Text

SONGS - 10-2005 - Final Reference Operating Exam
	ML060830508
Person / Time
Site:	San Onofre
Issue date:	10/28/2005
From:	; Operations Branch IV
To:	; Southern California Edison Co
References
	50-361/05-301, 50-362/05-301
	Download: ML060830508 (199)
	v • d • e

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO A.1.a INITIAL PLANT CONDITIONS Unit 2 has experienced a Loss of Forced Circulation/Loss of Offsite Power.

Recovery actions have commenced and SO23-12-7, Loss of Forced Circulation/Loss of Offsite Power, is in progress. Cooldown and Depressurization, Attachment 3 of SO23-12-11, has been started.

The Reactor tripped 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago.

T-120 level indication is 21.3%. T-121 level indication is 63.1%.

There are no other feedwater sources available.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform Attachment 16 of SO23-12-11, EOI Supporting Attachments, Determine the Time Until Shutdown Cooling is Required.

Page 1 of 8

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO A.1.a SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SO 10-05 JPM NRC RO A.1.a JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 2637 TASK DESCRIPTION Determine the time until Shutdown Cooling is required.

KA NUMBER: 025-AK1.01 KA VALUES: RO 3.9 SRO 4.3 10CFR55.45 APPLICABILITY: 7

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 16, Determine the Time Until Shutdown Cooling is Required, Rev. 3 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 3 Compared against SO23-12-7, Rev. 16 LRZ 6/14/00 WLL added a missing step and made procedural modifications.

3-1 Changed reference to SO23-12-11, RCW 11/06/03 AHH Rev. 1. Modified Initial Plant Conditions. Minor wording modifications to follow procedures changes. Added 2 non-critical steps to follow procedures changes.

3-2 Fixed typo in NOTE prior to JPM RCW 01/06/04 N/A Step 1.

3-3 Converted to an ADMIN JPM. RCW 09/29/04 MRN 4 Compared against SO23-12-11, Rev. 3 LRZ 07/27/05 REV and modified initial conditions and DWST Tank levels to yield new critical steps for available feedwater and time until SDC is required.

Page 4 of 8

SET-UP Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, 6, Determine Time Until Shutdown Cooling is Required.

Page 5 of 8

JPM: SO 10-05 JPM NRC RO A.1.a TITLE: Determine the Time Until Shutdown Cooling is Required

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the examinee with a copy of S023-12-11, EOI Supporting Attachments, Attachment 16.

1 Verify T-120/T-121 the only current VERIFY T-120 and T-121 are the only Start Time:________

feedwater source to SGs. current feedwater source to SGs.

2* Determine T-120 inventory from Using Table 1, DETERMINE T-120 Table 1, Condensate Storage Tank inventory to be 95,262 gallons.

Inventory.

3* Determine T-121 inventory from Table Using Table 1, DETERMINE T-121 1, Condensate Storage Tank Inventory. inventory to be 93,755 gallons.

4* Determine combined inventory from DETERMINE total condensate inventory to both Condensate Storage Tanks. be 189,017 gallons.

5 Determine additional feedwater source DETERMINE additional feedwater source inventory. inventory to be zero (0) gallons.

6 Determine Total feedwater source DETERMINE total feedwater source inventory. inventory to be 189,017 gallons.

7* Determine Net Available Feedwater for DETERMINE Net Available Feedwater decay heat removal. available for decay heat removal to be 134,017 gallons.

8 Determine the number of hours the DETERMINE Reactor was shutdown sixteen reactor has been shutdown. (16) hours ago.

Page 6 of 8

JPM: SO 10-05 JPM NRC RO A.1.a TITLE: Determine the Time Until Shutdown Cooling is Required

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 9* Using Figure 3: Remaining Time SGs DETERMINE time Steam Generators remain Available as Heat Sink determine time available for a heat sink and Shutdown remaining until shutdown Cooling Cooling will be required to be 13.5 (+/- 0.5) required for decay heat removal. hours.

TERMINATING CUE: Stop Time:________

This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/05/05 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC SRO A.1.a INITIAL PLANT CONDITIONS Unit 2 has been operating for several days at a steady state power level greater than 20%.

A reactor power calculation (Manual Method) has been performed due to COLSS Primary calculation being unavailable.

There is NO Auxiliary Feedwater Flow indicated.

Steam Generator E-088 and E-089 Steam and Feedwater Flow indications are within 500k lbm/hr of each other.

The Control Operator that completed this surveillance used the 1000 psia curve for specific enthalpy of subcooled water (temperature interpolated).

TASK TO BE PERFORMED As the Control Room Supervisor, review the Reactor Power Calculation (Manual Method) in accordance with SO23-3-3.38.

Identify, circle, and correct any errors found on this surveillance.

Page 1 of 9

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC SRO A.1.a SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 9

DOCUMENTATION SO 10-05 JPM NRC SRO A.1.a JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 30 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CRS TASK SYS ID: 187652 TASK DESCRIPTION Authorize, supervise, and review all surveillance tests performed on shift.

KA NUMBER: G2.1.20 KA VALUES: RO 4.3 SRO 4.2 10CFR55.45 APPLICABILITY: 12

REFERENCES:

SO23-3-3.38, Reactor Power Calculation (Manual Method), Revision 7 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

1 Compared against SO23-3.3.38, Rev. 7 LRZ 07/27/05 REV and modified errors contained within the Reactor Power Calculation.

Additionally, new final power level calculation required by SRO.

Page 4 of 9

SET-UP Provide the examinee with a copy of SO23-3-3.38, Reactor Power Calculation (Manual Method), with a filled out calculation.

Page 5 of 9

JPM: SO 10-05 JPM NRC SRO A.1.a TITLE: Review a Manual Reactor Power Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the examinee with a copy of SO23-3-3.38, Reactor Power Calculation (Manual Method), with a filled out calculation.

1 Complete prerequisites. VERIFY prerequisites are complete by Start Time: ________

checking:

Power > 20%

No AFW Flow

Reactor Power Stable 2 Verify data in Attachment 1 Steps 2.2.1 VERIFY the PMS Computer was used to thru 2.2.4. record data in Steps 2.2.1 thru 2.2.4 and VERIFY the appropriate boxes to indicate whether Preferred or Alternate points were used.

3 Determine Average Feedwater Inlet VERIFY the Average Feedwater Inlet Temperature. Temperature was calculated and recorded (447ºF) in the lower right hand column of Step 2.2.1.

4* Determine Average Feedwater Pressure. VERIFY the Average SG Inlet Pressure was calculated and recorded and DETERMINE the incorrect number was placed in the lower right hand column of Step 2.2.2 and corrects error.

Value should be 1025 psia, corrects error of 1024 psia.

Page 6 of 9

JPM: SO 10-05 JPM NRC SRO A.1.a TITLE: Review a Manual Reactor Power Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 Determine Average SG Pressure. VERIFY the Average SG Pressure was calculated and recorded and the correct number (809 psia) placed in the lower right hand column of Step 2.2.3.

6 Determine Total Feedwater Flow. VERIFY Total Feedwater flow and DETERMINE the correct number (1.484 E7 lbm/hr) was placed in the lower right hand column of Step 2.2.4.

7 Verify SG E-088 Stm/FW Flow DETERMINE SG E-088 Stm/FW Flow recorder NR & WR Pen indications Recorder NR (Blue) Pen 2FT-1122 & WR agree within 500K lbm/hr. (Green) Pen 2FT-1121 indications agree within 500K lbm/hr.

8 Verify SG E-089 Stm/FW Flow DETERMINE SG E-089 Stm/FW Flow Recorder NR & WR Pen indications Recorder NR (Blue) Pen 2FT-1112 & WR agree within 500K lbm/hr. (Green) Pen 2FT-1111 indications agree within 500K lbm/hr.

9* Determine the Change in Average VERIFY the Change in Average Enthalpy Enthalpy. 1199.1 +/- 1 Btu/lbm - 427.2 +/- 1 Btu/lbm =

771.9 +/- 1 Btu/lbm and DETERMINE correct number was placed in the lower right hand column of Step 2.3.1.

Page 7 of 9

JPM: SO 10-05 JPM NRC SRO A.1.a TITLE: Review a Manual Reactor Power Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10* Determine Average Secondary Power. DETERMINE the Average Secondary Power 771.9 Btu/lbm x 1.484 E7 lbm/hr =

1.145E10 Btu/hr and DETERMINE the incorrect number was placed in the lower right hand column of Step 2.3.2 and corrects error.

Value should be 1.145E10 Btu/hr, corrects error of 1.135E10 Btu/hr.

11* Determine % Full Reactor Power. DETERMINE the % Full Reactor Power (1.145E10 Btu/hr ÷ 1.173E8 Btu/hr = 97.6 +/-

0.5%) and DETERMINE the incorrect power level was calculated and recorded in the lower right hand column of Step 2.3.3 and corrects error.

Value should be 97.6 +/- 0.5%, corrects error of 96.7%.

12 Verify acceptance criteria have been VERIFY the acceptance criteria has been met met. by ensuring the following conditions were maintained during the calculations:

Power > 20%

No AFW Flow

Reactor Power Stable TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 8 of 9

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/05/05 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO A.1.b INITIAL PLANT CONDITIONS Unit 2 is in Mode 1 when you are directed to perform a blended makeup to the Unit 2 RWSTs at a total flow of 40 gpm to raise level 3%. The RWSTs are currently at 97%.

The Plant Monitoring System is UNAVAILABLE. VCT level is stable at 70%.

Current RWST Boron concentration is 2650 ppm.

BAMU Tank T-071 is at 97% and BAMU Tank T-072 is at 93%. Both BAMU Tanks have a concentration of 5420 ppm.

The Operations SRO has verified that an OPERABLE boration flowpath exists.

TASKS TO BE PERFORMED The Shift Manager directs you to:

1. Determine the required volume to raise RWST level from 97% to 100%.

2. Determine the required Boric Acid Flow Rate and Primary Makeup Water Flow Rate for a makeup concentration of 2650 ppm at a total flowrate of 40 gpm.

3. Complete the Prerequisites for SO23-3-2.2, Makeup Operations, Attachment 14, BAMU Tank Makeup to the RWSTs and return to the Shift Manager.

4. Record the following information:

a. Boric Acid Flowrate ________ gpm

b. Primary Water Flowrate ________ gpm

c. RWST Volume Required ________ gallons

d. Total Gallons of Boric Acid Used ________ gallons

e. Volume in BAMU Tanks after addition to RWST ________ gallons Page 1 of 9

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO A.1.b SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 9

DOCUMENTATION SO 10-05 JPM NRC RO/SRO A.1.b JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 141358 TASK DESCRIPTION Calculate a blend for automatic or manual makeup operations.

KA NUMBER: G2.1.23 KA VALUES: RO 3.9 SRO 4.0 10CFR55.45 APPLICABILITY: 2, 6

REFERENCES:

SO23-3-2.2, Makeup Operations, Rev. 18.

Licensee Controlled Specifications Figure 3.1.104-1, Minimum Stored Acid Volume, Rev. 2.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New. This JPM was derived from JPM - - -

215A.

Page 4 of 9

SET-UP Provide candidate with a complete copy of SO23-3-2.2, Makeup Operations and a copy of the Licensee Controlled Specifications, and a copy of LCS figure 3.1.104-1.

Page 5 of 9

JPM: SO 10-05 JPM NRC RO/SRO A.1.b TITLE: Perform an RWST Blended Makeup Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a complete copy of SO23-3-2.2, Makeup Operations and a copy of the Unit 2 Licensee Controlled Specifications.

1 Identifies Attachment 10, Section 2.2 LOCATE Attachment 10 and IDENTIFY Start Time: ________

applies. Section 2.2 as required Formula to Calculate a Blended Makeup to the RWSTs.

2* Determines Boric Acid flow rate. DETERMINE Boric Acid flow rate.

RWST ppm (2650) / BAMU ppm (5420) X Desired Flow Rate (40 gpm) = 19.5 +/- 0.1 gpm Boric Acid for blend.

3* Determines PMW flow rate. DETERMINE PMW flow rate.

Desired Total Flow (40 gpm) - gpm Acid for Blend (19.5) = 20.5 +/- 0.1 gpm PMW for blend.

4 Identifies Attachment 10, Section 2.4 LOCATE Attachment 10 and IDENTIFY applies. Section 2.5 as required Formula to Determine RWST Volume from a Change in Level.

5* Determines volume required to raise DETERMINE required RWST volume.

RWST volume from 97% to 100%. RWST volume in gallons = 4924 gallons / %

x 3% = 14772 gallons.

6* Complete Attachment 14, Section 1.0, VERIFY current copy of procedure and Prerequisites. CALCULATE that 14772 gallons of makeup is required to raise the RWST from 97% to 100% per Attachment 10 Step 2.4.

Page 6 of 9

JPM: SO 10-05 JPM NRC RO/SRO A.1.b TITLE: Perform an RWST Blended Makeup Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 Complete Attachment 14, Step 1.5, DETERMINE that the initial and final boron Determine RWST final Boron concentration will be 2650 ppm.

Concentration.

9 Complete Attachment 14, Step 1.6; Is DETERMINE that the final boron final RWST Boron Concentration concentration is 2650 ppm and CHECK the between 2650 and 2800 ppm? YES box.

10 Complete Attachment 14, Step 1.6.2 by CALCULATE the volume of boric acid determining the volume of boric acid available using Attachment 10, Section 2.6, available in the BAMU Tanks. Formula to Determine BAMU Tank Volume from a Change in Level.

97 % x 106 gal. / % = 10282 gallons in T-071.

93 % x 106 gal. / % = 9858 gallons in T-072.

Total gallons available = 20140 gallons 11* Complete Attachment 14, Step 1.6.2 by CALCULATE the volume of boric acid used:

determining the volume of boric acid 19.5 BA flow / 40 MU flow x 14772 gallons =

used. 7220 +/- 20 gallons of boric acid added.

12* Complete Attachment 14, Step 1.6.2 by CALCULATE the volume of boric acid determining the volume of boric acid available in the BAMU Tanks following the available in the BAMU Tanks following addition to the RWST:

addition to the RWSTs. 20140 - 7220 = 12920 +/- 20 gallons available in the BAMU tanks.

Page 7 of 9

JPM: SO 10-05 JPM NRC RO/SRO A.1.b TITLE: Perform an RWST Blended Makeup Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 13* Complete Attachment 14, Step 1.6.2 by REFER to LCS Figure 3.1.104-1, Minimum determining the minimum volume of Stored Acid Volume (Gallons) and boric acid required. DETERMINE 7600 +/- 200 gallons is the required minimum volume with the RWST at 2650 ppm and the BAMU Tanks at 3.1 weight %.

14 Complete Attachment 14, Step 1.6.2; DETERMINE that sufficient boron is Based on delta volume added to the available in the BAMU Tanks and CHECK RWST, will the BAMU Tanks continue the YES box.

to meet the requirements of LCS Figure 3.1.104-1?

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 8 of 9

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/05/05 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC SRO A.2 INITIAL PLANT CONDITIONS Unit 3 is in the Startup MODE at ~1% power with all equipment operating normally except the LCOAR/EDMR Tracking System (LETS) Computer is not available. The Shift Manager received a call from the Shift Chemist and Engineering this morning October 24, 2005 at 8 AM (10/24/05 @ 0800) stating that the biennial calculation for Unit 3 Trisodium Phosphate Dodecahydrate crystals was determined to be 285 ft3. It is believed that the cause is due to settling of contents over time. A Safety Function Determination (SFD) has been completed. A Non-Conformance Report (NCR), Work Authorization Request (WAR), and Action Request (AR) to correct the problem are in progress. A calculation for Unit 2 is also in progress.

TASK TO BE PERFORMED The Shift Manager directs you to complete a manual LCOAR for Unit 3 Trisodium Phosphate Dodecahydrate. Inform the Shift Manager when complete.

Page 1 of 8

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC SRO A.2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SO 10-05 JPM NRC SRO A.2 JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CRS TASK SYS ID: 192880 TASK DESCRIPTION Initiate, review, and closeout an LCOAR.

KA NUMBER: 2.2.24 KA VALUES: RO 2.6 SRO 3.8 10CFR55.45 APPLICABILITY: 13

REFERENCES:

SO123-0-A5, Technical Specification LCOAR/EDMR, Revision 2-2 Technical Specification 3.5.5, Trisodium Phosphate Dodecahydrate SO123-III-1.14.23, Trisodium Phosphate Rack Inspection, Sample Collection, and Testing, Rev. 6.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Compared against new version of LRZ 08/02/05 REV procedure using SO123-0-A5, Rev. 2-2 and implemented changes as required. Modified JPM to reflect new Technical Specification used.

Page 4 of 8

SET-UP Provide the examinee with a copy of SO123-0-A5, Technical Specification LCOAR/EDMR with extra copies of Attachments 1, 2 and 3 and Technical Specifications.

Complete Attachment 1 for use as an answer guide.

Definitions:

LCOAR - Limiting Condition for Operation ACTION Requirement EDMR - Equipment Deficiency MODE Restraint Page 5 of 8

JPM: SO 10-05 JPM NRC SRO A.2 TITLE: Complete a Manual LCOAR for Trisodium Phosphate Dodecahydrate

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: When located, provide the examinee with a copy of SO123-0-A5, Technical Specification LCOAR/EDMR with extra copies of Attachments 1, 2 and 3 and Technical Specifications.

1* Refer to Tech Specs to identify the LCO REFER to Tech Specs and IDENTIFY Start Time: ________

and Action requirements. Limiting Condition Operation 3.5.5 Action A.

2* Refer to the procedure and select the REFER to SO123-0-A5 and SELECT proper forms. Attachment 1.

NOTE: Keypoints in Step 3 are not critical to task completion. Keypoints in Step 4 are critical to task completion.

Any Keypoints not listed may or may not be filled in by the examinee.

3 Complete LCOAR, Attachment 1. COMPLETE Attachment 1, Keypoints 1, 2, 3, 6, 7, 10, 11 and 12 (as a minimum). REFER to Attachment 3 as necessary to complete the LCOAR.

NOTE: Examinee may choose to complete Keypoint 18 as opposed to the LCO shown in Keypoint 8.

4* Complete LCOAR, Attachment 1. COMPLETE Attachment 1, Keypoints 4, 5, 8, and 9 (as a minimum). REFER to Attachment 3 as necessary to complete the LCOAR.

NOTE: Refer to the completed Attachment 1 for representative entries for each Keypoint. It is not expected that the wording used by the candidate will match the reference Attachment 1 exactly.

Page 6 of 8

JPM: SO 10-05 JPM NRC SRO A.2 TITLE: Complete a Manual LCOAR for Trisodium Phosphate Dodecahydrate

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 Inform the Shift Manager when INFORM the Shift Manager that the LCOAR complete. is complete.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/05/05 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SO 10-05 NRC RO/SRO A.3 INITIAL PLANT CONDITIONS You have been directed to perform a valve alignment in for the Shutdown Cooling Heat Exchanger 3E004 Room. The task involves uncapping and opening several drain valves and attaching drain hoses directed to the floor drain.

TASK TO BE PERFORMED The Work Control Supervisor directs you to select the appropriate REP for the work to be performed, select the appropriate Survey Map and determine stay time in the general work area.

REP Number ____________

Survey Map Number ____________

Stay Time ____________

Page 1 of 7

JOB PERFORMANCE MEASURE SO 10-05 NRC RO/SRO A.3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 7

DOCUMENTATION SO 10-05 NRC RO/SRO A.3 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: N/A TASK DESCRIPTION Determine Stay Time.

KA NUMBER: G2.3.2 KA VALUES: RO 2.5 SRO 2.9 10CFR55.45 APPLICABILITY: 8, 9

REFERENCES:

SO123-VII-20.9, Radiological Surveys, Rev. 6-3 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 7

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

1 Compared against SO123-VII-20.9, LRZ 07/25/05 AHH Rev 6-3 with minor changes required.

Modified JPM with new Survey Maps and REPs. Selected different location for JPM to be performed.

Page 4 of 7

SET-UP Provide examinee with a copy of SO123-VII-20.9, Radiological Surveys, four (4) survey maps and three (3) REPs to choose from. Also supply Unit 3 Safety Equipment Building Floor Plan. (Mosaic will NOT be available.)

Note to Examiner: Information regarding methods of posting Radiological conditions on Survey Maps can be found in Section 6.2 of SO123-VII-20.9. Definitions for Survey Map abbreviations and acronyms can be found in Attachment 2 of SO123-VII-20.9.

Page 5 of 7

JPM: SO 10-05 NRC RO/SRO A.3 TITLE: Determine Stay Time for Work to be Performed

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide applicant with Survey Map #050705-006, Elevation 8 (2 maps) and -15 (2 maps), and 3 REPs to choose from. Also supply Unit 3 Safety Equipment Building Floor Plan. (Mosaic will NOT be available)

CUE: Direct examinee to assume all radiation exposure received is in the general area.

1* Determine applicable survey map. LOCATE survey map #050705-006, Page 4 Start Time: _______

of 4 for the task to be performed. (Safety Equipment Building: Train A Shutdown Cooling Heat Exchanger Room 3E-004 Room.)

2* Determine REP that provides coverage LOCATE and REVIEW REP #200198, of the task performed. which allows vent and drain activities.

3* Determine Stay Time in work area. Based upon general area radiation levels in area and required setpoint of alarming dosimeter, DETERMINE that stay time will be 200 minutes based on 30 mR/hr general area radiation and 100 mR dose alarm.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 6 of 7

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/05/05 Page 7 of 7

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO A.4 INITIAL PLANT CONDITIONS You are the Auxiliary Control Operator. A Site Area Emergency has just been declared at Unit 2.

This is NOT a Security Event. The Shift Manager (Emergency Coordinator) has assigned you to the position of Operations Leader.

The Shift Manager has informed you that:

Emergency response personnel are to report to their emergency duty stations.

Non-emergency response personnel are to report to designated assembly areas.

There is to be no eating, drinking or smoking until further notice.

TASK TO BE PERFORMED The Shift Manager directs you to perform the Siren and PA coordination using SO23-VIII-30, Units 2/3 Operations Leader Duties, Attachment 1.

Page 1 of 8

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO A.4 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SO 10-05 JPM NRC RO A.4 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 895 TASK DESCRIPTION Activate the Emergency Sirens during an Emergency Event.

KA NUMBER: 2.4.38 KA VALUES: RO 2.2 SRO 4.0 10CFR55.45 APPLICABILITY: 11

REFERENCES:

SO23-VIII-30, Units 2/3 Operations Leader Duties, Revision 11 AUTHOR: L. Zilli DATE: 06/13/00 OPERATIONS REVIEW: M. Jones DATE: 06/27/00 APPROVED BY: W. Lyke DATE: 06/29/00 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Reviewed SO23-VIII-30, Rev. 3, TCN LRZ 06/13/00 WLL 3-1 and modified as required.

1-1 Compared against SO23-VIII-30, LRZ 08/15/01 KR Rev. 5, with minor wording changes to comply with procedure. Changed K/A number.

1-2 Deleted perimeter PA. The simulator KM 10/18/01 KR doesnt have a perimeter PA phone.

1-3 Compared against SO23-VIII-30, LRZ 07/27/01 AHH Rev. 5, with minor wording changes required.

1-4 Compared against SO23-VIII-30, LRZ 08/05/05 AHH Rev. 11, with minor wording changes required.

Page 4 of 8

SET-UP Any IC can be used. The Phone Turret and Emergency Evacuation Siren pushbuttons will function in any Simulator setup.

INSTRUCTOR/MACHINE OPERATOR The Phone Turret pushbuttons in the simulator do not back-light. There are cues in the JPM to compensate for this.

Provide the Examinee with a copy of SO23-VIII-30, Units 2/3 Operations Leader Duties.

Page 5 of 8

JPM: SO 10-05 JPM NRC RO A.4 TITLE: Perform Siren and PA Coordination Duties as Operations Leader

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-VIII-30, Units 2/3 Operations Leader Duties.

NOTE: The lights on the phone turret pushbuttons do not work.

CUE: The Siren/PA process is not being coordinated from outside the Control Room.

1* Prepare the Site PA message using PREPARE the Site PA message using Time Start: ________

Attachment 1. Attachment 1 and MARK the boxes on Attachment 1 per the Initial Conditions:

NOTE: Refer to Attachment 1 answer key for appropriate markups.

2* Announce the prepared Site PA message MAKE the Site PA announcement by once over the Site PA system. DEPRESSING the PA SITE pushbutton (bottom two rows, left-hand button) on the phone turret. USE the black phone handset indicated by the directional arrow on the Site PA pushbutton. Can also dial 429 on a Control Room phone to make a Site PA.

MAKE the announcement once.

3* Sound Unit 2/3 sirens. Hold down the SOUND Unit 2/3 sirens. HOLD DOWN the PA Tone Generator Siren All button PA Tone Generator Siren All button on the on the phone turret until the Kill phone turret until the Kill button button illuminates. illuminates.

CUE: The Siren Kill light illuminates in 1 to 4 seconds, and extinguishes after 60 seconds.

NOTE: The lights on the phone turret pushbuttons do not work.

4* Press the Emergency Evacuation Siren DEPRESS 2HS-7890-1, Emergency start pushbutton (HS-7890-1) on CR 57. Evacuation Siren START pushbutton on CR-57.

Page 6 of 8

JPM: SO 10-05 JPM NRC RO A.4 TITLE: Perform Siren and PA Coordination Duties as Operations Leader

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: 60 seconds has elapsed.

5* After a 60 second run, press the After a 60 second run, DEPRESS 2HS-7890-Emergency Evacuation Siren stop 1, Emergency Evacuation Siren STOP pushbutton on CR 57. pushbutton on CR 57.

6 Ensure all sirens are secured. ENSURE all sirens are secured by checking with Plant personnel, or VERIFY 2HS-7890-1, Emergency Evacuation Siren, green light is illuminated.

CUE: All sirens are secured.

7* Repeat the PA announcement from MAKE the Site PA announcement by Attachment 1 two (2) times. DEPRESSING the PA SITE pushbutton (bottom two rows, left-hand button) on the phone turret. USE the black phone handset indicated by the directional arrow on the Site PA pushbutton. Can also dial 429 on a Control Room phone to make a Site PA.

MAKE the announcement twice.

TERMINATING CUE: Time Stop: ________

This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 07/27/05 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC SRO A.4 NOTE: THIS JPM IS WITHHELD FROM PUBLIC DISCLOSURE BECAUSE IT CONTAINS SENSITIVE UNCLASSIFIED INFORMATION Page 1 of 1

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO S-1 INITIAL PLANT CONDITIONS Unit 2 was operating at 100% power when a Steam Generator Tube Rupture (SGTR) occurred.

Both Steam Generators appear to have tube leakage.

A Main Steam Isolation Signal (MSIS) has occurred due to a rapid cooldown during the Steam Generator isolation phase.

SO23-12-4, Steam Generator Tube Rupture, has been completed through Step 16a.

E088 is isolated.

TASK TO BE PERFORMED The Control Room Supervisor directs you to verify isolation of the most affected Steam Generator using SO23-12-4, Steam Generator Tube Rupture.

SO23-12-4, Steam Generator Tube Rupture, has been completed through Step 16a.

Page 1 of 10

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO S-1 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SO 10-05 JPM NRC RO/SRO S-1 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 186690 TASK DESCRIPTION Respond to a Steam Generator tube rupture.

KA NUMBER: 038 EA1.32 KA VALUES: RO 4.6 SRO 4.7 10CFR55.45 APPLICABILITY: 4, 6, 9

REFERENCES:

SO23-12-4, Steam Generator Tube Rupture, Revision 20 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL New Verified against SO23-12-4, Rev. 20. - - -

This JPM was modified to require the operator to control SG pressure using the ADVs due to an MSIS. See J094FS for the original version.

Page 4 of 10

SET-UP SIMULATOR Use IC-171 for the October 2005 NRC Exam. This is an unsupported IC, and may be deleted after the exams are complete.

Otherwise, use any at power IC, and perform the following:

Insert SG06A = 0.01 (SGTR on E088).

Insert SG06B = 0.6 (SGTR on E089).

Initiate an MSIS

Take actions to lower Th to less than 530°F.

Initial conditions should be about 518°F and 1430 psia.

Leave 1 MFP and 3 Condensate Pumps running.

Perform the following to isolate the incorrect Steam Generator (E-088):

Press CLOSE on 2HS-8205, MSIV.

Press CLOSE on 2HS-4048, MFIV.

Press OVERRIDE and then CLOSE on 2HS-8201, Steam to P140.

Press CLOSE on 2HS-4058, S/G Sample Isol.

Press OVERRIDE and then STOP on 2HS-4733, P504 handswitch.

Ensure E088 level >40%.

EXAMINER Provide the Examinee with a copy of SO23-12-4, Steam Generator Tube Rupture, when located.

Page 5 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-1 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-3, Steam Generator Tube Rupture, when located.

1 IDENTIFY appropriate procedure and IDENTIFY SO23-12-4, Steam Generator Time Start: ________

step. Tube Rupture, Step 16 to be performed.

2 VERIFY Steam Line radiation level not Using DAS or 2L-405, Wide Range rising. Monitoring Panel, OBSERVE Main Steam Line Radiation Monitors 2RI-7874/75A1 (SG E088 low/high range) and 2RI-7874/75B1 (SG E089 low/high range).

CUE: 2RI-7874B1, Steam Generator E089 Low Range Main Steam Line Radiation Monitor, indicates a rising trend.

3 VERIFY Blowdown radiation level not OBSERVE Blowdown Radiation Monitors rising. 2RIT-6753 and 2RIT-6759.

CUE: 2RIT-6753, SG E089 Blowdown Radiation Monitor, indicates a rising trend.

4 VERIFY Air Ejector radiation level not OBSERVE Air Ejector Radiation Monitors rising. 2RT-7818 and 2RY-78701.

CUE: 2RY-78701, Air Ejector Radiation Monitors, indicates a rising trend.

5 EVALUATE SG samples and VERIFY IDENTIFY Chemistry results that show E089 isolated SG has highest activity levels. is the most affected SG instead of E088.

ENTERS RNO to restore isolated SG to service and isolate opposite SG.

CUE: Chemistry reports Steam Generator E089 activity is 1.9E-2 µci/ml and Steam Generator E088 activity is 7.7E-3µci/ml.

Page 6 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-1 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 Verify isolated SG trend consistent with OBSERVE E088 level indications 2LI-1123-plant conditions. 1, 2, 3, and A4, SG E088 Downcomer Level.

CUE: E088 level trend is rising.

NOTE: The following steps represent the alternate path of this JPM.

7 VERIFY SBCS available - Condenser DETERMINE that SBCS is not available for back pressure less than the SBCS operation.

interlock setpoint.

8* ESTABLISH RCS temperature control ESTABLISH RCS temperature control by with ADV on isolated SG. SETTING 2HV-8419-1 to the pressure setpoint on 2HV-8421-2 and DEPRESS OVERRIDE then OPEN on the Open/Modulate pushbutton on 2HV-8419 and select AUTO on 2HV-8419-1, SG E088 (N)

Atmospheric Dump Valve controller.

CUE: CRS directs starting P504 to feed E088.

9 START AFW Pump P504. DEPRESS the START pushbutton 2HS-4733-2 for P504.

10 OVERRIDE and OPEN AFW Pump DEPRESS OVERRIDE then OPEN for 2HV-Discharge Valve HV-4762 for P-504 to 4762, AFWP 2P504 to SG E088 (N) Disch 35% open. Valve Bypass and OPEN to 35%.

CUE: CRS directs you to OVERRIDE and OPEN 2HV-4714 to feed E088.

11 OVERRIDE and OPEN AFW Valve DEPRESS OVERRIDE and then OPEN for HV-4714. 2HV-4714, AFWP to SG E088 (N) Disch Valve.

Page 7 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-1 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 12 MAINTAIN reduced flow for 5 OBSERVE E-088 level indicators on CR-52 >

minutes. 40% by observing 2LI-1123-1, -2, -3 and A4, SG E088 Downcomer Level.

CUE: 5 minutes have elapsed.

CUE: Present Steam Generator E088 level is greater than 40% narrow range level.

13 VERIFY recovered SG level > 40% NR VERIFY SG E-088 level > 40% NR by:

and feedwater available, OR, level Observing 2LI-1123-1, -2, -3 and A4, SG trending to between 40% NR and E088 Downcomer Level, and VERIFY 80% NR. feedwater available.

14 ENSURE all valves to initially TRANSITION to Step 9 of SO23-12-4.

unisolated SG closed per Step 9.

15 CLOSE SG E-089 MSIV, 2HV-8204. VERIFY green CLOSE indicating light 2HV-8204, SG E089 (S) Main Steam Iso Valve closed at CR52 or CR57.

16 VERIFY SG E-089 MSIV Bypass, VERIFY green CLOSE indicating light on 2HV-8202 is closed. 2HV-8202, SG 2E089 Main Steam Iso Valve Bypass.

17* VERIFY SG E-089 ADV, 2HV-8421 is DEPRESS the CLOSE pushbutton on closed. 2HV-8421, SG E089 (S) Atmospheric Dump Valve and OBSERVE the green CLOSE indicating light.

18 CLOSE SG E-089 Main Feed Isolation, VERIFY 2HV-4052 FW to SG 2E089 (S) Iso 2HV-4052. Valve CLOSED at CR52 or CR57.

Page 8 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-1 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 19* CLOSE Aux Feed to SG E-089, DEPRESS the CLOSE pushbutton on 2HV-2HV-4731. 4731, AFW to SG 2E089 (S) Iso Valve, and OBSERVE the green CLOSE indicating light.

20 CLOSE Aux Feed to SG E-089, VERIFY 2HV-4715, AFW to SG 2E089 (S) 2HV-4715. Iso Valve, is CLOSED.

21* CLOSE Main Steam to Aux Feed Pump DEPRESS OVERRIDE and then CLOSE Turbine, 2HV-8200. pushbuttons for 2HV-8200, Main STM to AFWPT 2K007 SG 2E089 (S) Iso Valve and OBSERVE the green CLOSE indicating light.

22 CLOSE SG E-089 Blowdown Isolation, VERIFY 2HV-4053-2, SG 2E089 (S) 2HV-4053. Blowdown Iso Valve, is CLOSED.

23 CLOSE SG E-089 Steam Generator VERIFY 2HV-4057, SG 2E089 (S) Water Water Sample Isolation, 2HV-4057. Sample Iso Valve, is CLOSED.

24 STOP Aux Feed Pump P-141. DEPRESS OVERRIDE and then STOP pushbuttons for 2HS-4701-1, AFWP 2P141.

TERMINATING CUE: Time Stop: ________

This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 07/25/05 Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO S-2 INITIAL PLANT CONDITIONS Unit 2 is cooling down. Both Shutdown Cooling (SDC) pumps and both SDC heat exchangers are in operation.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform the actions required to place the Shutdown Cooling System in a single pump/single heat exchanger lineup.

Remove P-016 and E-003 from service per SO23-3-2.6 and establish Shutdown Cooling System flow at ~4500 gpm.

Page 1 of 9

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO S-2 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 9

DOCUMENTATION SO 10-05 JPM NRC RO/SRO S-2 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 007814 TASK DESCRIPTION Transfer from parallel to single shutdown cooling heat exchangers.

KA NUMBER: S04S-005-000-A1-01 KA VALUES: RO 3.5 SRO 3.6 10CFR55.45 APPLICABILITY: 2, 4, 6, 7, 10, 12

REFERENCES:

SO23-3-2.6, Shutdown Cooling System Operation, Rev. 22.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: A. Hagemeyer DATE:

APPROVED BY: M. Jones DATE:

Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Changed task number to properly HJW 10/05/93 MJK reflect task performed by JPM. NR-0122 Group III system approved for use as JPM due to KA value >3.0.

1-1 Changed setup page; minor editorial HJW 03/22/94 N/A corrections to standards for clarity.

1-2 Compared against SO23-3-2.6, TCN HJW 05/27/94 N/A 7-18 with no changes required.

1-3 Compared against SO23-3-2.6, TCN HJW 09/24/94 N/A 7-18 with no changes required.

1-4 Changed setup page to position valves HJW 10/26/94 N/A HV-8150 & 8151 to 32% open instead of 80% open.

1-5 Compared against SO23-3-2.6, TCN HJW 05/03/95 N/A 8-2 with minor changes required for step reference and flow limit updates.

1-6 Compared against SO23-3-2.6, TCN HJW 10/17/95 N/A 8-4 with minor changes to step reference numbers and parameters.

Corrected some standards to comply with actual plant components. Deleted step 3.

1-7 Compared against SO23-3-2.6, Rev. 9 HJW 09/18/96 N/A with no changes required.

2 Compared against SO23-3-2.6, Rev. LRZ 07/11/05 REV 22 and revised as required. Deleted critical steps to reflect the MOVAT improvements that no longer require holding the switches for valve closure.

Added a critical step to close 2HV-6500.

Page 4 of 9

SET-UP Use IC-5.

The following keys are required: 13, 14, 15, 16, 19, 21, 22, 28, 29, 30, 31, 34, 35, 36, 38, 42, 46, and 50.

Fully open 2HV-9325 & 2HV-9328.

Fully open 2HV-9322 & 2HV-9331 Start LPSI 2P015.

Position 2HV-8150 & 2HV-8151 to 32% open.

Allow conditions to stabilize.

Check 2FI-0306 between 8000 and 8400 gpm.

Provide examinee with a copy of SO23-3-2.6, Shutdown Cooling System Operation.

Page 5 of 9

JPM: SO 10-05 JPM NRC RO/SRO S-2 TITLE: Perform the Actions Required to Place the SDC in a Single Pump /

Single Heat Exchanger Lineup (Remove P-016 and E-003 from Service)

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-3-2.6, Shutdown Cooling System Operation.

1 NOTIFY Health Physics that radiation NOTIFY Health Physics that radiation levels Start Time: ________

levels in the SDC heat exchanger and in the SDC heat exchanger and LPSI pump LPSI pump areas may change. areas may change.

CUE: Health Physics has been notified.

2 TRANSITION to Step 6.6.6. TRANSITION to Step 6.6.6 for securing LPSI Pump P016.

CUE: If asked, inform the examinee that the RCS is filled with a bubble in the pressurizer.

3* Slowly CLOSE LPSI Header Isolation DEPRESS and hold the JOG CLOSE valve HV-9322. pushbutton for 2HV-9322, HDR to Loop 1A, until the GREEN light is illuminated.

4* Slowly CLOSE LPSI Header Isolation DEPRESS and hold the JOG CLOSE valve HV-9331. pushbutton for 2HV-9331, HDR to Loop 2B, until the GREEN light is illuminated.

5* STOP LPSI Pump P-016. DEPRESS STOP pushbutton 2HS-9391-2, LPSI Pump 2P016 (N).

NOTE: Values listed below are the limits through one heat exchanger.

6 THROTTLE the in-service SDC heat DEPRESS the JOG OPEN or JOG CLOSED exchanger bypass flow valve, HV-8160; pushbutton to THROTTLE 2HV-8160, SDC to control SDCS flow as required by HX Bypass Normal Flow Valve, to achieve present Mode and RCS level conditions. >2500 to <5320 gpm with a desired value of

~4500 gpm.

Page 6 of 9

JPM: SO 10-05 JPM NRC RO/SRO S-2 TITLE: Perform the Actions Required to Place the SDC in a Single Pump /

Single Heat Exchanger Lineup (Remove P-016 and E-003 from Service)

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: The examinee may not perform the next step since immediately following this step the second heat exchanger is removed from service. This is acceptable as long as temperature is monitored.

7 THROTTLE the SDC heat exchanger TURN the JOG OPEN or JOG CLOSED outlet to LPSI header valves, HV-8150 keylock switches as required THROTTLING and HV-8151, to achieve the desired 2HV-8150, SDC HX 2E004 to LPSI Header RCS cooling conditions. Control Valve and 2HV-8151, SDC HX 2E003 to LPSI Header Control Valve, to maintain temperature relatively constant.

CUE: Cooling requirement at this time is only to maintain present RCS conditions until evolution completed.

NOTE: The following two steps should be performed alternately to remove the second heat exchanger from service.

8* THROTTLE CLOSE on HV-8151, TURN and HOLD the JOG CLOSED keylock SDC Heat Exchanger E-003 outlet to switch for 2HV-8151, SDC HX 2E003 to LPSI header valve. LPSI Header Control Valve, until the GREEN light is illuminated.

9* THROTTLE OPEN HV-8150, SDC TURN and HOLD the JOG OPEN keylock Heat Exchanger E-004 outlet to LPSI switch for 2HV-8150, SDC HX 2E004 to header valve. LPSI Header Control Valve, to achieve the desired valve position.

Page 7 of 9

JPM: SO 10-05 JPM NRC RO/SRO S-2 TITLE: Perform the Actions Required to Place the SDC in a Single Pump /

Single Heat Exchanger Lineup (Remove P-016 and E-003 from Service)

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10 THROTTLE the in-service SDC heat TURN the JOG OPEN or JOG CLOSED exchanger outlet to LPSI header valve, keylock switch as required THROTTLING HV-8150, to achieve the desired RCS 2HV-8150, SDC HX 2E004 to LPSI Header cooling conditions. Control Valve, to achieve the desired RCS cooling conditions.

11 After the off-going SDC heat exchanger After the off-going SDC heat exchanger outlet outlet valve is fully closed, READJUST valve is fully closed, READJUST SDCS flow SDCS flow to same value as before by by DEPRESSING the JOG OPEN or JOG throttling HV-8160. CLOSED pushbutton to 2HV-8160, SDC HX Bypass Normal Flow Valve to ~4500 gpm.

12 CLOSE the CCW Outlet Valve for the CLOSE 2HV-6500, CCW from SDC HX off-going heat exchanger. 2E003 Block Valve.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 8 of 9

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 07/25/05 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO S-3 INITIAL PLANT CONDITIONS A LOCA has occurred and a Recirculation Actuation Signal has actuated.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform SO23-12-11, EOI Supporting Attachments, 4, RAS Operation.

Page 1 of 10

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO S-3 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SO 10-05 JPM NRC RO/SRO S-3 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 min TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 192219 TASK DESCRIPTION Initiate RAS and verify actuation.

KA NUMBER: E11-EK3.3 KA VALUES: RO 3.8 SRO 3.8 10CFR55.45 APPLICABILITY: 2, 3, 4, 6, 7

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 14, RAS Operation, Rev. 3 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

Page 4 of 10

SET-UP Use IC # 175 for the October 2005 NRC Exam. Enter malfunctions CH07A and CH07B, Containment Sump Basket Filter Clog per the Blocked Sumps Event File.

Provide the Examinee with a copy of SO23-12-11, Attachment 14, RAS Operation.

Page 5 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-3 TITLE: Perform Recirculation Actuation Signal Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-11, Attachment 14, RAS Operation.

1 VERIFY RWST level - less than 19%. OBSERVE RWT 2T006 LEVEL 2LI-0305-1, Start Time: ________

-2, -3, -4 and/or RWT 2T005 LEVEL 2LI-0301 less than 19%.

2 VERIFY Containment Emergency OBSERVE CNTMT EMER SUMP LEVEL Sump Level - greater than 18 feet 4 2LI-9386-1 OR 2LI-9389-2 greater than 18 inches. feet 4 inches.

3 ENSURE Containment Emergency OBSERVE Containment Emergency Sump Sump Outlet Valves - open. Outlet Valve red OPEN lights illuminated for:

Train A Train B Train A Train B HV-9303 HV-9302 2HV-9303 2HV-9302 HV-9305 HV-9304 2HV-9305 2HV-9304 4 ENSURE LPSI Pumps stopped. OBSERVE LPSI PUMP P015 (2HS-9390-1) and P016 (2HS-9391-2) green STOP lights illuminated.

5 ENSURE SI Pumps and Containment OBSERVE SI Pumps and Containment Spray Spray Pump Miniflow Isolation Valves Pump Miniflow Isolation Valves green

- closed. CLOSE lights illuminated for:

Train A Train B Train A Train B HV-9306 HV-9347 2HV-9306 2HV-9347 HV-9307 HV-9348 2HV-9307 2HV-9348 6 ENSURE CCAS - actuated. OBSERVE CCAS actuated by observing Annunciators 57A07 and 57B07 CCAS TRAIN A (B) ACTUATION.

Page 6 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-3 TITLE: Perform Recirculation Actuation Signal Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 7 ENSURE available Containment OBSERVE available Containment Emergency Emergency Cooling Units - operating. Cooling Unit red START lights illuminated Train A Train B on Panel 60:

E-399 E-400 Train A Train B E-401 E-402 2E-399 2E-400 2E-401 2E-402 8 ENSURE CCW Valves to operating OBSERVE CCW Valves to operating Emergency Cooling Units - open. Emergency Cooling Units red OPEN lights Train A Train B illuminated on Panel 60:

HV-6370 HV-6368 Train A Train B HV-6371 HV-6369 2HV-6370 2HV-6368 HV-6366 HV-6372 2HV-6371 2HV-6369 HV-6367 HV-6373 2HV-6366 2HV-6372 2HV-6367 2HV-6373 9 ENSURE available Containment Dome OBSERVE available Containment Dome Air Air Circulating Fans - operating. Circulating Fan red START lights illuminated Train A Train B on Panel 60:

A-071 A-072 Train A Train B A-074 A-073 2A-071 2A-072 2A-074 2A-073 10 VERIFY Containment Emergency OBSERVE CNTMT EMER SUMP AREA Sump Level - greater than 22 feet. LVL 2LI-9387-1 or 2LI-9388-2 greater than 22 feet.

11* CLOSE RWST Outlet Isolation Valves: OBTAIN key from Key Locker and INSERT HV-9300 and CLOSE RWT 2T005 Outlet Iso Valve HV-9301 2HV-9300 and RWT 2T006 Outlet Iso Valve 2HV-9301.

Page 7 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-3 TITLE: Perform Recirculation Actuation Signal Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 12 CLOSE CCW to/from Letdown Heat DEPRESS the CLOSE pushbutton for CCW Exchanger Valves: CLA LTDN HX 2E062 Supply/Return Valve Train A Train B 2HV-6293B/A and VERIFY CLOSED CCW HV-6293B/A HV-6522B/A CLA LTDN HX 2E062 Supply/Return Valve 2HV-6522B/A.

NOTE: The following steps represent the alternate path of this JPM.

13 VERIFY ECCS Pump(s) suction OBSERVE HPSI Pump fluctuating flow on performance: Train A Flow Indications 2FI-0321-1 and 2FI-Operating ECCS Pump(s) flow - stable. 0331-1 and Train B Flow Indications 2FI-Operating ECCS Pump(s) discharge 0311-2 and 2FI-0341-2.

pressure - stable. OBSERVE LPSI Pump fluctuating flow on Operating ECCS Pump(s) motor amps - Train A and B Flow Indication 2FI-0306.

stable. OBSERVE HPSI Pump fluctuating discharge pressure on 2PI-0308 for 2P-017 and 2PI-0309 for 2P-019.

OBSERVE LPSI Pump fluctuating discharge pressure on 2PI-0307.

OBSERVE HPSI and LPSI Pump fluctuating motor amps.

14* OVERRIDE and STOP both OVERRIDE and STOP both Containment Containment Spray Pumps. Spray Pumps by DEPRESSING STOP pushbuttons on 2HS-9395-1 for Containment Spray Pump 2P012 (SE) and 2HS-9396-2 for Containment Spray Pump 2P013 (NW) and OBSERVE green STOP lights illuminated.

Page 8 of 10

JPM: SO 10-05 JPM NRC RO/SRO S-3 TITLE: Perform Recirculation Actuation Signal Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 15* OVERRIDE and CLOSE both OVERRIDE and CLOSE both Containment Containment Spray Pump Discharge Spray Pump Discharge Valves by Valves. DEPRESSING STOP pushbuttons on 2HV-9368 for CNTMT Spray HDR NO2 Control Valve and 2HV- 9367 for CNTMT Spray HDR NO1 Control Valve and OBSERVE green CLOSED lights illuminated.

16 If HPSI Pump performance - unstable DETERMINE that HPSI Pump performance then throttle flow. is stable and RETURN to the Action /

Expected Response column.

17 MAINTAIN HPSI pump(s) flow: OBSERVE Train A Flow Indications 2FI-

- greater than 160 GPM in any one loop 0321-1 and 2FI-0331-1 and Train B Flow per operating pump. Indications 2FI-0311-2 and 2FI-0341-2 greater than 160 GPM in any one loop.

Cold Leg Injection:

Train A Train B Train A Train B FI-0321 FI-0311 2FI-0321-1 2FI-0311-2 FI-0331 FI-0341 2FI-0331-1 2FI-0341-2 Hot Leg Injection:

Train A Train B FI-9421 FI-9435 TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 07/25/05 Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO S-4 INITIAL PLANT CONDITIONS Unit 2 is operating at 70% power. Both CCW Loops are in service. Preparations are in progress to place the Train A CCW/SWC Loop in Standby IAW SO23-2-17, Component Cooling Water System Operation. The procedure is complete up to and including Step 6.4.4.

TASK TO BE PERFORMED The Control Room Supervisor directs you to place the Train A CCW/SWC Loop in standby.

Page 1 of 11

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO S-4 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 11

DOCUMENTATION SO 10-05 JPM NRC RO/SRO S-4 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 18 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACRO TASK SYS ID: 577 TASK DESCRIPTION Transfer the component cooling water non-critical loop.

KA NUMBER: 008 A4.01 KA VALUES: RO 3.3 SRO 3.1 10CFR55.45 APPLICABILITY: 5, 7

REFERENCES:

SO23-2-17, Component Cooling Water System Operation, Revision 18-4 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 11

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Compared to SO23-2-17, Rev. 15 and LRZ 08/01/00 WLL made changes as required. Deleted steps that isolated CCW to the SDC heat exchanger.

1-1 Compared to SO23-2-17, TCN 15-3 JJM 10/26/00 WLL and made changes to reflect the new format of the procedure and added steps that ensure two ECU Return valves are open on each train and that SDCHX outlet valves are to be repositioned during the performance of the JPM. Changed the setup page to reflect the changes to the procedure.

2 Compared to SO23-2-17, TCN 15-4 LRZ 05/14/01 WLL and made changes to reflect added steps to the procedure. Added Critical step to close the discharge valve on the SWC Pump that was secured.

2-1 Compared to SO23-2-17, Rev. 18. RCW 11/20/03 FM Updated Set-up page. Added cue.

Minor editorial changes.

3 Compared to SO23-2-17, Rev. 18-4. LRZ 07/26/05 REV Added two Critical Steps (Step 7 and 23). Added Cue before Step 22 to direct operator to align ECU and SDC Valves. Made minor editorial changes.

Page 4 of 11

SET-UP Use IC-174 (Event File Delete J-70) for October 2005 NRC JPM Exams.

Otherwise, place both CCW Critical Loops in service and start CCW Pump P-026.

OPEN the following ECU valves:

2HV-6369

2HV-6373

2HV-6367

2HV-6371 Restore operability to and OPEN SDCHX Valve 2HV-6500 Restore operability to and CLOSE SDCHX Valve 2HV-6501 Ensure the Non-critical Loop and the Letdown Heat Exchanger are aligned to the Train A CCW Critical Loop.

Provide the examinee with a copy of SO23-2-17, CCW System Operation, completed through Step 6.4.4.

NOTE: Examiner should be aware that some steps may be performed out of sequence.

Preview JPM and monitor examinee actions to ensure all critical steps are performed.

Page 5 of 11

JPM: SO 10-05 JPM NRC RO/SRO S-4 TITLE: Place the A CCW Critical Loop in Standby

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-2-17, CCW System Operation, completed through Step 6.4.4.

1 ENSURE the Non-Critical Loop is TRANSITION to Section 6.6 of SO23-2-17 to Start Time: ________

aligned to the train that is to remain in Transfer the CCW Non-Critical Loop from service. Critical Loop A to Critical Loop B.

NOTE: The examinee may choose to align the Non-Critical Loop using accepted operating practices and transition directly to JPM Step 8. Critical Step 7 should then be completed at Step 23 of the JPM.

NOTE: JPM Steps 2 through 12 are done in accordance with Section 6.6 of SO23-2-17.

2 ENSURE CCW Train B is running. OBSERVE CCW Pump P-026 is running on Train B with red START light illuminated.

3 ENSURE OPEN HV-6371, OBSERVE 2HV-6371, CCW from CNTMT Containment Emergency Cooler ME- ECU 2E399 Iso Valve red OPEN light 399 CCW Return Containment Isolation illuminated.

Valve.

4 ENSURE OPEN HV-6367, OBSERVE 2HV-6367, CCW from CNTMT Containment Emergency Cooler ME- ECU 2E401 Iso Valve red OPEN light 401 CCW Return Containment Isolation illuminated.

Valve.

5 ENSURE OPEN HV-6369, containment OBSERVE 2HV-6369, CCW from CNTMT Emergency Cooler ME-400 CCW ECU 2E400 Iso Valve red OPEN light Return Containment Isolation Valve. illuminated.

6 ENSURE OPEN HV-6373, OBSERVE 2HV-6373, CCW from CNTMT Containment Emergency Cooler ME- ECU 2E402 Iso Valve red OPEN light 402 CCW Return Containment Isolation illuminated.

Valve.

Page 6 of 11

JPM: SO 10-05 JPM NRC RO/SRO S-4 TITLE: Place the A CCW Critical Loop in Standby

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 7* ENSURE CLOSED HV-6500, CCW DEPRESS the CLOSE pushbutton for 2HV-from SDCHX, ME-003 Block Valve. 6500, CCW from SDC HX 2E003(N) Block Valve and OBSERVE green CLOSE light illuminated.

8* DEPRESS and MAINTAIN DEPRESS and HOLD the OPEN pushbuttons DEPRESSED the Open pushbutton for for 2HV-6213 and 2HV-6219, CCW to NCL HV-6213 and HV-6219, Critical Loop B to/from Loop B Isolation Valves.

Supply and Return to NCL.

9* When 2HV-6212 and 2HV-6218, OBSERVE the green lights illuminate for Critical Loop A Supply and Return to 2HV-6212 and 2HV-6218, CCW to NCL NCL indicate CLOSED, then to/from Loop A Isolation Valves and then RELEASE the Open pushbutton for RELEASE the OPEN pushbuttons for 2HV-2HV-6213 and 2HV-6219. 6213 and 2HV-6219, CCW to NCL to/from Loop B Isolation Valves.

10 Verify 2HV-6213 and 2HV-6219 VERIFY 2HV-6213 and 2HV-6219 remain remain OPEN. OPEN and OBSERVE that only the red lights remain illuminated.

11 Verify 2HV-6212 and 2HV-6218 are VERIFY 2HV-6212 and 2HV-6218 are fully fully CLOSED. CLOSED and OBSERVE that only the green lights remain illuminated.

NOTE: With Train A being placed in standby the examinee may not elect to do Step 12.

12 ENSURE OPEN 2HV-6501, CCW from DEPRESS the OPEN pushbutton for 2HV-SDCHX ME-004 Block Valve. 6501, CCW from SDC HX 2E004(S) Block Valve and OBSERVE red light illuminated.

Page 7 of 11

JPM: SO 10-05 JPM NRC RO/SRO S-4 TITLE: Place the A CCW Critical Loop in Standby

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 13 ENSURE the Letdown Heat Exchanger VERIFY that the Letdown Heat Exchanger is is aligned to the train that is to remain in not aligned to Train B and proceeds to align it service. to Train B.

14 ENSURE the CCW Train that the OBSERVE that CCW Pump 2P-026 and SWC Letdown Heat Exchanger is being Pump 2P-114 are running on Train B.

transferred to is running.

15* CLOSE HV-6293B/A, CCW Critical DEPRESS the CLOSE pushbutton for Loop A Letdown HX ME-062 2HV-6293B/A, CCW CLA LTDN HX 2E062 Return/Supply Valves. Supply/Return Valves and OBSERVE that the green light illuminates.

16* OPEN 2HV-6522B/A, CCW Critical DEPRESS the OPEN pushbutton for Loop B Letdown HX ME-062 2HV-6522B/A, CCW CLB LTDN HX 2E062 Return/Supply Valves. Supply/Return Valves and OBSERVE that the red light illuminates.

17* STOP the CCW Pump on the train DEPRESS the STOP pushbutton for being placed in standby. 2HS-6320-1, CCW Pump 2P025 and OBSERVE that the green light illuminates.

CUE: It is required to stop the SWC Pump on the train being placed in standby.

18* STOP the SWC Pump on the train being DEPRESS the STOP pushbutton for placed in standby. 2HS-6380-1, Saltwater Pump 2P112 and OBSERVE that the green light illuminates.

19* CLOSE the Discharge Valve on the Salt DEPRESS the CLOSE pushbutton for Water Cooling Pump that was secured. 2HS-6200, Saltwater Pump 2P112(W)

Discharge Valve and OBSERVE that the green light illuminates.

Page 8 of 11

JPM: SO 10-05 JPM NRC RO/SRO S-4 TITLE: Place the A CCW Critical Loop in Standby

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: The SWC Pump P-112 will not be restarted within one (1) hour.

20* CLOSE SWC Bearing Seal Water DEPRESS the CLOSE pushbutton for 2HV-Supply Valve. 6376, Saltwater Pump 2P112(W) Bearing Water Supply Valve and OBSERVE that the green light illuminates.

21* CLOSE the SWC Heat Exchanger DEPRESS the CLOSE pushbutton for 2HV-Outlet Valve. 6497, Saltwater from CCW HX 2E001 Circ Water Block Valve and OBSERVE that the green light illuminates.

22 ENSURE ECU Return Valves are OBSERVE that two ECU Return Valves are positioned per Table in Section 6.1. OPEN on both Trains:

2HV-6367, CCW from CNTMT ECU to 2E401 Iso Valve for Train A.

2HV-6371, CCW from CNTMT ECU to 2E399 Iso Valve for Train A.

2HV-6369, CCW from CNTMT ECU to 2E400 Iso Valve for Train B.

2HV-6373, CCW from CNTMT ECU to 2E402 Iso Valve for Train B.

Page 9 of 11

JPM: SO 10-05 JPM NRC RO/SRO S-4 TITLE: Place the A CCW Critical Loop in Standby

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: If JPM Step 7 is performed here then give the examinee credit.

23* CLOSE Shutdown Cooling Heat DEPRESS the CLOSE pushbutton for 2HV-Exchanger CCW Outlet Valve that is 6501, SDC HX 2E004(S) Block Valve and not required per Table in Section 6.1. OBSERVE that the green light illuminates and VERIFY that 2HV-6500, SDC HX 2E003(N) Block Valve is closed.

TERMINATING CUE: CCW Out of Stop Time: ________

Service tags will be placed on the Control Boards by another operator. This JPM is complete.

Page 10 of 11

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 07/26/05 Page 11 of 11

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO C-5 INITIAL PLANT CONDITIONS A Station Blackout has occurred on Units 2 & 3. The Control Room has lost ventilation.

The Control Room Emergency AC Units were aligned as follows prior to the Station Blackout:

Train A (E-418) was aligned to Unit 2.

Train B (E-419) was aligned to Unit 3.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform Attachment 9, Control Building Ventilation Emergency Actions per SO23-12-11, EOI Supporting Attachments.

Page 1 of 10

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO C-5 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SO 10-05 JPM NRC RO/SRO C-5 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO/ACO VISION ID: 188352 TASK DESCRIPTION Response to a Station Blackout.

KA NUMBER: 055-EK3.02 KA VALUES: RO 4.3 SRO 4.6 10CFR55.45 APPLICABILITY: 6, 12

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 9, Control Building Ventilation Emergency Actions, Rev. 3 AUTHOR: L.Zilli DATE: 03/12/05 OPERATIONS REVIEW: M. Jones DATE: 03/22/05 APPROVED BY: A. Hagemeyer DATE: 03/22/05 Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO23-12-11, Rev 3 LRZ 07/26/05 AHH with minor changes required.

Page 4 of 10

SET-UP Provide the Examinee with a copy of SO23-12-11, Attachment 9, Control Building Ventilation Emergency Actions.

Page 5 of 10

JPM: SO 10-05 JPM NRC RO/SRO C-5 TITLE: Control Building Ventilation Emergency Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-11, Attachment 9, Control Building Ventilation Emergency Actions.

CUE: No Unit 2 or Unit 3 4160 volt or 480 volt Buses are energized. Remind examinee to simulate all actions.

1 VERIFY a CR Emergency AC Unit VERIFY that both CR Emergency AC Units Start Time: ________

aligned to other units energized 1E 480V are de-energized per the Initial Conditions and bus: TRANSITIONS to the RNO.

Train A Train B E-418 E-419 2 OBTAIN keys to open the Control Room OBTAIN keys to open the Control Room Cabinets. Cabinets from the Nuclear Operations Assistant or the Control Room Key Cabinets.

CUE: You have the keys to unlock the Control Room Cabinet Doors. Open Priority 1 doors ONLY.

NOTE: The following two steps represent the alternate path of this JPM.

3* INITIATE opening CR Cabinet Doors INITIATE opening CR Cabinet Doors listed in listed in Table 1. Table 1.

Page 6 of 10

JPM: SO 10-05 JPM NRC RO/SRO C-5 TITLE: Control Building Ventilation Emergency Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

PANEL DESCRIPTION PANEL DOORS TO BE OPENED KEY NO.

2L154 HVAC Systems Control Panel Rear (4 doors) Unlocked 2L034 ESFAS Auxiliary Cabinet A Bays 1,2,3,4,5 and 8 - outer doors; Bay 5 - inner door 24 2L035 ESFAS Auxiliary Cabinet B Bays 1,2,3,4,5 and 8 - outer doors; Bay 5 - inner door 25 2L122 SPEC 200 Instrument Cabinet Process Protection, Channel 1 Front 27 or 28 2L123 SPEC 200 Instrument Cabinet Process Protection, Channel 1 Front 27 or 28 2L126 SPEC 200 Instrument Cabinet Process Protection, Channel 2 Front 27 or 28 2L127 SPEC 200 Instrument Cabinet Process Protection, Channel 2 Front 27 or 28 2L130 SPEC 200 Instrument Cabinet Process Protection, Channel 3 Front 27 or 28 2L422 SPEC 200 NSSS Interface Cabinet Front 27 or 28 2L134 SPEC 200 Instrument Cabinet Process Protection, Channel 4 Front 27 or 28 2L188A SPEC 200 NSSS Cabinet "A" Train Front 27 or 28 2L188B SPEC 200 NSSS Cabinet "B" Train Front 27 or 28 CUE: Attachment 9, Table 1 is now completed.

NOTE: If the Control Room is not accessible for continuing, then terminate this JPM.

CUE: Unit 3 EDG 3G003 has been started and Buses 3A06 and 3B06 are energized. CCW Pump 3P026 is running.

4 IF 1E 480 V bus energized at opposite DETERMINE that a 1E 480 V bus is Unit, THEN Transfer CR Emergency AC energized at opposite Unit and prepares to Unit E-416 or E-419 power supply per TRANSFER the Control Room Emergency SO23-3.2.27, Control Room Isolation and AC Units E-416 or E-419 power supply per Emergency Ventilation System. SO23-3.2.27, Control Room Isolation and Emergency Ventilation System.

CUE: Another operator will perform SO23-3.2.27, Control Room Isolation and Emergency Ventilation System. The Control Room Supervisor directs you to continue with Attachment 9.

Page 7 of 10

JPM: SO 10-05 JPM NRC RO/SRO C-5 TITLE: Control Building Ventilation Emergency Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 VERIFY an Emergency Chiller aligned to VERIFY Emergency Chiller E-335 is aligned other units energized 1E 4kV bus: to the Unit 3 Bus 3A06.

Train A Train B E-336 E-335 CUE: Emergency Chiller E-335 is aligned to the Unit 3 Bus 3A06.

6* ACTUATE CRIS for available train of CR ACTUATE Train B of CRIS by Emergency HVAC. DEPRESSING 2/3HS-7825A2.

CUE: Train B of CRIS is actuated.

7* START ESF Switchgear Room Emergency START ESF Switchgear Room Emergency Cooling Unit E-255 or E-257 for available Cooling E-257 on Unit 3 by DEPRESSING train. 3HS-9829-2.

CUE: ESF Switchgear Room Emergency Cooling E-257 on Unit 3 is running.

8 VERIFY Control Room Emergency AC VERIFY Control Room Emergency AC Unit Unit E-418 or E-419 - operating. 3 E-419 is operating.

CUE: Control Room Emergency AC Unit 3 E-419 is running.

9 START ESF Switchgear Room Emergency START ESF Switchgear Room Emergency Cooling Unit E-255 or E-257 - operating. Cooling E-257 on Unit 3 is running.

CUE: ESF Switchgear Room Emergency Cooling E-257 on Unit 3 is running. There are no Control Room Cabinet Emergency Cooling Units operating.

Page 8 of 10

JPM: SO 10-05 JPM NRC RO/SRO C-5 TITLE: Control Building Ventilation Emergency Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10* VERIFY Control Room Cabinet START Control Room Cabinet Emergency Emergency Cooling Units - operating. Cooling Unit E-426 on Unit 3 by Train A Train B DEPRESSING 3HS-9739-2.

E-424 E-423 E-427 E-426 TERMINATING CUE: Emergency Stop Time: ________

Cooling Unit E-426 on Unit 3 is running.

This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: R. Hampton DATE: 07/23/05 Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO S-6 INITIAL PLANT CONDITIONS You are operating at a power level of 70% and ESI is determined to be - 0.07.

The CRS directs you to restore ASI using PLCEAs.

TASK TO BE PERFORMED The Control Room Supervisor directs you to restore ASI to the 70% power level ESI using SO23-5-1.7, Power Operations, Attachment 6.

Page 1 of 8

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO S-6 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SO 10-05 JPM NRC RO/SRO S-6 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 188098 TASK DESCRIPTION Monitor and control ASI during steady state operations.

KA NUMBER: 001 A2.19 KA VALUES: RO 3.6 SRO 4.0 10CFR55.45 APPLICABILITY: 2, 4, 5, 6

REFERENCES:

SO23-5-1.7, Power Operations, Rev. 24 SO23-3-2.19, CEDMCS, Rev. 18-1 SO23-13-13, Misaligned Control Element Assembly, Rev.10-2 AUTHOR: L. Zilli DATE: 03/10/05 OPERATIONS REVIEW: M. Jones DATE: 03/18/05 APPROVED BY: A. Hagemeyer DATE: 03/18/05 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO23-5-1.7, Rev. LRZ 03/10/05 AHH 24 with minor changes required.

Page 4 of 8

SET-UP Reset to IC #187 for the October 2005 NRC Exam.

Malfunction numbers:

RD3003 for CEA # 30 RD3103 for CEA # 31 Ensure the ASI PMS indication is aligned at the ACO desk (upper scale @ -0.15 and lower scale @ -0.0).

Provide the examinee with a copy of SO23-5-1.7, Power Operations.

CAUTION: Leave the simulator in freeze until the examinee is ready to move the PLCEAs.

Page 5 of 8

JPM: SO 10-05 JPM NRC RO/SRO S-6 TITLE: Restore ASI to ESI

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: The applicant may also refer to SO23-3-2.19, CEDMCS Operation.

1 SELECT the PLCEAs with the Group PLACE the Group Selector Switch to P. Start Time: ________

Selector Switch.

2* SELECT MANUAL GROUP on the PLACE the Mode Select Switch in MANUAL Mode Select Switch. GROUP.

3* INSERT the PLCEAs. INSERT the PLCEAs in small, smooth, frequent movements of less than 3 inches per minute. PLACE Mode Select Switch in OFF when rod insertion is complete. Insertion should not exceed 112.5" (TS 3.1.8 and LCS 3.1.103).

4 MONITOR ASI and ESI. OBSERVE PMS screen and/or chart for ASI trend. DETERMINE that a second CEA insertion is required.

NOTE: The examiner may cue the simulator to insert malfunction at any time once the second CEA insertion is initiated by the examinee.

CUE: When Examiner directs, initiate malfunction to drop CEAs #30 and #31.

5* INSERT the PLCEAs. INSERT the PLCEAs in small, smooth, frequent movements of less than 3 inches per minute. PLACE Mode Select Switch in OFF when rod insertion is complete. Insertion should not exceed 112.5" (TS 3.1.8 and LCS 3.1.103).

NOTE: The following steps represent the alternate path of this JPM.

Page 6 of 8

JPM: SO 10-05 JPM NRC RO/SRO S-6 TITLE: Restore ASI to ESI

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 DETERMINE that two PLCEAs have VERIFY Rod Bottom indication for CEAs dropped. #30 and #31.

NOTE: Applicant may refer to SO23-13-13, Misaligned Control Element Assembly, to determine appropriate action.

7* TRIP the reactor. INITIATE a Reactor Trip by DEPRESSING at least two manual Reactor trip pushbuttons:

2HS-9132-2 and 2HS-9132-3 or 2HS-9132-1 and 2HS-9132-4 TERMINATING CUE: When the Stop Time: ________

examinee has tripped the Reactor, the evaluation for this JPM is complete.

Page 7 of 8

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO S-7 INITIAL PLANT CONDITIONS The plant is at 70% power with all systems operable.

The Control Operator notices that Safety Injection Tank (SIT T-007) pressure is near the low pressure alarm setpoint.

TASK TO BE PERFORMED The Control Room Supervisor directs you to increase pressure in SIT T-007 to 630 psia.

Page 1 of 8

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO S-7 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SO 10-05 JPM NRC RO/SRO S-7 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 141245 TASK DESCRIPTION Pressurize the Safety Injection Tank.

KA NUMBER: 006 A1.13 KA VALUES: RO 3.5 SRO 3.7 10CFR55.45 APPLICABILITY: 2, 6, and 8

REFERENCES:

SO23-3-2.7.1 Safety Injection Tank Operations, Revision 12 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared against SO23-3-2.7.1, Rev LRZ 07/26/05 REV 12 and removed NOTE that was no longer applicable. Modified setup for performance consistency. Removed Step for SIT Nitrogen Header Pressure verification as that indication is no longer available on the Control Board.

Page 4 of 8

SET-UP Machine Operator:

Use IC-174 (Event File Delete J-70) for October 2005 NRC JPM Exams. Otherwise use any 100% IC.

Reduce SIT T-007 pressure to about 620 psig.

Provide copy of SO23-3-2.7.1, Safety Injection Tank Operation, AFTER examinee identifies procedure to be used.

Page 5 of 8

JPM: SO 10-05 JPM NRC RO/SRO S-7 TITLE: Increase Pressure in SIT T-007 by 10 PSIG

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide copy of SO23-3-2.7.1, Safety Injection Tank Operation, AFTER examinee identifies procedure to be used.

1 Identify the procedure and step to be LOCATE a current copy of SO23-3-2.7.1 and Start Time:________

used. go to Step 6.1.

2 Ensure SIT pressure is 300 psia. OBSERVE SIT T-007 Narrow Range Pressure, 2PI-0322 and/or 2PI-0323 and DETERMINE that it is 300 psia.

3 Verify SIT level is between 79.2% and OBSERVE 2LI-0322 and/or 2LI-0323 SIT 82.9% NR for T-007. Narrow Range Level T007 (LOOP 1B) and DETERMINE that it is between 79.2% and 82.9%.

4* Open SIT Nitrogen Supply Containment DEPRESS the OPEN pushbutton for 2HV-Isolation Valve 2HV-5434 and verify 5434, SIT N2 Supply Iso Valve and VERIFY SIT Nitrogen header pressure is at least SIT Nitrogen header pressure is at least 610 610 psig (PI-5410). psig on 2PI-5410.

5* Open Nitrogen Supply Valve to DEPRESS the OPEN pushbutton for 2HV-SIT T-007, 2HV-9354. 9354, SIT 2T007 (LOOP 1B) N2 Supply Valve.

6* After achieving 630 psia, CLOSE the DEPRESS the CLOSE pushbutton for Nitrogen Supply Valve to SIT T-007, 2HV-9354, SIT N2 Supply Iso Valve when 2HV-9354. the pressure has increased to 630 psia +/- 2 psia.

Page 6 of 8

JPM: SO 10-05 JPM NRC RO/SRO S-7 TITLE: Increase Pressure in SIT T-007 by 10 PSIG

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 7 Verify SIT T-007 level is between OBSERVE 2LI-0322 and/or 2LI-0323 SIT 79.2% and 82.9%. Narrow Range Level T007 (LOOP 1B) and DETERMINE that level remains between 79.2% and 82.9%

8 Close SIT Nitrogen Supply DEPRESS the CLOSE pushbutton for Containment Isolation Valve 2HV-5434, SIT Nitrogen Supply Containment 2HV-5434. Isolation Valve.

TERMINATING CUE: The CO will make Stop Time:________

all required log entries. This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 07/26/05 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO S-8 INITIAL PLANT CONDITIONS Unit 2 is operating at 70% power. Both Component Cooling Water loops are in service. Both Containment Normal Chillers 2E-201 and 2E-202 have tripped. Containment temperature is

>105°F and rising.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform SO23-1-4.1, Containment Emergency Cooling, Section 6.1, Placing the Containment Emergency Cooling System in Service.

Page 1 of 10

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO S-8 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SO 10-05 JPM NRC RO S-8 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CRO TASK SYS ID: 186171 TASK DESCRIPTION Verify actuation, reset, and restoration of Containment Cooling after automatic actuation.

KA NUMBER: 022 A4.01 KA VALUES: RO 3.6 SRO 3.6 10CFR55.45 APPLICABILITY: 3, 8

REFERENCES:

SO23-1-4.1, Containment Emergency Cooling, Rev. 12-1 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

Page 4 of 10

SET-UP Use IC-187 for October 2005 NRC JPM Exams.

Otherwise, place both CCW Critical Loops in service and start CCW Pump P-026.

OPEN the following ECU valves:

2HV-6369

2HV-6373

2HV-6367

2HV-6371 Provide the examinee with a copy of SO23-1-4.1, Containment Emergency Cooling.

Page 5 of 10

JPM: SO 10-05 JPM NRC RO S-8 TITLE: Place Containment Emergency Cooling System in Service

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-1-4.1, Containment Emergency Cooling.

1 Determine if Containment Emergency DETERMINE that Containment Emergency Start Time: ________

Cooling is automatically actuated. Cooling is not automatically actuated by OBSERVING Annunciators 57A07 - CCAS TRAIN A ACTUATION and 57B07 - CCAS TRAIN B ACTUATION are not illuminated.

2 Observe average Containment OBSERVE average Containment temperature temperature > 105°F. > 105°F using TE9902F through TE9902J digital readout on recorder TJR-9899 on CR-60 or using TE9902A through TE9902E on the Plant Monitoring System.

CUE: The Control Room Supervisor directs you to place the Containment Emergency Cooling system in service on a system level.

3 ENSURE associated CCW Train is in DETERMINE that both CCW Trains are in service. service by OBSERVING Train A and Train B CCW Pumps START lamps illuminated on CR-64.

Page 6 of 10

JPM: SO 10-05 JPM NRC RO S-8 TITLE: Place Containment Emergency Cooling System in Service

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4 At CR-60, ENSURE by indication that At CR-60, VERIFY OPEN CCW to the following Motor Operated Valves Containment Emergency Cooling Units:

are OPEN:

2HV-6366, CCW to CNTMT ECU 2E401 CCW to Containment Emergency Iso Valve OPEN lamp illuminated.

Cooling Units

2HV-6370, CCW to CNTMT ECU 2E399

HV-6366, CCW to CNTMT ECU Iso Valve OPEN lamp illuminated.

ME-401 Isolation Valve.

2HV-6368, CCW to CNTMT ECU 2E400

HV-6370, CCW to CNTMT ECU Iso Valve OPEN lamp illuminated.

ME-399 Isolation Valve.

2HV-6372, CCW to CNTMT ECU 2E402

HV-6368, CCW to CNTMT ECU Iso Valve OPEN lamp illuminated.

ME-400 Isolation Valve.

HV-6372, CCW to CNTMT ECU ME-402 Isolation Valve.

5 At CR-60, ENSURE by indication that At CR-60, VERIFY OPEN CCW from the following Motor Operated Valves Containment Emergency Cooling Units:

are OPEN:

2HV-6367, CCW from CNTMT ECU CCW from Containment Emergency 2E401 Iso Valve OPEN lamp illuminated.

Cooling Units

2HV-6371, CCW from CNTMT ECU

HV-6367, CCW from CNTMT ECU 2E399 Iso Valve OPEN lamp illuminated.

ME-401 Isolation Valve.

2HV-6369, CCW from CNTMT ECU

HV-6371, CCW from CNTMT ECU 2E400 Iso Valve OPEN lamp illuminated.

ME-399 Isolation Valve.

2HV-6373, CCW from CNTMT ECU

HV-6369, CCW from CNTMT ECU 2E402 Iso Valve OPEN lamp illuminated.

ME-400 Isolation Valve.

HV-6373, CCW from CNTMT ECU ME-402 Isolation Valve.

Page 7 of 10

JPM: SO 10-05 JPM NRC RO S-8 TITLE: Place Containment Emergency Cooling System in Service

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6* PLACE the Containment Emergency PLACE the Containment Emergency Cooling Cooling System in service by manually System in service by DEPRESSING initiating a Containment Cooling 2HS-9138-1 and 2HS-9138-2 at CR-56 or Actuation Signal using HS-9138-1 and 2HS-9138-3 and 2HS-9138-4 at CR-53.

HS-9138-2 at CR-56 or HS-9138-3 and HS-9138-4 at CR-53.

7 VERIFY the following Annunciators DETERMINE that Containment Emergency actuate: Cooling is actuated by OBSERVING

57A07 - CCAS TRAIN A Annunciators illuminated:

ACTUATION

57A07 - CCAS TRAIN A ACTUATION

57B07 - CCAS TRAIN B

57B07 - CCAS TRAIN B ACTUATION ACTUATION 8 At CR-60, VERIFY by indication that At CR-60, DETERMINE that the Train B the following fans have started: Containment Emergency Cooling Fans Containment Emergency Cooling Fans: 2E-400 and 2E-402 have started by Train A Train B OBSERVING the red START lamps ME-399 ME-400 illuminated.

ME-401 ME-402 CUE: If asked, the CRS directs you to align components as required per SO23-1-4.1.

NOTE: The following steps represent the alternate path of this JPM.

9* At CR-60, START Train A At CR-60, DEPRESS the START pushbuttons Containment Emergency Cooling Fans for 2HS-9953-1 and 2HS-9947-1, Train A ME-399 and ME-401. Containment Emergency Cooling Fans 2E-399 and 2E-401 and OBSERVE the red START lights illuminated.

Page 8 of 10

JPM: SO 10-05 JPM NRC RO S-8 TITLE: Place Containment Emergency Cooling System in Service

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10 At CR-60, VERIFY by indication that At CR-60, DETERMINE that one Train A the following fans have started: (2A-074) and two Train B (2A-072 and 2A-Containment Dome Air Circulator Fans: 073 ) Containment Dome Air Circulator Fans Train A Train B have started by OBSERVING the red START MA-071 MA-072 lamps illuminated.

MA-074 MA-073 11* At CR-60, START Train A At CR-60, DEPRESS the START pushbutton Containment Dome Air Circulator Fan for 2HS-9965-1, Train A Containment Dome MA-071. Air Circulator Fans 2A-071 and OBSERVE the red START lamp illuminated.

TERMINATING CUE: The Radwaste Stop Time: ________

Operator will verify Component Cooling Water flow. This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/05 Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO P-1 INITIAL PLANT CONDITIONS A station blackout has occurred seven (7) hours ago. Class 1E Battery Bus voltages are currently 105 VDC and lowering. Power is not expected to be restored for at least 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

TASK TO BE PERFORMED The Shift Manager directs you to align 2G005 (Unit 2) or 3G005 (Unit 3) per SO23-12-11, , Floating Step 26.

Page 1 of 12

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO P-1 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 12

DOCUMENTATION SO 10-05 JPM NRC RO/SRO P-1 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO/ACO VISION ID: 192231 TASK DESCRIPTION Transfer L411 EPPM Panel power to G005 portable generator.

KA NUMBER: 055-EA1.04 KA VALUES: RO 3.5 SRO 3.9 10CFR55.45 APPLICABILITY: 6, 12

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 2, Floating Step 26, Connect G005 Portable Generator to L411 EPPM Panel / Startup Channel, Rev. 3 AUTHOR: L. Zilli DATE: 03/12/05 OPERATIONS REVIEW: M. Jones DATE: 03/22/05 APPROVED BY: A. Hagemeyer DATE: 03/22/05 Page 3 of 12

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO23-12-11, Rev 3 LRZ 07/26/05 AHH with minor changes required. Deleted Cue for mislabeled door that was corrected in Revision 3.

Page 4 of 12

SET-UP Provide the Examinee with a copy of SO23-12-11, Floating Step 26, Connect G005 Portable Generator to L411 EPPM Panel/Start-up Channel.

NOTE: Obtain permission from the Shift Manager to open cabinet doors associated with this JPM.

NOTE: Circle the Unit on which this JPM will be performed and inform the Examinee.

Page 5 of 12

JPM: SO 10-05 JPM NRC RO/SRO P-1 TITLE: Align G005 to the Essential Plant Parameters Monitoring Panel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Obtain permission from the Shift Manager to open cabinet doors associated with this JPM. Circle the Unit on which this JPM will be performed and inform the Examinee.

NOTE: Provide the Examinee with a copy of SO23-12-11, Floating Step 26, Connect G005 Portable Generator to L411 EPPM Panel/Start-up Channel.

1 VERIFY elapsed time from Station VERIFY elapsed time from Station Blackout Start Time: _________

Blackout greater than 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND greater than 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND restoration of power restoration of power NOT expected to NOT expected to occur within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months occur within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a Station following a Station Blackout and IDENTIFY Blackout, OR ALL Class 1E Battery Bus Class 1E Battery Bus voltages are 105 VDC voltages - less than 108 VDC. and lowering.

2 OBTAIN approval of Shift Manager to ACKNOWLEDGE that the Shift Manager has use G005, Portable Generator to supply: already directed performance of this Floating

- L411, EPPM Panel Step.

- Start-up Channel B.

Page 6 of 12

JPM: SO 10-05 JPM NRC RO/SRO P-1 TITLE: Align G005 to the Essential Plant Parameters Monitoring Panel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 3 INFORM Security and Health Physics INFORM Security and Health Physics that the that the following doors will be blocked following doors will be blocked open:

open: - Door 302 on Units 2 & 3 (45 Pen. To

- Door 302 on Units 2 & 3 (45 50 SEB Roof)

Pen. To 50 SEB Roof) - Door 307 on Unit 2 (45 Pen. To Cable

- Door 307 on Unit 2 (45 Pen. To Spreading Room)

Cable Spreading Room) - Door 342 on Unit 3 (45 Pen. To Cable

- Door 342 on Unit 3 (45 Pen. To Spreading Room)

Cable Spreading Room)

CUE: (When located) The doors are blocked open.

4* ALIGN L411, EPPM Panel: ALIGN L411, EPPM Panel:

- CONNECT extension cord to - CONNECT extension cord to L411P, L411P, Plug for EPPM Panel. Plug for EPPM Panel.

- SELECT HS-411X - to L411P. - SELECT HS-411X - to L411P.

- SELECT XS-411 - to - SELECT XS-411 - to ALTERNATE.

ALTERNATE.

Page 7 of 12

JPM: SO 10-05 JPM NRC RO/SRO P-1 TITLE: Align G005 to the Essential Plant Parameters Monitoring Panel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: Another operator will align L539 Start-up Channel in the Train A Switchgear Room.

NOTE: Step 5 is left for examiner reference only. These actions are not performed in this JPM as it would require the examinee to violate the HP Radiation Control Area and go to the 50 Control Building.

5 ALIGN L539, Start-up Channel: Another operator ALIGNS L539, Start-up

- CONNECT extension cord Channel:

L539P, Plug for Start-up - CONNECTS extension cord L539P, Channel: (Train A 1E Switchgear Plug for Start-up Channel in the Train Room). A 1E Switchgear Room.

- SELECT HS-539X - to L539P. - SELECTS HS-539X to L539P.

- SELECT XS-539B - to - SELECTS XS-539B to ALTERNATE.

ALTERNATE.

6* MOVE G005, Portable Generator from MOVE G005, Portable Generator from G005 G005 locker, (45 Pen. Bldg, west end), locker, (45 Pen. Bldg, west end), to SEB roof to SEB roof outside of Door 302. outside of Door 302.

NOTE: The examinee will be unable to go out onto the SEB roof without violating HP Radiation Controls. Have the examinee explain where they would go (outside onto the roof) and what they would do (get gas can from locker to fill G005 tank). The gasoline is located in a locker approximately 30 from Door 302.

CUE: (When located) G005 is on the SEB Roof.

NOTE: The next step cannot be performed until after exiting the RCA.

7* ADD gasoline located in storage area on ADD gasoline located in storage area on SEB SEB Roof (Between feedwater regulating Roof (Between feedwater regulating valves valves Rooms 110 and 111) to G005. Rooms 110 and 111) to G005.

Page 8 of 12

JPM: SO 10-05 JPM NRC RO/SRO P-1 TITLE: Align G005 to the Essential Plant Parameters Monitoring Panel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: (When located) The gas tank is full.

8 VERIFY oil level between marks. VERIFY G005 oil level is between marks on the oil fill stick.

CUE: (When located) The oil level is between the marks.

9 ENSURE all loads at G005 - ENSURE all loads at G005 are disconnected.

disconnected.

10* ENSURE tank vent - ON. PLACE the G005 gas tank vent to ON.

CUE: (When located) The gas tank vent is on.

11* ENSURE choke - CLOSED. PLACE the G005 choke to CLOSED.

CUE: (When located) The choke is closed.

12* ENSURE Eco-throttle switch - PLACE the G005 Eco-throttle switch to CLOSED. CLOSED.

CUE: (When located) The Eco-throttle switch is closed.

13* ENSURE engine switch - ON. PLACE the G005 engine switch to ON.

CUE: (When located) The engine switch is on.

14* PULL starter. PULL the starter on G005.

CUE: If the previous steps were completed correctly, tell the examinee that G005 is running and the engine is warm.

15* MOVE choke - to OPEN as engine MOVE choke to OPEN as engine warms up.

warms up.

CUE: (When located) The choke is open.

Page 9 of 12

JPM: SO 10-05 JPM NRC RO/SRO P-1 TITLE: Align G005 to the Essential Plant Parameters Monitoring Panel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Connecting extension cords to Startup Channel B cannot be performed without exiting the RCA.

16* CONNECT extension cords to G005 CONNECT extension cords to G005 from from L411P, EPPM Panel AND from L411P, EPPM Panel and from L539P, Start-up L539P, Start-up Channel B. Channel B.

CUE: (When located) The extension cords are connected.

NOTE: L411 (Essential Plant Parameters Monitoring Panel) power supplies are located inside L411 at the bottom of the cabinet. If permission has not been obtained to open the cabinet door then the examinee should explain the general location of the indicating lights and breakers.

17 VERIFY L411 power supply PS-A VERIFY L411 power supply PS-A energized energized: with breaker CLOSED and Red and Green

- Breaker CLOSED AND Red lights illuminated.

and Green lights illuminated.

CUE: (When located) The breaker is closed and the Red and Green lights are illuminated.

18 VERIFY L411 power supply PS-B VERIFY L411 power supply PS-B energized energized: with breaker CLOSED and Red and Green

- Breaker CLOSED AND Red lights illuminated.

and Green lights illuminated.

CUE: (When located) The breaker is closed and the Red and Green lights are illuminated.

Page 10 of 12

JPM: SO 10-05 JPM NRC RO/SRO P-1 TITLE: Align G005 to the Essential Plant Parameters Monitoring Panel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 19* SELECT SG level indications - to SELECT HS-1106 for E088 and HS-1105 for LOCAL. E089, SG level indication hand switches to E088 EO89 LOCAL.

HS-1106 HS-1105 CUE: (When located) The SG level indication hand switches are in LOCAL.

20* SELECT HS-0100F, PZR pressure SELECT HS-0100F, PZR Pressure indication indication - to LOCAL. hand switch to LOCAL.

CUE: (When located) The PZR Pressure indication hand switch is in LOCAL.

21* SELECT HS-0103A, PZR level SELECT HS-0103A, PZR Level indication indication - to LOCAL. hand switch to LOCAL.

CUE: (When located) The PZR Level indication hand switch is in LOCAL.

22 VERIFY Startup-up Channel B - VERIFY Startup-up Channel B is energized.

energized.

CUE: Another operator will energize Startup Channel B.

TERMINATING CUE: Stop Time: _________

This JPM is complete.

Page 11 of 12

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: R. Hampton DATE: 07/23/05 Page 12 of 12

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO P-2 INITIAL PLANT CONDITIONS You are the Unit 2(3) Primary ACO. The Control Room has been evacuated due to dense smoke.

All actions recommended or required to be accomplished prior to leaving the Control Room have been completed.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform duties of the Unit 2 (Unit 3) Primary ACO up to and including notifying the Unit 2 (Unit 3) ACO that 2G002 (3G002) is running at normal voltage and frequency.

THIS IS A TIME CRITICAL JPM Page 1 of 10

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO P-2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SO 10-05 JPM NRC RO/SRO P-2 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 6 minutes TIME CRITICAL JPM: YES CRITICAL TIME: 10 minutes POSITION: SPEO TASK SYS ID: 190519 TASK DESCRIPTION Perform secondary plant shutdown during a plant shutdown from outside the Control Room.

KA NUMBER: 068-AA1.31 KA VALUES: RO 3.9 SRO 4.0 10CFR55.45 APPLICABILITY: 5, 6

REFERENCES:

SO23-13-2, Shutdown From Outside the Control Room, Rev. 7-4 AUTHOR: R. Clement DATE: 11/18/91 OPERATIONS REVIEW: J. Braisted DATE: 09/05/93 APPROVED BY: M. Kirby DATE: 10/26/93 Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 New format. Split step 13 into 2 steps. SW 07/26/93 MJK Minor wording changes. Suggested Time Critical JPM, with a maximum time of 12 minutes. Actual time allow in SONGS 2/3 Appendix R Time and Manpower study is 6.2 minutes. Since we do not have past performance times, it is recommended 25 minutes be used to accommodate the examinees describing their actions until better times are obtained.

1-1 Compared to SO23-13-2, TCN 2-17; HJW 12/27/93 N/A no changes required.

1-2 Changed setup page; minor editorial HJW 03/17/94 N/A corrections for clarity; changed critical time from 12 to 10 based on history.

1-3 Compared against SO23-13-2, TCN 2- HJW 09/08/94 N/A 18 with no changes required.

1-4 Compared against SO23-13-2, TCN 2- HJW 04/26/96 N/A 20 with no changes required.

1-5 Compared against SO23-13-2, Rev. 3 HJW 06/04/97 N/A with minor editorial corrections.

Upgraded Document page for NUREG-1122, Rev. 1.

1-6 Compared against SO23-13-2, Rev. 5 RCW 08/26/98 N/A with no changes required. Swapped JPM steps 12 and 13 to coincide with procedure sequencing.

Page 4 of 10

REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1-7 Compared against SO23-13-2, TCN 5- JJM 10/15/99 FM 2, expanded cue that informs student that D/G will be supplying A04 thus idle start is n/a. Added Unit 3 designator to all components so that JPM can be performed on either unit.

Setup includes instructions to provide Att. 8 (U2) or Att. 9 (U3). Upgraded KA and changed old task number to VISION SYS ID. Added clarifying information to the note at the beginning of the JPM that the timing starts when the D/G bldg is entered.

Cue changed to reflect that the student already has been to the SSD locker and has his kit and equip.

1-8 Compared against SO23-13-2, TCN 6- JJM 08/06/02 AH

5. Removed BR-0122 Category from doc page. Added equipment obtained from SSD locker and added alpha-numeric designation for reset lamp and reset pushbutton.

1-9 Compared against SO23-13-2, TCN 7- RCW 09/01/04 AH

3. Added several cues. Made minor editorial changes. Updates Task Sys ID.

1-10 Compared against SO23-13-2, TCN 7- RHH 07/27/05 AHH 4 with no changes required.

Page 5 of 10

SET-UP Provide the Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, Attachment 8 (Unit 2) or Attachment 9 (Unit 3).

NOTE: Circle the Unit on which this JPM will be performed and inform the Examinee.

Page 6 of 10

JPM: SO 10-05 JPM NRC RO/SRO P-2 TITLE: Perform Duties of Unit 2(3) Primary ACO to Start 2(3)G002

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Proceed to 2G002 (3G002), then provide the examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, Attachment 8(9). The timing of this JPM starts when the student enters the Diesel Generator Building.

CUE: You have been to the Safe Shutdown Locker and have obtained the following from Safe Shutdown Kit 23(33): Emergency lantern, earplugs, headset, set of Security keys and Atmosphere Monitor.

1 Connect headset to CKT No. 1 jack in LOCATE Circuit 1 jack in West Lobby Area Start Time: ________

the West Lobby Area. and SIMULATE connecting a headset.

2* Select 2(3)G002 Fire Isolation switch SIMULATE PLACING 2(3)HS-1670A1, Fire HS-1670A1 to local at 2(3)L160. Isolation Switch DG Control, on 2(3)L160, in LOCAL position.

CUE: The switch is in LOCAL.

3* Select 2(3)G002 Fire Isolation switch SIMULATE PLACING 2(3)HS-1669A1, Fire HS-1669A1 to local at 2(3)L160. Isolation Switch Gov. & Exct. Cont, on 2(3)L160, in LOCAL.

CUE: The switch is in LOCAL.

4* Select 2(3)G002 Fire Isolation switch SIMULATE PLACING 2(3)HS-9537E1, Fire HS-9537EI to local at 2(3)L160. Isolation Switch DG Bldg Fans, on 2(3)L160, in LOCAL position.

CUE: The switch is in LOCAL.

CUE: There is no sound of an engine running.

Page 7 of 10

JPM: SO 10-05 JPM NRC RO/SRO P-2 TITLE: Perform Duties of Unit 2(3) Primary ACO to Start 2(3)G002

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 Determine whether 2(3)G002 Cooling OBSERVE both HI-HI Coolant Temperature Water System has been impaired, as Engine 1 and 2 alarms on 2(3)UA-0160 not indicated by presence of either of the alarming.

following alarms:

HI-HI COOLANT TEMPERATURE ENGINE #1" HI-HI COOLANT TEMPERATURE ENGINE #2" CUE: Both alarms are clear.

6 Select Diesel Generator Control Panel SIMULATE PLACING Diesel Generator ammeter to 1, 2 or 3. Control Panel Ammeter 2(3)HS-E936 on 2(3)L160 to 1, 2 or 3 position.

CUE: The switch is as-found.

7 Select the Diesel Generator Control SIMULATE PLACING Diesel Generator Panel voltmeter to 1-2, 2-3, or 3-1. Control Panel Voltmeter 2(3)HS-E935 on 2(3)L160 to 1-2, 2-3 or 3-1 position.

CUE: The switch is as-found.

8 Ensure Diesel Generator Lockout Relay OBSERVE Diesel Generator Lockout Relay reset [2(3)HS-E934; Reset Lamp is Reset lamp 2 (3) ZL-E906 on 2(3)L160 2 (3) ZL-E906] illuminated.

CUE: Lockout Relay Reset lamp is on.

9 Establish communications with and SIMULATE CONTACTING Unit 2(3) ACO notify the Unit 2(3) ACO that 2(3)G002 via sound powered phone, radio or PAX, ready to start. indicate 2(3)G002 is ready to start.

CUE: Unit 2(3) ACO directs you to start the diesel and informs you that the diesel will be supplying Bus 2(3)A04.

Page 8 of 10

JPM: SO 10-05 JPM NRC RO/SRO P-2 TITLE: Perform Duties of Unit 2(3) Primary ACO to Start 2(3)G002

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10* Start 2(3)G002 by momentarily placing SIMULATE PLACING Local Engine Control the Local Engine Control Switch to Switch, 2(3)HS-5995-1, to START.

START.

CUE: Engine speed increases.

11 Observe 2(3)G002 runup to normal OBSERVE indicators 2(3)SI-E933, Generator voltage and frequency ranges. Frequency, and 2(3)EI-E931, Generator Voltage, for 2(3)G002.

CUE: (When observed) Frequency indicates 58.5 Hz, Voltage 4100 VAC.

12 Adjust 2(3)G002 frequency to 60 Hz. SIMULATE PLACING Governor 2(3)HS-E940 to the RAISE position.

CUE: (When observed) Frequency indication is 60 Hz.

13 Adjust 2(3)G002 voltage to 4360 VAC. SIMULATE PLACING Local Volt Adjust 2(3)HS-E942 to the RAISE position.

CUE: (When observed) Voltage indication is 4360 VAC.

14 Notify the Unit 2(3) ACO when NOTIFY Unit 2(3) ACO via sound powered 2(3)G002 is running at normal voltage phone, radio or PAX, that 2(3)G002 is and frequency. running at normal voltage and frequency.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: R. Hampton DATE: 07/24/05 Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER SO 10-05 JPM NRC RO/SRO P-3 INITIAL PLANT CONDITIONS The Control Room has been evacuated. Both Units completed necessary actions prior to evacuation.

You are the Radwaste Operator.

You have been to the Safe Shutdown Locker, and have obtained all of the required equipment.

TASK TO BE PERFORMED If performing on Unit 2:

The Control Room Supervisor directs you to perform the Unit 2 duties of the Radwaste Operator following a Control Room evacuation, using SO23-13-2, Shutdown from Outside the Control Room, Attachment 10, Radwaste Operator Duties - Unit 2.

If performing on Unit 3:

The Control Room Supervisor directs you to perform the Unit 3 duties of the Auxiliary Primary Operator following a Control Room evacuation, using SO23-13-2, Shutdown from Outside the Control Room, Attachment 11, Auxiliary Primary Operator Duties - Unit 3.

Page 1 of 8

JOB PERFORMANCE MEASURE SO 10-05 JPM NRC RO/SRO P-3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SO 10-05 JPM NRC RO/SRO P-3 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 191625 TASK DESCRIPTION Perform the Radwaste Operator/Auxiliary Reactor Operator (Auxiliary Primary ACO) tasks during a shutdown from outside the Control Room.

KA NUMBER: 068 AA1.08 KA VALUES: RO 4.2 SRO 4.2 10CFR55.45 APPLICABILITY:

REFERENCES:

SO23-13-2, Shutdown from Outside the Control Room, Rev 7-4.

AUTHOR: R. Whitehouse DATE: 09/20/04 OPERATIONS REVIEW: M. Jones DATE: 09/20/04 APPROVED BY: S. Whitley DATE: 09/20/04 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - from J123F: J123F was Unit 3 RCW 08/17/04 NEW only and J122 was dual unit for the same task but not faulted. Converted J123F to J122F to be the faulted version of the dual unit JPM.

1 Removed the requirement to go to the RCW 09/20/04 REV SSD locker. This was a critical step.

1-1 Compared against SO23-13-2, Rev 7-4 RHH 07/27/05 AHH with no changes required.

Page 4 of 8

SET-UP Provide Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, 0 if performing on Unit 2 or Attachment 11 if performing on Unit 3.

This is a faulted JPM. The faulted condition is that valve 2(3)HV-6497, SWC/CCW HX Outlet Valve is closed and cannot be opened.

NOTE: Circle the Unit on which this JPM will be performed and inform the Examinee.

Page 5 of 8

JPM: SO 10-05 JPM NRC RO/SRO P-3 TITLE: Perform the Primary Operator Tasks During a Shutdown From Outside the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, Attachment 10 for Unit 2 or Attachment 11 for Unit 3.

CUE: You have been to the SSD locker and have all of the required equipment.

1 Proceed to Radwaste via Control PROCEED to Radwaste via the Control Start Time: ________

Building Central Stairwell and the Building Central Stairwell and the Health Health Physics Control Point. Physics Control Point.

NOTE: Both Gravity Feed Valves are opened in any order.

2* At 24' Radwaste open 2(3)HV-9235, At 24' Radwaste, SIMULATE OPENING BAMU Gravity Feed. 2(3)HV-9235, BAMU Tank 2(3)T072 Gravity Feed to Charging Pump suction Isolation Valve.

CUE: 2(3)HV-9235 is open.

3* At 24 Radwaste open 2(3)HV-9240, At 24 Radwaste, SIMULATE OPENING BAMU Gravity Feed. 2(3)HV-9240 2(3)T071 Gravity Feed to Charging Pump suction Isolation Valve.

CUE: 2(3)HV-9240 is open.

4* At 37' Radwaste close 2(3)LV-0227B, At 37' Radwaste, SIMULATE CLOSING VCT Outlet (RM. 319B, Key No. HR) 2(3)LV-0227B, VCT Outlet Valve in Room 319B. A key may not be needed for this room depending on present radiological conditions.

CUE: 2(3)LV-0227B is closed.

Page 6 of 8

JPM: SO 10-05 JPM NRC RO/SRO P-3 TITLE: Perform the Primary Operator Tasks During a Shutdown From Outside the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 At 9' Radwaste ensure closed At 9' Radwaste, VERIFY 2(3)LV-0227C, 2 (3) LV-0227C, RWST to Charging Boric Acid to Charging System Control Valve Pump suction. is CLOSED.

CUE: 2(3)LV-0227C is closed.

NOTE: The following steps represent the alternate path of this JPM.

This portion of the JPM is performed outside the RCA.

6* ENSURE OPEN 2(3)HV-6497, LOCATE 2(3)HV-6497, SWC/CCW HX SWC/CCW HX Outlet Valve. Outlet Valve, and IDENTIFY the valve position indicator.

CUE: 2(3)HV-6497, SWC/CCW HX Outlet Valve indicates closed and cannot be opened.

7* OPEN MCC Breaker 2BK23 (3BK22). SIMULATE OPENING MCC Breaker 2BK23 (3BK22), Salt Wtr Fr Component Clg Wtr Heat Exchanger 2(3)HV-6496.

CUE: 2BK23 (3BK22) is open.

8* MANUALLY OPEN 2(3)HV-6496, SIMULATE OPENING 2(3)HV-6496, Overboard Block Valve to Seawall. Overboard Block Valve to Seawall.

TERMINATING CUE: Stop Time: ________

2(3)HV-6496 is open. This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: R. Hampton DATE: 07/24/05 Page 8 of 8

Appendix D Scenario Outline for NRC Form ES-D-1 Facility: San Onofre Scenario No.: 1 Op Test No.: NRC Examiners: Operators:

Initial Conditions:

100% power - RCS Boron is 888 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Auxiliary Feedwater Pump (P-141) OOS

Train A High Pressure Safety Injection (P-017) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Maintain steady-state power conditions.

Critical Tasks:

Establish RCS temperature control (Turbine fails to trip).

Trip any RCP not satisfying RCP operating limits.

Stabilize RCS temperature/pressure following loss of heat removal from the faulted Steam Generator.

Event No. Malf. No. Event Type* Event Description 1 FW23 C (ACO, CRS) Partial loss of Condenser vacuum @ 3%.

+ 5 min 2 R (CO) Downpower for Condenser Backpressure.

+ 10 min N (ACO, CRS) 3 CV17A C (CO, CRS) Both BAMU Pumps trip.

+ 20 min CV17B TS(CRS) 4 TS (CRS) Main Steam and Main Feedwater Isolation Valves declared

+ 25 min inoperable.

5 RD2103 C (CO, ACO, CRS) Dropped CEA #21.

+ 30 min TS (CRS) 6 MS03B M (ALL) ESDE on E089 inside Containment.

+ 50 min 7 TU07 C (ACO) Turbine auto trip failure, manual trip required.

+50 min

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline for NRC Form ES-D-1 SCENARIO

SUMMARY

NRC #1 The crew will assume the watch at 100% power and maintain steady-state conditions per SO23-5-1.7, Power Operations.

When turnover is complete, a partial loss of vacuum will occur. The crew will respond per the Annunciator Response Procedures (ARP) and AOI SO23-13-10, Loss of Condenser Vacuum and lower power level until the Turbine Vacuum Limit is in the Area of Unrestricted Operation.

When the CO initiates RCS boration for the power reduction, the in-service and standby Boric Acid Makeup Pumps (BAMU) will trip, requiring gravity feed from the BAMU tanks for boration.

The CRS will evaluate Technical Specifications.

Once the plant is stabilized, the Main Steam and Main Feedwater Isolation Valves will be declared inoperable due to improper hydraulic fluid. The CRS will evaluate Technical Specifications.

This is followed by a dropped CEA and requires crew actions per the ARPs and AOI SO23 13, Misaligned or Immovable Control Element Assembly.

The EOP entry point is caused by an ESDE on E089 inside Containment. The crew performs SO23-12-1, Standard Post Trip Actions and diagnoses an ESDE. The crew will transition to SO23-12-5, Excess Steam Demand Event and perform necessary actions to stabilize RCS temperature.

During this event the Turbine fails to trip requiring manual actions on the part of the ACO. The scenario is terminated when the crew stabilizes RCS temperature/pressure following pressure following loss of heat removal from the faulted Steam Generator.

Risk Significance:

Risk important components out of service: HPSI P-017, AFW P-141

Failure of risk important system prior to trip: Loss of BAMU Pumps

Risk significant core damage sequence: ESDE with Turbine trip failure

Risk significant operator actions: Failure to trip Main Turbine Stabilize RCS temperature following ESDE Appendix D NUREG 1021 Revision 9

Scenario Event Description NRC Scenario 1 SONGS 2005 Facility NRC Initial License Examination Simulator Scenario Setup Scenario 1 MACHINE OPERATORS INSTRUCTIONS SETUP IC: Use IC #176 and see attached Event File for NRC Scenario #1.

STEPS TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER Appendix D NUREG 1021 Revision 9

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1, 2, & 3 Page 4 of 22 Event

Description:

Partial Loss of Condenser Vacuum, Downpower, RCS Boration using Gravity Feed Time Position Applicants Actions or Behavior Control Room Annunciators in Alarm at 100%:

57A58 - EMERGENCY FEEDWATER SYS TRAIN A INOPERABLE Indications available:

99B37 - VACUUM LO Indication of rising Main Condenser backpressure into the area of restricted operation Slight drop in Main Generator MWe output Condensate Pump P-053 may auto start due to the secondary transient 58A46 - BAMU PUMP P174 OC (once boration is attempted) 58A47 - BAMU PUMP P175 OC (once boration is attempted)

+1 min ACO REFER to Annunciator Response Procedure.

DETERMINE that vacuum is degrading due to an unknown and/or uncontrollable cause, and the Main Turbine is operating ACO in the restricted area of SO23-5-1.7, Attachment 5, Turbine Vacuum Limits and INFORM the CRS AOI SO23-13-10 entry required.

DIRECT performance of AOI SO23-13-10, Loss of Condenser CRS Vacuum.

VERIFY Vacuum Pump P-054 auto starts or manually START ACO Vacuum Pump.

DECLARE RT-7870 process flow rate monitor inoperable and CRS INITIATE a LCOAR/EDMR.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1, 2, & 3 Page 5 of 22 Event

Description:

Partial Loss of Condenser Vacuum, Downpower, RCS Boration using Gravity Feed Time Position Applicants Actions or Behavior Within one hour of completing a change of Condenser CRS/ACO evacuation flow, PERFORM SO23-3-3.21, Attachment for Shiftly Flow Estimates.

INITIATE aligning S21313MU219, Hogger/SJAE Nozzle CRS/ACO Manifold Selector fully to the MP-054 position.

After two minutes of operating, PLACE Vacuum Pump P-054 in ACO MANUAL.

ACO VERIFY Gland Seal steam pressure > 2 psig on PI-2845.

DETERMINE Condenser backpressure is NOT in the area of ACO Unrestricted Operation in Attachment 3.

INITIATE Attachment 1 and DISPATCH personnel to locate CREW source of vacuum leak.

CO VERIFY a Reactor trip has not occurred.

ACO VERIFY a Turbine trip has not occurred.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1, 2, & 3 Page 6 of 22 Event

Description:

Partial Loss of Condenser Vacuum, Downpower, RCS Boration using Gravity Feed Time Position Applicants Actions or Behavior ACO REDUCE Turbine load as required to maintain:

Backpressure in the Area of Unrestricted Operation in Attachment 3.

Condenser Delta T 25ºF.

Floor Cue: If asked, REPORT Condenser Delta T is 22ºF.

BORATE the RCS or INSERT CEAs as Turbine load is CO reduced.

INITIATE boration in accordance with SO23-3-2.2, Makeup CO Operations.

DETERMINE amount of boric acid to be added from thumb CO rules page.

COMMENCE periodically changing boronometer setpoints to CO

(+50, -25 ppm) of existing boron concentration.

POSITION FIC-0210Y, BAMU Flow Controller, to AUTOMATIC CO and set to the required flowrate.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1, 2, & 3 Page 7 of 22 Event

Description:

Partial Loss of Condenser Vacuum, Downpower, RCS Boration using Gravity Feed Time Position Applicants Actions or Behavior SET FQIS-0210Y, BAMU to VCT T-077, Borate Batching CO Counter, to the required volume (103 gallons for 5%).

SELECT the BAMU Pump associated with the BAMU Tank CO used.

CO BORATE to the Charging Pump suction:

VERIFY closed FV-9253, Blended Makeup to VCT isolation.

PLACE HV-9257, BAMU to Charging Pump Suction Block Valve in AUTOMATIC.

CO SELECT HS-0210, Makeup Mode Selector, to BORATE.

CO DETERMINE that selected BAMU Pump tripped upon starting:

58A46 - BAMU PUMP P174 OC.

START BAMU Pump P-175 by placing the pump control switch CO in START or by placing HS-9264 to the P-175 position.

CO DETERMINE that selected BAMU Pump tripped upon starting:

58A47 - BAMU PUMP P175 OC.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1, 2, & 3 Page 8 of 22 Event

Description:

Partial Loss of Condenser Vacuum, Downpower, RCS Boration using Gravity Feed Time Position Applicants Actions or Behavior OPEN Gravity Feed Valves from BAMU Tank (HV-9235 or HV-CO 9240) or RWST Graviity Feed Valve (LV-0227C) to initiate boration or INSERT CEAs.

CO MONITOR plant parameters.

+20 min CRS EVALUATE Technical Specifications.

3.1.9.A is applicable (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION) to restore boron injection flowpath to OPERABLE status.

NOTE: Loss of both BAMU Pumps represents loss of a single flowpath as both BAMU Pumps are powered from Train A. The Gravity Feed Valves are powered from Train B and represent the other Train.

CRS NOTIFY GCC of the load reduction.

NOTE: Crew may determine that Part Length CEA insertion is necessary for ASI control.

VERIFY that the loss of vacuum is not the result of recent CRS equipment status changes on either Unit.

When vacuum has stabilized and/or power reduction is complete, or at Lead Evaluators discretion, PROCEED to Event 4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 9 of 22 Event

Description:

Main Steam and Main Feedwater Isolation Valves Declared Inoperable Time Position Applicants Actions or Behavior Machine Operator: When directed, CONTACT Control Room as Maintenance Engineering and REPORT that the wrong hydraulic fluid was placed into the MSIVs and MFW Isolation Valves.

Indications available:

None

+1 min CRS EVALUATE Technical Specifications.

No available 3.7.2 LCO for two MSIVs inoperable in Mode 1 requires LCO 3.0.3 entry (7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ACTION).

3.7.3.A is applicable (7 day ACTION).

Close or isolate inoperable MFIV.

Floor Cue: Once the decision to shutdown is made, REPORT as the Shift Manager and DIRECT plant shutdown at 20% per hour.

+5 min DIRECT performance of a Plant Shutdown per SO23-5-1.7, CRS Power Operations to place the Unit in Mode 3.

When Technical Specifications have been reviewed, or at Lead Evaluators discretion, PROCEED to Event 5.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 10 of 22 Event

Description:

Dropped CEA #21 Time Position Applicants Actions or Behavior Indications available:

50A28 - CEA DEVIATION 50A36 - POWER DEPENDENT INSERTION LIMIT 50A37 - PRE-POWER DEPENDENT INSERTION LIMIT 50A38 - CEA GROUP DEVIATION 50A02 - COLSS ALARM 50A10 - CEDMCS CEA WITHDRAWAL PROHIBIT CEA #21 Rod Bottom indication

+1 min RECOGNIZE that Regulating Group 1 CEA 21 has dropped CO and INFORM the CRS AOI SO23-13-13 entry required.

DIRECT performance of AOI SO23-13-13, Misaligned or CRS Immovable Control Element Assembly.

CO VERIFY that no more than one CEA is misaligned > 7 inches.

CO ENSURE CEDMCS Mode Selector Switch in OFF.

REDUCE Turbine load using CVOL to restore RCS Tcold to the ACO pre-CEA drop value and block load changes.

CO VERIFY Reactor is critical.

RECORD initial and stabilized reactor power for subsequent CRS SDM calculation.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 11 of 22 Event

Description:

Dropped CEA #21 Time Position Applicants Actions or Behavior Within 15 minutes, DIRECT monitoring of DNBR and LPD per CRS SO23-3-3.6, Attachment 1.

Floor Cue: The Work Control Supervisor will complete the DNBR and LPD monitoring in accordance with SO23-3-3.6, Attachment 1.

DIRECT performance of Attachment 3, Misaligned CEA CRS checklist.

Within 15 minutes of discovery, DIRECT initiation of Reactor CRS power reduction.

For Non Group 6 Full Length CEA, REDUCE power 10%

within 60 minutes.

NOTE: CRS should recognize that power reduction due to dropped CEA

(~3%) satisfies the 15 minute requirement to initiate a power reduction. The remaining power reduction must be accomplished within 60 minutes.

COMMENCE lowering Turbine Generator load using CVOL ACO while maintaining Tcold per SO23-5-1.7.

DIRECT initiation of boration of the RCS per SO23-3-2.2 to CRS achieve target power level.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 12 of 22 Event

Description:

Dropped CEA #21 Time Position Applicants Actions or Behavior CO COMMENCE attempting to control ASI near full power ESI.

CRS REQUEST Reactor Engineering to report to the Control Room.

CRS INITIATE recovery of affected CEA per Attachment 1.

CO VERIFY CEA position indications agree:

COMPARE affected CEA PIDs from CEAC No. 1 and 2 at CPC Operator Console.

COMPARE affected CEA PIDs from CEAC No. 1 and 2 at Secondary Rod Position CRT.

CHECK UEL and LEL lights.

+20 min VERIFY one CEA has not been misaligned >7 inches for an CO/CRS unknown duration.

When the CEA evaluation is completed, or at Lead Evaluators discretion, PROCEED to Events 6 and 7.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 13 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior Indications available:

60A02 - CONTAINMENT HUMIDITY HIGH 60A12 - REACTOR CAVITY TEMP HI 60A03 - CONTAINMENT / FHB TEMP HI 56A35 - CONTAINMENT PRESSURE HI PRE-TRIP 56A16 - PRESSURIZER PRESSURE LO PRE-TRIP RECOGNIZE that an uncontrolled cooldown is in progress and CO/ACO INFORM the CRS that reactor trip is required.

CRS DIRECT entry into SO23-12-1, Standard Post Trip Actions.

CRS INITIATE Administrative Actions:

RECORD time of Reactor trip ____________.

ANNOUNCE Reactor trip via PA System.

INITIATE Attachment 4, WORKSHEET.

INITIATE Attachment 5, ADMINISTRATIVE ACTIONS.

CO VERIFY Reactivity Control criteria satisfied:

VERIFY Reactor Trip Circuit Breakers (8) - open.

VERIFY maximum of one full length CEA - NOT fully inserted.

VERIFY Reactor power - lowering AND Startup rate -

negative.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 14 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior ACO VERIFY Vital Auxiliaries functioning properly:

CRITICAL

Establish RCS Temperature Control - DETERMINE Main TASK Turbine NOT tripped and MANUALLY TRIP Turbine.

HP and LP Stop and Governor Valves - closed.

MWE output - lowering.

VERIFY both Unit Output Breakers - open.

VERIFY Main Turbine speed - less than 2000 RPM OR -

lowering.

VERIFY CCW Pump aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger - operating.

VERIFY both 1E 4 kV Buses - energized.

VERIFY both 1E 480 V Buses B04 and B06 - energized.

VERIFY all 6.9 kV and Non-1E Buses - energized.

VERIFY all Class 1E DC Buses - energized.

CO DETERMINE RCS Inventory Control criteria NOT satisfied:

DETERMINE PZR level NOT between 10% and 70% AND NOT trending to between 30% and 60%.

VERIFY Core Exit Saturation Margin - greater than or equal to 20°F:

QSPDS page 611.

CFMS page 311.

CO DETERMINE RCS Pressure Control criteria NOT satisfied:

DETERMINE PZR pressure (WR and NR) NOT between 1740 PSIA and 2380 PSIA AND NOT controlled AND NOT trending to between 2025 PSIA and 2275 PSIA.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 15 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior CO DETERMINE Core Heat Removal criteria is NOT satisfied:

CRITICAL

Trip any RCP not satisfying RCP operating limits - STOP all TASK RCPs due to CIAS.

RECORD time of all RCPs off.

VERIFY operating loop Delta T (Th-Tc) less than 58°F.

VERIFY Th and Tc not rising.

VERIFY operating loop Th and REP CET within 16°F.

QSPDS page 611.

CFMS page 311.

VERIFY Core Exit Saturation Margin 20°F.

QSPDS page 611.

CFMS page 311.

VERIFY Reactor Vessel level 100% (plenum).

QSPDS page 622.

CFMS page 312.

NOTE: It is acceptable for CO to report only Monitoring for Natural Circulation.

ACO DETERMINE RCS Heat Removal criteria NOT satisfied:

DETERMINE both SGs level - NOT greater than 21% NR.

VERIFY both SGs level - less than 80% NR.

DETERMINE the following:

Auxiliary feedwater available to restore E088 SG level - between 40% NR and 80% NR.

Main feedwater NOT available to restore both SGs level - between 40% NR and 80% NR with flow to each SG (MSIS actuated):

No MFW Pumps - operating.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 16 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior

RTO - actuated to both SGs.

PREVENT SG high level:

CLOSE MFW Block Valves:

E-088 E-089 HV-4047 HV-4051

DETERMINE heat removal NOT adequate:

TC - less than 555°F.

SG pressures - less than 1000 PSIA.

DETERMINE TC less than 545°F and NOT controlled.

DETERMINE SG pressures - less than 740 PSIA.

CO DETERMINE Containment Isolation criteria NOT satisfied:

DETERMINE Containment pressure - greater than 1.5 PSIG.

VERIFY Containment Area Radiation Monitors energized AND NOT alarming or trending to alarm.

VERIFY Secondary Plant Radiation Monitors energized AND NOT alarming or trending to alarm.

DETERMINE Containment Temperature, Pressure and CO Combustible Gas Control criteria NOT satisfied:

DETERMINE Containment average temperature - greater than 120°F.

DETERMINE Containment pressure - greater than 1.5 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 17 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior

+15 min CRS DIAGNOSE Event in Progress:

DETERMINE all safety function criteria are NOT met per Attachment 4, WORKSHEET.

COMPLETE Attachment 1, Recovery Diagnostic.

DIAGNOSE ESDE in progress.

NOTIFY personnel of event in progress.

DESIGNATE SRO-in-charge.

DIRECT initiation of Steps 11 through 14.

DIRECT performance of SO23-12-5, Excess Steam Demand CRS Event.

ENSURE SO23-12-1, Standard Post Trip Actions, Steps 1-10, CRS complete.

RECORD time of EOI entry.

CRS VERIFY ESDE diagnosis.

INITIATE SO23-12-10, Safety Function Status Checks.

INITIATE Foldout Page.

FS-7, SI Throttle/Stop

FS-3, Monitor Natural Circulation

Attachment 22, Non-Qualified Loads Restoration

FS-30, Stabilize RCS Temperature

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 18 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior

Attachment 28, Isolation of SG with ESDE

VERIFY ESDE diagnosis using Figure 1, Break Identification Chart.

INITIATE sampling of both Steam Generators for radioactivity and boron.

CRS INITIATE Administrative Actions.

NOTIFY Shift Manger/Operations Leader of SO23-12-5, Excess Steam Demand Event initiation.

ENSURE Emergency Plan is initiated.

IMPLEMENT Placekeeper.

CO VERIFY ESF actuation.

VERIFY SIAS actuation required.

PZR pressure less than SIAS setpoint.

OR

Containment pressure > 3.4 PSIG.

ENSURE the following actuated:

SIAS / CCAS / CRIS CRS RECORD time of SIAS.

ACO STOP unloaded Diesel Generators.

INITIATE SO23-12-11, Attachment 22, Non-Qualified Load ACO Restoration.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 19 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior ACO VERIFY MSIS actuation required and ENSURE MSIS actuated.

SG pressure < 740 PSIA..

CO VERIFY CIAS actuation required and ENSURE CIAS actuated.

Containment pressure > 3.4 psig.

CFMS pages 342 and 343.

CO VERIFY SIAS actuated.

CO ESTABLISH Optimum SI Alignment.

ESTABLISH two train operation

All Charging Pumps operating

One HPSI and one LPSI per train operating.

All Cold leg flow paths aligned

VERIFY SI flow required

SI flow indicated

RCS pressure greater than 1250 psia OR

VERIFY FS-7, Verify SI Throttle/Stop criteria satisfied.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 20 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior ACO CLOSE MSIVs and MSIV Bypasses.

ENSURE MSIVs - closed.

HV-8205 for E088

HV-8204 for E089

ENSURE MSIV Bypasses - closed

HV-8203 for E088

HV-8202 for E089 CREW PREVENT Pressurized Thermal Shock.

INITIATE FS-30, Establish Stable RCS temperature during ESDE.

NOTE: The following steps from FS-30 will be performed when conditions are met. Both the ESDE procedure and the ESDE Foldout Page direct performance of these steps.

+20 min VERIFY SG least affected by ESDE, SG E088, NOT isolated ACO for SGTR.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 21 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior CRITICAL Stabilize RCS temperature/pressure following loss of heat TASK ACO removal from the faulted Steam Generator.

OPERATE ADV on SG E088 to stabilize RCS temperatures as faulted SG level lowers.

SG E089 at 10% WR, position SG E088 ADV, HV-8419 to 10% open.

SG E089 at 5% WR, set SG E088 ADV, HV-8419, at Psat for lowest Tc.

SG E089 initial dryout, adjust SG E088 ADV, HV-8419, at Psat for lowest Tc attained as SG boils dry.

ACO STABILIZE least affected SG E088 pressure.

OPERATE ADV in automatic.

STABILIZE AFW flow.

VERIFY RCS pressure is to the right of the Appendix E curve CO on Attachment 29, Post-Accident Pressure/Temperature Limits.

OPERATE feedwater on SG E088 to maintain level between ACO 40% and 80% NR.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 Page 22 of 22 Event

Description:

ESDE on E089 Inside Containment / Turbine Trip Failure Time Position Applicants Actions or Behavior ACO ISOLATE SG E089. CLOSE/STOP the following components:

MSIV HV-8204

MSIV Bypass HV-8202

ADV HV-8421

MFIV HV-4052

AFW valves HV-4715, HV-4731

Steam to AFW P-140 HV-8200

SG Blowdown Isolation HV-4053

SG Water Sample Isolation HV-4057

Electric AFW Pump P-141 ACO ENSURE ADV on SG E089 selected to MANUAL.

When the affected Steam Generator E089 is isolated, TERMINATE the scenario.

Appendix D Scenario Outline for NRC Form ES-D-1 Facility: San Onofre Scenario No.: 3 Op Test No.: NRC Examiners: Operators:

Initial Conditions:

30% power - RCS Boron is 1237 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Auxiliary Feedwater Pump (P-141) OOS

Train A High Pressure Safety Injection (P-017) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Boration and downpower as directed by Operations Management.

Critical Tasks:

Energize at least one vital electrical AC bus and associated 480 V 1E bus.

Restore flow to the Component Cooling Water Non-Critical Loop (RCPs operating).

Event No. Malf. No. Event Type* Event Description 1 R (CO) Boration and downpower at 10%/hr.

+ 15 min N (ACO, CRS) 2 NI08B I (CO, CRS) NI Channel B Upper Detector failure.

+ 20 min TS (CRS) 3 PG22 C (ACO, CRS) Degraded grid voltage to Sustained Degraded Voltage Setpoint.

+30 min PG23 TS (CRS) 4 I (CO, CRS) Letdown Pressure instrument fails low (2PIC-0201 B-CR58-

+45 min MOI).

5 FW18A I(ACO, CRS) SG E089 Feed Flow Transmitter fails high.

+55 min 6 PG24 M (ALL) Loss of Offsite Power.

+ 65 min TU08 Turbine trip.

7 ED03B M (ALL) 2A06 Bus Fault.

+ 66 min 8 EG08A C (ACO) EDG 2G002 mechanical failure.

+67 min 9 PG57 M (ALL) Loss of SDG&E Switchyard.

+70 min

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline for NRC Form ES-D-1 SCENARIO

SUMMARY

NRC #3 The crew will assume the watch with a boration requested by Reactor Engineering (to obtain calorimetric data at 25% power) per SO23-5-1.7, Power Operations.

After the crew has demonstrated control of the power change, a Nuclear Instrument Upper Detector failure will occur. The crew will respond per the Annunciator Response Procedures (ARP) and Abnormal Operating Instruction (AOI) SO23-13-18, Reactor Protection System Failure. The CRS will evaluate Technical Specifications.

This is followed by a frequency drop and grid voltage decrease to the Sustained Degraded Voltage Signal (SDVS) for 110 seconds that will require crew response and entry into AOI SO23-13-4, Operation during Major System Disturbances. The ACO will be required to adjust Main Generator MVARs and restart a CCW Pump. The CRS will evaluate Technical Specifications.

With the plant stable, the crew will respond to a Letdown Pressure Instrument failure. This will require action per the Annunciator Response Procedures and SO23-3-2.1, CVCS Charging and Letdown Operations.

Once Letdown is restored, a feed flow transmitter will fail high on SG E089. The crew will regain control of feedwater flow per Annunciator Response Procedures and AOI SO23-13-24, Feedwater Malfunctions.

When the crew has stabilized feedwater flow, a Loss of Offsite Power will occur along with a mechanical failure of 2G002 and 2A06 Bus fault. The crew will perform SO23-12-1, Standard Post Trip Actions and during the SPTAs the ACO will take action associated with the mechanical failure of EDG 2G002. The crew will then transition to SO23-12-8, Station Blackout and attempt to restore offsite power.

Event termination will occur once an offsite line is restored and aligned to 1E Bus 2A04 with plant conditions stable.

Risk Significance:

Risk important components out of service: HPSI P-017, AFW P-141

Failure of risk important system prior to trip: Loss of CCW Pump

Risk significant core damage sequence: LOOP with loss of EDGs

Risk significant operator actions: Restore Non-Critical Loop Recover Offsite Power in 60 minutes Appendix D NUREG 1021 Revision 9

Scenario Event Description NRC Scenario 3 SONGS 2005 Facility NRC Initial License Examination Simulator Scenario Setup Scenario 3 MACHINE OPERATORS INSTRUCTIONS SETUP IC: Use IC #172 and see attached Event File for NRC Scenario #3.

STEPS TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER Appendix D NUREG 1021 Revision 9

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 4 of 22 Event

Description:

Boration and Downpower at 10%/hr Time Position Applicants Actions or Behavior Control Room Annunciators in Alarm at 30%:

57A58 - SI/ECW SYS TRAIN A INOPERABLE 56A30/40/50/60 - LOSS OF LOAD CHANNEL 1/2/3/4 TRIP DISABLED 53A20 - MFWP MINI FLOW VALVE OPEN 53B01 - CONDENSATE PUMP P053 AUTO START 53A49 - 5TH POINT HEATER LEVEL HI/LO 53A50 - 6TH POINT HEATER LEVEL HI/LO

+1 min CRS REFER to SO23-5-1.7, Section for Power Reduction.

CRS NOTIFY GCC of the power reduction.

NOTE: The crew may perform a manual calculation for amount of boron required or use the Plant Monitoring System and access the Reactor Coolant System Calculation page under MAIN MENU/USER FUNCTION. Either method is acceptable.

ENSURE SO23-5-1.7, Section 6.5, Preparations for Power CRS Descension has been completed.

MAINTAIN the guidelines of Section 6.6, Guidelines During CRS Power Descension.

CO DETERMINE boration/CEA position requirements.

CRS NOTIFY Chemistry Foreman of the planned power reduction.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 5 of 22 Event

Description:

Boration and Downpower at 10%/hr Time Position Applicants Actions or Behavior CONTACT Reactor Engineering for ASI control CRS recommendations.

CO INITIATE ASI monitoring.

CO COMMENCE forcing Pressurizer Spray flow:

PLACE both Spray Valve Controllers in AUTO.

PLACE PZR Proportional Heaters ON.

PLACE Backup Heaters in AUTO or ON as necessary to maintain desired Spray Valve position.

LOWER PIC-100, PZR pressure controller setpoint as required maintaining RCS pressure as directed by CRS.

REDUCE Main Turbine load as necessary to maintain Tcold on ACO program.

INITIATE boration in accordance with SO23-32.2, Makeup CO Operations.

DETERMINE the difference between the existing and the CO desired RCS boron concentration.

CO DETERMINE amount of boric acid to be added.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 6 of 22 Event

Description:

Boration and Downpower at 10%/hr Time Position Applicants Actions or Behavior COMMENCE periodically changing Boronometer setpoints to CO

(+50, -25 ppm) of existing boron concentration.

POSITION FIC-0210Y, BAMU Flow Controller, to AUTOMATIC CO and set to the required flowrate (~3.4 gpm).

SET FQIS-0210Y, BAMU to VCT T-077, Borate Batching CO Counter, to the required volume.

SELECT the BAMU Pump associated with the BAMU Tank CO used.

CO BORATE the Charging Pump suction:

VERIFY closed FV-9253, Blended Makeup to VCT isolation.

PLACE HV-9257, BAMU to Charging Pump Suction Block Valve, in AUTOMATIC.

CO SELECT HS-0210, Makeup Mode Selector, to BORATE.

+15 min CO/ACO MONITOR plant parameters.

When power has been reduced 3-5%, or at Lead Evaluators discretion, PROCEED to Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 7 of 22 Event

Description:

NI Channel B Upper Detector Failure Time Position Applicants Actions or Behavior Indications available:

56A03 - LOCAL POWER DENSITY HI CHANNEL TRIP 56A04 - DNBR LO CHANNEL TRIP 56A13 - LOCAL POWER DENSITY HI PRETRIP 56A14 - DNBR LO RPS PRETRIP 56B11 - LINEAR POWER DEVIATION CHANNEL 2 HI/LO 56B16 - PPS CHANNEL 2 TROUBLE 56C11 - CPC CHANNEL 2 SENSOR FAILURE Linear Power Range Channel B Recorder failing high (2JR0002B2)

+1 min CO REFER to Annunciator Response Procedures.

RECOGNIZE Power Range Channel failure and INFORM the CO CRS AOI SO23-13-18 entry required.

DIRECT performance of AOI SO23-13-18, Reactor Protection CRS System Failure/Loss of Vital Bus.

DETERMINE failure by observing instrumentation for the CO affected channel and alternate redundant indications monitoring the same parameter.

+3 min IDENTIFY Linear Power Channel B Upper Detector failure and CO REFER to SO23-3-2.13, CPC/CEAC Operation.

VERIFY that the same bistable is not in bypass on any other CO channel.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 8 of 22 Event

Description:

NI Channel B Upper Detector Failure Time Position Applicants Actions or Behavior CO VERIFY the Trip Channel Bypassed Annunciator alarms.

56A39 - PPS CHANNEL 2 TRIP BYPASSED LOG the bypass and the reason for the bypass in the Control CO Operators Log.

CRS INITIATE a LCOAR or follow guidelines of SO123-0-A5.

+10 min CRS EVALUATE Technical Specifications

LCO 3.3.1.A is applicable (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ACTION).

PLACE Channel in Bypass or Trip.

When Channel B trips have been placed in bypass, or at Lead Evaluators discretion, PROCEED to Event 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 9 of 22 Event

Description:

Degraded Grid Voltage to Sustained Degraded Voltage Setpoint Time Position Applicants Actions or Behavior Indications available:

63B01 - UNIT 2 DIGITAL FAULT RECORDER INITIATED 63B05 - 2A04 VOLTAGE LO 63C05 - 2A06 VOLTAGE LO 63B51 - OFFSITE POWER TROUBLE (on low frequency)

ACO REFER to Annunciator Response Procedures.

RECOGNIZE low grid voltage and frequency and INFORM the ACO CRS AOI SO23-13-4 entry required.

+1.5 min DIRECT performance of SO23-13-4, Operation During Major CRS System Disturbances.

NOTE: Grid voltage will initially drop to <218 kV to activate the Sustained Degraded Voltage Signal (SDVS) then return to ~228 kV.

ACO DETERMINE System Voltage is 218 kV.

CRITICAL Restore flow to the Component Cooling Water Non-Critical TASK ACO Loop (RCPs operating).

When SDVS initiates, START CCW Pump P-025 and VERIFY SWC Pump P-112 starts.

ACO VERIFY Generator AVR is in AUTO.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 10 of 22 Event

Description:

Degraded Grid Voltage to Sustained Degraded Voltage Setpoint Time Position Applicants Actions or Behavior

+4 min RAISE Exciter output to maintain rated Generator terminal ACO voltage.

M.O. Cue: If contacted as Grid Control Center (GCC), DIRECT SONGS to maintain 200 MVARs on the Unit 2 Main Generator.

MAXIMIZE Generator MVARs for the current power level to ACO assist in raising voltage:

JI-2990, Generator Megavars < 500 MVARs.

II-2916, Field Current < 4680 Amps.

EI-2917, Field Volts < 550 Volts.

+15 min CRS EVALUATE Technical Specifications.

LCO 3.8.1.C is applicable (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ACTION).

Both off-site lines are inoperable per SO23-3-3.23, Attachment 7, AC Sources Verification due to the EDGs powering the Vital 4 kV Buses.

Restore one required off-site circuit to OPERABLE status.

When Technical Specifications are addressed, or at Lead Evaluators discretion, PROCEED to Event 4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 11 of 22 Event

Description:

Letdown Pressure Instrument Fails Low Time Position Applicants Actions or Behavior Indications available:

58A21 - LETDOWN BACKPRESSURE HI/LO 61B11 - RELIEF VALVE LEAKING

+10 sec CO REFER to Annunciator Response Procedures.

RECOGNIZE pressure instrument failure and INFORM the CO CRS.

CRS DIRECT isolation of Letdown.

CO ISOLATES Letdown by closing 2TV-0221 or 2HV-9294.

CO VERIFY Letdown Flow isolated at 2FT-0202.

If only one Back Pressure Control Valve is in service, PLACE the Standby Back Pressure Control Valve per SO23-3-2.1, CRS/CO Attachment for Shifting Flow and Back Pressure Control Valves.

Floor CUE: DO NOT wait for restoration of Letdown to proceed to the next event.

When Letdown is isolated, or at Lead Evaluators discretion, PROCEED to Event 5.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 12 of 22 Event

Description:

Feed Flow Transmitter Failure Time Position Applicants Actions or Behavior Indications available:

53B23 - CONDENSATE FLOW BALANCE TROUBLE 52A06 - SG1 E089 LEVEL HI/LO Feedwater Regulating Valve position modulates closed Actual SG E089 level trending down

+1 min ACO REFER to Annunciator Response Procedures.

RECOGNIZE Feed Flow Transmitter failure and INFORM the ACO CRS AOI SO23-13-24 entry required.

DIRECT performance of SO23-13-24, Feedwater Control CRS System malfunction.

ACO DIRECT use of SO23-13-24, Attachment 1 for initial action.

ACO DETERMINE SG E089 level is lowering.

ACO DETERMINE Master Controller Output is NOT rising.

+5 min PLACE SG E-089 Master Controller in MANUAL and RAISE ACO output to stabilize SG level.

ACO REFER to flowchart to determine if other failures are present.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 13 of 22 Event

Description:

Feed Flow Transmitter Failure Time Position Applicants Actions or Behavior

+10 min Continue to MONITOR and ADJUST SG E089 Level Control as ACO necessary.

When SG E089 level is controlled, or at Lead Evaluators discretion, PROCEED to Events 6, 7, and 8.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 14 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE TU08, Turbine Trip, PG24 Loss of Offsite Power (+5 secs), ED03B, 2A06 Bus Fault (+1 min),

EG08A, 2G002 EDG Mechanical Failure (+2 min) and PG57, Loss of SDGE Switchyard (+5 min) trip.

Indications available:

99A24 - TURBINE TRIP RELAY TRIPPED Numerous Loss Of Offsite Power Related Alarms

+10 secs RECOGNIZE Reactor trip, Turbine trip, and Loss of Offsite CO/ACO Power and INFORM the CRS SO23-12-11 entry required.

DIRECT performance of SO23-12-1, Standard Post Trip CRS Actions.

CRS INITIATE Administrative Actions:

RECORD time of Reactor trip ____________.

ANNOUNCE Reactor trip via PA System.

INITIATE Attachment 4, WORKSHEET.

INITIATE Attachment 5, ADMINISTRATIVE ACTIONS.

CO VERIFY Reactivity Control criteria satisfied:

VERIFY Reactor Trip Circuit Breakers (8) - open.

VERIFY maximum of one full length CEA - NOT fully inserted.

VERIFY Reactor power - lowering AND Startup rate -

negative.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 15 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior ACO DETERMINE Vital Auxiliaries NOT functioning properly:

VERIFY Main Turbine tripped:

HP and LP Stop and Governor Valves - closed.

Mwe output - lowering.

VERIFY both Unit Output Breakers - open.

VERIFY Main Turbine speed - less than 2000 RPM and lowering.

DETERMINE CCW Pump NOT aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger.

DETERMINE both 1E 4 kV Buses de-energized.

DETERMINE loss of 2A04 due to loss of EDG 2G002.

DETERMINE loss of 2A06 due to bus fault.

DETERMINE both 1E 480 V Buses B04 and B06 de-energized.

DETERMINE all 6.9 kV and Non-1E Buses de-energized.

VERIFY all Class 1E DC Buses - energized.

M.O. Cue: If directed to investigate 2G002, WAIT 3 minutes and REPORT it is shutdown and there is a large amount of oil on the DG room floor.

If directed to investigate 2G003, WAIT 3 minutes and REPORT it is shutdown and that it appears to have tripped electrically.

CO VERIFY RCS Inventory Control criteria satisfied:

VERIFY PZR level between 10% and 70% and trending to between 30% and 60%.

VERIFY Core Exit Saturation Margin - greater than or equal to 20°F:

QSPDS page 611.

CFMS page 311.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 16 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior CO VERIFY RCS Pressure Control criteria satisfied:

VERIFY PZR pressure (WR and NR) between 1740 PSIA and 2380 PSIA and controlled AND trending to between 2025 PSIA and 2275 PSIA.

CO DETERMINE Core Heat Removal criteria is NOT satisfied:

DETERMINE no RCPs are operating.

RECORD time of all RCPs off.

VERIFY operating loop Delta T (Th-Tc) less than 58°F.

VERIFY Th and Tc not rising.

VERIFY operating loop Th and REP CET within 16°F.

QSPDS page 611.

CFMS page 311.

VERIFY Core Exit Saturation Margin 20°F.

QSPDS page 611.

CFMS page 311.

VERIFY Reactor Vessel level 100% (plenum).

QSPDS page 622.

CFMS page 312.

NOTE: It is acceptable for CO to report only Monitoring for Natural Circulation.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 17 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior ACO VERIFY RCS Heat Removal criteria satisfied:

VERIFY both SGs level - greater than 21% NR.

VERIFY both SGs level - less than 80% NR.

VERIFY the following:

Auxiliary feedwater available to restore both SGs level -

between 40% NR and 80% NR.

PREVENT SG high level:

CLOSE MFW Block Valves:

E-088 E-089 HV-4047 HV-4051

VERIFY heat removal adequate:

TC - less than 555°F.

SG pressures - approximately 1000 PSIA.

VERIFY TC - greater than 545°F or controlled.

VERIFY SG pressures - greater than 740 PSIA.

CO VERIFY Containment Isolation criteria satisfied:

VERIFY Containment pressure - less than 1.5 PSIG.

DETERMINE some Containment Area Radiation Monitors energized and NOT alarming or trending to alarm.

DETERMINE some Secondary Plant Radiation Monitors energized and NOT alarming or trending to alarm.

VERIFY Containment Temperature, Pressure and Combustible CO Gas Control criteria satisfied:

VERIFY Containment average temperature - less than 120°F.

VERIFY Containment pressure - less than 1.5 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 18 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior

+15 min CRS DIAGNOSE Event in Progress:

DETERMINE all safety function criteria are NOT met per Attachment 4, WORKSHEET.

COMPLETE Attachment 1, Recovery Diagnostic.

DIAGNOSE Station Blackout.

NOTIFY personnel of event in progress.

DESIGNATE SRO-in-charge.

DIRECT initiation of Steps 11 through 14.

CRS DIRECT performance of SO23-12-8, Station Blackout.

CRS VERIFY Station Blackout diagnosis:

INITIATE SO23-12-10, Safety Function Status Checks.

INITIATE Foldout Page.

DIRECT performance of FS-3, Monitor Natural Circulation.

DIRECT performance of SO23-12-11, Attachment 8, Restoration of Offsite Power.

DIRECT transfer of Q0612 to Emergency Source.

DIRECT performance of FS-18, Secondary Plant Protection.

EVALUATE 4 kV Bus cross tie per SO23-12-11, Attachment 24 (Cannot perform).

DIRECT performance of SO23-12-11, Attachment 6, Diesel Generator Failure Follow-up Actions.

DIRECT Chemistry to sample both SGs for radioactivity and boron.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 19 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior DIRECT initiation SO23-12-11, Attachment 8, Restoration of CRS Off-Site Power.

VERIFY Annunciators for Reserve Auxiliary Transformers ACO clear/reset.

ACO VERIFY any 220kV Section Bus de-energized.

ACO VERIFY System Separation alarm clear/reset.

ESTABLISH communication with SDG&E Grid Control Center ACO within 5 minutes.

ACO VERIFY SONGS Switchyard status.

VERIFY all four 220 kV Section Buses de-energized.

ACO ISOLATE 220kV Switchyard.

ENSURE all SCE controlled 220 kV CBs open OR switched out.

ACO DETERMINE both 1E 4 kV buses NOT energized.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 20 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior ACO ALIGN 1E 4 kV buses for restoration.

ENSURE 1E 4 kV Bus Tie Breaker AUTO/MANUAL transfer switches selected to MANUAL.

A04 - HS-1660B1

A06 - HS-1639B2 DISPATCH an operator to open TS-2 DC knife switches 127F1 ACO through 127F4 at DG Bus PT cubicle for Bus 2A04.

ALIGN all de-energized 6.9 kV buses on affected unit for ACO restoration.

ENSURE all 6.9 kV supply breakers and AUTO/MANUAL switches are aligned.

ALIGN all de-energized Non-1E 4 kV buses on affected unit for ACO restoration.

ENSURE all Non-1E 4 kV bus supply breakers and AUTO/MANUAL switches are aligned.

ENSURE breakers open to the following de-energized Non-1E ACO 4 kV loads.

Heater Drain Pumps

Main Condensate Pumps

Main Condenser Vacuum Pump

Turbine Plant Cooling Water Pumps

Main Circulating Water Pumps

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 21 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior When SO23-12-11, Attachment 8, Restoration of Off-Site CRS Power lineup is complete, REQUEST GCC energizes San Luis Rey Line.

VERIFY 220 kV Bus Section B energized from the San Luis ACO Rey Line.

ACO ENERGIZE Unit 3 Reserve Auxiliary Transformer.

ACO ENERGIZE adjacent 220 kV Section A.

ACO ENERGIZE Unit 2 Reserve Auxiliary Transformer.

ACO ENERGIZE CR63 220 kV metering.

ACO VERIFY 1E 4 kV bus status.

DETERMINE both 1E 4 kV buses NOT energized.

ACO ENSURE breakers open to the NOT OPERATING 4 kV loads.

Emergency Chillers

Containment Spray Pumps

HPSI Pumps

LPSI Pumps

AFW Pumps

CCW Pumps

SWC Pumps

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6, 7, and 8 Page 22 of 22 Event

Description:

Turbine Trip / Loss of Offsite Power / EDG Mechanical Failure / 2A06 Bus Fault Time Position Applicants Actions or Behavior CRITICAL Energize at least one vital electrical AC bus and associated 480 TASK ACO V 1E bus.

+30 min ENERGIZE Bus 2A04 from the Reserve Auxiliary Transformer.

DISPATCH an operator to close TS-2 DC knife switches 127F1 ACO through 127F4 at DG Bus PT cubicle for Bus 2A04.

ACO ENSURE associated 480 V 1E Bus 2B04 is energized.

When power is restored to Bus 2A04, TERMINATE the scenario.

ML060830508

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