure HPCI auto initiation is reset.

HPC/ auto initiation is reset.

SAT/UNSAT*

Step 3 - Ensure Auxiliary Oil Pump is not running.

Auxiliary Oil Pump verified not running.

SAT/UNSAT*

Step 4 - Ensure E41-V9 and E41-V8 are closed.

E41- V9 and E41-VB indicate closed.

SAT/UNSAT*

Step 5 - Open E41-F011.

E41-F011 indicates full open.

- CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-019-14 Page 4 of9 REV. 0

HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

Step 6 - Open E41-F059.

E41-FOS9 indicates full open.

- CRITICAL STEP ** SAT/UNSAT*

Step 7 - Start Vacuum Pump and leave in start Vacuum Pump is running SAT/UNSAT*

Step 8 - Open E41-FOO 1.

E41-F001 indicates full open.

- CRITICAL STEP ** SAT/UNSAT*

Step 9 - Start Auxiliary Oil Pump and Leave in START.

Auxiliary Oil Pump control switch in the START position.

- CRITICAL STEP ** SAT/UNSAT*

Step 10 - Throttle open E41-F008 to maintain desired reactor pressure.

E41-FOOB indicates dual indication.

- CRITICAL STEP ** SATIUNSAT*

Final Reactor Pressure: _ _ _ __

Step 11 - Diagnose indications of a HPCI Exhaust Diaphragm rupture.

Determined the exhaust diaphragm has ruptured.

SAT/UNSAT*

LOT-SIM-JP-019-14 Page 5 of9 REV. 0

HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

Step 12 - Determine HPCI has failed to auto isolate and manually isolate HPCI by closing E41-F002 and F003.

E41-F002 or E41-F003 indicate full closed.

- CRITICAL STEP ** SAT/UNSAT*

Step 13 - Inform Unit SCO HPCI is isolated and unavailable for pressure control.

seo informed HPCI is unavailable for injection.

SAT/UNSAT*

Comments required for any step evaluated as UNSAT.

Time completed: _ _ _ __

LOT-SIM-JP-019-14 Page 6 of 9 REV. 0

HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

RELATED TASKS:

2062008401, Place HPCI in Reactor Pressure control from the standby lineup per OP-19 KIA REFERENCE AND IMPORTANCE RATING:

295025 EA 1.04 3.8/3.9 Ability to operate and/or monitor the following as they apply to High Reactor Pressure:

HPCI (plant specific)

REFERENCES:

20P-19, Section 8.2 Hard Card S/1 019, HPCI Pressure Control In EOPs TOOLS AND EQUIPMENT:

None.

SAFETY FUNCTION (from NUREG 1123, Rev 2.)

3 - Pressure Control (HPCI)

REASON FOR REVISION:

Modified JPM to have exhaust diaphragm failure.

LOT-SIM-JP-019-14 Page 7 of 9 REV. 0

HPCI Start in Pressure Control Per The Hard Card - Exhaust Diaphragm Failure.

Vailidation Time: -..1L Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual v Unit: _2_

Setting: Control Room Simulator_v_{ Not applicable to In-Plant JPMs )

Time Critical: Yes No v Time Limit N/A Alternate Path: Yes v No EVALUATION Trainee: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass _ _ Fail _ _

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure?: Yes _ _ No _ __

(Each Student should verify one JPM per evaluation set.)

Comments:

Comments reviewed with Student Evaluator Signature: Date: _ _ _ _ _ __

LOT-SIM-JP-019-14 Page 8 of 9 REV. 0

TASK CONDITIONS:

1. The reactor has scrammed due to MSIV closure.

2. RPV water level is stable.

3. HPCI is not required for RPV level control.

INITIATING CUE:

You are directed by the Unit sca to start HPCI for pressure control to lower pressure to 800 psig per the Hard Card and inform the Unit sca when the actions are complete.

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR S-5 LESSON TITLE: RCIC Start Using the Hard Card - Flow Controller Failure LESSON NUMBER: LOT-SIM-JP-016-A02 REVISION NO: 3

RCIC Start Using the Hard Card - Flow Controller Failure SIMULATOR SETUP Recommended Initial Conditions IC-11 Rx Pwr 100%

BOC Required Plant Conditions:

RPV level <105 inches" RFPTs tripped and HPCI not available Triggers:

1 - RCIC Flow Control Failure Malfunctions:

Active, ES041 F (RCIC Auto Start Fail)

Overrides:

Trigger 1, Switch, P601, K1 H12E, RCIC FC Setpoint Decrease, PUSH Remotes None Special Instructions:

Place HPCI Aux Oil Pump in PTL. Trip RFPTs to reduce RPV level below +105 inches.

Complete scram immediate actions. Start SBGT.

When RPV level is <105 inches (LL2), place simulator in Freeze.

LOT-OJT-J P-002-AO 1 Page 2 of 9 REV. 3

RCIC Start Using the Hard Card - Flow Controller Failure SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL NOT be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

l1li11111 I TI III Read the following to trainee.

TASK CONDITIONS:

1. Both Reactor Feed Pumps have tripped.

2. HPCI is not available

3. Reactor Vessel Level has decreased to less than LL2.

4. SBGT is running.

5. RCIC has failed to auto start.

INITIATING CUE:

You are directed to manually start RCIC per the Hard Card, raise RCIC flow to 500 gpm and inform the Unit SCO when actions to start RCIC per the Hard Card are complete.

LOT-OJT-JP-002-A01 Page 3 of 9 REV. 3

RCIC Start Using the Hard Card - Flow Controller Failure PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain Hard Card RCIC Operations For EOPs.

Hard Card RC/C Operations For EOPs obtained at P601.

SAT/UNSAT*

Time Started: _ _ _ __

Step 2 - Ensure E51-V8 (valve position), E51-V8 (actuator position), and E51-V9 indicate OPEN.

E51-VB (va/ve position), E51-VB (actuator position), and E51-V9 verified open.

SAT/UNSAT*

Step 3 - OPEN E51-F046.

E51-F046 is full OPEN (cooling water valve).

- CRITICAL STEP ** SAT/UNSAT*

Step 4 - Start Vacuum Pump and leave switch in START.

Vacuum Pump running with switch in START.

SAT/UNSAT*

Step 5 - OPEN E51-F045.

E51-F045 is full OPEN.

- CRITICAL STEP ** SAT/UNSAT*

Step 6 - OPEN E51-F013.

E51-F013 is full OPEN.

- CRITICAL STEP ** SAT/UNSAT*

LOT-OJT-JP-002-AO1 Page 4 of9 REV. 3

RCIC Start Using the Hard Card - Flow Controller Failure Step 7 - Ensure RCIC turbine starts and comes up to speed as directed by RCIC flow control.

RCIC Turbine speed observed to come up to speed.

SAT/UNSAT*

Step 8 - Adjust RCIC flow controller to obtain desired flow rate.

RCIC controller adjusted to achieve flow rate 500 gpm.

- CRITICAL STEP ** SAT/UNSAT*

Step 9 - Recognize failure of RCIC, Flow Controller, E51-FIC-R600, and place E51-FIC-R600, in Manual and raise output to re-establish RCIC flow.

E51-FIC-R600, flow controller, in Manual and output raised to achieve 500 gpm.

- CRITICAL STEP ** SAT/UNSAT*

LOT-OJT-JP-002-A01 Page 5 of 9 REV. 3

RCIC Start Using the Hard Card - Flow Controller Failure Step 10 - Ensure E51-F019 CLOSED with flow >80 gpm.

E51-F019 verified CLOSED.

SAT/UNSAT*

Step 11 - Ensure E51-F025, E51-F026, E51-F004, and E51-F005 are CLOSED.

E51-F025, E51-F026, E51-F004, and E51-F005 verified CLOSED.

SAT/UNSAT*

Step 12 - START SBGT (OP-10)

SBGT fans verified to be running.

SAT/UNSAT*

Step 13 - ENSURE SGT-V8 and SGT-V9.

SGT-V8 and SGT-V9 verified to be OPEN.

SAT/UNSAT*

Step 14 - Ensure barometric condenser condensate pump operates.

Barometric condenser condensate pump operation verified.

SAT/UNSAT*

Step 15 - Inform Unit SCO RCIC is injecting to the RPV with the flow controller in Manual due to failure of automatic flow control.

Unit SCO informed RCIC injecting in Manual with auto flow controller failed.

SAT/UNSAT*

Time Completed: _ _ _ __

Comments required for any step evaluated as UNSAT.

LOT-OJT-J P-002-AO 1 Page 6 of9 REV. 3

RCIC Start Using the Hard Card - Flow Controller Failure RELATED TASKS:

2170038101, Manually Startup The RCIC System Per OP-16 KIA REFERENCE AND IMPORTANCE RATING:

295031 EA1.054.3/4.3 Ability to operate and/or monitor the following as they apply to Reactor Low Water Level:

Reactor Core Isolation System (plant specific)

REFERENCES:

S/969 (RCIC Hard Card)

OP-16, Section 5.3 TOOLS AND EQUIPMENT:

None.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

2 - Inventory Control REASON FOR REVISION:

Formatting and comment incorporation LOT-OJT-J P-002-AO 1 Page 7 of 9 REV. 3

RCIC Start Using the Hard Card - Flow Controller Failure Validation Time: ...1L Minutes (approximate).

TI 11111 In APPLICABLE METHOD OF TESTING Performance: Simulate Actual 'VI Unit: 2 Setting: Control Room Simulator~ ( Not applicable to In-Plant JPMs)

Time Critical: Yes No 'VI Time Limit N/A Alternate Path: Yes 'VI No EVALUATION Trainee: --------------------------------

JPM: Pass _ _ Fail Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure Revision?: Yes No ____

(Each Student should verify one JPM per evaluation set.)

1 III n 1111 n mnnn II Comments Comments reviewed with Student Evaluator Signature: Date: ___________

LOT-OJT-J P-002-AO 1 Page 8 of9 REV. 3

TASK CONDITIONS:

1. Both Reactor Feed Pumps have tripped.

2. HPCI is not available

3. Reactor Vessel Level has decreased to less than LL2.

4. SBGT is running.

5. RCIC has failed to auto start.

INITIATING CUE:

You are directed to manually start RCIC per the Hard Card, raise RCIC flow to 500 gpm and inform the Unit SCQ when actions to start RCIC per the Hard Card are complete.

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR S-6 LESSON TITLE: Manual Transfer Of E Bus From DG To Normal Feeder.

LESSON NUMBER: LOT-SIM-JP-050-A02 REVISION NO: 2

Manual Transfer Of E Bus From OG To Normal Feeder Recommended Simulator Setup Initial Conditions IC-11 Triggers None Malfunctions/Overrides None Special instructions

1. Start OG3 and tie to E3, pick up E3 load on OG3 and open the master/slave from 20 to E3.

2. Ensure all motors fed from E3 are not running (Le. CRO, CSW, NSW).

3. Place OG3 in Auto Mode of operation (output breaker will remain closed).

4. Start loads on OG3 to pick up approximately 3200 - 3500 KW. (CRO A, CSW A, NSW A, RHR Loop A in suppression pool cooling)

5. Return OG3 frequency to approximately 60 hertz.

LOT-S IM-J P-050-A02 Page 2 of 10 Rev.2

Manual Transfer Of E Bus From DG To Normal Feeder SAFETY CONSIDERATIONS:

None.

EVALUATOR NOTES: (Do not read to examinee)

1. The applicable procedure section WILL provided to the examinee after the appropriate procedure section is identified.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the examinee.

Read the following to examinee.

TASK CONDITIONS:

1. Diesel Generator #3 is supplying power to 4160 VAC Bus E3.

2. Bus 2D is energized.

3. The dispatcher has been notified that the E Bus power is being shifted to the normal feeder.

INITIATING CUE:

You are directed by the Unit SCO to perform the actions of OOP-50.1 for control room manual transfer of Bus E3 from the Diesel Generator to the normal feeder and inform the Unit seo when actions are complete.

LOT-SI M-JP-050-A02 Page 3 of 10 Rev.2

Manual Transfer Of E Bus From OG To Normal Feeder PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain a current revision of OOP-50.1, Section 8.6.

Current Revision of OOP-50. 1, Section 8.6 obtained. Examinee may refer to figure 1 SAT/UNSAT*

Time Started: - - - - -

Step 2 - Reduce diesel generator load or raise diesel generator frequency as necessary to prevent RPS EPA breaker trip.

OG3 frequency is raised (by adjusting the governor in the raise direction).

- CRITICAL STEP ** SAT/UNSAT*

Step 3 - Place OG3 in control room manual.

OG3 is verified to be in control room manual.

- CRITICAL STEP ** SAT/UNSAT*

Step 4 - Place the synchroscope to ON for Bus 20 to E3 Bus 20 to E3 synchroscope switch is in ON.

- CRITICAL STEP ** SAT/UNSAT*

LOT-S IM-JP-050-A02 Page 4 of 10 Rev.2

Manual Transfer Of E Bus From OG To Normal Feeder Step 5 - Ensure incoming and running voltages are matched.

Incoming and running voltages are matched as indicated on the incoming and running voltmeters on XU-1.

SAT/UNSAT*

Step 6 - Adjust the OG3 governor control switch as necessary so the synchroscope is rotating slowly in the SLOW direction.

Synchroscope is rotating slowly in the SLOW direction.

SAT/UNSAT*

Step 7 - When the synchroscope is at 12 o'clock position, Then place and hold the control switch for Bus 20 to E3 in CLOSE until both MSTR and SLAVE breakers indicate closed.

Bus 20 to E3 Master and Slave breakers are both closed.

- CRITICAL STEP ** SAT/UNSAT*

Step 8 - Confirm synchroscope remains at 12 o'clock.

Synchroscope remains at 12 o'clock.

SAT/UNSAT*

Step 9 - Place synchroscope for Bus 20 to E3 in OFF.

Synchroscope for Bus 20 to E3 is in OFF.

SAT/UNSAT*

Step 10 - Lower DG3 load to between 450 and 550 KW by placing the governor switch in LOWER while maintaining generator vars with voltage adjusting rheostat OG3 load is between 450 and 550 KW

- CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-050-A02 Page 5 of 10 Rev.2

Manual Transfer Of E Bus From DG To Normal Feeder Step 11 - Open DG3 to E3 output breaker.

DG3 to E3 breaker (AI5) is open.

- CRITICAL STEP ** SATIUNSAT*

Step 12 - Observe the following indications:

a. Breaker open in accordance with indicating lights.

Breaker open indication observed.

SAT/UNSAT*

b. Emergency Bus voltage remains constant.

Emergency Bus voltage observed to remain constant.

SAT/UNSAT*

c. Diesel generator load and amps are zero.

DG load and amps observed to be zero.

SATIUNSAT*

d. NO LOAD and AVAIL lights are illuminated.

No Load and Avail lights observed to be on SAT/UNSAT*

Step 13 - Unit seo informed actions complete to transfer Bus E3 from DG to normal.

seo informed actions to transfer E3 from DG to normal are complete.

SAT/UNSAT*

LOT-SIM-JP-050-A02 Page 6 of 10 Rev.2

Manual Transfer Of E Bus From DG To Normal Feeder

Comments required for any step evaluated as UNSAT.

Time Completed: _ _ __

LOT-5 IM-JP-050-A02 Page 7 of 10 Rev.2

Manual Transfer Of E Bus From DG To Normal Feeder RELATED TASKS:

262017B101, Complete A Control Room Manual Transfer Of Emergency Bus Supply From Diesel Generator To Normal Feeder Per OP-50.1 KIA REFERENCE AND IMPORTANCE RATING:

264000 A4.05 3.6/3.7 Ability to manually operate and/or monitor in the control room: Transfer of emergency generator (with load) to grid.

REFERENCES:

OOP-50.1 , Section 8.6 TOOLS AND EQUIPMENT:

None.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

6 - Electrical (Emergency Generators)

REASON FOR REVISION:

Formatting and comment incorporation LOT-SIM-JP-050-A02 Page 8 of 10 Rev.2

Manual Transfer Of E Bus From DG To Normal Feeder Validation Time:~ Minutes (approximate).

In 17 rrn n APPLICABLE METHOD OF TESTING Performance: Simulate Actual ..; Unit: 2 Setting: Control Room Simulator~ (Not applicable to In-Plant JPMs)

Time Critical: Yes No ..; Time Limit N/A Alternate Path: Yes No ..;

EVALUATION Examinee: _______________

JPM: Pass Fail _ _

Remedial Training Required: Yes No _ _

Did Examinee Verify Procedure?: Yes No _ __

(Each Student should verify one JPM per evaluation set.)

Comments:

Comments reviewed with Student Evaluator Signature: Date: _ _ _ _ _ __

LOT-S IM-JP-050-A02 Page 9 of 10 Rev.2

TASK CONDITIONS:

1. Diesel Generator #3 is supplying power to 4160 VAC Bus E3.

2. Bus 20 is energized.

3. The dispatcher has been notified that the E Bus power is being shifted to the normal feeder.

INITIATING CUE:

You are directed by the Unit SCQ to perform the actions of OQP-50.1 for control room manual transfer of Bus E3 from the Diesel Generator to the normal feeder and inform the Unit SCQ when actions are complete.

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR S-7 LESSON TITLE: Restore Nitrogen Backup System after an Isolation LESSON NUMBER: LOT-SIM-JP-046-001 REVISION NO: 0

Restore Nitrogen Backup System after an Isolation SIMULATOR SETUP Recommended Initial Conditions IC-11 Rx Pwr 100%

BOC Required Plant Conditions:

Triggers:

Malfunctions:

Insert an inadvertent CS initiation and then remove the malfunction.

Overrides:

Remotes None Special Instructions:

Verify auto actions occurred for the inadvertent CS initiation signal.

Turn both Core Spray pumps off.

LOT-S IM-J P-046-00 1 Page 2 of 9 REV. 0

Restore Nitrogen Backup System after an Isolation SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL NOT be provided to the trainee. The applicable procedure section can be provided to the student after they have identified the correct procedure that is needed.

2. Do not provide the student with OP-18 until asked for.

3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. Core Spray instrumentation was bumped causing an inadvertent initiation signal.

2. Auto actions have been verified.

3. Core Spray Pumps have been secured.

4. Prerequisites of OOP-46 are all met.

INITIATING CUE:

You are directed to Restore the Nitrogen Backup System in accordance with OOP-46.

Inform the Unit SCO when the Nitrogen Backup System is restored to normal.

LOT-SI M-J P-046-00 1 Page 3 of9 REV. 0

Restore Nitrogen Backup System after an Isolation PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain copy of OOP-46 Section 8.10 to restore Nitrogen Backup System to normal.

Section 8. 10 of OOP-46 is obtained.

SATIUNSAT*

TIME START: _ _ _ __

Step 2 - Verifies Initial conditions of OOP-46 Section 8.10.

Initial conditions are verified.

SAT/UNSAT*

LOT-S IM-JP-046-00 1 Page 4 of 9 REV. 0

Restore Nitrogen Backup System after an Isolation Step 3 -Perform the following two steps within 10 seconds of each other:

a. Depress both Initiation Signal/Reset pushbuttons, E21-CS-15A and E21-CS-15B and verify both white Initiation Signal Sealed-In lights go out Depresses push buttons and verifies white initiation lights are not lit.

(OP-46 step 8.10.2.1 or OP-18 step 7.1.5)

- CRITICAL STEP ** SAT/UNSAT*

b. Depress both Loop A and B LPCI Injection Signal/Reset pushbuttons, E11-CS-S26A and E11-CS-S26B, and verify both white Initiation Signal Sealed-In lights are out Verifies white initiation lights are not lit.

SATIUNSAT*

Step 4 - Verifies instrument air header pressure (IA-PI-724-1) is greater than 98 psig.

Verifies air header pressure is normal. (Step 8.10.2.2)

SAT/UNSAT*

Step 5 -Verifies that the following alarms are clear:

Alarms are clear. (Step 8.10.2.3)

UA-01 1-1 RB Instr Air Receiver 2A Press Low UA-01 1-2 RB Instr Air Receiver 2B Press Low SAT/UNSAT*

Step 6 - Momentarily place Div I Non-Intrpt RNA, RNA-SV-5262, control switch to the Override/Reset position, then to OPEN.

Control switch placed to overridelreset then back to open. (Step 8.10.2.4)

- CRITICAL STEP ** SAT/UNSAT*

LOT-S IM-J P-046-00 1 Page 5 of 9 REV. 0

Restore Nitrogen Backup System after an Isolation Step 7 - Ensures the following valve positions:

Valves in their appropriate position. (Step 8.10.2.4a/b)

SATIUNSAT*

Step 8 - Momentarily place Div" Non-Intrpt RNA, HNA-SV-5261, control switch to the Override/Reset position, then to OPEN.

Control switch placed to overridelreset then back to open. (Step 8.10.2.5)

- CRITICAL STEP ** SAT/UNSAT*

Step 9 - Ensures the following valve positions:

Valves in their appropriate position. (Step 8. 10.2. Sa/b)

SAT/UNSAT*

Step 10- Inform Unit SCO that Core Spray has been shutdown and Nitrogen Backup System is in normal alignment.

Unit sca informed.

SAT/UNSAT*

Comments required for any step evaluated as UNSAT.

Time completed: _ _ _ __

LOT-SIM-JP-046-001 Page 6of9 REV. 0

Restore Nitrogen Backup System after an Isolation RELATED TASKS:

278203B1 01, Restore the Backup Nitrogen System following an Auto Initiation Per OP-46.

KIA REFERENCE AND IMPORTANCE RATING:

232002 A4.03 3.6/3.5 Ability to manually operate and/or monitor in the control room: Reset system isolations.

REFERENCES:

OP-46, Section 8.10 Op-18, Section 7.

TOOLS AND EQUIPMENT:

None.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

5 - Containment Integrity REASON FOR REVISION:

New JPM.

LOT-SIM-JP-046-001 Page 7 of 9 REV. 0

Restore Nitrogen Backup System after an Isolation Validation Time: 14 Minutes (approximate).

I U III 1111 1111 APPLICABLE METHOD OF TESTING Performance: Simulate Actual \I Unit: _2_

Setting: Control Room Simulator~ ( Not applicable to In-Plant JPMs)

Time Critical: Yes No \I Time Limit N/A Alternate Path: Yes No \I EVALUATION Trainee: ________________

JPM: Pass - - Fail --

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure Revision?: Yes No _ __

(Each Student should verify one JPM per evaluation set.)

1II1IIRTF I m HI I II IFn Comments Comments reviewed with Student Evaluator Signature: ________________ Date: _ _ _ _ __

LOT-SIM-JP-046-001 Page 8 of9 REV. 0

TASK CONDITIONS:

1. Core Spray instrumentation was bumped causing an inadvertent initiation signal.

2. Auto actions have been verified.

3. Core Spray Pumps have been secured.

4. Prerequisites of OQP-46 are all met.

INITIATING CUE:

You are directed to Restore the Nitrogen Backup System in accordance with OQP-46.

Inform the Unit SeQ when the Nitrogen Backup System is restored to normal.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR S-8 LESSON TITLE: Bypass a Control Rod from the RWM Sequence LESSON NUMBER: LOT-SIM-JP-007-A01 REVISION NO: 2

Bypass A Control Rod From The RWM Sequence SIMULATOR SETUP IC-32 (suggested)

Triggers None Malfunctions None Overrides None Remote None Special Instructions Ensure rod 30-07 is full in.

Control Rod 30-07 will have to be un bypassed in the RWM PRIOR TO subsequent JPM administration.

Verify key is not in the RWM.

Resetting the simulator to the established IC for the JPM setup DOES NOT clear the bypassed rod in the RWM.

LOT-SIM-JP-007-A01 Page 2 of 9 REV. 2

Bypass A Control Rod From The RWM Sequence SAFETY CONSIDERATIONS:

None.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee after finding the appropriate section of the procedrue.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. Control Rod 30-07 has been fully inserted to suppress a fuel leak.

2. Control Rod 30-07 has not been bypassed in the Rod Worth Minimizer.

3. The RWM does not have a critical self test failure.

4. 2QP-07, Section 4.0 Prerequisites are met.

5. The Reactor Engineer has been notified and Technical Specifications have been reviewed.

INITIATING CUE:

The Unit SCQ directs you to bypass Control Rod 30-07 in the Rod Worth Minimizer and inform him when the rod has been bypassed.

LQT-SIM-JP-007-A01 Page 3 of 9 REV. 2

Bypass A Control Rod From The RWM Sequence PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain a copy of 20P-07, Section 8.13.

Current Revision of 20P-07, Section 8. 13 obtained.

SATIUNSAT*

Time Start: _ _ _ __

Step 2 - Obtain key to RWM Computer Display (P607 - Key #37).

Key for RWM Computer display obtained.

SAT/UNSAT*

Step 3 - Place RWM Computer Display keylock switch in the INOP position.

RWM Computer Display keylock switch is in INOP.

- CRITICAL STEP ** SAT/UNSAT*

Step 4 - Press the ETC soft key until Rod Bypass Options appears.

Rod Bypass Options is displayed.

SAT/UNSAT*

Step 5 - Press the Rod Bypass Options soft key.

Rod Bypass Options sQftkey is pressed.

- CRITICAL STEP ** SATIUNSAT*

LOT-SIM-JP-007-A01 Page 4 of 9 REV. 2

Bypass A Control Rod From The RWM Sequence Step 6 - Use Up/Down cursor to ensure correct ID of rod to bypass.

Rod 30-07 identified for bypassing.

- CRITICAL STEP ** SAT/UNSAT*

Step 7 - Press Bypass Rod softkey Bypass Rod softkey is pressed.

- CRITICAL STEP ** SAT/UNSAT*

Step 8 - Confirm the selected rod is added to the display of bypassed rods Bypassed Rod is displayed.

SAT/UNSAT*

Step 9 - Place RWM Computer Display to OPER (Operate).

RWM Computer Display is in OPER

- CRITICAL STEP ** SAT/UNSAT*

Step 10 - Press the Display Off softkey to extinguish the screen.

Display Off pressed.

SAT/UNSAT*

LOT-S IM-J P-007 -AO 1 Page 5 of 9 REV. 2

Bypass A Control Rod From The RWM Sequence Step 11 - Ensure annunciator Rod Block RWM/RMCS Sys Trouble (A-05 5-2) is clear.

Rod Block RWMIRMCS Sys Trouble alarm verified clear.

SAT/UNSAT*

Step 12 - Inform the Unit SCQ that Control Rod 30-07 is bypassed Unit SCQ informed Rod 30-07 is bypassed.

SAT/UNSAT*

Time completed: _ _ _ __

Comments required for any step evaluated as UNSAT.

LQT-SIM-JP-007-A01 Page 6 of9 REV. 2

Bypass A Control Rod From The RWM Sequence RELATED TASKS:

214201 B401 Bypass/unbypass a control rod from the Rod Worth Minimizer Computer Display KIA REFERENCE AND IMPORTANCE RATING:

201006 A2.0S 3.1/3.S Ability to use procedures to correct or control out of sequence rod movement.

REFERENCES:

20P-07 Rev. 87 TOOLS AND EQUIPMENT:

Key for RWM Computer Display.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

7 - Instrumentation REASON FOR REVISION:

Formatting.

LOT-S IM-JP-007-AO 1 Page 7 of 9 REV. 2

Bypass A Control Rod From The RWM Sequence Validation Time: --.1Q... Minutes (approximate).

UI APPLICABLE METHOD OF TESTING

- lin 11111 r I Performance: Simulate Actual v Unit: _2_

Setting: Control Room Simulator_v_ (Not applicable to In-Plant JPMs)

Time Critical: Yes No v Time Limit N/A Alternate Path: Yes No EVALUATION Trainee: --------------------------------

JPM: Pass _ _ Fail ____

Remedial Training Required: Yes No ___

Did Trainee Verify Procedure?: Yes No 7UIII n KF n u n 111.11 III Comments:

Comments reviewed with Student Evaluator Signature: _____________________________ Date: _________

LOT-SIM-JP-007-A01 Page 8 of9 REV. 2

TASK CONDITIONS:

1. Control Rod 30-07 has been fully inserted to suppress a fuel leak.

2. Control Rod 30-07 has not been bypassed in the Rod Worth Minimizer.

3. The RWM does not have a critical self test failure.

4. 2QP-07, Section 4.0 Prerequisites are met.

5. The Reactor Engineer has been notified and Technical Specifications have been reviewed.

INITIATING CUE:

The Unit SCQ directs you to bypass Control Rod 30-07 in the Rod Worth Minimizer and inform him when the rod has been bypassed.

ML090270042

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