ML052710205

09-2005-FINAL-Operating Exam

ML052710205
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/15/2005
From:	Gody A Operations Branch IV
To:	Forbes J Entergy Operations
References
50-313/05-301, ES-301-1 50-313/05-301
Download: ML052710205 (285)

Text

-- ES-301 Administrative Topics Outline Form ES-301-1 ES-301, Page 22 of 27 - Facility:

ANO-1 Date of Examination:

9-12-05 Examination Level (circle one):

Operating Test Number: 1 Administrative Topic (see note) Conduct of Operations Ability to use plant computer to obtain and evaluate AIJPM-RO-PMSI Rev. 2 Conduct of Operations AIJPM-RO-RBAL3 Rev. 1 Equipment Control Type code* 2.2.26 (Imp 2.5) Radiation Control 2.3.1 1 (Imp 2.7) Emergency Plan Describe activity to be performed NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room (D)irect from bank (5 3 for ROs; 5 4 for SROs) (N)ew or (M)odified from bank (2 1 (Pfrevious (2 1; randomly selected) (S)imulator DIPIS AIJPM-RO-REFULI Rev. 0 Ability to control radiation releases.

A1 JPM-RO-RADI Rev. 2 ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-PMSI Page 1 of 4 UNIT: 1 REV # 2 DATE: TUOI NUMBER: A1 JPM-RO-PMSI SYSTEMIDUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONS TASK: OPERATE THE PLANT COMPUTER JTA#: ANOI-RO-PMS-NORM-4 KA VALUE RO: 3.0 SRO: 3.0 I<A

REFERENCE:

2.1 .I 9 APPROVED FOR ADMINISTRATION TO:

RO: X SRO: TASK LOCATION: INSIDE CR:X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE): PLANT SITE:

SIMULATOR:

PERFORM LAB: POSITION EVALUATED:

RO: SRO: ACTUAL TESTING ENVIRONMENT:

SIMULATOR:

X PLANT SITE:

LAB: TESTING METHOD: SIMULATE: PERFORM: X APPROXIMATE COMPLETION TIME IN MINUTES: 10 MINUTES REFERENCE(S):

1105.010.

Cha. 01 1-00-0 EXAMINEE'S NAME: SSN ---- EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THlS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THlS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-PMSI Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is at 100% power operations. The Makeup Tank level is at 60 inches. RCS boron concentration is 1000 ppm. BAAT boron concentration is 12,000 ppm. TASK STANDARD:

The examinee uses the plant computer "BORON" proqram to calculate a total addition to the Makeup Tank of aporoximatelv 600 to 630 qallons consistina of 50 to 52.5 oallons boric acid and 550 to 577.5 oallons of Dl water. TASK PERFORMANCE AIDS: 1105.010.

Plant Monitorina Svstem NOTE: 1105.010 provides instructions for the Plant Monitoring System but the exact manipulations of this task are within the "skill of the craft." Therefore, procedure in hand is not required.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-PMSI Page 3 of 4 INITIATING CUE: The CRS directs you to use the plant computer to calculate a "No Concentration Change" to raise the Makeup Tank level to -80 inches. CRITICAL ELEMENTS (C) 2. 3. 4. 5 1. Select NASP on PMS screen or keyboard.

1 (c) I PERFORMANCE CHECKLIST Selected NASP on PMS. 1 (C) / 2 Select BORON program.

1 Selected BORON program on PMS 1 1 I STANDARD 3. Select option No. 5, No Concentration Change.

Typed "5" and pressed ENTER key on PMS keyboard.

NIA 4. Select option 0, boric acid and Dl water addition.

Typed "0" and pressed ENTER key on PMS keyboard.

SAT 5. Enter values requested by BORON program. UNSA T Examinee entered the following values: Makeup volume required (gallons)

= 600 to 630 (trainee should calculate the value needed using 20 inches x 30.86 gallonslin.) Makeup boron concentration required (ppm) = 1000 Available feed solution Boron concentration (ppm) = 12,000 The PMS displayed the following values after entry of final value: Feed volume Dl HZ0 - 550 to 577.5 gallons Feed volume boric acid - 50 to 52.5 gallons END ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-PMSI EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100% power operations.

The Makeup Tank level is at 60 inches. . RCS boron concentration

= 1000 ppm BAAT boron concentration

= 12,000 ppm INITIATING CUE: Page 4 of 4 The CRS directs you to use the plant computer to calculate a "No Concentration Change" to raise the Makeup Tank level to -80 inches.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RBAL3 Page 1 of 5 UNIT: 1 REV # 1 DATE: TUOI NUMBER: A1 JPM-RO-RBAL3 SYSTEMIDUTY AREA: ADMINISTRATIVE TOPIC -CONDUCT OF OPERATIONS TASK: ESTIMATE BORON CONCENTRATION REQUIRED TO MAINTAIN SHUTDOWN MARGIN DURING HEATUP USING RHOBAL PROGRAM JTA#: ANOI-RO-OPROC-NORM-70 KA VALUE RO: 3.9 SRO: 4.0 KA

REFERENCE:

2.1.23 APPROVED FOR ADMINISTRATION TO: RO: x SRO: X TASK LOCATION:

INSIDE CR:X OUTSIDE CR:

BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: PERFORM LAB:

POSITION EVALUATED:

RO: SRO: ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S):

N/A EXAMINEE'S NAME: SSN ---- EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THlS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THlS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RBAL3 Page 2 of 5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: The olant is oreparina for startup after a reactor trip. The plant had ooerated continuouslv at 100% oower since the refuelina outaae EFPD = 0. RCS Tave = 185°F. Desired final RCS Tave = 534" Heatup is scheduled to commence later today. TASK STANDARD:

The examinee has calculated the reauired Boron concentration to maintain shutdown mamin durina heatuo usina RHOBAL and determined the value to be 1570 to 1578 oom. TASK PERFORMANCE AIDS: Personal comouter with RHOBAL oroaram available.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-REAL3 Page 3 of 5 INITIATING CUE: The Control Room Supervisor directs you to calculate Boron concentration required to maintain shutdown margin during heatup to 534°F using the RHOBAL program.

CRITICAL ELEMENTS (C) 1,2.5 1. Activate "Shutdown Margin" on pull down menu. 2. Run program to determine Boron concentration required to maintain shutdown margin. Clicked (or Alt S via keyboard) on Shutdown Margin" in menu bar. Performed the following actions: Clicked on Worksheet 5, "Boron Concentration Required to Maintain SDM during Cooldown or Heatup". . Entered 0 for "Cycle Burnup in EFPD". Entered 0 for all CRA positions, except 30.4 for APSRs. Entered 185 for "RCS Average Temperature in degrees F". Entered 534 for "Final Desired RCS Average Temperature in degrees F". I -- .- I I NOTE: Step 3 may be performed prior to step 1 via the "Poison" menu. -r---- I I I 1 3. Activate "Xenon and Samarium" I I menu. Clicked (or Alt P via keyboard) on "Xenon and Samarium" in menu bar. Performed the following actions: Entered 0% "Power Level" Entered today's date.

Entered 0 for "Burnup" Clicked on "Beginning of cycle concentrations".

Clicked on "INITIALIZE POISONS" button. . Close 'Xenon and Samarium" menu.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RBAL3 Page 4 of 5 (C) I PERFORMANCE CHECKLIST I STANDARD I N/A I SAT ( UNSAT I I I I 5. Determine required Boron concentration.

Noted the "required Boron conc from Table or Figure B6" to be 1574. Candidate may discuss different boron concentration requirements for the various temperature ranges during heatup. Accept 1570 to 1578 for final minimum boron concentration at 534°F. END ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RBAL3 EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:

The plant is preparing for startup after a refueling outage. The plant had operated continuously at 100% power prior to the refueling outage. EFPD= 0 . RCS Tave = 18YF Final RCS Tave = 534°F Heatup is scheduled to commence later today. INITIATING CUE: Page 5 of 5 The SMICRS directs you to calculate Boron concentration required to maintain shutdown margin during heatup to 534°F using the RHOBAL program.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-REFULI Page 1 of 4 UNIT: I REV # &.-.- DATE: TUOI NUMBER: A1 JPM-RO-REFULI SYSTEMIDUN AREA: ADMINISTRATIVE TOPIC - EQUIPMENT CONTROL TASK: Perform Attachment B of 1502.004, Refuelina Boron. Temaerature, Tritium. and Level Check JTA#: ANOl-RO-FUELH-NORM-25 KA VALUE RO: 2.5 SRO: 3.7 KA

REFERENCE:

2.2.26 APPROVED FOR ADMINISTRATION TO: RO: X SRO: TASK LOCATION:

INSIDE CR:- OUTSIDE CR: BOTH:

X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: PERFORM LAB: POSITION EVALUATED:

RO: SRO: ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:

LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S): 1502.004. Cha.

034-02-0 EXAMINEE'S NAME SSN ---- EVALUATOR'S NAME THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THlS JPM AND IS DETERMINED TO BE, SATISFACTORY:

UNSATISFACTORY: PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THlS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-REFULI Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

A refuelinq outaae is in oroaress.

Fuel handlina is in proaress.

TASK STANDARD: The examinee has correctlv identified that VEF-15 should be runnina and stated the reauirements of note 3 of At!. B. TASK PERFORMANCE AIDS: 1502.004 Att. B ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-REFULI Page 3 of 4 INITIATING CUE: The CRS asks you to review Att.

B of 1502.004, Control of Unit 1 Refueling, which has just been completed by a license candidate.

Determine if refueling requirements have been met. CRITICAL ELEMENTS (C) 2 I (c) 1 PERFORMANCE CHECKLIST - END NIA STANDARD 2. Identify errors.

1. Review the completed Att. B of 1502.004.

Examinee identified the following:

1. VEF-15 FAN ON box not checked. 2. NIA entered under RECORD FLOWRATE for VEF-15. 3. IAW Note 3 TRM 3.6.1Condition A should be entered. 4. IAW Note 3 fuel movement should cease OR the remaining steps in this standard should be taken: RB purge should be isolated.

a tritium sample of refueling canal water obtained.

Shiftly tritium sampling of RB atmosphere commenced.

SAT Examinee reviewed the attachment.

UNSA T ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-REFULI EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:

A refueling outage is in progress . Fuel handling is in progress.

INITIATING CUE: Page 4 of 4 The CRS asks you to review An. B of 2502.004, Control of Unit 1 Refueling, which has just been completed by a license candidate. Determine if refueling requirements have been met.

I I I I ATTACHMENT 9 ?age 1 of 3 REFUELING BORON, TEMPERATURE, TRITIUM, AND LEVEL CHECK PROCNVORK PLAN NO. 1502.004 BORON SAMPLE wcad#2.9ipn SBIFTLY RB ATMOSPHERE TRITIUM CHECK (3) IF RB Purge in operation, THEN N/A. PROCEDURUWORK PLAN TITLE COMTROL OF UNIT 1 REFUELING PAGE: 28 of 44 CHANGE! 034-0213 (Notes on riext pages) SHIFT TIME DAYS SAMPLE POINT A/ 6 RESULTS ATTACHMENT B Page 2 of 3 PROC.MIORK PLAN NO. 1502.004 Log date and time of system startup following last test in the Chronological Log. Log indicated F5 Purge flow rate after system startup and each time that major flow changes occur such as opening equipment hacch, etc. IF Systems are secured, THEN log date and time in Chronological Log, and log date and time of - subsequent startup. VEF-14 A/Y flowrate from SYING

3. VEF-15 from SPING

1. PROCUlURUWMlK PLAN TITLE: CONTROL OF UNIT 1 REFUELING During fuel handling, F5 purge shall be operable, and should be in operation.

RB purge is inoperable, TfiEN enter TRN 3.6.1 Condition A, and either cease fuel movement, or isolate the RB purge system, obtain 1 tritium sample of refueling calla1 water, and commence shiftly tritium sampling of F5 atmosphere.

The Fuel Hsndling Area Ventilation System (FHAVS) shall be operable and in operation during movement of irradiated fuel assemblies in the fuel handliiig area ITS 3.7.12). IF VEF-14A/B flow rate degrades to outside required band, THEN enter TS 3.7.12 Condition A, stop irradiated fuel movement, and reset dampers per Initial Conditions of Control of Fuel and Control Rod Movement in U-1 Spent Fuel Area 11502.0101.

Log completion of requirements for this date in Attachment C. IF sampling indicates that the concentration is dropping unexpectedly, is below the Refueling Boron Concentration, (from Reactivity Balance Calculation, 1103.015, Worksheet 5 or 6) THEN secure all fuel movement, and initiate boration to greater than the Refueiing Boron Concentration. Boration shall be from the BAAT to the suction of DH Pumps per 1104.006. Use available indication that is represeritative of RCS temperature.

Prefer installed TI-1404 and TI-14Cj. Note instrument used in header. Use available indication that is representative of lake temperature from one of the following locations.

Note instrument used in header. PAGE: 29 of 44 ctinrroe 034-02-0 Unit 1 plant computer (T3640, T3642, T3644 or T3616). Ensure associated waterbox is in-service Unit 2 plant computer (T1430, TI436 or T1442). Ensure associated SW pump is in-service.

ATTACHYENT B Page 3 of 3 (9) WZiE! SF-45 closed, obtain both SFP and Transfer Canai level. SF-45 open, obtain either SFP or Transfer Canal level and N/A the other iiri this case either reading will satisfy SR 3.9.6.1).

(10) SAR minimum level is based upon maintaining 23 feet over irradiated fuel assenhlies in the Spent Fuel Pool storage racks. PAGE: 30 of 44 CHANGE: 034-025 PROCMORK PLAN NO. 1502.004 (11) Daily determine if purge flow rate has varied by greater than 1300 cfm.

Compare logged values to values recorded in chronological log (ensure con~parison i.s made between similar conditions, i.e. VEF-15 and VSP-2 in operation equipment hatch open would not be comparable to same conditions with equipment hatch closed. IF values vary greater than 1300 cfm from recorded values, contact SYE to determine impact. PROCEDVRUW[)RK PLAN nN: CONTROL OF UNIT I REFUELING (12) IF Temporary Alteration 1104.ii28 Attachment B modifying Service Water Outlet of E-28C is ill serlrice, THEN SW pressure must be verified as meeting the requirexents of the Terporary Alteration.

This -- reading is required to verify limits of TRM Figure 3.7.3-1 are maintained.

Reference 1104.028 Attachment B to determine which indicator

(?P-3840/PI-3607/PI-3508) is required to be monitored.

It may be required to valve in "-3340 temporary pressure gauge to obtair, this reading. Obtain inclependent verification of gauge isolati.on if P?-3840 was valved in. Performed by V Reviewed by - Date Time SRO in Charge of Fuel Handling, CRS, or SM ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RADI Page I of 4 UNIT: 1 REV # 2 DATE: TUOI NUMBER: A1 JPM-RO-RADI SYSTEMIDUTY AREA: ADMINISTRATIVE TOPIC-RADIATION CONTROL TASK: ABILITY TO CONTROL RADIATION RELEASES.

JTA#: ANOI-WCO-CZ-NORM-11 KA VALUE RO:2,7 SRO: 3.2 KA

REFERENCE:

2.3.1 1 APPROVED FOR ADMINISTRATION TO: RO: X SRO: TASK LOCATION:

INSIDE CR: X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: PERFORM LAB:

POSITION EVALUATED:

RO: X SRO: NIA ACTUAL TESTING ENVIRONMENT:

SIMULATOR:

X PLANT SITE:

LAB: TESTING METHOD: SIMULATE:

X PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S):

1104.020.

Cha. 042-00-0.

P-47B Pump Differential Pressure versus Flow Rate oraoh EXAMINEE'S NAME: SSN EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THlS JPM AND IS DETERMINED TO BE:

SATISFACTORY:

UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS: Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RADI Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Plant is shutdown for a Refueling Outaae. Circulatina Water PU~D P-3A in service. ALL other Circ Water Purnos are OOS for maintenance.

Dischame flow to flume indicator (Fl-4642) is INOPERABLE and 00s. T-16B TWMT release is in proaress.

Maximum allowable flow rate for the release from Preliminarv Reoort is 90 apm. WCO reoorts CV-4642. CZ Discharae to Flume Flow Control Valve. is throttled ooen. WCO reports that P-476, Treated Waste Monitorina Pumo, parameters afler establishina flow throuah CV-4642: Suction Pressure = 10 osia. Discharae Pressure = 38 osia. TASK STANDARD: Candidate estimates release flow rate between 75 to 85 aom and is within the allowable flow rate soecified in the Preliminary Reoort.

TASK PERFORMANCE AIDS: 1104,020. Att.

"82. Offsite Dose Calculation Manual fODCM) and P-47B Pumtt Differential Pressure versus Flow Rate araoh.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RADI Page 3 of 4 INITIATING CUE: The CRS directs you to perform step 4.15.1 of 1104.020 Att. "82" Treated Waste Monitor Tank (TWMT) T-I68 Liquid Release Permit and report if the release flow rate is within the allowable limit. CRITICAL ELEMENTS (C): 2,4 1. Perform step 4.1 5.1 .A Fl-4642 inoperable actions.

2. Determine required actions for conducting release with Fl-4642 inoperable. Recognized actions for inoperable flow indicator contained in ODCM App. 1 Table 2.1-1. Utilized procedure to ensure compliance with ODCM App, 1 Table 2.1-1 Action 2. Determined release flow rate required to be estimated at least once every four hours utilizing oumo curves. --- /' ' Note Candidate should discuss options available to obtain pump curve data which may include any of the following:

1) Contacting System Engineer 2) Reference Pump Technical Manual. with copy of P-478 Pump Curve upon request. 3. Obtain pump curve data to estimate release flow rate.

I I I I I I Note: Pump Suction and Discharge pressure are give,? in Initial Task Conditions.

.. Candidate obtained pump curve data.

--- C I 1 5. Report that flow is within allowable

4. Determine pump flow rate based on pump differential pressure.

Candidate calculated pump differential pressure and estimates a flow rate of 70 to 80 gpm using pump curve. END - Candidate reported to CRS that flow is within allowable limit. --- - -

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-RO-RADI Page 4 of 4 JPM INITIAL TASK CONDITIONS:

Plant is shutdown for a Refueling Outage. Circulating Water Pump P-3A in service. ALL other Circ Water Pumps are 00s for maintenance. Discharge flow to flume indicator (Fl-4642) is INOPERABLE and 00s. T-16B TWMT release is in progress.

Maximum allowable flow rate for the release from Preliminary Report is 90 gpm. WCO reports CV-4642, CZ Discharge to Flume Flow Control Valve, is throttled open.

WCO reports that P-47B, Treated Waste Monitoring Pump, parameters after establishing flow through CV-4642: Suction Pressure

= 10 psig Discharge Pressure

= 38 psig INITIATING CUE: The CRS directs you to perform step 4.15.1 of 1104.020 Att. "B2 Treated Waste Monitor Tank (TWMT) T-16B Liquid Release Permit and report if the release flow rate is within the allowable limit.

Treated Waste Monitor Pump P-476 0 2'0 40 6'0 80 100 120 140 160 Flow - GPM (5 GPM increments)

ATTACHMENT B2 PROC.iWORK PLAN NO. 1 104.020 Page 1 of 9 TREATED WASTE MONITOR TANK (TWMT) T-16B LIQUID RELEASE PERMIT PROCEDUREWORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION PERMIT # 1-LR-2005-0100 (Assigned by Chemistry) 09/12/2005 Date PAGE: 97 Of 122 CHANGE: 042-00-0 INITIALS 1.0 REQUEST (Operations) 1.1 T-16B taken out of service and placed on recirc for sampling and release: SRP Date 09/12/2005 Time 0010 NOTE Tag contains information to remind personnel that tank is isolated for chemistry sample. 1.2 Verify Treated Waste Monitor T-16B Inlet (CZ-47B) is closed and tag is installed on handwheel chain operator. - 1.3 Initial T-168 level 92 %. Record local or - remote level indication. (Circle one) 1.4 - IF Liquid Radwaste Process Monitor (RI-4642) is available, THEN perform the following: - 1.4.1 Verify RI-4642 operable by performing one of the following:: A IF monitor count rate is 5 1000 cpm, - THEN perform the following: - 1. Verify no Liquid Release in progress using FI-4642. 2. Select "Check Source" on RI-4642 and verify that the monitor responds to check source with a count rate rise >lo0 cpm. B. IF monitor count rate

>lo00 cpm, - THEN verify that count rate is <4.2236 cpm. - 1.4.2 - IF RI-4642 is operable, THEN record Rad Monitor RI-4642 - background counts and continue.

1.0 E4 cprn SRP SRP SRP SRP 1.4.3 IF RI-4642 is inoperable, ?;riEN notify Chemistry and continue.

ATTACHMENT 82 Page 2 of 9 1.5 Record the following:

SRP PROC.MTORK PLAN NO. 1104.020 1.5.1 # of CW Pumps running 1 and CW pump Disch Press 1.1 psig - PROCEDURUWORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION 1.6 - IF adjustments are made to CW flow, THEN terminate release. - PAGE: 98 of 122 CHANGE: 042-00-0 1.7 Submitted to Chemistry for Analysis, Section 2.0. SRP Date 9/12/2005 Time 0120 Section 1.0 Performed By Steven R. Pullin 2.0 Analysis (Chemistry) 2.1 Tank T-16B sample obtained for release analysis.

JB Performed by John Brown 2.2 - IF required for weekly sample for oil and grease, - N/A THEN Tank T-16B sample obtained. Otherwise N/A. Performed by N/A 2.3 T-16B pH analysis performed by John Brown JB 2.4 - IF pH is not between 6.0 and 9.0, N/A THEN adjust per Sampling the Treated Waste Monitor Tanks - (T-16A/B) (1607.009). Otherwise N/A. 2.4.1 Tank T-16B post neutralization pH sample, N/A Obtained by N/A 2.4.2 T-16B post neutralization pH sample, N/A Analysis performed by N/A 2.4.3 T-16B post neutralization pH N/A 2.4.4 IF pH is not between 6.0 and 9.0, - N/A THEN re-perform adjustment and analysis sequence until pH is between 6.0 and 9.0. Otherwise N/A. 2.5 Gamma spectroscopy performed by John Brown 2.6 Gamma spectroscopy report reviewed by Jim Smith 2.7 Tritium analysis performed by John Brown ATTACHMENT B2 Page 3 of 9 PROCJWORK PLAN NO. 1104.020 2.8 - IF Liquid Radwaste Process Monitor (RI-4642) is inoperable N/A or unavailable as identified in "Request" or "Verification - of Pre-Release Requirements" sections of this permit, THEN the following ODCM App.

1, Table 2.1-1 requirements shall be met. Otherwise N/A. 2.8.1 An independent sample of the tank contents shall be obtained and analyzed.

PROCEDUREMJORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION Performed by N/A PAGE: 99 of 122 CHANGE: 042-00-0 2.8.2 Computer input data shall be independently verified correct.

Performed by N/A 2.9 Sample results indicate release of total tank contents will JB not violate AN0 radioactive effluent discharge limit. 2.10 Preliminary release report prepared by John Brown IF not radioactive THEN N/A. - 2.11 Preliminary release report and/or permit returned to Control Room. By John Brown Date 09/12/05 Time 0700 3.0 Verification of Pre-Release Requirements (Operations) 3.1 Verify CW flow/configuration recorded in initial release SRP submittal data is still valid. 3.2 Verify appropriate signatures on preliminary report. S RP 3.3 CRS/SM approval to proceed with release CRS/SM Ahel Leader 3.4 Provide copy of Setpoints section from Preliminary Report SRP to Control Room Operators. 3.5 Verify F560 in service by performing the following:

3.5.1 Verify open: SRP CZ-74 (LRW Disch Filter F-560 Inlet) CZ-77 (LRW Disch Filter F-560 Outlet)

SRP 3.5.2 Verify closed CZ-83 (LRW Disch Filter F-560 SRP Bypass!

ATTACHMENT 82 Pr PROC.MTORK PLAN NO. 1104.020 3.6 - IF Liquid Radwaste Process Monitor (RI-4642) is operable and available, - THEN verify proper operation of radiation monitor and - interlocks as follows. Otherwise N/A. 3.6.1 Check Liquid Radwaste Process Monitor (RI-4642) available by one of the following methods: PROCEDURWORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION - IF monitor count rate is 2 1000 cpm, THEN select CHECK SOURCE on RI-4642 and verify that the monitor responds to check source with a count rate rise

>I00 cpm. IF monitor count rate

>I000 cpm, - THEN verify that count rate is <4.2236. - 3.6.2 Verify the following valves closed:

FWMT Disch to CW Flumes (DZ-25) LZ Drain Pump P-45 Discharge to Flume (LZ-5) Treated Waste Discharge to Circ Water Flume (CZ-58) 3.6.3 Place CZ Disch to Flume Flow Control Valve (CV-4642) hand switch to OPEN. A. Verify FIC-4642 in Manual and fully open CV-4642 using the Manual Adjustment Knob. 3.6.4 Lower RI-4642 alarm setpoint until HIGH RAD alarm actuates.

3.6.5 Verify from CV-4642 indicating lights that CV-4642 trips closed. 3.6.6 Place CV-4642 HS to CLOSED position.

A. Turn Man. Adj.

Knob to fully Closed Position (fully counterclockwise).

3.6.7 Adjust RI-4642 setpoint to the value listed in the Preliminary Report for total Circ Water flow. 3.6.8 Verify a Licensed Operator, other than individual who initially set RI-4642 setpoint, has independently verified that RI-4642 setpoint is correct for total circ water flow.

3.6.9 Reset RI-4642 HIGH R4D alarm. 3.7 - IF RI-4642 is inoperable unavailable, THEN verify requirements specified in "Analysis" section of - this permit for RI-4642 inoperable 5 unavailable have been performed.

Otherwise N/A. Section 3.0 Performed By Steve Pullim PAGE: 100 Of 122 CHANGE: 042-006 ige 4 of 9 SRP SRP SRP SRP SRP SRP SRP SRP SRP SRP SRP SRP SRP ATTACHMENT B2 Page 5 of 9 PROCJWORK PLAN NO. 1104.020 4.0 Release (Operations)

CAUTION Unauthorized discharge to Lake Dardanelle via the flume shall be avoided. I PROCEDUREMTORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION 4.1 Verify CZ Disch to Flume Flow (CV-4642) closed. SRP PAGE: 101 Of I22 CHANGE: 042-00-0 4.2 Verify T-16B X-FER PP (P-47B) stopped. SRP NOTE - Tag contains information to remind personnel that tank is isolated for chemistry sample. 4.3 Verify Treated Waste Monitor Tank T-16B Inlet (CZ-47B) SRP closed tagged.

4.3.1 - IF tag is missing has been removed since tank was last sampled, THEN perform the following.

Otherwise N/A. A. Terminate this release.

B. Install tag on CZ-47B. C. Submit new release permit to Chemistry.

N/A 4.4 Verify Treated Waste Monitor Tank T-16B Outlet (CZ-48B) SRP open. 4.5 Verify Treated Waste Discharge Valve to Header from P-47A SRP (CZ-55A) closed. 4.6 Verify Treated Waste Monitor Tank T-168 Recirc Inlet SRP (CZ-54B) closed. 4.7 Open Treated Waste Discharge Valve to Header from P-478 SRP (CZ-558).

4.8 Open Treated Waste Discharge to Circ. Water Flume (CZ-58). S RP 4.9 Verify Treated Waste Monitor Pump Discharge to Clean Waste S RP Tanks (CZ-57) closed. 4.10 Verify Unit l/Unit 2 Liquid Radwaste Manifold Is01 (CZ-87) S RP closed. 4.11 Verify Suction Crossover on Treated Waste Monitor Pumps SRP (CZ-50) closed.

ATTACHMENT B2 Page 6 of 9 PROC.WORK PLAN NO. 11 04.020 4.12 IF Liquid Radwaste Process Monitor (RI-4642) is inoperable or unavailable, - THEN perform the following. Otherwise N/A (ODCM App.1, L2.1.l). 4.12.1 Verify FWMT Disch to CW Flumes (DZ-25) closed. N/A PROCEDUREWORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION 4.12.2 Verify LZ Drain Pump P-45 Discharge to Flume N/A (LZ-5) closed. PAGE: 102 of 122 CHANGE: 042-00-0 4.12.3 Person qualified as Waste Control Operator, N/A independently verify release path valve alignment prior to release (ODCM App.1, Table 2.1-1). SRP 4.13 Notify control room of intent to begin release. 4.14 Commence T-16B release as follows: 4.14.1 Start P-47B. SRP 4.14.2 Place CZ Disch to Flume Flow (CV-4642) hand SRP switch to OPEN. CAUTION Use of flow rate areater than allowable by the release permit may violate I - ODCM limlts for release and may be NRC reportable.

I NOTE - Allowable Release Flow Rate is Listed in the "Max Waste (GPM)" Column of the Preliminary Report.

4.14.3 Use CZ Disch to Flume (FIC-4642) to obtain flow rate < allowable release flow rate for total circ water flow. Max Flow Rate from Preliminary Report ( 90 gpm) 1. Note: FIC 4642 inoperable, cannot determine flow rate, procedure is deviated, release can continue as long as flow is estimated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ATTACHMENT B2 Page 7 of 9 PAGE: 103 of 122 CHANGE: 042000 . PROC.MIORK PLAN NO. 1104.020 4.15 WHEN release has started, perform the following:

2 PROCEDUREMIORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION 4.15.1 Control Room Personnel shall observe Discharge - Flow to Flume (FI-4642).

Verify release flow rate is 5 allowable release flow rate for total circ water flow. A. IF FI-4642 is inoperable, %EN estimate flow rate at least once every - four hours during release (ODCM App.1, Table 2.1-1). Otherwise N/A. NOTE - If a Plant Computer tabular Log (DUMP) is used instead of Process Radiation Monitoring Effluent Recorder (RR-48301, the tabular log shall contain at least points R4642, R3618 and be set at 5 5 minute intervals and cover the duration of the release. 4.15.2 Record the following data on RR-4830. IF RR-4830 not available, ZEN verify Plant Computer tabular log is - activated and record data on it. A. Release start time Date B. Release permit number C. Name and number of tank being released: "TWMT (T-16B) " 4.15.3 Notify RP that T-168 release has started and LRW disch filter F-560 should be periodically monitored for Rad levels.

4.15.4 Notify Chemistry that T-16B release has started.

ATTACHMENT B2 Page 8 of 9 WTIUN Pumping radioactive liquid tanks empty can cause sediment in bottom of tank to be deposited in discharge piping. This can produce higher radiation areas in the vicinity of the discharge piping than previously existed. ..' PAGE: 104 of 122 CHANGE: 042-00-0 r PROC.MM)RK PLAN NO. 1104.020 4.16 Verify by tank level observation that only T-16B is being released.

NOTE - Liquid Radwaste Disch Filter (F-560) inlet press should not exceed 25 psig. i PRDCEDUREMlORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION 4.16.1 Monitor F-560 during release for a rise in inlet pressure.

4.16.2 - IF LRW Disch Filter (F-560) inlet press on PI-4606 exceeds 25 psig, THEN perform the following: - A. Stop P-478. B. Place CZ Disch to Flume Flow (CV-4642) handswitch to Close. C. Perform "Backflushing the Liquid Radwaste Discharge Filter (F-560)" section of this procedure.

D. WHEN backflush is complete, THEN recommence release at step 4.14 of this Attachment.

4.17 WHEN release is complete, THEN perform the following. - 4.17.1 Verify P-47B is off and hand switch is "Green Flagged".

4.17.2 Verify discharge flow -zero gpm. 4.17.3 Notify RP that T-16B release is complete and that F-560 should be surveyed for Rad levels to determine the need to back flush F-560. 4.17.4 Back flush F-560 as necessary per RP survey. - 4.18 Notify control room that release is complete.

4.19 Record the following data on RR-4830.

IF RR-4830 was not available, - THEN record on Plant Computer tabular logsheets. - A. Release stop time Date B. Release permit number 4.20 Flush clean waste to discharge flume piping as follows: 4.20.1 Close Treated Waste Discharge Valve to Header from P-47B (CZ-550) PAGE: 105 of 122 CHANGE: 042-00-0 PROCNORK PLAN NO. 1104.020 4.20.2 Close CZ-58. ATTACHMENT B2 Page 9 of 9 PROCEDUREWORK PLAN TITLE: CLEAN WASTE SYSTEM OPERATION 4.20.3 Align demineralized water to discharge piping by opening Condensate Flush Disch Hdr (CS-256).

4.20.4 After flushing piping for - 5 minutes, Close CS-256. 4.21 Place CV-4642 hand switch to CLOSE and verify indicating lights show valve closed.

4.21.1 Verify FIC-4642 in manual and turn Man. Adj.

Knob to CLOSED position

[fully counterclockwise) 4.22 Record final T-16B level 6 4.23 Remove tag from Treated Waste Monitor T-16B Inlet (CZ-47B).

4.24 Return release permit with all attachments to CRS/SM. Performed by Date Approved by CRS/SM Date 4.25 Return the following to Chemistry:

This attachment Release permit Tabular logsheets, if used.

ES-301, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 Facility:

ANO-1 Date of Examination:

9-12-05 Examination Level (circle one): RO I@ Operating Test Number: 1 Administrative Topic (see note) Conduct of Operations 2.1.12 (Imp 4.0) Conduct of Operations 2.1.34 (lmp2.9) Equipment Control 2.2.11 (Imp 3.4) Radiation Control 2.3.10 (Imp 3.3) Emergency Plan 2.4.29 (Imp 4.0) NOTE: All items (5 total) are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (Cfontrol room (D)irect from bank (S 3 for ROs; S 4 for SROs) (N)ew or (M)odified from bank (2. I (P)revious (2 1; randomly selected) (S)imulator J Type code' NIS NIS NIS MIS NIS required for Describe activity to be performed Ability to apply technical specifications for a system. New adrnin JPM A1 JPM-SRO-TS1 Ability to maintain primary and secondary plant chemistry within allowable limits. New admin JPM AIJPM-SRO-CHEMI Knowledge of the process for controlling temporary changes. New admin JPM A1 JPM-SRO-TALT2 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

Modified A1 JPM-SRO-RC22 Knowledge of the emergency plan, New admin JPM AIJPM-SRO-EAL9.

SROs. RO applicants require only 4 items unless they are ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-TS1 Page I of 4 UNIT: 1 REV # -Q.,-- DATE: TUOI NUMBER: A1 JPM-SRO-TS1 SYSTEMIDUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONS TASK: Applv technical specifications for a system.

JTA#: ANO-SRO-ADMIN-NORM-22 KA VALUE RO: 2.9 SRO: 4.0 KA

REFERENCE:

2.1.12 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR:

PERFORM LAB: POSITION EVALUATED:

RO: NlA SRO: X ACTUAL TESTING ENVIRONMENT: SIMULATOR: X PLANT SITE: LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 30 MINUTES REFERENCE(S): Unit One Technical Specifications:

1104.036 EXAMINEE'S NAME:

SSN ---- EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THlS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THlS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" poition of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant had been operatina at 100% for 100 davs. DH ourno P-34A is taaaed out to replace a leakinq seal. The monthly surveillance for DG2 has beaun to ensure it is completed within the requirements of the surveillance schedule.

TASK STANDARD, Examinee correctly recoqnizes that Tech Spec LC0 SR 3.8.1 .I . 3.8.1 condition B is applicable.

LC0 3.8.1 condition 8.2 declare the DH pump P-34B inoperable due to inoperable ememencv power supply. LC0 3.5.2 condition C applicable due to both DH pumps inoperable.

3.5.2 condition C is also applicable, and LC0 3.0.3 must be entered. TASK PERFORMANCE AIDS: 11 04.036: Technical Specifications ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-TS1 Page 3 of 4 INITIATING CUE: The CBOT has just performed, Supplement 2, DG2 Monthly Test, of 1104.036 through step 2.9.4, he discontinued the test per step 2.9.5, and has given you, the CRS, the supplement for review.

CRITICAL ELEMENTS (C) 4 I I Review supplement.

1 Reviewed supplement (c) 2. Perform step 3.2.

Performed the following:

Immediately notified Shifl Manager. Declared DG2 inoperable.

Verified a Condition Report initiated.

Initiated corrective action.

I I PERFORMANCE CHECKLIST 3. Per step 3.2, reference Tech Specs. Referenced Tech Specs STANDARD 4. Determine applicable Tech Specs and required actions. Determined the following: SR 3.8.1.1 LC0 3.8.1 condition B applicable due to inoperable DG2. . LC0 3.8.1 condition 8.2. declare the DH pump P-348 inoperable due to inoperable emergency power supply.

LC0 3.5.2 condition C applicable due to both DH pumps inoperable, LC0 3.0.3 would be entered.

END ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-TS1 Page 4 of 4 EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS: The plant had been operating at 100% for 100 days. DH pump P-34A is tagged out to replace a leaking seal. The monthly surveillance for DG2 has begun to ensure it is completed within the requirements of the surveillance schedule.

INITIATING CUE: The CBOT has just performed, Supplement 2, DG2 Monthly Test, of 1104.036 through step 2.9.4, he discontinued the test per step 2.9.5, and has given you, the CRS, the supplement for review.

r ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE EMERGENCY DIESEL GENERATOR OPERATION SET # When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionl~nterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiWLast Shift Peer Pressure Procedures ChangeiW Normal Job Eriefing DOCUMENT NO 1104.056 WORK PLAN EXP DATE NIA SAFETY-RELATED BYES RNO TEMP ALT RYES @NO CHANGE NO 042-03-0 TC U(P DATE NIA IPTE BYES mN0 SUPPLEMENT 2 Page 1 of 30 PROC.IWORK PLAN NO. 1104.036 DG2 MONTHLY TEST This test demonstrates operability of DG2 and the AC, DC, and shaft-driven lube oil system; air start system; fuel oil transfer system; engine cooling system and ventilation system and satisfies SR 3.8.1.2, SR 3.8.1.3, SR 3.8.1.4, SR 3.8.1.6, SR 3.8.3.3, TR 3.8.3.1, and TS 5.5.8 (AN0 IST program requirements). Reg Guide 1.97 Instrumentation channel check6 of DG instrumentation are performed in this Supplement. Instructions are provided for pre- and post-operation checks. Data is recorded to assist in tracking performance trends of the diesel and generator.

PROCEDUREIWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION

,. NOTE - Inoperable safety-feature valves may be locked in their actuated position to maintain overall operability.

PAGE: 104 Of 214 CHANGE: 042-035 DG start location alternates with each performance of a regularly scheduled test. I 1.0 INITIAL CONDITIONS INITIALS 1.1 Ci- ck the purpose of this test: . Regularly scheduled monthly test - (local, remote start) circle one - 8. Regularly scheduled quarterly test (includes P-169/DG vibration data). (!.ocal, remote start) circle one - C. Operability test foliowing significant maintenance (describe maintenance performed in section 4.0). - D. Two hour loaded run following a series of Supplement 12 Operability tests. .- E. Other (describe in section 4.0). 1.2 Service water loop II in service 1.3 - IF this rest is returning DG2 to operable condition, EN verify DG2 aligned for emergency standby per Attachment D. 1.4 A stopwatch shall be used to clock DG to verify unit is available to carry load within 15 seconds. M&TE No. bEl, 07g- cal Due Date -- il-C?-PS 1.4.1 Record stopwatch M&TE number in section 3.0.

SUPPLEMENT 2 Page 2 of 30 PROC.MTORK PLAN NO. 11 04.036 1.5 Contact Dispatcher with the following information exchange:

Notify Dispatcher that DG surveillance will be conducted.

PROCEOUREMTORK PUN TITLE: EMERGENCY DIESEL GENERATOR OPERATION . Verify no off-site grid disturbance is expected, such as a severe electrical storm in the area. PAGE: 105 of 214 CHANGE: 042-03-0 Request dispatcher notify AN0 Unit 1 if any disturbances develop. 1.6 IF this is a regularly scheduled monthly or quarterly test, /P/ notify Chemistry to prepare to sample fuel oil, lube oil, and cooling water. 1.7 Obtain cylinder drain cock tool, engine jacking mechanism, y;.r - and hearing protection.

1.8 Review the following limits and precautions:

&c!I.c. Diesel rJn time unloaded or at low load (<75%3 should be minimized in order to prevent carbon fouling (improper combustion) and excessive turbocharger gear train wear. Do not attempt diesel generator restarts until engine has stopped I0 RPM) . Governor booster pump tubing should be inspected for leaks during diesel run to prevent loss of governor control oil pressure. During periods of known off-site electrical grid disturbances, neither diesel should we paralleled with the grid. Do not tie both EDGs to the grid simultaneously when both EDGe are in operation.

One DG shall be dedicated only to its ES bus. Otherwise a single grid electrical fault may cause a loss of both emergency diesel generators. . A delay in opening output breaker at 100 KW when unloading a diesel may result in a motoring trip A delay in loading a diesel after closing the output breaker may result in a motoring trip. Actions such as resetting, changing control switch positions, reconfiguring components, or attempting diesel restart after failure can cause loss of data useful in diagnosing problems and should be avoided if not an emergency.

SUPPLEMrnT 2 Page 3 of 30 PROC-MYORK PLAN NO. 1104.036 Adjusting either Unit 1 or Unit 2 Main Generator reactive loading may result in significant changes in EDG reactive loading while the diesel generator is paralleled to the grid. Maximum ambient temp for diesel operation is 122°F. Verify ventilation fans operate to maintain ambient temp < maximum allowed.

PROCEDUREIWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION r Maximum engine outlet water temperature is 205°F. PAGE: 106 of 214 CHANGE: 042-03-0 Minimum oil pressure is 26 psig when diesel is operating at 900 RPM. 1.9 Verify SERV WTR to 002 CLRS (CV-3807!

is closed. 2.L 1.10 Portable vibrometer available. - 4r' 2.0 TEST METHOD 2.1 - IF during the performance of this supplement it is desired - to monitor DG2 crankcase pressure, THEN perform the following:

.- 2.1.1 Open K-48 Crankcase Pressure PI-52448 Isolation (FO-5244B). 2.1.2 Monitor PI-5244B 2.1.3 Close F0-52448 2.2 - IF during the performance of this supplement it is desired - to nonitor m2 air box pressure, THEN perform the following:

2.2.1 Open K-4B Air Box Pressure PI-52458 Isolatio31 (FO-5245B1. 2.2.2 Monitor PI-52458 2.2.3 Close FO-5245B SUPPLEMENT 2 Page 4 of 30 . PR0C.NVORK PLAN NO. 11 04.036 2.3 Lubrication System Testing 2.3.1 Check engine lube oil level between '/, and 1" above dipstick full mark with engine stopped. ..&L PROCEDUREMTORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION A. g oil level. is low, THEM submit WR/WO for oil addition. .Mi%. - PAGE: 107 Of 214 CHANGE: 042-03-0 8. IF oil level is below LOW mark, - M% do run diesel untii oil is added. 1) Stop the test AND notify the Shift Manager. 2.3.2 Verify DG2 AC Lube Oil Soak Back Pump (P-10683) 4rg running. A. Record lube oil pressure at DGZ r*t - Turbocharger BRG Oil PRESS (11-5271) on OG2 engine control panel ClO8. 2 6 psis 2.3.3 Turn DG2 AC Lube Oil Soak Back Pump (P-10683) - fnt hand switch to OPF. A. Check 062 DC Lube Oil Soak Back Pump JP-106B1) starts. B. Acknowledge SOAK BACK PP (P-106B3)

OPF (K1613 on C567) annunciator.

C. Record lube oil pressure to turbo bearings - Adb at PI-5271. '4" Z 2.3.4 Place P-106B3 hand switch to ON. A. Check P-106B3 starts. B. Check P-10681 stops. C. Record lube oil pressure to turbo bearings - -"M at PI-5271. &b psig SUPPLEMENT 2 Page 5 of 30 PROC.MIORK PLAN NO. 11 04.036 2.3.5 Verify nG2 AC Lube Oil Soak Back hlmp (P-10682) dx.- running. I NOTE Pump discharge pressure must be 730 psig to circulate oil through 30# spring loaded check valve. DGZ AC Lube Oil Soak Back PumD P-10602 Disch CK PROCERUROWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION A. Record discharge pressure at DG2 AC labe - '@ Oil Soak Back Pump P-10692 DISCH PRESS PAGE: 108 of 214 CHANGE: 042-031) B. IF P-10682 discharge pressure is c30 psig, %EN stop test and notify Shift Manager. 23- - 2.3.6 Clear Soak Rack Pump alarms. SL NOTE - Technical Specification SR 3.8.3.3 requires verifying each DC air start receiver pressure is 2 175 psig on a 31 day frequency.

This surveillance requirement ensures that without the aid of the starting air compressor, sufficient air start capacity for DG is available.

The required receiver consists of one bank of two tanks, The following step checks both banks, although only one bank is required. 2.4 Air Start Receiver Test 2.4.1 'Jerify the DGZ Starting Air Corrpressor Receiver li.8' - pressure is s 175 psig per the following pressure indicators: (circle inszruinents used here and in Section 3.0)

SUPPLEMENT 2 Page 6 of 30 PROC.MIORK PIAN NO. 1104.036 NOTE - Governor oil level is intended to be maintained between the high and low marks when che EDG is in operation.

Governor should operate normally with high oil level. Governor oil level will rise when the EDC is shutdown.

2.5 Control oil Check PROCEDUREWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION 2.5.1 Check governor oil level sightglass - 1/2 full PAQE: 709 of 214 CHANGE: 042-03-0 A. P low, submit WR/WO for oil addition

0. gempty, THEN do NOT run diesel until oil is added. C. IF governor oil level is above the - - sightglass, THEN submit WR/WO for oil removal. 2.6 Cooling Water Check 2.6.1 Check OG2 Cooling Water Expansion Tank (T-78Bl water level within band for engine stopped. A. 2 below lower limit, THEN add DI water uxtil -I/, band is reached - in the "Engine Stopped" band. 2.7 Verify no compression cylinder inleakage as follows: 2.7.1 IF any of the following conditions exist, N/A steps 2.7.2 through 2.7.11. Otherwise N/A this step and GO TO step 2.7.2. A. iX1 inoperable In,

• B. Any Tech Spec required odd train ES component inoperable SUPPLEMENT 2 Page 7 of 30 PROC.NVORK PLAPl NO. 1104.036 CAUTION Placing engine control selector switch in MAINT will prevent diesel start, rendering DG2 inoperable.

I NOTE - If DG2 becomes inoperable for ?1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, then the following should be performed:

PROCEDURElWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION . E55/56 should be aligned to load center associated with operable diesel. . OP and STBY HPI pumps shou1.d be aligned to the operable EDG. PAGE: 1100f 214 CHANGE: 042-03-0 2.7.2 Perform the following:

A. IP i(CS above Mode 5, - s~f' THEN enter TS 3.8.1 Condition B. - Time 0933 Date 3-tz.G~ NOTE - Ucit 2 requires 30th VSF-9 and 2VSF-9 to maintain auto-start capability in Modes 1-4, which also requires operability of both normal and emergency power supplies.

Thus if VSF-9 is powered from AND1 and B55/56 are aligned to an inoperable EX, AN02 must declare VSF-9 inoperable.

B. Notify Unit 2 that DG2 is inoperable.

in/ 1. B55/B56 are aligned to 86, THEN inform Unit 2 that VSF-9 is % - inoperable for Unit

2. C. DGZ inoperability will exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, perform the following:

Complete 1107.001, Sup 10, Verification - of Two Offsite Circuit Power Sources

• If desired, align B55/56 to load center associated with operable EDG If desired, align OP and STBY HPI pumps - to bus associated with operable EDG SUPPLEMENT 2 Page 8 of 30 PROC.MORK PLAN NO. 1104.036 2.7.3 Place Engine Control selector switch an Cl08 in S Per. - MAINT. A. Xecord time HS placed in MAINT. XbJ - 0%~ PROCEDUREMORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION B. IF power is iost to bus A4 during performance of this section of the urocedure . PAGE: 11% of 214 CHANGE: 04253-0 THEN - perfbrm the following:

1. Verify MCC B55 and 856 powered from bus B5. 2. Remove engine jacking mechanism

3. Close a11 cylinder drain cocks snug1.y using the cylinder drain cock tool. 4. Return Engine Control selector switch to REMOTE. 2.7.4 Open all cylinder drain cocks

-3 tunis. & CAUTION Water or oil exiting ports prior to engine rollover indicates gross water jacket or fuel system failure. I 2.7.5 Observe cylinder drain cock ports for water or oil. 2.7.6 - IF drainage is observed, THEN perform the following: - A. Do NOT roll over diesel as engine damage WILL occur. A 1 B. Mark affected cylinderls) on vibration reading data sheet diesel illustration.

4- 1. Record type of Liquid in section 4.0. -I- C. Discontinue this test AND notify Shift Manager that 002 is inoperable.

SUPPLEMENT 2 Page 9 of 30 PROC.hVORK PLAN MO. 1104.036 2.7.7 Roll over diesel by installing engine jacking mechanism and manually jacking engine over at fAr least one full turn. 2.7.8 Remove engine jacking mechanism. - Jq . PROCEDUREWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION 2.7.9 Observe cylinder drain cock ports for water or - -."#I oil. > PAGE: 112 of 214 CHANGE: 042-03-0 2.7.10 IF drainage is observed, %EN perform the following: - A. Mark affected cylinder(s) on vibration reading data sheet diesel illustration.

&@-- 1. Record type of liquid in seccion 4.0. B. Discontinue this teat AND notify Shift - b Manager that E2 is inoperable.

2.7.11 Close all cyf inder drain cocks snugly using the /"\P cylinder drain cocR tool.

SUPPLEMENT 2 Page 10 of 30 PROC.iWORK PLAN NO. 1104.036 2.8 Verification of r,ocaI Start Capability 2.8.1 Record DG2 Engine Total HRS (C1OB) : *bdZ.$ hrs. - jB( NOTE - If other than regularly scheduled test, start location is optional.

k PROCEUURUWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION 2.8.2 From "Initial Conditions" section of this supplement, note which starting station is to be used for this test, local or remote. PAGE: 1130f214 CHANGE: 042-034 A. IF remote, /*/ - THEN place Engine Control Selector switch on C108 in RBMOTE. 8. I[F Local, TKEN place Engine Control Selector switch rvqA on ClO8 in LOCAL. C. Record time HS removed from MAINT. '~6 - o?JI NOTE Placing Engine Control Selector switch in LOCAL restores autostart capability and operability.

D. IF applicable, a ZEN exit all TS Conditions entered for perfoririance of this test. Time 0'tfL Date 4 -I%-*? E. Notify Unit 2 that M2 is operable.

Otherwise N/A, if proving operability after maintenance.

2.8.3 IF LOCAL is selected, - THEN continue with step 2.8.4 - 2.8.4 IF REMOTE is selected, f nf - ZEN W TO step 2.9 and N/A steps 2.8.5 through - 2.8.15. 2.8.5 Station operators to observe starter rnotor(si - Ma used for diesel start to determine which starter functioned AND verify presence of oil in starter exhaust.

SUPPLEMENT 2 Page 11 of 30 PROC.MIORK PLAN NO. 1104.036 NOTE Be prepared to clock elapsed time from start signal until voltage exceeds i750 volts. 2.8.6 Perform local start of diesel aa follows: I PROCEDUREMIORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION A. Start, or verify started, Diesel Generator Room Exhaust Fans AND verify dampers open on C19 or locally. 1. Verify VEF-24C running. - PIA 2. Check Damper TV-7902A open. 3. Verify VEF-24D running. 4. Check Damper TV-7902B open. E PAGE: 114 Of 214 CHANGE: 042434 5. Record verification in section 3.0 I B. Verify volts selector switch for DG2 AC Voltage meter Lon E211 NOT in OFF. --I- C. Simultaneously depress START pushbutton on ClOB AND star; the stopwatch.

+ D. m2 voltage exceeds 3750 volts, THEN stop the watch. - 2.8.7 Record the following in section 3.0: A. Time elapsed from operation of start switch until voltage exceeded 3750 volts. B. stroking of starter bank used: (Check one) SV-5237, CV-5237 and FO-164(north bankl-we-, OI' SV-5239, CV-5239 and FO-163 (south bank)- 2.8.8 Record Time/Date of DG2 start. 9..

SUPPLEMENT 2 Page 12 of 30 PROC.IWORK PLAN NO. 1104.036 2.8.9 Check presence of oil in exhaust of starter used. kYL. A. no indication of oil, THEN submit WR/WO to refill oiler and - continue surveillance.

t PROCEDUREWORK PUW TITLE: EMERGENCY DIESEL GENERATOR OPERATION 2.8.10 Open DG2 Air Box Trap ST-68 Bypass (FO-1066Di AND check for water in effluent.

PAGE: 1150f214 CRANGe: 042-03-0 A. Close PO-1066D.

+ 5. IF there is water in effluent, THEN submit WRIWO and continue surveillance.

2.8.11 Stop diesel (pushbutton on C1OB) 2.8.12 Record TimelDate of DC2 stop. 2.8.13 - IF time to exceed 3750 volts is greater than 15 seconds, THEN perform the following. A. Inform the Shift Manager. -+ B. Declare DG2 inoperable.

I C. Discontinue the test. 4- 2.8.14 Place Engine Control selector switch Ln REMOTE. 2 NWLrj - Starting diesel generator from each bank (north and south) satisfies quarterly ASME stroking requirements of Emergency Diesel Generator Air Relay Valves to K-4B (CV-5237 CV-S239).

Failure of starter to engage does not render diesel inoperable provided opposite starter bank maintains required 15 ~econd Start time.

2.8.15 Station an operator at the diesel to verify a opposite starter bank is used on second (control room) start AND verify presence of oil in starter exhaust. 2.9 Verification of Remote Start Capability 2.9.1 Reset or acknowledge all alarm8 on local alarm I., panel K1613. 2.9.2 Record initial DG2 Watt-Hour Meter (C20j reading: '"d SUPPLEMENT 2 Page 13 of 30 PROC.NIORK PLAN NO. 1104.036 i NVlCl - Be prepared to ciock elapsed time from start signal until voltage exceeds 3750 volts. I 2.9.3 Perfom remote start of diesel as follows: PROCEDUREWORK PLAN ~TLE EMERGENCY DIESEL GENERATOR OPERATION A. Start, or verify started. Diesel Generator Room Exhaust Fans AND verify dampers open on C19 or locally. PAGE: 116of214 CHIINGE: 042-03.0 1. Verify VEP-24C running. 2. Check damper 7%-7902A open. - /r{ 3. Verify VEF-24D running. - Jfi f 4. Check damper TV-7902B open. /n, 5. Record verification in section 3.0.

JAf B. Verify DG2 Volts Select switch NOT in OFF Jlr ?' (C10). C. Simultsneousiy depress STiiXT pushbutton A?JD A Start the stopwatch.

D. -WUi 062 voltage exceeds 3750 volts. THEN stop the watch. & 2.9.4 Record time elapsed from operation of start switch unt;il voltage exceeded 3750 volts on panel C10 in section 3.0. 2.9.5 IF time is greater than 15 seconds, ?%EN perform the following.

A. Inform Shift Manager. R. Declare DG2 inoperable

'C. Discontinue test. 2.9.6 Verify SERV WTR to 302 CLRS (CV-3807) is open - and record verification in section 3.0. 2.9.7 Record Time/Date of DG2 start. - 2.9.8 Gather the following data and record parameters - per log OPS-Al5b:

Each DG2 Voltage Phase (1-2, 2-3, 3-1) DG2 Fiald Amps Voltage Regulator Controi current SUPPLEMENT 2 Page 14 of 30 PROC.IWORK PL#N NO. 1104.036 2.iO ParalLel of diesel generator with grid:

C!AUTION With the DG paralleled to the grid, grid disturbance could cause damage to the D

G. PROCEDURE

lWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION 2.10.1 IF DC2 is paralleled to the grid, & the reactor trips.

PAGE: 117 0f 214 CHANGE: 042-03-0 i)!! offsite power is lost, THEN follow "DG operation when paralleled to the - grid and the reactor trips or offsite power is lost" section of this procedure.

2.10.2 Turn Synchronize switch ON for DG2 Output - Breaker (A-408).

2.10.3 Verify smooth voltage and frequency control by - exercising controls on CiO. NOTE - ES Bus A4 voltage (running) and DG2 voltage (incoming) can be compared by using SPDS. Comparison points are:

ElA4 (A4 Voltage) EiDG2 (DG2 Voltage1 2.10.4 Adjust DC2 voltage regulator to match RUNNING P and INCOMING voltages (DG2 is INCOMING).

2.10.5 Adjust 1x22 governor control until frequency is - -60 Hz with synchroscope rotating slowly in FAST direction.

SUPPLEMENT 2 Page 15 of 30 r PROC.IWORK PLAN NO. 1104.036 CAUTION A delay in loading diesel after closing output breaker may result in a motoring trip. . In parallel operation, maximum allowed reactive load is 1200 XVAR out and 500 WAR in at full load. . Maximum current is 450 amps. Do not exceed except in emergency.

NOTE - If synchroscope is rotating too fast, sync-check relay will prevent breaker from closing.

PRWEDUREIWORK PLAN TIRE! EMERGENCY DIESEL GENERATOR OPERATION I Gradual and uniform load changes minimize engine wear and internal stresses.

A 100% load change requires -90 sec. I PAGE: I18 of 214 CHANGE: 042-036 j . If available, SPDS point JlDG2 or EDS Display should be used for DG load. 1 Momentary transients above or below the required loading value due to variations in load do not invalidate the test. 2.10.6 As synchroscope approaches 12 o'clock position - (-5 min 'til), close breaker A-408. A. Immediately begin gradually raising load to - Eull load (2750 KWI using DG2 governor control. Take -90 seconds. B. Maintain -0 kilovars using DGZ voltage - regulator.

2.10.7 Record Time/Date when DG2 output is between 2625 - and 2750 KW. 2.10.8 Turn Synchronize switch OFF. - 2.11 Perform the following as applicable:

2.11.1 IF this is a regularly scheduled monthly or - quarterly test, THEN request Chemistry Department to sample - Emergency Diesel Fuel Tank T-57B per Sampling Diesel Fuel (1618.010) and cooling water per Sampling Emergency Diesel Generator's Caoling Water (1618.014).

Name of Chemist Informed SUPPLEMENT 2 Page 16 of 30 PROC.IWORK PLAN NO. 1104.036 2.11.2 - IF this is a local start test, - THEN record stroking of opposite DG2 starter - bank, in section 3.0. 2.11.3 - IF this is a local start test, THEN check for presence of oil in exhaust of starter used. PROCEDUReNVORK PLAN TIRE: EMERGENCY DIESEL GENERATOR OPERATION A. g no indication of oil, THEN submit IVR/WO to refill oiler and - continue sumeillance.

PAGE: 1190f 214 CHANGE: 042-03 2.11.4 Verify cylinder drain cock tool and engine jacking mechanism returned to appropriate storage location.

1 2.11.5 IF requested by SYE, EEN open DG2 Air Box Trap ST-68 Bypass - (FO-1066D).

A. Close PO-1066D.

2.12 WHEN DG2 has operated for 15 minutes between 2625 and 2750 KW, TKN perform the following:

2.12.1 this is a regularly scheduled quarterly test - as noted in Initial Conditions, THEN notify vibration data collection personnel

-- to take P-16B vibration data when the pump is running. Otherwise N/A this step and P-169 vibration data in section 3.0.

CAUTION Running DGZ Fuel Transfer Pump (P-16Bj in HAND can cause overflow of DG2 i 1 Fuel oil Day Tank T-30a. DO not allow tank to fill ,250 gallons. f I Completion of the following steps satisfres quarterly ASME stroking requirements of P-168 Outlet Check Valve(F0-8B).

i I 35 minutes ensures the EDG has consumed sufficient fuel oil to reqiiire Fuel Transfer Pump operation.

I 2.12.2 Monitor day tank level to determine if DG2 Fuel - Transfer P!mp I?-16Bl is running. A. IFP-16BisErunning. - at least 35 minutes of EDG operation has elapsed, THEN verify T-30B S 220 gal. and start - P-16B in HAND.

SUPPLEMENT 2 Page PROC lWORK PLAN NO 2 104.036 2.12.3 Monitor day tank level until level rises by at Least lo gallons. A. Record ability of P-16B to raise level in section 3.0. PROCEDUREIWORK PLAN TIRE EMERGENCY DIESEL GENERATOR OPERATION U. Record T-308 level here and in section 3.0. PAGE 120 of 214 CHANGE 542-03-0 gal (LG-5237) 2.12.4 IF P-16B is in HAND, %EN return P-16U to AUTO - 2.13 DaKa gathering afcer 30 minutes between 2625 and 2750 KW: 2.13.1 Record DGZ parameters per DG2 Logsheet IOPS-AlSb).

2.13.2 Record local 002 Emergency Diesel Fuel Tank T-578 Level (PDIS-52121 (in fuel vault). inches. 2.13.3 IF tank level is c148". "."" initiate corrective actions 2.13.4 IF this is a regularly scheduled quarterly test, stroke DGZ Emerg Diesel Fuel Tank T-57B crossover (FO-1OB) as follows: A. Stroke FO-1OB open, then closed

1. Record results in section 3.0 2.13.5 IF this is a regularly scheduled quarterly test, THEN verify vibrometer readings taken per data sheet of this supplement.

2.13.6 Check SPDS EDS VTAL screen and verify diesel generator parameters display approximately the same value as C10 instrumentation for: DG2 Power DG2 Voltage DG2 Frequency A. Record in section 3.0.

SUPPLEMENT 2 Page 18 of 30 1 PROC.NYORU PLAN NO. 1104.036 The fuel oil filter "bypass" sight glass (farthest from the engine) should be empty in normal operazion, if fuel oil is in this sight glans, the fuel oil filter should be changed. The "return fuel" sight glass (nearer the engine) passes returning fuel from the injectors to the day tank. This sight glass should normally be full. Air bubbles in this sight glass with the fuel priming pump running and the engine stopped indicates air entering the suction of the pump.

Bubbles appearing only when engine is running indicates leaky valves in file1 injectors.

Little or no fuel in the sight glass indicates insufficient Euel to the engine.

PROCEDURUWORU PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION 2.13.7 Check duplex fuel oil filter sight glasses. - PAGE: 121 Of214 CHANGE: 042-03-0 A. Submit a WR/WO for repairs, as necessary, - and continue surveillance.

2.14 Data gathering after one hour between 2625 and 2750 KW: 2.14.1 Record DG2 parameters per log OPS-A15b. - 2.14.2 Contact Chemistry and verify cooling water corrosion inhibitor concentration in-spec. NOTE - The following values are given to help determine when diesel temperatures have stabilized, and are not intended to limit operation:

Scavenging Pump Disc. Temp. - 190°F - 135°F Water Pump Suction Temp. - 155-F - 160°F Water Leaving Engine Temp. - 16S°F - 175OF -- 2.15 WHEN one hour between 2625 and 2750 KW has elapsed @. engine water and oil temperatures have stabilized, THEN perform the following: - 2.15.1 this is a test following a series of - Supplement 12 Operability Teets, THEN continue full load operation for a total time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. 2.15.2 IF this test is to prove operability foilowing siqnificant maintenance. - OR requested by System Engineering, perform extended run as follows : A. Raise load between 2730 and 2860 KW using - DG2 governor control.

SUPPLEMENT 2 Page 19 of 30 PROC.IWORK PLAN NO. 11 04.036 B. Maintain -0 kilovars using DGZ voltage - regulator.

C. Record Time/Date when DG2 output is between - 2730 and 2860 KW: Time/Date - / ., PROCEDURWORK PLAN TRLE: EMERGENCY DIESEL GENERATOR OPERATION D Record initial time between 2625 and 2750 KW in Section 3.0. PAGE 122 of 214 CHANGE: 042-034 E. Continue taking hourly DG logs per DGZ togsheet (OPS-A15b1 F. ffi2 has operated for two hours between - 2730 and 2860 KW, THEN reduce load between 2625 and 2750 KW. - 1. Record Time/Date

/ - 2. Record run time between 2730 and - 2860 Kw in section 3.0. NOTE - additional run time will be determined by System Engineering.

G. additional run time between 2625 and - 2750 KW is requested by System Engineering, THEN maintain load between 2625 and 2750 KW - until requested duration has elapsed. 2.15.3 Relsove diesel generator from parallel operation as follows: A, Record Time/Date at which load reduction is - commenced.

Time/Date

-/ CAUTION A delay in opening output breaker at 100 Kw when unloading diesel may result in a motoring trip. = Gradual and uniform load changes minimize engine wear and internal stresses.

A 100% load change requires

-90 sec. B. Gradually unload DGZ to -100 KW using DG2 - governor control whiLe minimizing kilovars using DG2 voltage regulator.

Take -90 seconds.

SUPPLEMENT 2 Page 20 of 30 PROC.NUORK PLAN NO. 1104.036 C. Open DGZ Output Breaker (A-408). - D. Record Time/Date A-408 Opened: - PROCEDUREMtORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION E. F additional run time per System - Enaineerincl's request was ~erformed. - PAGE: 123 of 214 CHANGE: 042-03 - - THEN record the additional runtime between - 2625 and 2750 KW in section 3.0. NOTE - Total runti.me between 2625 and 2750 KW is as follows: I . If additional runtime was performed, the total runtime is the initial time between 2625 and 2750 KW added to any additional runtime between 2625 and 2750 KW, OR If no additional runtime was performed, the total runtime is the difference in time from when the EDG is between 2625 and 2750 KW and the time at which load reduction began.

F. Record EN initial run time as follows: - -- IF extended rim was performed, THEN record total time DG2 between 2625 .- and 2750 KW in section 3.0. - IP extended run was NOT performed, TEEN record initial time DG2 between - 2625 and 2750 KW in section 3.0. 2.15.4 Stop diesel as follows: A. Adjust frequency to 60 HZ using DG2 - governor control. 8. Adjust voltage to 4160 volts using DG2 - voltage regulator.

C. DG2 has run for 17-minutes unloaded, - depress STOP pushbutton.

D. Record Time/Date W2 stopped. - 2.15.5 Complete CG Start/Load-Rim Information Sheet - (Form ll04.036Al .

SUPPLEMENT 2 Page 21 of 30 ' PROC.FNORK PLAN NO. 1104.036 NOTE - The following Functional Capability Test (Optional) is performed at the request of System Engineering.

When required, the DG must be started within 5 minutes. If not pertormed, NIA subsection 2.16 and GO TO 2.17. 2.16 Functional Capability Test (Optional) 2.16.1 Time starting of DG2 from controi room as follows: PROCEDURWWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION A. Simultaneously depress DGZ START pushbutton - (C101 and start the stopwatch.

PAGE. 124 of 214 CHANGE: 042-035 B. Record time elapsed from operation of start switch until voltage exceeds 3750 volts in section 3.0, Functional Capability Test Table. 2.16.2 Parailel of diesel as follows: - ES Bus A4 voltage (running) and DGZ voltage (incoming1 can be compared by using SPDS. Comparison points are: ElA4 (A4 Voltage) EIDG2 (DG2 Voltage) A. Inform dispatcher that diesel generator is - ready for loading. 3. Turn Synchronize switch ON for DG2 output - Breaker (A-408). C. Verify voltage and frequency control by - exercising controls on C10. D. Adjust DG2 voltage regulator to match - RUNNING and INCOMING voltages. E. Adjust DG2 goverilor control until frequency - is -60 HZ with synchroscope rotating slowly in FAST direction.

SUPPLEMENT 2 Page 22 of 30 PROC.NIORK PLAN NO. PROCEDURUWORK PLAN TITLE: 11 04.036 / EMERGENCY DIESEL GENERATOR OPERATION - CAUTION A delay in loading diesel after closing output breaker may result in a motoring trip. , PAGE: 125 Of 214 CHANGE: 042-03-0 NOTE . If synchroscope ia rotating too fast, sync-check relay will prevent breaker from closing. Prepare to clock diesel loading. Full load will be applied within 30 seconds of closing breaker.

F. As synchroscope approaches 12 o'clock - position (-5 min ti, simuLtaneously close breaker A-408 AND start the stopwatch.

Using DGZ governor control.

raise load to 2750 KW in c30 seconds. G. WEND02 load is 22750 KW, THEN stop the stopwatch.

II. Record time elapsed from when output - breaker closed to full load in section 3.0, Functional Capability Test Tabie. I, Turn Synchronize switch OFF. - 2.16.3 WHEN DG2 has operated for 15 minutes at 2625 to 2750 KW, THEN remove DG2 from parallel operation as - f o1lows : CAUTION A delay in opening output breaker at 100 KW when unloading diesel may result in a motoring trip.

NOTE Gradual and uniform load changes minimize engine wear and internal stresses.

A 100% load change requires

-90 sec. A. Gradually unload DG2 to -100 KW using DG2 - governor control while minimizing kilovars using DG2 voltage regulator.

Take -90 seconds. B. Open DG1 Output Breaker (A-408) . -

SUPPLEMENT 2 Page 23 of 30 2.16.4 stop diesel as follows: PROC.NVORK PLAN NO. 1104.036 A. Adjust frequency to 60 WZ using DG2 - governor control. B. Adjust voltage to 4160 volts using DG2 - voltage regulator.

PROCEDUREWORK PU\M TITLE: EMERGENCY DIESEL GENERATOR OPERATION C. Record DG2 Watt-Hour meter reading - PAGE: 126 of 214 C~ANGE: 042-03-0 KWH D. DG2 has run for 17-minutes unloaded, - ?.HEN depress DGZ STOP pushbutton. 2.16.5 Complete DG Start/toad-Run Informaeion Sheet - (Form li04.036A). 2.17 Restoration 2.17.1 Record DG2 ENGINE TOTAL HRS iC1O.S) : hrs. 2.17.2 Record DG2 Watt-hour meter reading IC20): - KWH. 2.17.3 Verify associated critical and non-critical - alarms ciear: ED62 CRITICAL TROUBLE lK01-C41 EDG2 NON-CRITICAL TROUBLE (K01-D4) 2.17.4 mN one of the following sets of conditions are met, Ambient temperature is 540.F 9 diesel has been stopped for at least 5 min~tes Ambient temperature is s40'F AND diesel has been stopped for at least 20 minutes AND IF conditions allow, THEN return EDG Ventilation to AUTO as follows: A. Verify VEP-24C handswitch to AUTO. - B. Verify VEF-24D handswitch to AUTO. - C. Verify that at least one of the following cycles off in AUTO: 2.17.5 WHEN D62 has been stopped for at least 20 - minutes, THEN close SERV WTR to DG2 CLRS (cv-3ao71.

SUPPLEMENT 2 Page 24 of 30 PROC.MORK PLAN NO. 1104.036 2.18 Verify the following valves closed: K-48 Crankcase Pressure PI-52448 ISOL (PO-5244B) - PROCEDUREMORK PLANTITLE:

EMERGENCY DIESEL GENERATOR OPERATION K-48 Air Box Pressure PI-52458 ISOL (30-5245B) - PAGE: 127 of 214 CHANGE: 042-03-0 2.1.9 IF this is a regularly scheduled monthly or quarterly test. THEN notify chemists to obtain following samples.

DG2 Fuel Oil Day Tank T-30B per 1618.028.

DG2 lube oil sample per 1.618.039 2.20 Verify vibrometer readings recorded in section 3.0 as - required.

2.21 Record AND review required data in Trend Spreadsheet Recorded and reviewed by (SE/SRO) Date 2.21.1 IF available, - %EN attach copies of graphs. -

3.1 Record values observed during DGZ testing and compare with - "Limiting Range For Operability.tr

-.\- DG2 remote PROC WORK PLAN NO. 1104.036 SUPPLWENT 2 Page 25 of 30 3.0 ACCEPTANCE CRITERIA PROCEDUREIWORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION PAGE: 128 0f 21 4 CHANGE: 042-03-0

SUPPLEMENT 2 Page 27 of 30 PROC.WORK PLAN NO. 1104.036 3.2 IF "NO" is circled in the right hand column, - EN perform the following:

PROCEDURUWORK PLAN TIRE: EMERGENCY DIESEL GENERATOR OPERATION Immediately notify the Shift Manager, Declare DG2 or component inoperable, verify a Condition Report initiated, Initiate corrective action.

PAGE: 1300f 214 CHANGE: 042-03-0 Reference Tech Specs for applicable Conditions and Required Actions. It is not necessary to write a Condition Report for a failure which is already specifically addressed by an open CR, or for a fan out of service for planned maintenance.

3.3 - IF any measured value does not fall within "Acceptable Normal Range", THEN initiate corrective action.

(1) If "NO" is circled, declare that component only inoperabie.

(2) If remote start only N/A. (31 N/A unless test was to prove operability following significant maintenance requested by System Engineering. Performed by - Operator Date/Time

? ~!I/Q< /* Performed by Operator Date/Time Performed by Operator Date/Time 1 /' 4' horizontal

'3 6 5 horizontal.

I3 horizontal PROC.WORK PLAN NO. 1104.036 - SUPPLEMENT 2 Pase 28 of ?n PROCEDUREWORK PLAN TRLE: PAGE: 131 of 214 , , horizontal 8 9 12 11 10 horizontal EMERGENCY DIESEL GENERATOR OPERATION POINT _ NO. 1 2 3 4 CHANGE: 042436 VELOCITY (IN/SEC.)

12 5 6 7 8 16 Emergency Diesel

1. Data Collected By -- - Date Vibrometer M&TE # Calibration Due Date POINT NO. 9 10 11 VELOCITY (IN/SEC. ) POINT NO. 13 14 15 VELOCITY (IN/SEC. )

SUPPLEMENT 2 P-16B r Page 29 of 30 PROC.NORK PLAN NO. 1104.036 PUMP VIERATXON HORIZONTAL VERTICAL Horizontal Vertical PROCEOURUYVORK PLAN TITLE: Data Collected BY Date Vibrometer M&TE # Calibration Due Date - EMERGENCY DIESEL GENERATOR OPERATION old vibroneter probe tip firmly against the survey point marker, perpendicular to the surface. Locations of markers are depicted above. PAGE: 132 Of 214 CHANGE: 042-03-0 SUPPLMENT 2 Page 30 of 30 PROC.MIORK PLAW NO. 1104.036 4.0 SHIP1' MANAGER RI?VIEW RM) ANALYSIS (circle on^ 4.1 Do all measured values recorded in the Acceptance Criteria section fall within the specified LIMITING WE FOR OPERABILITY?

YES NO PROCEDUREMIORK PLAN TITLE: EMERGENCY DIESEL GENERATOR OPERATION 4.2 Do all measured values recorded in the Acceptance Criteria section fall within the ACCEPTAaLE NORMAL RANGE? YES NO PAGE: 133 of 214 CMANoE: 042-039 4.2.1. IF "NO", - - TWEN initiate corrective action and raise test frequency to once per 6 weeks mt=i resolved satisfactorily.

4.3 IF answer to either 4.1 or 4.2 is "NO', THEN describe acrion taken below. - 4.4 Has this equipment been proven operable per the ACCEPTANCE CRITERIA?

YES NO 4.5 Have all the administrative requirements of this test been satisfied (i.e.. ali initial blocks initialed or N/A'd, a11 data entered, cal due dates listed, applicable signature spaces signed, etc. 1 ? YES NO SHIFT MANAGER

-- DATE ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-CHEMI Page 1 of 4 UNIT: 1 REV # &.-- DATE: TUOI NUMBER: A1 JPM-SRO-CHEMI SYSTEMIDUTY AREA: ADMINISTRATIVE TOPIC -CONDUCT OF OPERATIONS TASK: Respond to secondary chemist^

parameter out of specification JTA#: ANO-SM-ADMIN-NORM-165 UA VALUE RO: 2.3 SRO: 2.9 UA

REFERENCE:

2.1.34 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION:

INSIDE CR: X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE): PLANT SITE:

SIMULATOR: PERFORM LAB: POSITION EVALUATED:

RO: N/A SRO: X ACTUAL TESTING ENVIRONMENT:

SIMULATOR:

X PLANT SITE: LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S):

1000.042 Steam Generator Water Chemistry Monitorina - Unit One EXAMINEE'S NAME:

SSN ---- EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-CHEMI Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The ~lant has been operatinq at 100% for 215 davs. The shift chemist has iust arrived in your office and has qiven vou, the Shift Manaaer, form 1000.042A to review. TASK STANDARD:

Examinee correctlv recoanizes that the threshold for Action Level 3 has been exceeded and the Dlant should be shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. TASK PERFORMANCE AIDS: 1000.042 ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-CHEMI INITIATING CUE: As Shifl Manager, review the 1000.042A form for out of specification Feedwater chlorides.

CRITICAL ELEMENTS (C) 3 1. Compare results of confirmatory analyses to readings from continuous monitors.

Requested readings of continuous monitors to compare with lab analyses results on 1000.042A.

I I I NOTE Inform lrainee that Chemistry suspects a bad polisher to be the source of the chlorides. I I I I 2. Identify and isolate sources of Inquired as to results of searches for impurity ingress. source of chloride in-leakage.

I 3. Refer to Attachment 3 1000.042 Referred to Att. 3 and determined that Action Level 2 as shown on the form is incorrect and that Action Level 3 had been exceeded.

Action Level 3 requires the plant to be shutdown as quickly as possible (typically within six hours) instead of the 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> allowed for Action Level 2. Page 3 of 4 END ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-CHEMI Page 4 of 4 EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:

The plant had been operating at 100% for 215 days. The shift chemist has just arrived in your office and has given you, the Shift Manager, form 1000.042A to review. INITIATING CUE: As Shift Manager, review the 1000 042A form for out of specification Feedwater chlorides.

Page 20 of 21 PROCEDURE REQUIREMENTS:

/UL'O,O'rC&r

/2ose Y cP PAGE CHEMISTRY RE ONMENDATIONS.

/ NUMBER: Ar.kcfl 40 . o /F.,JF/ .+MO b,, ; /no ASL,~S, MONITORING ACTIVITY SHIFT WAGER: TIME : 1 SAMPLING FREQUENCY:

oil, . ( /w - TIME CLOCK ENDS: DATE: 9- ,/7 TINE: - 0 .I CHEMIST REPORTING OUT-OF-SPEC.

DATE : PiL +f; 9-//3.-os TIME: T%yy /'/ -7 il U Hideout Return for planned outage. Ifr'marked, then Shift Manager reviews (nay be N/A. REVIEWED BY SHIFT MANGER: DATE : TIME: FORM TITLE: FORM NO. CHANGE UNiT 1 STEAM GENERATOR MONVORING REPORT 1000.042A 013-010 IN SPEC TEST PARAMETER CHEMIST ERIYYING DATE : NOTES : IN SPEC. CONDITION:

TIME: CORRECTIVE ACTION TAKEN BY OPEFATIONS:

REVIEWED BY DATE : 1 LIMIT DATE __ TIME - IN SPEC P-ETER -- TEST RESULTS -- LIMIT - DATE i TIME - IN SPSC PARAMETER

-- TEST 1 I DATE L gI_T ___ TIME -

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-TALT2 Page I of 4 UNIT: 1 REV # -&.-.- DATE: TUOl NUMBER: A1 JPM-SRO-TALT2 SYSTEMIDUTY AREA: ADMINISTRATIVE TOPIC - EQUIPMENT CONTROL TASK: QUARTERLY CHECK OF TEMPORARY ALTERATIONS JTA#: ANO-SRO-ADMIN-NORM-89 KA VALUE RO: 2.8 SRO:3,4 KA

REFERENCE:

2.2.1 1 APPROVED FOR ADMINISTRATION TO:

RO: SRO: X TASK LOCATION:

INSIDE CR:- OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE): PLANT SITE:

PERFORM SIMULATOR:

LAB: POSITION EVALUATED: RO:

SRO: ACTUAL TESTING ENVIRONMENT: SIMULATOR:

PLANT SITE: LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIE IN MINUTES: 20 MINUTES REFERENCE(S):

1000.028 Cha. 024-00 EXAMINEE'S NAME: SSN ---- EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAlNST THE STANDARDS CONTAINED IN THlS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY: PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THlS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-TALT2 Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is in Mode 3 for turbine repairs. All Temporaw Alterations taqs are in olace. TASK STANDARD: The examinee has reviewed the attached temporaw alteration and identified at least 2 administrative errors. TASK PERFORMANCE AIDS: Temporaw Alteration with 3 errors.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-TALT2 INITIATING CUE: Page 3 of 4 The Shifl Manager directs you to conduct a Quarterly Review of Temporary Alteration 03-1-009 per 1000.028 You have in hand the package as found in the Control Room file. Identify at least 2 administrative errors. CRITICAL ELEMENTS (C) 2 2. Identify administrative errors in Temporary Alteration Package 03-1 -009. ('3 Examinee identified at least 2 of 3 errors on Temporary Alteration Package 03-1

-009: Improper mode (only Mode 1 checked, all modes should be checked) Installation authorization not signed r 1000.028E Integrated Drawing list is missing does not agree with 1000.028G, Affected Drawing list in TAP. E-13 sh. 1 and E-I 11 sh. 3 are not on 1000.028E.

END PERFORMANCE CHECKLIST

1. Review Temporary Alteration Package 03-1-009.

STANDARD Examinee reviewed Temporary Alteration Package 03-1-009.

NIA SAT UNSA T ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-TALT2 EXAMINEE'S COPY Page 4 of 4 JPM INITIAL TASK CONDITIONS:

The plant is in Mode 3 for turbine repairs. All Temporary Alterations tags are in place INITIATING CUE: The Shift Manager directs you to conduct a Quarterly Review of Temporary Alteration 03 009 per 1000.028. You have in hand the package as found in the Control Room file. Identify at feast 2 administrative errors.

TAP #: 03-1909 TAP Installation WO# 00033175 (?I . TAP Removal WWO# WR #00014536 3 TAP ER # ER-ANO-2003-0906-00u I TITLE: 'C' Phase Main Transformer Removal ARKANSAS NUCLEAR ONE -K>m ~LE: E-DOC NO. CHANGE NO. ANO-1 IX[ ANO-2 ANO- Common 17 Qa Fn sC] TEMPORARY ALTERATION FORM :

• If both units are affected, mark common. Unit responsible forthe affected SSC, as defined in the Component Data Ease, will number and control the TAP. r ] Affected SSC: Associated SSC: I ~ ~ ".-~ support the future installation of the replaced transformer.

1000.026-A Reason for lnstallation:

t Due to current olant conditions, removal of the deoraded C-Phase Main Transformer has been requested to 026-00-0 L 1 Nodes - Plant Modes for whi~h @ 7 p-$4480) b TAP mayremain installed:

C] 2 (mark all which apply): 11 3 0 4 o 5 during 0 6 duration, installation Engineer:

Date: Independent Reviewer:

Date: Supervisor:

Date: J, /24 (03 - Manager: Date: /1/t6/03 j System Engineer: System Engr Manager: Date: Operations Manager: Date: /I /z~/o - 3 OSRC Chairman:

Date: N /& Plant Manager: Date: I\ -&-6 > val has been granted lMSTALLATION AUTHORIZATION SM 1 CRS: Dale: . -. ~ - REMOVAL AUTHORIZATION SM / CRS: Date:

TAP Serial No. 03-1-OW Page: 2 LIST OF EFFECTIVE PAGES t WNSAS NUCLEAR ONE f DOC TITLE: E-DOC NO. (Additional sheets must be numbered and include the TAP serial number) TEMPORARY ALTERATION FORM 1000.028-A CHANGE NO.

026-00-0 TAP Serial No. 03-1-009 Page: 3 ARKANSAS NUCLEAR ONE Ka0C TITLE: E-DOC NO. CHANGE NO. Summary Description of temporary alteration:

This T-AK will provide the necessary instructions to support the temporary removal of the original Unit-1 C-Phase Main Transformer

@-OIC). TEMPORARY ALTERATION FORM . documentation-to the i Verification Signature:

1000.028-A 3 ( 026-00-0 Special Instruction:

The installation engineer (or designee) shall verify that the requirements of ER-ANO-2003-0906-00&3 have been implemented in the installation work order (WO# 00033175 Task W)). If certain steps, or work instructions, have Suggested Temporary Alteration Tag Locations:

lsophase Bus Duct Blanks Temporary Junction Box for Generator Lockout Circuit wiring installed nearlon X-O1C concrete pad. been previously oerfomed, visually veMe comleteness of the work and attach a copy of supporting Verify that a copy of the lation work order has been attached to this Temporary Alternation after installa '=/c/o 5 ockout functions have been performed dunng functional testing ntinuity check described in ER-ANO-2003-090600823.

Attach blies' structural support under WR# 00014479 and I 1 Suggested Caution Cards 1 Locations None (Additional sheets must be numbered and include the TAP serial number) 3 1 lsophase Bus Duct Blanks (Covers) for conduit openings per WR# 00014477. (Testing to verify properflow balance and capability of the lsophase bus cooling will be tested in conjunction with the test performed by the X- 018 and X-01s lsoph NO-2003-0893-001 and will verify that the lsophase Bus Duct Blanks have an Verification Signature rsuMs i hu-h\h\;Y wl)p'& t#.rfa\bA.

Removal of this T-Alt will be covered in a separate WO (presently WR# 00014536) iaw linked ER-ANO-2003-906-001. (See ER-ANO-2003-0906-001323 Section 5.2) The removal instructions will depend on the transformer model that will be installed as a replacement for X-OIC.

The installation Engineer (or designee) must verify that the removal WO and supporting ER appropriately address all facets of the TAP and attach the supporting documentation (including the WO and ER) to this Temporary Alteration prior to removal. Verification Signature:

TAP Serial No,03-14W Page: 4 ARKANSAS NUCLEAR ONE &-DOC TITLE: VERIFICATION AND DOCUMENTATiON OF INSTALLATION TEMPORARY ALTERATION FORM NQE if partial installation is desired, Fom 1000.024E "Provisional Release" shall be complied with. This form shall be filed with the Temporary Aiteration Package, with a copy in the installation WO. The lnstaliation Engineer 01 other ind temporacy alteration has been install INSTALLATION ENGINEER:

DATE: The Shift Manager or designee vetifi J++$=- stalled Der Section 6.1 1.2. i I E-DOC NO. 1000.028-A SHIFT MANAGEWDESLGNEE:

DATE: / ~/~/663 , , CHANGE NO. 026-00-0 Copies of the Temporacy Alteration Package are forwarded to:

a) If OSRC final review has not been obtained, forward originai to OSRC promptly and file a copy in the Control Room; otherwise mark N/A. FORWARDEDBY:

&,/A DATE: , b) Manager, Design Engineering (Affeded Drawing List only) FORWARDED BY:

DATE: /z/gb~ /-I C) Manager, System Engineering FORWARDED B DATE: /2/&c~ - d) Control Room of other unit, if affected (otherwise NIA) FORWARDED BY: &/A DATE: &/A 1. The Installation Engineer audit should be completed within 7 days of the installation of the temporary Alteration.

2. it Is not necessary to make copies of drawings lamer Wan 8% x 11". 3. TheTag Record Sheet (Form 1000.0288) and a copy of any Lifted Lead Logs used for this installation shall be filed with the TAP. The Installation Engineer shall perfom an audit of th tion Package in accordance with Section 6.12.1. tNSTALLATlON ENGINEER:

DATE:

TAP Serial No. 03-1-009 Page: 5 . ARKANSAS MUCLEAR ONE VERIFICATION AND DOCUMENTATION OF REMOVAL E-oocnn~:

TEMWRARY ALTEWON FORM If pariial removal is desired, Foim 1000.024E 'Provisional Release" shall be complied with. This form shall be filed wiih the Temporary Alteration Package, with a copy in the Removal WO. The Installation Engineer verifies that the temporary alteration has been removed and configuration restored per Section 6.16.2. I E-DOC NO. 1000.028-A INSTALLATION ENGINEER:

DATE: CHANGE NO. 026-004 The Shift Manager w designee verifies that the temporary alteration has been removed and configuration restored per Section 6.16.4. SWIFT MANAGERJDESIGNEE:

DATE: Copies of this page of the closed-out Temporary Alteration Package are forwarded to: A. Manager, Design Engineeiing FORWARDED BY: DATE: 6. Manager. System Engineeting FORWARDED BY:

DATE: If other unit was affected, remove their copy (otherwise NIA). REMOVED BY: DATE: SHIFT MANAGERIDESIGNEE:

DATE: Forward original Temporary Alteration Package to Records. FORWARDED BY: DATE:

TAP Serial No. 03-1 009 Page: 8 ARKANSAS NUCLEAR ONE AFFECTED DRAWING LlST P-DOC TITLE: TEMPORARY ALTERATION AFFECTED DRAWING LIST FORM 1A. The Installation Engineer wiil list below in Column 1 all Category A 8 B drawings, affected by this Temporary Alteration (if none, enter "none"), and wili sign below.

If addrtional space is required, additional coptes of this sheet may be attached.

Provide sheet numbers in the upper right corner. 18. The System Engineer will review and concurwith the information in column 1 and will sign below. 2. The Shift Manager will assign an individual to determine whether each listed drawing is filed in the Control Room and to mark Column 2 appropriately.

3. The Shift Manager will assign an individual to list each affected Contml Room drawing on the Temporary Alteration Integrated Drawing List and all required copies. As each drawing is listed, the individual will initial the table in Column 3 below ("NIA" if not in Control Room). When all have been listed, he wili sign below (even if "none" are listed).

4. When the Temporary Alteration is deared, the Shift Manager wiil assign an individual to dear each affected drawing from the Temporay Alterat,ion lntegrated Drawing List and all requir* copies. As each drawing is cleared, Column 4 below wi I be rnNaled When all have been cleared, .~. . the . indrvKfual will sign below. 5. At each quartefiy review, the person perfoning the review will enter the date of the review and initial below the date for each Control Room drawing to indicate that the listed drawing a pro rl listed on the Temporary Alteratron Integrated Drawing List.

If additional columns are requ@red?adbitional copies of this sheet may be attached, with the information in Columns 1 and 2 repeated and Columns 3 and 4 diagonally lined through and marked "MA". (No review is required if no dmwings are listed.) E-DOC NO. 1000.02843 Affected drawings have been cleared fWm the integrated Drawing List and all copies: I Assigned Individual Date CHANGE NO. 025005 (Additional sheets must be numbered and include the TAP serial number)

I I ARKANSAS NUCLEAR ONE E-DOC TITLE: E40C NO, TEMPORARY ALTERATION TAG RECORD SHEET . . 02600-0 I , . TEMPORARY ALTERATION TAG RECORD SHEET TAP SERIAL NUMBER 03-1-009 Sheet -- 7 1000.028%

CHANGE NO.

TEMPORARY ALTERATION PACKAGE REVISION (TAPR) TAP Serial Number: 03-1509 TAPR Number: 1 ChangecYAdded Pages: 1.2.3.6.7.Attachment 11 8 AWNSAS NUCLEAR ONE n Summary of Changes: INCORPORATED ER-ANO-2003-0906-002 Added wirina chan~es to address the nuisance alarms caused bv the X-O1C fire detedion disabled detectors which have been removed from service.

Provide alternative method for supgortlna west end of lsoahase Bus Bushino Box. Corred WO# tvpos. Justification of Changes: Prevents nuisance alarms from distradlna Ooerations personnel and from maskinq valid common trouble alarms from remainina fire detedion svstem inouts. Prov~des acceotable method for supoortinq west end of lsophase Bus Bushinc Box. &DOC WTLE: TEMPORARY ALTERATION PACKAGE REVISION (TAPR) TAPR APPROVAL A YES response to a screenang questaon requires the apprwal of Management and OLiRC. IF screening questions are answered NO. - THEN obtain only a Systeqs-Qngineerlng Supervisor approval.

I Page 8 E-DOC NO. 1000.028-D Operations Manager : CHANGE NO.

025505 OSRC Chairman : Plant Manager : I n INSTALLATION AUTHORIZATION SMlCRS : ate 12-13 !g - 1 . (additional sheets must be numbered and must include the TAP serial number)

TEMPORARY ALTERATION PACKAGE REVISION (TAPR) 1 TAP Serial Number: 03-1509 TAPR Number: A ..........................................

! ChangedIAdded Pages:~ddtt*.~~~~~.?a**.~.O

................. - ARKANSAS NUCLEAR ONE ! Summary of Changes: esc: son o~,imm s. own Wmarked-uodrawinasE-113Sh2reU2andE:4!jmgy...~-

i *aMdalona with ca-and cola*? ...... % .............

/ Justification of Changes: Clarificationofails

... ....................

alreadv-..

...............

.............

.............

CHANGE NO. e-wc nn~: E-DOC NO. addressed by the originally approved temporary alteration? - I 4. Does this change affed performance requirements in a manner OQ! already addressed by ~UYES MNO A 1. Does this change require a revision to the original 50.59 Review 2. Does this change allow the Temporary Alteration Package to be applied to a different component, system . structure, or associated OSRC?

3. Does thls chanqe affed the basic function of a system, structure, or component

~o1 already I or reaulatow reauirements to which the 1 UYES WNO UYES MNO DYES MNO DYES MNO 026-00-0 TEMPORARY ALTERATION PACKAGE REVISION (TAPR) TAPR APPROVAL 1000.028 NOTE A YES response to a screening question requires the approval of Maaagement and OSRC. - - screening questions are answered NO, THEN obtain only a Systems Engineering Supervisor approval. plant is comrnitikd, not addressed by the approved

~em~ora& ~lteration Package? Date 12/4/2003 Date 12/4/2003 Date 12/4/2003 System Engineer .</A Date Systems Engineering Manager : $4 Date Operations Manager : Date OSRC Chairman

n/& Date Plant Manager

Date , . / / INSTALLATION AUTHORIZATIOA Date /2/cgd~ I (additional sheets must be numbered and must include the TAP serial number) 7pqp-03-l-a~q Page 10 & The following detailed steps are for additional clarification of information already contained in the supporting ER for this T-Alt.

Per connection drawing E-113 Sheet 2 and E-471 Sheet 15, in C482: lift wire at terminal 8E (Cable # U34DB Color: OR-BK) jumper 2E to 8E d~l~103 &p$yb3 lift WYm& & (Cable # U34A5 Color: G#) 6 4 gk jumpe 11 #I . ah.-.--.$+, v4 lift wire at terminal 6E2 (Cable # U34DB Color: BK) /+ jumper 3E to 5E2

- -- - - - - Page 11 ARKANSAS NUCLEAR ONE La TEMPORARY ALTERATION PACKAGE REVISION (TAPR) TAP Serial Number: 03-1-009 , to %GO ,a(5(03 TAPR Number: _;?_ ChangedIAdded Pages: Changed PaQes 3h d Attachment 1 from ER-ANO-2003-0906-002 to ER-ANO-2003-0906-003 E-DOC TITLE: TEMPORARY ALTERATION PACKAGE REVISION (TAPR)

Summary of Changes: ER-ANO-2003-0906-003 added to correct instruction for fire detection bvoass wlrina and added thhb~aass of the Operatina Relay to orevent inadvertent actuation, Enhancements from TAP 03-1-009 TAPR 2 incnroorated into ER for comoleteness.

E-DOC NO. 1000.028-D Justification of Changes: 3-1 13 Sh2 Rev 2 contamed draflina errors not detectable until attemuted installation creference CR-1-2003-1212).

Chanqes necessaw lo meet scooe. CHANGE NO. 025-00-0 TAPR APPROVAL NOTE A YES response to a soreenxng questaon reqUrres the approval of Management and OSRC. IF screening questions are answered NO, - THEN obtain only a Systems Engineering Supervisor approval. - the originally approved temporary alteration?

I System Engineer ?i~~pnr--~afi'n Kf / zjssw?ttmbr/

CR'S Date 5. Does this change deviate from codes, standards, or regulatory requirements to which the Systems Engineering Manager : d/& Date UYES &NO Operations Manager : pi //t Date plant is committed, not addressed by the approved Temporary Alteration Package? OSRC Chairman : ,d Date Piant Manager : pi4 Date INSTALLATION AUTHORIZATION SMlCRS , ate /Z-F cC 3 I I (additional sheeis must be numbered and must include the TAP serial number)

- ER COVER SHEET 17%' I --c@ R rmthwr 3.. ER #: ER-ANO-2W3-0906-003 I Revision #: 0 I Grade: N.0.R.80 Page 1 of 1 I 1 - - -- - -- Title: Removal of Origlnal G-Phase Maln Transformer - (will superscede ER-ANO-2003-0906-002)

System ID: Date Required:

Equipment ID: Sugg. Milestone:

ProblemlProposed SolutionNustification: (Attach additional sheets as required)

This ER will provide the engineering bases for T-Ait 03-1-009.

Cannot revise ER-ANO-2W3-0906d02 and as a result this ER was initiated to superscede the original ER. [Note that ER-ANO-2003-0906-002 superceded ER-ANO-2003-0906400.

This revision is necessarv as a result of a drawina error on El 13-2 (ref CR-1-03-1212). . . .. Quality Classification:

Non Safety Implementation:

Response Type: Evaluation Problem Resolution: (Attach additional sheets as required)

See Attached LBD Impacted 0 YES 8 NO Responsible Engineer:

fviehta,Niranian K Date: 12/4/2003

@ Technical Reviewer 0winas.Roaer Lacey Date: 12/5/2003 n Desian verifier Date: -- @ Supervisor Allen.Rhouts E D8k 12/5/2003 a Engineering Manager Date: PSRC Required PSRC Meeting Number: Date: GMPO Date:

Revison: 0 I Review Results Title: Removal of Original C-Phase Main Transformer - (will suoerscede ER-ANO-2003-090B002)

ER: ER-ANO-2003-0906-003 COMPUTER SUPPORT GROUP Package Mehta.Nirsn]an K TIGER TEAM Package Mehta,Nlranjan K via telecon for Saulsbeny,Da~yll 12104i2003 TIGER TEAM Packaae Mehta.Niran~an K via teleeon for Sauisbem Derrit 12/05/2003 Engineering Request UNIT 1 OPERATIONS STANDARDS Packaoe I Mehta Nlranlan K ma tal-n for TaulOl .lmsc T 1710dl~m2 - - ~ .~ - - .- ~ .. .. ... . .. . COMPUTER SUPPORT GROUP Flnal Team Mehta.Niranjan K via telecon fa Tayw.James T 1V05QW3 UNIT 1 OPERATIONS STANDARDS Final Team t Mehta.Niranian K via teleeon for Canih.Kenneth V 12/05/2003 i Page @of l+ c

@ TEMPORARY ALTERATION INTEGRATED DRAWING LIST ARKANSAS MUCLEAR ONE EDOC TITLE: E-DOC NO. CHANGE NO. TEMPORARY ALTERATION INTEGRATED DRAWING LIST Maintain original in the Temporary Alteration file.

TAP NUMBER 03-1 -009 04-1 -007 04-1 -002 OP-1104.032 Att. E Distribute copies to: Contml Room Control Room Extension Auxiliary Operator Shack (UnR 1 only) WCO Office (Unit 1 Only) Page 1 of j. 1000.028-E NOTE: all other copies shall be stamped "Unwnfrolled Copy" or words to that effect 025404 DRAWINGS AFFECTED E-14-1, E-111-1,2, E-452-4, E-113-1,2, E-471-15 M-230 Sh. 2 E-71 Sh. 14 M-209 Sh. 4 M-219 Sh. 1 DATE INSTALLED Z 2/5/03 511 0104 511 1/04 3/3/05 DATE REMOVED - -

TUOI NUMBER: A1 JPM-SRO-RC22 Page I of 4 JOB PERFORMANCE MEASURE Unit: 1 Rev # 0 Date: 311 512005 TUOI NUMBER: A1 JPM-SRO-RC22 SystemlDuty Area: Administrative Topic-Radiation Control Task: Calculate Stay times for yourself and another operator JA# ANO-SRO-ADMIN-NORM-162 KA Value RO 2.6 SRO 3.3 KA Reference G 2.3.10 Approved For Administration To: RO SRO IZi/ Task Location: Inside CR:

Outside CR: Both: *3 Suggested Testing Environment And Method (Perform Or Simulate):

Simulate Plant Site:

Simulator:

Perform Lab: Position Evaluated:

RO: SRO: X Actual Testing Environment:

Simulator:

Plant Site: Lab Testing Method: Simulate:

Perform: Approximate Completion Time In Minutes: 20 Minutes Reference(S): HP Survey Map of P36C, Pump Room

54. Examinee's SSN: Name: Evaluatoi's Name: The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be: Satisfactory:

Unsatisfactory:

Performance Checklist Comments:

Start Time Stop Time Total Time Signed Date: Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

TUOI NUMBER: A1 JPM-SRO-RC22 Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

A hot spot has developed on Makeup PUMP P36C. An operator will be working in the vicinity of the reduction gear assembly in order to flush the lines and reduce the hot spot radiation field. Using the supplied survey map, determine the individual stay times the operator without exceeding the annual administrative dose limit (Ignore dose received during transit). He has an accumulated annual Whole Body dose of 1750 mR (AN0 records).

No additional dose has been received at any other site. Also, calculate stay times if the air in the pump room was contaminated with a level of 0.40 DAC (stochastic) assuming no respirators are used. Calculations should be based on AN0 Unit 1 Administrative dose limits. Provide answers with 3 significant figures (example 4.51 hours5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br />). Do not consider AURA task requirements.

Any required dose extensions have been processed and approved.

TASK STANDARD:

The examinee has correctly determined the stay times for an operator on the assignment.

TASK PERFORMANCE AIDS: HP Su~ey map of P36C Pump Room, Room number 54 SIMULATOR SETUP: N/A TUOI NUMBER:

A1 JPM-SRO-RC22 Page 3 of 4 INITIATING CUE: Determine the Stay time for an operator on the job. Also determine the stay time if the air in the pump room was contaminated with a level of 0.40 DAC (stochastic) assuming no respirators are used Provide answers with 3 significant figures (example X.XX hours). CRITICAL ELEMENTS (c): 1,2. and 3 C PERFORMANCE CHECKLIST STANDARD N/A SAT UN C I I Operator has 1750mR. =>allowed dose 250mR I . . - .- . . . .. - ... -. . . . .. . . . -. .- .- .. - SAT -. -. . - . . . . -. C 250mR = 3.33 hr, I / 75mWhr 1. Determine the HIGHEST general area dose rate in the area of the reduction gear assembly to be used from the survey map. Examinee has determined the HIGHEST general area dose rate in the area of the reduction gear assembly to be used from the survey map of P36C pump room. 2. Determine Stay time (to 3 significant figures) with no airborne contamination for both operators.

Key: Max dose at AN01 is 2000 mR I ,I -- -- . ' EXAMINERS CUE: This concludes the JPM. .---7 -- - _ Examinee has determined that the stay time for operator is 3.33 hrs plus or minus 0.01 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, C END 3. Determine Stay time( to 3 significant figures) WITH airborne contamination, IDAC = 2.5mWhr => 0.40DAC =zl ,OmWhr Total rate = 75mRlhr + I .OmR/hr = 76mWhr Examinee has determined that the stay time for operator is 3.29hrs plus or minus 0.01 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

TUOI NUMBER: A1 JPM-SRO-RC22 Page 4 of 4 EXAMINEE'S COPY INITIAL CONDITIONS:

A hot spot has developed on Makeup PUMP P36C. An operator will be working in the vicinity of the reduction gear assembly in order to flush the lines and reduce the hot spot radiation field. Using the supplied survey map, determine the individual stay times for the operator without exceeding the annual administrative dose limit (Ignore dose received during transit). He has an accumulated annual Whole Body dose of 1750 mR (AN0 records).

No additional dose has been received at any other site. Also calculate stay times if the air in the pump room was contaminated with a level of 0.40 DAC (stochastic) assuming no respirators are used. Calculations should be based on AN0 Unit 1 Administrative dose limits.

Provide answers with 3 significant figures (example X.XX hours). Do not consider ALARA task requirements.

Any required dose extensions have been processed and approved. See handout for definitions.

INITIATING CUE: Determine the Stay time for you an operator on the job. Also determine stay time if the air in the pump room was contaminated with a level of 0.40 DAC (stochastic) assuming no respirators are used. Provide answers with 3 significant figures (example X.XX hours).

I MAP NUMBER. 1A2-16 LOCATION Aux building posted: RM,RWPR 335 posted RA U1 AUX 335' EL P36C PUMP ROOM. ROOM NUMBER 54 I DPM: 100~m2 No. Activity Dose Rate lnst HP-DR-170 Cal Due Date 12/31/2005 I Dose Rate Inst #2 RM-065 1 I z .=I 1 ~al l)ue Date 1213112005 I Count Inst RO-705 I - Gal Due Date 1213 112005 -- Count Inst. #2 RO-708 - -- --- - - -- - - -- -- - -- .- -- -- -- - RP Supervisor Review: -. - All Radiation values are in memhour unless othmvise noted. - 125 denotes gamma general area dose rates. - -- - -- - Smear contanination values are in DPMilOO Sqm unless 0th-ise noted. H. S. Denotes Hot Spot Kuidinp lIANl# 011256 -. - ...

• 1211 3 Denotes Ganuna Contadmar reading (30 m) 0 Denotes smear location (100 sqm) Page 1 of 12 Denotes Cornact dose rate (gmna) '12 B Denotes Beta Contact Dose Knte n ~en~tes I,, area rn~ hti, Fam to be retained for records ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-EAL9 Page 1 of 4 UNIT: 1 REV # 0 DATE: TUOI NUMBER: A1 JPM-SRO-EAL9 SYSTEMIDUTY AREA: ADMINISTRATIVE TOPIC - EMERGENCY PROCEDURESIPLAN TASK: TAKE EMERGENCY DIRECTION AND CONTROL JTA#: ANO-SM-EPLAN-EMERG-302 KA VALUE RO: 2.6 SRO: 4.0 KA

REFERENCE:

2.4.29 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION:

INSIDE CR: X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE): PLANT SITE:

SIMULATOR:

PERFORM LAB: POSITION EVALUATED: RO: NIA SRO: X ACTUAL TESTING ENVIRONMENT:

SIMULATOR:

X PLANT SITE:

LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S):

1903.010 Chp. 037-03-0.1903.011.

Cha. 028-00-0 EXAMINEE'S NAME: SSN ---- EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY: PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1 JPM-SRO-EALQ Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The followina conditions exist: Unit One reactor has tripped one hour aao.

Reactor Buildina radiation levels are readina 190 Whr. RP reports radiation levels are 2000 mWhr from sample point SA-229. RB Sump level on L-1405 is steady at 60%. Aux. Bldo. Sump level on L-4403 is risina. Dirtv Waste Drain Tank T-2OAIB levels are aoina up. SE calculates an RCS leak rate of 60 aam. RDACS is indicatina an offsite release is in oroaress.

TASK STANDARD: Examinee correctlv classifies this event as a GE per EAL 1.7 and makes notifications to alant personnel per step 4 of 1903.011S.

TASK PERFORMANCE AIDS:

1903.010 Attachments 1 and 3. and 1903.01 1 ADMINISTRATIVE JOB PERFORMANCE MEASURE Page 3 of 4 INITIATING CUE: For the given plant conditions, determine the applicable EAL classification and initiate notifications through step 4 of the applicable Shifl Manager checklist in 1903.01

1. 2. Tum to appropriate EAL and Turned to a specific EAL in Safety compare EAL criteria with event System Function, Attachment 3 of conditions.

1903.010.

CRITICAL ELEMENTS (C) 3. 5 (C) 3. Declare the emergency classification. (C) Declared or stated the event is a GE based on EAL 1.7, Loss of or challenge to all three fission product barriers (not required to be stated). I I I I I I NOTE: Cue the examinee that the Unit 2 Shift Engineer is performing the initial notificat~ons per 1903011 after the examinee has stated that Untt 2 Shift Engineer (or control room communicator) has been requested.

+I I I I I PERFORMANCE CHECKLIST

1. Compare event conditions with the Index of EALs, Attachment 1 of 1903.010, Emergency Action Level Classification.

4. Initiate immediate notifications.

NIA STANDARD Turned to Attachment 1 of 1903.010, Index of EALs. Examinee should fill in the data on items 1 and 2. I I I 5. Begin completion of form 1903.011S, GE Emeqency Direction and Control Checklist for Shifl Manager. Examinee should simulate (or state) direction of the SE to complete the initial notification.

SAT --- Referred to 1903.01 1. Completed form 1903.01 1 S GE Emergency Direction and Control Checklist for Shifl Manager, thru step 4. UNSAT --- END 6. Inform Control Room Staff of Emergency Class declaration. Informed Control Room Staff of GE.

ADMINISTRATIVE JOB PERFORMANCE MEASURE Page 4 of 4 EXAMINEE'S COPY JPM INITIAL TASK CONDITIONS:

Unit One reactor has tripped one hour ago. Reactor Building radiation levels are reading 190 Whr. RP reports radiation levels are 2000 mWhr from sample point SA-229 RB Sump level on L-1405 is steady at 60%. Aux. Bldg. Sump level on L-4403 is rising. Dirty Waste Drain Tank T-20AlB levels are going up.

SE calculates an RCS leak rate of 60 gpm. RDACS is indicating an offsite release is in progress.

INITIATING CUE: For the given plant conditions, determine the applicable EAL classification and initiate notifications through step 4 of the applicable Shift Manager checklist in 1903.01 1.

Page 14 of 58 Page I of 2 NUE This form is intended to be used by the person with Emergency Direction and Control when a Notification of Unusuai Svent has been declared.

01. Nozification of Unusuai Event declared:

Unit ___ Time -- Date - **EMERGENCY CLASSIFICATION ANNOUNC-NT SHOULD BE MADE WITHIN 15 MINUTES OF THE DECLARATION**

02. EALN0.-

Description:

C]3. Notification Communicator 03.1 Single/Dual Unit Emergency

01. Activate CNS IF CNS already activated for an NUE emergency class, - THEN go to step 2 below. - Direct your unit's Shift Engineer to activate CNS in accordance with Attachment 9 of rhis procedure.

02. Direct the opposite unit Shift Engineer to perform notifications using Form 1903.011-Y, Emergency Class Initial Notification Message. 03.2 Additional Notification Communicator is Available IF a Notification Communicator is available, - THEN request the Notification Communicator to perform notifications in - accordance with Form 1903.011-Y, Emergency Class Initial Notification Message. 04. Inform the Control Room staff of the Emergency Class declaration

05. Make the foilowing announcement over the plant paging system (dial 197): "Attention all personnel. Attention all personnel. A Norification of Unusual Event has been declared on Unit - (One/Twe).

All personnel continue normal activities unless instructed otherwise." 05.; Dial 191 and repeat the above announcement.

05.2 .Yake the above announcement over the EOF Public Address System (dial 199 and pause approximately 15 seconds).

FORM TITLE: NUE EMERGENCY DIRECTION AND CONTROL CHECKLIST , FORM NO. 4903.01 1 J REV. 028-00-0 Page 15 of 55 Page 2 of 2 06. [IF on-site personnel hazards exist, THEN direct implementation of protective actions as necessary. - 06.1 Refer to Fonn 1903.030C, mLocalized Evaluation Checklist", to determine if a localized evacuation will be performed.]

07. an approach route to the plant site should be avoided, THEN instruct Security to direct incoming traffic. (Examples of this include - security situations in which onsite/offsite personnel are directed to the EOF, radiological releases that prohibit entry to the site via either guard station, etc.) 08. Direcr Chemistry personnel (Initial Dose Assessor) to implement procedure 1904.002, "Offsite Dose Projection - RDACS Computer Method". Performed by: - REV. 028-00-0 FORM TITLE. NUE EWlERGENCY DIRECTION AND CONTROL CHECKLIST FORM NO. 1903.01 1 J Page 1 of 2 ALERT This form is intended to be used by the person with Emergency Direction and Control when an Alert has been declared.

01. Alert declared: Unit Time Date **EMERGENCY CLASSIFICATION ANNOUNCEMENT SHOULD BE MADE WITHIN 15 MINUTES OF THE DECLARATION**

02. Conditions warranting declaration of an A;ert: EAL No.-

Description:

03. Notification Communicator 03.1 Single/Dual Unit Emergency

01. Activate CNS IF CNS already activated for an Alert or higher emergency class, - THEN go to step 2 below. - Direct your unit's Shift Engineer to activate CNS in accordance with Attachment 9 of this procedure.

q Use Section 8 of Attachment 9 if ERO is at risk due to site conditions (e.9. security event, toxic gas release, major onsite fire, etc). ERO will respond to rhe Aiternate EOF. q use Secrion 1 of Attachment 9 for normal ERO cailout. 02. Direct the opposite unit's Shift Engineer

e perform notifications using Form 1903.011-Y, Emergency Class Initial Notification Message. 03.2 Additional Notification Comunicator is Available

01. g a Notification Comunicator is available, THEN request the Notification Communicator to perform - notifications in accordance with Form 1903.011-Y, Emergency Class Initial Notification Message. 04. Inform the Control Room staff of the Emergency Class declaration.

05. Inform both units' operators in the field to log onto the Emergency RWP. 06. Make the fo1;owing announcement over the plant paging system (dial 197): "Attention all personnel. Attention all personnel.

An Alert Emergency Class has been declared on Unit (One/Two). Emergency response personnel report to your designated assembly areas. A;1 other personnel continue normal activities unless instructed otherwise." 06.1 Dial 197 and repeat the above announcement.

06.2 Make the above announcement over the EOF Public Address System (dial 199 and pause approximately 15 sec.) FORM TITLE: ALERT EMERGENCY DIRECTION AND CONTROL CHECKLIST FORM NO. 1903.011M REV. 028-00-0 Page 18 of 58 Page 2 of 2 El1 [IF on-site personnel hazards exits, THEN direct implementation of protective actions as necessary. - 07.1 Refer to Form 1903.030C, "Localized Evacuation Checklist", to determine if a localized evacuation will be performed.]

178. an approach route to the plant site should be avoided, THEN instruct Security 70 direct incoming traffic. (Examples of this include - security situations in which onsite/offsite personnel are directed to the EOF, radiological releases that prohibit entry to the site via secondary guard station, etc.) 09. Direct Chemistry personnel (Initial Dose Assessor) to the Control Room to implement procedure 1904.002, "Offsite Dose Prolection - RDACS Computer Metnod". Performed by: FORM TITLE: ALERT EMERGENCY DIRECTION AND CONTROL CHECKLIST FORM NO. 1903.01 1 M REV. 028-00-0 Page 20 of 58 Page 1 of 4 SAE This form is intended to be used by the SHIFT MANAGFJ7 when a Site Area Emergency has been deciared and the Shift Manager has the responsibility for Emergency Direction and Control. 01. Site Area Emergency declared:

Unit Time Date **EMERGENCY CLASSIFICATION

/ PLANT EVACUATION ANNOUNCEMENT SHOULD BE MADE WITHIN 15 MINUTES OF THE DECLARATION**

02. EAL No.-

Description:

133. Notification Communicator 173.1 Single/Dual Unit Emergency

01. Activate CNS IF CNS already activated for an Alert or higher emergency class, - THEN go to step 2 below. - Direct your unit's Shift Engineer to activate CNS in accordance with Attachment 9 of this procedure.

C1 Use Section 8 of Attachment 9 if ERO is at risk due to size conditions (e.g. security event, toxic gas release, major onsite fire, etc). ERO will respond to the Alternate EOF. C1 Use Section 1 of Attacnmenr 9 for normal ERO callout. 02. Direct the opposite unit's Shift Engineer to perform notifications using Form 1903.011-Y, Emergency Class Initial Notification Message. 03.2 Additional Notification Communicator is Available 0;. IF a Notification Communicator is available, THEN request the Notification Communicator to perform - notifications in accordance with Form 1903.0il-Y, Emergency Class Initial Notification Message.

04. Inform the Control Room staff of the Emergency Class declaration REV 028-00-0 FORM TITLE SAE EMERGENCY DIRECTION AND CONTROL CHECKLIST SHIFT MANAGER FORM NO 1903.011P Page 21 of 58 ?age 2 of 4 05. Has a plant evacuation been performed?

NO - GO step 6. q YES - perform the following announcement:

OA. Dial 197 03. Make the following announcement: "Attention all personnel, Attention all personnel. A Site Area Zmergency has been declared on Unit - (One/Two) . Emergency response personnel report to your designated assembly areas." OC. Dial 197 and repeat the above announcement OD. Repeat the above announcement using the EOP public address system by dialing 199 and pausing approximately 15 seconds before making the announcement.

OE. c;o TO step 15. Plant Evacuation Section 06. Determine the appropriate evacuation routes:

06.1 DOES a radiological or toxic gas release exist or is a release suspected, which is originating from the plant? q YES - THEN determine the available routes from the chart below using wind direction.

IF wind direction is From: - THEN use Evacuation Routes - 0 to 100 degrees C] 1 and 2 101 to 220 degrees 22: to 359 degrees q 1 Clz NO - THEN use routes 1 and/or 2. 06.2 Check the appropriate routes in the plant announcement Step iO below. 07. Determine any areas of the plant to avoid during evacuation or special protective measures to be taken by plant evacuees.

08. Direcx Security to perform the following (ext. 3388, 3108 or 3109): 08.1 Use manual scanning to expedite evacuation, if necessary.

08.2 Perform initial accountability by (Time) (30 minutes from SAE declaration)

FORM TITLE: SAE EMERGENCY DIRECTION AND CONTROL CHECKLIST SHIFT MANAGER FORM NO. 1903.011P REV. 028-00-0 Page 22 of 58 Page 3 of 4 09. Contact Radiation Zrotection (CAI - 5166 or CA2 - 3018): 09.1 Request Health Physics coverage a: the planr exit porcal monitors.

09.2 Instruct Health Physics personnel at the controlled access exit point to relax decontamination and radiation protection measures as necessary in order to expedite evacuation of the controlled access area. 010. [Make the following announcement using the plant paging system (dial 197): "Attention all personnel.

Attention all personnel.

A Site Area Emergency has been declared on Unit -(One/Two). Emergency response and emergency standby personnel report to your designated assembly areas and perform initial accountability. All other personnel evacuate the plant using evacuation route(s) C] 1 C] 2 and proceed to the Atkins Emergency Worker Center." If necessary, include in the announcement any plant areas to avoid, or special protective actions to be taken by plant evacuees:

010.1 Sound the evacuation alarm for approximately 10 seconds. C]10.2 Repeat the announcement at least 2 times, alternating the announcement with the plant evacuation alarm.] 11 Make the foILowing announcement using the EOF public address system (dial 199 and pause approximately 15 seconds). "Attention ail personnel. Attention all personnel.

A Site Area Emergency has been declared on Unit - (One/Two). Emergency response personnel report to your designated assembly areas. n12. instruct all Control Room personnel (operators, chemists, RP, etc.) to log into the designated security card reader using "0000".

m13. Instruct both units' operators in the field to log into the nearest security card reader using "0000" and log onto the emergency RWP. m14. Inform the opposite unit Control 3oom personnel to iog into the designated security card reader using "0000".

FORM TITLE: SAE EMERGENCY DIRECTION AND CONTROL CHECKLIST SHIFT MANAGER FORM NO. 1903.011P REV. 028-00-0 Page 23 of 58 Page 4 of 4 015. the incident extends into the Exclusion Area, THEN consider an Exclusion Area Evacuation. Perform the following if an - Exclusion Area Evacuation is deemed necessary:

Ui5.1 Request that the u.S. Army Corps of Engineers (teiephone number located in Zzergency Telephone Directory) control boat access to the portions of Lake Dardanelle within the exclusion area.

015.2 Direct Security to evacuate tne Generation Support Building (GSB) and all buildings outside the security fence but within the exclusion area. Plant Evacuation Section Ends 016. Direct Chemistry personnel (Initial Dose Assessor) to the Control Room to implement procedure 1904.002, "Offsite Dose Projection - RDACS Computer Yethod". 017. IF an approach route to the plant site should be avoided, THEN instruct Security to direct incoming traffic. (2xamples of this inciude - security situations in which onsite/offsite personnel are directed to the EOF, radioiogicai releases that prohibit entry to the site via secondary guard station, etc.) Serfcrmed by: Shift Manager FORM TITLE. SAE EMERGENCY DIRECTION AND CONTROL CHECKLIST SHIFT MANAGER FORM NO. 1903.01 1 P REV. 02850-0 Page 30 of 58 2age 1 of 4 This form is intended to be used by the SHIFT blANAGER when a General Emergency has been declared and the Shift Manager has the responsibility for emergency Direction and Control. 01. General Emergency declared:

Unit Time Date **EMERGENCY CLASSIFICATION

/ PLANT EVACUATION ANNOUNCl?XENT SHOULD BE MADE WITHIN 15 MINUTES OF THE DECLARATION**

02. Condltrens warranting declaration of a General Emergency:

EAL No.-

Description:

- 03. Notrficatlon Communicator 03.1 Single/Dual Unit Emergency

01. Activate CNS IF CNS already activated for an Alert or higher emergency class, - THEN go to step 2 below. - Direct your unit's Shift Engineer to activate CNS in accordance with Attachment 9 of this procedure.

17 Use Section 8 of Attachment 9 if ERO is at risk due to site conditions (e.g. security event, toxic gas release, major onsite fire, ctc). ERO will respond to the Alternate EOF. 17 Use Section 1 of Attachment 9 for normal ERO callout. 02. Direct the opposite unit's Shift Engineer to perform notifications using Form 1903.011-Y, "Emergency Class Initial Notification Message." 03.2 Additional Notification Comunicator is Available

01. IF a Notification Communicator is available, THEN request the Notification Com~unicator to perform notifications in - accordance with Form 1903.011-Y, "Emergency Class Initial Notification Message. " 04. Inform the Control Room staff of the Emergency Class declaration.

I GE EMERGENCY DIRECTION AND CONTROL CHECKLIST I 1903.OllS I 028404 I SHIFT MANAGER Page 31 of 58 ?age 2 of 4 175. Has a plant evacuation been performed, No - GO TO Step 6 C1 YES - THEN perform the following:

CIA. Dial 197 EB. Make the following announcement: "Attention all personnel.

Attention all personnel. A General Emergency has been declared on Unit -(One/Two).

Zmergency response personnel report to your designated assembly areas." UC. Dial 197 and repeat the above announcement.

OD. Repeat the above announcement using the ZCF pubbiic address system by dialing 199 and pausing approximately 15 seconds before making the announcement.

OZ. GO " step 15. Plant Evacuation Section

06. Deternine the appropriate evacuation routes: 06.1 a radiological or coxic gas release exist or is a release suspected, which is originating from the plant? C] YES - THEN determine the available routes from the chart below uslng wlnd direction.

IF wind direction is From: - - THEN use Zvacuation Routes 0 to 100 degrees C] 1 and 2 101 to 220 degrees 221 to 359 degrees 1 2 C] - EN use routes 1 and/or 2 06.2 Check the appropriate routes in the plant announcenen:, step 10 below. 07. Determine any areas of the plant to avoid during evacuarion and/or special protective measures to be taken by plant evacuees. List these instructions in plant announcement Step 10 below. 08. Direct Security to perform the following (ext. 3388, 3108 or 3109): 08.1 Use manual scanning to expedite evacuation, if necessary.

08.2 Perform initial accountability by (Time) (30 minu:es from GE declaration)

FORM TITLE: GE EMERGENCY DIRECTION AND CONTROL CHECKLIST SHIFT MANAGER FORM NO. 1903.011S REV. 028-00-0 Page 32 of 58 Page 3 of 4 09. Contact Radiation Protection (CAI - 5166 or CA2 - 3018): 09.1 Request Heaith Physics coverage at the plant exit portal monitors.

09.2 Instruct Health Physics personnel at the controlled access exit point to relax decontamination and radiation protection measures as necessary in order to expedite evacuation of the controlled access area.

010. [Make the following announcement using the plant paging system (dial 197): "Attention all personnel.

Attention all personnel.

A General Emergency has been declared on Unit -(One/Two).

Emergency response and emergency standby personnel report to your designated assembly areas and perform initial accountability.

All other personnel evacuate the plant using evacuation route(s) q 1 q 2 and proceed to the Atkins Emergency Worker Center." If necessary, include in the announcement any plant areas to avoid, or special protective actions to be taken by plant evacuees:

m10.1 Sound the evacuation alarm for approximately 10 seconds 010.2 Repeat the announcement at least 2 times, alternating the announcement with the plant evacuation alarm.]

nil. Make the following announcement using the EOF public address system (dial 199 and pause approximately 15 seconds). "Attention all personnel. Attention all personnel. A General Emergency has been declared on Unit - (One/Two). Emergency response personnel report to your designated assembly areas." 012. Instruct all Control Room personnei (operators, chemists, RP, etc.) to log into the designated security card reader using "0000". 013. Instruct both units' operators in the field co log into the nearest security card reader using "0000" and log onto the emergency RWP. 014. Inform the opposite unit Control Room personnel to log into the designated security card reader using "0000".

I SHIFT MANAGER I I I FORM TITLE: FORM NO. GE EMERGENCY DIRECTION AND CONTROL CHECKLIST 1903.011S REV. 028-00-0 Page 33 of 58 Page 4 of 4 Qi5. Has an exclusion area evacuation been performed?

YES - GO TO Step 16 C1 9 - THEN perform the following:

C] Xequest that the U.S. Army Corps of Engineers (telephone number located in Emergency Telephone Directory) control boat access to the portions of Lake Dardanelie within the exciusion area. C] Direct Security to evacuate the Generation Support auilding (GSBI and all buildings outside the security fence but within the exciusion area. Plant Evacuation Section Ends 016. Determine the appropriate Protective Action Recornvendation using Attachment 6, "Protective Action Recommendations (PAR) for General Emergency".

PAR No. Review PAR criteria every 15 minutes. Notify within 15 minutes the NRC, State and local government of PAR changes in accordance with Form 1903.011-Y, "Emergency Class Initial Notification Xessage." 017. Direct Chemistry personnel (Initial Dose Assessor) to the Control Room to implement procedure 1904.002, "Offsite Dose Prolection - RDACS Computer Method" 018. IF an approach route to the plant site should be avoided, THEN instruct Security to direct incolainq traffic. (Examples of this include 7 security situations in which onsite/offsite personnel are directed to the EOF, radiological releases which prohibit entry to the site via secondary guard station, etc.1 Performed by: Shift Manager REV. 028-00-0 FORM TITLE: GE EMERGENCY DIRECTION AND CONTROL CHECKLIST SHIFT MANAGER FORM NO. 1903.01 IS ES-301 Control Room 1 in Plant Systems Outline Form ES-301-2 ES-301, Page 23 of 27 Date of Examination:

911212005 Reactor Pressure @All control room (and in-plant) systems must be different and serve different safety functions; Type Codes (Aftternate path (C)ontroi room @)direct from bank (E)mer$ency or abnormal in-plant (L)ow-Power (N)ew or (M)odifted from bank including 1(A) (P)revious 2 Exams WC.4 (S)imulator Criteria for RO ISRO-i / SRO-U 4-6 I 46 / 2-3 $9 158 / 64 21 121 12.1 21 I21 I 21 22 122 1 21 6 3 / s 3 / 5 2 (randomly selected) 21 121 i 21 ES-301 - Control Room 1 in Plant Systems Outline Form ES-301-2 ES-301, Page 23 of 27 Facili: ANO-1 Date of Examination:

9/12/2005 Exam Level (circle one): RO i Operating Test No.: One -- Control Room systemsa ( 8 for RO; 7 for SRO-I; 2 or 3 for SRO- U) Safety Function System 1 JPM Title 002 K4.10 RO 4.21SRO 4.4 (D)direct from bank 59 / 58 1 54 21 I21 12% 21 / 21 / 21 22 / 22 / 21 5 3 / 5 3 / 5 2 (randomly selected) 21 121 1 21 Type Code.

ES-301 Control Room I in Plant Systems Outline Fom ES-301-2 Date of Examination:

911212005 002 K4.10 RO 4.21SRO 4.4 h9 / 58 1 54 (E)rnergency or abnormal in-plant 21 121 1 21 ES-30$, Page 23 of 27 Page 1 of 5 TUOI NUMBER:

AIJPM-RO-EOP22 JOB PERFORMANCE MEASURE Unit: 1 Rev # 0 Date: System/Duty Area: Emergency and Abnormal Operations Task: Emergency Boration JA# AN0 1 -RO-EOP-EMERG-55 KAValueRO 4.0 SRO 4.6 KA Reference 007 EK3.01 Approved For Administration To: RO (Xi SRO Task Location:

Inside CR: (Xi Outside CR: Both: Suggested Testing Environment And Method (Perform Or Simulate #): Plant Site:

Simulator#:

Perform Lab: Position Evaluated:

RO: SRO: Actnal Testing Environment: Simulator

1. Plant Site:

Lab Testing Method: Simulate:

Perform: Approximate Completion Time In Minutes: 10 Minutes Reference@): 1202.012, Repetitive Tasks, 004-034 Examinee's Name: SSN: Evaluator's Name:

The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be: Satisfactory:

Unsatisfactory: Performance Checklist Comments: Start Time Stop Time Total Time Signed # Date: # TQ-202 attachment 9 is complete and on file for performance of this JPM for the current Reactor core configuration. Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

TUOI NUMBER: AlPM-RO-EOP22 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE: The examiner shaIl review the "Briefing ChecMist - System WaLkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Two control rods failed to lnsett upon a reactor trip, CRD AC breakers did trip and the CRD Power Supply Breaker PBs on C03 have been depressed.

TASK STANDARD: Boric acid is being injected into the RCS by the operating HPI pump from the BWST. This is an Alternate Success Path JPM. TASKPERFORMANCE AIDS: 1202.012, RT-12, Emergency Boration NOTE: This is an Alternate Success Path JPM infended to be performed, not simulated NOTES TO IA OPERATOR AND EAYMINER:

I. P-36C or B on the A-4 side musr be the operating HPIpump, withP-36A the ES pump. 2. Fail CV-1250 in the closedpodtion; this forces the alternate option for Emergency Boration TUOI NUMBER: AlJPM-RO-EOP22 INITIATING CUE: The CRSISM directs you to perform Emergency Boration per RT-12. CRITICAL ELEh4ENTS (c): 4,6,8 C PERFORMANCE CHECKLIST

1. Set Batch Controller for maximum hatch size (999999).

POSITIVE CUE: Batch Controller set to add 999999 gallons.

2. Verlfy Condensate to Batch Controller (CV-1251) closed. POSITIVE CUE: CV-1251 green light on. 3. Open CV-1250. FAULTED CUE:

CV-1250 green light on and red light off EXAMINER NOTE: Examinee should now transition to RT-2, Initiate BPI. STANDARD Batch set key depressed, 999999 gallons batch size set by depressing appropriate number keys. Depressed enter and lower display keys in sequence (red LED next to display key should be on.). On C04, verified CV-1251 closed.

On C04, attempted to open CV-1250; identified that CV-1250 failed to open. C C N/A - 4. Open BWST outlq CV-1408. PosInvE CUE: CV-1408 red light on. 5. Place RCP Seal Inj. Block (CV-1206) in override.

POSITIVE CUE: CV-1206 in OW. 6. mN BWST Outlet is open, THEN open WI Block valve (CV-1285) to maintain PZR level 200 to 220. POSITIVE CUE: CV-1285 red light on. EXAMINER NOTE: Examinee should now return to RT-12, Emergency Boration.

SAT - --- --- At C-16, opened CV-1408. At C04, placed CV-1206 in OW. On C-16, opened CV-1285. 7. Place 3-way valve (CV-1248 in BLEED) POSITIVE CUE: CV-1248 blue light on, red light off.

UN SAT - --- --- --- On C04, placed CV-1248 in the BLEED position ---

TUOI NUMBER: AlJPM-RO-EOP22

/ EXAMMER NOTE: If PZR level is less than loo", inform examinee that PZR level is 110", slowly rising.

1 I I NEGATIVE CUE: Letdown flow is 40 gpm C I I I I I NOTE: TerminateJPM when maximum Letdown flow is established.

8. When PZR level is 2100, THEN establish maximum Letdown flow.

POSITIVE CUE: Letdown flow is 80 gpm. On C04, placed a second Letdown filter in service and adjusted CV- 1223 to raise Letdown flow to at least 80-100 gpm. - - -

TUOI NUMBER: AlJPM-RO-EOP22 INITIAL CONDITIONS: Two control rods failed to insert upon a reactor trip, CRD AC breakers did trip and the CRD Power Supply Breaker Trip PBs on C03 have been depressed. INITIATING CUE:

The SMJCRS directs you to perform Emergency Boration per RT-12 ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLWR ONE CHANGE NO 004-03-0 TC EXP DATE NIA IPTE DYES @NO TITLE REPETITIVE TASKS SET # When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShifVLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME r' FORM TITLE: I FORM NO. I CHANGE NO. VERIFICATION COVER SHEET I 1000.006A 1 050-00-0 DOCUMENT NO 1202.012 WORK PLAN EXP DATE NIA SAFETY-RELATED YES NO TEMP ALT DYES (XINO Page 1 of 3 12. Emergency Boration:

A. IF Boric Acid pump (P39A or B) and Batch Controller are available, THEN perform the following: - 1) Set Batch Controller for maximum batch size (999999).

2) Verify Condensate to Batch Controller (CV-1251) closed. 3) Open Batch Controller Outlet (CV-1250).

4) Verify both Letdown Filters in service (F-3A and 8). 5) Record initial BAAT (T-6) level in. 6) Start available Boric Acid Pump(s) (P-39A or B or both).

7) Start Batch Controller by depressing RUN key. 8) Adjust Batch Controller Flow CNTRL VLV (CV-1249) to 100% open.

9) Adjust Pressurizer Level Control Setpoint to 220". 10) Open BWST Outlet to OP HPI Pump (CV-1407 or 1408). 11) WHEN PZR level is 2 loo", THEN establish maximum Letdown flow.

12) Perform the following as necessary to maintain MU Tank level 55 to 86. a) Close Batch Controller Outlet (CV-1250).

b) Stop running Boric Acid Pump(s) (P-39A, P39B). c) Place 3-Way valve in BLEED. d) WHEN MU Tank level is lowered to desired level, THEN perform the following:

(1) Return 3-Way valve to LETDOWN. (2) Start available Boric Acid Pump(s) (P-39A or B or both).

(3) Open Batch Controller Outlet (CV-1250).

(12, CONTINUED ON NEXT PAGE)

Page 2 of 3 12. (Continued).

13) As time permits, determine actual required boration as follows: a) Obtain required boron concentration from the Plant Data Book PP~B. b) Calculate batch add required using Plant Computer OR ~olub~~oison Concentration Control (1 103.004), Attachment A.3, "Calculation of Feed Volume For Batch Boration or Dilution".

gal c) Use 1103.004, Attachment D, 'Volume of BAAT vs. Depth of Liquid" to determine desired final BAAT level.

in 14) WHEN required amount of boric acid has been added per step 13) OR as determined by Reactor Engineering, THEN perform the following:

a) Stop Boric Acid pump (P39A and 8). b) Close Batch Controller Outlet (CV-1250) c) Verify MU Tank level 55 to 86 AND close BWST Outlet to OP HPI pump (CV-1407 or 1408). d) Adjust Letdown flow to desired rate. (12. CONTINUED ON NEXT PAGE)

12. (Continued) Page 3 of 3 B. IF no Boric Acid pumps are available (P39A or B), OR ~atch~ontroller is p& available, THEN perform the following: - 1) Initiate HPI (RT 2) perform the following:

a) Open HPI Block valve (CV-1220 or 1285) associated with running HPI Pump to maintain PZR level 200 to 220. 2) Place BWay valve in BLEED. 3) WHEN PZR level is 2 100, THEN establish maximum Letdown flow.

4) As time permits, determine actual required boration as follows: a) Obtain required boron concentration from the Plant Data Book PPmB b) Calculate final BWST level for required boron addition using Plant Computer OR ~olubie Poison Concentration Control (1 103.004), Attachment A.6. "Continuous Feed and Bleed from BWST". n. 5) WnEN required amount of boric acid has been added per step 4) OR as determined by Reactor Engineering, THEN perform the following:

a) Operate HPI as directed by CRS. b) Adjust Letdown flow as directed by CRS END JOB PERFORMANCE MEASURE UNIT : 1 REV # 2 DATE : TUOI NUMBER: A1JPM-RO-LTOP1 SYSTEM/DUTY ARFA: REACTOR COOLANT SYSTEM TASK: ESTABLISH LTOP PROTECTION DURING COOLDOWN OF THE RCS JTA#: ANO1-RO-RCS-NORM-2 KA VALUE RO: 4.2 SRO: 4.4 KA

REFERENCE:

002 K4.10 APPROVED FOR ADMINISTRATION TO:

RO: X SRO: X TASK LOCATION:

INSIDE CR: X OUTSIDE CR: BOTH : SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: PERFORM LAB: POSITION EVALUATED:

RO: SRO: ACTUAL TESTING ENVIRONMENT:

SIMULATOR: PLANT SITE:

LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 10 MINUTES REFERENCE(S):

1102.010 Chg. 053-11-0 EXAMINEE'S NAME: SSN - - EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE: SAT1 S FACTORY : UNSATISFACTORY: PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE : SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

TUOI NUMBER: AIJPM-RO-LTOP1 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is in a cooldown with RCS temperature

<300°F but >275"~. RCS pressure as indicated on PT-1020 "A" LOOP WR Pressure (ESAS-1) is Less than 380 psig. TASK STANDARD:

LTOP established with all HPI MOVs in the LTOP position and ERV block open and ERV setpoint switch in the 400 psig position. TASK PERFORMANCE AIDS: 1102.010 Step 10.2 Simulator setup: On PMS establish Mode 3 in PMA.

TUOI NUMBER:

AlJPM-RO-LTOPI INITIATING CUE: The SM/CRS directs you to establish LTOP protection as per step 10.2 1102.010. CRITICAL ELEMENTS (C) : 2, 6 (C) (C1 PERFORMANCE CHECKLIST

1. Verify RC pressure is 1380 psig. POSITIVE CUE: RC pressure is 360 psig. 2. Place ERV Setpoint hand switch in 400 PSIG position.

POSITIVE CUE: 400 PSIG amber light lit.

NEGATIVE CUE: 2450 PSIG white light lit. 3. Verify the ERV Isolation (CV-10001 open. POSITIVE CUE:

red light ON, green light OFF. NEGATIVE CUE: green light ON, red light OFF. 4. If the plant computer is operating, verify the following LTOP alarm plant computer points are do not have a quality of DEL: RCS Loop "A" Inlet Temperature Wide Range T1016 and Tl017 LTOP Trouble Alarm T3071 RCS Overpressurization Enable PS3086 LTOP Constant (272 "F) CON272 . POSITIVE CUE: T1016, T1017, T3071, PS3086, CON272 are not deleted. STANDARD Verified pressure 1380 psig on as indicated on PT-1020 On C04, positioned the ERV setpoint hand switch to the 400 PSIG position.

On C04, verified CV-1000 in the open position by observing red light ON, green light OFF above HS- 1000. On the plant computer, used SVD function and selected T1016, T1017, T3071, PS3086 and CON272 and verified that each point does not have a quality of DEL. N/A - SAT --- - --- --- UNSAT -

TUOI NUMBER: AlJPM-RO-LTOP1 (c) 1 PERFORMANCE CHECKLIST I STANDARD / N/A I SAT / UNSAT 5. Verify pressurizer level is between 70" and 95". POSITIVE CUE: Pressurizer level is 85". I with white lights OFF. CV-1278 CV-1227 CV-1279 CV-1228 11 Verified Pressurizer level between 70 to 95" on level indicators located on C04. 6. Close the following HPI MOVs and place in the LTOP position (may be done in any order) : POSITIVE CUE: green lights ON for all valves, white LTOP in 1 EXAMINER NOTE: If trainee asks, inform that Pressurizer level is being plotted and RCS cooldown rate is within the specifications of Att. 3. I I I I I On C16 and C18, verified each HPI valve closed and placed key switch for each valve in the LTOP position "NORMAL,, lights OFF for all valves. NEGATIVE CUE: red light ON or white LTOP in "NORMAL" light ON for any applicable mispositioned valve/key switch. EXAMINER NOTE: Inform trainee that it is not desired to unprotect Pressurizer level computer points. END TUOI NUMBER: AlJPM-RO-LTOP1 INITIAL CONDITIONS:

The plant is in a cool down with RCS temperature

<300°F but >275'F. RCS pressure as indicated on PT-1020 "A" Loop WR Pressure (ESAS-1) is less than 380 psig. INITIATING CUE: The SM/CRS directs you to establish LTOP protection as per step 10.2 1102.010.

ENTERGY OPEFWTIONS INCORPORATED ARKANSASNUCLEARONE CHANGE NO 053-114 TC EXP. DATE NIA IPTE DYES NNO 'TITLE PLANT SHUTDOWN AND COOLDOWN SET # DOCUMENT NO. 1102.010 WORK PLAN EXP DATE N/A SAFETY-RELATED BYES ON0 TEMP ALT DYES BNO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/lntermption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiiLast Shift Knowledge Peer Pressure Procedures ChangeiOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: VERIFICATION COVER SHEET FORM NO. 1000.006A CHANGE NO. 05090-0 10.0 Establishing Decay Heat Removal System Operation PROC.lWORK PLAN NO. 1102.010 10.1 IPgoingtoMode5, THEN implement Containment Closure Control per Decay Heat Removal and LTOP System Control (1015.002).

Attachment G prior to placing plant in a condition where containment integrity is not required.

10.1.1 Complete Attachment G of 1015.002 for applicable valves listed in Category E/Locked Component Log (E-doc 1015 .OOlHl . PROCEDURElWORK PLAN TITLE: PLANT SHUTDOWN AND COOLDOWN i4.3.2) 10.2 WHEN RC temperature is <300°F but >27S°F, THEN verify RC pressure is S380 psig as indicated on - PT-1020 (SPDS P1020) and establish LTOP protection as f ollows : PAGE: 31 of 80 CHANGE: 053-1 1-0 10.2.1 Place ERV Setpoint hand switch in 400 PSIG position.

10.2.2 Verify ERV Isolation (CV-1000) open . 10.2.3 - IF the plant computer is operating, THEN verify by using computer function SVD or OD - (LTOP) that the following LTOP alarm plant computer points do have a quality of DEL. RCS Loop "A" Inlet Temperature Wide Range (TI016 and T1017) . LTOP TROUBLE Alarm (T3071) RCS Overpressurization Enable (PS3086) LTOP Constant (272-8) (CON2721 10.2.4 - IF the plant computer is NOT operating, T5N contact Computer Support to enable LTOP - alarm.

NOTE - For LTOP concerns, maximum allowable Pressurizer level with RCS temperature c27Z0F Reactor Vessel head in place is: - <105" at RCS pressures

,100 psig - SI.50" at RCS pressures

<I00 psig PROC.MIORK PLAN NO. 1102.010 Annunciator "LTOP Trouble" (K09-E71 alarms at the following Pressurizer level setpoints with RCS temperature

<27Z°F: I - 95" at RCS pressures

,100 psig - 140" at RCS pressures 5100 psig PROCEDUREWORK PLAN TITLE: PLANT SHUTDOWN AND COOLDOWN 10.2.5 Verify Pressurizer level is between 70' and 95". PAGE: 32 of 80 CHANGE: 053-1 1-0 10.2.6 Monitor and plot Pressurizer level vs.

time during cooldown at least once every 15 minutes while RCS temperature is 5272-F (SR 3.4.11.1) . 10.2.7 Limit RCS cooldown rate as necessary to maintain RCS temDerature above and to the riaht of the RCS Functional Specification curve,- Attachment J. 10.2.8 For each of the followina HPI to P-32(A. B. C. or D) Discharge valves, close valve and'place key switch in LTOP position.

10.2.9 - IF desired, THEN contact Computer Support to unprotect the alarm functions on the plant computer for PZR Level (L1001B and L1002B). A. WHEN unprotected, THEN adjust setpoints below current LTOP requirements. N/A if not performed.

NOTE - RCS maximum cooldown rate from 28O0F to 150'F is 50°F/hr, which equates to O.133~F/min.

10.3 Prior to cooling below 280°F, establish a cooldown rate of - S50°F/hr.

JOB PERFORMANCE MEASURE Page 1 of 5 UNIT: I REV # 1 DATE: TUOI NUMBER: A1JPM-RO-RCPO5 SYSTEM/DUTY AREA: REACTOR COOLANT PUMP SYSTEM TASK: Shutdown P-32C & D after DH in service. - JTA#: ANO1-RO-RCP-NORM-3 KAVALUE RO: 2.8 SRO: 2.5 KA

REFERENCE:

003 A4.03 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR:

X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR:

PERFORM LAB: POSITION EVALUATED:

RO: SRO: ACTUAL TESTING ENVIRONMENT: SIMULATOR:

PLANT SITE: LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 20 MINUTES REFERENCE(S):

1102.010 Chg. 053-11-0, 1103.006 Chg. 025-04-0 EXAMINEE'S NAME: SSN - - EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY: PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JOB PERFORMANCE MEASURE Page 2 of 5 TUOI NUMBER: AlJPM-RO-RCP05 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of 1064.023 Attachment 6 with the examinee.

JEW INITIAL TASK CONDITIONS:

Plant cooldown is in progress.

'A" DHR is in service. "C" and "D" RCPs are operating. Hot leg cooling is no longer required.

RCS is at the desired boron concentration. Predictive maintenance is standing by. TASK STANDARD: "C" and 'D" RCPs off and cooldown on DH commenced.

TASK PERFORMANCE AIDS: 1102.010 and 1103.006.

ADMINISTRATION NOTE: Ensure 1102.010 procedure has T-cold temperature recorded for simulator conditions.

JOB PERFORMANCE MEASURE Page 3 of 5 TUOI NUMBER: A1JPM-RO-RCP05 INITIATING CUE: The SM/CRS dlrects you to stop "C" and "D" RCPs usrng "A" DHR loop in accordance with 1102.010, step 10.15.6. Steps 10.15.1 through 10.15.5 have been completed.

CRITICAL ELEMENTS (C): 1, 2, 4 UNSAT - - - - - SAT - - - - -~-~~ - - - - - STANDARD N/A On C-14/C-18, adjusted DH cooler bypass/outlet valves until DH cooler outlet temperature was between 10 "F to 15 'F below T-cold value recorded in previous step. Started HP Oil Lift Pumps (P-63), Emergency HP Oil Lift Pumps (P-80), and Backup Backstop Lube Oil Pumps (P-82) for "C" and 'D" RCPs by placing handswitches on C-13 to the start position.

On C-13, verified Backstop Lube Oil Pumps (Pal) running for

'C" and "D" RCPS. Stopped "C" and 'D" RCPs by placing the handswitches on C-13 to the stop position. Last RCP was stopped within two minutes of stopping (C! (C! (C) (C) PERFORMANCE CHECKLIST

1. Establish DH cooler outlet temp 10 to 15 OF below T-cold temp. POSITIVE CUE: DH Cooler outlet temperature is 10°F to 15 OF below T- cold temp. 2. Start HP Oil Lift Pump, Emergency HP Oil Lift Pump, and Backup Backstop Lube Oil Pumps for "C" and 'D" RCPs . POSITIVE CUE: HP Oil Lift Pumps and Backstop Lube oil Pumps red lights ON green lights OFF. 3. Verify Backstop Lube Oil Pumps running for "C" and 'D" RCPs . POSITIVE CUE: Backstop Lube Oil Pumps red lights ON, green lights OFF. 4. Stop RCP s. POSITIVE CUE:

'C" 'D" RCPs green lights ON red lights OFF. - 5. Verify HP Oil Lift Pumps and Backstop Lube Oil Pumps remain on during RCP coastdown.

POSITIVE CUE: HP Oil Lift Pumps and Backstop Lube Oil Pumps red lights ON green lights OFF. Verified HP Oil Lift Pumps and Backstop Lube Oil Pumps remain on during RCP coastdown. -

JOB PERE'ORMANCE MEASURE Page 4 of 5 END without reverse rotation rotation. POSITIVE CUE:

maintenance. Predictive maintenance reports shaft is stopped.

7. When shaft has stopped, stop ail oil pumps for the idle RCP. POSTTIVE CUE: "C" and "D" oil pumps red lights OFF and green lights ON. 8. While RCS is

>I50 OF, maintain seal injection flow and ICW flow to RCP Seal Cooling Water Heat Exchangers.

POSITIVE CUE: Seal injection and seal cooling is being maintained.

9. Maintain ICW flow to RCP Motor Air Coolers. POSITIVE CUE: RCP motor cooling is being maintained.

10. After RCP coast-down, record DH cooler outlet temperature.

POSITIVE CUE: DH cooler outlet temperature is 204 OF. 11. Verify step change is

<15'F: CET temperature (step 1) minus DH cooler outlet temperature. POSITIVE CUE:

Step change is <15 OF. Rcs loop flow indication Plant computer reverse rotation alarm remains clear. Stopped all oil pumps for "C" and 'D" RCPs by placing the handswitches on C-13 in the PULL-TO- LOCK position. Verified seal injection flow and ICW flow to RCP Seal Cooling Water Heat Exchangers. Verified ICW flow to RCP Motor Air Coolers. Recorded DH cooler outlet temperature in step 10.15.6 of 1102.010. Verified step change was <I5 OF and recorded step change in 1102.010. - - - - - - - - - - - - - - -

JOB PERFORMANCE MEASURE Page 5 of 5 TUOI NUMBER:

AlJPM-RO-RCPO5 JPM INITIAL TASK CONDITIONS:

Plant cooldown is in progress. "A" DHR is in service. "C" and "D" RCPs are operating. Hot leg cooling is no longer required.

RCS is at the desired boron concentration. Predictive maintenance is standing by. INITIATING CUE:

The SM/CRS directs you to stop 'C" and "Do RCPs using "AN DHR loop in accordance with 1102.010, step 10.15.6. Steps 10.15.1 through 10.15.5 have been completed.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE CHANGE NO 053-1 1-0 TC EXP DATE NIA IPTE WES HNO . 'TITLE PLANT SHUTDOWN AND COOLDOWN SET # DOCUMENT NO 1102.010 WORK PLAN EXP DATE NIA SAFETY-RELATED NYES ON0 TEMP ALT DYES BNO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Dlstraction/lnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM IIRE: VERIFICATION COVER SHEET FORM NO. 1000.006A CHANGE NO. 050-00-0

- If the RCS is to be opened after cooldown, it is desirable to run the RCPs in parallel with the Decay Heat system to cool the RCS hot legs. This helps to prevent flashing in the hot legs when the RCS is depressurized.

RCP NPSH limits of Att. A must be met during RCP and DH system parallel operation.

PR0C.WORK PLAN NO. 1102.010 RCPs should be secured together or as near together as feasible 10.15 WHEN CET temperature is between 166°F and 270°F AND when cooling RCS hot legs is no longer desired, THEN secure RCPs as follows: -- PROCEDUREWORK PLAN TITLE: PLANT SHUTDOWN AND COOLDOWN 10 15.1 IF performed, - THEN verify Acid Reducing Phase of the Reactor - Coolant Shutdown Chemistry per RCS Shutdown PAGE: 36 of 80 CHANGE: 053-11-0 Chemistry Program (1604.050i complete 10.15.3 Verify RCS at final desired boron concentration. - 10.15.4 Record T-cold temperature used - for plotting cooldown rate: OF 10.15.5 Stop RCS cooldown. - L CAUTION If in Mode 5 and adequate margin does not exist to 200°F RCS temperature, an unexpected mode change may occur when DH cooler outlet temperature is adjusted to <15OF below T-cold temperature.

NOTE P Plant Computer points T1406 and T1407 are the most accurate indication of DH cooler outlet temperature and should be used when available.

10.15.6 The following steps should be performed expeditiously to minimize RCS heatup: A. Prior to stopping RCPs, adjust DH cooler - outlet temp to c15OF below T-cold temp used for plotting cooldown rate. B. Stop both RCPs per Reactor Coolant Pump - Operation (1103.0061, "RCP Stop' section. C. Record DH cooler - outlet temperature OF.

NOTE - Step change limit of s1S0F is applicable only during transition from RCP operation to DH Removal. This step change must be included when calculating cooldown rate. PROC.M(ORK PLAN NO. 11 02.01 0 D. Check step change is ~15°F: - T-cold temperature (step 10.15.4) minus DH cooler outlet temperature

= Step Change = OF. NOTE - sO°F/hr is equivalent to 12.S0F change per 15 minute plot. >2S0P change in c30 minutes is a violation of Tech Spec cooldown limit. PROCEDUREWORK PLAN TITLE: PLANT SHUTDOWN AND COOLDOWN 10.15.7 Slowly adjust DH cooler outlet temp to establish RCS cooldown rate <SO°F/hr (<0.83°F/minl.

PAGE: 37 of 80 CHANGE: 053-11-0 10.15.8 desired by Chemistry department, THEN continue cycling SG levels until ready for wet layup. 10.16 Continue cooldown plot as follows: Plot DH Cooler outlet temperature from step 10.15.6.C Stop plotting T-cold. Start plotting DH Cooler outlet temperature.

10.17 g required by the Surveillance Test Schedule or the Operations Manager, THEN verify Condensate, Feedwater and Steam System Tests - (1305.032). Supplement 3 and 4, MSIV Instrument Air System Leak Test is in progress or has been completed.

10.18 Secure main steam heating to Low Pressure Feedwater Heaters (E-2A and E-2B) by closing the following valves, N/A if main steam heating is not being used:

Main Steam to E-2B Control Valve (CV-3021A) . Main Steam to E-2A Control Valve (CV-3028A) Main Steam Heating to Feedwater Heater E-2A (CV-3028)

Main Steam Heating to Feedwater Heater E-2B (CV-3021) 10.19 IF degassing was required, THEN complete degassing before reducing RC pressure below that required to maintain adequate letdown flow rate.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE REACTOR COOLANT PUMP OPERATION SET # DOCUMENT NO. 1103.006 WORK PLAN EXP. DATE NIA SAFETY-RELATED EYES ON0 TEMP ALT BYES ON0 CHANGE NO 025-04-0 TC EXP DATE NIA IPTE DYES EN0 When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: VERIFICATION COVER SHEET FORM NO. 1000.006A CHANGE NO. 050-00-0 10.0 RCP Stop PROC.MTORK PLAN NO. 1103.006 10.1 IF RCP is tripped

?% emergency manual trip is required, - THEN refer to Reactor Coolant Pump Trip (1203.022) - 10.2 IF time permits, THEN contact predictive maintenance to install backup indication of RCP zero s~eed ~rior to RCP stop. PROCEDUREMTORK PLAN TITLE: REACTOR COOLANT PUMP OPERATION (0-3-1) _I CAUTION Stopping or shifting RCPs or changing RCP loop configuration when RPS is reset can cause a reactor trip or an ICS runback. . Stopping the last RCP prior to bypassing EPIC will cause EPW actuation. - PAGE: 29 of 48 CHANGE: 025-044 10.3 - IP RPS is reset, AND NOT inThutdown Bypass, - TKEN perform the following: - Maintain 1 RCP per loop Notify load dispatcher of any load change. - IF stopping 1 of 4 RCPs, THEN reduce power to 560% I CAUTION Operation with only 1 RCP in each loop is permitted for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> with the Rx Critical per TS 3.4.4 Condition A. Mode 3 is required within an additional I 1 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> pkr TS 3.4.4 Condition B. 1 IF stopping 1 of 3 RCPs, resulting in 1 pump per loop, THEN reduce power to 540%. -

CAUTION Single pump operation in excess of 2 minutes may cause pump damage due to inadequate flow through the hydrostatic bearing. PROC.fWORK PLAN NO. 1103.006 ~p NOTE - Computer alarm BACKSTOP LO FLOW will not clear until backstop oil pumps are running with adequate flow. (not applicable for P-32B) 10.4 Stop RCP(s) as follows: 10.4.1 - IF P-32A, THEN perform the following:

PROCEDURUWORK PLAN TITLE: REACTOR COOLANT PUMP OPERATION NOTE - During RCP start, running only one HP Oil Lift Pump will insure adequate HP Oil Lift pressure.

PAGE: 30 of 48 CHANGE: 025-04-0 A. Start the following pumps: HP Oil Lift Pump (P-63A) Emergency HP Oil Lift Pump (P-80A) NOTE - Flow through each Backstop Lube Oil Pump and Backup Backstop Lube Oil Pump can be verified utilizing the following computer points:

B. Start the BACKUP Backstop Lube Oil Pump (P-82A). C. Verify Backstop Lube Oil Pump (P-81A) indicates running. D. Stop P-32A. NOTE - P-32B has a mechanical anti-reverse rotation device that is extremely noisy during startup and coast down. E. IF only one RCP remains running, THEN stop the remaining RCP within 2 minutes 10.4.2 IF P-32C, THEN perform the following:

PROC.MIORK PLAN NO. 1103.006 NOTE - During RCP start, running only one HP Oil Lift Pump will insure adequate HP Oil Lift pressure.

A. Start the following pumps: PROCEDUREWORK PLAN TITLE: REACTOR COOLANT PUMP OPERATION HP Oil Lift Pump (P-63Cl r Emergency HP Oil Lift Pump (P-80Cl PAGE: 31 of 48 CHANGE: 02544-0 NOTE - Flow through each Backstop Lube Oil Pump and Backup Backstop Lube Oil Pump can be verified utilizing the following computer points:

8. Start the BACKUP Backstop Lube Oil Pump (P-82C) C. Verify Backstop Lube Oil Pump (P-81C) indicates running. D. Stop P-32C. NOTE - P-32B has a mechanical anti-reverse rotation device that is extremely noisy during startup and coast down.

E. F only one RCP remains running, THEN stop the remaining RCP within 2 minutes -

10.4.3 - IF P-32D, THEN perform the following: - PROC.NYORK PLAN NO. 1103.006 NOTE - During RCP start, running only one HP Oil Lift Pump will insure adequate HP Oil Lift pressure.

A. Start the following pumps: PROCEDURENYORK PLAN TITLE: REACTOR COOLANT PUMP OPERATION HP Oil Lift Pump (P-63D) Emergency HP Oil Lift Pump (P-BOD) PAGE: 32 of 48 CHANGE: 025-04-0 NOTE - Flow through each Backstop Lube Oil Pump and Backup Backstop Lube Oil Pump can be verified utilizing the following computer points:

B. Start the BACKUP Backstop Lube Oil Pump (P-82D). C. Verify Backstop Lube Oil Pump (P-81D) indicates running. D. Stop P-32D. NOTE - P-32B has a mechanical anti-reverse rotation device that is extremely noisy durins startup and coast down.

E. g only one RCP remains running, THEN stop the remaining RCP within 2 minutes. - 10.4.4 - IF stopping P-328, THEN start P-63B OR P-SOB. NOTE - P-32B has a mechanical anti-reverse rotation device that is extremely noisy durins startup and coast down. A. Stop P-32B B. F only one RCP remains running, THEN stop the remaining RCP within 2 minutes -

10.5 Perform the following during RCP coast down:

PROC.MIORK PLAN NO. 1 103.006 - 10.5.1 - IF P-32A stopped. THEN verify the following pumps remain on: HP Oil Lift Pump (P-63A) Backstop Lube Oil Pump (P-81Al PROCEDURENVORK PLAN TITLE: REACTOR COOLANT PUMP OPERATION IF P-32C stopped, 10.5.2 - THEN verify the following pumps remain on: PAGE: 33 of 48 CHANGE: 025-04-0 HP Oil Lift Pump (P-63C) Backstop Lube Oil Pump (P-81Cl 10.5.3 - IF P-32D stopped, THEN verify the following pumps remain on: - HP Oil Lift Pump (P-63D) Backstop Lube Oil Pump (P-81Dl 10.5.4 - IF P-328 stopped, THEN verify HP Oil Lift Pump (P-638) remains on - 10.6 Verify shaft stops, without reverse rotation, as follows: Verify Predictive Maintenance or Shift Engineer contacted to install backup indication of zero speed. IF associated RCS loop flow is no longer dropping, ;E-fiEN consider the shaft stopped. Plant computer reverse rotation alarm remains clear.(not applicable for P-32Bl RCP P32-D REVERSE ROTATION (FS6513) RCP P32-C REVERSE ROTATION (FS65121 RCP P32-A REVERSE ROTATION (FS6510) NOTE - Reverse rotation is indicated by the following: Computer alarm based on reverse lube oil flow RCP high vibration RCP motor bearing high temperature 10.7 - IF reverse rotation indicated, THEN trip reactor. 10.7.1 Trip running RCP (s) . 10.7.2 Refer to Reactor Trip (1202.001) 10.8 WHEN shaft has stopped, THEN stop all oil pumps for the idle RCP by placing handswitches in - PULL-TO-LOCK. (Backstop Lube Oil Pump not applicable to P-32B) PROC.WORK PLAN NO. 1103.006 . Emergency HP Oil Lift Pump (P-80A thru D) . HP Oil Lift Pumps (P-63A thru D) Backstop Lube Oil Pumps (P-81A, C, and D) . Backup Backstop Lube Oil Pumps (P-82A, C, and D) 10.9 While RCS is >150°F, maintain seal injection flow and ICW flow to RCP Seal Cooling Water Heat Exchangers (E-25A thru D). PROCEDUREWORK PLAN TITLE: REACTOR COOLANT PUMP OPERATION 10.9.1 Maintain ICW flow to RCP Motor Air Coolers PAGE: 34 of 48 CHANGE: 025-04-0 RCP Motor Air Coolers (E-41A1 and E-41A2) RCP Motor Air Coolers (E-41B1 and E-41B2) RCP Motor Air Coolers (E-41C1 and E-41C2) RCP Motor Air Coolers (E-41D1 and E-41D2) 10.10 IF RCP stop at power, perform the following:

10.10.1 Lower the UW HI-Load Limit 5% below runback limit. NOTE - RCP breaker status (normal or tripped) feeds NSSS Index Point which is used in the heat balance power calculation.

10.10.2 Verify Plant Computer reflects current RCP breaker status on ZSlH11, ZSlHl2, ZSlH21 and ZSlH22. 10.10.3 IF breaker status is incorrect.

%EN contact Computer Support to update Plant Computer to - match current breaker status.

NOTE The Temuerature Comuensated Total Flow (XWRCFT) and RC Pressure (P1021, P1023, $1038. ~1039: alarm limits for the Plant Computer are dependent upon RCP combination. Normally Plant Computer alarm setpoints are operator adjustable, however, these points are some of the alarm points that are blocked that are carried on Tech Spec Cross-check log (OPS-A24). Refer to Unit 1 Operations Logs (1015.003A), Attachment C for these alarm limits. 10.10.4 Request Computer Support to adjust XWRCFT and RC pressure (4 points) alarms for current RCP status. 10.10.5 Continue plant operations per Power Operations, 1102.004 JOB PERFORMANCE MEASURE UNIT: 1 REV # 1 DATE : TUOI NUMBER: AIJPM-RO-EOP16 SYSTEM/DUTY AREA: EMERGENCY AND ABNORMAL OPERATIONS TASK: PERFORM ACTIONS REQUIRED TO CORRECT OVERCOOLING OF THE RCS (DUE TO TBVs) JTA#: ANOI-RO-EOP-EMERG-14 KA VALUE RO: 3.4 SRO: 3.7 KA

REFERENCE:

039 A2.04 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION:

INSIDE CR: X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR:

PERFORM LAB: POSITION EVALUATED:

RO: SRO: ACTUAL TESTING ENVIRONMENT:

SIMULATOR:

PLANT SITE: LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 5 MINUTES REFERENCE(S):

1202.003 Chg. 005-01-0 EXAMINEE'S NAME: SSN - - EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY: PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SICNE.? . - - . .. . . . .. . -. . . >ATE: .. . . . . -. ,SL';?I?.T;IE 1?:2:CATTS

':'dl2 ???I :US BE?!! CCKl'Ai?F3 T3 ITS AiDF:.ICA3LE

?RCC?CIJRE BY A L'UhL:FTED

N31V1?'JAL NOT ?!(E LX.W,!IllfE Ah!D IS Z!.'RRZ!,J'?

'/!YT;l THAT XLVIS13b:.

TUOI NUMBER: AlJPM-RO-EOPl6 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee. JPM INITIAL TASK CONDITIONS:

The reactor is tripped and the plant is in an over- cooling event at this time. - TASK STANDARD: "B" MSIV closed. TASK PERFORMANCE AIDS: Step 19 from 1202.003.

SIMULATOR SETUP: 100% power, fail turbine bypass valves CV-6687 and CV-6688 100% open then trip the reactor and reduce letdown.

TUOI NUMBER: AlJPM-RO-EOP16 INITIATING CUE: The SM/CRS directs you to check turbine bypass valves closed per step 19 of the Overcooling EOP. CRITICAL ELEMENTS (C) : 2, 3, 4 (C) (C) I I I I I EXAMINER NOTE: Inform examinee that an operator has been dispatched to locally close TBVs and reports they can NOT be closed locally. I I I I I PERFORMANCE CHECKLIST

1. Check turbine bypass valves closed.

FAULTED CUE: CV-6687 and CV-6688 are 100% open. POSITIVE CUE: "B" turbine bypass valve controller in HAND but valves NOT responding.

3. Close "B" OTSG MSIV On panel C09, closed 'B" CV-2692. OTSG MSIV CV-2692. Ill 2. Place turbine bypass valve hand/auto station for "B" OTSG in HAND and close. and attempted to close CV-6687 and CV-6688.

STANDARD Identified that CV-6687 and CV-6688 are full open (by valve position indication on panel C03). On panel C03, placed turbine bypass valve hand/auto station for "8" OTSG in HAND (C) N/A POSITIVE CUE: Green light ON, red light OFF for CV-2692. (C) 5. Trip the "A" main feedwater pump. POSITIVE CUE: "A" MFP is tripped.

SAT 4. Open Feedwater Pumps Discharge Crosstie CV-2827. POSITIVE CUE: Red light ON, green light OFF for CV-2827. UNSAY On panel C03, opened CV-2827. On panel C02, tripped the "A" main feedwater pump.

---

TUOI NUMBER: AlJPM-RO-EOP16 I I 6. Operate ATM Dump Control On panel C09, adjusted the System for "B" OTSG to "B" OTSG atmospheric dump I I stabilize RCS temperature. control system (CV-2618

& I CV-26191 to stabilize RCS 1-1-----1 I I POSITIVE CUE: temperature (as necessary).

RCS temperature is stable. EOP will now send examinee to step 25 since the overcoolzng is terminated.

I END TUOI NUMBER: AlJPM-RO-EOP16 INITIAL TASK CONDITIONS: The reactor is tripped and the plant is in an over-cooling event at this time. INITIATING CUE : The SM/CRS directs you to check turbine bypass valves closed per step 19 of the Overcooling EOP.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: OVERCOOLING SET # DOCUMENT NO. 1202.003 WORK PLAN EXP. DATE NIA SAFETY-REIAED lEifYES ON0 TEMP ALT OYES EN0 CHANGE NO. 005614 TC EXP. DATE NIA IPTE BYES BNO , When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllntermption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShifULast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. VERIFICATION COVER SHEET 1000.006A CHANGE NO. 050-00-0 INSTRUCTIONS

18. Check ATM Dump ISOL valves closed (CV-2619 and 2676). 19. Check TURB BYP valves closed. (19. CONTINUED ON NEXT PAGE)

CONTINGENCY ACTIONS 18. Perform the following:

A. IF associated ATM Dump Control System is being used to control SG press, THEN verify proper control:

B. IF associated ATM Dump Control System is being used to control SG press, THEN close ATM Dump ISOL valve:

SG B CV-2619 CV-2618 SG A CV-2676 CV-2668 19. Place TURB BYP valve H/A Station in HAND close. ATM Dump ISOL ATM Dump CNTRL A. IF TURB BYP valve fails to close, THEN dispatch an operator to close failed TURB BYP valve locally, while continuing with this procedure.

SG B CV-2619 CV-2618 SG A CV-2676 CV-2668 ATM Dump ISOL ATM Dump CNTRL INSTRUCTIONS

19. (Continued).

CONTINGENCY ACTIONS B. IF associated SG press drops below 700 ~sia 'OR TURBFYP valve cannot be closed locally, TkJ@ perform the following:

1) Close associated MSIV: 2) LF: MFW pumps are operating, THEN perform the following: - SG A CV-2691 CV-6689 CV-6690 a) Open Feedwater Pumps DlSCH Crosstie (CV-2827).

(1) 1E CV-2827 fails to open, THEN actuate EFW AND - verify proper actuation and control (RT 5). MSlV TURB BYP valves b) Trip associated MFW pump: SG B CV-2692 CV-6687 CV-6688 c) both MFW pumps are tripped, THEN actuate EFW verify - proper actuation and control (RT 5). SG A CV-2691 B MFW pump 3) Operate ATM Dump Control System for bad SG to stabilize RCS temp: SG B CV-2692 A MFW pump - 4) overcooling is terminated, THEN GO TO step 25. - ATM Dump CV-2676 CV-2619 ATM Dump Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev # 1 Date: TUOI NUMBER: AIJPM-RO-HYD03 Systeduty Area: Hydrogen Recombiner and Purge Control System Task: Place Hydrogen Recombiner M55B in Operation JA# ANOI-RO-RBH2-NORM-I KA Value RO 4.0 SRO 4.0 KA Reference 028 A4.01 Approved For Administration To:

RO *3 SRO IXI Task Location:

Inside CR: *4 Outside CR:

Both: Suggested Testing Environment And Method (Perform Or Simulate #): Plant Site: Simulator#:

Perform Lab: Position Evaluated:

RO: SRO: Actual Testing Environment:

Simulator

1. Plant Site:

Lab Testing Method: Simulate:

Perform: Approximate Completion Time In Minutes: 15 Minutes Reference@):

1104.03 1 Chg. 01443-0 Examinee's Name:

SSN: Evaluator's Name:

The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be: Satisfactory:

Unsatisfactory:

Performance Checklist Comments: Start Time - Stop Time Total Time Signed # - Date: # TQ-202 attachment 9 is complete and on file for performance of this JPM for the current Reactor core configuration. Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

TUOI NUMBER: A1 JPM-RO-HYD03 TfE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System WaIMhrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

A LOCA has occurred.

Containment hvdrogen concentration is 2.5%. Both hydrozen recombiners are shutdonn.

Containment pressure is 26.0 psia. Pre-LOCA containment temperature was 120°F. TASK STANDARD:

Hvdro@x recombiner M55B in operation at power settine, of 68.0 KW to 7W.0 KW on JI-1001. TASK PERFORMANCE AIDS: 1104 031. sectron 8 Oand Att B TUOl NUMBER: AIJPM-RO-HYDO3 INITIATING CUE: The CRSISM directs you to place both hydrogen recombiners (M55AiB) in standby and then place M55B in operation.

Note: Your task is complete when the power you have determinedfor recombiner operation is achieved.

CRITICAL ELEMENTS (c): 2, 4, 5, 6, 7, 8 I c 1 PERFORMANCE CHECKLIST 1 STANDARD I NIA I SAT I UN I I I POSITIVE CUE: Power adjust ootentiometers for M55AiB are set at zero on 1 SAT zero used knurled

&b on power - adjust potentiometers on C26 and turned to the left and set at zero using HS-7472 and HS-7473).

1. Verffy power adjust potentiometers are set at zero. Verified power adjust potentiometers set to zero on C26 (if not already at I I POSITIVE CUE: MSSA/B red lights ON C / I NEGATIX CUE: M55- green lights ON. Id 3. Select thermocouple

1. I, 2 or 3 to input to recombiner temperature mdicators TI-2300 and TI-2301. POSITIVE CUE: Thermocouple

1. I, 2 or 3 selected as desired to input to TI- 2300 and TI-2301. 2. Turn hydrogen recombiners M55A and M55B on. Turned on hydrogen recombiners M55A and M55B using HS-7470 and

/. Thermocouple

1. I, 2 or 3 selected to input to TI-2300 and TI-2301 using handswitches HS-7474 and HS-7475 on C26. 4. Increase power to -5 KW. L clockwise until power on JI-1000 and JI-1001 on C26 indicated-5 KW. POSITIVE CUE: Power on JI-1000 and J1-1001 indicates 5KW. 8 , INSTRUCTOR NOTE: Inform examinee that ten minutes have elapsed after one minute at 10 KW. 1 POSITIVE CUE: Power is at 10 KW on JI-1000 and JI-1001 C power adjust potentiometers on C26. Recorded time 10 KW was achieved. - 5. Slowly increase power to 10 KW and record initial time. INSTRUCTOR NOTE: Inform examinee that taking data every 30 minutes on Attachment E will be simulated.

Inform examinee that ten minutes have elapsed after achieving 10 KW. Inform examinee that five minutes have elapsed after one minute at 20 KW. 1 C 6. Slowly increase power to 20 KW on M55B and hold for 5 minutes.

POSITIVE CUE: Power at 20 KW on JI-1001. Increased power on M55B to -20 KW using power adjust potentiometer on C26.

---

Page 4 of 5 TUOI NUMBER:

AIJPM-RO-HYDO3 I c 1 PERFORMANCE CHECKLIST 1 STANDARD 1 NIA I SAT I UN 1 C NEGATIVE CUE: Hydrogen concentration rising or steady on QI-7459. I C END 7. Determine power required from Attachment B based on containment pressure (26.0 psia and 120°F Pre-LOCA containment temperature).

8. Slowly increase power to 68.0-70.0 KW range. POSITIVE CUE: Hydrogen concentration dropping on QI-7459 and M55B maintaining power at determined value.

Determined Recombiner power to be from 68.0 to 70.0 KW using Attachment B of 1104.03 1. Power increased to 68.0 to 70.0 KW range using power adjust potentiometer on C26. --- --- SAT TUOl NUMBER: AIJPM-RO-HYD03 INITIAL CONDITIONS:

A LOCA has occurred. Containment hydrogen concentration is 2.5%. Both hydrogen recombiners are shutdown. Containment pressure is 26.0 psia. Pre-LOCA containment temperature was 120°F. INITIATING CUE: The CRSISM directs you to place both hydrogen recombiners (M55AIB) in standby and then place M55B in operation.

Note: Your task is complete when the power you have determined for recombiner operation is achieved 7 ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE CHANGE NO 014-03-0 TC EXP DATE NIA IPTE DYES @NO . TITLE CONTAINMENT HYDROGEN CONTROL SET # DOCUMENT NO 1104.031 WORK PLAN EXP DATE NIA SAFEN-RELATED BYES ON0 TEMP ALT OYES @NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftILast Shift Knowledge Peer Pressure Procedures ChangeIOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: VERIFICATION COVER SHEET FORM NO. 1000.006A CHANGE NO. 050-00-0 CAUTION Hydrogen recombiners should be placed in operation following a LOCA as soon as time permits and must be in operation before hydrogen concentration reaches 3.0%. 8.0 Placing Hydrogen Recombiner (M55A or M55B) in Operation PAGE: 8 of 52 CHANGE: 014-030 PROC.M'ORK PLAN NO. 1104.031 NOTE - Both M55A and M55B are placed in standby, then either may be placed in PROCEDUREM'ORK PLAN TITLE: CONTAINMENT HYDROGEN CONTROL I operation.

I 8.1 Place both MSIA and M55B in standby as follows 8.1.1 Place M55A in standby by performing the following:

A. Verify Power Adjust Potentiometer is set at zero for M55A. 8. Start M55A by placing HS-7470 in ON C. Select thermocouple

1. 1, 2, or 3 (HS-7474) to input to M55A Temperature (TI-2300).

D. Slowly turn power adjust potentiometers clockwise to raise power to 5 KW as indicated on M55A Power (JI-1000).

E. Slowly raise power to 10 KW 1. Record initial time at 10 KW: 2. Maintain 10 KW output for standby service.

8.1.2 Place M55B in standby by performing the following:

A. Verify Power Adjust Potentiometer is set at zero for M55B. B. Start M55B by placing 853-7471 in ON C. Select thermocouple

1. 1, 2, or 3 (HS-7475) to input to M55B Temperature (TI-2301).

D. Slowly turn power adjust potentiometers clockwise to raise power to 5 KW as indicated on M55B Power (31-1001).

E. Slowly raise power to 10 KW. 1. Record initial time at 10 KW: 2. Maintain 10 KW output for standby service NOTE - Following a LOCA, M55A or M55B must be in operation before Hz concentration reaches 3.0% as indicated on the highest reading H, analyzer.

8.2 Place recombiners in operation as follows: PAGE: 9 0f 52 CHANGE: 014-03-0 PROC.NIIORK PLAN NO. 1104.031 8.2.1 Place M55A in service by performing the following:

PROCEDUREIWORK PLAN TITLE: CONTAINMENT HYDROGEN CONTROL A. During heatup, monitor and record all three thermocouple temperatures every 30 minutes on Attachment D. B. Verify M55A has been at 10 KW for at least 10 minutes C. Slowly raise power to 20 KW AND hold for 5 minutes. D. Determine power required from Recombiner Power (M-55Al Versus Containment Pressure (Attachment B of this procedure) based on containment pressure.

11 KW setting I CAUTION Excessive power and temperature may cause heater failure.

I 2) Slowly raise power to the value determined above E. Verify proper recombiner operation by observing the following:

NOTE Hydrogen concentration reduction is the long-term, primary method of verification.

H, concentration reduction shall be used regardless of recombiner power or temperature indication as the verification of proper recombiner operation. Hydrogen concentration stable or dropping at % Hydrogen (QI-7457 and QI-74591 . Recombiner maintaining power at value determined NOTE - Thermocouples are non-Q and will not be reliable indicators in a post-LOCA environment. Recombiner temperature can aid in trending recombiner operation.

The following steps are provided as guidelines.

I PAGE: 10 of52 CHANGE: 014-03-0 PROC.PNORK PLAN NO. 1104.031 Recombiner temperature may be plotted on Attachment C for verifying thermocouple operation and estimating time when recombination temperature will be reached. PROCEDUREiWORK PLAN TITLE: CONTAINMENT HYDROGEN CONTROL F. Establish validity of temperature indication by comparing AT between thermocouples.

1. IF all three thermocouples fall within a 6O0F band, THEN average the three temperatures. - 2. IF no two thermocouples are within 60°F of each other, THEN thermocouples should be considered - inaccurate.

3. IF difference of the three temperatures

>60°F, two temperatures are within 6O0F, THEN average the closest two. - G. Monitor for indication that recombiner operating temperature of 1225OF has been reached. NOTE - Valid thermocouples show a ramp rise in temperature with H, concentration

~2%. indicating recombination temperature has been reached and recombination is taking place. H. hydrogen concentration is ,2%, THEN monitor for a ramp rise in temperature - I. After four hours of full power operation, log data in Attachment D once per hour.

8.2.2 Place M55B in service by performing the following:

PROC.MORK PLAN NO. 1104.031 A. During heatup, monitor and record all three thermocouple temperatures every 30 minutes on Attachment E. B. Verify M55B has been at 10 KW for at least 10 minutes.

PROCEDUREMORK PLAN TITLE: CONTAINMENT HYDROGEN CONTROL C. Slowly raise power to 20 KW AND hold for 5 minutes PAGE: 11 of 52 CHANGE: 014-03-0 D. Determine power required from Recombiner Power (M-558) Versus Containment Pressure (Attachment B of this procedure) based on containment pressure.

1) KW setting I CAUTION Excessive power and temperature may cause heater failure.

I 2) Slowly raise power to the value determined above E. Verify proper recombiner operation by observing the following:

NOTE - Hydrogen concentration reduction is the long-term, primary method of verification.

H, concentration reduction shall be used regardless of recombiner power or temperature indication as the verification of proper recombiner operation. Hydrogen concentration stable or dropping at % Hydrogen (QI-7457 and 01-7459) . Recombiner maintaining power at value determined NOTE Thermocouples are non-Q and will not be reliable indicators in a post-LOCA environment.

PROC.IWORK PLAN NO. 1104.031 Recombiner temperature can aid in trending recombiner operation.

The following steps are provided as guidelines.

I Recombiner temperature may be plotted on Attachment C for verifying thermocouple operation and estimating time when recombination temperature will be reached. PROCEDUREIWORK PLAN TIRE: CONTAINMENT HYDROGEN CONTROL F. Establish validity of temperature indication by comparing AT between thermocouples.

> PAGE: 12of 52 CHANGE: 014-03-0 1. F all three thermocouples fall within a 60°F band, THEN average the three temperatures. - 2. 2 no two thermocouples are within 60°F of each other, THEN thermocouples should be considered - inaccurate.

3. IF difference of the three temperatures

>60°F, two temperatures are within 60°F. THEN average the closest two. G. Monitor for indication that recombiner operating temperature of 1225°F has been reached. NOTE Valid thermocouples show a ramp rise in temperature with H, concentration 22%. indicating recombination temperature has been reached and recombination is taking place. H. IF hydrogen concentration is 12%, THEN monitor for a ramp rise in temperature.

I. After four hours of full power operation, log data in Attachment E once per hour. 8.2.3 - IF proper power setting causes average valid temperature to exceed 1450°F OR in-service recombiner has insufficient capacity, - THEN place standby recombiner in service. - 8.2.4 Do NOT lower recombiner power based on extreme temperature Maintain power until standby recombiner is heated to operating temperature.

8.3 Monitor Hydrogen Samplers (C178 and C179) to verify recombiner(s) maintaining or lowering hydrogen concentration.

I CAUTION Excessive power and temperature may cause heater failure.

3 PROC.NVORK PLAN NO. 11 04.031 NOTE - I A power change of 4 KW will change temperature approximately 75OF I PROCEDUREWORK PLAN TITLE:

CONTAINMENT HYDROGEN CONTROL 8.3.1 - IF H, concentration has risen by

>0.5% in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR H, concentration

>3.0%, - THEN raise recombiner power setting by 4 KW above the previous setting.

• PAGE: 13of52 CHANGE: 014-03-0 NOTE - A change in containment pressure will require an adjustment to recombiner I power. I 8.4 Monitor containment pressure 8.4.1 WHEN pressure changes, THEN adjust recombiner power to new value from Attachment B. 8.5 - WHEN no longer required, THEN secure Hydrogen Recombiner as follows: - 8.5.1 Secure M55A as follows: A. Lower power to zero B. Secure M55A by placing HS-7470 to OFF C. Leave a thermocouple selected as input to M55A Temperature (TI-2300).

8.5.2 Secure M55B as follows: A. Lower power to zero B. Secure M55B by placing HS-7471 to OFF C. Leave a thermocouple selected as input to M55B Temperature (TI-23011 .

ATTACHMENT B Page 2 of 2 RECOMBINER POWER (M-556) VERSUS CONTAINMENT PRESSURE PAGE: 18of 52 CHANGE: 014.034 PROC.WORK PLAN NO. 1104.031 45 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 Post-LOCA Containment Pressure (0.2 psia increments)

PROCEDUREWORK PLAN TITLE: CONTAINMENT HYDROGEN CONTROL Note: Use pre- LOCA average Reactor Building Temperature from SPDS (TAVRB1) from history file if available. Otherwise use logs.

Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev # 4 Date: TUOI NUMBER: AlJPM-RO-ED008 SystemlDuty Area: Electrical Distribution Task: Shift buses Al, A2, H1, H2 from Stmp One to Unit Aux Transformer JA# ANO1-RO-ELECD-NORM-25 KA Value RO 3.1 SRO 3.1 KA Reference 062 A4.07 Approved For Administration To: RO El SRO Task Location:

Inside CR: Ed Outside CR: Both: Suggested Testing Environment And Method (Perform Or Simulate

1. ): Plant Site:

Simulator#:

Perform Lab: Position Evaluated:

RO: SRO: Actual Testing Environment: Simulator

1. Plant Site: Lab Testing Method:

Simulate:

Perfom: Approximate Completion Time In Minutes: 10 Minutes Reference(S):

1107.001 Chg. 060-19-0 Examinee's Name:

SSN: Evaluator's Name:

The Examinee's performance was evaluated against the standards contained m this JPM and is determined to be: Satisfactory:

Unsatisfactory: Performance Checklist Comments:

Start Time Stop Time Total Time Signed # Date: # TQ-202 attachment 9 is complete and on file for performance of this JPM for the current Reactor core configufdtion. Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

TUOI NUMBER: AlJPM-RO-ED008 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMIEE: The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee JPM ATTI& TASK CONDITIONS: Plant is at 20-40% wwer and readv to transfer plant auxiliaries to the Unit Aux Transformer. The Unit Auxiliw Transformer is available and all breaker controls are in Remote." SEE SETUP BELOW.

TASK STANDARD:

Plant auxiliaries (Al, A2, HI. HZ) are being powered from the Unit Auxiliary Transformer.

This is a faulted JPM, the ouerator must manuaUv trip one of the power supplies to A1 bus. TASK PERFORMANCE AIDS:

Svnch-switch handle. 1107.001 Step 8.2 Simulator setuo: The fanited breaker for this JPM w~ll be implemented by use of an override.

Prior to providing the initial conditions for this JPM insert the following:

Override DI-A112R;False This will cause the SUI feeder breaker to bus A1 to fail to open when the Unit Aux feeder handswitch is released aRer being closed (the override defeats the return-to-normal for breaker A-112, Unit Am to Al).

TUOI NUMBER:

AIJPM-RO-ED008 INITIATING CUE: The CRSISM directs you to transfer plant auxiliaries from Startup One Transformer to the Unit Auxiliary Transformer.

CRlTICAL ELEMENTS (c): LU C I PERFORMANCE CNECKLIST I STANDARD I NIA I SAT I UN I 1 SAT 1 INSTRUCTOR NOTE: Thts 1s a faulted JPM the Startup One to A1 breaker w11 not automatically open after the Umt AUX to A1 breaker 1s closed, the operator must manually tnp one of the feeder breakers to A1 Steps 1 through 5 will be completed four times for four buses. POSITIVE CUE: Synchronize switcb ON Tmed ON Synchronize switcb for correct breaker.

C 1. On C10, place Synchronize switch to ON for the Unit Aux Feeder Breaker that is to be closed. 2. Verify synchroscope is at I2 o'clock. Verified sycnhroscope stopped near the 12 o'clock position, POSITIVE CUE: Synchronize switch OW. - , L I I I I I INSTRUCTOR NOTE: When examinee closes Unit Aux breaker on A1 bus, the SU #I feeder breaker for A1 will not open. 4. On C10, tnrn Synchronize switch OFF. - C Tnmed Synchronize switch OFF. NEGATIVE CUE:

Al SU1 breaker did not open, Unit Aux and SUI feeder breakers to A1 are closed. 3. On C10, close Unit Aux Feeder breaker.

Allow control switch to return to normal-after-close position.

POSITIVE CUE: Unit Aux Feeder Breaker closed.

--- verify that the SU1 Feeder Breaker opens.

POSITIVE CUE: SU1 feeder breaker opened. Closed Unit Aux Feeder Breaker and allowed control switch to return to normal-after-close position.

Verified that the SU1 Feeder Breaker Opened. C 7. Place the open breaker's controt switcb in nod-after-open. 6. If the SU1 breaker does not immediately open, trip it. POSITIVE CUE: SU1 to A1 breaker is open. Placed the open breaker's control switch in the nod-afterapen position. Tripped (to open) the SU1 feeder breaker to A1 bus (A-113). ---

Page 4 of 5 END TUOI NUMJ3ER: AIJPM-RO-ED008 UN SAT NIA STANDARD Verified Startup XlWRS Pref Transfer selector switch is in the desired position (to SUI). C SAT PERFORMANCE CHECKLIST

8. Venfy Startnp XFMRS Pref Transfer selector switch is in the desired position.

--- -9 buses remain above 6010V. 10. Contact relay group to perform visual verification of contact closure of Sync Check Relays. Verified proper voltages on Al, A2, H1 and H2. Contacted relay group.

TUOI NUMBER: AlJPM-RO-ED008 INITIAL CONDITIONS:

Plant is at 20-40% power and ready to transfer plant auxiliaries to the Unit Aux Transformer.

The Unit Auxiliary Transformer is available and all breaker controls are in "Remote." INITIATING CUE: The CRSISM directs you to transfer plant auxiliaries fiom Startup One Transformer to the Unit Auxiliary Transformer.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE ELECTRICAL SYSTEM OPERATIONS SET # DOCUMENT NO 1107.001 WORK PLAN EXP DATE NfA SAFEPI-RELATED BYES ON0 TEMP ALT mYES ON0 CHANGE NO 060-194 TC EXP DATE NIA IPTE BYES ON0 When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/lnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiWLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME CHANGE NO. 050-009 FORM TITLE: VERIFICATION COVER SHEET FORM NO. 1000.006A 8.1.4 IF RCS is S200°F @ it is desired to remove SU 2 Transformer Feeder Breakers to A2, HI, H2 control switches from PULL-TO-LOCK, THEN perform the following:

PROC.JWORK PLAN NO. 1107.001 NOTE - Lamps for Load Shed circuits only indicate power available to the circuit. Test switches for defeating this feature do not cause the lamps to go out. SU2 Load Shed feature is defeated by opening Switch G located beneath the cover of TS-1 111 Test SW and TS-1 211 Test SW, at A-111 and A-211, respectively. The switch cover cannot be installed with Switch G open. PROCEDUREJWORK PLAN TITLE: ELECTRICAL SYSTEM OPERATIONS A. SU 2 Transformer load shed circuit operable as follows : PAGE: 16 of 276 CHANGE: 060-19-0 Lamp on at Startup XFMR

1. 2 Feed to A1 (A-111) illuminated.

Lamp on at Startup XFMR

1. 2 Feed to H1 (H-13) illuminated. . Cover installed on TS-1 111 Test SW at A-111. Cover installed on TS-1 211 Test SW at A-211. B. UNLESS allowed by Design Engineering Evaluation, verify Unit 2 has SU 2 Transformer feeder breakers in PULL-TO-LOCK. C. Inform Unit 2 of intent to remove Unit 1 feeder breakers from SU 2 from PULL-TO-LOCK.

D. Remove SU 2 feeder breakers to A2, HI, and H2 as desired from PULL-TO-LOCK.

8.1.5 To transfer loads to SU 2 perform the appropriate section of this procedure. 8.2 Transferring Buses From SU 1 to Unit Aux 8.2.1 Verify breakers to be operated are in the remote position.

8.2.2 Verify Unit Aux Transformer is operable.

8.2.3 For Unit Aux Feeder Breaker that is to be closed, turn Synchronize switch on.

8.2.4 Verifv svnchrosco~e between 11 and 1 o'clock . . (4.3.4) CAUTION High circulating currents may trip bus lockout relay if both feeder breakers remain closed. PAGE: 17 Of 276 CHANGE: 060-19-0 PROC.MlORK PLAN NO. 1107.001 8.2.5 Close Unit Aux Feeder breaker. Allow control switch to return to NORMAL-AFTER-CLOSE position.

PROCEDUREMlORK PLAN TITLE: ELECTRICAL SYSTEM OPERATIONS NOTE - Svnchronize switch must be off to verify feeder breaker opens. With 1 Synchronize switch on, red light for feeder breaker position goes out even if breaker does not trip. 8.2.6 Turn Synchronize switch off 8.2.7 Verify that the SU 1 Feeder Breaker opens A. _IPI the SU 1 breaker does immediately open, trip it. B. IF the SU 1 breaker will NOT trip, THEN reopen the Unit Aux Feeder breaker - AND delay power escalation until the problem is resolved.

1. neither SU 1 breaker nor Unit Aux breaker will open, THEN dispatch an operator to manually trip the - Unit Aux Feeder breaker AND delay power escalation until the problem is resolved.

2. Initiate maintenance action for repairs 8.2.8 Place the open breaker's control switch in NORMAL-AFTER-OPEN.

8.2.9 Repeat steps until all buses are on Unit Aux 8.2.10 Verify Startup XFMRS Pref Transfer selector switch is in the desired position.

8.2.11 Verify 4160V buses remain above 3640V and 6900V buses remain above 6010V. 8.2.12 Contact Relay Group to perform visual verification of contact closure of Sync Check Relays.

JOB PERFORMANCE MEASURE Unit: 1 Rev # 0 Date: TUOI NUMBER: AIJPM-RO-ARM01 SystemDuty Area: Area Radiation Monitor System Task: Respond to Area Radiation Monitor alann JA# ANOl-WCO-RMS-SURV-7 KA ValueRO 3.0 SRO 3.3 KA Reference 072 A4.01 Approved For Administration To: RO El SRO Task Location: Inside CR:

Outside CR: a Both: 0 Suggested Testing Environment And Method (Perform Or Simulate

1. ): Plant Site: Simulator#:

Perform Lab: Position Evaluated:

RO: SRO: Actual Testing Environment: Simulator

1. Plant Site:

Lab Testing Method: Simulate:

Perform: Approximate Completion Time In Minutes: 20 Minutes Reference(s):

1305.001 Chg. 014-15-0 Examinee's Name:

SSN: Evaluator's Name:

The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be: Satisfactory:

Unsatisfactory: Performance Checklist Comments: Start Time Stop Time Total Time Signed # Date: # TO-202 attachment 9 is comulete and on file for uerformance of this JPM for the current Reactor core confimtion.

Signitwe indicates this JPM has been compared to'its applicable procedure by a qualified individual (not the &minee) and is cnrrent with that revision.

TUOI NUMBER: AIJPM-RO-ARMOl THE EXAMINER SHALL REVlEW TI-IE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" porlion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Annunciator KlO-B1. AREA MONITOR RADIATION HI, has alarmed. A check of C-25 Bav 3 shows RI-8006. Radio Chem Lab, Warning light is on and is reading 1.5 mRk. Radiation Protection has snrveved the area and reported to the CRS. TASK STANDARD:

RI-8006 Radio Chem Lab warning setpoint adjusted to 1.6 to 2.5 mRh. TASK PEREORMANCE AIDS:

1305.001.

supulement 6

TUOI NUMBER: A13PM-RO-ARM01 . . .- - . L-- I.. L.-= EXAMINER NO'I'E: Wtlcn Wdinn. pklces ;11ann settilig snitch ln tlic WARNING position.

Uien ii~onn lriiincc the indicator is re;td~ng I tnmlr. ... ..... L ... -. ...............

__ ..........

....-.---

-. INITIATING CUE: The CRS directs you to adjust the warning setpoint for RI-8006 to 2.0 mRfhr. CRITICAL ELEMENTS (c): I / POSITIVE CUE: I I 1 I 1. On RI-8006, place darm setting switch in the WARNING position and observe warning setpoint vdne on indicator.

RI-8006 i11ann sctting s\\itch in \VARNlNG.

.............

...... I .. .I .--.... .................. - ' I.._ EXAMINER NOTE lnforln mince RI-XOU6 indicator 1s rcading 1.5 tnWhr b;ickground

-.... ..- . ......- - .... .- ........ -. -............ - ........ -. ..........

-- - - -.* - , SAT NIA J c! 2. Slide RI-8006 drawer out. UN SAT STANDARD C On C25 Bay 3, placed RI-8006 alarm setting sw~tch in WARNING. Observed warning setpoint value. I I POSITIVE CUE: RI-8006 drawer out PERFORMANCE CIIECKLIST

--- On RI-8006, depressed handle release buttons and pulled drawer out. I I-I- / 1 4. Slide RI-8006 drawer int. C POSITIVE CUE:

RI-8006 drawer inserted, 3. Hold alarm setting switch in the WARNING position and adjust warning potentiometer to 2.0 mRk. POSITIVE CUE: Warning potentiometer set to 2.0 mWhr. 1 I 5. Reset Waming dm. On RI-8006, slid drawer in. I I POSITIVE CUE: Warning alarm clear.

On Ri-8006 drawer, held alarm setting switch in the WARNING position and adjusted warning potentiometer to 2.0 mR/hr. --- --- On RI-8006, turned ALARM RESET/CIIECK SOURCE swttch to ALARM RESET. --- C . ...............

... . .........

I - I 7 EXAMINER NOE: \\hen trdinec places almi selling s\\iich in tlic HIGH position.

then inforin trdirice thc indicator is reading 4 rttK/ltr ... ... .... -. .........

.. . . . . j 6. Record as-left setpoint vdne in section 3.0 In section 3.0, recorded value of 2.0 mR/hr in warning as-left setpoint space for RI-8006. ---

Page 4 of 5 TUOI NUMBER: AlJPM-RO-ARM0 1 7. On RI-8006, place alarm setting switch in the HIGH position and observe high alarm setpoint value on indicator.

C POSITIVE CUE: RI-8006 alarm setting switch in high. On C25 Bay 3, placed RI-8006 alarm setting switch in HIGH. Observed high setpoint value. - - PERFORMANCE CHECKLIST

__._I-. . -- . . .. . . .LL ..I.- EXAMINER NOT: Infonil trainee that no adjustmcnr is nacssin? for the HIGH sctpoinl. , -. , - - -. . . . - -. . - . - .- .. - -. - - _. -. -_I , STANDARD N/A SAT 8. Record as-left setpoint value in section 3.0, In section 3.0, recorded value of 4.0 mR/hr for the high as-left setpoint for RI-8006. ---

TUOI NUMBER: AIJPM-RO-ARM01 INITIAL CONDITIONS:

Annunciator KIO-B 1, AREA MONITOR RADIATION HI, has alarmed A check of C-25 Bay 3 shows RI-8006, Radio Chem Lab, Warning light is on and is reading 1 5 mR/hr Radiation Protection has sulveyed the area and reported to the CRS INITIATING CUE: The CRS directs you to adjust the warning setpoint for RI-8006 to 2 0 mR/hr Distractionllnterruption Questioning Attitude Multiple Tasks Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment I VERIFICATION COVER SHEET SUPPLEMENT 6 Page 1 of 11 AREA RADIATION MONITOR MONTHLY ALARM CHECK PROC.MORK PLAN NO. 1305.001 This check verifies high alarm setpoints on Unit 1 Area Monitors and checks or sets the warning alarm setpoint to provide a meaningful alarm. This check records the high alarm setpoint for Unit 1 CR Supply Vent Rad Detectors ZRITS-8001A AND ZRITS-8001B.

1.0 INITIAL CONDITIONS 1.1 Check purpose of this test PROCEDUREMIORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST INITIALS PAGE: 40 of 50 CHANGE: 014-15-0 Regularly scheduled monthly test

__ Other (describe in section 4.0) 1.2 Observe the following precautions: - The warning alarm on Control Room Area Monitor (RI-8001) is interlocked with the control room isolation system. NOTE - Control Room Area Monitor does not have audible alarm.

The hi alarm of all area monitors is interlocked to give audible and visual remote alarms at the location of each monitor. The alarm setting knob will cause RAD MONITOR IN TEST annunciator (K-10-F1) to alarm. It will not cause a warning or hi alarm interlock to actuate. The energizing of the check source will cause automatic interlocks of the alarm and warning to actuate if the setpoint is exceeded.

Do not energize the check source during the performance of this test. - IF elevated background radiation levels exceed the Maximum Normal Warning setpoint listed in section 3.0, THEN the warning setpoint may be adjusted above the - Maximum Normal setpoints by performance of this supplement. Documentation of reason for elevated radiation levels will he recorded in section 4.0. The warning setpoint shall he set below the Minimum setpoint listed in Section 3.0. Except for brief periods during evolutions such as Dry Fuel movement, the high alarm setpoint shall NOT exceed Maximum High Alarm Setpoint listed in section_@.

SUPPLEMENT 6 Page 2 of 11 PROC.MIORK PLAN NO. 1305.001 2.0 PROCEDURE 2.1 Perform one of the following:

N/A method not used. PROCEDURElWORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST - IF performing the monthly test, - THEN complete steps 2.2 for Control Room Rrea Radiation Monitor (RE-8001) and step 2.3 for all other area monitors listed in Section 3.0. PAGE: 41 of 50 CHANGE: 014-155 - IF performing this supplement for other than monthly - requirement, THEN perform only the area monitor(s) determined by the Shift Manager/CRS and N/A all others. 2.2 Control Room Area Radiation Monitor (RE-8001)

CAUTION The warning alarm on Control Room Monitor (RI-8001) is interlocked with the control room isolation system. Energizing of the check source will cause automatic actuation of the Control Room isolation system when the warning alarm setpoint is reached.

2.2.1 Place Alarm Setting switch in the WARNING - position and observe warning setpoint value on RI-8001 is 51 MR/HR. NOTE - Warning setpoints should be adjusted as necessary to a value high enough to preclude warninq actuations due to electrical noise deflections but low I ;nough to detec; rising radiation levels as early as possible.

I 2.2.2 - IF RI-8001 background is such that the warning - setpoint needs to be adjusted, THEN adjust the setpoint as follows. - A. Notify Unit 2 to place CONTROL ROOM DAMPER - HANDSWITCH (2HS-8685-2) on 2C33-2 in the CLOSE position.

8. Isolate Unit 1 Control Room by placing - Channel A and Channel B Control Room Isolation handswitches in the MAN position.

C. Verify Actuation Control Room Isolation - (K16-82) in alarm indicating isolation of control room.

SUPPLEMENT 6 Page 3 of 11 PROC.MIORK PLAN NO. 1305.001 D. Slide Area Monitor drawer out to gain - access to Alarm Setting potentiometers.

E. While holding the Alarm Setting switch in - the WARNING position, adjust the warning potentiometer to the desired setpoint but not less than 1 XR/ER. F. Slide Area Monitor drawer back to the - normal position and secure. PROCEDUREMIORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST G. Reset alarms if applicable. - PAGE: 42 of 50 CHANGE: 014-15-0 H. Place Channel A and Channel B Control Room - Isolation handswitches in the AUTO position.

I. At C141 in the computer room, depress PB Unit One Radiation Reset pushbutton.

J. At C141A in the computer room, depress PB System Trip Reset pushbutton.

K. At C141B in the computer room, depress PB System Trip Reset pushbutton.

L. Verify all Control Room Isolation trips - reset and K16-B2 is clear. M. Notify Unit 2 to place 2HS-8685-2 on 2C33 in the AUTO position.

2.2.3 Record As-Left Setpoint for RI-8001 in section - 3.0. 2.2.4 Place the Alarm Setting switch in the HIGH - position and observe the high alarm setpoint on RI-8001. 2.2.5 Release switch and record As-Left setpoint in - section 3.0. 2.2.6 Use DBM function of PMS computer, adjust Area - Monitor RI-8001 alarm setpoint to be in accordance with as-left data of this supplement.

SUPPLEMENT 6 Page 4 of 11 PROC.MIORK PLAN NO. 1305.001 2.3 For each remaining area monitor perform the following:

1 - NOTE 1 PROCEDUREWORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST i Monitors may be tested in any order. Test steps shall be followed in order. PAGE: 43 of 50 CHANGE: 014-155 Warning setpoints should be adjusted as necessary to a value high enough to preclude warning actuations due to electrical noise deflections but low enough to detect rising radiation levels as early as possible.

2.3.1 Place Alarm Setting switch in the WARNING - position and observe warning setpoint value on indicator.

2.3.2 - IF the background for the monitor is such that the warning setpoint needs to be adjusted, THEN adjust the setpoint as follows. - A. Slide Area Monitor drawer out to gain access to Alarm Setting potentiometers B. While holding the Alarm Setting switch in the WARNING position, adjust the warning potentiometer to the desired setpoint.

C. Slide Area Monitor drawer back to the normal position and secure.

D. Reset alarms if applicable 2.3.3 Record As-Left Setpoint for each monitor in - section 3.0. NOTE - Except for brief periods during evolutions such as Dry Fuel movement, the high alarm setpoint shall exceed Maximum High Alarm Setpoint listed in Section 3.0. The high alarm setpoint should be adjusted slightly below or equal to the Maximum High Alarm Setpoint listed in Section 3.0. 2.3.4 Place the Alarm Setting switch in the HIGH - position and observe the high alarm setpoint on indicator.

SUPPLEMENT 6 Page 5 of 11 PROC.IWORK PLAN NO. 1305.001 2.3.5 IF Alarm setpoint exceeds max allowable value or - - if high alarm setpoint must be adjusted for any reason, adjust the setpoint as follows: A. Slide Area Monitor drawer out to gain access to Alarm Setting potentiometers.

PROCEDUREIWORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST B. While holding the Alarm Setting switch in the HIGH position, adjust the HIGH potentiometer to the desired setpoint.

PAGE: 44 of 50 CHANGE: 014.154 C. Slide Area Monitor drawer back to the normal position and secure. D. Reset alarms if applicable.

E. Inform SM/CRS of any abnormal findings.

2.3.6 Record As-Left Setpoint in section 3.0. - 2.3.7 Use "DBM" function of PMS computer, adjust Area - Monitor alarm setpoints to be in accordance with as-left data of this supplement.

2.4 Check Unit 1 CR Supply Vent Rad Detector 2RITS-8001A high alarm setpoint as follows.

2.4.1 At 2RITS-8001A, press MODE to display high alarm - setpoint and record in section 3.0. 2.4.2 At PMS computer, check 2RITS-8001A High Alarm - Static Point (C02-7) indicates same value as monitor setpoint. Otherwise, using PMS "CREVSA" display, change point to display current high alarm setpoint.

2.4.3 Using DBM function on PMS computer, check alarm - setting for (R8001AMG) with Low setpoint at 21.2 and High setpoint at 21.8.

SUPPLEMENT 6 Page 6 of 11 PROC.WORK PLAN NO. 1305.001 2.5 Check Unit 1 CR Supply Vent Rad Detector 2RITS-8001B high alarm setpoint as follows. 2.5.1 At 2RITS-8001B, press MODE to display high alarm - setpoint and record in section 3.0. PROCEDUREWORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST 2.5.2 At PMS computer, check 2RITS-80018 High Alarm - Static Point (C03-7) indicates same value as monitor setpoint. Otherwise, using PMS

'CREVSB" display, change point to display current high alarm setpoint.

• PAGE: 45 of 50 CHANGE: 014-15-0 2.5.3 Using "DBM" function on PMS computer, check - alarm setting for (R8001BMG) with Low setpoint at 21.2 and High setpoint at 51.8.

SUPPLEMENT 6 Page 7 of 11 PROC.WORK PLAN NO. 1305.001 PROCEDUREWORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST (4.3.1) (4.3.2) backgLound reading to minimize constant alarming.

1f alarm setpoint must exceed 100 mRjHR, ensure HP is notified and thearea properly PAGE: 46 of 50 CHANGE: 014-15-0 Note 2 Note 1 5 X 10' mR 5 7 mR/m (30 days) (24 hr/day) This is based on the design value for this area during normal operation (assuming 1% failed fuel) according to ANO-1 SAR. During refueling shutdown, set the alarm sufficiently above the 3.0 ACCEPTANCE CRITERIA This is based on the Control Room being designed for continuous occupancy at a maximum of 5 Rem for the duration of a maximum hypothetical accident (30 days continuous occupancy) according to ANO-1 SAR. It was calculated as follows: Note 4 Note 5 3.1 Compare the As-Left Setpoint to the Maximum Normal Setpoint - and the As-Left High Alarm Setpoint to the Max High Alarm Setpoint.

posted. Establish the background for this meter and set the warning lower than the alarm setpoint but sufficiently above the background reading to minimize constant alarming.

Based upon lMPC XE-133. (Calc 91-E-0067-01)

NOTE - Warning alarm setpoints should be adjusted as necessary to a value high enough to preclude any warning actuations due to electrical noise deflections but low enough to detect rising radiation levels as early as possible. . High alarm setpoints are based, with the noted exceptions, on minimizing spurious alarms due to transient radiation level rises but low enough to provide early detection of abnormal radiological conditions in the area. I WARNING SETTING I ALARM SETTING I I I I I IS I AS-LEFT / MONITOR INDICATOR NUMBER/ (continued next page) 14.3.1) AS-LEFT SETPOINT MINIMUM AS-LEFT NOTE: NUMBERS IN PARENTHESES REPE DESCRIPTION AS-LEFT HIGH ALAIRM SETPOINT (2) HIS PAGE. SETPOINT YES NO SETPOINT 7 mR/HR YES NO SETPOINT RI-8001 CONTROL ROOM ! TO NOTES AT TOP OP 1 mR/m PROC.lWORK PLAN NO. 1305.001 SUPPLEMENT 6 Page 8 of 11 PROCEDURElWORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST 3.0 (Continued)

MONITOR INDICATOR NUMBER/ DESCRIPTION RI-8002 RELAY ROOM RI-8003 MACHINE SHOP RI-8004 OUTSIDE STAIRWAY EL 317' RI-8005 SAMPLE RM VESTIBULE RI-6006 RADIOCHEM.

LAB RI-8007 OUTSIDE STAIRWAY EL 369' RI-8008 DECON RM EL 386' RI-8009 SF POOL RI-8010 CA AREA EL 386' RI-6011 OUTSIDE STAIRWAY EL 335' NOTE: NUXBERS PAGE: 47 of 50 CHANGE: 014-15-0 (continued next page) MINIMUM SETPOINT 1 mR/HR 1 mR/HR 1 ~R/HR 1 mR/HR 1 ~R/HR 1 mR/HR 1 mR/HR I ~R/HR 1 mR/HR 1 mR/HR IN PARENTBESES AS-LEFT HIGH ALARM SETPOINT OP THIS WARNING AS-LEFT SETPOINT REPER ALARM SETTING MAXIMUM HIGH ALARM SETPOINT 2 mR/HR 2 mR/HR 20 ~R/HR 7.5 mR/HR 7.5 ~R/HR 7.5 mR/HR 20 mR/HR 20 ~R/HR 2.5 mR/HR 20 mR/HR SUPPLEMENT.

SETTING MAXIMUM NORMAL SETPOINT 1 mR/HR (2) 1 mR/HR (21 lo ~R/HR 2.5 mR/HR 2.5 ~R/HR 2.5 mR/HR 10 m/HR 10 ~R/HR 1 mR/HR (2) 10 mR/HR TO NOTES IS AS-LEFT HIGH ALARM SETPOINT 5 HIGH ALARM SETPOINT YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO IS AS - LEFT SETPOINT 5 MAX NORMAL SETPOINT YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO ON PAGE 7 SUPPLEMENT 6 Page 9 of 11 PROC.IWORK PLAN NO. 1305.001 PROCEDUREMORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST WARNING SETTING PAGE: 48 of 50 CHANGE: 014-154 ALARM SETTING IS AS-LEFT HIGH MONITOR INDICATOR NUMBER/ DESCRIPTION RI-8012 PIPING AREA I BY ELEV EL 335' RI-8013 STAIRWAY I 1 I I I I I I MINIMUM SETPOINT PIPING AREA I1 BY EMERG FEED PMP RI-8014 VESTIBULE I 3. ~R/HR I I 10 ~R/HR I YES NO I / 20 ~R/HR I YES NO RI-8015 I 1 I 1 mR/HR / I 1 1 1 mR/HR AS-LEFT SETPOINT 1 ~R/HR 10 mR/HR COND. DEMIN RI-8016 SPENT FUEL FILTERS AREA ACCESS HATCH 1 .04 R/HR I 1 .04 R/HR I YES NO I j .a6 R/HR / YES NO I 1 1 *1.2 1 I 1 *1.8 1 MAXIMUM NORMAL SETPOINT 2.5 ~R/HR RI-8017 FUEL HANDLING EQUIPMENT RI-8018 PERSONNEL YES NO 1 ~R/HR 1 mR/HR

• Reactor critical ** Reactor shut down IS AS-LEFT SETPOINT 5 MAX NORMAL SETPOINT YES NO .04 R/HR RI-8019 INCORE INSTRUMENT TANK NOTE: NUMBERS IN PARENTHESES REFER TO NOTES ON PAGE 7 OF THIS SUPPLEMENT.

20 mR/HR (2) 48 mR/HR (continued next page) AS-LEFT HIGH ALARM SETPOINT YES NO 7.5 ~R/HR *.3 R/HR t* Variable .04 R/HR YES NO YES NO YES NO MAXIMUM HIGH ALARM SETPOINT YES NO R/HR ** Variable (4) ALARM SETPOINT 5 MAX HIGH ALARM SETPOINT 2 ~R/HR 72 mR/HR '.45 YES NO YES NO R/HR *f Variable (3) YES NO YES NO R/HR

• Variable (3) YES NO SUPPLEMENT 6 Page 10 of 11 PROC.MIORK PLAN NO. 1305.001 NOTE: NUMBERS IN PARENTEESES REFER TO NOTES ON PAGE 7 OF THIS SUPPLEMENT.

PROCEDUREM~ORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST MONITOR INDICATOR NUMBER/ DESCRIPTION RI-8020 EQUIPMENT HATCH 2RITS-8001A High Alarm Setpoint 2RITS-8001B High Alarm Setpoint 3.2 IF "No" - is circled in the above table, THEN perform the following: - PAGE: 49 of 50 CHANGE: 014-15-0 Immediately notify the Shift Manager/CRS Document reason for raised background in section 4.0 Initiate corrective actions as required Performed By Operator Date/Time MINIMUM SETPOINT .04 R/HR N/A N/A AS-LEFT HIGH ALARM SETPOINT WARNING AS-LEFT SETPOINT N/A N/A ALARM SETTING MAXIMUM HIGH ALARM SETPOINT *.I2 R/HR *

• Variable (3) 800 CPM (5) 800 CPM (5) IS AS - LEFT HIGH ALARM SETPOINT < MAX HIGH ALARM SETPOINT YES NO YES NO YES NO SETTING MAXIMUM NORMAL SETPOINT *. 08 R/HR ** Variable (4) N/A N/A IS AS - LEFT SETPOINT 2 NORMAL SETPOINT YES NO N/A N/A SUPPLEMENT 6 Page 11 of 11 PROC.MIORK PLAN NO. 1305.001 4.0 SHIFT MANAGER REVIEW AND ANALYSIS (circle one) 4.1 Are the As-Left Setpoints within the Maximum Normal Setpoints?

.................................................

YES NO PROCEDUREWORK PLAN TITLE: RADIATION MONITORING SYSTEM CHECK AND TEST 4.2 Do the As-Left High Alarm Setpoints fall within the .....................

Maximum High Alarm Setpoints?

PAGE: 50 of 50 CHANGE: 014-15-0 4.3 IF answer to 4.1 or 4.2 is "NO", - THEN describe the action taken below YES NO 4.4 Have all of the administrative requirements of this test been satisfied (i.e., all initial blocks initialed or N/ACd, all data entered, applicable signature spaces signed, etc.)? ... YES NO SHIFT MANAGER DATE JOB PERFORMANCE MEASURE TUOI NUMBER: AIJPM-RO-AOP28 Page 1 of 4 UNIT: 1 REV #: 2 DATE: TUOI NUMBER: AlJPM-RO-AOP28 SYSTEM: Emergency and Abnormal Operations TASK: Respond to Lo-Lo Instrument Air Pressure.

JTA ANOI-RO-AOP-OFFNORM-178 - KAVALUE RO: 3.7 SRO: 3.9 KA

REFERENCE:

065 AK3.08 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION:

INSIDE CR: X OUTSIDE CR: BOTH: SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: X LAB: POSITION EVALUATED:

RO: SRO: ACTUAL TESTING ENVIRONMENT:

SIMULATOR: - PLANT SITE: LAB: TESTING METHOD: SIMULATE:

PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 20 minutes REFERENCE(5):

1203.024, Chg. 010-08-0 EXAMINEE'S NAME: SSN: - - EVALUATOR'S NAME: THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

JOB PERFORMANCE MEASURE TUOI NUMBER: AlJPM-RO-AOP28 Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Instrument Air pressure dropping due to unisolable leak on IA main line. ICW RB isolation valves inadvertently closed and will not reopen. Plant Shutdown commenced at >I08 per minute per Rapid Plant Shutdown 1203.045.

PZR Level 290" and trending up. TASK STANDARD:

Rx Tripped, EEW in service, Seal Injection isolated, and RCP's secured with normal and alternate seal bleedoff flowpaths isolated. TASK PERFORMANCE AIDS: 1203.024 Section

2.

JOB PERFORMANCE MEASURE TUOI NUMBER: A1 JPM-RO-AOP28 Page 3 of 4 INITIATING CUE : The SM/CRS directs you to perform 1203.024 Section 2 Lo-Lo Instrument Air Pressure step 3.6 through step 3.6.6. CRITICAL EWNTS (C) : 1, 4, 5, 6, 7, 8 ( C 1 (C) (C) (C) (Cl (Cl (Ci PERFORMANCE CHECKLIST

1. Manually trip Reactor, verify all rods inserted and power dropping.

2. Manually trip the turbine and verify all throttle and governor valves closed. 3. Check adequate SCM. 4. Actuate EEW for both OTSG' s . 5. Isolate Seal Injection by closing CV-1206.

6. Trip all running RCP' s . 7. Isolate Alternate Seal Bleedoff flowpath to the Quench Tank. 8. Isolate Normal Seal Bleedoff flowpath.

STANDARDS On C03, depressed the Rx Trip pushbutton.

On C13, observed all rod bottom lights have come on. On C03 observed power dropping.

On C01, depressed the Turbine Trip pushbutton and verified all TVs and GVs closed. On ICC display on C19 (or C041, verified that SCM is adequate.

On C09, All 4 Em push buttons pushed on EFIC remote matrix. On C04, placed HS-1206 in close position.

On C13 tripped All running RCP' s . P-32A/P-32B/P-32C/P-32D. On C13, placed SV-1270 thru SV-1273 handswitches in closed position.

On C16, close CV-1274 or on C18 close CV-1270 thru CV-1273.

END N/ A - - - - - SAT - - - - - - - UNSAT JOB PEFWORMANCE MEASURE TWO1 NUMBER: AlJPM-RO-AOP28 Page 4 of 4 JPM INITIAL TASK CONDITIONS:

a Instrument Air pressure dropping due to unisolable leak on IA main line.

ICW RB isolation valves inadvertently closed and will not reopen. Plant Shutdown commenced at >lo% per minute per Rapid Plant Shutdown 1203.045.

PZR Level 290" and trending up. INITATING CUE : The SM/CRS directs you to perform 1203.024 Section 2 Lo-Lo Instrument Air Pressure step 3.6 through step 3.6.6.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE CHANGE NO 010-08-0 TC MP DATE NIA IPTE BYES BNO TITLE LOSS OF INSTRUMENT AIR SET # When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/lnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shiftltast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: I FORM NO. I CHANGE NO. VERIFICATION COVER SHEET I 1000.006A 1 050-00-0 DOCUMENT NO 1203.024 WORK PLAN EXP DATE NIA SAFETY-RELATED , BYES DNQ TEMP ALT DYES EN0 SECTlON 2 -- LOW-LOW INSTRUMENT AIR PRESSURE (560 PSIG) DISCUSSION PAGE: 7 Of 24 CHANGE: 010-08-0 PROC.WORK PLAN NO. 1203.024 The air pressure in the IA line(s) nearest the leak will be lower than the indicated air beader pressure.

For this reason, components nearest the leak will exhibit abnormal indication and abnormal control characteristics first.

The longer air pressure rrlndins degraded, the greater the number of malfunctions.

PROCEDUREWORK PLAN TITLE: LOSS OF INSTRUMENT AIR 1f IA pressure continues to degrade, power reduction at the maximum rate is specified to minimize plant impact. Close monitoring of air operated systems and components is required to minimize transients resulting from failures.

For additional discussion, see Attachment D. 1.0 SYMPTOMS i.1 IA header pressure 560 psig. 2.0 IMYEDIATE ACTION None. 3.0 FOLLOW-UP ACTIONS 3.1 Commence plant shutdown at 210% per minute per Rapid Plant Shutdown (1203.045) while continuing with :his procedure.

3.1.1 - IF instrument air pressure recovers

(>60 psig), THEN stop plant shutdown. - 3.2 - IF IA header pressure drops below 35 psig, 02 any system degrades to the extent that in the judgment of the - operator requires reactor trip, THEN GO TO Section 3, "Loss of Instrument Air Pressure (535 PSIG)". - 3.3 Place RCP Seal INJ Block (CV-1206) pushbutton in OVRD (OVRD light On) NOTE - Using HPI Block Valves CV-1220 or CV-1285 will minimize nozzle stress cycles because of the normal makeup path. Pressurizer Makeup Flow Control Valve (CV-1235) will fail as is, when IA pressure drops to -45 psig.

I 3.4 - IF necessary to maintain pressurizer level 5100", THEN use HPI block valves to provide makeup to RCS, or take manua: - control of CV-1235 as follows: 3.4.1 Align srem and gear holes. 3.4.2 Install lock pin. 3.4.3 Open equalizing valve.

SECTION 2

-- LOW-LOW INSTRCMENT AIR PRESSURE (continued) 3.5 IF necessary to maintain pressurizer level

<290", @ ICW is available to RCP seal coolers, THEN perform one or both of the following (3.5.1, 3.5.2) as required: - PAGE: 8 of 24 CHANGE: 010-08-0 PROC.NORK PLAN NO. 1203.024 3.5.1 Isolate seal injection by closing RCP Seal INJ 3lock (CV-1206).

PROCEDURENORK PLAN TITLE: LOSS OF INSTRUMENT AIR 3.5.2 Perform the following:

A. Secure the operating makeup pump. B. Verify letdown isolated.

C. Perform actions of Loss of Reactor Coolant Makeup (1203.026).

3.6 IF ICW is available to RCP seal coolers, @ pressurizer level reaches 290", THEN perform the following:

3.6.: Trip the reactor and perform Reactor Trip (1202.001) in con]unction with this procedure.

3.6.2 Fully actuate ZFW to both SGs. 3.6.3 Close CV-1206. 3.6.4 Trip all running RCPs. 3.6.5 Place the following RCP Seals Bleedoff (Alternate Path to Quench Tank) in CLOSE:

3.6.6 Isolate RCP Seal Bleedoff (Normal) by closing either A or B below: A. CV-1274, or 3.6.7 Refer to 1202.001 and continue with this procedure.

SECTION 2 -- LOW-LOW INSTRUMENT AIR PRESSURE (continued]

3.7 - IF 2VSF-9 is out of service, THEN direct Unit 2 to perform the following due to IA pressure no - longer being sufficient for 2VSF-9 outside air damper operation:

PAGE: 9 of 24 CHANGE: 010-08-0 PROC.MIORK PLAN NO, 1203.024 3.7.1 Declare 2VSF-9 inoperable.

PROCEDUREMlORK PLAN TITLE: LOSS OF INSTRUMENT AIR 3.7.2 Place 2VSF-9 Outside Air Damper (2PCD-86078) in RESIRVE. 3.8 Continue with efforts to rerurn IA pressure to normal as directed by Section 1, "Low lnstrument Air Pressure (575 PSIG)".

Page 1 of 5 JOB PERFORMANCE

!vlEASURE Unit: 1 Rev # 0 Date: TUOf NUMBER: AlJPM-RO-CAO1 Systeduty Area: Chemical Addition System Task: Borate via alternate path bypassing batch controller JA# ANOl-RO-CA-NORM-2 KA Value RO 3.1 SRO 3.3 KA Reference 004 K6.13 Approved For Adminisbation To: RO 5 SRO 5 Task Location: Inside CR:

Outside CR: 5 Both: Suggested Testing Environment And Method (Perform Or Simulate #): Plant Site: Simulate Simulator#:

Lab: Position Evaluated:

RO: SRO: Actual Testing Environment: Simulator

1. Plant Site: Lab Testing Method: Sirnulate:

Perform: Approximate Completion Time In Minutes:

20 Minutes Reference(s):

1305.001, Chg. 017-04-0 Examinee's Name: SSN: Evaluator's Name: The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be: Satisfactory:

Unsatisfactory:

Performance Checklist Comments:

Start Tnne Stop T~me Total Time Signed # Date: # TQ-202 attachment 9 is complete and on file for performance of this JPM for the current Reactor core configuration. Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision TUOI NIJMBER: AlJPM-RO-CAOl THE EXAMTNER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Plant is in process of cooling down for a refueling outage. Boration was in progress to establish refueling boron concentration when batch controller sto!J~ed functionine.

TASK STANDARD: Boration of 200 gallons com~leted with batch controller bvaassed.

TASK PERFORMANCE AIDS: 1103.004 section 9.0 TUOI NUMBER: A1 JPM-RO-CAOI INITIATING CUE: The CRS directs you to bypass the batch controller per section 9.0 of 1103.004 and add 200 gallons of boric acid.

This procedure section is complete through step 9.1.7. CRITICAL ELEMENTS (c): I c 1 PERFORMANCE CHECKLIST I STANDARD I NlA I SAT I UN 1 .............

I .- I.-. ... I... ~E~ylN~Rh2T~:

shcy U-~atec slitei titc nced for a local operalor, then inlontt trrinee a11 operator is a,rilable.

.. - ... --.7 1. Station an operator at FI-1608 with communications Stated the need to station an operator 1 1 withControlRoom.

locally at MU Filter Flow Indicator, I I- ..... ........ 1 ............

L ...... -+ EXAMINER NOTE When rninee slates thc nccd to close C V-1251. thcn inform r~~inec \.;rlvc is closed. . - .......................

........ -. - 7...... -..-...-..l

.. / / 2. Close Condensate to Batch Controller CV-1251. I Called Control Room and requested

/ 1 / I POSITIVE CUE: CV-1251 closed. closure of CV- 125 1 I I I I I 1 3. Verify valves at BAAT closed. 1 At BAAT, verified the following POSITIVE CUE: Valves are closed.

........... . -. ... .- ... 1 ........ -. . - - .- I I EXAMliLER YOTE. Step 0.2.4 is YIA. .. .- - - .......................

.- - - valves closed:

Boric Acid to SFP CA-78 Boric Acid to BWST CA-76 . FI-1608 Bypass CA-1608-3.

--- 4. Unlock and close Boric Acid to Batch Controller, CA- 73. POSITIVE CUE: Unlocked and closed CA-73.

6. Venfy valves at BAAT open. POSITIVE CUE: Valves are closed.

5. Verified CA-72 closed and CA-71 open. POSITIVE CUE: CA-72 closed, CA-71 open. Unlocked and closed Boric Acid to Batch Controller, CA-73. Mentioned need to make Cat-E log entry (not required for full credit).

In "B MU pump room, verified Boric Acid Line Flush to ABD Header CA-72 closed and Boric Acid to Makeup Filters CA-71 open. At BAAT, verified the following valves open: Boric Acid to MU Filters Root Isol CA-69 FI-1608 Inlet CA-1608-1 FI-1608 Outlet CA-1608 - - - - - -

Page 4 of 5 TUOI NUMBER: AlJPM-RO-CAOl POSITIVE CUE: P-39A red light ON. POSITIVE CUE: Trainee calculated 200 gallons. .. .. .........

-....... - - - .... ...... ~x~~MIUEK VOTE. i4fir.r trainre stops punip. then inlonn vrinee that ih i~ire re-aliyunent is uarresaq and ,411. B llis bren opd:itud .. ,.I. ...... .- .. .- .... - .. .-... ... C 9. Stop rnnning boric acid pump.

POSITIVE CUE: P-39A stopped.

At C101, stopped boric acid pump P- 39A. ---

TUOI NUMBER: AIJPM-RO-CAOl INITIAL CONDITIONS:

Plant is in process of cooling down for a refueling outage.

Boration was in progress to establish refueling boron concentration when batch controller stopped functioning.

INITIATING CUE: The CRS directs you to bypass the batch controller per section 9 0 of 1103.004 and add 200 gallons of boric acid. This procedure section is complete through step 9.1.7.

Distractionflnterruption Questioning Affitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShlWLast Shift Peer Pressure Procedures ChangelOff Norma1 Job Briefing PhysDcal Environment I VERIFICATION COVER SHEET 9.0 Boration - Alternate Method From BAAT, Bypassing Batch Controller:

9.1 Initial Conditions PAGE: 22 of 90 CHANGE: 017-05-0 PROC.IWORK PLAN NO. 1103.004 9.1.1 Xakeup and purification system in opcrotion per Makeup & Purification System Operation (1104.002) "System Startup" section. PROCEDURUWORK PLAN TITLE: SOLUBLE POISON CONCENTRATION CONTROL 9.1.2 Chemical addition system aligned per Chemical Addition (1104.003), Attachment F. 9.1.3 - IF manual bleed is :o be initiated, THEN verify the following:

A. Vacuum degasifier either bypassed or in-service per Vacuum Degasifier Operations (1104.016). B. Clean liquid waste system in operation per Clean Waste System Operation (ii04.020), "Initial Startup" seccion. 9.1.1 Sample RCS and boric acid source to determine boron concentration as needed.

NOTE Simultaneous boric acid addition to the Makeup System using both batch controller and bypassing batch controller flow paths is permitted during RCS cooldown in Modes 3 and 4. 9.1.5 Unless during plant cooldown, verify no other transfer of boric acid from BAAT in progress.

NOTE When using the BORON program, any operating conditions may be input. Attachment C and the BORON program automatically add 167,000 lb. to the reactor coolant mass when RCS temperature is < 250.O0F, to account for the decay heat system.

9.1.6 Perform the following calculations:

A. Use Attachment A.3 OR Plant Monitoring System BORON program to determine volume needed. B. Xecord volume of batch to be added on Attachment 9, RCS Liquid Addition Data Sheet. C. Obtain an RO/SRO independent review of calculation and record on Attachment B. D. I_r needed, THEN complete "BAAT Inventory Planning Sheet", - Attachment A.lO.

9.1.7 Ensure adequate storage availability exists for any waste to be generated, if applicable.

PROC.IWORK PLAN NO. 1103.004 Compare volume of feed calculated in above step vs. available T-12s. - IF T-12s cannot receive required volume, THEN transfer applicable 7-12s to Unit 2 per Clean Waste System Operation (1104.020).

PROCEDURUWORK PLAN TITLE: SOLUBLE POISON CONCENTRATION CONTROL NOTE - The following alignment retains the ability to borate to cold shutdown.

For PAGE: 23 of 90 CHANGE: 017-054 boric acid additions, other than boration to cold shutdown, an operator is required at MU Filter Flow IND (FI-1608) for flow monitoring.

I 9.2 Zstablish addition lineup as follows:

9.2.1 Verify the following valves in the '3' MU pump room: Boric Acid Line Flush to ABD Header (CA-72) closed. Boric Acid to Makeup Filters Isol (CA-71) open. 9.2.2 Close Condensate to Batch Controller (CV-i251).

9.2.3 Verify the following valves at the BAAT closed: . Boric Acid to SF Pool (CA-78) e Boric Acid to BWST (CA-76) . FI-1608 Bypass (CA-1608-3)

NOTE I Aliunment for simultaneous addition throuuh batch controller and batch I I coniroiler bypass should not be used except during RCS cooldown in Mode 3 or Mode 4. 9.2.4 - IF this lineup is for simultaneous addition through batch controller AND batch controller bypass during RCS cooldown, THSN verify Boric Acid to Batch Controller (CA-73) open. 9.2.5 - IF lineup is for any other activity, THEN unlock and close CA-73.

A. Make appropriate entry in Category E/Locked Component Log (E-DOC 1015.001H) . 9.2.6 Verify the following valves open at the BAAT:

• Boric Acid to MU Filters Root Isel (CA-69) . FI-1608 Inlet (CA-1608-1) . FI-1608 Outlet (CA-1608-2) 9.2.7 Station an operator at FI-1608 with communications with Control Room. PROC.MIORK PLAN NO. 1103.004 I CAUTION Do NOT run a boric acid pump dead-headed for more than 30 seconds. 1 NOTE - Local operation of boric acid pumps must be performed by a licensed operator, or an RO trainee in the presence of a licensed operator.

PROCEOURElWORK PLAN TITLE: SOLUBLE POISON CONCENTRATION CONTROL 9.3 Operate Boric Acid Pump(s) (2-39A or P-39B or both) locally from Boric Acid Panel ClOI OR remotely from C04 to add desired volume recorded on Attachment B. PAGE: 24 of 90 CHANGE: 017-05-0 9.3.1 Calculate volume addition by multiplying MU Filter Flow IND (FI-1608) flow rate by time in minutes BA pump(s) are run. 9.3.2 Verify RCS concen~ration at each 30 ppmB interval by chemistry sampie. 9.4 WHEN desired addition is complete AND it is desired to realign the Batch Controller, THEN perform the following: - 9.4.1 Stop the running boric acid pump(s). 9.4.2 Close CA-71. 9.4.3 Close CA-69.

9.4.4 - IF CA-73 was closed, THEN perform the following:

A. Cpen CA-73.

3. Lock CA-73. C. Complete required encry on Category E/Locked Component Log (E-DOC 10i5.001H).

D. lerform required Independent Verification that CA-73 is open AND locked.

E. Complete rcquired entry on Category E/Locked Component Log (a-DOC 1015.001H).

9.5 Update Attachment

3.

TUOI NUMBER: A I JPM-RO-EFWO 1 Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev # 11 Date: 01/12/2004 TUOl NUMBER: AIJPM-RO-EFWO 1 System'Duty Area: Emergency Feedwater and EFIC Task: Reset the Steam Driven Emergency Feedwater Pump after an overspeed trip JA# AN0 1 -RO-EFW-NORM-13 KA Value RO 3.4 SRO 3.8 KA Reference 061 A2.04 Approved For Administration To: RO [XI SRO [XI Task Location:

Inside CR. C] Outside CR:

[XI Both: C] Suggested Testing Environment And Method (Perfom Or Simulate):

Simulate Plant Site: Perform Simulator:

Lab: Position Evaluated:

RO: X SRO: X Actual Testing Environment: Simulator: Plant Site:

Lab Testing Method: Simnlate:

X Perform: Approximate Completion Time In Minutes: 15 Minutes Reference(S):

1106.006 Exhibit A and Exhibit B, change 064-07-0. Examinee's Name:

SSN: Evaluator's Name: The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be: Satisfactory:

Unsatisfactory: Performance Checklist Comments:

Stan Time Stop Tie Total Time Signed Date: Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

TUOI NUMBER: AlJPM-RO-EFWOI THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

P7A Emergency Feedwater Pump has tripped on overspeed during an EFIC actuation.

TASK STANDARD:

P7A turbine has been reset per 1106.006 Exhibit A. TASK PERFORMANCE AIDS:

OP 1106.006 Exhibit A and B SIMULATOR SETUP: N/A TUOI NUMBER: AlJPM-RO-EFWO1 INITIATING CUE: The SMICRS directs you to reset P7A overspeed trip per 1106.006, Exhibit A CRITICAL ELEMENTS (c): 2.3, and 8 C PERFORMANCE CHECKLIST STANDARD N/A SAT UN - -- ..........

SAT ...... . . ... ..... .. .. EXAMINER'S NOTE: Simulate communications with the Control Room. .. ... ,. -, -. ... - ..... ..... . . .. ..... ...-.. ..-. - -. -. ... 1. Verify the following valves are closed. If ERN initiate signal is present, manual control is required.

EFW Pump Turbine K3 Steam Admission Valves (CV-2613 and CV-2663)

EFW Pump Turbine K3 Steam Admission Valve Bypasses (SV-2613 and SV-2663)

POSITIVE CUE: SV-2613, SV-2663, CV-2613. CV-2663 have valve stems full out with handwheel's full CW. 2. Tum EFW Turbine K3 Trip-Throttle Valve (CV- 6601A) handwheel clockwise. Observe rotation of screw raises sliding nut and latch lever to where it will engage the trip hook. POSITIVE CUE: Trip/ Throttle valve (CV5601A) sliding nut raised and latch lever has engaged the trip hook. Called control room to verify SV- 261 3, SV-2663, CV-2613, CV- 2663 are closed. Trip1 Throttle valve (CV-6601A) handwheel turned clockwise until sliding nut rises and latch lever engages the trip hook. POSITIVE CUE: Head lever moved away from tappet and tappet nut. I C Connecting rod pulled against spring force to move head lever away from tappet and tappet nut. 3. Pull spring-loaded connecting rod against spring force to move head lever away from tappet and tappet nut. 4. Lift and release tappet assembly POSITIVE CUE: Tappet assembly lifted and released.

Tappet assembly lifted and released.

5. Verify tappet nut in trip reset position POSITIVE CUE: Tappet nut in trip reset position Verified tappet nut in trip reset position.

TUOl NUMBER: AIJPM-RO-EFWO1 1 1 6 Obsewe tappet returns to reset position C PERFORMANCE CHECKLIST

.- . .. .......................

..... - I ! POSITIVE CUE: Tappet is in reset position.

7. Verify the following: Tappet nut in trip reset position and properly aligned. . Spring tension holds connecting rod in position.

STANDARD Observed tappet returns to reset position.

POSITIVE CUE: Tappet nut in trip reset position and properly aligned Spring tension is holding connecting rod in position.

SAT NIA --- Verified tappet nut in trip reset position and properly aligned. Verified spring tension holds connecting rod in position.

UN SAT .... POSITIVE CUE: CV-6601A has valve stem full out with handwheel in the full CW position.

C CV-6601A fully opened. 6. Slowly turn CV-66OlA handwheel counterclockwise until valve is fully open. 9. Close valve (CV-6601A) 314 turn to prevent binding on heatup. CV-6601A closed 314 turn. --- 10. Verify P-7A TURBINE TRIP (K12-85) clear. POSITIVE CUE: P-7A TURBINE TRlP (K12-85) clear ........................

I 1 1 ........__L 1 EXAMINERS CUE: This concludes the JPM. -- -- .... . . ..... --- .. . ................

I 11. Notify Control Room that P-7A is ready for restart. POSITIVE CUE:

Control Room notified that P-7A is ready for restart. Call Control Room and verified that P-7A TURBINE TRlP (K12- 55) is clear. Control Room notified that P-7A is ready for restart. - --- - -

TUOI NUMBER: AIJPM-RO-EFWO1 EXAMINEE'S COPY INITIAL CONDITIONS:

P7A Emergency Feedwater Pump has tripped on overspeed during an EFlC actuation.

INITIATING CUE: The SMICRS directs you to reset P7A overspeed trip per 1106.006, Exhibit A.

When you see these mme Pressure Effective Communication Distractionnnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast ShiR Peer Pressure Procedures ChangelOff Normal Job Briefing

- PROC.IWORK PLAN N

O. PROCEDURE

MlORK PLAN TITLE: PAGE: 60 of 193 1106.006 EMERGENCY FEEDWATER PUMP OPERATION CHANGE: 064-074 I 04/30/05 EXHIBIT A Page 1 of 2 EMERGENCY FEEDWATER PUMP ?-7A OVERSPEED TRIP RESET

/ 1.0 Verify the following valves are closed:

I i 1.1 - IF EFW initiate signal is present, THEN manual control is required: - . EFW Pump Turbine K3 Steam Admission Valve (CV-26131 2FW Pump Turbine K3 Steam Admission Valve (CV-26631 Em Pump Turbine K3 Steam Advission Valve Bypass (SV-26131 8 EFW ?ump Turbine K3 Steam Admission Valve Bypass (SV-26631 1 2.0 Turn EFW Turbine K3 Trip/Throttle Valve (CV-6601A) handwheel clockwise.

I I 2.1 Observe rotation of screw raises sliding nut and latch lever to where it wil; engage the trip hook. 3.0 Manually reset mechanical trip linkage as follows: I I 3.1 Pull spring-loaded connectinq rod against spring force to move head lever away from tappet and tappet nut. 3.2 Lift and release tappet assembly.

I I 3.2.1 Observe tappet returns to reset position.

I CAUTION If necessary to manually push tappet down into position, force must be - applied straight downward to prevent bending aluminum tappet. 3.2.2 - IF tappet spring force did not move tappet into proper position, THEN manually press tappet straight downward into position. - 3.2.3 IF it was necessary to manually reposition tappet, - THEN notify CXS, - AND upon completion verify Condition Report initiated. -

1106.006 04/30/05 EXHIBIT A Page 2 of 2 EMERGENCY FEEDWATER PUMP P-7A OVERSPEED TRIP RZSET PROC.MIORK PLAN NO. 1106.006 NOTE Flat side of tappet nut must be alignem the flat of the head lever (parallei to shaft).

Otherwise latch lever and trip hook can disengage when CV-6601A is opened. 3.3 Verify the following:

PROCEOURE~ORK PLAN TITLE: EMERGENCY FEEDWATER PUMP OPERATION A. Tappet nut in trip reset position AND properly aligned.

PAGE: 61 of 193 CHANGE: 064-07-0 B. Spring tension holds connecting rod in position.

NOTE I .. . -- - Steam pressure trapped between Steam Admission Valves and CV-6601A will be admitted to turbine when CV-6601A is opened and may result in turbine I rotation.

CV-6601A must indicate open to clear overspeed trip alarm.

3.4 Slowly turn CV-660lA handwheel counterclockwise until valve is fully open. 3.4.1 Close valve 3/4 turn to prevent binding on heatup. 3.4.2 Verify 2-7A TURBINE TRIP (K12-B5) clear. 4.0 Notify Control Room that P-7A is ready for restart.

1106.006 EXHIBIT B PROC.NVORK PLAN NO. 1106.006 EMERGENCY FEEDWATER PUMP P-7A OVERSPEED TRIP MECHANISM - PROCEDURENVORK PLAN TITLE: EMERGENCY FEEDWATER PUMP OPERATION PAGE: 62 of 193 CHANGE: 064-07-0 TUOI: AIJPM-RO-ED030 JOB PERFORMANCE MEASURE Page 1 of 5 UNIT: 1 REV#L DATE: TUOI NUMBER:

A1lPM-RO-ED030 SYSTEMDUTY AREA: BATTERY AND 125V DC DISTRIBUTION TASK: PLACE BATTERY CHARGER D-03B IN SERVICE .lTA#: ANO1-AO-125DC-NORM-I2 KA VALUE RO: 3.9 SRO: 3.4 KA

REFERENCE:

2.1.30 APPROVED FOR ADMINISTRATION TO: RO: X SRO. X TASK LOCATION: INSIDE CR: OUTSIDECR:

X BOTK: SUGGESTED TESTJNG ENVIRONMENT AND METHOD (T'ERFORM OR SIMULATE):

PLANTSITE:

X SIMULATOR:

LAB: POSITION EVALUATED:

RO: X SRO: X ACTUAL TESTING ENVIRONMENT:

SIMULATOR:

PLANTSITE: X LAB: TESTING METHOD: SIMULATE: X PERFORM: APPROXIMATE COMPLETION TIME IN MINUTES: 20 MINUTES REFERENCE(S):

1107.004, Che. 012-13-0 EXAMINEE'S NAME: SSN --..--- EVALUATOR'S NAME THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE: SATISFACTORY:

UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS: Start Time Stop Time Total Time SIGNED DATE: SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE)

AND IS CURRENT WITH THAT REVISION.

JOB PERFORMANCE MEASURE TUOI: AIJPM-RO-ED030 Page 2 of 5 THE EXAMINER SHALL REVIEW TEE FOLLOWING WITH THE EXAMINEE: The examiner shall review the "Briefing Checklist - System Walkthrongh" partion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Battcrv Charger D-03A is in service on Battew DO1 TASK STANDARD:

IAW 1107.004, Att. B, examinee places charzer D-03B in service, removes D-03A from service, and performs actions for D-03A DC output voltage drifting to zero. THIS IS AN ALTERNATE SUCCESS PATH JPM. TASK PERFORMANCE AIDS: 1107.0004 Attachment B

JOB PERFORMANCE MEASURE TUOI: AlJPM-RO-ED030 Page 3 of 5 INITIATING CUE: The Shift Manager requests you to place Battery Charger 0-038 in service on Bus DO1 and remove Battery Charger D-03A from service. CRITICAL ELEMENTS (C) 5.6. 8, 9. 12, 15, 17 (C) I Pf;KI;ORZIA?ICL:

CHECKLIST 1 STASDARD 1 NJA I SAT /USSAl' I I 1. Verify breakers open for charger 0-038. AC lnput breaker DC Output breaker

2. Verify AC feeder breaker to charger 0-038 closed (8-5733).

On front of charger 0-038, verified the AC lnput and DC Output breakers open (OFF). Verified breaker B-5733 closed (ON) 3. Verify charger D-03B supply to bus Inside panel D01, verified breaker breaker closed (DO1 -42). DO1 -42 closed (ON). - - 4. Verify Manual Disconnect for At D13, verified manual disconnect - - battery 0-07 closed (D-13). for battery DO7 closed (ON). 5. Close D-038 AC Input breaker.

On front of charger 0-038, closed the AC Input breaker (ON). 1-1-1 1 1 6. Close 0-038 DC Output breaker. On front of charger 0-038, closed the DC Output breaker (ON). 1-1 7. Wait -1 minute for automatic load sharing to occur.

CUE: Amps are rising on D-038 output ammeter and amps are falling on D-03A output ammeter. 8. Open D-03A DC Output breaker. Waited -1 minute, observed rising amps on D-03B and falling amps on D-03A. On front of charger D-03A, opened the DC Output breaker (OFF). (c) 9. Open D-03A AC lnput breaker. I I On front of charger D-03A, opened the AC Input breaker (OFF). 1-1-1 JOB PERFORMANCE MEASURE TUOI: AlJPM-RO-ED030 Page 4 of 5 (c) ! PERFORMANCE CHECKLIST STANDARD I N/A I SAT 1 UNSAT 10. Check Charger D-03B picks up load. CUE: . D-036 DC Out -100 amps AC In -30 amps DO1 bus voltage 130V At charger D-03B checked ammeter deflected to a nominal value, and at DO1 checked bus voltage maintained at -130 volts. 12. Place 0-038 alarm to control room At charger 0-038, placed control toggle switch ON. room alarm switch to ON (up). l-lp1-! 11. Reset local alarm panel for Charger D-038. I I 13. Place D-03A alarm to control room At charger D-03A, placed control toggle switch OFF. room alarm switch to OFF (down). I-14-l 14. Check annunciator DO1 CHARGER TROUBLE (K01-E7) clears. At charger D-036, pressed "R" button on RIS panel.

Called control room and requested check for clear annunciator K01-E7. I I I I I I ALTERNATE PATH CUE: Inform examinee that D-03A DC Output Voltage drifted to zero, also inform examinee that one minute has passed since D-03A was de-energized.

I I I I - I I 15. Close D-03A AC lnput breaker. 16. Check D-03A DC output voltage and AC input voltage. - CUE: DC Output Voltage -90V AC lnput Voltage -480V - I (q I 17. Open D-03A AC lnput breaker. 18. Submit condition report and WR. On charger D-03A, obsewed DC output voltage and AC input voltage meters. On front of charger D-03A, closed the AC Input breaker (ON). Examinee stated that he would contact electrical maintenance for support. --- On front of charger D-03A, opened the AC Input breaker (OFF).

1-1/-1 Examinee stated that he would submit a condition report and Work Request or Work Order on D-03A. I I I I I JPM Complete JOB PERFORMANCE MEASURE EXAMINEE'S COPY Page 5 of 5 JPM INITIAL TASK CONDITIONS:

Battery Charger D-03A is in service on Bus DO1 INITIATING CUE: The Shift Manager requests you to place Battery Charger D-03B in service on Bus DO1 and remove Battery Charger D-03A from service per 1107.004, Battery and 125V DC Distribution, Attachment B.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE CHANGE NO 012-130 TC EXP DATE NIA IPTE @YES UNO TITLE BATTERY AND 125V DC DISTRIBUTION SET # DOCUMENT NO 1107.004 WORK PLAN EXP DATE NIA SAFETY-RELATED NYES ONO TEMP ALT nYES EN0 When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiWLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: VERIFICATION COVER SHEET FORM NO. 1000.006A CHANGE NO. 050-00-0 ATTACHMENT B Page 1 of 3 PROC.MI0RK PLAN NO. 1107.004 PLACING BATTERY CHARGER D-03B INTO SERVICE NOTE - Section 1 contains instructions for placing D-03B into service with D-03A to be removed from service. PROCEOURENVORK PLAN TITLE: BATTERY AND 125V DC DISTRIBUTION Section 2 contains instructions for placing D-03B into service with D-03A out of service. PAGE: 24 of 97 CHANGE: 012-13-0 1.0 To place Battery Charger for DO1 (D-03B) into service and remove charger D-03A from service, perform the following:

1.1 Verify the following breakers open for charger D-038: A. D-03B AC Input Breaker on charger cabinet front. B. D-038 DC Output Breaker on charger cabinet front. 1.2 Verify the following breakers closed for charger D-03B: A. Battery Charger D-038 (B-5733) B. Supply from Battery Charger D-038 (D01-42).

Breaker inside cubicle, no external handle. 1.3 Verify Battery D-07 Manual Disconnect (D-13) closed 1.4 Close D-03B AC Input Breaker on cabinet front CAUTION Cycling Battery Charger Output Breaker could cause inservice inverters associated with this Battery Charger to swap to alternate source and blow fuses. 1.5 Close D-03B DC Output Breaker on cabinet front.

NOTE - Automatic load sharing should equalize the charger load within

-1 minute. However it is not necessary to wait if load does not equalize.

1.6 Wait -1 minute to check for automatic load sharing (rising amps on D-03B, falling amps on D-03A, and then stabilizes).

1.6.1 - IF load sharing does NOT occur, THEN check D-03B DC output voltage

-130 volts AND continue. -

ATTACHMENT B Page 2 of 3 NOTE - Opening the DC Output Breaker for D-03A may cause its DC output voltage to drift to zero and Local Alarm Panel lights to fade. (CR-ANO-2-2003-0423).

PAOE: 25 of 97 CHANGE: 012-130 PROC.MIORK PLAN NO. 1107.004 Open D-03A OC Output Breaker on cabinet front PROCEDURE~ORK PLAN TITLE: BATTERY AND 12% DC DISTRIBUTION Open D-03A AC Input Breaker on cabinet front. Check charger D-03B picks up load to maintain proper DC bus voltage: 1.9.1 Charger ammeter deflects to some nominal value 1.9.2 Bus DO1 voltage is maintained at -130 volts. Reset local alarm panel for charger D-03B. Place D-03B alarm to control room toggle switch ON Place D-03A alarm to control room toggle switch OFF. Check annunciator DO1 CHARGER TROUBLE (K01-E71 clears IF D-03A DC output voltage drifted to zero when its DC - output breaker was opened, THEN perform the following to prove D-03A operability: - 1.14.1 Ensure -1 minute has passed after de-energizing D-03A 1.14.2 Close D-03A AC Input Breaker on cabinet front 1.14.3 Check 0-03A DC output voltage - 130 VDC. 1.14.4 Check D-03A AC input voltage normal - 480 VAC IF D-03A DC output voltage does NOT return to normal, 1.14.5 - THEN contact electrical maintenance for support. - 1.14.6 Open D-03A AC Input Breaker on cabinet front 1.14.7 Perform the following even if D-03A is operable: . Submit Condition Report ATTACHMENT B Page 3 of 3 2.0 To place Battery Charger for DO1 (D-03B) into service with charger D-03A out of service, perform the following:

PAGE: 26 of 97 CHANGE: 012-13-0 PROC.MIORK PLAN NO. 1107.004 2.1 Verify the following breakers open for charger D-03B: PROCEDUREWORK PLAN TITLE: BATTERY AND 125V DC DISTRIBUTION A. D-038 AC Input Breaker on charger cabinet front. B. D-03B DC Output Breaker on charger cabinet front. 2.2 Verify the following breakers closed for charger D-03B: A. Battery Charger D-038 (8-5733) B. Supply from Battery Charger 0-038 (D01-42). Breaker inside cubicle, no external handle.

2.3 Verify Battery D-07 Manual Disconnect (0-13) closed. 2.4 Close 0-038 AC Input Breaker on cabinet front 2.5 Close D-03B DC Output Breaker on cabinet front.

2.6 Check charger D-03B picks up load to maintain proper DC bus voltage: 2.6.1 Charger ammeter deflects to some nominal value 2.6.2 Bus DO1 voltage is maintained at -130 volts. 2.7 Reset local alarm panel for charger D-03B. 2.8 Place D-03B alarm to control room toggle switch ON 2.9 Check annunciator DO1 CHARGER TROUBLE (K01-E7) clears.

ES-301 Transient and Event Checklist Form ES-301-5 I. Circle the applicant level and enter the operating test number and Form ES-D-I event numbers for each event type; TS are not applicable for RO applicants.

ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (IIC) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*)Reactivity and normal evolutions may he replaced with additional instrument or component malfunctions on a I-for-l basis. Author: NRC Reviewer:

ES-301, Page 26 of 27 ES-301 Competencies Checklist Form ES-301 Instructions:

Facility:

ANO-1 Date of Examination: 9/12/2005 Operating Test No.: 2005-1 Circle the applicant3 license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Competencies ES-301, Page 27 of 27 Interpret 1 Diagnose Events and Conditions (1) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U. (3) Only applicable to SROs. APPLICANTS RO (ATC) / RO (BOP) 11 SRO-U SCENARIO SCENARIO SCENARIO ES-301 Competencies Checklist Form ES-301-6 Instructions:

Facility:

ANO-1 Date of Examination: 9/12/2005 Operating Test No.: 2005-1 Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Competencies Interpret I Diagnose Events and Conditions Comply With and Use Procedures (1) Operate Control Boards (2) Communicate and ES-301, Page 27 of 27 (1) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U. (3) Only applicable to SROs. APPLICANTS SRO-I SCENARIO 1 3,5,6,7 1,2,3,4,5, 6,7,8,9 NIA 1,2,3,4,5, 6,7,8,9 SRO-I (ATC)

SCENARIO 1 2 1,2,3,6,7 1,2,3,4,5, 6,7,8,9 NIA 1,2,3,4,5, 6,7,8,9 2 2,3,6,7 1,2,4,5,6,7 1.2,4,5,6,7

---

1,2,3,4,5, 6,7 3 2,4,5,6,7,8 1,2,3,4,5, 6,7,8,9 NIA 1,2,3,4,5 673 4 2,4,5,6 1,2,3,4,5, 6.7,s NIA 1,2,3,4,5

,6,7,8 3 4 A~~endix D Scenario 1 Form FS-D-1 pleted. Condensate s in "MANUAL".

3 4 5 6 7 8 9 TR565 Ramp=4 Min. N/A RX604 30%/min. ED191 ED183 IRF ~~3807 IRF 86231 DI-A-MSLI-lA False DI-A-MSLI-18 False DI-A-MSLI-ZA False Dl-A-MSLI-28 False Dl-8-MSLI-1A False Dl-8-MSLI-1B False Dl-8-MSL12A False Dl-8-MSLI-28 False * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I (CBOR) N (CBOR) C (CBOT) C (CBOT) M (All) C (CBOT) C (CBOR) J maintenance to main Feedwater pump and after Heater Drain Pumps in service. RCS That slowly fails low Place the ICS in AUTO. False increasing pulser signal to EHC causes Turbine Generator to raise load. Loss of non vital bus 83 Random electrical grid upsets result in loss of offsite power. Reactor trip. Degraded Power. EDG #2 service water valve (CV3807) breaker trips during opening causing minimal flow to the EDG for cooling. All MSLl pushbuttons on the EFlC Remote Switch Matrix fail to manually actuate the MSLl function requiring alternative effort for performing function.

ADDendix D Scenario 1 Form ES-D-1 Scenario #I Obiectives

1) Evaluate individual response to input signal failures to the lntegrated Control System 2) Evaluate individual response to electrical system abnormal conditions

3) Evaluate individual response to a loss of offsite electrical power

4) Evaluate individual ability to start and control components of the feed and condensate system 5) Evaluate individual ability to perform a power escalation in accordance with plant procedures

6) Evaluate individual ability to recognize abnormal conditions associated with automatically actuated systems and components 7) Evaluate individual response to failure of actuation function associated with the Main Steam Line Isolation portion of EFlC SCENARIO #I NARRATIVE The scenario begins with a power escalation to 100%

in progress following maintenance to the "A" Main Feedwater pump. Power has been stabilized at -70% to place the heater drain pumps in service to provide sufficient feedwater pump suction pressure to continue the power rise to 100%. The crew will place the second heater drain pump in service and begin the power escalation.

As power is raised toward

-80% power, an RCS hot leg temperature transmitter, that is providing input to the lntegrated Control System, fails low. This failure, being a slow failure, and therefore the Smart Automatic Signal Selector system will not select the redundant instrument, causes a plant transient that will include control rods to withdraw and feedwater flow to be lowered. The crew is expected to intervene and stop the transient by placing the ICS in "Manual" mode and correct the affected plant parameters to stabilize the plant. Once stable, the crew will select the redundant (good) instrument to provide input to the ICS and perform the normal operation of placing the ICS in "Automatic" mode. When the ICS is placed in "AUTO" following the temperature transmitter failure, the Turbine will begin rising without a commanded signal. The crew should recognize the rising turbine load and lowering of the turbine header pressure and place the turbine in a manual mode, either "OPER AUTO" or "Turbine Manual".

Contacts to support organizations should begin to troubleshoot the turbine malfunction. The Turbine will remain in a manual mode at this time. An internal breaker fault in the feeder breaker to the non-vital B3 bus will cause the breaker to trip, causing a loss of the non-vital 83 bus. The crew is expected to respond to the loss of B3 using Annunciator Corrective Actions and Abnormal Operating Procedure for Loss of Loadcenter.

The crew will start redundant equipment as directed by the operating procedures and stabilize the plant.

eegendlx D Scenario 1 Form FS-D-1 SCENARIO #I NARRATIVE (continued)

Due to random electrical grid upsets in the system, a loss of offsite power will occur. The Reactor will trip automatically and the crew will begin addressing the Reactor Trip and degraded power situation. Once the Reactor Trip immediate actions have been completed, the crew will transition to the Degraded Power procedure for guidance.

While verifying the proper operation of actuated components due to the degraded power, the discovery of the service water valve to the

1. 2 EDG failure will require the crew to take action to restore service water to the EDG or stop the EDG to protect it from damage due to overheating.

During performance of actions required by the Degraded Power procedure, the crew will be prompted to actuate MSLl on both OTSGs to establish a "vital island" concept for the heat removal from the primary to the secondary.

When the operator attempts to actuate the function from the normally utilized remote switch matrix, the matrix buttons fail to execute the command. The crew must take contingency action to establish the MSLl function.

This may be accomplished by manual positioning of the affected components or actuation of the function from the EFIC cabinets in the back of the control room. The scenario will be terminated when the plant is at a point where the crew is awaiting the return of offsite power or at the discretion of the lead evaluator.

hendix D Scenario 1 Form ES-D-1 Simulator Instructions for Scenario 1 8 9 T=67 Pre-loaded hi^ event will occur when the crew step to actuate MSLl ED183 Actuate Trigger 1 IRF ~~3807 IRF 86231 DI-A-MSLI-IA Dl-A-MSLl-1B DI-A-MSL1-2A DI-A-MSLIZB Dl-8-MSLI-?A Dl-8-MSLI-18 Dl-8-MSLI-ZA 01-0-MSLI-20

.05 OFF False False False False False False False False EDG #2 service water valve (CV3807) breaker trips during opening causing minimal flow to the EDG for cooling. All MSLl pushbuttons on the EFlC Remote Switch Matrix fail to manually actuate the MSLI function requiring alternative effort for performing function.

Appendix D Required Operator Actions Form ES-D-2 CRS Direct the crew to place the "B Heater Drain Pump in service per 1106.016, I T=O I I Condensate, Feedwater, and Steam System Operation.

I CBOT I At panel CIZ. Start P8B. CBOT Monitor Heater Drain Pump discharge flow on the plant computer.

CBOT Dispatch the Auxiliary Operator to gradually open the manual discharge valve for P8B, (CS-59B), approximately 5 turns.

IA NOTE: To open CS59B; IRF CS59B .35 60 CBOT Using the controller on C12 for CV2810, slowly throttle closed the associated Recirc Control Valve. Monitor drain tank level, P8B discharge flow, and main feedwater pump suction pressure, while slowly lowering T40B level. CREW When discharge flow is approximately 0.5 X lo6 lblhr, verify K06-A8 (P8AIP8B FLOW LO) clears.

CBOT WHEN T-40 level

-1 1 I", THEN place Recirc Control Valve in AUTO. CBOT Verify Recirc Control Valve maintains Heater Drain Tank I I level -1 11" (-49%).

CBOT Coordinate with the Auxiliary Operator to complete the alignment per the procedure.

I CBOT 1 Return idle Condensate Pump.

P-2, handswitch to normal-after-stop I CBOT I Close Low Level Condenser Sprays (CV-2901 and CV-2868) on C02 I I Event Termination:

P8B in service with recirc valve in AUTO - -- . -. .- Page 5 of 13 Appendix D Required Operator Actions Form ES-D-2 applicable procedures, instructions, ODMls, etc. NOTE: The normal maneuvering rate for this situation would be 30°h/Hr. however due to the small failed fuel the unit is experiencing, Reactor Engineering has recommended a rate of 15%/Hr. to 90% power, and 5%/Hr. to 100% in accordance with the ODMl established for this condition. (This begins the power escalation to approximately 90% power.)

Appendix D Required Operator Actions Form ES-D OpTest No: 2005-1 Scenario No: 1 Event No:

3 Event

Description:

RCS Tm slowly fails low

... - Time - Applicant's Actions or Behavior - ... -- Cued by CBOR Acknowledge and report annunciator alarm K07-B4, SASS Mismatch, is in Evaluator alarm. CBOR Identify the SASS enable light for the loop "A" Thot instrument on C03 has gone out. 1 CBOR I Identify a plant transient is in progress II I CRS I Direct the CBOR to place ICS in "MANUAL" (At a minimum, the "A" and "B" feedwater loop demands and the Reactor Demand HandIAuto stations should be placed in "MANUAL")

CBOR Place the "A" and "B feedwater loop demands and the Reactor Demand CT handlauto stations in "Manuai" and verify the transient stops. IF the control rods continue to move, place the Diamond Station in "MANUAL".

I I CRs I Direct the crew using Annunciator Corrective Action 1203.012F for the SASS Mismatch alarm. I CBOT Verify the signal from the non-selected instrument is a valid good signal on PMS. 1 CBOR I When directed. select the opposite instrument for Loop "A" Thot on C03 1 CBOR 1 Verify the proper response to the selection of the good instrument.

Y CRS Direct the crew to slowly adjust control rods and feedwater to restore Tave back to the desired value. CBOR Slowly adjust feedwater demand stations and control rods to return Tave to -579°F. u I I Event Termination: Next event I .-

Appendix D Required Operator Actions Form ES-D-2 (This may require placing the SGlRX Master to "HAND") approximately equal.

A. Rod Controller (Diamond Panel), if applicable

0. Reactor Demand C. Feedwater Loop Demands D. Load Ratio AT-cold E. SGlRX Master Page 8 of 13 Appendix D Required Operator Actions Form ES-D-2 NOTE: The CRS may also direct the placement of the SGlRX Master station to "HAND", but is not Appendix D Required Operator Actions Form ES-D-2 associated with electrical distribution and AMP meters on C10. Verify Backup Air Side Seal Oil Pump P-25 running. Operations (1 107.001) to determine any additional components that may Appendix D Required Operator Actions Form ES-D-2 Direct immediate actions per the Reactor Trip Procedure, 1202.001. the CRS when asked. Direct operations per 1202.007. frequency and foading: 41 00 to 4200V 59.5 to 60.5 Hz Appendix D Required Operator Actions Form ES-D-2 CBOR CRS CBOR CRS CBOT time delay (P4A, B, C). Actuate MSLl for both SGs AND verify proper actuation and control of EFW and MSLl (RT 6): Identify that the remote switch matrix will not work to actuate MSLl for either OTSG on either train. (Tech. Spec.

3.3.12 Emergency Feedwater lnitiation and Control (EFIC) Manual Initiation)

Two manual initiation switches per actuation train for each of the following EFlC Functions shall be OPERABLE:

a. Steam generator (SG) A Main Steam Line Isolation;

b. SG B Main Steam Line Isolation; and

c. Emergency Feedwater (EFW) Initiation.)

Direct the CBOR to manually close the MSlVs and MFlVs on panel C09 or use the trip modules in the EFlC cabinets to actuate MSLl for both OTSGs.

Close the MSlVs and MFlVs for both OTSGs using the handswitches on C09 OR go to the EFlC cabinets and actuate MSLl for both OTSGs on both trains on the trip modules. Verify the actions per RT6 steps C. and D. Check RCS press remains 21700 psig AND PZR level remains 230. Isolate Letdown by closing either: Letdown Coolers Outlet (CV-1221)

OR Letdown Cooler Outlets (CV-1214 and 1216). -Continued-Appendix D Required Operator Actions Form ES-D-2 (Tech. Spec. 3.8.1.6, Two diesel generators (DGs) each capable of supplying one train of the onsite Class 1E AC Electrical Power Page 13 of 13 UNIT I SHIFT RELIEF SHEET Computer Generated Form (ref. 1015.015)

Page 1 of 2 . .- L- ... - .... .- .. . _..A-. ......... power maneuver will be performed wing the Integrated Control System (ICS). Contingency Reactivity Plans are-.? located in the Plant Data Book and at ANONJlOPSlAPPSlContingency RX Plans. ........ ...-.-.. . ..-- ...... ......- . -- DAT* : ACTION STATEMENTS IN EFFECT (TS/TRM/ODCM/FS ETC) None CONTROL ROOM ALARM STATUS K05-A5 MSRiT40 CRITICAL DRN TROUBLE 9/13/2005

......... . - .,., . .........

..*.>.. ........ .-, -":. .z:>~: ..... :.., . .........

..... a<$.>,:>K>z<$&:>, ....'.. :,:>,. EVOLUTIONS IN PRO(iRES5 70% power holding for the start of P8B (2nd heater drain pump). Heater Drain 1106.016, section 16.0 through 16.19. Step 16.20 is ready to be performed and P8B tions for the start of P8B have been completed. Condensate Pump, P2A, is in P-T-L per the procedure "MANUAL".

Power escalation to 100%

in progress following maintenance to the "A" MFW PLANT POWER : 70% a lnjec ion control valve is in hand. Small fuel leak based on RCS isotopic analysis for Cycle 19.

WMC/FIN REQUESTS Power escalation to 100%

ONCOMING SHIFT. PLANTMODE

' 1 CREW Days DAYS ON UME ' YOU= 250 CHEDULU) RISK: MMNTTWUN . MINIMAL RED UNIT I SHIFT RELIEF SHEET Computer Generated Fon (ref. 1015.015)

Page 2 of 2 CHEMISTRY

/ Malntaln >30# hydrogen pressure m the Makeup Tank. r I OFF-GOING SHIFT SIGNATURE CRSISM OTHER UNIT IMPACT SWTCHYARD ACnVtTIES COMPENSATORY ACTIONS None None . SPP OnMTii ADDendlx D Scenario 2 Form ES - D - 1 Page 1 of 13 i f er; Equilibrium xenon per 1104.002, Section 19.2. 2 3 4 5 6 7 8 9 * (N)omlal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor CV1008 .I2 FW087 NIA Dl-lCC0009L False TR049 0 RCOOl (.325) R20:OO Dl-H15C False CO-P75 C (CBOR) C (CBOT) R (CBOR) C (CBOR) I (CBOR) M (ALL) R C (CBOT) C (CBOT) concentration Pressurizer Spray Valve fails open Heater drain pump "B bearing heat up resulting in need to trip the pump. Pump will trip if no action is taken. (2 min.15 sec.- alarm, 3 min. 15 sec. -trip) Lower power to -70% in response to a trip of a heater drain pump ULD station fails to lower demand signal in manual Pressurizer level transmitter fails low OTSG tube leak progressing to a -150 gpm. HI feeder breaker from SU#1 transformer fails to close when transferring auxiliaries.

P75 will not start Aooendtx D Scwr~o 2 Form ES-D-1 Scenario #2 Objectives

1) Evaluate individual response to a feedwater and condensate system component failure. 2) Evaluate individual response to an Integrated Control System failure.

3) Evaluate individual response to a transmitter signal input failure to a controlling - function.

4) Evaluate individual response to an electrical breaker failure

5) Evaluate individual response to an OTSG tube leaklrupture.

6) Evaluate individual ability to lower plant load in accordance with plant procedures.

7) Evaluate individual ability to operate controls to equalize boron concentrations between Reactor Coolant System and Pressurizer.

8) Evaluate the individual response to a failure of the RCS pressure or inventory control system component SCENARIO #2 NARRATIVE The scenario begins with an expected call from Chemistry to report the results of routine RCS sampling. The report informs the crew that a difference of 55 PPM exists between the RCS and the Pressurizer, requiring equalization to be performed to get the concentrations within 50 PPM. The crew will perform an RCSIPressurizer boron equalization.

Using a compressed time line, Chemistry will call an inform the crew that the difference between RCS and Pressurizer boron is 5 PPM and the equalization can be secured, as they desire. The crew will take the actions to complete the equalization.

As the Pressurizer spray valve is attempted to be closed, the operator will report the valve will not close and RCS pressure is continuing to decline. The crew should take the actions for a Pressurizer spray valve failure using AOP 1203.015 for guidance.

The "8" Heater Drain pump bearing will begin to heatup and cause an annunciator alarm. The crew will respond to the alarm by checking for the affected pump and taking actions to stop the pump. The pump may trip before the crew can stop it, and the CRS should direct a plant power reduction to stay within the high level dump capacity of the affected heater drain tank. As the crew is performing a power reduction, the operator will report the ULD station, being used to perform the power reduction, will not respond to his command. The CRS should direct the operator to use the SGlRX Master station to perform the power reduction.

The selected pressurizer level transmitter will fail low. The crew will take action to select the redundant transmitter for indication and control . Page 2 of 13 Wndix D Scenario 2 Form ES-D-1 SCENARIO #2 NARRATIVE (continued)

The power maneuver will cause a tube in the "A OTSG to begin leaking and progress to a rupture of -150 gpm.

The crew will respond to the "A N16 Alarm and begin taking the actions of AOP 1203.023, Small Steam Generator Tube Leaks. The leak will exceed 10 gpm and require the crew to transition to the OTSG Tube Rupture EOP. The crew will begin a controlled plant shutdown.

At -50% power, when plant auxiliaries are being shifted to startup transformer, the operator will report the feeder breaker from SU#1 to the HI bus will not close. The crew must make a decision to either place the HI bus on SU#2 or remove the handswitch from SU#2 out of Pull-To-Lock and allow the bus to transfer to SU#2 automatically when the unit is tripped. The crew will continue with the shutdown and at -12% power trip the unit. The CIW should begin a plant shutdown at 5 100°F/Hr.

When directed to place the Auxiliary Feedwater Pump in service the pump will fail to start. This will require the crew to initiate EFW and continue the cooldown using EFW as the feedwater source until the Auxiliary Feedwater Pump is made available.

The scenario will be terminated when a cooldown is in progress and EFW is in service.

Aaoendix D Scenario 2 Form ES-D-1 Page 4 of 13 Simulator Instructions for Scenario 2 2 3 4 5 6 7 8 9 T=15 T=20 N/A N/A T=35 T=40 Pre- loaded Pre- loaded IMF CV1008 IMF FW087 NIA IOR Dl-lCC0009L IMF TR049 IMF RCOOl IOR DI-HI 5c IRF CO-P75 .I2 N/A NIA False 0 ,325 R20:OO False OFF samples with a 55 PPM difference.

Equalize RCS/Pzr boron concentration Pressurizer Spray Valve fails open (Use a value of .I0 if the red light is not lit when the spray valve is opened) Heater drain pump "B bearing heat up resulting in need to trip the pump. Pump will trip if no action is taken. (2 min.15 sec.- alarm, 3 min.

15 sec. -trip) Lower power to -70% in response to a trip of a heater drain pump ULD station fails to lower demand signal in manual Pressurizer level transmitter fails low OTSG tube leak progressing to a -150 gpm. HI feeder breaker from SU#1 transformer fails to close when transferring auxiliaries.

P75 will not start Appendix D Required Operator Actions Form ES-D-2 ROLE PLAY: Call as Chemistry and report RCS boron concentration is 782 PPM and Pressurize boron concentration is 837 PPM. on the report from Nuclear Chemistry that the Pressurizer is

>50 ppm higher than the RCS. sing normal operations procedure 1103.005, direct the equilization of boron by ither method 1 or 2. Place Pressurizer spray valve in manual and open slightly Place some Pzr heaters in manual and throttle spray flow to hold pressure Monitor RCS pressure closely. ed Pzr heaters in manual and monitor RCS pressure closely. Page 5 of 13 Appendix D Required Operator Actions Form ES-D-2 ROLE PLAY: Using time compression to complete the evolution, call as Chemistry and report the difference between RCS and Pressurizer boron is

<5 PPM and equalization can be pressure continues to lower. Valve Isolation, CV1009. Page 6 of 13 Appendix D Required Operator Actions Form ES-D-2 Page 7 of 13 T=20 CBOR CRS CBOT Acknowledge and report Heater Dram Pump Bearlng Temp HI alarm, K06-E8 D~rect actlons per 1203 012E , Annunciator Correcttve Action for K06-E8 Check TR-2890 for the affected pump Determine and report P8B bearing temperature rtstng NOTE The crew may elect to stop the heater drain pump prlor to it tripplng due to the fault CBORl CBOT CRS CBOR CBOR CRS Report P8B, Heater Drain Pump, trlp Dtrect operattons per ACA 1203 012E, K06-A8 (P8NB Flow Lo) and/or 1203 012E, K06-87 (Condensate Pump Autostart)

Commence reduct~on in unit load to -70% at -lO%lminute using the ULD Report to the CRS that the ULD wtll not change demand as requested Dlrect the CBOR to place the SGlRX Master H/A statlon in "HAND" and lower power to -70% at -IO%/m~nute NOTE: In the manual mode on the SGlRX master, the operator has control of the rate the plant will change it is expected the operator will maintain the rate of change near the dlrected rate by the CRS CBOR Place the SGlRX master in "HAND" and slowly toggled down, checking to determine the rate directed by the CRS -Cont~nued-Appendix D Required Operator Actions Form ES-D-2 at or near setpoint. (Auto or manual)

Appendix D Required Operator Actions Form ES-D-2 (Tech Spec.

3.3.15.A, Post Accident Monitoring (PAM) Instrumentation.)

Appendix D Required Operator Actions Form ES-D-2 Appendix D Required Operator Actions Form ES-D-2 NOTE The CRS may elect to place HI bus on SU#2 transformer or remove the handswltch for SU#2 from P-T-L and allow the bus to transfer to SU#2 when the unit IS trlpped CBOT CBOT CBOR CRS 1 Place both Feedwater Demand HIA Statlons In HAND 2 Adjust demands to zero 3 Place Reactor Demand HIA statlon in HAND 4 Adjust to control reactor power at 10-12%

When unlt IS 5180 MW open HP Turblne Dram valves on C02 When untt IS 5100 MW secure reheaters When reactor power IS 42% 1 Select bad SG to lndtcate on Header press recorder 2 Check Turblne Bypass valves controlling header pressure 880-920 pslg 3 Verlfy plant auxlllar~es on SU1 Check PZR Level >200" -Continued-Appendix D Required Operator Actions Form ES-D-2 1 CBOR Trip Reactor AND immediately adjust Header Pressure Controller setpoint to 45. I I verify all rods inserted AND Reactor power dropping CBOT Verify Turbine tripped. CBOR Check Turbine Bypass valves controlling OTSG pressure 950-990psig.

I Operate PZR heater and spray in hand as required to maintain RCS pressure low within the limits of figure 3. Stabil~ze PZR level 255" Ver~fy OTSG N16 mon~tors selected to GROSS posttion.

D~rect the CBOR to begin a cooldown at < 100" FIHr. /I / CRS I Direct placing the Auxiliary Feed pump, P75, in service.

CT I CRS I Go To step 24 and direct the CBOR to actuate EFW and verify proper actuation and control (RT 5).

CBOR CBOT Place Turbine Bypass valves for the "6" OTSG in hand and adjust to inltiate and maintain a cooldown rate of ~lOO°FIHr. (Within 15 minutes of unit offllne) Attempt to start P75 from the handswitch on C12. Report to the CRS that P75 will not start. Page 12 of 13 CBOR Actuate EFW and verify proper actuation and control (RT 5). -Continued-Appendix D Required Operator Actions Form ES-D-2 Page 13 of 13 4goendix D Scenario 3 Form ES-0-1 outlet valve CV1407 fails to open on ESAS Aooendix D Scenario 3 Form ES-D-1 Scenario #3 Objectives

1) Evaluate individual response to component failures affecting cooling of the main turbine generator.

2) Evaluate individual response to input failures to the Integrated Control System. 3) Evaluate individual response to a loss of reactor coolant accident

4) Evaluate individual response to failure of automatic actuation systems. 5) Evaluate individual response to failure of Emergency Core Cooling System components.

6) Evaluate individual ability to maneuver the plant in accordance with plant procedures.

7) Evaluate individual ability to start and operate feedwater and condensate system components in accordance with plant procedures.

8) Evaluate individual response to failure of system or components associated with control of the secondary heat removal capabilities.

SCENARIO #3 NARRATIVE This scenario begins with the plant at 30% power with the "A" Main Feedwater Pump operating, and the lntegrated Control System in "AUTO" with the exception of the ULD (STAR Module) which is in manual to perform power escalation.

When the crew accepts responsibility for the control boards, the first event will be a power escalation to 40% power to place the "B" Main Feedwater Pump in service and split the feedwater loops. As plant load is increased, a failure of the automatic control valve for control of Auxiliary Cooling Water to the Main Generator hydrogen coolers causes Generator gas temperatures to begin rising. The crew will respond to alarms associated with generator gas temperature monitor and take manual control of the ACW control valve and regain cooling of the hydrogen gas. The crew will place the "B" Main Feedwater Pump in service and prepare to continue the power escalation.

After the Feedwater pump is placed in service ("AUTO") the selected "B" OTSG Startup Level transmitter will fail low requiring the crew to stop the Feedwater transient that occurs as the "B" Main Feedwater pump overfeeds the "B" OTSG. When the crew stabilizes the plant, they will select the good transmitter for control and place the ICS stations in "AUTO". The "C" Circulating Water Pump, P3C, will experience an internal electrical failure that will cause the winding temperature to rise to alarm setpoint. The crew will respond to the alarms and take actions to secure the faulted pump or respond to the trip of the pump. The idle pump should be placed in service. The crew should also monitor for loss of vacuum and lower plant load, if necessary, to stabilize vacuum. Page 2 of 12 A j~endix D Scenario 3 Form ES-D-I SCENARIO #3 NARRATIVE (continued)

A reactor coolant system leak on an HPI line will cause RCS pressure to begin to rapidly drop. The crew should identify the LOCA and trip the unit. The RPS will fail to perform an automatic trip if the low pressure trip setpoint is reached and will require the crew to manually trip the reactor. The normal reactor trip pushbutton will fail to trip the reactor and the operator will need to use the backup trip pushbuttons on C03. The reactor will trip and the crew will perform the immediate actions of the Reactor Trip EOP and identify the failure of the RPS to perform its function.

RCS pressure will drop to the ESAS actuation setpoint and ESAS will actuate.

CV1407, the BWST outlet to the "Red" Train components, will fail to open. The crew should stop the ES pumps associated with the RED train until the valve can be manually opened locally. While performing verifications of proper actuation of components, the operator will discover a difference in flows on the only operating HPI loop and throttle the valve associated with high flow to within 20 gpm of the other flows. The scenario will be terminated when the RED train is restored to operation following the opening of CV1407 and EFW is feeding both OTSGs. Page 3 of 12 A~oendtx D Scenario 3 Form ES-D-I Simulator Instructions for Scenario 3 "B" OTSG startup level transmitter fails 5 6 7 8 T-45 T-55 Pre- Loaded Pre- Loaded IMF CW084 IMF RC464 RP246 RP247 RP248 RP249 IOR Dl-lCC0020 IMF CV1407 N/A 2.5 R7:00 NIA NIA NlA NIA False 0 P3C, Circulating Water Pump, winding temperature begins to heatup due to internal motor problem.

LOCA- Leak on an HPI line inside containment RPS fails to trip the reactor automatically on a valid RPS trip setpoint.

The "Manual"trip button on C03 fails to perform a reactor trip. (The backup pushbuttons on C03 must be depressed to complete a reactor trip)

BWST outlet valve CV1407 fails to open on ESAS signal Appendix D Required Operator Actions Form ES-D-2 CBOR CBOT CBOR CRS CBOT CBOT CBOT Monitor Heat Balance power on plant computer polnt XPP Compare Heat Balance power wlth nuclear instrumentation Place Moisture Separator Reheaters in service Acknowledge and report annunciator KO4 66 in alarm (Generator 1-12 Temp HI) Provlde direction per 1203 012C, Annunciator Correctwe Action Monltor recorder TR-9001 and/or PMS dynamlc alarm display for rlsing temperatures on the main generator CheckNerlfy CV4018, Generator Hydrogen Cooler outlet control valve on C19, operating properly Report the hydrogen cooler outlet control valve is closed CRS Dlrect the CBOT to attempt to manually operate the valve from the controller on C19 Appendix D Required Operator Actions Form ES-D-2 TR-9001 for signs of generator winding degradation.

Page 6 of 12 Appendix D Required Operator Actions Form ES-D-2 Anticipatory Reactor Trip System (ARTS) Reset" for the 2nd MFWP. Discharge pressure, if available Suction flows on Feed Pumps Recirc HIA stations Appendix D Required Operator Actions Form ES-D-2 gain control of feedwater flow.

station in "AUTO". Page 8 of 12 Appendix D Required Operator Actions Form ES-D-2 for the circ water pumps. NOTE: The "C" Circ Water Pump may trip before the CRS can direct the pump be stopped. Page 9 of 12 Appendix D Required Operator Actions Form ES-D-2 governor valves closed CREW CRS Recognize the actuation of ESAS on low RCS pressure Transition to ESAS procedure, 1202 010, and direct crew operations -Continued-Appendix D Required Operator Actions Form ES-D-2 IA OPERATOR NOTE: When the WCO is sent to manually open CV1407, open the valve.

IMF CV1407 1 240 Appendix D Required Operator Actions Form ES-5-2 UNIT I SHIFT RELIEF SHEET Computer Generated Fom (ref. 1015.0f5)

Page 1 of 2 n Makeuo No Concentration Chanae LXTE : / Delithiation performed last shift 1 No / minutes / Delithiation required oncoming shift

/ No / minutes I I 911412005 Reactivity change Last Shift . . . .- . . - . . . . . - . - - - . . Any unplanned power maneuver will be performed using the Integrated Control System (ICS). Contingency Reactivity Plans are located in the Plant Data Book and at ANONJIOPSlAPPSlContingency RX Plans. . . - . . -. . . . . . .. -. - . -. .. . . -. - -. . - .. .- .. .. -. . - . -- L PLANT POWER: 2 ppm / Dilution / 172 gals I Water I ACTION STATEMENTS IN EFFECT (TS/TRM/ODCM/FS ETC) None ONCOMING SHIFT. Anticipated reactivity change for oncoming shift / 2 ppm I Dilution 1 172 gals / Water CONTROL ROOM ALARM STATUS Annunciators associated with 30% power ICS in Automatic at

-30% power following a mid-cycle shutdown.

Power escalation is in progress per the Startup and Power Operations procedures. "A" MFW pump is in service and "B MFW pump is running at minimum speed.

CV1207 seal injection control valve is in hand, 30% ..., None ..* .., .dT :.>. ..*,: .,:" ..>:: . Days CREW : PUNT MODE: CHEMISTRY 1 Malntaxn >30# hydrogen pressure In the Makeup Tank.

Voum MINIMAL DAYS ON UNE : 250 CHEDULED RISK: UNT WN : RED UNIT 1 SHIFT RELIEF SHEET Computer Generated Form (ref. 1015.015)

Page 2 of 2 OFF-GOING SHIFT SIGNATURE CRSlSM - .. . . . -.____.. . . .. .. . . . . ___ . -. . . . __ .. . . .. . . - . - . . -.

ADDendlx D Scenar~o 4 Form FS-D-1 100% Power, Equilibrium Xenon CV1207, Seal Injection control valve, is in manual due to oscillations of seal injection when in 2 3 4 5 6 7 8 * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BAT ES19-2.txt (Batch fiie that creates this condition)

NIA CV097 BAT crd-asym.txt (Batch fiie that creates this wndition)

MSf43 MS134.4 TU155 TU156 CV2648 CV2626 C (CBOT) R (CBOR) C (CBOT) I(CB0R) M (ALL) C (CBOT) C (CBOR) Condenser vacuum leak caused by the failure of the #5 turbine bearing gland seal regulator.

Power reduction to stabilize vacuum Operating MUlHPl pump experiences high winding temperature and causes the pump to trip. The standby pump has no oil indicated in one of the oil bubblers and must have oil added prior to start. CRD position indication faulty with a CRD WID inhibit Main steam safety valve associated with '6' OTSG experiences structural failure and lifts.

Steam Leak significant to warrant manual reactor trip.

The main turbine fails to fully trip when the unit is tripped. One governor valve and one throttle valve fail to close, requiring the crew to shut the MSlV from the affected OTSG. EFW valves to "B" OTSG from P7B fail open and will not close from the handswitches.

BBoendix D Scenario 4 Form ES-D-1 Scenario #4 Objectives

1) Evaluate individual ability to perform an RCS delithiation in accordance with plant procedures.

2) Evaluate individual ability to perform a plant power reduction and stabilize the plant in accordance with plant procedures.

3) Evaluate individual response to faulty control rod position indication.

4) Evaluate individual response to a loss of condenser vacuum. 5) Evaluate individual response to loss of RCS makeup due to an HPI pump trip. 6) Evaluate individual response to a main steam line break/overcooling event. 7) Evaluate individual response to failure of the main turbine steam valves to close on a turbine trip. 8) Evaluate individual response to a failure of Emergency Feedwater System components.

SCENARIO #4 NARRATIVE The scenario begins with the crew responding to annunciator alarms associated with the Control Drive System.

The "Control Rod Asymmetric" and "CRD Withdrawal Inhibit" alarms are received and the crew will refer to the respective Annunciator Corrective Action procedures for direction. The ACAs will direct the crew to the "CRD Malfunction" AOP and the crew will begin diagnosing the situation.

It should be determined by the crew that the condition is caused by faulty indication for Group 2, Rod #4. The crew will perform the actions required for a faulty control rod indication problem and bypass the alarm function for that rod. This will allow the crew to reset the asymmetric condition and regain control of the movement of the rods inhibited by the asymmetric condition. Chemistry will call the control room and request they perform the 5 minute delithiation or the RCS that was anticipated at turnover. Chemistry will inform the crew that the idle Purification Demineralizer is 65 PPM boron higher than the current RCS boron concentration. The crew will refer to the Makeup and Purification procedure, 1104.002, and perform the actions for RCS Delithiation. Condenser vacuum will begin to slowly decline and annunciators associated with the main turbine bearing

1. 5 gland seal will alert the crew of a problem with the gland seal supply to the #5 bearing. The crew will respond to the ACA for the #5 bearing gland seal and "Loss of Condenser Vacuum" AOP. The crew will reduce plant load to stabilize vacuum. Gland sealing steam will be restored to the bearing gland and the vacuum will recover. The operating makeup pump will experience rising motor windings temperatures due to an electrical fault in the motor. The crew will be prompted by an annunciator alarm and respond to stop the affected pump and start the standby makeup pump. The pump may trip prior to stopping and the crew should refer to the AOP for "Loss of Reactor Coolant Makeup", 1203.026.

The standby pump will be placed in service.

ADDendix D Scenario 4 Form ES-D-1 SCENARIO #4 NARRATIVE (continued)

The crew will receive an "MSSV OPEN" annunciator alarm. Verification using the SPDS will identify one MSSV on the "B" main steam line open and the crew will dispatch an operator to confirm steam releasing from exhaust piping in the penthouse area. The operator will report not only steam from the exhaust piping but steam releasing from the sides of the penthouse structure, indicating a significant size steam leak. The crew will determine the leak sufficient enough to trip the unit and begin isolation of the affected OTSG. During the isolation process, the crew discovers Emergency Feedwater is still being supplied to the affected OTSG and must take action to stop the flow of feedwater to stop the overcooling that is occurring as a result of the continuous feed. The crew will have to stop the electric driven EFW pump, P7B, to stop the flow of EFW to the "B" OTSG. This will allow the OTSG to boil dry and terminate the overcooling.

mndix D Scenario 4 Fom ES-D-1 Page 4 of 13 Simulator Instructions for Scenario 4 4 5 6 7 8 T=30 T=40 T=60 Just prior to time of trip Pre- loaded IMF CV097 BAT crd-asym.txt IMF MS143 IMF MS134 IMF TU155 IMF TUI~~ IMF CV2648 IMF CV2626 NIA NIA 6 .4 100% 100% ----- 1 I Operating MUlHPl pump experiences high winding temperature and causes the pump to trip. The standby pump has no oil indicated in one of the oil bubblers and must have oil added prior to start. CRD position indication faulty with a CRD WID inhibit Main steam safety valve associated with

'B' OTSG experiences structural failure and lifts. Steam Leak significant to warrant manual reactor trip. The main turbine fails to fully trip when the unit is tripped. One governor valve and one throttle valve fail to close, requiring the crew to shut the MSlV from the affected OTSG. EFW valves to "B" OTSG from P7B fail open and will not close from the handswitches.

Appendix D Required Operator Actions Form ES-D-2 1203.045, Rapid Plant Shutdown.

NOTE: After -3 minutes from the time the A0 was directed to investigate

1. 5 bearing seal pressure, restore gland seal steam to #5 bearing. IRF GS6826-1 1 DMF MC088 Page 6 of 13 Appendix D Required Operator Actions Form ES-D-2 Appendix D Required Operator Actions Form ES-D-2 WDG TEMP HI. NOTE: If the running MIU pump trips before the crew stops it, the following actions should be performed:

Tech Specs. 3.5.2.A ECCS - Operating Page 8 of 13 Appendix D Required Operator Actions Form ES-D-2 Close Letdown Cooler Outlets (RCS) (CV-1214 and CV-1216). RC Pumps Total INJ Flow (CV-1207) Pressurizer Level Control (CV-1235)

Appendix D Required Operator Actions Form ES-D-2 A. IF seal bleedoff temperature is

>180"F, THEN establish and maintain 8 to 12 gpm RCP Seal Total Injection Flow until

~180°F. B. WHEN seal bleedoff temperature is

<180"F, THEN adjust CV-1207 for 30-40 C. Place CV-1207 in AUTO. (The crew may leave in "MANUAL" due to operational guidance Page 10 of 13 Appendix D Required Operator Actions Form ES-D-2 Malfunction Action) and direct the crew actions. BOR to RESET the Asymmetric Fault using 1203.012G, K08-A2, Page 11 of 13 Appendix D Required Operator Actions Form ES-D-2 ROLE PLAY: Call as the A0 and report steam coming from the MSSV piping and coming from the sides of the penthouse.

all rods inserted and reactor power the valves to close. -Continued-Page 12 of 13 Appendix D Required Operator Actions Form ES-D-2 UE 3.1 Uncontrolled OTSG Depressurization Resulting in MSLl Page 13 of 13