Text

Initial Examination 2009-301 Final Administrative JPMs
	ML091110264
Person / Time
Site:	Oconee
Issue date:	03/13/2009
From:	; NRC/RGN-II
To:	; Duke Energy Corp
References
	50-269/09-301, 50-270/09-301, 50-287/09-301, ADM-408 R3 50-269/09-301, 50-270/09-301, 50-287/09-301
	Download: ML091110264 (260)
	v • d • e

ADM-408 R3 Page 1 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE .

Admin-408 Determine Emergency Classification and Protective Action Recommendations {Complete Emergency Notification Form}

CANDIDATE EXAMINER

ADM-408 R3 Page 2 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Determine Emergency Classification and Protective Action Recommendations (Complete Emergency Notification Form)

Alternate Path:

NO Facility JPM #:

New KIA Rating(s):

System: G KIA: 2.4.38 Rating: 2.2/4.0 Task Standard:

Appropriate classification is determined and associated Emergency Notification Form is completed.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant _~X-,---_ Perform X Simulate__

References:

RP/0/B/1 000101 RP/0/B/1000102 BASIS Document (Volume "A", Section "0" of the Emergency Plan)

RP/0/B/10001015A Validation Time: 20 min. Time Critical: Yes

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

Candidate: Time Start: _ _ __

NAME Time Finish: - - -

Performance Rating: SAT ___ UNSAT _ __ Performance Time: _ _ __

Examiner: _ _ _ _--,-,_ _ _ _ _ _ __

NAME SIGNATURE DATE

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

Comments

ADM-408 R3 Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS:

NONE

ADM-408 R3 Page 4 of 9 Tools/Equipment/Procedures Needed:

RP/0/B/1000101 1 RP/0/B/1000102 1 RP/0/B/1 0001015A (optional) 1 Message Sheet #1 READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS: THIS IS A DRILL 08:00:00 Unit 1 (Mode 1, 100%) has a SG Tube Rupture (SGTR) of 35 gpm in the 1A SG

1RIA-40 is in HIGH alarm 08:05:00 ERO activated by the OSM due to the SGTR 08:25:00 Offsite Communicator informs OSM that offsite agencies have received Message

1 at 0811 CURRENT CONDITIONS: THIS IS A DRILL While Unit 1 is shutting down due to the SGTR, the following event time-line occurs; 08:30:00 Unit 1 Turbine/Generator trips and CT-1 locks out.

08:30:28 Unit 1 BOP dispatched to activate the SSF using AP/25, per EOP immediate manual actions step 3.5-RNO.

08:30:45 OATC performs Rule 3 for a loss of Main FDW; SGs being fed by 1TDEFWP.

08:32:50 Control Room crew notifies OSM that BOTH Keowee Units have experienced Emergency Lockouts and that CT-5 is available. Unit 2 BOP is performing EOP Encl. 5.38 (Restoration of Power).

08:41 :00 SSF RO reports that flow has been established to Unit 1's RCP Seals per AP/25 08:47:05 Power has not been restored. Enclosure 5.38 is still in progress.

INITIATING CUE:

Current time is 0848. Perform the required actions of the Emergency Coordinator:

1. Determine Emergency Classification

2. Complete appropriate Emergency Notification Form for current conditions THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinator's judgment while classifying the event. When required, other operators will maintain the Emergency Coordinator's Log and perform the duties of the Control Room Offsite Communicator.

ADM-408 R3 Page 5 of9 START TIME #1: _ __

STEP 1: Classify the Event at 08:47:05 CRITICAL STEP STANDARD: Refer to RP/0/B/1000101 (Emergency Classification) Enclosure 4.5 (Loss of Power). SAT Classify the event as a "Site Area Emergency" due to the following:

LOSS OF POWER

MFB 1 and 2 de-energized AND Failure to restore power to at UNSAT least one MFB within 15 minutes from the time of loss of both offsite and onsite AC power.

STOP TIME #1: Time for Classification _ _ __

(SAT =Start Time #1 + 15 minutes)

COMMENTS:

START TIME #2 _ __

STEP 2: Complete the Off-Site Notification Form.

SAT STANDARD: Go to RP/0/B/10001002 (Control Room Emergency Coordinator Procedure) and initiate procedure by performing Steps 1.1 -thru- 2.9

_UNSAT COMMENTS:

STEP 3: Step 2.2 Declare the appropriate Emergency Classification level.

Classification SAE (UE, ALERT, SAE, GE)

Time Declared: (Inserts time declared from Step 1) SAT STANDARD: Declare a Site Area Emergency due to:

"MFB 1 and 2 de-energized AND Failure to restore power to at least one UNSAT MFB within 15 minutes from the time of loss of both offsite and onsite AC power."

COMMENTS:

ADM-40B R3 Page 6 of9 STEP 4: Step 2.5 Appoint Control Room Offsite Communicator(s) and notify him to be prepared to transmit messages.

- SAT STANDARD: Offsite Communicator is already established COMMENTS: - UNSAT STEP 5: Step 2.6 IAAT Changing plant conditions require an emergency classification upgrade, THEN Notify Offsite Communicator to complete the in-progress notifications per RP/O/S/1 OOO/15A, (Offsite Communications From The - SAT CR)

AND Re-initiate a clean copy of this procedure for the upgraded classification and stop this procedure.

- UNSAT STANDARD: An Upgrade is about to occur with the SAE declaration. The communicator is notified to complete Message #1 and start a clean message sheet for the Upgrade to SAE COMMENTS:

CRITICAL TASK STEP 6: Step 2.B Obtain the appropriate Offsite Notification form from the Emergency Plan - SAT cart.

STANDARD: Initial Site Area Emergency form # 4.5.S.1 isselected and candidate - UNSAT continues to fill-out the above form per the Step 2.8 substeps.

COMMENTS:

ADM-408 R3 Page 70f9 STEP 7: Step 2.8 CRITICAL STEP Ensure EAL # as determined by RP/0/B/1000/001 matches Line 4.

(4.5.S.1 ) SAT Line 1 - Mark appropriate box "Drill" or "Actual Event" (DRILL)

Line 1 - Enter Message # (#2)

UNSAT Line 2 - Mark Initial (INITIAL marked)

Line 6 - A. Mark "Is Occurring" if any of the following are true:

RIAs 40, 45, or 46 are increasing or in alarm (TRUE-Is Occurring is marked due to RIA-40 in alarm)

If containment is breached

Containment pressure> 1 psig B. Mark "None" if none of the above is applicable.

Line 7 - If Line 6 Box B or C is marked, mark Box D. Otherwise mark Box A (mark D)

Line 8 - Mark "Stable" unless an upgrade or additional PARs are anticipated within an hour. (Stable, improving or degrading- does not matter- this part will not be a critical step)

Refer to Enclosure 4.9, (Event Prognosis Definitions)

Line 10 - Military time and date of declaration (Refer to date/time in Step 2.2) (Inserts time from STEP 1)

Line 11 - If more than one unit affected, mark "All" (Unit 1 only)

Line 12 - Mark affected unit(s) (reference Line 11) AND enter power level of affected unit(s) or time/date of shutdown {14}

Line 13 - If the OSM has no remarks, write "None" (NOT BLANK)

If Condition "A" exists ensure following PARs are included Line 5.

A. Evacuate: Move residents living downstream of the Keowee Hydro Project dams to higher ground B. Other: Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed.

Line 17 - OSM signature, CURRENT Time/Date (MUST SIGN)

STANDARD: Correctly fills out Emergency Notification Form in accordance with Key:

NOTE: All of the yellow high-lighted items on the form are CRITICAL. The correct form from LINE 4 - EAL# 4.5.S.1 is especially critical and will result in absolute failure if this form is not selected.

Form complete within 15 minutes of classification in step 1.

(SAT = START TIME #2 + 15 minutes)

COMMENTS:

END OF TASK TIME STOP #2: _ __

ADM-408 R3 Page 80f9 CRITICAL STEP EXPLANATIONS:

STEP # Explanation The candidate needs to be able to utilize the procedure and determine that a Site Area Emergency classification within 15 minutes of beginning the JPM.

6 The correct form that matches the EAL # is selected.

7 The emergency notification form is accurately filled-out; items high-lited in yellow on the KEY are the critical items.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS: THIS IS A DRILL 08:00:00 Unit 1 (Mode 1, 100%) has a SG Tube Rupture (SGTR) of 35 gpm in the 1A SG

1RIA-40 is in HIGH alarm 08:05:00 ERO activated by the OSM due to the SGTR 08:25:00 Offsite Communicator informs OSM that offsite agencies have received Message

1 at0811 CURRENT CONDITIONS: THIS IS A DRILL While Unit 1 is shutting down due to the SGTR, the following event time-line occurs; 08:30:00 Unit 1 Turbine/Generator trips and CT-1 locks out.

08:30:28 Unit 1 BOP dispatched to activate the SSF using AP/25, per EOP immediate manual actions step 3.5-RNO.

08:30:45 OATC performs Rule 3 for a loss of Main Fdw; SGs being fed by 1TDEFWP.

08:32:50 Control Room crew notifies OSM that BOTH Keowee Units have experienced Emergency Lockouts and that CT-5 is available. Unit 2 BOP is performing EOP Encl. 5.38 (Restoration of Power).

08:41 :00 SSF RO reports that flow has been established to Unit 1's RCP Seals per AP/25 08:47:05 Power has not been restored. Enclosure 5.38 is still in progress.

INITIATING CUE:

Current time is 0848. Perform the required actions of the Emergency Coordinator:

1. Determine Emergency Classification

2. Complete appropriate Emergency Notification Form for current conditions THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinator's judgment while classifying the event. When required, other operators will maintain the Emergency Coordinator's Log and perform the duties of the Control Room Offsite Communicator.

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM 1*lil_DRILL [!IACTUALEVENT MESSAGE #

2.~INITIAL ((]FOLLOW-UP NOTIFICATION: TIME olJl( AUTHENTICATION #_71-..lo6",--_

3. SITE: Oconee Nuclear Site Confirmation Phone # (864) 882-7076 i 4. EMERGENCY .UNUSUALEVENT mSITE AREA EMERGENCY [§]GENERALEMERGENCY CLASSIFICATION:

BASED ON EAL# ....;4~.2;;.;;..U.;;;..;..;.1_ __ EAL DESCRIPTION Water is leaking from the reactor coolant system in excess of allowed limits.

Current plant conditions DO NOT threaten public safety.

5. PROTECTIVE ACTION RECOMMENDATIONS:

((]EVACUATE_____________________________________________________________________________

mSHELTER _____________________________________________________________________________

[§] CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.

[!]OTHER__________________________________ ~,_------------------------------------------

6. EMERGENCY RELEASE: 0None Is Occurring mHas Occurred

7. RELEASE SIGNIFICANCE: 0Not applicable ~Within normal operating limits mAbove normal operating limits Under Evaluation

8. EVENT PROGNOSIS: o Improving ~Stable mDegrading

9. METEOROLOGICAL DATA: Wind Direction from degrees Wind Speed* _______ mph r May not be available for Initial Notifications)

Precipitation*

Stability Class* 0mm[§][!][IJm 10.11 DECLARATION ~ TERMINATION Time lJ 'OO( Date 12>(J 4l{

f Oll-T£..

11. AFFECTED UNIT(S):

1AJIT11Il1EI

12. Unit Status:

(unanectea Unlt(S) Status Not KeqUirea tor Initial r"i7'i R

U1 Jf1fl.. % Power Shutdown at: Time Date Notifications) [!I U2 % Power Shutdown at: Time Date

13. REMARKS:--'-"V'-O.;....L...Il_t.

m U3

% Power Shutdown at: Time Date FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)

EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6A IS SELECTED.

14. RELEASE CHARACTERIZATION: TYPE: 0Elevated [!]Mixed ())GrOUnd UNITS:0Ci [!ICi/sec ())IJCi/sec MAGNITUDE: Noble Gases: lodines:

Particulates:

Other:

FORM: 0Airborne Start Time: _______ Date: Stop Time: Date

[ ! I Liquid Start Time: Date: Stop Time: Date

15. PROJECTION PARAMETERS: Projection Period: ___________ Hours Estimated Release Duration: ____________ Hou~

Projection performed: Time Date

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles SMiles 10 Miles

17. APPROVED BY: {)fm S/6-J}If(4.(2£.

Title:

Emergency Coordinator Time:

_~REG.EIVEDBY: Time:

Date:---- I (o¥'\""ltll.{c~)

Admin-302 rS Page 1 of 7 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-302 Calculate the Maximum Permissible Stay Time Within Duke Power Basic Administrative Limits CANDIDATE EXAMINER

Admin-302 r5 Page 2 of 7 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Calculate the Maximum Permissible Stay Time Within Duke Power Basic Administrative Limits Alternate Path:

Facility JPM #:

KIA Rating(s):

Gen 2.3.4 2.5/3.1 Task Standard:

Calculate the Maximum Permissible Stay Time Within Duke Power Basic Administrative Limits Preferred Evaluation Location: Preferred Evaluation Method:

Simulator ___ In-Plant _-"X-,-_ Perform _X_ Simulate

References:

NSD-507, Radiation Protection Validation Time: 12 min. Time Critical: NO

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

Candidate: Time Start: _ _ __

NAME Time Finish: _ __

Performance Rating: SAT ___ UNSAT _ __ Performance Time: _ _ __

Examiner: _ _ _ _ _ _ _ _ _ _ _ __ ~-------------~/_--

NAME SIGNATURE DATE

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

COMMENTS

Admin-302 rS Page 3 of 7 SIMULATOR OPERATOR INSTRUCTIONS:

NONE

Admin-302 rS Page 4 of 7 Tools/Equipment/Procedures Needed:

READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Date =Today's date

2. The NEO selected to perform a job has the following dose history:

1940 mrem TEDE received this year

3. The NEO will receive 20 mrem total during transit (to and from) the area due to high dose rates in the Auxiliary Building and the route he is required to take.

4. The dose rate in the area of the job is 110 mr/hr.

INITIATING CUE:

Using to the attached RWP and standard radiation work practices, determine how long the NEO can perform the job before being required to leave the area. No administrative extensions or approvals are obtained.

Admin-302 rS Page S of 7 START TIME: _ __

Note: Candidate may perform these steps in a different order however the calculated stay time should be correct.

STEP 1: Calculate maximum stay time CRITICAL STEP STANDARD: Stay time is calculated to be: SAT Available Dose = 50 mrem - (20 mrem) =0.27 hrs (16.3 min)

Dose Rate 110 mremihr UNSAT Acceptance Band = 16.0 -to- 16.4 minutes Note: The NEO must leave the room when his ED alarms (set at 50 mrem).

Note: The 20 mrem is the dose the NEO will receive in transit to and from the job.

COMMENTS:

END OF TASK TIME STOP: _ __

Admin-302 rS Page 6 of 7 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Required to calculate stay time.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Date = Today's date

2. The NEO selected to perform a job has the following dose history:

1940 mrem TEDE received this year

3. The NEO will receive 20 mrem total during transit (to and from) the area due to high dose rates in the Auxiliary Building and the route he is required to take.

4. The dose rate in the area of the job is 110 mr/hr.

INITIATING CUE:

Using to the attached RWP and standard radiation work practices, determine how long the NEO can perform the job before being required to leave the area. No administrative extensions or approvals are obtained.

- - Important - Please Read! ***

with the RWP displayed on EDC or the posted hard copy at the EDC Access Station Oconee Nuclear Station AND SYSTEMS OPERATION (OPERATIONS)

ED(MG) Set Points Dose RateAlarm: 150mtemlhr

- 8000 MREMlHR

- 999 MREMlHR

~'Jfd~'X~it~~~~H_'~30~:0~~MRADIHR BETA-GAMMA & 42,309 DPM ALPHA EQUIPMENT TO EtlIv1INATEROOMENTRY

,C~h't:~;;:J::;" "'-'-'-"H" OF ED (MG) AN})~ISNOT REMOTF;LY PLACE ED (MG) EXTERNAL TO THE OUTERMOST

ADMIN 209 r2 Page 1 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-209 DETERMINE LTOP REQUIREMENTS CANDIDATE EXAMINER

ADMIN 209 r2 Page 2 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Determine LTOP Requirements Alternate Path:

Facility JPM #:

KIA Rating(s):

System: 001 KIA: Gen 2.2.12 Rating: 3.7/4.1 Task Standard:

Per OP/1/A111 04/049, Low Temperature Overpressure Protection, and based on conditions provided and plant knowledge determine if LTOP requirements are being met.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant --:..X=--_ Perform X Simulate

References:

Validation Time: 30 minutes Time Critical: NO

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

Candidate: Time Start: _ _ __

NAME Time Finish: _ __

Performance Rating: SAT ___ UNSAT _ __ Performance Time: _ _ __

Examiner: _ _ _ _ _ _ _ _ _ _ _ __ - - - - - - - - - -_____~/__-

NAME SIGNATURE DATE

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

COMMENTS

ADMIN 209 r2 Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS:

NONE

ADMIN 209 r2 Page 4 of 12 Tools/Equipment/Procedures Needed:

-Attachment listing current plant conditions

-Working copy of OP/11A/11 04/049, LTOP, Encl. 4.13 (LTOP Requirements Logic Diagram)

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 controlling procedure for unit shutdown and cooldown is in progress for entering a refueling outage. Plant conditions are as described in the attachment provided.

INITIATING CUES:

Based on the conditions described above and by using any associated plant procedures, verify that LTOP requirements are being met per Encl. 4.13 (LTOP Requirements Logic Diagram) of OP/1/A/1104/049 (Low Temperature Overpressure Protection).

If not being met, then list all the LTOP requirements that result in LTOP not being met on the provided working copy of "LTOP Requirements Logic Diagram" Encl. 4.13 of OP/1/A/11 04/049, LTOP.

ADMIN 209 r2 Page 5 of 12 START TIME: _ __

STEP 1: CRITICAL STEP LTOP (HPI) Verify HPI deactivated per OP/1/A/11 04/049 (LTOP).

- SAT STANDARD: Refers to OP/1 1A/11 04/049 (LTOP) Enc!. 4.13 and attachment and determines that HPI is NOT deactivated in that:

- UNSAT

-1A HPI Pump is still operating

-1 HP-26 breaker is not open COMMENTS:

STEP 2:

LTOP (CFT) Verify each CFT isolated per OP/1/A/1104/049 (LTOP) when - SAT CFT pressure <:: 373 psig.

STANDARD: Determines from attachment that Core Flood Tanks (CFTs) are isolated - UNSAT COMMENTS:

STEP 3: CRITICAL STEP LTOP (pzr Level)

Verify Pzr level within LTOP limits per heatup/cooldown curves in - SAT OP/O/A/1108/001 (Curves And General Information).

STANDARD: Determines that Pzr Level is NOT within limits; Pzr Level must be < 220 inches. It is currently 223 inches. - UNSAT COMMENTS:

ADMIN 209 r2 Page 6 0 f 12 STEP 4:

LTOP (Pressurizer Heater Bank 3 or 4)

Verify Pressurizer Heater Bank 3 OR 4 white tagged open per OP/1 IN11 04/049 (Low Pressure Overpressure Protection (LTOP). - SAT STANDARD: Determines from attachment that Bank 3 Heaters are white tagged open.

- UNSAT Either Bank 3 or 4 heaters being deactivated meets requirements.

COMMENTS:

STEP 5:

LTOP (1 RC-4)

Verify 1RC-4 open when PORV is required to be operable. - SAT STANDARD: 1RC-4 is open when PORV required to be operable UNSAT COMMENTS:

STEP 6:

LTOP (1 RC-4)

Verify 1RC-4 open when the following conditions are met:

PORV removed - SAT

1RC-4 installed

1RC-4 part of LTOP vent path

- UNSAT STANDARD: Verifies 1RC-4 is open; but none of the above conditions require 1RC-4 to be open COMMENTS:

ADMIN 209 r2 Page70f 12 STEP 7:

LTOP (RC Pressure) - SAT Verify RCS < 525 psig when RCS > 220°F and s325°F.

OR Verify RCS < 375 psig when RCS s 220°F.

- UNSAT STANDARD: Determines RC Pressure to be within limits COMMENTS:

STEP 8:

LTOP (RC Makeup Flow)

Verify 1HP-120 travel stop operable per OP/1/N1104/049 (LTOP) - SAT or HPI Pumps NOT capable of starting and injection into RCS via 1HP-120.

STANDARD: 1H P-120 Travel Stop operable UNSAT COMMENTS:

STEP 9: - Page 9-SR 3.4.12.6 LTOP (OAC Alarms) - SAT NOTE: The 225" Pressurizer Level Computer alarm is included in this check.

Verify 01 L3153 NOT in alarm AND OAC operable.

IF 01 L3153 in alarm, evaluate LTOP input points valid by using LTOP OAC - UNSAT Screen.

Refer to OP/1/N1104/049 (Low Temperature Overpressure Protection (LTOP).

STANDARD: Per Attachment, computer point is not in alarm (pzr Level is <225" so the alarm is not actuated; however Pzr Level exceeds LTOP limits)

COMMENTS:

ADMIN 209 r2 Page 8 af 12 STEP 10: SR 3.4.12.6 LTOP (OAC Alarms) (260" Pressurizer Level Computer alarm.)

Verify the following: - SAT

1SA-2/C-3 "RC Pressurizer Level High/Low" Statalarm card NOT Pulled.

IF Either 1SA/18/A-3 OR 1SA/18/A-4 is in alarm OR card pulled, THEN verify the following Computer Point status: - UNSAT

01X2256 Quality = GOOD Value = FALSE

01X2274 Quality = GOOD Value = FALSE

01X2285 Quality = GOOD Value = FALSE STANDARD: Per attachment, SA Cards are not pulled and not in alarm COMMENTS:

STEP 11: SR 3.4.12.6 LTOP (OAC Alarms) (315"Pressurizer Level Computer alarm)

Verify 1SA-2/C-4 "RC Pressurizer Level Emerg High/Low" Statalarm card - SAT NOT Pulled.

- UNSAT STANDARD: Determines per attachment, SA card Is not pulled COMMENTS:

ADMIN 209 r2 Page 9 0 f12 STEP 12: SR 3.4.12.6 LTOP (HP Nitrogen System)

Verify 1N-121 white tagged closed per OP/1/N11 04/049 (LTOP).

- SAT STANDARD: Determines per attachment that 1N-121 is closed and white tagged.

- UNSAT COMMENTS:

-Go To Page 19-STEP 13: - page 19- CRITICAL STEP LTOP (Logic Diagram)

Verify LTOP requirements met per Enclosure "LTOP Requirements Logic Diagram" of OP/1 IN11 04/049 (LTOP). - SAT STANDARD: Determines from the Logic diagram and the attachment that LTOP surveillance requirements are NOT satisfied due to 6 items in that: - UNSAT

-HPI is NOT appropriately deactivated

1A HPI pump is NOT racked out and tagged

1HP-26 breaker is still closed

-pzr Level is too high

-No dedicated LTOP operator is assigned

-LTOP vent is NOT established

-pzr Relief standpipe (valve removed) or greater vent path is NOT established Candidate may list items such as the following that are LTOP entry requirements not surveillance requirements. These shall not be counted as part of the required answers:

Tc < 325°F

RV Head Off 1 or SG Primary Manway Off 1 or Pzr Manway Off NOTE: Incorrectly listing a reason(s) that meets LTOP requirements will be counted towards overall unsatisfactory completion of the task.

COMMENTS:

END TASK STOP TIME: _ _ _ __

ADMIN 209 r2 Page 10 of 12 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Requires determination of HPI not being deactivated 3 Requires determination of un-satisfactory Pzr Level from other procedures 13 Requires the determination of other un-satisfactory LTOP requirements not individually itemized on pgs 8 & 9

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 controlling procedure for unit shutdown and cooldown is in progress for entering a refueling outage. Plant conditions are as described in the attachment provided.

INITIATING CUES:

Based on the conditions described above and by using any associated plant procedures, verify that LTOP requirements are being met per Enc!. 4.13 (LTOP Requirements Logic Diagram) of OP/1/A/1104/049 (Low Temperature Overpressure Protection). .

If not being met, then list all the LTOP requirements that result in LTOP not being met on the provided working copy of "LTOP Requirements Logic Diagram" Enc!. 4.13 of OP/1/A/11 04/049, LTOP.

Unit One Conditions for Determining LTOP Requirements Procedures in progress:

OP/1/Al11 02/01 0, Controlling Procedure for Unit Shutdown

-Encl. 4.10, SID from Mode 3 to Mode 4 in progress RCS Parameters:

Tc = 225°F slowly decreasing

RCS Pressure = 285 psig decreasing

Pressurizer Level = 223 inches decreasing slowly

LPI operation (Series Mode) in progress

210 RCP operation exists Primary Systems/Components status:

1A HPI pump is supplying RCP Seals

1Band 1C HPI Pumps have been racked out and tagged

1HP-27 closed; handwheel tagged; breaker tagged open

1HP-26 closed; handwheels tagged; breakers not open

1HP-409 and-41 0 switches in CR have been tagged closed

1CF-1 and -2 are Closed/ handwheels tagged and breakers tagged open

1HP-120 Travel Stop installed

LTOP Vent path has not yet been established

LTOP computer point 01 L3153 is not in alarm

1SA-2/C-3, C-4 and 1SA-18/A-3, A-4 cards are not pulled and not in alarm

1N-121 is tagged closed

Pressurizer Heater Bank 3 is deactivated with breaker white tagged

No dedicated LTOP Operator assigned

1 RC-4 is open NOTE: Any other equipment or components associated with LTOP requirements that are not described above can be assumed to be in the required position/condition to support Unit 1's current plant status.

Enclosure 4.13 OP/I/AI1104/049 LTOP Requirements Logic Diagram Page 1 of 1 RC-4 Open Tc> 325" F - - - - - - - - - - ,

PORV Auto Operable Performed By PORV Removed

~>-------,

Res < 100 psig LTOPTRAIN 1 Date/Time

_a_a ___ ._._a_a_a_._a_a_a_a_a_.

LTOPTRAIN 2 1HP*26 closedlhandwheel lagged and bkr lagged open 1HP409 CR switch lagged closed 1HP-41 a CR switch tagged closed LTOP 1 Hp*27 closedlhandwheel tagged and bkr tagged open -------i Requirements 1HP-409 CR switch tagged closed Satisfied 1HP-410 CR switch tagged closed 1CF-1Closedl handwheel tagged and bkr tagged open OR')>-------------'

1A eFT depressurized to < 373 psig i I NOTE: Ene. 4.7 (LTOP Computer 1CF-2 closed/handwheel tagged and bkr lagged open 1B eFT depressurized to < 373 psig 0" ) } - - - - - - - - - - - - - - ' i Points) contains a list of points

~ HPI NOT in operation and aligned via 1HP-120 l_ ._______~~:::i:~e~._~~t~ ~~~~_:perability.

1HP-120 Travel Stop Operable - - - - - '

LTOP Computer point 01L3153 not in alarm 1SA-21C-3, C-4 cards nol pulled/not in alarm "HIGH" 1SA-1B1A-3, A-4 cards not pulled/not in alarm OAe operable IN-121 Tagged Closed pzr Htr Bank 3 Deactivated Pzr Htr Bank 4 Deactivated oo)}-------'

Res pressure within limits RV Head Off PZR level within limits SG Primary Manway Off OR )-------'

Dedicated LTOP Operator assigned pzr Manway Off Unit 1 LTOP Logic Rev. 21.des LTOP vent established 01 LTOP0001.DES 04/02/08 rtr

If an ReS vent path is established per Enclosure 4.5 (LTOP Vent Paths). this requirement can be considered met during HPI testing.

Admin-123 r2 Page 1 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-123 MINIMUM INCORE DETECTOR OPERABILITY VERIFICATION CANDIDATE EXAMINER

Admin-123 r2 Page 2 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Minimum incore detector operability verification Alternate Path:

Facility JPM #:

KIA Rating(s):

Gen 2.1.37 (4.3/4.6)

Task Standard:

Student determines if the minimum number of operable Incore detectors is available for the Backup Incore Detector system.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant _ __ Perform _X_ Simulate

References:

PT111A/0600/001, Periodic Instrument Surveillance, Enclosures 13.1 OP/1/A/110S/014, Control Rom Instrumentation Operation And Information PT/1/A/11 03/019, Backup Incore Detector System Validation Time: 20 min. Time Critical: NO

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

Candidate: Time Start: _ __

NAME Time Finish: _ __

Performance Rating: SAT ___ UNSAT _ __ Performance Time _ __

Examiner: _ _ _ _ _ _ _ _ _ _ _ __ - - - - - - - - -_____~/__-

NAME SIGNATURE DATE

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

COMMENTS

Admin-123 r2 Page 3 of 10 SIMULATOR OPERATOR INSTRUCTIONS:

1. NONE

Admin-123 r2 Page 4 of 10 Tools/Equipment/Procedures Needed:

PT/1/A/06001001, Periodic Instrument Surveillance, Enclosures 13.1 OP/1/A/11 OS/014, Control Rom Instrumentation Operation And Information PT/O/A/11 03/019 (Backup Incore Detector System)

READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 has been operating at 100% power for 4 days.

On the OAC the Computer Reactor Calculation Package for Incore Detector data calculations has been OOS for the past 2 days.

Backup Incore Chart Recorder "B" is OOS for the past week. Parts ordered.

1NI-7 has just failed.

The Control Rom SRO has verified per OP/1/A/110S/014, Control Rom Instrumentation Operation And Information, (Encl. 4.7, RPS Information; Step 3.3.3) that Axial Imbalance and aPT surveillances must now be performed using the Backup Incore Detectors.

INITIATING CUE:

The SRO directs you to verify that minimum Incore detector operability requirements are met by performing PT/1/A/11 03/019, Backup Incore Detector System, through Step 12.1.4. using the attached data sheet.

Admin-123 r2 Page 5 of 10 START TIME: _ __

STEP 1: Step 3.3.3 (OP/1/A/1105/014, Control Rom Instrumentation Operation And Information, Enc!. 4.7, RPS Information)

- SAT IF Reactor calculation package is NOT running, verify minimum incore detector operability requirements are met. Refer to PT/1/A/11 03/019 (Backup Incore Detector System).

- UNSAT STANDARD: Determines that Reactor calculation package is NOT running per Initial Conditions and refers to PT/1/A/1103/019 (Backup Incore Detector System).

COMMENTS:

STEP 2: PT/1/A/1103/019, Backup Incore Detector System NOTE: IF this procedure is being performed only to satisfy section 1.1, then perform Section 12.1 AND N/A Section 12.2. - SAT

_12.1.1 On Enclosure 13.1, Required Backup Recorder Points for - UNSAT Calculating Axial Power Imbalance AND 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt, place an "X" next to the backup recorder points which are inoperable as indicated by off-scale readings OR notes attached to the recorders.

STANDARD: Candidate utilizes the provided list of Recorder A Incore Detector data.

On Enclosure 13.1, PT/1/A/11 03/019 (Backup Incore Detector System) candidate places an "X" on each numbered point that is inoperable as indicated by off-scale readings or notes attached to the chart.

-Points #5 and #9 are NOT operable

-Per initial conditions all Recorder B data pOints are NOT operable.

COMMENTS:

Admin-123 r2 Page 6 of 10 STEP 3 CRITICAL STEP

_12.1.2 Verify that all three required points on at least three detector strings are operable per instructions on Enclosure 13.1, Required Backup - SAT Recorder Points for Calculating Axial Power Imbalance. (Acceptance Criteria 11.1.1)

- UNSAT STANDARD: Determines that a sufficient number of incore detectors DOES exist to allow calculation of Axial Power Imbalance.

COMMENTS:

STEP 4 CRITICAL STEP

__ 12.1.3 Verify that all four required pOints on at least four sets (two sets in each axial core half) are operable per instructions on Enclosure 13.2, Required Backup Recorder Points for Calculating Quadrant Power - SAT Tilt. (Acceptance Criteria 11.1 .2)

STANDARD: Determines that a sufficient number of incore detectors DOES NOT exist - UNSAT to allow calculation of Quadrant Power Tilt.

COMMENTS:

Admin-123 r2 Page 7 of 10 STEP 5: CRITICAL STEP

_12.1.4 IF either step 12.1.2 OR 12.1.3 CANNOT be satisfied; A. Notify the Unit Supervisor. SAT B. Take actions described in 6.2.

UNSAT STANDARD: Candidate determines to notify the Unit Supervisor and to take actions described in Step 6.2 as described below:

Step 6.2 IF the incore system is NOT available on the unit computer AND the backup recorder points are NOT operable per this procedure, then the reactor power shall be reduced below 80% of the power allowable for the existing reactor coolant pump combination within eight hours unless:

6.2.1 The incore system is restored on the unit computer.

OR 6.2.2 The backup recorder points are restored to meet the minimum requirements for operability. (ref. SLC 16.7.8)

COMMENTS:

END TASK TIME STOP: _ __

Admin-123 r2 Page 8 of 10 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 3 Determines if enough incore detectors are available to calculate Power Imbalance 4 Determines if enough incore detectors are available to calculate Quadrant Power Tilt 6 Provides final determination of overall incore detector availability, notification requirements, and required actions.

BACKUP INCORE CHART "A" Point # % Location 1 132.7 G09-L2 2 138.0 G09-L4 3 133.3 G09-L6 4 145.6 E09-L2 5 *Off scale high E09-L4 6 142.5 E09-L6 7 128.8 G05-L4 8 133.8 G05-L6 9 **126.3 M07-L2 10 122.9 M07-L2 11 127.5 K11-L2 12 122.2 K11-L2 13 144.4 F13-L2 14 145.0 D05-L2 15 143.1 F13-L4 16 142.5 C03-L6 17 144.5 C06-L2 18 133.6 F13-L6 19 133.8 010-L6 20 135.5 L03-L2 21 136.1 L03-L4 22 135.6 D05-L6 23 133.8 010-L6 24 142.5 D05-L4

Work Request written

- Replaced last RFO: OOS until calibration is complete

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 has been operating at 100% power for 4 days.

On the OAC the Computer Reactor Calculation Package for Incore Detector data calculations has been OOS for the past 2 days.

Backup Incore Chart Recorder "B" is OOS for the past week. Parts ordered.

1NI-7 has just failed.

The Control Rom SRO has verified per OP/1/A/1105/014, Control Rom Instrumentation Operation And Information, (Enc!. 4.7, RPS Information; Step 3.3.3) that Axial Imbalance and OPT surveillances must now be performed using the Backup Incore Detectors.

INITIATING CUE:

The SRO directs you to verify that minimum Incore detector operability requirements are met by performing PT/1/A/11 03/019, Backup Incore Detector System, through Step 12.1.4. using the attached data sheet.

Duke Power Company Procedure No.

Oconee Nuclear Station PTI O/Alll03/019 Revision No.

006 BACKUP INCORE DETECTOR SYSTEM Electronic Reference No.

OP00941W Continuous Use PERFORMANCE I

- - - - UNCONTROLLEDFORPruNT**********

(ISSUED) - PDF Format

PT/O/A/II03/019 Page 2 of6 Backup Incore Detector System

1. Purpose 1.1 To verify the operable backup recorder points meet the minimum requirements for the inc ore instrumentation system upon loss of the incore system on the unit computer OR loss of the unit computer.

1.2 To provide a method to calculate reactor power axial imbalance AND quadrant power tilt using the backup incore detector system WHEN the inc ore system is NOT available on the unit computer AND one OR more of the excore detectors are inoperable.

2. References 2.1 Technical Specifications 3.2.2, Axial Power Imbalance 3.2.3, Quadrant Power Tilt 2.2 PT/0/A/0600/001 A (Loss of Computer) 2.3 PT11,2,3/A/0600/00 1 (Periodic Instrument Surveillance) 2.4 Unit Core Operating Limits Report (COLR) 2.5 NSD 304, Reactivity Management 2.6 Selected Licensee Commitment 16.7.8 2.7 PIP 0-01-00927

3. Time Required 3.1 Verify Backup Incore Recorders operable (Section 12.1) - 10 minutes - 1 Operator OR Reactor Engineer 3.2 Calculate Backup Tilt/Imbalance (Section 12.2) - 30 minutes - 2 Operators AND/OR Reactor Engineers

4. Prerequisite Tests 4.1 None

5. Test Equipment 5.1 Calculator

PT/O/A/1l03/019 Page 3 of6

6. Limits and Precautions 6.1 This procedure has the potential to affect Reactivity Management, since the backup incore recorders are used to monitor reactivity.

6.2 IF the incore system is NOT available on the unit computer AND the backup recorder points are NOT operable per this procedure, then the reactor power shall be reduced below 80% of the power allowable for the existing reactor coolant pump combination within eight hours unless:

6.2.1 The incore system is restored on the unit computer.

6.2.2 The backup recorder points are restored to meet the minimum requirements for operability. (ref. SLC 16.7.8) 6.3 IF the backup incore limits are exceeded then action must be taken per the applicable Technical Specifications as listed below:

6.3.1 Quadrant Power Tilt - TS 3.2.3 6.3.2 Axial Power hnbalance - TS 3.2.2

7. Required Plant Status 7.1 Quadrant power tilt surveillances are required WHEN the Unit is above 20% full power.

7.2 Reactor power imbalance surveillances are required WHEN the Unit is above 40% rated power.

8. Prerequisite System Conditions 8.1 Loss of inc ore system on the unit computer OR loss of the unit computer

9. Test Method 9.1 The backup recorder points will be checked to identify which points are a) inoperable as indicated by off-scale readings OR b) identified as inoperable OR out of calibration during the last functional verification. The remaining operable points will be checked to verify the minimum number of detectors are operable to measure axial imbalance AND quadrant power tilt as required.

9.2 Axial hnbalance AND quadrant power tilt calculations may be performed using the operable backup recorder points.

PT/O/A/II03/019 Page 4 of6

10. Data Required 10.1 Incore Backup recorder point readings

11. Acceptance Criteria NOTE: The following acceptance criteria apply only to section 12.1 of this procedure.

11.1 IF this procedure is being performed to satisfy section 1.1 of this procedure the following acceptance criteria apply.

11.1.1 All three required points on at least three detector strings are operable per instructions on Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance.

11.1.2 All four required points on at least four sets (two sets in each axial core half) are operable per instructions on Enclosure 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt.

NOTE: The following acceptance criteria apply only to section 12.2 of this procedure.

11.2 IF this procedure is being performed to satisfy section 1.2 of this procedure the following acceptance criteria apply.

11.2.1 The calculated axial imbalance is within the curve for the appropriate pump configuration shown in the current Core Operating Limits Report (COLR) on the Backup Incore Setpoint Column of the (Error-Adjusted) "Operational Power Imbalance Setpoints" Table.

11.2.2 The calculated quadrant power tilt is less than the value given in the current Core Operating Limits Report (COLR) on the Backup Incore row of the (Error- Adjusted) "Quadrant Power Tilt Setpoints" Table.

PT/O/A/1103/019 Page 5 of6

12. Procedure NOTE: IF this procedure is being performed only to satisfy section 1.1, then perform Section 12.1 AND N/A Section 12.2.

12.1 Verification of Minimum Incore Detector Operability 12.1.1 On Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance AND 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt, place an "X" next to the backup recorder points which are inoperable as indicated by off-scale readings OR notes attached to the recorders.

12.1.2 Verify that all three required points on at least three detector strings are operable per instructions on Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance. (Acceptance Criteria 11.1.1) 12.1.3 Verify that all four required points on at least four sets (two sets in each axial core half) are operable per instructions on Enclosure 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt. (Acceptance Criteria 11.1.2) 12.1.4 IF either step 12.1.2 OR 12.1.3 CANNOT be satisfied; A. Notify the Unit Supervisor.

B. Take actions described in 6.2.

NOTE: IF this portion of the procedure is being performed to fulfill the requirements of PT/I,2,3/A/0600/01 (Periodic Instrument Surveillance), then repeat the steps below every twelve hours as required AND record the calculated values in that procedure.

12.2 Calculation of Axial Imbalance AND Quadrant Power Tilt 12.2.1 Verify the reactor has been at steady state conditions (+/-2% FP) for at least 30 minutes.

12.2.2 Calculate axial imbalance per Enclosure 13.3, Axial Power Imbalance Calculation Sheet using operable recorder points identified on Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance.

12.2.3 Calculate quadrant power tilt per Enclosure 13.4, Quadrant Power Tilt Calculation Sheet using operable recorder points identified on Enclosure 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt.

PT/O/A/1103/019 Page 6 of6 12.2.4 Verify the calculated axial imbalance does NOT exceed the backup incore limits per Acceptance Criteria 11.2.1.

12.2.5 Verify the calculated quadrant power tilt does NOT exceed the backup incore limits per Acceptance Criteria 11.2.2.

12.2.6 IF either step 12.2.4 OR 12.2.5 CANNOT be satisfied, notify the Unit Supervisor AND take appropriate actions described in the applicable Technical Specification as listed below:

Quadrant Power Tilt - TS 3.2.3 Axial Power Imbalance - TS 3.2.2.

13. Enclosures 13.1 Required Backup Recorder Points for Calculating Axial Power Imbalance 13.2 Required Backup Recorder Points for Calculating Quadrant Power Tilt 13.3 Axial Power Imbalance Calculation Sheet 13.4 Quadrant Power Tilt Calculation Sheet

Enclosure 13.1 PT/O/AI1103/019 Required Backup Recorder Points for Calculating Axial Power Imbalance Page 10f3

UNIT 1 ONLY

From the following list of allowed point groupings for calculating axial power imbalance, three sets for which the points indicated are all operable AND in calibration must be available.

NOTE: 1. "A" recorder is on the Control Board; "B" is on the vertical board.

2. A set of recorder points for imbalance calculations consist of three operable points grouped together.

Any of the following groupings may be used:

Recorder Number Point Number Core Location Level Recorder Number Point Number Core Location Level A 3 G9 6 B 8 L6 6 A 2 G9 4 B 7 L6 4 A I G9 2 B 6 L6 2 I

A 22 D5 6 B 19 N4 6 A 24 D5 4 B 18 N4 4 A 14 .- --------

D5 2 B 17 N4 2 i ONLY one of the following groupings may be used:

Recorder Number Point Number Core Location Level Recorder Number Point Number Core Location Level A 6 E9 6 B 4 K5 6 A 5 E9 4 B 5 K5 4 A 4 E9 2 B 10 K5 2 ONLY one of the following groupings may be used:

Recorder Number Point Number Core Location Level Recorder Number Point Number Core Location Level A 18 F13 6 B 22 06 6 A 15 F13 4 B 21 06 4 A 13 F13 2 B 20 06 2 Recorded By Date _ _ _ _ _ _ __

Enclosure 13.1 PT/O/A/II03/019 Required Backup Recorder Points for Calculating Axial Power Imbalance Page2of3

UNIT 2 ONLY

From the following list of allowed point groupings for calculating axial power imbalance, three sets for which the points indicated are all operable AND in calibration must be available.

NOTE: 1. "A" recorder is on the Control Board; "B" is on the vertical board.

2. A set of recorder points for imbalance calculations consist of three operable points grouped together.

ANY 3 of the following 4 groupings may be used: OR ANY 3 of the following 4 groupings may be used:

Recorded By Date _ _ _ _ _ _ __

Enclosure 13.1 PT/O/AI1103/019 Required Backup Recorder Points for Calculating Axial Power Imbalance Page 3 of3

UNIT 3 ONLY

From the following list of allowed point groupings for calculating axial power imbalance, three sets for which the points indicated are all operable AND in calibration must be available.

NOTE: 1. "A" recorder is on the Control Board; "B" is on the vertical board.

2. A set of recorder points for imbalance calculations consist of three operable points grouped together.

Any of the following groupings may be used:

Recorder Number Point Number Core Location Level Recorder Number Point Number Core Location Level A 6 L6 6 B 3 G9 6 A 5 L6 4 B 2 G9 4 A 2 L6 2 B 1 G9 2 A 19 D10 6 B 19 D5 6 A 17 D10 4 B 23 D5 4 A 16 DI0 2 B 6 ~

D5

~----.------.-

2 ONLY one ofthe following groupings may be used:

Recorder Number Point Number Core Location Level Recorder Number Point Number Core Location Level A 1 GIl 6 B 5 G5 6 A 4 GIl 4 B 11 G5 4 A 10 GIl 2 B 15 G5 2 ONLY one of the following groupings may be used:

Recorder Number Point Number Core Location Level Recorder Number Point Number Core Location Level A 23 06 6 B 22 010 6 A 21 06 4 B 12 010 4 A 15 06 2 B 21 010 2 Recorded By Date _ _ _ _ _ _ __

Enclosure 13.2 PT/O/AI1lO3/019 Required Backup Recorder Points for Calculating Quadrant Power Tilt Page 10f3

UNIT 1 ONLY

From the following list of backup recorder points for calculating tilt, two sets of symmetric rings of detectors in each core half for which all the points indicated are operable AND in calibration must be available.

NOTE: 1. "A" recorder is on the Control Board; "B" is on the vertical board.

2. The sets of symmetric detectors are listed in rows horizontally.

UPPER CORE HALF CLeve I 6):

WX Xy YZ ZW Recorder Point Core Recorder Point Core Recorder Point Core Recorder Point Core Loc Number Loc Number Loc Number Loc Number A 8 05 A 6 E9 A 12 Kll A lO M7 A 17 C6 A 18 F13 A 19 OlO A 20 L3 B 1 E7 B 2 011 B 3 M9 B 4 K5 B 16 F3 B 14 ClO B 24 L13 B 22 06 LOWER CORE HALF (Level 2);

WX Xy YZ ZW Recorder Point Core Recorder Point Core Recorder Point Core Recorder Point Core Loc Number Loc Number Loc Number Loc Number A 7 05 A 4 E9 A 11 Kll A 9 M7 A 16 C6 A 13 F13 A 23 OlO A 21 L3 i B 12 E7 B 11 011 B 9 M9 B lO K5 I

,. B -----

15 F3 ~Ii_____. 13 ClO B 23 L13 B 20 06 I Recorded By Date _ _ _ _ _ _ __

Enclosure 13.2 PT/O/A/II03/019 Required Backup Recorder Points for Calculating Quadrant Power Tilt Page 2 of3

UNIT 2 ONLY

From the following list of backup recorder points for calculating tilt, two sets of symmetric rings of detectors in each core half for which all the points indicated are operable AND in calibration must be available.

NOTE: 1. "A" recorder is on the Control Board; "B" is on the vertical board.

2. The sets of symmetric detectors are listed in rows horizontally.

UPPER CORE HALF (Level 6 - first two rows, Level 5 -last two rows):

WX Xy YZ ZW Recorder Point Core Recorder Point Core Loc Recorder Point Core Recorder Point Core Loc Number Loc Number Number Loc Number A 17 G5 A 16 E9 A 20 Kll A 18 M7 !

A 22 C6 A 21 F13 A 24 010 A 23 L3 I B 17 G5 B 15 E9 B 19 Kll B 18 M7 B 22 F3 B 20 CIO B ....

24 113 B 23 06 LOWER CORE HALF (Level 2 - first two rows, Level 3 -last two rows):

WX Xy YZ ZW Recorder Point Core Loc Recorder Point Core Loc Recorder Point Core Recorder Point Core Loc Number Number Number Loc Number A 3 G5 A 2 E9 A 6 Kll A 4 M7 A 8 C6 A 7 F13 A 10 010 A 9 L3 B 3 G5 B 1 E9 B 5 Kll B 4 M7 B -_ _ 8 F3 B 6 CIO B 10 L13 B 9 06 Recorded By Date _ _ _ _ _ _ __

Enclosure 13.2 PT/O/AI1103/019 Required Backup Recorder Points for Calculating Quadrant Power Tilt Page30f3

UNIT 3 ONLY

From the following list of backup recorder points for calculating tilt, two sets of symmetric rings of detectors in each core half for which all the points indicated are operable AND in calibration must be available.

NOTE: 1. "A" recorder is on the Control Board; "B" is on the vertical board.

2. The sets of symmetric detectors are listed in rows horizontally.

UPPER CORE HALF (Level 6);

WX Xy YZ ZW Recorder Point Core Recorder Point Core Recorder Point Core Recorder Point Core Loc Number Loc Number Loc Number Loc Number A 22 E7 A 1 G11 A 18 M9 A 20 K5 A 3 F3 A 14 ClO A 24 L13 A 23 06 B 5 G5 B 4 E9 B 9 Kll B 7 M7 B 18 C6 B 20 F13 B 22 010 B 24 L3 LOWER CORE HALF (Level 2);

WX Xy YZ ZW Recorder Point Core Recorder Point Core Recorder Point Core Recorder Point Core Loc Number Loc Number Loc Number Loc Number A 12 E7 A 10 Gll A 7 M9 A 8 K5 A 9 F3 A 11 ClO A 13 L13 A 15 06 B 15 G5 B 17 E9 B 8 Kll B l3 M7 B 14 C6 B 10 F13 B 21 010 B 16 L3 I Recorded By Date _ _ _ _ _ _ __

Enclosure 13.3 PT/O/A/I103/019 Axial Power Imbalance Calculation Sheet Page lof2

1. Purpose 1.1 The purpose of this enclosure is to calculate axial power imbalance using the appropriate operable points from Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance.

2. Procedure 2.1 Using Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance choose a set of backup recorder points for which all points are operable AND record the point identifications (recorder, point number, detector location, AND level) on the blanks provided on page 2 of this enclosure.

2.2 Record the backup recorder readings on the blank provided on page 2 of this enclosure.

2.3 Record current % FP on the blanks provided on page 2 of this enclosure using the priority of thermal power indications listed in PT/I,2,3/A/06001001 (Periodic Instrument Surveillance).

Enclosure 13.3 PT/O/AI1103/019 Axial Power Imbalance Calculation Sheet Page 2 of2 2.4 Calculate imbalance for each of the three detector groupings using the following formula:

1MB = R Clevel6 OR 5) - R Clevel2 OR 3) x % FP R (level 6 OR 5) + R (level 4) + R (level 2 OR 3) where R = detector reading 2.5 The imbalance from the backup recorders is the average for the three detector groupings, calculated as indicated below:

DETECTOR DETECTOR DETECTOR READING RECORDER ID POINT # LOCATION LEVEL -ffi}

60R5 I 4 IMBr= ( ) x _ _%FP = %IMB 20R3 (--+--+-)

60R5 II 4 20R3 IMBIJ= ~ ( +__ 1

- +__ x ___ %FP = _ _%IMB 60R5 III 4 IMB IlI= ( ) x _ _%FP = _ _%IMB 20R3 (--+--+~

TOTAL _ _%IMB AVERAGE IMBALANCE = TOTALl3 = %IMB Calculated by Date/Time Verified by DatelTime _ _ _ _ _ _-

Enclosure 13.4 PT/O/A/II03/019 Quadrant Power Tilt Calculation Sheet Page 1 of 1

1. Purpose 1.1 The purpose of this enclosure is to calculate quadrant power tilt using the appropriate operable points from Enclosure 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt.

2. Procedure 2.1 Using Enclosure 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt choose an acceptable set (row) of recorder points for which all points are operable, AND record the point identifications (recorder, point number, detector location) on the blanks provided below.

2.2 Record the backup recorder readings (R) on the blanks provided below.

2.3 Calculate quadrant power tilt as indicated below:

WX Quadrant XY Quadrant Recorder Point # Core Loc Reading Recorder Point # Core Loc Reading 1st Ring Upper Core Half 2nd Ring Upper Core Half 1st Ring Lower Core Half 2nd Ring Lower Core Half Swx (sum ofWX readings) = _ __ Sxy (sum ofXY readings) = _ _ __

YZ Quadrant ZW Quadrant Recorder Point # Core Loc Reading Recorder Point # Core Loc Reading 1st Ring Upper Core Half 2nd Ring Upper Core Half 1st Ring Lower Core Half 2nd Ring Lower Core Half SyZ (sum ofYZ readings)=_ _ __ Szw (sum of ZW readings) = _ _ __

Savg = (Swx + Sxy + Syz + Szw ) 14 = _ _ _ _ _ __

Tiltquadrant = [ (Squadrant I Savg ) - 1 ] x 100 (conversion from fraction to %)

Tiltwx =[ ( _ _ 1 _ _ ) -1] x 100 = _ _% Tiltxy=[ C_ _ I _ _ ) -1] x 100 = _ _%;

Tiltyz =[ ( _ _ 1 _ _ ) -1] x 100= _ _% Tiltzw=[ C_ _ I _ _ ) -1] x 100= _ _%;

Calculated By _ _ _ _ _ _ _ _ _ _ _ Date _ _ _ _ _ _ _ _ _ Time _ _ _ __

Verified By _ _ _ _ _ _ _ _ _ _ _ Date _ _ _ _ _ _ _ _ _ Time _ _ _ __

Admin-120 r3 Page 1 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-120 Unit 3 SFP Boron and Volume Change Calculation CANDIDATE EXAMINER

Admin-120 r3 Page 2 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate the minimum makeup volumes from CBAST and 3B BHUT to raise Final SFP Boron Concentration and level and determine operability of CBAST if makeup is performed Alternate Path:

NO Facility JPM #:

ADM-106 KIA Rating(s):

Gen 2.1.23 4.3/4.4 Task Standard:

Calculate makeup volumes within +/- 10 gallons and recognize that CBAST will be outside the procedural limits of operability if used as the boric acid makeup source Preferred Evaluation Location: Preferred Evaluation Method:

Simulator _ _ In-Plant --'X'-"--__ Perform X Simulate

References:

OP/3/Al1104/006 C (SFP Makeup), Enclosure 4.8 (Unit 3 SFP Makeup From CBAST)

OP/3/Al1104/006 C (SFP Makeup), Enclosure 4.1 (Unit 3 SFP Boron and Volume Change Calculation)

OP/01Al1108/001 (Curves and General Information), Enclosure 3.2 (CBAST Volume Vs. Level Curve - All Units)

OP/0IAl1108/001 (Curves and General Information), Enclosure 3.17 (CBAST Concentration Vs. Level Curve - Unit 3)

Validation Time: 30 min. Time Critical: NO

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

Candidate: Time Start: _ __

NAME Time Finish: _ _ __

Performance Rating: SAT ___ UNSAT _ __ Performance Time _ __

Examiner: __________- - - - - -

NAME

~~~~~

SIGNATURE

____~/__ DATE

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

Comments

Admin-120 r3 Page 3 of 10 SIMULATOR OPERATOR INSTRUCTIONS:

NONE

Admin-120 r3 Page 4 of 10 Tools/EguipmenUProcedures Needed:

OP/3/A11104/006 C (SFP Makeup)

OP/0IAl1108/001 (Curves and General Information), Enclosure 3.2 (CBAST Volume Vs. Level Curve - All Units)

OP/0IAl1108/001 (Curves and General Information), Enclosure 3.17 (CBAST Concentration Vs. Level Curve-Unit 3)

Clear plastic chart reading aid READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 3 Reactor power = 75% stable

Unit 3 Spent Fuel Pool (SFP) level = 0.0 ft

Unit 3 SFP Boron = 2275 ppm

Unit 3 CBAST Boron = 13,200 ppm

Unit 3 CBAST level = 91 inches

3B BHUT Boron = 0 ppm

3SF-1 and 3SF-2 are closed

Unit 3 SFP level will be increased to + 0.6 ft and the Unit 3 SFP concentration will be raised to 2400 ppmb using Unit 3 CBAST .and 3B BHUT.

INITIATING CUE:

You are directed to perform the procedure to makeup to the Unit 3 SFP as follows:

Raise Final Unit 3 SFP Boron Concentration to 2400 ppm and level to +0.6 feet.

Using the in-progress procedure provided and any other required procedure(s), perform OP/3/A/1104/006 C (SFP Makeup), Enc!. 4.8 (Unit 3 SFP Makeup) through Step 2.4.

Admin-120 r3 Page 5 of 10 START TIME: _ __

STEP 1: Determine and locate appropriate procedure for Unit 3 CBAST makeup to the U3 SFP.

- SAT STANDARD: Candidate locates Enclosure 4.8 (U3 SFP Makeup From CBAST) of OP/3/N1104/006 C (SFP Makeup).

- UNSAT COMMENTS:

STEP 2: Step 2.2 CRITICAL STEP Determine required U3 SFP makeup volume from CBAST and OW.

IF, desired utilize Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation).

- SAT STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation) and determine that there is 1041 ga1l0.1 foot in the SFP and then calculate total gallons required to raise level to +0.6 ft. - UNSAT 0.6 ft x 1041 ga//0.1 ft = 6246 gal/ons OR Calculate the total gallons required to raise level to + 0.6 ft using OP/110B/001 (Curves and General Information) Encl. 4.26 (Miscellaneous Data).

0.6 ft x 1041 gal/O. 1 ft =6246 gal/ons COMMENTS:

Admin-120 r3 Paqe 6 of 10 STEP 3: Determine CBAST minimum makeup volume required. CRITICAL STEP STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation) SAT step 2.1.

CN1 + C2 V2 + CN3 =CNI UNSAT C 1 = 2275 ppm Present Unit 3 SFP Boron concentration V 1 = 376,000 gal = Present Unit 3 SFP volume gal C2 = 0 ppm = 3B BHUT Boron concentration V 2 =6246 gal- V3 =3B BHUT gal required C2 = 13,200 ppm = CBAST Boron concentration V3 = CBAST volume required CI = 2400 ppm = Final Unit 3 SFP Boron concentration VI =376,000 gal+ 6246 gal =382,246 gal = Final unit 3 SFP volume gal Note: SFP final vol =376,000 gal + (1041 gal/0.1ft X 0.6 ft)

=382,246 gal CBAST volume gal = (SFP final ppm) (SFP final vol) - (SFP present ppm) (SFP present vol)

CBAST ppm

= (2400 ppm) (382246 gal) - (2275 ppm) (376,000 gal) 13200 ppm CBAST volume gal = 4696.24 gal = 4696 gal (+1)

COMMENTS:

STEP 4: Determine 3B BHUT minimum makeup volume required.

CRITICAL STEP STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation) SAT step 2.1.

V2 =6246 gal- V3 =3B BHUT gal required UNSAT 3B BHUT volume gal = 6246 - 4696 = 1550 gal (+1)

COMMENTS:

Admin-120 r3 Parle 7 0 f10 STEP 5: Per Step 2.4 determine that sufficient level will be available to satisfy "CBAST Concentration vs. Level" curve in OP/0IN1108/001 (Curves and CRITICAL STEP General Information)

- SAT STANDARD: Refer to OP/0IN11 08/001 Enclosure 4.2 (CBAST Volume Vs. Level Curve - All Units) and determine that a CBAST level of 91 inches equates to 14,000 gallons in CBAST.

- UNSAT COMMENTS:

STEP 6: Per Step 2.4 determine that sufficient level will be available to satisfy CRITICAL STEP "CBAST Concentration vs. Level" curve in OP/0IN11 08/001 (Curves and General Information) , - SAT STANDARD: Refer to OP/0IN11 08/001 Enclosure 4.17 (CBAST Concentration Vs.

Level Curve - Unit 3) determine that the minimum level required in CBAST at 13,200 ppm to meet Operability is approximately 71.5 inches - UNSAT COMMENTS:

STEP 7: Per Step 2.4 determine that sufficient level will be available to satisfy CRITICAL STEP "CBAST Concentration vs. Level" curve in OP/0IN1108/001 (Curves and General Information) - SAT STANDARD: Refer to OP/0/A/1108/001 Enclosure 4.2 (CBAST Volume Vs. Level Curve - All Units) and calculate the remaining level in CBAST if 4696 gallons is transferred from CBAST to the Unit 3 SFP. - UNSAT 14,000 gal- 4696 gal =9304 gal 9304 gal is approximately 67 inches COMMENTS

Admin-120 r3 Page 8 of 10 STEP 8: Per Step 2.4 determine that sufficient level will be available to satisfy CRITICAL STEP "CBAST Concentration vs. Level" curve in OP/O/A/1108/001 (Curves and General Information) SAT STANDARD: Determine that the CBAST that would be available after the transfer would be less than that required for CBAST operability and make notification to the SRO. UNSAT 67 inches is less than the 71.5 inches required to meet operability.

Therefore, the notification to the SRO is that: There will NOT be sufficient level available to satisfy the "CBAST Concentration vs. Level" curve of OP/O/A/1108/001 if Unit 3 CBAST is used for this makeup to the Unit 3 SFP.

END OF TASK TIME STOP: _ __

Admin-120 r3 Page 9 of 10 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 2 SFP volume change required to determine minimum CBAST volume.

3 C1 V1 calculation required to determine minimum CBAST volume.

4 C1V1 calculation required to determine minimum 3B BHUT volume 5 Required to calculate final CBAST level 6 Required to determine minimum CBAST level to meet Operability 7 Required to determine if final CAST level is less than that to meet Operability 8 Required to ensure SRO is notified of CBAST inoperability if water transfer is made so the SRO can make an informed decision of whether to continue with the procedure.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 3 Reactor power =75% stable

Unit 3 Spent Fuel Pool (SFP) level = 0.0 ft

Unit 3 SFP Boron = 2275 ppm

Unit 3 CBAST Boron =13,200 ppm

Unit 3 CBAST level = 91 inches

3B BHUT Boron =0 ppm

3SF-1 and 3SF-2 are closed

Unit 3 SFP level will be increased to + 0.6 ft and the Unit 3 SFP concentration will be raised to 2400 ppmb using Unit 3 CBAST and 3B BHUT.

INITIATING CUE:

You are directed to perform the procedure to makeup to the Unit 3 SFP as follows:

Raise Final Unit 3 SFP Boron Concentration to 2400 ppm and level to +0.6 feet.

Using the in-progress procedure provided and any other required procedure(s), perform OP/3/A/1104/006 C (SFP Makeup), Enc!. 4.8 (Unit 3 SFP Makeup) through Step 2.4.

Duke Energy Procedure No.

Oconee Nuclear Station OP;3/A/ll04/006 C SFPMakeup Revision No.

010 Electronic Reference No.

OP0095IE Continuous Use PERFORMANCE I

* * * * * * * *

UNCONTROLLED FOR PRINT * * * * * * * * * *

(ISSUED) - PDF Format

OP!3IA/II04/006 C Page 2 of4 SFPMakeup

1. Purpose To describe procedures for U3 SFP makeup.

2~ Limits and Precautions 2.1 This procedure affects reactivity management due to the potential for changing U3 SFP boron concentration. (R.M.) {I}

NOTE:

Lower SFP boron limit is to prevent violation of COLR requirements.

Upper SFP boron limit is an operational guideline. If exceeded, future makeup should be calculated to reduce concentration to within acceptable range. No other action is required for exceeding high end of range. {12}

2.2 Other related reactivity management issues: (R.M.)

U3 SFP boron should be maintained between 2250 - 2950 ppm. {7}

2.3 U3 SFP level should be maintained ~ - 2.0' to meet TS 3.7.11 requirements.

2.4 IfU3 SFP level alarms inoperable or locked in:

U3 SFP level indication should be monitored once per hour.

U3 SFP level indication should be monitored continuously during alignment changes.

2.5 IfU3 SFP level indication inoperable:

U3 SFP level should be checked locally once per hour.

U3 SFP level should be continuously monitored locally during alignment changes.

2.6 U3 SFP level should be maintained as follows:

Maximum level: + 0.7' (prevents flooding of electrical outlets).

Minimum level: - 1.0' (maintains adequate shielding for fuel handling). {2}

2.7 To prevent BWST overflow do NOT makeup to U3 SFP with BWST in purification. {3}

OP!3IA/1104/006 C Page 3 of4 NOTE:

3C SF Pump should NOT be in service when U3 SFP makeup is required prior to initiation of boiling in U3 SFP. {5}

Back pressure from 3C SF Pump will NOT allow required makeup flow from Bleed Transfer Pumps. {5}

2.8 Ability to makeup to U3 SFP at a minimum of70 gpm required prior to initiation of boiling in U3 SFP.

Either of the following provides 70 gpm makeup to U3 SFP: {4}

2A Bleed Transfer Pump

3A Bleed Transfer Pump.

3. Procedure 3.1 Perform applicable enclosure to makeup to U3 SFP.

4. Enclosures 4.1 U3 SFP Boron and Volume Change Calculation 4.2 U3 SFP Makeup From 3A BHUT 4.3 U3 SFP Makeup From 3B BHUT 4.4 U3 SFP Makeup From 2A BHUT 4.5 U3 SFP Makeup From 2B BHUT 4.6 U3 SFP Makeup From lA BHUT 4.7 U3 SFP Makeup From lB BHUT 4.8 U3 SFP Makeup From CBAST 4.9 U3 SFP Makeup From CBAST With 3A Bleed Transfer Pump 4.10 U3 SFP Makeup From BAMT

OP/3/A/I104/006 C Page 4 of 4 4.11 U3 FTC Makeup To Maximize Level For Shielding 4.12 Degraded U3 SFP Makeup Flow

Appendix

Enclosure 4.1 OP!3/A/I104/006 C U3 SFP Boron and Volume Change Page 1 of 1 Calculation

1. Initial Conditions 1.1 None.

2. Procedure NOTE:

Adding the wrong volume of makeup to U3 SFP can change final U3 SFP boron.

(R.M.)

U3 SFP boron should be maintained between 2250 - 2950 ppm. (R.M.)

Lower SFP boron limit is to prevent violation of COLR requirements.

Upper SFP boron limit is an operational guideline. If exceeded, future makeup should be calculated to reduce concentration to within acceptable range. No other action is required for exceeding high end of range. {12}

U3 SFP: 1041 gall 0.1 foot; "" 376,000 gal. total at 0 feet

U3 SFP/FTC: 1907 gal/inch 2.1 Perform calculation as required per the following equation for U3 SFP boron and volume changes:

C, = Initial Conc (ppm) V, = Initial Volume C2 = MID Conc (ppm) V2 = MID Volume C f = Final Conc (ppm) Vf= Final Volume

Enclosure 4.8 OP/3/A/I104/006 C U3 SFP Makeup From CBAST Page 1 of4

1. Initial Conditions

~1.1 U3 BWST NOT aligned for purification.

~*1.2 U3 BWST NOT aligned for makeup.

1.3 Ensure one of the following:

SF Cooling System shutdown per OP/3/AI1104/006 (SF Cooling System)

~

3A and/or 3B SF Pump(s) in operation.

~1.4 Verify 3A CBAST Pump off.

~1.5 Review OP/OIAI1104/025 (Primary Water Control Guidelines).

1.6 Perform the following: {13 }

~ 1.6.1 Review enclosure for proposed alignment.

~ 1.6.2 Mark proposed Spent Fuel Cooling System alignment on U3 CR OFD(s).

4 1.6 .3 Verify NO alignment conflicts.

~1.7 Ensure R3 reactivity management controls are established in the Control Room per SOMP 01-02 (Reactivity Management). (R.M.)

1.8 Review Limits and Precautions.

2. Procedure 2.1 Review Section 3 (U3 SFP Makeup From CBAST Information).

SRO NOTE: Minimum of5 minute flush from DW is required to ensure boron does NOT crystallize in piping.

2.2 Determine required U3 SFP makeup volume from CBAST and DW. (R.M.)

IF desired, utilize Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation).

CBAST Volume: _ _ _ _ _ _ _ gals DWVolume: _ _ _ _ _ _ _ gals 2.3 Approval of required U3 SFP makeup volume from CBAST and DW. (R.M.)

SRO

Enclosure 4.8 OP!3/AlII04/006 C U3 SFP Makeup From CBAST Page 2 of4 2.4 IF U3 in MODE I OR 2, verify that sufficient level will be available to satisfy "CBAST Concentration vs. Level" curve in OP/O/AlIIOS/OOI (Curves and General InfOlmation).

2.5 Verify Closed 3HP-16 (LDST MAKEUP ISOLATION). (R.M.)

2.6 Place "T/O SHEET" CR tag on 3HP-16 (LDST MAKEUP ISOLATION) to indicate during U3 LDST makeup only one valve isolates U3 CBAST from U3 LDST while U3 SFP makeup in progress.

2.7 Open 3CS-7S (CBAST to SF Pump Suet). (A-I-LPI Clr Rm, N End) 2.S Open 3CS-126 (CBAST to SF Pump Suet). (A-2-SF Clr Rm, N End Above and East of 3C SF Cooling Pump) 2.9 Verify Open 3CS-64 (CBAST OUTLET).

2.10 Begin monitoring the following: (R.M.)

U3 SFP level

U3 CBAST level

U3 BWST level.

2.11 Ensure 3A CBAST Pump in "MAN".

2.12 Place 3A CBAST Pump to "ON".

2.13 WHEN required volume added, place 3A CBAST Pump to "OFF".

2.14 Check CBAST volume added to U3 SFP. (R.M.)

2.15 IF incorrect volume was added, notify SRO for evaluation. (R.M.)

NOTE: This ensures adequate DW flush pressure.

2.16 Ensure DW makeup stopped to all units USTs.

2.17 Close 3CS-64 (CBAST OUTLET).

2.1S Close 3CS-70 (CBAST Recirc). (A-1-CBAST Rm) 2.19 Open 3DW-S7 (DW to CBAST Pump 3A Suction). (A-I-CBAST Rm)

Enclosure 4.8 OP/3/A/11041006 C UJ SFP Makeup From CBAST Page 3 of4 2.20 IF higher flow rate is desired:

2.20.1 Verify 3A CBAST Pump in "MAN".

2.20.2 Place 3A CBAST Pump to "ON".

2.21 Flush for;:::: 5 minutes or until total required amount ofDW added. (R.M.)

2.22 Ensure 3A CBAST Pump in "OFF".

2.23 Close 3DW-87 (DW to CBAST Pump 3A Suction). (A-I-CBAST Rm) 2.24 Check DW volume added to U3 SFP. (R.M.)

2.25 IF incorrect volume was added, notify SRO for evaluation. (R.M.)

2.26 Close 3CS-78 (CBAST to SF Pump Suet). (A-I-LPI Clr Rm, N End) 2.27 Close 3CS-126 (CBAST to SF Pump Suet). (A-2-SF Clr Rm, N End above and E of3C SF Cooling Pump) 2.28 Open 3CS-64 (CBAST OUTLET). (R.M.)

2.29 Remove "T/O SHEET" CR tag from 3HP-16 (LDST MAKEUP ISOLATION).

2.30 Open 3CS-70 (CBAST Recirc). (A-I-CBAST Rm) 2.31 Place U3 CBAST in recife per OP/31All 104/003 (Chemical Addition).

2.32 Request the following boron samples: (R.M.) {1}

U3 CBAST

U3 SFP.

2.33 Mark current Spent Fuel Cooling System alignment on U3 CR OFD(s). {13}

Enclosure 4.8 OP/31A11104/006 C U3 SFP Makeup From CBAST Page 4 of4

3. U3 SFP Makeup From CBAST Information 3.1 Makeup flow is dependent on number and configuration of SF Pumps in operation.

Makeup flow enters at SF Pump suction piping.

If SF Cooling System is operating, at least 3A or 3B SF Pump operating is required to ensure adequate mixing.

If SF Cooling System is shutdown, 3A or 3B SF Pump will be started during system startup and ensure adequate mixing.

Enclosure 4.2 OP/O/A/110S/OOl CBAST Volume Vs. Level Curve (All Units) Page 1 of 1 24 22 t-

] I II II II I I T I I -

11 i I II Y_.1 ~

20 I

18 I

I I 1~

16

_ I I I I *1 /v ~

14

_ I J I

~

(/)~ /V

.z c 00 T I )/

U

..J OJ 12

..J :J

<<0 C).c I- 10 t J/ I I I ~

8 - I 1/1/ I I 1 I 1/ I J t 1 tI I 6

4

~I~I 11:/11 T 1 T 11 2

0 o

'f 12

= ITT 24 36 48

~ I 1 I rr ' I 1T-I T

60

.. rrr 72 1 I Il" 84 I'TT rr 96 108 I*

120 I 'I 132

'1 I'TTT1 144 LEVEL (INCHES) fZ+6 /1;17ha--

Cbast 1 v.des

Enclosure 4.17 OP/O/A/IIOS/OOl CBAST Concentration Vs. Level Curve (Unit 3) Page I of I 14500 14500 14000 14000 13500 13500 13000 13000 Operable Range e e

0 Operating Guidelines: 0 0 12500 12500 '-

0

.0 10,000-14,500 ppm boron, normally .0 E

~ 12000 > 13,000 ppm boron prior to RFO. {6} 12000 n.

n.

e" e"

.Q 11500 11500 0 co co e'-

Q)

()

11000 11000 --'-

e Q)

()

e e 0 0 U 10500 10500 U l- I-(f) (f)

<{

co 10000 Inoperable Range 10000 <{

co u U 9500 9500 9000 9000 8500 8500 8000 8000 o 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 CBAST Level, inches Unit 3 CBAST Source Data: OSC-4708 Rev. 4

Enclosure 4.26 OP/O/AlI108/001 Miscellaneous Data Page lof2 NOTE: The values in this enclosure are approximations only. Do not use these numbers to perform calculations other than estimates.

1. Lake Keowee Elevation Calculation From Keowee Forebay Elevation Indication (2AB3) {14}

FOREBAY ELEV + 700' = Lake Keowee Level (level above sea level in feet)

2. Volume Vs. Level For Various Tanks And SFP Pressurizer 23.94 gallinch Quench Tank 34.94 gallinch BWST 7608 gal/foot SFP (Unit 1&2) 1512 gall 0.1 foot; "" 544,000 gal. total at 0 feet (1)

(Unit 3) 1041 gall 0.1 foot; "" 376,000 gal. total at 0 feet (2)

SFP/FTC (Unit 1&2) 2300 gallinch (3)

(Unit 3) 1907 gallinch (3)

Core Flood Tank 5 gall 0.01 foot RB Normal Sump 15 gal/inch BAMT (All Units) 400 gallons + 40 gal/inch; tank contains 400 gallons when level indication is at 0 inches. {5}

LDST (All Units) 677 gallons + 31.3 gal/inch; tank contains 677 gallons when level indication is at 0 inches. (4)

CC Surge Tank Level (All Units) 7.8 gal/inch

References:

1. OSC-4998 and drawing 0-155G

2. OSC-4776 and drawing 0-2155G

3. Drawing 0-58A

4. OSC-7129

Enclosure 4.26 OP/O/A/II08/001 Miscellaneous Data Page 2 of2

3. Volume For Various Plant Components {8}

Component Volume (gal)* Reference Letdown Coolers 60 Letdown Filters 60 Seal Return Coolers 20 Seal Return Filter Bypass 1 Seal Supply Filters 5 Seal Supply Filter Bypass 1 Pzr at 0" 718 OSC 7129 {II}

Pzr Surge Line 163 Total volume with Pzr at 0" 881 Vl,2,& 3 HPI Pump 'A' 75 Vl,2 & 3 HPI Pump 'B' 75 VI HPI Pump 'C' 136 V2 HPI Pump 'Co 121 U3 HPI Pump 'c' 128 V 1 Purification IX Bypass Line 12 0-435E & 0-435L {9}

U2 Purification IX Bypass Line 4 0-435D & 0-435L {9}

Piping between 1CS-89 and 57 3CS-89

If original volume information provided had fractional value, Volume is rounded up to next whole gallon.

Admin-122 r3 Page 1 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-122 Calculation of Primary to Secondary Leak Rate SRO ONLY CANDIDATE EXAMINER

Admin-122 r3 Page 2 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Calculation of Primary to Secondary Leak Rate and determination of shutdown requirements Alternate Path:

No Facility JPM #:

NEW KIA Rating(s):

System: 037 KIA: AA2.12 Rating: 3.3/4.1 Task Standard:

Utilize AP/11A117001031 (Primary to Secondary Leakage) Subsequent Actions to determine correct procedure path, calculation enclosure to use to quantify the leak rate, and enclosure to determine unit shutdown requirements.

Utilize AP/11A117001031 (Primary to Secondary Leakage) Enclosure 5.5 (Calculation of Primary to Secondary Leak Rate using 1RIA-40) and RCS Samples to correctly calculate SG Tube Leak flow rate.

Utilize AP/11Al17001031 (Primary to Secondary Leakage), Enclosure 5.1 (Unit Shutdown Requirements) to determine shutdown requirements based on quantified leak rate from Enclosure 5.5.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant _,,-,X,--_ Perform X Simulate

References:

Validation Time: 16 minutes Time Critical: NO

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

Candidate: Time Start: _ _ __

NAME Time Finish: _ _ __

Performance Rating: SAT ___ UNSAT _ __ Performance Time: _ _ __

Examiner: _________________

NAME SIGNATURE DATE

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

COMMENTS

Admin-122 r3 Page 3 of 10 SIMULATOR OPERATOR INSTRUCTIONS:

None

Admin-122 r3 Page 4 of 10 Tools/Equipment/Procedures Needed:

AP/11A117001031 complete up thru Step 4.13 Calculator READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit ONE initial conditions:

Time =0400

Reactor power =37% stable

AP/11A117001031 (Primary to Secondary Leakage) entered due to suspected leakage

> 5 gpd but < 25 gpm

1RIA-40 = 452 cpm

~ Spiked as high as 721 cpm over the last two hours

OAC primary to secondary leak rate calculation is NOT available

RP and Primary Chemistry sample results are as follows:

~ Total Xe 133 equivalent activity (from RP CSAE off-gas sample) = 2.0 E-5 IJCilml

~ Total Xe 133 activity (from RP CSAE off-gas sample) =2.13 E-5 IJCilml

~ RCS Xe 133 equivalent corrected (from Primary Chemistry RCS sample) =0.252 IJCilml

~ RCS Xe 133 activity (from Primary Chemistry RCS sample) = 0.275 IJCi/ml

~ CSAE off-gas flow = 12.5 scfm INITIATING CUES:

AP/1/Al1700/031 is complete up thru Step 4.13. You are to continue in the AP and determine the primary to secondary leak rate and make a recommendation for continued operation based on the calculated leak rate.

Primary to Secondary Leak Rate = _ _ _ _ _ _ __

Print Name Signature

Admin-122 r3 Page 5 of 10 START TIME: _ __

STEP 1: SA Step 4.14 Verify OAC primary to secondary leak rate calculation available (including 1RIA-40 operable). - SAT STANDARD: Candidate determines from initial conditions that OAC program is NOT available. He must follow the RNO and GO TO Step 4.17 - UNSAT COMMENTS:

STEP 2: SA Step 4.17 Verify §ll of the following:

- SAT

_ Rx power >40%

_ 1RIA-59 operable

_ 1RIA-60 operable

- UNSAT STANDARD: Candidate determines from initial conditions that power is < 40%. He must follow the RNO and GO TO Step 4.19 COMMENTS:

STEP 3: SA Step 4.19 CRITICAL STEP

_ Verify 1RIA-40 operable.

- SAT STANDARD: Candidate determines from initial conditions that 1RIA-40 is operable.

He must NOT follow the RNO. If the candidate is confused about the OAC calculation being operable, he could go to the RNO and perform Encl 5.4 (Calculation of Primary to Secondary Leak Rate using CSAE UNSAT Off-gas and RCS Samples). There is enough information in the Initial -

Conditions to perform the calculation, although the calculation would give an incorrect, but plausible value)

COMMENTS:

Admin-122 r3 Page 6 0 f10 STEP 4: SA Step 4.20 CRITICAL STEP

_ PERFORM Encl 5.5 (Calculation of Primary to Secondary Leak Rate using 1RIA-40).

- SAT STANDARD: Candidate proceeds to Enclosure 5.5 COMMENTS: - UNSAT STEP 5: Enclosure 5.5 Step 1 CRITICAL STEP Obtain RCS Xe 133 equivalent corrected.

SAT STANDARD: Candidate must pick the correct RCS Xe 133 activity from the Initial conditions. It is possible to pick the wrong RCS Xe 133 activity. If the candidate uses RCS Xe 133 activity rather than RCS Xe 133 equivalent corrected activity, he will calculate an incorrect but plausible answer. - UNSAT COMMENTS:

STEP 6: Enclosure 5.5 Step 2 CRITICAL STEP Obtain 1RIA-40 counts. THEN PERFORM Enc!. 5.5 (Calculation of Primary to Secondary Leak Rate using 1RIA-40).

- SAT STANDARD: Candidate obtains the 1RIA-40 spike counts per the NOTE preceding Step 2. If the candidate uses 1RIA-40 present counts, he will calculate an incorrect but plausible answer - UNSAT COMMENTS:

Admin-122 r3 Page 7 of 10 STEP 7: Enclosure 5.5 Step 3 CRITICAL STEP Determine primary to secondary leak rate from the following formulas:

SAT STANDARD: Candidate calculates the SGTL size as follows per Ene!. 5.5. formula:

LR =100 ft3 X -,::1R,-=-IA!--4.!...::0<--,(,"",c~pm,-,-,-,-)_ _ _ _ _ X 3.67E-4 (gal)(min)(uCi/ml) UNSAT Min RCS Xe 133 eq corr (uCi/ml) (ft3)(day)(cpm)

LR = 100 ft3 X 721 cpm X 3.67E-4 (gal)(min)(uCilml) = 105 gpd (+/- 2 gpd)

Min 0.252 uCi/ml res (ft3)(day)(cpm)

COMMENTS:

STEP 8: SA Step 21 GO TO the appropriate step' based on Primary to Secondary Leak rate: SAT STANDARD: Candidate determines that the Go TO step is 4.86 based on leak rate calculation being between 100 gpd and 25 gpm and proceeds to that UNSAT step.

COMMENTS:

Step 9 SA Steps 86 and 87 Steps 86 and 87 are steps to make notifications per OMP 1-14 and to log RIA reading every 15 minutes.

These steps are not part of the JPM and if asked, the cue is that these steps are complete.

Admin-122 r3 Page 8 0 f10 STEP 10: SA Step 88 Initiate a unit shutdown to meet requirements of Encl 5.1 (Unit Shutdown -

SAT Requirements) using the following, as applicable:

STANDARD: Candidate proceeds to Enclosure 5.1 - UNSAT COMMENTS STEP 11: Encl 5.1 - Unit Shutdown Requirement CRITICAL STEP Most recent RP and Primary Chemistry samples have resulted in a SGTL rate = 105 gpd

- SAT STANDARD: Candidate utilizes the Table and Notes in AP/31 Encl. 5.1, Unit Shutdown Requirements, and determines the time to be in Mode 3 based on a leak rate of 105 gpd to be 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months from the time of - UNSAT quantification Time of quantification is assumed to be 0400 since the present time is 0400 and the time to perform the calculation should not be that long ANSWER: Unit 1 must be shutdown and in Mode 3 by 0700

- 2) Leak rate ~ 100 gpd ~ 150 gpd (sustained leak or spike)

- Per Note bullet 1, the time limits for all conditions begins when the associated leak rate is first quantified

- Per Note bullet 2, shutdown must commence immediately COMMENTS:

END TASK - PART TWO STOP TIME: _ _ _ __

Admin-122 r3 Page 9 of 10 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 3 Required to perform the correct procedural path 4 Required to calculate the leak rate correctly 5 Required to calculate the leak rate correctly 6 Required to calculate the leak rate correctly 7 Required to calculate the leak rate correctly 11 Required to determine time of shutdown to Mode 3

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit ONE initial conditions:

Time = 0400

Reactor power = 37% stable

AP/1/N17001031 (Primary to Secondary Leakage) entered due to suspected leakage

> 5 gpd but < 25 gpm

1RIA-40 = 452 cpm

~ Spiked as high as 721 cpm over the last two hours

OAC primary to secondary leak rate calculation is NOT available

RP and Primary Chemistry sample results are as follows:

~ Total Xe 133 equivalent activity (from RP CSAE off-gas sample) =2.0 E-5 jJCilml

~ Total Xe 133 activity (from RP CSAE off-gas sample) = 2.13 E-5 jJCilml

~ RCS Xe 133 equivalent corrected (from Primary Chemistry RCS sample =0.252 jJCilml

~ RCS Xe 133 activity (from Primary Chemistry RCS sample = 0.275 jJCilml

~ CSAE off-gas flow = 12.5 scfm INITIATING CUES:

AP/1/N17001031 is complete up thru Step 4.13. You are to continue in the AP and determine the primary to secondary leak rate and make a recommendation for continued operation based on the calculated leak rate.

Primary to Secondary Leak Rate =________

Print Name Signature

Duke Energy Procedure No.

Oconee Nuclear Station AP/I/A/1700/031 PRIMARY TO SECONDARY LEAKAGE Revision No.

015 Electronic Reference No.

OPOO95Z1 PERFORMANCE I

- - - - UNCONTROLLEDFORPillNT**********

(ISSUED) - PDF Format

THIS PAGE INTENTIONALLY BLANK AP/liAJ1700/031 Page 1 of 45

1. Entry Conditions Any actual or suspected primary to secondary leakage ~ 5 gpd and < 25 gpm while above decay heat removal.

2. Automatic Systems Actions None

3. Immediate Manual Actions None

AP/I/A/17001031 Page 2 of45 THIS PAGE INTENTIONALLY BLANK

AP/l!NI700/031 Page 3 of 45

4. Subsequent Actions ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

NOTE The primary to secondary leak rate can be determined by the following means:

OAC point OlPl599 (EST TOTAL PRI TO SEC LEAKRATE) ifOAC primary to secondary leak rate calculation available (including lRIA-40 operable).

Sum of I RIA-59 and lRlA-60 readings ifboth operable and reactor power> 40%.

Estimated SGTR leak rate formula:

Leak rate = +

MU SI LD TSR Where:

MU Makeup Flow SI Seal Inlet Hdr Flow LD Letdown TSR = Total Seal Return Flow If the EOP is NOT already in progress, entry will be directly to the SGTR tab.

4.1 ~ IAAT primary to secondary leak rate is ~ 25 gpm (36,000 gpd),

THEN GO TO Unit 1 EOP.

4.2 t IAAT either of the following exists for lRIA-54:

/Go TO Step 4.5.

_ is in High alann

_ inoperable THEN perform Steps 4.3 - 4.4.

NOTE The white tags can be created and hung after the TBS pump breakers are opened. {I}

4.3 Dispatch an operator to open and white tag the following:

IXD-R3C (lA TURBINE BUILDING SUMP PUMP BKR)

_IXE-R3D (IB TURBINE BUILDING SUMP PUMP BKR)

AP/I/AJ17001031 Page 4 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) 1RIA-54 in High alarm or inoperable ... (open TBS pump breakers)

AP/liAl1700/031 Page 5 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OnTAINED 4.4 NotifY Secondary Chemistry to perform the following:

/obtain a TBS sample.

~commend TBS release path.

4.5 -.x:. IAAT gross tube leakage is indicated r by an increase in normal RC makeup flow, THEN GO TO Step 4.79.

4.6 ;L' IAAT a tritium sample indicates

~ 75 gpd primary to secondary leakage, THEN GO TO Step 4.86.

............................................ ********************-7*************_******************..............................

4.7 VerifY power escalation in progress. ~ GO TO Step 4.12.

4.8 VerifY both of the following: _ GO TO Step 4.10

_ Rx power::;; 40 %

1RlA-40 in alarm 4.9 _ Suspend power escalation until new data (RCS Xe-133 Equivalent Corrected, Total CSAE Flow) can be put into OAC tube leak calculation per OP/O/AlII 06/031 (Primary to Secondary Leak Rate Monitoring and Instrumentation).

4.10 Verify both of the following: _ GO TO Step 4.12.

_ Rx power> 40 %

_ Any ofthe following in alann:

lRlA-40

lR1A-59

lRlA-60 4.11 _ Suspend power escalation until leak rate is validated using an alternate indication.

APII1AI17001031 Page 6 of45 IF AT ANY TIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) 1RIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates;:::: 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

AP/l!AJI700/031 Page 7 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE The samples taken in the steps below are used to verifY primary to secondary leak rate. CSAE off-gas samples and RCS samples should be taken at approximately the same time (within 15 minutes of each other, if possible).

4.12 Notify RP to perform the following:

~e a portable monitor to identifY leaking SG. {2}

~tain CSAE off-gas sample.

~pect contact from Primary Chemistry to coordinate CSAE off-gas and RCS sample times within 15 minutes.

4.13 Notify Primary Chemistry to perform the following:

~btain an RCS sample for use in c~lating SG tube leakage rate.

V"Contact RP to coordinate CSAE off-gas and ReS sample times within 15 minutes.

4.14 _ VerifY OAC primary to secondary leak _ GO TO Step 4.17.

rate calculation available (including lRIA-40 operable).

4.15 _ Determine primary to secondary leakage rate using OAC point 01P1599 (EST TOTAL PRI TO SEC LEAKRATE).

4.16 _

- - - _.MM ** _

GO TO Step 4.21.

- - _ _ _ . _ **** _ _ _ _ *** _ *** _ _ _ _ _ ***** _ _ _ _ **** _ _ _ _ ********* _ ** _ . _ ******* ____ ********* __ ** _ ............. M ******************** _ **** __ ***** _ **** _ _ *********** _ _ _ _ **** _ _ _ ** * ****** _ *********** _ ............ _ . _ ** _._ ...... _ ***** _._ *** _ _ _ _ ** _ ***** _ .......... _ ** _ **** _ ** _ ******* _ ** _ ***** _ *** _ *** _ **** _ _ ** _ *** __

__ ...... ___ ._ **** _._. _ _ ********** _ _ _ _ ** _ _ . _.. _

4.17 VerifY all of the following: _ GO TO Step 4.19.

_ Rx power> 40 %

_ lRIA-59 operable

_ IRIA-60 operable 4.18 _ GO TO Step 4.21.

AP!l/A/17001031 Page 8 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

APit/AJ1700/031 Page 9 of 45 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.19 _ VerifY 1RIA-40 operable. 1. Initiate action to meet SLC 16.11.3 requirements.

2. _ WHEN CSAE off-gas and RCS samples are available, THEN PERFORM Encl5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples).

3._ GO TO Step 4.21.

4.20 _ PERFORM Encl 5.5 (Calculation of Primary to Secondary Leak Rate using 1RIA-40). {3}

4.21 GO TO the appropriate step based on Primary to Secondary Leak Rate:

Primary to Secondary Step Leak Rate

> 25 gpm (36,000 gpd) 4.1 100 gpd - 25 gpm 4.86 (0.0694 gpm - 36,000 gpd) 75 gpd - < 100 gpd 4.51 (0.05205 gpm - < 0.0694 gpm) 30 gpd - < 75 gpd 4.53 (0.02082 gpm - < 0.05205 gpm) 5 gpd - < 30 gpd 4.33 (0.003472 gpm - < 0.02082 gpm)

< 5 gpd (0.003472 gpm) 4.22

AP/I/A/17001031 Page 10 0[45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alann or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in nonnal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

1 API I Al1700/031 Page 11 of45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.22 _ WHEN CSAE off-gas and RCS samples are available, THEN PERFORM Encl 5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples) to confirm rate.

4.23 _ Verify primary to secondary leak rate _ GO TO Step 4.33.

confrrmed < 5 gpd (0.003472 gpm).

4.24 Notify the following to take a second sample (within 15 minutes of each other, if possible):

Group Sample RP CSAE Primary Chemistry RCS 4.25 _ WHEN second CSAE off-gas and RCS samples are available, THEN PERFORM Encl 5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples) to confirm rate.

4.26 _ Verify primary to secondary leak rate _ GO TO Step 4.33.

confirmed < 5 gpd (0.003472 gpm).

4.27 _ Verify lRlA-40 operable. 1. Initiate action to meet SLC 16.11.3 requirements.

2._ GO TO Step 4.29.

/

AP/I1AJ17001031 Page 12 of 45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

AP/I/A/17001031 Page 13 of 45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.28 Initiate Encl 5.8 (Resetting lRIA-40 and OAC Setpoints) to install the following alann setpoints: {7}

_ lRIA-40 High - 30 gpd

_ lRIA-40 Alert - 5 gpd

_ OAC point 01K1430 (TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT) - 5 gpd 4.29 Notify SPOC to perform AMlOIA/03611014 (Resetting Alarm Setpoints for MGP Main Steam Line N-16 Radiation Monitor) to install the following setpoints:

_ lRIA-59 High - 30 gpd

_ lRIA-60 High - 30 gpd

_ lRIA-59 Alert - 5 gpd

_ 1RIA-60 Alert - 5 gpd 4.30 Notify Secondary Chemistry of the following:

_ Primary to secondary leak rate has been confirmed < 5 gpd and this procedure will be exited.

_ To recommend TBS release path.

4.31 Notify the following that primary to secondary leak rate has been confirmed

< 5 gpd and this procedure will be exited:

RP

_ Primary Chemistry

_ Personnel previously notified per OMP 1-14 (Notifications) 4.32 _ EXIT this procedure.

AP/I/A/17001031 Page 14 of 45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is 2': 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates 2': 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

API 1IAil 700103 1 Page 15 of 45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.33 _ IAAT primary to secondary leak rate increases to ;?:: 30 gpd (0.02082 gpm),

THEN GO TO Step 4.53.

4.34 Verify lRIA-40 operable. 1. Initiate action to meet SLC 16.11.3 requirements.

2. _ Monitor the following at least twice per shift for indications of an increasing leak rate: {4}

lRIA-16

lRIA-17

lRIA-59 (when Rx power> 40 %)

lRIA-60 (when Rx power> 40 %)

3. _ GO TO Step 4.36.

4.35 _ Monitor the following at least once per shift for indications of an increasing leak rate: {4}

lRIA-16

1RIA-I 7

1RIA-40

1RIA-59 (when Rx power> 40 %)

1RIA-60 (when Rx power> 40 %)

4.36 _ Make notifications of primary to secondary leakage per OMP 1-14 (N otifications).

4.37 _ Maintain the Auto Log to include the following:

lRIA-16, 17,40,59, and 60 readings

RCS activity levels

Calculated leak sizes (including those based on lRlA-40 readings)

AP/I/A/1700/031 Page 16 of 45 IF AT ANY TIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRlA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.33) primary to secondary leak rate increases to ~ 30 gpd ... (GO TO guidance to increase monitoring)

AP/l/A/1700/031 Page 17 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.38 _ Issue a priority work request for any OOS SG tube leak monitoring equipment.

4.39 Notify RP and Primary Chemistry to perform CSAE off-gas and RCS samples based on RIA operability: {5}{6}

Frequency tRIA 40 Inoperable (hr)

Rx power:S; 40 % 12 1RIA-59 or lRIA-60 12 Inoperable Both lRIA-59 and 1RIA-60 Operable with Rx power> 40 % 8 AND 1RIA-45 inoperable {17}

Both tRIA-59 and lRIA-60 Operable with Rx power> 40 % 24 AND lRIA-45 operable Frequency tRIA 40 Operable (hr)

Yes 24 4.40 _ IAAT CSAE off-gas sample and RCS _ GO TO Step 4.44.

sample results become available, THEN perform Steps 4.41 - 4.43.

4.41 _ PERFORM Encl5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples).

4.42 _ Log leak rate calculation results in Auto Log.

AP/I/A/17001031 Page 18 of 45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.33) primary to secondary leak rate increases to ~ 30 gpd ... (GO TO guidance to increase monitoring)

(4.40) CSAE off-gas sample and RCS sample results become available ... (calculate and record primary to secondary leak rate)

AP/I/A/l7001031 Page 19 of 45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.43 Notify the following to enter leak rate calculation results in the Excel leakage spreadsheet:

_ Ops Mods Supervisor

_ Ops Work Process Manager Administrative Specialist 4.44 Notify SP~C to perfonn AM/OIA/036 11014 (Resetting Alann Setpoints for MGP Main Steam Line N-l6 Radiation Monitor) to install the following setpoints for the RIA on any SG with ~

5gpd leakage:

_ lRIA-59 High - 75 gpd

_ lRIA-60 High - 75 gpd

_ lRIA-59 Alert - 30 gpd

_ lRIA-60 Alert - 30 gpd 4.45 _ Keep turnover sheet up to date with:

OlK1430 (Total Pri To Sec Leakrate Admin Limit) setpoint

lRIA-40, 59, 60 High and Alert alann setpoints 4.46 _ IAAT lRIA-40 is operable, _ GO TO Step 4.48.

THEN GO TO Step 4.47.

4.47 PERFORM Encl5.8 (Resetting lRIA-40 and OAC Setpoints) to set the following alann setpoints: {7}

_ lRIA-40 High - 75 gpd

_ 1RIA-40 Alert - 30 gpd

_ OAC point OlK1430 (TOTAL PRJ TO SEC LEAKRATE ADMIN LIMIT) - 30 gpd 4.48 _ Notify OSM to include most recent primary to secondary leak rate (detennined by CSAE off-gas sample or lRIA-40 on the OSM turnover sheet). {8}

APil/Al1700/031 Page 20 of45 IF AT ANY TIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.33) primary to secondary leak rate increases to ~ 30 gpd ... (GO TO guidance to increase monitoring)

(4.40) CSAE off-gas sample and RCS sample results become available ... (calculate and record primary to secondary leak rate)

(4.46) lRIA-40 is operable ... (reset OAC and lRIA-40 setpoints and record new setpoints)

AP/l/A/1700/031 Page 21 of 45 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 4.49 -

IAAT CSAE off-gas sample indicates primary to secondary leak rate

< 5 gpd (0.003472 gpm),

THEN perform the following:

A. Notify the following to take another sample (within 15 minutes of each other, if possible):

Group Sample RP CSAE Primary Chemistry RCS B. - GO TO Step 4.25.

_ _ ****** H**HH.H ****** _ _ ._ ........ _ _ ._ ..... _ _ _

__ **** _ _ _

_ ...... _ _ _ _ ...... _ _ _ . _ ..... _ _ ......... _ _ _ ........... _ _

_ _ *** _ _ _ _ _ ** _ _ _

_ _ **** _ ********* H ................. _ _ ............ __ " ............. _ .............. _ .............* _OH ***** _m_...... _.................*...........*......._........._.._......._........__ ......__ ......__ . _.............._............__...........

4.50 - WHEN in MODE 5, THEN EXIT this procedure.

AP/I/A/1700/031 Page 22 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

AP!l/AlI700/031 Page 23 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.51 _ Verity primary to secondary leak rate _ GO TO Step 4.53.

is ~ 75 gpd for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

4.52 _ GO TO Step 4.86.

+-------_._--------------_._-------

NOTE Continuous Primary to Secondary Leakage Monitoring is provided by the following methods:

1 - OAC Point 01P1599 (EST TOTAL PRJ TO SEC LEAKRATE) including lRIA-40 operable 2 - lRIA-59 and lRIA-60 operable with power> 40%

4.53 _ IAAT all the following conditions exist:

_ Both Continuous Primary to Secondary Leakage Monitoring methods are inoperable

_ Primary to secondary leak rate

> 60 gpd (0.04164 gpm)

_ Leak unstable or increasing at time both Continuous Primary to Secondary Leakage Monitoring methods became inoperable THEN GO TO Step 4.86.

4.54 _ IAAT primary to secondary leak rate increases to either of the following:

_ ~ 75 gpd (0.05205 gpm) for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

~ 100 gpd (0.0694 gpm)

THEN GO TO Step 4.86.

4.55 _ Make notifications of primary to secondary leakage per OMP 1-14 (Notifications).

AP/l/AJI700/031 Page 24 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.53) both Continuous Primary to Secondary Leakage Monitoring methods inoperable AND primary to secondary leak rate> 60 gpd AND leak unstable/increasing at time both Continuous Primary Secondary Leakage Monitoring methods became inoperable ...

(GO TO shutdown guidance)

(4.54) primary to secondary leak rate increases to ~ 75 gpd for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR ~ 100 gpd ...

(GO TO shutdown guidance)

AP!l/Al1700/031 Page 25 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.56 _ Monitor the following every 15 minutes for indications of increasing leak rate: {9}

1RlA-16

1RlA-17

1RlA-40

lRlA-59 (when Rx power> 40 %)

lRlA-60 (when Rx power> 40 %)

4.57 IAAT leak rate is stable (~ lO%

change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time period),

THEN reduce monitoring frequency of the following to every two hours:

lRlA-16

1RlA-17

1RlA-40

lRlA-59 (when Rx power> 40 %)

lRlA-60 (when Rx power> 40 %)

4.58 _ Maintain the Auto Log to include the following:

1RlA-16, 17,40,59, and 60 readings

RCS activity levels

Calculated leak sizes (including those based on 1RIA -40 readings) 4.59 _ VerifY affected SG identified. {2} Attempt to identify affected SG by any of the following methods:

_ 1RlA -16/17 readings

_ 1RlA-59/60 readings (when Rx power

>40%)

_ Local RP surveys of MS lines

AP/l/A/1700/031 Page 26 of45 IF AT ANY TIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable .. , (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.53) both Continuous Primary to Secondary Leakage Monitoring methods inoperable AND primary to secondary leak rate> 60 gpd AND leak unstable/increasing at time both Continuous Primary Secondary Leakage Monitoring methods became inoperable ...

(GO TO shutdown guidance)

(4.54) primary to secondary leak rate increases to ~ 75 gpd for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR ~ 100 gpd ...

(GO TO shutdown guidance)

(4.57) leak rate is stable (~ 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time period) ... (reduce monitoring frequency of RIAs to every two hours)

AP/I/A/1700/031 Page 27 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.60 _ Issue a priority work request for any OOS SG tube leak monitoring equipment.

4.61 IAAT the OSM desires, THEN initiate Encl5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination). {lO}

4.62 Notify RP and Primary Chemistry to perform CSAE off-gas and RCS samples based on RIA operability: {5}{6}

Frequency tRIA 40 Inoperable (hr)

Rx power::;; 40 % 4 1RIA-59 or 1RlA-60 4

Inoperable Both 1RIA-59 and 1RIA-60 Operable with Rxpower> 40 % 8 AND 1RlA-45 inoperable {l7}

Both 1RIA-59 and 1RIA-60 Operable with Rx power> 40 % 12 AND 1RIA-45 operable Frequency tRIA 40 Operable (hr)

Yes 12 4.63 _ IAAT CSAE off-gas sample and RCS _ GO TO Step 4.67.

sample results become available, THEN perform Steps 4.64 - 4.66.

AP/l/A/1700/031 Page 28 of 45 IF AT ANY TIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.53) both Continuous Primary to Secondary Leakage Monitoring methods inoperable AND primary to secondary leak rate> 60 gpd AND leak unstable/increasing at time both Continuous Primary Secondary Leakage Monitoring methods became inoperable ...

(GO TO shutdown guidance)

(4.54) primary to secondary leak rate increases to ~ 75 gpd for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR ~ 100 gpd ...

(GO TO shutdown guidance)

(4.57) leak rate is stable ($; 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time period) ... (reduce monitoring frequency of RIAs to every two hours)

(4.61) OSM desires ... (initiate Encl5.2 to reduce secondary leakage and cross-unit contamination)

(4.63) CSAE off-gas and RCS sample results become available ... (calculate and record primary to secondary leak rate)

AP!l IAI 1700/03 1 Page 29 of 45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.64 _ PERFORM Enc1 5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples).

4.65 _ Log leak rate calculation results in Auto Log.

4.66 Notify the following to enter leak rate calculation results in the Excel leakage spreadsheet:

_ Ops Mods Supervisor

_ Ops Work Process Manager Administrative Specialist 4.67 _ Keep turnover sheet up to date with:

01Kl430 (TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT) setpoint

lRIA-40, 59, 60 High and Alert alarm setpoints 4.68 _ IAAT lRIA-40 is operable, _ GO TO Step 4.70.

AND primary to secondary leak rate is unstable (> 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period),

THEN GO TO Step 4.69 4.69 PERFORM Enc1 5.8 (Resetting lRIA-40 and OAC Setpoints) to set the following alarm setpoints: {7}

_ lRIA-40 High -75 gpd

_ 1RIA -40 Alert - 75 gpd

_ OAC point 01K1430 (TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT) - 75 gpd 4.70 _ IAAT lRIA-40 is operable, _ GO TO Step 4.72.

AND primary to secondary leak rate is stable (510% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period),

THEN GO TO Step 4.71.

AP/l/AJ1700/031 Page 30 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) 1RIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.53) both Continuous Primary to Secondary Leakage Monitoring methods inoperable AND primary to secondary leak rate> 60 gpd AND leak unstable/increasing at time both Continuous Primary Secondary Leakage Monitoring methods became inoperable ...

(GO TO shutdown guidance)

(4.54) primary to secondary leak rate increases to ~ 75 gpd for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR ~ 100 gpd ...

(GO TO shutdown guidance)

(4.57) leak rate is stable (~ 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time period) ... (reduce monitoring frequency of RIAs to every two hours)

(4.61) OSM desires ... (initiate Enc15.2 to reduce secondary leakage and cross-unit contamination)

(4.63) CSAE off-gas and RCS sample results become available ... (calculate and record primary to secondary leak rate)

(4.68) lRIA-40 is operable AND primary to secondary leak rate is unstable ... (set OAC and lRIA-40 setpoints to 75 gpd)

(4.70) lRIA-40 is operable AND primary to secondary leak rate is stable ... (set OAC and lRIA-40 setpoints to 75 gpd and 30 gpd above current reading)

APll/A/17001031 Page 31 of45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.71 PERFORM Encl5.8 (Resetting 1RIA-40 and OAC Setpoints) to set the following alarm setpoints: {7}

_ 1RIA-40 High - 75 gpd

_ 1RIA-40 Alert - 30 gpd above existing leak rate (NOT to exceed 75 gpd)

OAC point 01K1430 (TOTAL PRl TO SEC LEAKRATE ADMIN LIMIT) - 30 gpd above existing leak rate (NOT to exceed 75 gpd) 4.72 _ IAA T primary to secondary leak rate _ GO TO Step 4.74.

is unstable (> 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period),

THEN GO TO Step 4.73.

4.73 Notify SPOC to perform AM/O/A/036l/014 (Resetting Alarm Setpoints for MGP Main Steam Line N-l6 Radiation Monitor) to install the following setpoints for the RIA on any SG with ~

30gpd leakage:

lRIA-59 High -75 gpd lRIA-60 High -75 gpd lRIA-59 Alert - 75 gpd

_ lRlA-60 Alert - 75 gpd 4.74 _ IAAT primary to secondary leak rate _ GO TO Step 4.76.

is stable (~ 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period),

THEN GO TO Step 4.75.

AP/l/AJ1700/031 Page 32 of 45 IF AT ANY TIME:

(4.1) primary to secondary leak rate is :2: 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alann or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in nonnal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates:2: 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.53) both Continuous Primary to Secondary Leakage Monitoring methods inoperable AND primary to secondary leak rate> 60 gpd AND leak unstable/increasing at time both Continuous Primary Secondary Leakage Monitoring methods became inoperable ...

(GO TO shutdown guidance)

(4.54) primary to secondary leak rate increases to:2: 75 gpd for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR:2: 100 gpd ...

(GO TO shutdown guidance)

(4.57) leak rate is stable (~ 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time period) ... (reduce monitoring frequency of RIAs to every two hours)

(4.61) OSM desires ... (initiate Enc15.2 to reduce secondary leakage and cross-unit contamination)

(4.63) CSAE off-gas and RCS sample results become available ... (calculate and record primary to secondary leak rate)

(4.68) 1RIA-40 is operable AND primary to secondary leak rate is unstable ... (set OAC and 1RIA -40 setpoints to 75 gpd)

(4.70) lRIA-40 is operable AND primary to secondary leak rate is stable ... (set OAC and lRIA-40 setpoints to 75 gpd and 30 gpd above current reading)

(4.72) primary to secondary leak rate is unstable ... (THEN GO TO applicable step)

(4.74) primary to secondary leak rate is stable ... (THEN GO TO applicable step)

AP/l!Al1700/031 Page 33 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.75 Notify SPOC to perform AM/0/A/03611014 (Resetting Alarm Setpoints for MGP Main Steam Line N-16 Radiation Monitor) to install the following setpoints for the RIA on any SG with ~

30gpd leakage:

lRIA-59 High - 75 gpd lRIA-60 High - 75 gpd lRIA-59 Alert - 30 gpd above existing leak rate (NOT to exceed 75 gpd)

_ lRIA-60 Alert - 30 gpd above existing leak rate (NOT to exceed 75 gpd) 4.76 Notify OSM to include most recent primary to secondary leak rate (determined by CSAE off-gas sample or lRIA-40) on the OSM turnover sheet. {8}

4.77 _ Prepare for response to primary to secondary leakage ~ 75 gpd by reviewing Steps 4.86 - 4.110. {lJ}

4.78 WHEN in MODE 5, THEN EXIT this procedure.

AP/I/A/1700/031 Page 34 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) 1RlA-54 in High alann or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

AP!l/Al1700/031 Page 35 of 45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.79 _ VerifY OAC primary to secondary leak _ GO TO Step 4.82.

rate calculation available (including lRlA-40 operable).

4.80 _ Determine primary to secondary leakage rate using OAC point 01P1599 (EST TOTAL PRI TO SEC LEAKRATE).

4.81 _

_._~

GO TO Step 4.86.

_ _ _ *_ _ *__ *__ *___ ** ____ ** ____ ' _ _ _ 'M'**_* _ _ _ _ _ _ _ _ _ _ _ *_ _ _ *. ____ ....... _ _ _ _ _ _ _ _ _ _ *. __ .... ___ *** _ _ _ .___ , ___ *____ ._.,. ____ ....... __ ... _ *.* _ _ _ _ _ ** _ ...... _. ___ .... __ ** _ .... __ .......... __ ...... _ _ ... _ _ _ ....... __ *____ _

4.82 VerifY all ofthe following: _ GO TO Step 4.85.

_ Rx power> 40 %

_ 1RlA-59 operable

_ I RlA-60 operable 4.83 _ Determine primary to secondary leakage rate using sum of lRlA-59 and 1RlA-60 readings.

4.84 _ GO TO Step 4.86.

4.85 Estimate SGTR leak rate:

Leak rate = - - + - -

MU SI LD TSR Leak rate = __ gpm Where:

MU Makeup Flow SI Seal Inlet Hdr Flow LD Letdown TSR = Total Seal Return Flow

AP/IIA11700/031 Page 36 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alann or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in nonnal RC makeup flow ...

(GO TO shutdown guidance)

AP/I/A/1700/031 Page 37 of 45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.86 _ Make notifications of primary to secondary leakage per OMP 1-14 (Notifications).

4.87 _ Log readings from the following every 15 minutes in the Auto Log: {9}

lR1A-16

lRIA-17

lR1A-40

lR1A-59 (when Rx power> 40 %)

lR1A-60 (when Rx power> 40 %)

4.88 Initiate a unit shutdown to meet requirements of Encl 5.1 (Unit Shutdown Requirements) using the following, as applicable:

AP129 (Rapid Unit Shutdown)

OP/1/A/ll02/004 (Operation at Power)

OP/1/A/ll02/010 (Controlling Procedure for Unit Shutdown) 4.89 _ IAAT primary to secondary leakage increases, THEN modify shutdown as required by Encl 5.1 (Unit Shutdown Requirements).

4.90 _ Notify Radwaste to stop all liquid releases in progress until sample results assures release rates within limits.

4.91 _ Stop all gaseous releases in progress until sample results assure release rates within limits.

AP/I/A/1700/031 Page 38 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) 1RIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.89) primary to secondary leakage increases ... (modify shutdown as required by EncI5.I)

AP!l/A/1700/031 Page 39 of 45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.92 _ IAAT all the following exist:

_ Primary to secondary leak rate

< 100 gpd (0.0694 gpm)

_ lRIA-40 inoperable Rx Power ~ 40 %

THEN notify RP and Primary Chemistry to sample CSAE off-gas and RCS every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.93 _ Make up to the UST only as necessary to maintain UST level> 7'.

4.94 Notify the following that a shutdown is in progress due to primary to secondary leakage:

RP

_ Primary Chemistry

_ Secondary Chemistry

AP/I/A/17001031 Page 40 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is 2:: 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.89) primary to secondary leakage increases ... (modify shutdown as required by EncI5.I)

(4.92) primary to secondary leak rate < 100 gpd (0.0694 gpm) AND lRIA-40 inoperable AND Rx Power::; 40 % ... (sample CSAE off-gas and RCS every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )

AP/l!A/I700/031 Page 41 of45 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.95 _ Initiate End 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination). {to}

1----------------

4.96 _ Verify affected SG identified. {2} Attempt to identify affected SG by any of the following methods:

_ 1RIA -16117 readings

_ lRIA-59/60 readings (when Rx power

>40%)

_ Local RP surveys of MS lines 4.97 Verify entry into this procedure was due to _ GO TO Step 4.99.

one of the following:

_ Gross tube leakage indicated by an increase in normal RC makeup flow

_ Tritium sample indicating? 75 gpd primary to secondary leak 4.98 _ GO TO Step 4.106.

4.99 _ Verify CSAE off-gas sample and RCS Notify the following to take another sample sample have been requested to verify (within 15 minutes of each other, if possible):

leak rate. Group Sample RP CSAE Primary Chemistry RCS 4.100 _ WHEN CSAE off-gas and RCS sample results become available, THEN PERFORM End 5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples).

4.101_ Log leak rate calculation results in Auto Log.

4.102 Notify the following to enter leak rate calculation results in the Excel leakage spreadsheet:

_ Ops Mods Supervisor

_ Ops Work Process Manager Administrative Specialist

AP/I/A/17001031 Page 42 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.89) primary to secondary leakage increases ... (modify shutdown as required by End 5.1)

(4.92) primary to secondary leak rate < 100 gpd (0.0694 gpm) AND lRIA-40 inoperable AND Rx Power ~ 40 % ... (sample CSAE off-gas and RCS every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )

AP/I/AJ1700/031 Page 43 of45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.103_ Ensure unit shutdown is in progress to meet the shutdown requirements of EncI5.1 (Unit Shutdown Requirements).

4.104 WHEN in MODE 3, THEN continue.

4.105_ Verify leak rate calculation 1. IF OSM desires, (Step 4.100) confirms shutdown to THEN stop unit shutdown.

MODE 5 is required due to leakage

2. _ IF unit shutdown is stopped, exceeding limits ofEncI5.1 (Unit AND only one confirmation of leak rate Shutdown Requirements).

(per Step 4.100) has been made, THEN perform the following:

A. Notify the following to take a second sample (within 15 minutes of each other, if possible):

Group Sample RP CSAE Primary Chemistry RCS B. _GO TO Step 4.100.

3. _ IF unit shutdown is stopped, THEN GO TO Step 4.21.

4._ GO TO Step 4.106.

4.106_ WHEN LPI is providing DHR, THEN dispatch an operator to perform Encl 5.3 (Local SG Isolation) to isolate affected SGs. {12}

APll/A/1700/031 Page 44 of45 IF AT ANYTIME:

(4.1) primary to secondary leak rate is;:::: 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRIA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.89) primary to secondary leakage increases ... (modify shutdown as required by End5.l)

(4.92) primary to secondary leak rate < 100 gpd (0.0694 gpm) AND lRIA-40 inoperable AND Rx Power ~ 40 % ... (sample CSAE off-gas and RCS every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )

AP/11AJ17001031 Page 45 of 45 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.107 Close the following on affected SGs: {12}

lASG IBSG 1FDW-31 1FDW-40 1FDW-36 1FDW-45 1FDW-38 1FDW-47 1FDW-372 1FDW-382 1MS-79 1MS-76 1MS-24 1MS-33 1MS-35 1MS-36 1MS-82 1MS-84 1FDW-368 1FDW-369 1SD-2 1SD-5 1SD-27 1SD-290 1SD-358 1SD-418 1SD-420 1SD-419 1SD-421 4.108 WHEN condenser vacuum is broken, OR in MODE 5, THEN notifY RP to stop taking CSAE off-gas samples.

4.109_ NotifY Primary Chemistry to stop taking non-routine samples as part of their primary to secondary leak rate monitoring program.

4.110_ EXIT this procedure.

THIS PAGE INTENTIONALLY BLANK Enclosure 5.1 APIlIAl1700/031 Unit Shutdown Requirements Page 1 of I NOTE

The time limits for all conditions begin when the associated leak rate is first quantified, typically by OAC point 01P1599 or lRIA-59/60 reading. Although grab samples may be collected to validate leak size, the time limits begin from the first quantified leak rate.

For items 1&2, shutdown must commence immediately.

For items 3-5, commencement of shutdown may be delayed until leak rate is confirmed by grab samples, however the time limit begins when the leak rate was first quantified.

Continuous Primary to Secondary Leakage Monitoring is provided by the following methods:

1-0AC Point 01P1599 (EST TOTAL PRI TO SEC LEAKRATE) including lRIA-40 operable 2-1RIA-59 and lRIA-60 operable with power> 40%

If shutdown begins based on crediting lRIA-59 and lRIA-60 (lRIA-40 inoperable), the time limit does NOT change when Rx power is decreased below 40%.

Leak Rate/Continuous Primary to Plant Condition Secondary Leakage Monitoring Status <50% Power MODE 3 MODES

1) Leak rate> 150 gpd (0.10410 gpm)

I hour 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months {I3) 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months {19)

(TS 3.4.13 applies)

2) Leak rate ~ 100 gpd ~ 150 gpd 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months {13} N/A (sustained leak or spike)

3) Leak rate ~ 75 gpd < 100 gpd with Continuous Primary to Secondary Leakage Monitoring N/A 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months N/A operable (sustained for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

4) Leak rate ~ 75 gpd < 100 gpd with both methods of Continuous Primary to Secondary Leakage N/A 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months N/A Monitoring inoperable (sustained for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

5) Leak rate> 60 gpd < 100 gpd with both methods Continuous Primary to Secondary Leakage Monitoring inoperable N/A 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months N/A (leak rate unstable or increasing when Continuous Primary to Secondary Leakage Monitoring became inoperable)

THIS PAGE INTENTIONALLY BLANK.

Enclosure 5.2 AP/l!AlI700/031 Reduction of Secondary Leakage and Page 1 of9 Cross-Unit Contamination ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Steps 1 - 12 may be perfonned in any order.

1. _ Verify AS header being supplied by _ Initiate EnclS.33 (Swapping Aux Steam Unit 2 or 3. Header to Another Unit) of the Unit I EOP.

2. Perfonn the following (T-3/M-22):

A. _ Open LPSW-769 (AHU Cond Drain to Yard Drains).

B. Close LPSW-768 (AHU COND DRAIN TO TB SUMP).

3. Close IHPE-34 CC' BLEED TO PLANT HEATING BLOCK)

(T-3, N ofF-IS, 20' up)

4. _ Close I C-168 (UNIT I UST RISER TO AUXBOILER)

(T-I, I' S ofD-24, I6'up).

___________. - - - - - - - - - - j e - - - - - - - - - - - - - - - - - - - - -_ _

5. Perfonn the following:

A. Open one of the following from an unaffected unit to transfer Radwaste Bldg Desuperheater Condensate supply:

_ 2C-3S7 (UNIT 2 CBP TO AS DESUPERHEATER BLOCK)

(T-I, 2' NE ofH-36, 20' up) 3C-357 (UNIT 3 CBP TO AS DESUPERHEATER BLOCK)

(T-I, 8' S ofG-46, 20' up)

B. _Close C-365 (AS DESUPERHEATER CONDo SUPPLY TIE)

(T-I, 5' S ofH-28, 20' up).

6. Close lC-21O (CBP DISCHARGE TO MISe. DE SUPERHEATERS)

(T-I, NE ofH-23, 20' up).

_ _.----'1 _ _ _ _ _ _- - - - - - - - - - - - - - - - -

Enclosure 5.2 AP/IIAl1700/031 Reduction of Secondary Leakage and Page 2 of9 Cross-Unit Contamination THIS PAGE INTENTIONALLY BLANK

Enclosure 5.2 AP/I/A/1700/031 Reduction of Secondary Leakage and Page 3 of9 Cross-Unit Contamination ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

7. Ensure valves connecting Unit 112 and Unit 3 TB trenches are closed:

_ CCW-503 (UNITS 1/2/3 TB SUMP TRENCH X-CONN) (T-IID-38)

_ CCW-504 (UNITS 112/3 TB SUMP TRENCH X-CONN) (T-1I1-40)

_ CCW-505 (UNITS 1/2/3 TB SUMP TRENCH X-CONN) (T-IIK-40)

8. Ensure the following are closed:

_ lC-135 (CONDENSATE CROSSOVER BLOCK)

(T-IID-27, 12' up)

_ IFDW-313 (IA EFDW LINE DISCH TO lA S/G X-CONN)

(T-l, N ofM-16, 20' up)

_ IFDW-314 (IB EFDW LINE DISCH TO 1B S/G X-CONN) (T-1, S ofM-24)

_ 1FDW-97 (lA EFDW LINE CROSS TIE) (T-1, 15' E ofC-19, 40' up) 1FDW-98 (IB EFDW LINE CROSS TIE) (T-1, 15' E ofC-20, 40' up)

9. _ Direct leakage of contaminated secondary water to TB trenches by placing funnels, buckets, etc. under leaking components.

10. _ Stop all non-essential secondary system draining.

Enclosure 5.2 AP/I/A/17001031 Reduction of Secondary Leakage and Page 4 of9 Cross-Unit Contamination THIS PAGE INTENTIONALLY BLANK

Enclosure 5.2 AP/I/A/1700/031 Reduction of Secondary Leakage and Page 5 of9 Cross-Unit Contamination ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Throttling cooling water to continuous vacuum priming pumps should be performed slowly and the pumps checked every 112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months until temperature stabilizes.

11. Throttle the following until the Continuous Vacuum Priming pumps are warm to the touch:

_ lLPSW-285 (lA CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-lIC-19)

_ lLPSW-291 (lB CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-lIC-I9)

_ 2LPSW-285 (C CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-lIC-36)

_ 2LPSW-291 (D CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-lIC-36)

12. _ Issue a work request to install a bladder in Unit 112 Powdex Sump to isolate Powdex overflow to TBS.

13. White tag closed the following:

_ IC-I68 (UNIT 1 UST RlSER TO AUX BOILER) (T-l, l' S ofD-24, 16' up)

_ lC-21O (CBP DISCHARGE TO MISC.

DESUPERHEATERS)

(T-l, NE ofH-23, 20' up)

_ C-365 (AS DE SUPERHEATER CONDo SUPPLY TIE)

(T-l, 5' S ofH-28, 20' up)

Enclosure 5.2 APIl/Al1700/031 Reduction of Secondary Leakage and Page 6 of9 Cross-Unit Contamination THIS PAGE INTENTIONALLY BLANK

Enclosure 5.2 AP/l/A/1700/031 Reduction of Secondary Leakage and Page 7 of9 Cross-Unit Contamination ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

14. _ WHEN tube leak is stopped, AND recovery from conditions created by this enclosure are desired, THEN continue this enclosure.

NOTE Steps 15 - 19 may be performed in any order.

15. _ Initiate a work request to clean TBS.

16. _ Notify SPOC to remove bladder from Unit 112 Powdex Sump.

17. Perfonn the following (T-3/M-22):

A. _ Close LPSW-769 (AHU Cond Drain to Yard Drains).

B. _ Open LPSW-768 (AHU COND DRAIN TO TB SUMP).

18. Open the following:

lLPSW-285 (IA CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-1IC-19)

_ lLPSW-291 (IB CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-IIC-19) 2LPSW -285 (C CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-IIC-36) 2LPSW-291 (D CONTINUOUS VACUUM PRIMING PUMP SOLENOID OUTLET) (T-IIC-36)

-'~--------------'--'------------'-------'--'-----'--'-,-_.----_._--_._---.-- ' - - - _..__ ._--_._-_.. __ .-_. __._-----_._.._----,-_._--_._.------

Enclosure 5.2 AP/I/AJ1700/031 Reduction of Secondary Leakage and Page 8 of9 Cross-Unit Contamination THIS PAGE INTENTIONALLY BLANK

Enclosure 5.2 APil/NI700/03I Reduction of Secondary Leakage and Page 9 of9 Cross-Unit Contamination ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

19. Remove white tags from the following:

IC-I68 (UNIT I UST RISER TO AUX BOILER) (T-I, I' S ofD-24, 16' up)

IC-210 (CBP DISCHARGE TO MISe.

DESUPERHEATERS)

(T-I, NE ofH-23, 20' up)

C-365 (AS DE SUPERHEATER COND. SUPPLY TIE)

(T-I, 5' S ofH-28, 20' up)

20. WHEN directed by CR SRO, THEN EXIT this enclosure.

THIS PAGE INTENTIONALLY BLANK Enclosure 5.3 AP/l/A/1700/031 Local SG Isolation Page I of3 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. _ VerifY isolation of IA SG desired. _ GO TO Step 3.

2. Ensure the following are closed:

_ IFDW-127 (lA NORMAL FDW HDR DRAIN ISOLA nON)

(T-3, 12' NE ofM-22, on floor below J leg)

_ ISD-25 (lAMS HDR TURBINE BYPASS STEAM TRAP INLET)

(T-3/M-18, 9' up)

ISD-28 (lA MS TURBINE BYPASS LINE DRAIN BLOCK)

(T-3/M-18, 7' up)

_ ISD-359 (MS TO S/U HDR STEAM TRAP INLET) (T-3, LlM-17, 16' up)

ISD-366 (MS TO S/U HDR STEAM DRAIN TO TRENCH BLOCK)

(T-3/L-17, 6' up)

_ ISD-1 (lAMS LINE DRAIN TRAP INLET) (T-3/F-13/14, 15' up)

_ ISD-7 (lA MS LINE DRAIN TO TRENCH BLOCK) (T-3/F-14, 6' up)

IMS-I90 (lMS-79 BYP)

(T-3, F-13/G-13, 40' up)

3. VerifY isolation of IB SG desired. _ GO TO Step 5.

Enclosure 5.3 AP/I/A/17001031 LocarSG Isolation Page 2 of3 THIS PAGE INTENTIONALLY BLANK

Enclosure 5.3 AP/I/A/1700/031 Local SG Isolation Page 3 of3 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

4. Ensure the following are closed:

1FDW-216 (lB NORMALFDW HDR DRAIN BLOCK)

(T-3, 10' NE ofM-23, on floor below J leg)

_ lSD-322 (lB MS TURBINE BYPASS STEAM TRAP INLET)

(T-3, N ofM-17N, 8' up) lSD-324 (lA TURBINE BYPASS STEAM LINE DRAIN BLOCK)

(T-3, N ofM-17, 6' up)

_ ISD-9 (lB MS LINE DRAIN TO TRAP BLOCK) (T-3/F-14, S' up)

_ lSD-4 (IB MS LINE DRAIN TRAP INLET) (T-3, E-13IF-13, IS' up)

_ 1MS-189 (lMS-76 BYP) (T-3/D-13, 40' up)

S. EXIT this enclosure.

THIS PAGE INTENTIONALLY BLANK Enclosure 5.4 AP/11Al17001031 Calculation of Primary to Secondary Leak Page 1 of 1 Rate using CSAE Off-gas and RCS Samples ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Primary to secondary leak rates < 1.0 gpd CANNOT be accurately quantified, but they should be recorded for trending purposes. {14}

1. _ Obtain Total Xe 133 equivalent activity 1. _ IF NO detectable activity, from RP CSAE off-gas sample. THEN log leak rate = 0 gpd.

_ _ _ _ _ _ _ _(j.lCi/ml) 2. _ GO TO Step 4.

2. _ Obtain RCS Xe 133 equivalent corrected from Primary Chemistry RCS sample.

_ _ _ _ _ _ _ _(j.lCi/ml)

3. _ Determine primary to secondary leak rate from the following formula: {20}

_ _-=C=.:SA:....:E=-=.o::..:ff...;;-gc as=-T-=-o=.:t-=-X::..:e-=1c::..3=..3-=-eq:J...>L(j.l'-.::C:.:..i/~m=<I),--_ X 10800 (gal)(min)

Leak rate = 100 ft3/min X RCS Xe 133 eq corr (j.lCi/ml) (ft3)(day)

_ ___ JO_0_tl_t3_ X _ _ _ _ _ _-'f1:.:. :C:..i/ .:c.::.:m=lc""'s""AE"-- X 10800(gal)(min)

Leak rate = gpd min j.lCi/mlRcs (ft3)(day)

.**--0-*****----***-****---*****-**-*-*******--*-**--*----...--.----.--..-****--*-.-.*-**--*-..**----------0--*-----*1*********************-******-*------*----*.0.-....-.-*-0--.----..***-- ..... _-....-.-.....-...- -.........--...-.-...-._..--..--.-..- -

4. EXIT this enclosure. _

THIS PAGE lNTENTlONALLY BLANK Enclosure 5.5 1 API lA/I 700103 I Calculation of Primary to Secondary Leak Page 1 of 1 Rate using lRlA-40 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

1. _ Obtain RCS Xe 133 equivalent corrected from latest available Primary Chemistry RCS sample.

_ _ _ _ _ _ _ _(!..tCi/ml)

NOTE The maximum indicated IR1A-40 count rate (the peak of any spikes) should be used to calculate leak rate. {l5}

2. Obtain IR1A-40 cOlmts from the _ Obtain lRIA-40 counts from OAC point Control Room RIA View Node. (I VB2) 0lE3020 (IRIA-40 CSAE

_ _ _ _ _ _ _ _ cpm EXHAUST). {l6}

cpm

3. Determine primary to secondary leak rate from the following formulas: {20}

_ _ _ _ _I_RI_A_-4_0_('--'c.....

p m--')'---_ _ _ X 3.67E-4 (gal)(min)( gCi/ml)

Leak rate = 100 ft 3/min X RCS Xe 133 eq corr (J..tCilml) (~)(day)(cpm)

Leak rate = . __ IO_O_fi_f_ X _ _ _ _-----'cp_m_ X 3.67E-4 (gal)(min)( gCi/ml) min ~Ci/ml (ft3)(day)(cpm) gpd

**---**--*----*----*---***--*---------r--**-----------------.--

4. EXIT this enclosure.

THIS PAGE INTENTIONALLY BLANK Enclosure 5.6 AP!l/A/1700/031 Deleted Page 1 of 1 THIS PAGE INTENTIONALLY BLANK

THIS PAGE INTENTIONALLY BLANK r')

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THIS PAGE INTENTIONALLY BLANK Enclosure 5.8 AP/l/A/1700/031 Resetting lRIA-40 and OAC Setpoints Page 1 of 3 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE RCS Xe 133 equivalent corrected is required for this calculation.

l. _ Obtain RCS Xe 133 equivalent corrected from latest available Primary Chemistry RCS sample.

_ _ _ _ _ _ _ _(/lCi/ml)

2. Determine IRIA-40 High setpoint from the following formulas: {20}

High RCS Xe 133 eq corr (/lCi/ml) 2.7IE+3 (ft3)(day)(cpm)

Leakrate IRIA-40 High Setpoint (cpm)= X 100 fe/min X (gal)(min)(/lCi/ml)

Value (gpd) 1RIA-40 High Setpoint _ _ _ _-----L/l_C_i/m_1 X 2.7IE+3 (ft3)(day)(cpm)

_ _gpd X cpm (cpm)= 100 fe/min (gal)(min)(/lCi/ml)

3. Determine IRIA-40 Alert setpoint from the following formulas: {20}

Alert RCS Xe 133 eq corr (/lCi/ml) 2.7IE+3 (fe)(day)(cpm)

Leakrate IRIA-40 Alert Setpoint (cpm)= X (gal)(min)(/lCi/ml)

Value (gpd)

IRIA-40 Alert Setpoint _ _ _ _-----L/l_C_i/m_1 X 2.71E+3 (ft3)(day)(cpm)

_ _gpd X cpm (cpm)= 100 fe/min (gaI)( min )(/lCi/ml)

4. _ Enter the new I RIA -40 Alert and High Setpoints in the RIA View Node.

Enclosure 5.8 AP/I/A/1700/031 Resetting lRIA-40 and OAC Setpoints Page 2 of3 THIS PAGE INTENTIONALLY BLANK

Enclosure 5.8 AP/I/Al1700/031 Resetting lRIA-40 and OAC Setpoints Page 3 of3 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

5. Enter the new OAC TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT by perfonning the following:

A. Enter MVU.

B. Select PRI-LEAK PRIMARY TO SECONDARY LEAKAGE MANUAL INPUTS.

C. Select UPDATE.

D. _ SelectOlK1430(TOTALPRITO SEC LEAKRATE ADMIN LIMIT).

E. Enter the new TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT.

F. _ Enter your LAN identification and reason for change.

G. Select SAVE.

6. EXIT this enclosure.

THIS PAGE INTENTIONALLY BLANK Appendix AP/IIA11700/031 Page 10f3

1. PIP 00-3614 CA #2. The Turbine Building sump pump breakers shall be opened as quickly as possible. The white tags can be created and hung later when time permits.

2. PIP 00-0760 CA #24. NSD 513.4.1.3, 513.4.1.4, 513.4.1.5 (Rev 4). These NSD sections require that the leaking Steam Generator is identified when leakage greater than 5 gpd exists.

3. PIP 00-0760 CA #37. NSD 513.4.6 (Rev 4). This NSD section requires that operational decisions be made based on the RIA-40 reading unless RIA-40 is out of service.

4. PIP 00-0760 CA #25. NSD 513.4.1.3, 513.4.7 (Rev 4). These NSD sections require that Operator awareness of the off-gas and main steam line monitors is increased when the primary to secondary leak rate is greater than 5 gpd.

5. PIP 00-0760 CA #23. NSD 513.4.1.3, 513.4.1.4 (Rev 4). These NSD sections require that the frequency of off-gas monitor sampling be increased when primary to secondary leakage exceeds 5 gpd.

6. PIP 00-0760 CA #15. NSD 513.4.1.1, 513.4.7 (Rev 4). These NSD sections require that Steam Generator tube leak rates be calculated at a certain frequency when there is no available Continuous Radiation Monitor..

7. PIP 00-0760 CA #22. NSD 513.4.1.3, 513.4.1.4 (Rev 4). These NSD sections require that RIA-40 setpoints be adjusted when primary to secondary leak rate conditions change.

8. PIP 00-0760 CA #26. NSD 513.4.1.3, (Rev 4). These NSD sections require that plant management be notified of the leak rate status and trends when the primary to secondary leak rate exceeds 5 gpd.

9. PIP 00-0760 CA #27. NSD 513.4.1.3, 513.4.7 (Rev 4). These NSD sections require that Operator awareness of the off-gas and main steam line monitors is increased when the primary to secondary leak rate exceeds 30 gpd.

10. PIP 00-0760 CA #28. NSD 513.4.1.4 (Rev 4). This NSD section requires that action be taken to minimize the spread of secondary contamination when leakage in excess of 30 gpd exists.

11. PIP 00-0760 CA #29. NSD 513.4.1.4 (Rev 4). This NSD section requires that Operators initiate preparations for response to a possible Action Level 2 leak rate when the primary to secondary leak rate exceeds 30 gpd.

12. PIP 00-0760 CA #32. NSD 513.4.1.5 (Rev 4). This NSD section requires that the affected Steam Generator is isolated to minimize contamination of the secondary systems.

13. PIP 00-0760 CA #30. NSD 513.4.1.5 (Rev 4). This NSD section requires that a shut down to Mode 3 be performed within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months when primary to secondary leakage exceeds 100 gpd in any steam generator.

14. PIP 00-3726 CA #2. This PIP tracked changes as a result of Rev 1 to NSD-513. In addition, the PIP specifically mentioned "detection limits". The note stating" .. .leak rates < 1.0 gpd cannot be accurately quantified ... " was added.

15. PIP 00-0760 CA #35. NSD 513.4.2 (Rev 4). This NSD section requires that the leak rate be classified using the peak value of any spikes.

16. PIP 02-1678 CA #5. Added specific OAC point to prevent selecting OAC point that is non-conservative.

Appendix AP/I/A/1700/031 Page 2 of3 THIS PAGE INTENTIONALLY BLANK

Appendix AP!l/A/1700/031 Page 3 on

17. SLC 16.11.3 Radioactive Effluent Monitoring Instrumentation

18. PIP 04-0034 (Difficulty in detennining CSAE offgas flow when meters off scale high) 19.36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months time limit is from T.S. 3.4.13.

20. PIP 0-07-05869: The L1Ps observed during testing for each Unit's CSAE Blower were too high (> 58.2 inches of H20) to detennine flow rates using vendor perfonnance curves or the curve in OP/O/AlII 081001 (Curves And General Infonnation), Enclosure "CSAE Blower Head Curve". The M observed implies that all three Units' CSAE Blowers are operating at very low flows. Therefore, the total off gas flow for any Unit is conservatively bounded at 100 SCFM based on the CSAE Blower L1P test data. "100 SCFM" will be used in place of measured CSAE off gas flow.

THIS PAGE INTENTIONALLY BLANK Primary to Secondary Leakage AP/l!Al1700/031 Carryover Steps Page 1 of2 IF AT ANY TIME:

(4.1) primary to secondary leak rate is ~ 25 gpm ... (GO TO Unit 1 EOP)

(4.2) lRlA-54 in High alarm or inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates ~ 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.33) primary to secondary leak rate increases to ~ 30 gpd ... (GO TO guidance to increase monitoring)

(4.40) CSAE off-gas sample and RCS sample results become available ... (calculate and record primary to secondary leak rate)

(4.46) lRlA-40 is operable ... (reset OAC and lRlA-40 setpoints and record new setpoints)

(4.49) CSAE off-gas sample indicates primary to secondary leak rate < 5 gpd ... (request second sample)

(4.53) both Continuous Primary to Secondary Leakage Monitoring methods inoperable AND primary to secondary leak rate> 60 gpd AND leak unstable/increasing at time both Continuous Primary Secondary Leakage Monitoring methods became inoperable ...

(GO TO shutdown guidance)

(4.54) primary to secondary leak rate increases to ~ 75 gpd for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR ~ 100 gpd ...

(GO TO shutdown guidance)

(4.57) leak rate is stable (~ 10% change in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time period) ... (reduce monitoring frequency of RlAs to every two hours)

(4.61) OSM desires ... (initiate Enc15.2 to reduce secondary leakage and cross-unit contamination)

(4.63) CSAE off-gas and RCS sample results become available ... (calculate and record primary to secondary leak rate)

(4.68) lRlA-40 is operable AND primary to secondary leak rate is unstable ... (set OAC and lRlA-40 setpoints to 75 gpd)

Primary to Secondary Leakage 1 API I All 700/03 1 Carryover Steps Page 2 of2 (4.70) lRlA-40 is operable AND primary to secondary leak rate is stable ... (set OAC and lRlA-40 setpoints to 75 gpd and 30 gpd above current reading)

(4.72) primary to secondary leak rate is unstable ... (THEN GO TO applicable step)

(4.74) primary to secondary leak rate is stable ... (THEN GO TO applicable step)

(4.89) primary to secondary leakage increases ... (modify shutdown as required by End 5.1)

(4.92) primary to secondary leak rate < 100 gpd (0.0694 gpm) AND lRlA-40 inoperable AND Rx Power::; 40 % ... (sample CSAE off-gas and RCS every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) .

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