ML040200674

April 2003-301 Exam Draft JPMs

ML040200674
Person / Time
Site:	Catawba
Issue date:	05/15/2003
From:	Ernstes M Operator Licensing and Human Performance Branch
To:	Gordon Peterson Duke Energy Corp
References
50-413/03-301, 50-414/03-301 50-413/03-301, 50-414/03-301
Download: ML040200674 (406)

Text

Draft Submittal (Pink Paper)

CAPAWBA EXAM 2003-301 50-413 & 50-414 CH 31 -APRIL 4 &

APFUL. I O , 2003 A

I Page 1 of 8 CATAWBA INlTlAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM ISWADMIN Perform a Manual Shutdown Margin Calculation (Unit at Power)

CANBIBATE EXAMINER

Page 2 of 8 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

&& Perform a manual shutdown margin calculation (Unit at Power)

Alternate Path:

NIA Facilitv JPM #:

OP-CN-RT-RB-121 (Modified)

KIA Ratinufs):

2.1.25 (2.8/3.1)

Task Standard:

Determine that adequate shutdown margin exists per Technical Specifications.

Preferred Evaluation Location: Preferred Evaluation Method:

SimulatorJ In-Plant Perform Simulate ~

Refe?eRlXS:

OQ/O/N6100/006 Reactivity Balance Calculation Enclosure 4.3 Revision 64 ROD Rook Section 5 Candidate: Time Start :

NAME Time Finish:

Performance Ratina: SAT -UNSAT -Performance Time ___

COMMENTS

Page 3 of 8 ToolslEsuivmenffProcedu~~s Needed:

QQ/O/A/6100/806Reactivity Balance Calculation Enclosure 4.3 ROD Book Section 5 READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. A11 control room steps shall be performed for this JPM. including any required communications. Iwill 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:

You are the Unit 1 Balance of Plant operator. You have just been informed by the Control Room SRO that the following rods are determined to be untrippable:

8-4 C-7 Current Plant Conditions:

iNlPlATlNG CUE:

Perform a Manual Shutdown Margin Calculation for these untrippable rods per OP/0/A/6100/006 (Reactivity Balance Calculation) and determine if adequate shutdown margin exists

Page 4 of 8 Start Time:

STEP 1: Performs Section 2.3 and NIB's Section 2.2.

STANDARD: Step 2.2 marked N/A. -SAT COMMENTS:

-UNSAT STEP 2: Record data required in step 2.3.

STANDARD: Operator determines the following using the initial conditions.:

Unit: 1 -SAT DateiPime: Present DatdTime Present Thermal Power, Best Estimate: 94.45%

Present Cycle Burnup. 277 EFPD -UNSAT Present Control Bank Position: 215 SWD, Control Bank D Number of untrippable RCCA(s): 8 4 and C7 COMMENTS:

STEP 3: Determine total available rod worth.

-SAT STANDARD: Determine total available rod worth to be 4879 pcm per section 5.7 of R.O.D. Manual.

-UNSBT COMMENTS STEP 4: Determine there are multiple untrippable WCCAs.

STANDARD: NIB steps 2.4.3and 2.4.4. -§AT COMMENTS:

-UNSAT

Page 5 of 8 STEP 5: Determine location of highest reactivity worth RCCA and its reactivity worth penaity..

-SAT STANDARD: Determines RCCA C7 Rod worth is 263 r)mper section 5.8 of the R.O.D. Manual.

-UNSAT COMMENTS:

STEP 6: Determine maximum stuck rod worth during cycle.

STANDARD: Determines maximum stuck rad worth during cycle is 970 pcrn per -SAT section 5.7 of the R.O.B. Manual.

COMMENTS: -UNSAT 3-w 7: Calculate total untrippable RCCA reactivity worth penalty.

STANDARD: Calculates a penalty: ([2-1] X 970pcm) + 263pcm = 1233 pcm -SAT COMMENTS:

-UNSAT I

STEP 8: Calculate inserted reactivity worth of rods.

STANDARD: Determines: -SAT Worth of Control Banks HFP, Eq Xenon IRW: 12-Worth of Shutdown Banks WFP Eq Xenon IRW:

-UNSAT inserted Worth of Present Position 12 m.

CQMMENTS:

I

Page 6 of 8 STEP 9: Calculate available reactivity worth of trippatale rods.

STANDARD: Determines:

Total available rod worth 4879 acm Untrippable RCCA penaltv 1233 pcm Inserted Rod Worth 12 pcm Available Worth of Trippable RCCB's: 3634 pcm COMMENTS:

STEP 'IO: Calculate total misaligned RCCA reactivity worth.

STANDARD: Determines:

Quantity of Misaligned Rods: Q pcm Maximum Dropped or Misaligned Rod Worth: 200 pcm Total Misaligned RCCA Worth: 0 pcm COMMENTS:

STEP 11: Calculate SBM for present conditions. CRITICAL STEP STANDARD: Determines:

Available Worth of trippatale RCAs: 3634 pcm Total Misalianed RCCA Worth: 0 pcm -SAT Total Bower Defect 1882 pcrn Transient Flux Redistribution Allowance: 34Q pcm Present SDM: 1 4 1 2 ~

COMMENTS:

Page 7 of 8 STEP 12: Ensure Present SDM equal to greater than 1300 PCM. CRITICAL STEP STANDARD: Determines present SDM is greater than 1300 pcm.

I TIME STOP:

Page 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Unit 1 Balance of Plant operator. You have just been informed by the Control Room SRO that the following rods are determined to be untrippable:

0 B-4

• c-7 Current Plant Conditions:

INITIATING CUE:

Perform a Manual Shutdown Margin Calculation for these untrippable rods per OP/O/N6100/006 (Reactivity Balance Calculation) and determine if adequate shutdown margin exists.

Enclkure 4.3 OWo/A/6I OO/O6 Shutdown Margin - Untrippable RCCA(S) - Pagc 1 of 4 Modes 1 & 2

1. Initial Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure 2.1 performing a MANUAL calculation, N/A Step 2.2.

% 2.2 Perform the following steps if using the REACT program to somplcte the calculation:

2.2.1 Access Reactivity Baiance Program per Enclosure 4.4.

2.2.2 Select View then Reactivity Balance Calculations on toolbar.

2.2.3 Select SDM - Mode E or 2 tab in Reactivity Balance Calculations window.

NOTE: 1. Sign must be provided with Difference from Equilibrium Samarium [i.e., ( -pcm].

2. Quantity of Misaligned Rods refers to rods that are misaligned but remain OPERABLE (trippable). Only the total number of rods is required.

I i

3. Input inoperable (untrippable) con(ro1 rods by clicking Seiect Inoperable Rods and input any inserted shutdown banks using Shutdown Banks Inserted tab.

2.2.4 Enter appropriate values as pronipted 2.2.5 Click Calculate, print program results, label appropriately, and attach to this enclosure.

2.2.6 Ensure EEective Shutdown Margin for Prescnt Position is greater than Required Shutdown Margin.

2.2.7 Ensure that a separate, independent calculation has been performed per steps 2.2.1 though 2.2.6.

2.2.8 Verify that both attachments to this enclosure yield the same results.

2.2.9 N/A the rest of this enclosure (steps 2.3 through 2.7).

Performed By: Date/Time: /

Verified By: l)ate/Tinie: /

EnCloSUre 4.3 OPi&AI6 1O0/06 Shutdown Margin - Untrippable RCCA(S) - Page 2 of 4 Modes 1 & 2 NOTE: I. In Modes 1 or 2 with all RCCAs trippablc, shutdown margin is satisfied provided control banks are positioned above the Control Rod Insertion limits in Section 2.2 of the K.O.D. manual.

2. Asstunc all values are positive uniess otherwise indicated by parentheses.

parenthescs precede the value [Le. ( j pcm], record the sign provided with data. The caiculations account for these sign conventions.

2.3 2.4 Determine available reactivity worth of trippablc RCCAs for present conditions:

2.4.1 Determine Total Available Rod Worth (Section 5.7 of R.Q.D. manual)

-fzz.zLPcm 2.4.2 -

IF there are multiple untrippable RCCAs, N/A steps 2.4.3 and 2.4.4 vb2.4.3 Detenninc reactivity worth penalty for untrippable pcm RCCA core location of Step 2.3.9 (Section 5.8 of R.O.D. manual).

Nh2.4.4 N!A steps 2.4.5 through 2.4.8 2.4.5 Determine untrippable RCCA of Step 2.3.9 Corc Location C 7 with the highest reactivity worth penalty(Section 5.8 of ROD Manual).

2.4.6 Rccorci reactivity worth ofthe untrippabie RCCA of dd 3 pim Step 2.4.5 (Section 5.8 of ROD Manual).

Enclosure 4.3 OW0!A!6 100/06 Shutdown Margin - Untrippable RCCA(S) - Page 3 of 4 Modes 1 & 2 2.4.7 Determine maximum stuck rod worth during cycle q4s Pcm (Section 5.4 ofthe R.O.D. manual).

2.4.8 Calculate total untrippable RCCA reactivity worth penalty below:

2.4.9 Record Total Untrippable RCCA Penalty ,4233 pcm from Step 2.4.3 or Step 2.4.8, whichever is applicable.

2.4.10 current son&ol b a n k p p B. HFP. Eq Xenon IRW for I Step 2.3.6 current shutdown bank positions 2.4.11

Enclosure 4.3 OPIO:A/6100/06 Shutdown Margin Untrippable RCCA(S) -

~ Page 4 of 4 Modes 1 & 2 2.4.12 Calculate total misaiigned RCCA reactivity worth below:

~

NOTE: Interpolation of Power Defect is not required for step 2.5. Bounding bumups and power levels may be used to select the highest Power Defect from section 5.9 of the R.O.D.

manual.

2.5 Calculate SDM for present conditions:

3. Total misaligned RCCA Worth D. Transient Flux Redistribution Section 5.7 of 2.6 Ensure Present SDM is 2 1300 pcm. (TS 3.1.1 via COLR)

I NOTE: Separate, independent calculation mnst he perfomied by the verifier.

~~

I i

2.7 Sign the appropriate space below. N/A the unsigned space.

Performed By: DateiTime: I Verified By: Date/Time: /

Catawba Nuclear §tation Reactivity Balance Calculation t--

OP~/A/6100/006 Revision No.

064 CN0092MR TROLLED FOR PRINT **********

(ISSUED) - PDF Format I

OP/~iN6100/06 Page 2 of 3 Reactivity Balance Calculation

1. PMrpOSe 1.1 To estimate critical NC System boron concentration before criticality based on other assumed core reactivity conditions.

1.2 To estimate critical control hank position before criticality based on other assunid core reactivity conditions.

1.3 To calculate shutdown margin in Modes 1 and 2 with UNTRIPPABLE RCCA5 (ITS 3.1.4) 1.4 Tocalculate the NC System boron concentration at which shutdown margin will NOT he met in Modes 2 (with K-eff < IB), 3,4, and 5. (ITS 3.1.1) i .5 To verify K-eff < 0.99 with shutdown barks withdrawn.

I .6 To calculate the NC System boron concentration at which refueling boron concentration will NOT be met in Mode 6. (ITS 3.9.1)

2. Limits and Precautions NOTE: All curvesitabies used in this procedure are found in Unit One (Two) Reactor Operating Data (R.O.D.) manual.

2.1 Ensure all data used by this procedure are for the correct unit.

2.2 NC System T-AVG should be maintained within *I F of T-REF in Modes 1 and 2 to reduce uncertainties in calculations.

2.3 Shutdown margin (SDM) shall be 21000 pcm in Mode 5 . (Tech Spec 3.1.1 and Enciosure 4.4) 2.4 SDM shall be t i 3 0 0 pcm in Modes 1,2, 3, and 4. (Tech Spec 3.1.1 and Enclosure 4.3, or 4.4) 2.5 Required refueling boron concentration is obtained from Trch Spec 3.9.1 and Enclosure 4.6.

2.6 -

IF T-AVG <500 OF, credit for only 50% of xenon worth can be taken for verifying SDM.

2.4 NC System boron concentration shall he > required boron concentration for SDM at a new NC System T-AVG before beginning NC System T-AVG changes in Modes 3,4, and 5.

OP/o/A/6IO0/06 Page 3 o f 3 2.8 Criticality shall NOT be obtained outside the maximum window (lt750 pcm) of estimated critical control bank position.

2.9 Desired critical control bank position shali be below the controi bank insertion limits above any temporary control bank withdrawal limits.

2.10 Verification of K-eff < 0.99 with shutdown banks withdrawn shall only be performed above 200 OF.

2.11 REACT and manual calculations may NOT yicld equal results due to minor differences in methods (ie interpolation). Reactor Engineering should be contacted if questions arise.

3. Procedure 3.1 For eslimated critical NC System boron concentration (ECB), refer to Enclosure 4.1.

3.2 For estimated critical control bank position (ECP) refer to Enclosure 4.2.

4.3 For SDM calculation with untrippable RCCAs, refer to Enclosure 4.3.

3.4 For SDM verification in Modes 5,4,3, or 2 (with K-eff (c 1.01, (with or without xenon credit), refer to Enclosure 4.4.

3.5 For Verification of K-eff < 0.99 with shutdown banks withdrawn, refer to Enclosure 4.5.

3.6 For refueling boron concentration verification in Mode 6, refer to Enclosure 4.6.

3.7 For instructions on running REACT computer program, refer to Enclosure 4.4.

3.8 For Shutdown Fission Product Correction Factor, refer to Enclosure 4.8.

4. Enclosures 4.1 Estimated Critical Boron Concentration (ECB).

4.2 Estimated Critical Control Bank Position (ECP).

4.3 Shutdown Margin - Modes 1 ,and 2 - Untrippable RCCA(s).

4.4 Shutdown Margin - (With or Without Xenon Credit).

4.5 Verification of K-eff < 0.99 with Shutdown Banks Withdrawn 4.6 Shutdown Boron Concentration - Mode 6.

4.7 REACT Computer Program Directions.

4.8 Shutdown Fission Product Correction Factor

Enclosure 4.1 OPl~/A/61OO/06 Estimated Critical Boron Concentration (ECB) Page 1 of 1

1. lnitial Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure NOTE: 1. Assume all values are positive unless otherwise indicated by parentheses.

parentheses precede the value [Le.( ) d c m ] , enter the sign provided with data. The calculations account for these sign conventions.

2. All ECB calculations must be performed independently by a Qualified Reactor Engineer and a Licensed Operator.

2.1 cycle burnup is > 12 EFPD, perform Enclosure 4.8 to determine Shutdown Fission Product Correction Factor.

Shutdown Fission Product Correction Factor PPm 2.2 Access Reactivity Balance Program per Enclosure 4.7.

2.3 Select View then Reactivity Balance Calculations on toolbar.

2.4 Select ECB (Estimated Critical Boron Concentration) tab in Reactivity Balance Calculations window.

NOTE: 1, Sign must be provided with Difference from Equilibrium Samarium [i.e., ( ) __ pcm].

2.5 Enter appropriate values as prompted.

2.6 Enter a desired critical rod position at least 1000 pcm above HZP Rod Insertion Limit (Section 2.2 of ROD Manual).

2.7 Click Calculate, print program results, label appropriately, and attach to this enclosure.

2.8 Ensure that separate, independent calculation has been performed per steps 2.1 through 2.7.

2.9 Verify that both attachments to this enclosure yield the same result.

Licensed Operator: DateITime: I Reactor Engineer: DateiTime: I

Enclosure 4.2 QPIo/AJ6100106 Estimated Critical Control Bank Position (ECP) Page 1 of 1 I. Initial Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure NOTE: 1. Assume all values are positive unless otherwise indicated by parentheses.

parentheses precede the value [Le.( ) p m ] , enter the sign provided with data. The Calculations account for these sign conventions.

2. All ECP calculations must be performed independently by a Quaiified Reactor Engineer and a Licensed Operator.

2.1 cycle bumup is > 12 EPPD, perform Enclosure 4.8 to detemiine Shutdown Fission Product Correction Factor.

Shutdown Fission Product Corrrection Factor PPm 2.2 Access Reactivity Balance Program per Enclosure 4.7.

2.3 Select View then Reactivity Balance Calculations on toolbar.

2.4 Select ECP (Estimated Critical Control Bank Position) tab in Reactivity Balance Calculations window.

I NOTE: 1. Sign must be provided with Difference rom Equilibrium Samarium [Le., ( ) -pcm].

1 2.5 Enter appropriate values as prompted.

2.6 Click Calculate and verify that Rod Ensertion Limits and (if applicable) Rod Withdrawal Limits will NOT be violated based on ECP results.

2.7 Print program results, label appropriately, and attach to this enclosure.

2.8 Ensure that separate, independent calculation has been performed per steps 2.1 through 2.7.

2.9 Verify that both attachments to this enclosure yield the same results.

Licensed Operator: DatdTime: I-.--

Keactor Engincer: Datemime: -f

Enclosure 4.3 QPIOIAI61 OO/06 ShutdoFn Margin - Untrippable RCCA(S) - Page 1 of 4 Modes 1 & 2

1. Initial Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure 2.1 2 performing a MANUAL calculation, N/A Step 2.2.

2.2 Perform the following steps if using the REACT program to complete the calculation:

2.2.1 Access Rcactivity Balance Program per Enclosure 4.7.

2.2.2 Select View then Reactivity Balance Calculations on toolbar.

2.2.3 Select SDM - Mode 1 or 2 tab in Reactivity Balance Calculations window.

NOTE: 1. Sign must be provided with Difference from Equilibrium Samarium [i.e., ( ) -pcm].

I

2. Quantity of Misaligned Rods refers to rods that are misaligned but remain OPERABLE (trippable). Only the total number of rods is required.

I I 3. Input inoperable (untrippable) control rods by clicking Select Inoperable Rods and input any inserted shutdown banks using Shutdown Banks Inserted tab. i 2.2.4 Enter appropriate values as prompted.

2.2.5 Click Calculate, print program results, label appropriately, and attach to this enclosure.

2.2.6 Ensure Effective Shutdown Margin for Present Position is greater than Required Shutdown Margin.

2.2.7 Ensure that a separate, independent calculation has been performed per steps 2.2.1 through 2.2.6.

2.2.8 Verify that both attachments to this enclosure yield the same results.

2.2.9 NIA the rest of this enclosure (steps 2.3 through 2.7).

Performed By: Datemime: I Verified By: Datemime: i

Enclosure 4.3 OP/o/N61OOf06 Shutdown Margin Untrippabie RCCA(S) -

~ Page 2 of 4 Mndes 1 & 2 NOTE: I. In Modes I or 2 with all RCCAs trippahie, shutdown margin is satisfied provided control banks are positioned above the Control Rod insertion limits in Section 2.2 of the R.O.D. manual.

2. Assume all values are positive unless otherwise indicated by parentheses.

parentheses precede the value [i.e. ( ) pcm], record the sign provided with data. The calculations account for these sign conventions.

2.3 2.4 Determine available reactivity worth of trippable RCCAs for present conditions:

2.4.1 Determine Total Available Rod Worth (Section 5.7 of R.O.D. manual) 2.4.2 there are multiple untrippable RCCAs, N/A steps 2.4.3 and 2.4.4 2.4.3 Determine reactivity worth penalty for untrippable pcm RCCA core location of Step 2.3.9 (Section 5.8 of K.O.D. manual).

2.4.4 N/A steps 2.4.5 through 2.4.8.

2.43 Determine untrippable RCCA of Step 2.3.9 Core Location with the highest reactivity worth penalty(Section 5.8 of ROD Manual).

2.4.4 Record reactivity worth of the untrippable RCCA of pcrn Step 2.4.5 (Section 5.8 of ROD Manual).

Enclosure 4.3 0P/~iN6100~06 Shut wn Margin - Untrippr._.. R CA(S) - Page 3 of 4 Modes 1 & 2 2.4.7 Determine maximum stuck rod worth during cycle pcm (Section 5.7 of the R.Q.D. manual).

2.4.8 Calculate total untrippahle RCCA reactivity worth penalty below:

2.4.9 Record Total Untrippable RCCA Penalty pcm from Step 2.4.3 or Step 2.4.8, whichever is applicable.

with rod positions that bound the present rod position.

2.4.10 current shutdown bank positions 2.4.1 1

Enclosure 4.3 OP/~IAi610Oi06 Shutdown Margin Untrippable RCCA(S) -

~ Page 4 o f 4 Modes 1 & 2 2.4.12 Calculate total misaligned RCCA reactivity worth below:

NOTE: Interpolation of Power Defect is not required for step 2.5. Bounding bumups and power levels may be used to select the highest Power Defect from section 5.9 of the R.O.D.

manual.

I CAUTION: SDM shall be within the limits specified by the COLR per Tech Spec 3.1.1. I 2.5 Calculate SDM for present conditions:

2.6 Ensure Present SDM is 2 I300 pcm. (TS 3.1.1 via COLR) I I NOTE: Separate, independent calculation must be performed by the verifier. I 2.7 Sign the appropriate space below. N/A the unsigned space.

Performed By: DateKime: I Verified By: Date/Time: I

Enclosure 4.4 OPI~IN61001O6 Shutdown Margin (With or Without Xenon Credit) Page 1 of 6

1. Initial Conditions I. 1 Limits and Precautions have been reviewed.

2. Procedure 2.1 E performing a MANUAL calculation, N/A Step 2.2.

2.2 Perform the following steps if using the REACT program to complete the calculation:

2.2.1 Access Reactivity Balance Program per Enclosure 4.7.

2.2.2 Select View then Reactivity Balance Calculations on toolbar.

I NOTE:

~ ~ ~

SDM -Mode 5,4,OK 3 option also applies to Mode 2 with K-eff -z 1.O.

2.2.3 Select SDM - Mode 5,4,or 3 tab in Reactivity Balance Calculations window.

NOTE: 1. Sign must be provided with Difference from Equilibrium Samarium @e., ( 1 pcm].

2. In REACT, Inoperable RCCAs refers to untrippable RCCAs.

3. Rod locations are put in REACT in a text only format ( e . g B12 or 3-12). REACT uses the maximum stuck rod worth for ail known untrippabls RCCAs.

2.2.4 Enter appropriate valuss as prompted.

2.2.5 Click Calculate, print program results, label appropriately, and attach to this enclosure.

2.2.6 Compare required boron concentration to present boron concentration.

2.2.7 Xenon Credit was selected AND a potential boron deficit is indicated in the calculation results, complete the following steps:

A. Record Adjusted SDM Deficit from Reacivity Balance Calculation output: pcm B. Select View then XenorVSamarium Calculations on toolbar.

C. Select Xenon for Isotope and Transient Prediction for Caiculation Type.

Enclosure 4.4 OPIolh~610OlO6 Shutdown Margin (With or Without Xenon Credit) Page 2 of 6 D. Enter initial concentrations. These can be obtained from the OAC or Reactor Engineering. The OAC point ids for these concentrations arc C1(2)P0125 andC1(2)P0124.

E. Enter appropriate power history F. Print program results, label appropriately, and attach to this enclosure.

Adequate SDM exists when Xenon worth from Xenon predict calculation equals or exceeds adjusted SDM deficit recorded in step 2.2.7.A. I 2.2.8 Ensure that a separate, independent calculation has been performed per steps 2.2.1 through 2.2.7.

2.2.9 Verify that both attachments to this enclosure yield the same results.

2.2.10 N A the rest of this enclosure (steps 2.3 through 2.9).

Performed By: DateEiine: I Verified By: DateRime: I

Enclosure 4.4 OP/O/A/6 1OO/O6 Shutdown Margin (With or Without Xenon credit) Page 3 of 6 NOTE: Assume all values arc positive d e s s otherwise indicated by parentheses. parentheses

~.

2.3 precede the value [Le. ( ) pcm], record the sign provided with data. The calculations account for these sign conventions.

~~ -. i on is not required for step 2.4. Bounding temperatures and burnups may be uscd 2.4 Select the boron concentration for the T-AVGs between PPm the range of Step 2.3.4 and Step 2.3.5 at current cycle bumup (Step 2.3.6) in Section 5.11 ofthe R.O.D. manual. {PIP 0-C99-0318}

2.5 Calculate additional boron concentration penalties:

23.1 Calculate untrippable RCCA penalty:

Enclosure 4.4 OP/0/A/6 100/06 Shutdown Margin (With or Without Xenon Credit) Page 4 of 6 2.5.2 Enter Zero Power Physics Testing penalty; PPm 100 ppm if physics testing is not complete, otherwise, enter 0 ppm.

2.5.3 Calculate total additional boron concentration penalty:

2.6 CaIculate total required boron concentration for SDM:

2.7 Determine the Boron Difference between Required Boron Concentration for SDM and current NC System boron concentration.

Boron Difference NOTE: A negative boron difference in Step 2.7 implies that SDM is maintained for Xenon free conditions. A positive boron difference means that SDM is maintained using a Xenon credit and/or boration. {0-C99-03 1x1 2.4.1 Boron Difference (Step 2.7) is negative, N/A Step 2.8.

Enclosure 4.4 8P/o/N6100i06 Shutdown Margin (With or Without Xenon Credit) Page 5 of 6 2.8 Determine the Xenon Credit as follows:

NOTE: Interpolation is not required for step 2.8.1. Bounding NC System T-AVG and cycle hurnup may be used to select the highest Differential Boron Worth from Section 5.3 of R.0.D manual.

2.8.1 Determine the ARI, Differential Boron Worth at PcdPPm lower T-AVG of Step 2.3.4 or 2.3.5 cycle bumup of step 2.3.6 from Section 5.3 of the R.Q.D.

manual.

2.8.2 Calculate the reactivity worth of the boron difference:

2.8.3 Calculate the xenon worth that is required to ensure SDM at the present NC System boron.

A. T-AVG is 500 F, calculate the Xenon Worth as follows:

B. T-AVG is < 500 'F, calculate the Xenon Worth as follows:

2.8.4 Predict Xenon for approximately two days into the future using O K Xenon Predict Program or REACT program (per Enclosure 4.4) and data from 2.3.1 through 2.3.10.

Enclosure 4.4 OPI~/N6100/06 Shutdown Margin (With or Without Xenon Credit) Page 6 of 6 I NOTE: SDM is ensured between the DatesKimes of step 2.8.5 at the present NC System boron or i higher. After the Datemime of xenon decay of step 2.8.5,NC System boration wiil be required to maintain SDM.

2.8.5 Interpolate the DatedTimes from the xenon predict of step 2.8.4 that equal the xenon worth of step 2.8.3.

xenon build-in /

xenon decay I 1 NOTE: Separate, independent calculation must be performed by the verifier. I 2.9 Sign the appropriate space below. N/A the unsigned space.

Performed By: Dateirime: I Verified By: Date,/Time: I

Enclosure 4.5 OPIOIAI6 100/06

\critication of K-eff 6 0.99 With Shutdown Page 1 of 1 Banks Withdrawn

1. Initial Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure NOTE: Assume all values are positive unless otherwise indicated by parentheses. E parentheses precede the value [Le.( ) pcm], enter the sign provided with data. The calculations account for these sign conventions.

2.1 E cycle bumup is > 12 EFPD, perform Enclosure 4.8 to determine Shutdown Fission Product Correction Factor.

Shutdown Fission Product Cnrrection Factor PPm 2.2 Access Reactivity Balance Program per Enclosure 4.7.

2.3 Select View then Reactivity Balance Calculations on tonlbar.

2.4 Select Mode 3 Verification tab in Reactivity Balance Calculations window.

NOTE: 1. Sign must be provided with Difference from Equilibrium Samarium [Le.( ) p c m j .

2.5 Enter appropriate values as prompted.

2.6 Click calculate, print program results, label appropriately, and attach to this enclosure.

2.1 Compare current boron concentration to required.

2.8 -

IF Xenon Wortb is NOT zero Potential Mode 2 Boron Deficit is negative, obtain and attach printout of Xenon Predict from OAC program or REACT program for current and future xenon worth.

2.9 Record date and time Adjusted Mode 2 Deficit equals value of Xenon Worth on printout attached per Step 2.8. Mode 3 shall be maintained until this date and time. Prior to exceeding this date and time, boration wil1 be required tn maintain Mode 3 k-eff eO.99 with shutdown banks withdrawn.

Date Time 2.10 Ensure that separate, independent calculation has been performed per steps 2.1 - 2.9.

2.11 Verify that attachments to this enclosure yield the same result.

Performed By: DateRime: 1 Verified By: DateiTime: I

Enclosure 4.6 OP/O/N61OW06 Shutdown Boron Concentration - Mode 6 Page 1 of 1

1. Initiai Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure 2.1 Determine present boron concentration of the operating ND train. PP*n 2.2 Record Tech Spec Refueling Boron Concentration from bottom of PPm page of Section 5.11 of the R.Q.D. manual.

2.3 Verify present boron concentration of Step 2.1 is greater than refileling boron concentration of Step 2.2.

[ NOTE: Separate, independent calculation must be performed by the verifier. I 2.4 Sign the appropriate space beiow. NIA the unsigned space.

Perfonned By: Date!Time: I Verified By: DateKime: j

Enclosure 4.7 OPIOIN6 1O0/06 KEACT Computer Program Instructions Page 1 of 1

1. Initial Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure 1 NOTE: The following steps assnnie the use of the BOP PC located in the control room horseshoe. I 2.1 Select (Double-Ciick) the Reactivity Balance icon on the desktop.

~~~~~~~ ~

CAUTION: Check all inputs carefuliy and correct as needed before calculating results. Ensure the correct Unit is specified. I 2.2 Select an option as directed by the procedure. Input data appropriately where prompted.

Hit the tab key or use left mouse button to move from one item to the next.

2.3 Once the C_alculatebutton is left clicked, results will be displayed. The program output can then be printed by clicking on File followed by Print.

2.4 When finished using program, select File and Tzit or left click on x in upper right comer.

Enclosure 4.8 OPiOiAi6100iO6 Shutdown Fission Product Correction Factor Page I of 2

1. Initial Conditions 1.1 Limits and Precautions have been reviewed.

2. Procedure 2.1 no previous Unit TripiShutdown has occurred in the last 3 EFPD, determine thc Shutdown Fission Product Correction Factor as follows:

2.1.1 NiA Steps 2.2 and 2.3.

2.2 E previous Unit Trip/Shutdown has occurred in the last I EFPD, perform the following:

2.2.1 NfAStep 2.3

Enclosure 4.8 QP/o/A/6100i06 Shutdown Fission Product Correction Factor Page 2 of 2 2.3 there has been 1 to 3 EFPD of burnup between present Unit TriplShutdown and previous Unit TriplShutdown, perform the following:

2.3.1 @duration of shutdown from 2.3.C is > 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> Shutdown Fission Product Correction Factor is a5 shown in Step 2.3.D.

A. NIA Step 2.3.2.

2.3.2 duration from 2.3.C is < 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> perfom the following:

2.4 Ensure that separate, independent calculation has been performed and yields the same result.

Performed By: BateiTime: I Verified By: DateiTiine: I

Source: CNEI-04B0-26 UNIT ONE Prepared by: M.W. Hawes REACTOR OPERATING DATA Revision Number: 373 SECTION 5.1 Date: 7117/02 HZP CRITICAL BORON CONCENTRATlON (ARO, NO XE, EQ SM)

EFPD PPMB 2100 0' 1867 4 1889 2030 12 1887 25 1906 i900 SO 1946 75 1965 1800 100 1961 125 1937 1730 150 1902 200 1800 1 GO0 lR 250 1663 E 300 1504

0. 1500 Q 350 1327 400 1138

.-*K0 '400 450 943 e 500 745 E 1300 6l b) 510 705 u

1200 515 686 530 629 c

2 1300 545 573 0

m 1000 900 a30 700 5c0 500 0 50 100 150 200 250 300 350 400 450 500 550 Cycle Burnup, EFPD

Source: CNEI-0400-26 UNIT ONE Prepared by: MW #awes RACTOR OPERATING DATA Revision Number: 373 SECTION 5.2 Date: 7/17/02 HFP CRITICAL BORON CONCENTRATION (ARO, EQ XE, EQ SM) 1900 iFPD PPMB

'"1c Xe, Peak Sm 1600 0' 1664 4 1276 15C.O 12 1274 25 1232 i4CO 50 1331 75 1348

300 100 1344 1200 125 1320 150 1284 m 1100 !OO 1178 E ?50 1035 8 1000 300 868 i 350 679 2 900 100 477 2

E 800 150 272 al 500 66 0

5 700 510 25 0

515 7 600 20 i30 -48 m 500 545 -102 400 200 200 i00 0

I

-100 0 50 100 150 200 250 300 350 400 450 500 550 Cycle Burnup, EFPR

UNIT ONE SOUrCe CN61-0400-26 REACTOROPERATINGDATA Prepared L3y M W t i a v e s SECTION 5.3 Revision Number 363 ARi DIFFERENTIAL BORON WORTH Date 5 / 1 4 4 2 rPChl;FP~II

Source: CNEI-0400-26. ClC14 SOR Prepared by: MW Hawes Revision Number: 373 Date: ?!17/02 UNIT ONE REACTOR OPERATING DATA SECTION 5.4 HZP DIFFERENTIAL BQRQN WORTH I

~ _ _.. _ _ ~

'Peak Samarium

h

source: LNHWUJ-LD Prepared by M.W. Hawes Revision Number: 363 Dale: 5/14/02!

UNIT ONE REACTOR OPERATING DATA SECTION 5.6 INTEGRAL ROD WORTH IN OVERLAP Page lo1 15 Integral Rod Worth in Overlap HZP, No Xenon

source- L N ~ I ~ ) ~ U O - Z ~

Prepared by: M.W. Hawes Revison Number: 363 Dale: 5/14102 UNIT ONE REACTOR OPERATING DATA SECTION 5 6 INTEGRAL ROD WORTH IN OVERLAP Page 2 of 15 Integral Rod Worth in Overlap NZP, No Xcwon

.>"UILC.. L,IYCII)L*W-LO Prepared by M.W. Haws Revision Number: 363 Date: Y14lO2 UNIT ONE REACTOR OPERATING DATA SECTION s 6 INTEGRAL. ROD WORTH IN OVERLAP Page 3 of 15 Integral Rod Worth in Overlap IfZI', No Xenon

.3vu,(.e LIYLI-ww-dD Prepared by- M.W. Hawes f?evisionNumber: 363 Bate: 5/74/02 UNIT ONf-REACTOR OPERATING DATA SECTION 5 6

~~

INTEGRAL no0 WORTH IN OVERLAP Integral Rod IVorlh in Overlap IIZP, No Xenon

Y"Y.lr "..C. '_

Prepared by: M . W Hawes f7ev1sionNumber: 363 Dale: 5/14/02

.a,, UNll ONE REACTOR OPERATING DATA SECTION 5 6 INTEGRAL ROD WORTH IN OVERLAP Page 5 ol 15 Integral Rod Worth in Overlap HZP,No Xenon

0""ILe.. bI"LI-W,N-'U Prepared by: M.W. Hawes Revision Number: 363 Dale: Y14/02 UNIT ONE REACTOR OPERATING DATA SECTION 5 6 INTEGRAL ROD WORTH IN OVERLAP Page6of 15 Integral Rod Worth in Overlap FIZP, Peak Xenon

Prepared by: M.W. Hawes Flewsion Number: 363 Date: Y14/02 UNIT ONE RE STOR OPERATING C TA SECTION 5.6 INTEGRAL ROD WORTH IN OVERLAf' Page 7 u f i s Inkgral Rod Worth in Overlap iiZP. Peak Xenon C m ~ oDank l Po'ositioii Steps Witdrawn

.l"ll.II,. V,.LI VIW~LI, Prepared by: M.W. Hawes Revision Number: 363 Date: 5/14/02 UNIT ONF AtACTOR OPERATING DATA SECTION 5 6 INTEGRAL ROD WORTH IN OVERLAP Page 8 Of 1s Integral Rod Worth in Overlap HZP, Peak Xenon

auu1L;e. ~,lYflu*w-Lu Prepared by: M.W. Hawes Revision Number: 363 Date: Y 14/02 UNIT ONE REACTOR OPERATING DATA SECTION 5.6 INTEGRAL ROD WOHTH IN OVERLAP Page9of15 Integral Rod Worth in Overlap HZP, Peak Xenon

""_.I* .C I -\N i" Prepared by: M W. #awes Revision Number: 363 Dale: 5/14/02 UNIT ONE REACTOR OPERATING DATA SECTION 5.6 INTEGRAL ROD WORTH IN OVEHLAP PagelOof15 Integral Rod Worth i n Overlap HZP, Peak Xenon

.J)YYI C r . ~IILI-W-C" Prepared by: M.W. Hawes Revisicm Number: 363 Date: 5/14/02 UNIT ONt REACTOR OPERATING DATA SECTION 5 6 INTEGRAL ROD WORTH IN OVERLAP Page 11 of 15 Integral R d Worth in Overlap HFF, Equilibrium Xrnon

-"ul~l._ -,.LI __I L" Preparedby: M W Hawes Reviston Number .%3 Date. 5/14/02 UNIT ONE REACTOR OPERATING OATA SECTION 5 6 INTCGRAL ROD WOHl H IN OVERLAP Page12of 15 Integral Rod Worth in Overlap HFI', Equilibrium Xenon Control Bank Position srcps WltMraWn

Preparedby M W Hawes Revision Number 363 Dale 5/14/02 UNIT ONE REACTOR OPERATING DA.rA SECTION 5 6 INTEGRAL ROD WORTH IN OVERLAP Page 13ol 15 Integral Rod Worth in Overlap HFP, Equilibrium Xenon

U""8L.C. bk*L*ww-Lo Prepared by: M.W. Hawes Revtslon Number: 363 Date: 5/14/02 UNIT ONE REACTOR OPERATING U A l A SECTION 5 6 INTEGRAL ROD WORTH IN O V t R U P Page 14 of 15 lriregral R o d Worth in 0verl:ap HFP, Equilibrium Xenon

Preparedby: M W Hawes Revision Number 363 Date Y14/02 UNIT ONE REACTOR OPERATING DATA SECTION 5 6 IN rEGRAL ROD WOH i H IN OVCRL AP Page 150f 15 Individual Shutdown Bank Integral Hod Worth HFP, Equilibrium Xenon

Source: CNEi-0400-26 Prepared by: M.W. Hawes Revision Number: 380 Date: 9/18/02 UNIT ONE REACTOR OPERATING DATA SECTION 5.7 TOTAL AVAILABLE ROD WORTH NOTE: Most conservative (lowest) value of Total Available Rod Worth over applicable Burnup range is to be u5ed for Shutdown Margin calculations.

I CYCLE BURNUP I TOTAL AVAILABLE ROD WORTH I 5 4 EFPD I 5127 pcm I 100 EFPD I 4936 pcm tI 200 EFPD 300 EFPD 400 EFPD I!

~.c_.___..__~..~..

I I

4879 pcm 4935 pcm 5050 pcm 500 EFPD 530 EFPD 5260 pcm

~ ~

545 EFPD 5295 pcm Maximum Stuck Rod Worth During Cycle = 975 pcm Transient Flux Redistribution Allowance = 340 pcm Maximum Dropped of Mis-aligned Rod Worth = 200 pcm

Source: CNEI-0400-26 Prepared by: M.W. #awes Revision Number: 380 Date: 9/1W02 UNIT ONE REACTOR OPERATING DATA SECTION 5.8 iNOPERABE RCCA WORTHS CRDM CflDM WORM CWBM CRDM WORTH NUMBER LOCATION (P6M) NUMBER LOCATION _o sA2-1 8-4 45 CAI -2 H-10 658 CB2-1 B-6 212 SE1-3 H-12 418 cc1-2 B-8 40 cc1-3 H-14 40 CB1-2 6-10 212 SB2-4 J-3 263

§A1 -2 6-12 45 SB1-3 J-13 263 SDI-1 c -5 588 C82-4 K-2 212 SB2-1 C-7 263 662-4 K-6 658 SBt-2 c-9 263 cA2-2 K-8 658 SC1-2 6-1 1 588 CC2-3 K-10 658 SA1-1 D-2 45 CB1-3 K-14 212 CDI-1 D-4 604 581-4 L-3 588 SE1-2 D-8 418 SC1-3 L-13 588 CD2-1 D-12 684 sA2-4 M-2 45 sA2-2 D-14 45 CD2-2 M-4 604 SCI-1 E-3 588 SE1-4 M-E 418 SD1-2 E-13 588 CB1-2 M-12 604 C81-1 F-2 212 SA1-3 M-14 45 cc2-1 F-6 658 SC1-4 N-5 588 cA2-1 F-8 658 SB1-4 N-7 263 cc2-2 I=-10 658 $62-3 N-9 263 CB2-2 F-14 212 SD1-3 N-11 588 SE1-1 6-3 263 SA1-4 P-4 45 SB2-2 6-13 263 CB1-4 P-6 212 CCl-1 H-2 40 CC1-4 P-8 40 SE1-1 H-4 418 CB2-3 P-10 212 CAI-1 H-6 658 SA2-3 P-12 45 CD2-3 #-8 363

Told P o w r Defect (PCM) as n Function of Power and Cycle Burnup fro111 0 . SO%, I T

'I ulol Power Defect (PChI) as n Funclion of P o w r and Cycle Burnup rroni 55 - 100% FP

!SI: I I :(.:I I3<!5

..,?

i 409 1513 1616 1?31 1x46 I960 2075 2189 I??'. ,~>..L 1449 I5 5 h I663 17x1 I899 2017 2135 22Sl

L!NIT ONE Source: CNEI-0400-2(,

REACTOR OPERATING DATA Prepared By: M W Hawes SECTION 5.10 Revision Number: 383

\l!>DERAIOR AND ISOTHERMAL TEMPERATURE COEFFICIENTS

~.

Date: 10/16/02

~ ~~~ ~ ~~ ~~~~ ~

- .~~

1I Ii I

I i

550 555 560 565 570 575 580 585 590 595 600 i

Average Moderator Temperature (deg F) I I

1 i

Source: CNEI-C40D-26. CIC 14 SOR Prepared By: MW Fiawes Revision Number: 361 Dsrc: 4/35/02 P a g , ~I o f 2 UNIT ONE I11~4C'TOROPfiRATING DATA SECTION 5.11 h ~ l ~ ~ k lSI[ iirruxw j>~ MARG:N E O R O N Rcquircd Roron Cnnceotratioo for Shu(down Margin as a Function of Temperature and Burriup 3:.  : >:

?:I .-l!> 1256 1264 1262 1261 1258 1256 I255 1253 1251 I249 I247 1245

.-,> 121.1 1212 IZCY 120: 12% I204 I232 1200 1198 I186 4 J 4Al)

I 1032 94s SSY 99.1

'!M 879

'2 :j 3

~2.X,

\ 7n (i9 j 933 876 989 91 I

~~

873 987 929 870 985 122c 86R 983 924 865 Ye0

'122 863 978 919 860 976 917 858 973 914 855 97 I 912 E53 968

'109 850 966 906

~

54:

963 sn?

844 776 773 770 767 764 76 i 755 156 753 750 747 144 74 I 753 ;iH 734 73 I 726 725 122 719 716 713 7iO 707 704 7cil 697 c.93 690 687 684 6RI 676 674 GI 668 665 66 I 658 654 KO'lk.:S: 1) 'l'ccli Spec l < ~ ~ u c l horaii k ~ g concentration is 2700 ppniR (per ClC14 COLRI

2) 1311 i i i i i l \'ciit Itoron conccotratiorr is 1931 ppniI3

Source: CNEI-0400-26. C1C14 SOR Prepared By: MW H;iwcs Revision Number: 361 mc:c/~G:o~

f'agc 2 of2 I,.?', 1623 1620 1616 1610 16C3 !594 I582 1571 :557 1538 1514 1483 144? 14?1 1b.G  ! 647 1044 1641 1636 1623 1621 i61C I600 :58h 156.7 I543 1512 I474 I(?!X 1638 1594 I576 is51 I520 1482 1469 15G8 I5K7 1573 I554 1529 1497 1451 1444 i572 IS61 I546 IS25 1500 1461 i425 141, 1540 I528 1513 1492 1465 1430 I385 1371 1503 149; :474 I452 l4i4 I381 1340 1325 i46: i448 1431 I408 1375 1339 1229

E

e m

P 0

Operational Mode Boron Concentrations Boron Concentration (.iPlvlD) Tor K-eff = 0.99 ;IS a ~ur;ct;oiiof Tem?erature nnd Buin:!p with Co?!!ro!B o d s Or;/? /,iscricd e~xidA s R I cast:? with Hichest Worth Bank W J h d r p ~ n

SOURCE CNEI-0400-26 PREPARED BY M.W.Hawes REVISION 363 DATE 5/14/02 UNIT ONE REACTOR OPERATING DATA SECTION 5.13 SHUTDOWN FISSION PRQDUCT CORRECTION Time Correction Time eOrreCFiQn (hours) (days) (ppm) -(hours) ( d a y s ) (ppmL 0 000 00 240 10.00 49.0 1056 44.00 55.3 6 025 27 246 10.25 49.0 1080 45.00 55.4 12 0.50 55 252 10.50 49.1 1104 46.00 55.6

18. 0

....7 5 Q ? 258 10.95 49.2 1128

-.~ 47.00 55.7 24 1.00 13.0 264 11.00 49.2 1152 48.00 55.8 30 1.25 15.7 270 11.25 49.3 1176 19.00 55.9 36 1.50 18.4 276 11.50 49.3 - -

I 1200 50.00 56.1 47 1.75 21.1 282 11.75 49.4 1224 51.00 56.2 48 2.00 23.7 - I 288 12.00 49.4 .- 1248 52.00 56.3 I 54

_ 2.25 26.3 ... 312 13.00_--.-I. 49.7~

?17? 53.00~. 56.5 .-

. 60 2.50 --_I_.._

28.9 336 14.00 49.9 1736 54 00 56.t; I.-__ ~-

-I 66 2.75 31.6

-___I 360 lS.00 50.1 .- 1320 55.00 56.7 72 .'3.00 34.2 384 1600 50 ,'3 1344 56.00 56.8

~

408

~~ i 7 00.. .50

... f; - -. _

1368 57.00 57 0 l _

432 18.00 50.6 - -_ 1392 58.00 57.1__

456 I_

19.00 5:_.0_ 141f5 59.00 57.2_I_

480 20.00 51 2 -_1440 65.00 57.4 504 21.00 51.5 ~.1464 61.00 57 3 528 22.00 51.1 1488 62.00 57.3

~

552 23.00 51.9 ........ 1512.~ 63.00 57.?

576 24.00 ._I.~ 52.2 1536 64.00 Sl.2 600 25.00 52.4 624 26.00 52.6 .. .._I___

648 77.00 52.8 1800 75.00 ... 56,R 672 28.00 53.1 - _I 1920 80.00 56.7 696 29.00 53.3 2040 85.00 I 56 5

_ _ _ ~

720 30.00 53.5 I ~

2160 90.00 56.3 744 ..... 00 31 i ?6

....... . 2780 95.00 56.2 768 32.00 53.R - 2400 100.00 56.0

.-792 33.00 53.9 ~. 2520 105.00 55.8 816 34.00 54.0 54.2

__ 2640 2760 1 1 0 . 0 0~.~ ~55.6 115.00

~~

-~

55.5 840 35.00 __.

864 36.00 54.3 2680 120.00 55.3

.... 888 37.00 _ 54.4 _ _ ~ .. 3000 125.00 55.1 204 8.50 46.8 912 38.00 54,s

~. 130.60 54 9 210 8.7;

..... 47.? ..- 936 39.00

.- 54.1 175 00 54 7 950

---..___ 40.00 ~

54.8 - 3360- 140.00 51.5 ~

I480

--___ 145.00 5 43

%i)0 I50 00 S'l 1

I Page t of 7 CATAWBA INITlAL LICENSE EXAM1NATION JOB PERFORMANCE MEASURE JPM 2WADMIN Monitor Reactor Coolant System Leakage During LOSSof OAC CANDIDATE EXAMfNER

Page 2 of 7 CATAWBA INITIAL LICENSE EXAMINATION JOBP~R~ORMANCEMASURE Task: Monitor Reactor Coolant System Leakage and determine status of leakage during Loss of OAC Alternate Path:

N/A Facilitv JPM #

NEW WA Ratinnts):

2.1.23 (3.914.0)

Task Standard:

Collect data on Reactor Coolant system Leakage and correctly determines that the acceptance criteria of Endosufes 13.5 and 13.7 are not met and notifies §BO.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator 2 In-Plant X Perform X Simulate ~

References:

13T/1/A/46001009 (Loss of Operator Aid Computer) Revision 67 Candidate: Time §tart :

NAME Time Finish:

Performance Ratins: SAT UNSAT Performance Time COMMENTS

Page 3 of 7 Toolsl~quipmentlPfoeduhesNeeded:

PT/18/4600/009 (Lossof Operator Aid Computer)

Enclosures with first set of data entered READ TO OPERATOR DIRECTION TO TRAINEE:

1 will explain the initial conditions, and state the task to be performed. All controi room steps shall be performed for this JPM, induding 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 skeet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 3. You are the Balance of Plant Operator responding to a boss of Operator Aid Computer. The Control Room SRO is assigning tasks to complete in PT/1lA14600/009 (Loss of Operator Aid Computer). The initial set of data has been entered (0830 hrs) into all required enclosures.

lNlTlATlNG CUE:

The Control Room SRO directs you to gather the next set of readings (0930 hrs) for:

Enclosure 13.4 (Ventilation Unit Condensate Drain Tank Input Rate Determination)

Enclosure 13.5 (Containment Floor and Equipment Sumps Input Rate Determination)

Enclosure 13.6 (1EMF-38 Delta Count Rate Determination)

Enclosure 13.7 (IEMF-39 Delta Count Rate Determination)

Evaluate data obtained from each enclosure to determine if it is acceptable and notify the Control Room SRO of the results.

Page 4 of 7 Start Time:

STEP I: Record secund data set for "Unit 1 VUCDT LEVEL" on Enclosure 13.4, VUCDT INLEAKAGE !?APE LOG SHEET -SAT STANDARD: Contacts either Radwaste Chemistry or sends NLO to Unit 1 VUCDT Level instrument on panel IELCCOOI 3 to obtain data. -UNSAT EXAMINER CUE: WHEN operator dispatched or Radwaste technician is called, report that VUCDT level is reading 14%.

STEP 2: Candidate determines that VUCDT level has increased less than 1%

since last data collection -SAT STANDARD: Based un previous data and current VUCDT level, candidate determines level increase is 0% per hour and criterk is met. -UNSAT COMMENTS:

Page 5 of 7 STEP 3: Enclosure 13.5, Containment Floor and Equipment Sumps Input Rate CRITICAL Determination actions are performed. STEP EXAMINER CUE: The Containment Floor and Equipment pumps were turned off 90 minutes ago. -SAT STANDARD: Enters time and sump Ieveis. Calculates leak rate per calculation formula on Enclosure 13.5 Page 4 of 4: -UNSAT A Sump 12.1 inches is 467.6 gallons, (current reading) 9.5 inches is 399.5 gallons, (previous reading) 467.6 - 399.5 = 6 8 ~ 1gallons per hour B SumD 8.7 inches is 369.7 gallons, (current reading) 7.5 inches is 311.9 gallons, (previous reading) 369.7 - 311.9 = 57.8 gallons per hour Total leakage = 68.1+ 57.8 = 125.9 gallons per hour 125.9 gallons/6Q minutes = 2.098gallons per minute EXAMINER CUE: Containment Floor and Equipment Sump A reads 12.1 inches and Sump 0reads 8.7 inches COMMENTS:

STEP 4: Enclosure 13.5, Containment Floor and Equipment Sumps Input Rate CRITICAL Determination leakage is checked against the criteria. STEP STANDARD: Candidate determines that the leak rate is greater than 1 gpm for the Containment Floor and Equipment Sump and criteria is NOT met. -SAT COMMENTS:

-UNSAT

Page 6 of 7 STEP 5: Enclosure 13.6, 1EMF-48 Delta Count Rate Determination is performed.

-SAT EXAMINER CUE: EMF38 Low Range is reading 200 CPM STANDARD: Candidate records EMF38 Low Range radiation count rate at module. -UNSAT Determines delta reading is less than 750 cpm.

COMMENTS:

STEP 6: Enclosure 13.7, 1EMF-39 Delta Count Rate Determination is CRlnCAL performed. STEP EXAMINER CUE: EMF39 Low Range is reading 8979 CPM

-SAT STANDARD: Candidate records EMF39 Low Range radiation count rate at module. Determines delta reading is greater than 6700 cpm and criteria is NOT met -CLMSAT COMMENTS:

STEP 7: Reports results to SR8 CRITICAL STEP STANDARD: Candidate reports that Containment Floor and Equipment Sump input Rate and 1EMF-39 Count Rate Change do NOT meet criteria.

EXAMINER CUE: I understand that the Containment Floor and Equipment Sump Input Rate and IEMF-39 Count Rate change do not meet acceptable criteria. -UNSAT COMMENTS:

JPM Complete TIME STOP:

Page 7 of 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 is in Mode 3. You are the Balance of Plant Operator responding to a LOSS of Operator Aid Computer. The Control Room SRB is assigning tasks to complete in PT/1/A/4600/009 (Loss of Operator Aid Computer). The initial set of data has been entered (0830 hrs) into all required enclosures.

INlTlATlNG CUE:

The Control Room SRO directs you to gather the next set of readings (0930 hrs) for:

Enclosure 13.4 (Ventilation Unit Condensate Drain Tank Input Rate Determination)

Enclosure 13.5 (Containment Floor and Equipment Sumps Input Rate Determination)

Enclosure 13.6 (1EMF-38 Delta Count Rate Determination)

Enclosure 13.7 (1EMF-39 Delta Count Rate Determination)

Evaluate data Qbtain6dfrom each enclosure to determine if it is acceptable and notify the Control Room SRO of the results.

Duke Power Company Procedure No Catawba Nuclear Station I Loss of Operator Aid Computer 067 TROLLED FOR PRINT **********

(ISSUED) - PDF Format

PT!1 IN46OQ1009 Page 2 of 8 Loss of Operator Aid Computer

1. Purpose.

To document Technical Specifications requirements normally performed by the Operator Aid Computer in the event that the unit Operator Aid Computer is out of service.

2. Referense

2. I OPll/A/6400!Q03 (Operation with the Operator Aid Computer Out of Service) 2.2 Catawba TS and SLC Requirsments:

2.2.1 TS 3.1.4 2.2.2 TS 3.1.6 2.2.3 TS 3.2.3 2.2.4 TS 3.2.4 2.2.5 TS 3.3.1 2.2.6 TS 3.4.2 2.2.4 TS 3.7.5 2.2.8 TS 3.4.13 2.2.9 TS 3.4.15 2.2.10 SR3.1.4.1 2.2.1 1 SR 3.1.6.2 2.2.12 SR 3.2.3.1 2.2.13 SK 3.2.4.1 2.2.14 SR3.4.2.1 2.2.15 SLC 16.5-7 2.2.16 TS 3.6.3 2.2.14 TS 3.7.3

3. Time Required 3.1 Manpower - One Operator 3.2 Time - Until the Operator Aid Computer is restored to service.

3.3 Frequency - When the Operator Aid Computer is out of service.

4. Prerequisite Tests None

5. Test Equipment None

6. Limits and Precautions 6.1 If an acceptaim criteria is NOT met, the Operations Shifi Manager and the Operator at the Controls should be notified immediately.

6.2 If the unit status or system condition prevents the performance of a survcillance item, the item should be noted on the affected data sheet with an explanation and the Operations Shift Manager and the Operator at the Controls should be notified immediately.

7. Required Unit Status None

8. Prerequisite System Condition

=Verify the Operator Aid Computer is out of service

9. Test Method A visual inspection of various system instrumentation will be made until the computer is returned to service.

10. Data Required Complete Enclosures as required.

11. Acceptance Criteria No data taken shall exceed Limits Listed on the Enclosures

PTiliA/4600/009 Page 4 of 8

12. Procedure

12. I -

IF in 1 des 5 6,EVERY 15 MINUTES document the critical core parameters listed on Enclosure 13.1 (Criticai Core Parameters Sheet) (Reference OEP).

12.2 -

IF Start Up Of ND System During Plant Cooldown (OP/1/W6200/004) is in progress AND KCHX Maximized CooIing Temperature Monitoring is being performed, within 15 minutes and every 15 minutes thereafter record parameters on Enclosure 13.2 (KCHX Maximized Cooling Temperature Monitoring) 12.3 EVERY 15 MINUTES record on Enclosure 13.3 (Auxiliary Building Ventilation Supply Unit Status) the status of the Auxiliary Building Ventilation System supply units.

12.4 - IF in Modes 1-4,within 30 minutes ofLoss of OAC and once per hour thereafter, verify and record on Enclosure 13.4(Ventiiation Unit Condensate Drain Tank Input Rate Determination) that the rate of increase in VUCDT level is < 1% per hour. (TS 3.4.13 and 3.4.15) 12.5 -

IF in Modes 1-4,within 30 minutes of Loss of OAC, begin performing Enclosure 13.5 (Containment Floor and Equipment Sumps Input Rate Determination) to verify input to the Containment Floor and Equipment Sump is less than 1 gpm. (TS 3.4.13and 3.4.15) 12.6 - IF in Modes 1-4> within 30 minutes of Loss of OAC and once per hour thereafter, verify and record on Enclosure 13.6 (IEMF-38Delta Count Kate Determination) that the change in count rate on EMF-38 is < 750 cpxn in one hour. (TS 3.4.13and 3.4.15) 12.7 - IF in Modes 1-4,within 30 minutes of Loss of OAC and once per hour thereafter, verify and record on Enclosure 13.7 (IEMF-39 Delta Count Rate Determination) that the change in count rate on 1EMF-39 is < 6700 cpm in one hour. (TS 3.4.13 and 3.4.15) 12.8 -

IF ALL. the following conditions exist (Reference SR 3.4.2.1):

Reactor Critical TAVG < 561°F TREP - TAoCT- IIiiLo Alarm Present, Annunciator lAD2 A!4 EVERY 30 MKIJTES verify Reactor Coolant loops TAVC  ? 551°F by completing Enclosure 13.8 ( l ~Data . Sheet).

~ ~ ~

NOTE: The YC Operable But Degraded Condition is normally active during the winter months based on Lake Wyiie and SNSWP temperaturcs.

I 12.9 the YC Operable But Degraded Condition is active, perform Enclosure 13.9 (YC Operable But Degraded Temperature Monitoring).

PTI 1iAl46OOIOO9 Page. 5 of 8 12.10 both trains of the plasma display monitor are inoperahle in Modes 1-6, EVERY 60 MINUTES or after 10% change in power, complete Enclosure 13.10 (Suhcooling Data Sheet) to monitor subcooiing margin.

12. I I Unit 1 net generation CANNOT be obtained from the Unit 1 operator aid computer, perfom the following:

12.11.1 At the top of the first hour during loss of OAC, notify SOC that they will not he getting station or unit MWK hourly values from both CNS units.

Person notifred c &&WJ 12.11.2 EVERY HOUR on the HOUR complete Enclosure 13.11 (Electrical Data Sheet).

2. Use a calibrated pyrometer to obtain SIG shell temperatures.

12.12 NC Tc: is > 80°F AND a NC pump is operating, then the secondary side temperature is > 8Q"Fand documentation of shell temps is NOT necessary. in Modes 5 , 6 No Mode, EVERY 60 MKUTES complete Enclosure 13.12 (Steam Generator Data Sheet)

(Reference SLC 16.5-7).

12.13 in Mode 1 AND less than 50% rated power, prior to exceeding 50% rated power and every 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> thereafter, with the AFD monitor alarm inoperable, monitor and log the indicated Axial Flux Difference for each operable excore channel on Enclosure 13.13 (Axial Flux Difference (%A Flux) Following Loss of AFD Monitor Alarm). (Reference SR 3.2.3.1 and TS 3.2.3).

12.14 in Mode 1 AND 2 50% rated power, once within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> thereafter with the AFD monitor alarm inoperable, monitor and log the indicated Axial Flux Difference for each operable excore channel on Enclosure 13.13 (Axial Flux Difference

(%A Flux) Following Loss of AFD Monitor Alarm). (Reference SR 3.2.3.I and TS 3.2.3).

12.15 in Modes 1 2, EVERY 4 HOURS verify by signing off on Enclosure 14.14 (Rod Verification Checklist) that the Digital Rod Position indication for all rods are within

+ 12 steps of their group step counter demand position and operable (Reference SR 3.1.4.1).

12.16 in Mode 1 2 AND KEFF 1 .O, EVERY 4 HOURS verify and record on Enclosure 13.15 (Rod Insertion Limit Checksheet) that each control bank of rods is above the rod insertion limit (Reference SR 3.1.6.2).

PT/ 1/A/46O0/009 Page 6 of 8 12.17 in Modes 1,2, 3, O R Mode 4, when steam generators are being used for heat removal; EVERY 4 HOURS record CA suction source temperatures measured loc,allyusing a calibrated Keithley S72 digital thermometer, Type J or its equivalent, as required, per Enclosure 13.16 (CA Suction Source Temperature Monitoring Data) 12.18 in Modes 1-4, within 4 HOURS and every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter, monitor the CF containment isolation valves N2 accumulator pressures on Enclosure 13.17 (CF Containment Isolation Valve N2 Accumulator Pressure Monitoring).

12.19 z_F in Modes 1-4, EVERY 6 HOURS, document data needed for primary to secondary leakage calculation on Enclosure 13.18 (Primary to Secondary Leakage Calculation Data) and provide data to Chemistry. Notify Secondary Chemistry to perform PT/I/B/4600/028 (Determination Of Steam Generator Tube Leak Rate For Unit 1).

12.20 E Auxiliary Spray is being used for pressurizer pressure control, EVERY 12 HOURS complete Enclosure 13.19 (Pressurizer Spray AT Data Sheet).

12.21 in Mode 1 AND above 50% rated power, once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, document Quadrant Power Tilt Ratio, as calculated by PT/Q/A~4600/08B (Man. Cal. of Quad. Tilt), in Enclosure 13.1 of PT!l/A/4600/002A (Mode 1 Periodic Surveillance Items). (Reference SR 3.2.4.1) 12.22 E in Modes 1-39within 12 HOURS of the Loss of QAC and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, monitor the CA piping surfme temperatures. Perform OP/liAi6250!002, Enclosure 4.12 (Checking Pipe Surface Temperatures).

12.23 in Modes 1-2, within 12 HOURS of the Loss of OAC and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, monitor the Qvertemperature Delta T parameters and record on Enclosure 13.20 (Overtemperature Delta T Setpoint Channel Check). (Reference SR 3.3.1. I )

12.24 E in Modes 1-4, EVERY 24 IIOURS perform a manual leakage calculation of the NC System in accordance with PT/i/N4 15010011 (NC Manual Leakage Calculation).

(Reference TS 3.4.1.5,Required Action A.1).

12.25 Update Enclosure 13.21 (Chemistry Data Sheet) as information becomes available from Chemistry.

12.26 WHEN the OAC is returned to service, notify Shift Work Manager to coordinate with L.ocal IT and Reactor Group Duty Engineer to ensure OAC is updating properly.

12.26.1 Notify SOC that MWH data should be valid at the top of the next hour.

Peeson notified 12.26.2 Give a copy of Enclosure 13. I 1 to the SSA to assist them in editing the switch board logs.

PT/l!pJ4600/009 Page 7 of 8 12.27 Evaiuate the acceptance criteria by performing one of the following:

12.27.1 Verify the acceptance criteria specified in Section 1 I is met.

OR

- 12.27.2 the acceptance criteria is NOT met, perform the following:

3 Notify the UnWWCC SRO that the acceptance criteria is NOT met.

~- /

Unit/WCC SRO Contacted Date Time 0 Initiate a PIP to dociiment the test failure.

0 Document all issues on a proc.edure discrepancy sheet,

- 12.28 E any discrepancy is noted during the performance of this test that does NOT keep the test from meeting the acceptance criteria, it shall be given to the UnitlNCC SIZO for evaluation via a discrepancy sheet.

~

12.29 Submit PT/lih4600/009 (Loss of Operator Aid Computer) to the UnitWCC SRO.

13. Enclosures 13.1 Critical Core Parameters Sheet 13.2 KCKX Maximized Cooling Temperature Monitoring 13.3 Auxiliary Building Ventilation Supply Knit Status 13.4 Ventilation Unit Condensate Drain Tank Input Rate Determination 13.5 Containment Floor and Equipment Sumps input Rate Determination 13.6 IEMF-38 L>elta Count Rate Determination 13.7 1EMF-39 Delta Count Rate Determination 13.8 TAVGData Sheet 13.9 YC Operable But Degraded Temperature Monitoring

-. PTibAi4600/009 Page 8 of 8 13.10 Subcooling Data Sheet 13.11 Electrical Data Sheet 13.12 Steam Generator Data Sheet 13.13 Axial Flux Difference (%A Flux) Following Loss of AFD Monitcr Alarm 13.14 Kod Verification Checklist 13.15 Rod Insertion Limit Checksheet 13.16 CA Suction Source Temperature Monitoring Data 13.17 CF Containment Isolation Valve N2 Accumulator Pressure Monitoring 13.18 Primary to Seccndary Leakage Calculation Data 13.19 Pressurizer Spray AT Data Sheet 13.20 Overtempmature Delta T Setpoint Channel Check 13.21 Chemistry Data Sheet

Enclosure 13.4 IYr/1/A/4600/009 Ventilation Unit Condensate Drain Tank Page 1 of 1 Input Hate Determination Acceptance Criteria - Rate of increase must be il%/hour.

NOTE: I. Either ofthe following instruments may be used to perform this surveillance, however.

the same instrument should be used for the duration of time the procedure is in effect:

0 "UNIT 1 VUCDT LEVEL on Auxiliary Waste Processing Control Panel (lELCC0013) (AB-543, MM, 53-54) .

1WLP.5441 (AB-543, BB-CC, 50) CA Pump Room (Next to VUCDT)

2. If the rate of increase is > I%/hour, the VIJCDT input rate is > 1 gpm. Refer to TS 3.4.13 and TS 3.4.15 and determine ifNC System leakage is > 1 gpm.

inate with Radwaste Chemistry as required when the WJCDT needs to be pumped

Enclosure 13.5 r"r:1/~/4600/009 Containment Floor and Equipment Sumps Page 1 o f 4 Input Rate Determination

1. Procedure NOTE: If any containment floor and equipment sump pmnp starts during the 10 minute test period the test results wili be valid. The test should be repeated until valid results are obtained. (Le. no pump start during test period) 1.1 Stop the following sump pumps and piace in "Manual":

0 "Pump 1At Cont Floor & Equip Sump" a "Pump 1A2 Cont Floor & Equip Sump" "Pump 1B1 Cont Floor & Equip Sump" "Pump 1B2 Cont Floor & Equip Sump" NOTE: The Containment Floor and Equipment Sumps may be pumped down as necessary, however, a new initial sump level reading should be recorded after the pumps are returned to the "Manual" position.

I .2 at any time during the performance of this test the sump level reaches 15". perform the foliowing:

1.2.1 Piace the following sump pimps in "AUTO":

e "Pump 1Al Cont Floor Kr Equip Sump"

• "Pump 1A2 Cont Floor &. Equip Sump" "Pump i B 1 Cant Floor & Equip Sump" "Pump 182 Cont Floor & Equip Sunip" etection Systems must be declared 1.2.2 Verify the affected sump level is lowered to 10" as indicated on 1WLP5740 (Cont Floor and Equipment Sump A Level) or 1WLP5750 (Cont Floor and Equipment Sump B Ixvel).

1.2.3 Return the following sump pumps to "Manual" and stopped:

"Pump 1.41 Cant Floor Kr Equip Sump" 0 "Pump 1A2 Cont Floor & Equip Sump" 0 "Pump 1R I Cont Floor Kr Equip Sump" "Pump IR2 Cant Floor & Equip Sump"

Enclosure 13.5 PT/ 1!A!460O/OW Containment Floor and Equipment Sumps Page 2 o f 4 Input Rate Determination

.3 Record initial sump readings on the "Containment Floor and Equipment Sump Inleakage Rate Log Sheet".

1.4 Once per hour, record sump level readings on the "Containment Floor and Equipment Sump Inleakage Rate Log Sheet".

1.5 Calculate the leakage rate using the "Sump Volume vs. Level Indication Table".

1.6 Verify leakage is I gpm 1.7 the input to the Containment Floor and Equipment Sumps is f. 1 gpm, perform the following:

0 RefertoTS3.4.13 andTS3.4.15.

• Determine if NC System leakage is 3%1 gpm.

__ 1.8 WHEN the OAC is returned to sewice, place the following sump pumps in "AUTO":

"Pump IAI Cont Floor & Equip Sump" "Pump IA2 Cont Floor & Equip Sump" 0 "Pump IBI Cont Floor & Equip Sump"

• "Pump iB2 Cont Floor & Equip Sump"

Enclosure 13.5 PT/1 iA/4600!009 Containment Floor and Equipment Sumps Page 3 of 4 Input Rate Determination Containment Floor and Equipment Sump Inleakage Rate Log Sheet

Enclosure 13.5 PT/lik~4600/009 Containment Floor and Equipment Sumps Page 4 of 4 Input Rate Determination SUMP V Q I A M E VS. LEVEL INDICATION TABLE To calculate the Rate of volume increase in the Sump, perfom the following calculation:

(Sunlp A Gals.(T2]~:~Surnr,A (ials.(Tljj ~t (Sump B Gals.(TZ) -~Sumpu Cials.(TID (Time at TZ ~ T i m at c T1)

NOTE: i. TI is the data from the previous reading.

2. T2 is the data from the current reading.

Enclosure 13.6 PT/1 /A/4600/009 1EMP-38 Delta Count Rate Determination Page 1 of 1 Acceptance Criteria Change in count ~ a t <

e 450 cpm per hour.

2. A digital readout of 1EMF-38 may be obtained from recorder lMHCR6640.

c Enclosure 13.7 P?.il!Ai460OiOO9 1EMF-39 Delta Count Rate Determination Page 1 of 1 Acceptance Criteria - Change in count rate < 6700 cpm per hour.

L NOTE: If the change in count rate per hour is 6300 cpm, refer to TS 3.4.13 and TS3.4.15 and determine ifNC System leakage is 1 gpm.

i Page 1 of 8 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM 3FUADMIN Classify Emergency Diesel Generator Start and Make Required Log Entries CANDIDATE EXAMINER

Page 2 of 8 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Classify Emergency Diesel Generator Start and Make Required Log Entries Alternate Path:

MIA Facilltv JPM #:

NEW KIA RatinqW:

2.2.12 (3.0j3.4)

Task Standard:

Correct classification of Emergency Diesel Generator is determined as an INVALID FAILURE and OMP 2-28 Attachment 10.1 is filled out down the point where it is ready to be reviewed by the casao.

Preferred Evaluation Location: Preferred Evaluation Method:

SimulatorX In-Plant X Perform Simulate ~

References:

Operations Management Procedures 2-28, Diesel Generator Logbook Revision 24 Examiner: I NAME SIGNATURE BATE

Page 3 of 8 ToolslEsui~entlProc~~ures Needed; OMF-2-28 Completed Attachment 10.2 showing last diesel run and total run hours for 2003.

READ TO OPRATOR DIRECTION TO TRAINEE:

B 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 2 is in Mode 1. You are an extra operator on shift and assisting the Operation Test Group in a scheduled surveillance test of the 28 Emergency Diesel Generator. The test will be conducted using procedure PT/ZA/4350/002B, B/G Operability Test.

INITIATING CUE:

The history of what occurred during the 2i3 diesel operability is as follows:

e The test was performed as a Turbo Prelube and Manual key start.

Speed, frequency, and voltage reached their required values in 7.3 seconds.

Diesel Generator ran loaded to 3600 KW from 0830 to 0915 then tripped on "High Jacket Water Temperature"

• IAE Technicians determined that the trip was spurious since the highest recorded water temperature only reached 198 O F .

Classify the test and complete a Diesel Generator Logbook entry fer this test and submit to the CRSRO for review.

Page 4 of 8 Start Time:

EXAMINER CUE: Brevide a copy of QMB 2-28 and a completed copy of Attachment 40.2 shewing the last logbook entry for 2 8 STEP 1: Candidate enters diesel generator on Attachment 10.1

-SAT STANDARD: Candidate enters Diesel Generator: 28 COMMENTS: -UNSAT STEP 2: Candidate enters hisher name as Recorded By on Attachment

-SAT STANDARD: Candidate enters Recorder by: Candidate performinq test

-UNSAT STEP 3: Candidate enters START ATTEMPT NUMBER on Attachment -SAT 10.1 STANDARD: Candidate enters next start attempt number based on last entry -UNSAT of Attachment 10.2. Enters 2003-16 COMMENTS:

Page 5 of 8 1 STEP4: Candidate enters DATE onto Attachment 10.1 STANDARD: Candidate enters TODAY'S DATE on Attachment 10.1.

-SAT

-UNSAT COMMENTS:

STEP 5: Candidate enters PROCEDURE USED onto Attachment 20.1. -SAT STANDARD: Candidate checks PT/l(2)/4350/002A(B) based on initial cue on Attachment I O . I. -UNSAT COMMENTS:

STEP 6: Candidate enters REASON FOR DIG OPERATION onto -SAT Attachment 10.1, STANDARD: Candidate checks SCHEDULED SURVIELLANCE per the initial -UNSAT cue on Attachment I O . I, COMMENTS:

STEP 7: Candidate enters TYPE OF START onto Attachment 10.1.

STANDARD: Candidate cheeks TURBO PRELUBE from the initial cue on Attachment 10.1 ~

COMMENTS:

Page 6 of 8 STEP 8: Candidate refers to OMP 2-28 Section 6 and determines the CRITICAL TEST CLASSIFICATION and checked that block on Attachment STEP 10.1.

STANDARD: Candidate determines the following and checks the appropriate -SAT block for:

It is NOT a Valid Success due to NOT meeting criteria 6.1 C It is NOT a INVALID TEST due to NOT meeting criteria 6.1 -UNSAT A,B, or C 0 *it IS an INVALID FAILURE due to MEETING CRITERIA 6.1 B (Spurious operation of a trip that is bypassed in the EMEKGENCY OPERATING MODE) The Jacket Water Trip is a NON-Emergency trip which is bypassed during the Emergency Operating Mode.

It is NOT a INVALID FAILURE due to NOT meeting criteria 6.2A, B, or C.

EXAMINER NOTE: Critical Step den~tedby

• COMMENTS:

Candidate enters OPERATING DATA onto Attachment 10.1, STANDARD: Candidate enters the start and step times for the diesel generator from the initial cue. Based on Attachment 10.2 run log, -UNSAT adds current and previous hours for new total run hours:

Previous Run Time: t3.75hours Latest Kun Time: 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Totat DIG Engine Yearly Run Time: 14.50 Hrs.

COMMENTS:

Page 7 of 8 I

I STEP 10: Candidate enters explanation in detail the reason DIG operation was not a Valid Success onto Attachment 10.1.

-SAT STANDARD: Candidate records that the diesel tripped spuriously on the Hiqh -UNSAT Jacket Water Temperature Trip prior to reachinq the one hour at qreater than 2875 KW criteria.

COMMENTS:

STEP 11: Note If a Valid or Invalid failure, route copy to MCE.

STANDARD: Candidate determines that note applies to this situation.

EXAMINER CUE: SSA will route copy to the MCE.

COMMENTS:

STEP 12: Submit Attachment 10.7 to CKSRO for review. -SAT STANDARD: Candidate submits attachment to CRSRO.

-UNSAT EXAMINER CUE: CRSRO will review the attachment.

COMMENTS:

JPM is complete TIME STOP:

Page El of 8 CANDIDATE CUE SHEET (POBE RETURNED TO EXAMINIER UPON COMPLETION OF TASK) lNlTrAL CONDITIONS:

Unit 2 is in Mode 1. You are an extra operator on shifl and assisting the Operation Test Group in a scheduled surveillance test of the 2B Emergency Diesel Generator. The test will be conducted using procedure PT/2/N4350/002B, Q/G Operability Test.

INITIATING CUE:

The history of what occurred during the 2B diesel operability is as follows:

The test was performed as a Turbo Prelube and Manual key start.

Speed, frequency, and voltage reached their required vaiues in 7.3 seconds.

e Diesel Generator ran loaded to 3600 Kw from 0830 to 0915 then tripped on High Jacket Water Temperature e IAE Technicians determined that the trip was spurious since the highest recorded water temperature only reached 178 O F .

Classify the test and complete a Diesei Generator Logbook entry for this test and submit to the CRSRQ for review.

_____ -- ~

Operations Management Procedure 2-28 Page 1 of 1 Attachment 10.2 Index Sheet DiG __2B

Operations Management Procedure 2-28 Page 1 of 1 Attachment 10.1 Diesel Generator Sheet DIESEL GENERATOR LE3 RECORDED BY W W @ D 4 Z START ATTEMPT NUMBER 2m3-/6 DATE FaDms DAfi PROCEDURE USED: REASON FOR D/G OPERATION:

~PT/l(Z)/A/4350/oo2A(B)(D!G Operability Test) !I6 Scheduled S u n 4 l a n c e OP/l(Z)/A/6350/002 (DIG Operation) 0 Opposite Train Inoperable 61 Other, Speci@: 0 Functiond Verification (Maintenance)

U Other, Specify:

TEST CLASSIFICATION: (See OMP 2-28, Sect. 6 )

d u r b o Prelube 0 VALID SUCCESS

[3 Non-Prelube Time required to reach 1 441 IiPM (98%

speed) and Frequency 60 A 1.2 Hz sec.

OPERATING DATA:

• Time required: Voltage 1 4160 420 volts sec.

Time Load? 2875 KW hrS.

E l INVALID TEST D/G Engine Start DateiTime DLS DIG Engine Shutdown Date/Time B W ? Y ,/0@/5-0 VALID FAILURE Run Time (hrs) 0.75- /3.95+95

• Total D!G Engine Yearly Run Time Hrs.

Explain in detail the reason D/G operation was a VALID SUCCESS/failed to meet NOTE: If a VALID or INVALID failure, rnule copy to MCE.

- 7 REVIEW PIP # (CRSRO)

CRSRO SYS.ENC;./Designee Keq'd if other than Valid Success

• Notify Environmental Management if Total Run Time exceeds 260 hours0.00301 days <br />0.0722 hours <br />4.298942e-4 weeks <br />9.893e-5 months <br /> per calendar year for any DIG.

Duke Power Company Document No Catawba Nuclear Station OMP 2-28 Revision No.

024 Diesel Generator Logbook Electronic Reference No.

Information Use CP00941Q

Operations Management Procedure 2-28 (OTG)

Approval Rev 24 Date DUKE POWER COMPAhT CATAWBA NUCLEAR STATION DIESEL GENDMTOR LOGBOOK I. Purpose 1.1. To describe the method used to log all emergency diesel generator start attempts and classify them as a "VALD SUCCESS", "VALKI FAILURE", "INVALID TEST" or "INVALID FALbRF?'.

1.2. To describe the method used to log information related to emergency diesel generator starting. acceleration and loading required as input for various records used for operational analyses and for various reports.

2. References 2.1. Technical Specifications, Sections 3.8.1 Surveillance Requirements 2.2. Regulatory Guide 1.108, Rev. 1, August 1977 2.3. Generic Safety Issue B-56, "Diesel Generator Reliabiiity"

3. Descriptions 3.1. All emergency diesel generator starts, acceleration and loading attempts, whether automatic or manual, shall be documented by this procedure to indicate the performance and reliability of the following emergency diesel generators: lA,2A, 1B and 2B.

3.2. This procedure will provide a chronological list of all emergency diesel generator start attempts for the 1A, 2A, 1B and 28 diesel generators.

3.3. Each emergency diesel generator start attempt will be classified in one of the following categories per this procedure:

A. Valid Success B. Valid - Failure C. hvalid - Test D. Invalid - Failure

Operations Management Procedure 2-28 Page 2 of 8 3.4. Determination of each emergency diesel generator "VALID-FAILURE",LNVALIQ-TEST", or "INVALID-FAILURE" shall be documentcd per this procedure.

3.5. Reasons for "VALID-FAILURE", "INVALID-TEST", or "ENVALID-FAILURE" shall be documented per this procedure.

4. Responsibilities 4.1. The CRSRO is responsible for ensuring that the proper entries are made in the logs for all emergency diesel generators and for routing a copy of the D/G Log Sheets to the MCE Secondary Systems Supervisor if test classification is other than a valid success.

4.2. The CRSRO is responsible for notifying Environmental Management if Total Run Time exceeds 260 hours0.00301 days <br />0.0722 hours <br />4.298942e-4 weeks <br />9.893e-5 months <br /> per calendar year for any emergency diesel generator to comply with station air permit requirements.

4.3. The MCE Secondary Systems Supervisor or designee should review the log monthly.

4.4. The Unit Supervisor shall ensure that the proper entries are made in each log per this procedure for the emergency diesel generators associated with his assigned unit.

4.5. Within 7 days of an Invalid Test, Invalid Failure, or Valid Failure, the MCE Secondary Systems Supervisor or designee should review and sign the D/G Logbook Sheet. This review should verify that the test results are classified correctly, and that all necessary data is documented for a knowledgeable third party to veri% that the classification of the test result is correct.

4.6. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any failure (valid or invaiid) or a Reverse Power Trip, the CRSRO shall ensure a Problem Investigation Process (PIP) is issued, and shall ensure that the PIP number is recorded in the D/G Logbook. The PIP will be utilized to address operability.

4.7. The MCE Secondary Systems Supervisor or designee will ensure that the final determination of the failure type is recorded in the D/G Log%ook.The MCE Secondary Systems Supervisor or designee will ensure the failure is properly classified according to the Maintenance Rule so that required actions are taken.

Operations Management Procedure 2-28 Page 3 of 8 4.8. The MCE Secondary Systems Supervisor or designee will determine the number of valid failures according to NUMARC 8700 as required by the Maintenance Rule, 10CFR50.65.

5. Reporting Requirements 5.1. Notify the MCE Secondary Systems Supervisor of all VALID and INVALID failures by sending him a copy ofthe appropriate DiG Logbook Sheet.

5.2. The Operations Shift SSA will report the run hours for each of the four main diesel generators to EM by the i 5th of the following month. The Operations Shift SSA will report the gallons of diesel fuei burned on Unit I and Unit 2 to EM by the 15th of the following month.

6. Criteria 6.1. A test is considered a .:VALID S U L J S S ? if all of the following conditions are met:

A. The diesel engine starts and accelerates to 441 RPM (198%

SPEED) within 11 seconds.

3. D/G Voltage and frequency shall be at least 4160 =k 420 Volts and 60 5 1.2 Hz within 11 seconds after start signal.

C. The D/G is successfully loaded to 2 2875 KW (50%

continuous rating) and operates at this load for > one hour.

D. DiG shutdown was E t due to an abnormal condition that would have ultimateiy resulted in DiG damage or failure.

6.2. A test is considered an "INVALID= if any of the conditions in Section 6.1 are met due to the following:

A. An intentional shutdown prior to loading or operating for > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and ? 2875 KW that was due to an abnormal condition that would have ultimately resulted in DiG darnage or failure.

D. The testing instrumentation used to meet the acceptance criteria in Section 6.1 fails and all available indications indicated the DiG started and loaded properly.

C. D/G break in runs are considered to be an "INVALID TEST".

Operations Management Procedure 2-28 Page 4 of 8 6.3. A test is considered an "INVALID FAILURE if Ah2 of the conditions in Section 6 .I are met, the test is NQJ an INVALID TEST as defined in Section 6.2, and of the following conditions are met:

A. Operator error.

B. Spurious operation of a trip that is bypassed in the EMERGENCY OPERATING MODE.

C. Malfunction of equipment that is & operativc in the EMERGENCY OPERATING MQDE OF is not part of the defined D/Gunit design.

D. During the process of troubleshooting a specific failure, the same failure reoccurs.

E. The failure occurs on the component on which work was performed during the process of a Functional Check Qut prior to returning the DIG to service following maintenance.

6.4. A test is considered a "VALID FAILURE" if of the following conditions are met:

A. The test can be classified as a VALID SUCCESS, INVALD TEST INVALID FAILURE as defined in Sections 6.1, 6.2, 6.3.

B. The test is intentionally terminated before completion because of an abnormal condition that would have ultimately resulted in D/G damage or failure.

C. Performance o f a cranking and venting procedure leads to the discovery of conditions (e.g. excessive water or oil in a cylinder) that would have resulted in the failure of the D/G unit during opention.

Operations Management Procedure 2-28 Page 5 of 8

7. General Instructions 7.1. Definitions A. "TEST" - Any attempt (manual or by sequencer) to start an emergency diesel generator. This includes safety injection and blackout start attempts by the sequencer.

B. "SUCCESSFUL START" - The D/G starts and accelerates to

> 441 RF'M in less than or equal to 11.O seconds.

C. "EMERGENCY OPERATING MODE" - DIG started and operated by an automatic start signal from the scqnencer with only the emergency trips operative (is. low lube oil pressure.

engine overspeed, generator differential and generator voltage controlled overcurrent).

D. -

"MANUAL OPERATING MODE" D/G started and operated manually from the Control Room or local panel and all DIG trips are operative.

E. "VALID TEST" - Any "VALID FAILURE" or "VALID SUCCESS" as described under Section 6, Criteria.

7.2. The logs are to be a chronological record of each D/Ci start, acceleration and loading attempt and a record of whether each attempt is a valid success, valid failure, invalid test or an invalid failure. A D/G logbook entry will be made for any unsuccessful loading attempt following a successful engine start.

7.3. The logs will be used in developing reports for the Maintenance Rule and for operational analyses of each D/G.

7.4. Separate logs shall be maintained for each of the following D/Gs: 1A, IB, 2A, 2R.

7.5. Each DIG log shall provide information on start attempts and test failurelinvalid test description.

7.6. Sufficient information shall be entered in each log so that the causes for an invalid test or the causes for a test failure can be determined at a later date.

7.7. All entries shall be made with a black ball-point pen.

7.8. All entries shall be printed or written legibly.

Operations Management Procedure 2-28 Page 6 of 8 7.9. A single, straight line shall be drawn through mistakes, errors or changes and initialed by the person making the correction.

7.10. Each entry should he made at the time of the occurrence ofthe event or when knowledge of the event is fist obtained. After an investigation of the problem is made, a further explanation may he needed in the log.

8. DIG Log Entries

1. .I. Actual Start Attempts A. DIESEL GENERATOR - Indicate diesel generator being started. (lA, 2A, lB, 2B)

B. RECORDED BY - The person responsible for filling out the D G Loghock should sign the Logbook.

C. START ATTEMPT NUMBER - Log all start attempts consecutively assigning a number to each start in chronoiogical order of the starts. Start attempt number can be determined from the last Logbook entry.

D. DATE

1. Log the date as follows:

Month/Dayr(ear E. PROCEDURE USED - Indicate which procedure was used to start the D/G by checking the appropriate biock and writing in procedure number if listed.

F. REASON FOR D/G OPERATION - Indicate reason for DIG start by checking the appropriate block and/or writing in the reason.

Example - Trouble Shoot Sequence

6. TYPE OF START - Check "TURBO PRELIJBE" if "TURBO OJL SOL VLV" was open prior to engine start. Check WON-PRELUBE' if it was not. A non-preluhe start should only occur on automatic starts unless otherwise planned.

Operations Management Procedure 2-28 Page 7 of 8 H. TEST CLASSIFICATION - Make determination of Test Type using criteria in Section 6 of this procedure. Indicate test type by checking appropriate block. If "VALID SUCCESS", fill in required acceptance criteria times in seconds and hours.

1. For each "VALD SUCCESS", log:

a. The time in seconds to accelerate to ? 441 RPM (98% speed) and Frequency 60 + 1.2 HZ Gom visicorder trace.

b. The time in seconds to achieve a Voltage > 4160 k 420 volts from the visicorder trace.

c. The time in hours Loaded 2875 KW.

2. For each "INVALID TEST, "INVALID FAILURE" and "VALID FAILURE", fully explain the reason in the section provided. Explanation to include what part of acceptance criteria was a met. Refer to Section 6 for explanation of rest criteria.

3. If other than a "VALID SUCCESS", a copy of this DIG Logbook sheet shall be routed to the MCE Secondary Systems Supervisor or designee for review.

4. The MCE Secondary Systems Supervisor or designee shall review and sign the original DIG Logbook sheet within 30 days.

I. OPERATLVG DATA - Record operating data as follows:

1. D/G Engine Start Date/Time Record date and time of

~

day DIG engine was started.

2. DIG Engine Shutdown DateiTimc - Record date and time of day DIG engine wds shutdown.

3. Total DIG Yearly Run Time in hours, J. REVIEW The Control Room SRO should review for proper entries and sign.

K. PIP # - A PIP is required to be issued if a D/G start attempt is classified as a failure (valid or invalid) or if a Reverse Power Trip occurs. The CRSRO shall ensure that the PPX is recorded.

Operations Management Procedure 2-28 Page 8 of 8 L. SYS. ENG.DESIGNEE The MCE Secondary Systems

~

Supervisor or designee should review the log for completeness and accuracy on a monthly basis.

9. Retention 9.1. All Diesel Generator Logbook information shall remain in the appropriate log or sent to Document Management far retention per NSD 702 Document hhnagement 9.2. Log sheets for test other than those associated with Valid Success should be routed to the MCE Secondary Systems Supervisor for his review and signature.

10. Attachments

10. I. Diesel Generator Logbook 10.2. Index Sheet

Operations Management Procedure 2-28 Page 1 of 1 Attachment 10.1 Diesel Generator Sheet DIESEL GENERATOR RECORDED BY START ATTEMPT NUMBER DATE PROCEDURE USED: REASON FOR DIG OPERATION:

PT/1~2?)IA14350/002A(~) ( D G Operability Test) Scheduled Surveillance 0 OP/1(2)/A/6350/002 (D/G Operation) Opposite Train Inoperable 0 Other, Specify: 0 Functional Verification (Maintenance) 17 Other, Specilj.:

TYPE OF START: TEST CLASSIFICATION: (See OMP 2-28, Sect. 6.)

gl Turbo Prelube gl VALID SUCCESS Nan-Prelube Time required to reach 2 441 RPM (98%

speed) and Frequency 1 60 1.2 Hz sec.

OPERATING DATA: Tinic required: Voltage 1 4160 420 volts SeC.

Time Load 2 2875 KW hrs.

0 INVALID TEST D/G Engine Start DateKime - 0 INVALID FAILURE DIG Engine Shutdown DateKime 0 VALID FAILURE Run Time (hrs)

• Total D/G Engine Yearly Run Time __ IIIX Explain in detail the reason D/G operation was a t a VALID SUCCESS/failed to meet acceptance criteria.

NOTE: If a VALID or INVALID failure, route copy to MCE.

REVIEW PIP # (CRSRO)

CRSRO SYS.ENG.IDeaignee Req'd if other than Vaiid Success

• Notify Environmental Management if Total Run Tinie exceeds 260 hours0.00301 days <br />0.0722 hours <br />4.298942e-4 weeks <br />9.893e-5 months <br /> per calendar year for any DG

Operations Management Procedure 2-28 Page 1 of 1 Attachment 10.2 Index Sheet DIG

Page 1 of 8 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM 4SWADMIN Calculate Low Pressure Service Water Discharge Flow for Liquid Radioactive Release CANDIDATE EXAMINER

Page 2 of 8 CATAWBA lNlTlAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Calculate Low Pressure Service Water Discharge Flow for Liquid Radioactive Release.

Alternate Path:

N/A Facility JPM #:

New KIA Ratinnb):

2.3.11 (2.7D.2)

Task Standard:

Candidate obtains needed data, correctly calculates total discharge flew and determines that the liquid waste release can continue.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator& In-Plant X Perform Simulate __

References:

PT/O/A/4250/011 (Rb Temperature and Discharge Flow Determinations) Revision 037 Candidate: Time Start :

NAME Time Finish:

Performance Ratinn: SAT -UNSAT - Question Grade __ Performance Time ~

Examiner: I NAME SIGNATURE BATE

Page 3 of 8 PBolslEcrui~merstiPsoceduresNeeded:

Each candidate will be provided a copy of PT/Q/N4250/011, appropriate data sheets, and a copy of the LWR permit report. A calculator will be needed to complete the enclosures.

READ TO OPERATOR DiRECTlON TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shail 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:

m Unit 1 is currently performing a liquid waste release from the Waste Monitor building.

Low Pressure Service Water (Rb) Flow transmitter ORLPfjQ80(RL Disch Fiow) and OAC points ClP0903 and C2P5903 (Rk Line A Disch Flow-Hourly Average) are inoperable and have been removed from service.

The RN system is aligned to the WL discharge header.

0 PT/O/8/42~/0'14 (RL Temperature and Discharge Flow Determinations) was last completed at 0700.

• Current time is 1030.

INITIATING CUE:

Calculate total discharge flow using Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/B/Af4250/QI1and determine if adequate flow exists to continue the release per the LMR currently in progress.

Page 4 of 8 START TIME:

EXAMINER CUE: Provide a copy of PT~O/A/4250/0~1 enclosure 13.2, data sheets, and LWR permit report.

EXAMINER NOPE: If asked about YT and YF inputs from RL, provide the following cue.

CUE: "This is chemistry, inputs to Y l and YF were secured at 0645 today."

STEP 4: To obtain Total Rb Supply perform the following: CRITICAL STEP STANDARD: Calculates Total RL supply with the following:

-SAT RL Disch Pressure = Rb HDR PRESS (0RLP5030) + 5.6 psi 67 f = 72.6 psi

-UNSAT psig X 2.311 Wpsig) -+ (577.25 -569 ft) = 178.03 ft Total Discharge Head RL Pump A Flow 30000 gpm (obtained from End. 13.7 for Pump " A )

Bb Pump B Flow 32000 gpm (obtained from End. 13.4 for Pump "B")

RLPumpCFlow OFF gpm Total RL Supply 62000 gpm (A)

EXAMINER NOTE: The following ranges on the flow calculations are acceptable:

RL pump A 28500 to 31500 gpm RL pump B: 30500 to 33500 gpm Total Flow range 59000 to 65000 gprn COMMENTS:

Page 5 of 8 I STEP2: Po obtain Total RN Flow perform the following:

3TANDARD: Calculates Total RN Flow with the following:

CRITICAL STP WN Pump 1B is the only pump in service, Train B meter = 16,500 gpm -SAT RN Pump Train A Flow = (1RNP7520) + (2RNP7520) = 0 gpm RN Pump Train 3 Flow = (lRNF'7510) + (2RNP7510) = 16500gpm

-UNSAT Total RN Flow = 16500 a ~ (B) m COMMENTS:

STEP 3: To obtain Total Cooling Tower Evaporation, perform the following CRITICAL STEP STANDARD: Calculates Total Cooling Tower evaporation using the following:

IF OAC is in service for Unit 1 Cooling Tower evaporation, perform the following -SAT calculations:

(3406.879 - =+19) x 6.837 gp& = 15006.38 gpm Total Tower Evaporation ClPq355 ClAf632 mw -UNSAT I-IF OAC is in service for Unit 2 Cooling Tower evaporation, perfon the following CalCUlatkIn:

(3402.602 ClP1355

- = +19) x 6.837 CIA1632 mw

= 14979.15 gpm Total Tower Evaporation Total Evaporation = 15006.38 + 14997.15 = 29983.53 gpm (C)

EXAMINER NOTE: Due to potential for rounding, a range of 29983.53 +I- 100 gpm is acceptable.

COMMENTS:

Page 6 of 8 STEP 4: To obtain Total RL Disch Flow, perform the following. CRITICAL STEP STANDARD: Calculates Total Cooling Tower evaporation using the following:

I Total RL Sunelv 62000 gprn +

Total RN Flow 16588 RL Disch Total Eviraoration gpm- 29983.53 gpm=

-SAT (W (C)

-UNSAT Total Flow 48516.47 gpm EXAMINER NOTE: Based on previous acceptable values, a range of 45416.47 gpm to 51616.47 gpm is acceptable.

COMMENTS:

Data Recorded by: SAT STANDARD: Candidate initials and enters date and time

-UNSAT 1 COMMENTS:

Compare flow value obtained to required flow per LWR. CRITICAL STEP STANDARD: Determines that LWR required flew is 19000 gprn and that the calculated flow exceeds the required flow and the LWR may continue.

-SAT COMMENTS:

-UNSAT TIME STOP:

Page 7 of 8 (TO BE RETURNEB TO EXAMINER UPON COMPLETION OF TASK)

Unit 1 and 2 Data Sheet for 1030 Unit 1 Generator Megawatts (PID C1A1632) 1231 MW Reactor thermal Power, Best (PID CaP1355) 3406.879 MW Unit 2 Generator Megawatts (PIB C2A1632) 1231 MW Reactor thermal Power, Best (PI5 CZPl355) 3402.602 MW Low Pressure Service Water Status:

Rb Bump A and B in service Lake Wylie Level (ORNP7380) 567 feet RL Header Pressure (ORbP5030) 67 PSI6 Nuclear Service Water Status:

18 RN pump in service RN Pump Train A Flow (1RNP7520) = 0 gpm RN Pump Train A Flow (2RNP7520) = 0 gpm RN Pump Train B Flow (ZRNP7510) = 16500 gpm RN Pump Train B Flow (2RNP7510) = 0 gpm

Page 8 of 8 CANDIDATE CUE SHEET (TO&E RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

e Unit 4 is currently performing a liquid waste release from the Waste Monitor building.

bow Pressure Service Water (RL) Flow transmitter 0RLP5080 (Rb Bisch Flow) and OAC points CIP8903 and C2P0903 (RL Line A Disch Flow-Hourly Average) are inoperable and have been removed from service.

The RN system is aligned to the RL discharge header.

PT/O/N4250/01I(RL Temperature and Discharge Flow Determinations) was last completed at 0700.

• Current time is 1030.

INITIATING CUE:

Calculate total discharge flow using Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/O/N4250/02 1 and determine if adequate flow exists to continue the release per the LWR currently in progress.

Enclosure 13.2 PT!OiA/4250/011 Total Discharge Flow Cakulation Sheet Page I of 2 To obtain Total RL Supply, perform the following:

RL Disch Pressure = RL IIDR PRESS (ORLP5030) + 5.6 psi

.by KL Disch Pressure Lake Elevation Total Discharge Head

( T 2 *h psig X 2.31 1 Wpsig) + (577.25 - 567 ft) = rss8.03 ft RL Pump A Flow RL Pump B Flow RL Pump C Flow Total RL Supply 3oSao mm+ 32a0 gpm+ o ; F ~ \' a m =

I '

6- RPm(A)

,cjL(o&l?i?& (e0S-m- SI.-)

(zcscw- SPSav1 (n-. -6SU)

To obtain Total RN Flow, perform the following:

RN Pump Train A Flow RN Pump Train B Flow Total RX Flow

[(IRNP7520) + (2RNP7520)] [(lRNP7510) +(2RNP751O)]

0 2pm + /&so0 p p m = /6sba gprn(B) 0 To obtain Total Cooling Tower Evaporation, perform the following:

-IF OAC is in service for Unit 1 Cooling Tower evaporation, perform the following calculations:

(jW.4I7S ~ /L%I + 1 9 ) x 6 . 8 3 7 ~ = 1 5 a . 3 g ClP1355 ClA1632 mw Cooling Tower Evaporation 91 OAC is in service for Unit 2 Cooling Tower evaporation, perform the following calculation:

(4qoz.b2- f23j -19)x6.837gp-m= /YQT? {PIP 96-0822)

C2P1355 C2A1632 mw Cooling Tower Evaporation

/SO06 3 6I + /V977./S = Z9993.?? (c)

Unit 1 Unit 2 Total Evaporation Evaporation Evaporation dL@&G& p*=G z.OQy3.s-3

Enclosure 13.2 PT/O/A/4250!01 i Total Discharge Flow Calculation Sheet Page 2 of 2 IF OAC is in service for either both Units, Cooling Tower Evaporation is calculated by the following:

Cooling Tower Evaporation = ((341 IMW) (%Rx Power) + 19 - Gen MW)(6.837 gpm)

Mw Unit 1 Cooling Tower Evaporation ~ ( ( 3 4 1IMW) ( _ _ I + 19 - -) (6.837 m)=

% Rx Power Gen MW Unit 1 (ex. 95%=0.95) MW Evaporation (wm)

Unit 2 Cooling Tower Evaporation =((341 IMWj ( _ _ _ j + 19 - __ j (6.834 gpmJ=

% Rx Power Gen Unit 2 (ex. 95%=0.95) MW Evaporation (urn)

Total Cooling Tower Evaporation = + -

- (C!

Unit 1 Unit 2 Total Evaporation Evaporation Evaporation (@In)

(om) (@m)

• To obtain Total RL Disch Flow, perform the following:

Total Total RL Disch Total RL Supply RN Flow Total Evaporation Flow

V6EI P.*. - :

'rocedure No.

Catawba Nuclear PTfiIA142501011 ievision Nu.

031 RL Temperature And Discharge Flow Determinations I Electronic Reference No.

1 ********** UNCONTROLLEDFQRPRINT * *********

(ISSUED) PDF Format

PTIO/N4250/011 Page 2 of 8 RL Temperature and Discharge Flow Determinations

1. PIIrpQSe 1.1 To verify that the RL total discharge header flow is monitored or manually calculated when the RL. discharge flow instrumentation or the OAC is operable.

1.2 To verify that the RL System temperature is manually obtained when the RL temperature instrumentation is NQT operable.

I .3 To verify the RL. Heat Rise (AT) is calculated and verified below the NPDES limit when both Unit OACs me inoperable.

2. References 2.1 SLC 16.11-2,Table 16.11-2-1.

2.2 Environmental Report Vol. 2, Section 3.4 2.3 South Carolina Department of Health and Environmental Control, Discharge Permit

1. SC0004298 2.4 NSM CN-50136, RL Flow Instrumentation Modification 2.5 SD 3.1.23, Scan Lockout/Out of Service 2.6 CN-1575-1 .O, RL System Flow Diagram

PTIOIN4250/011 Page 3 of 8

3. Time Required 3.1 Manpower 3.1.1 One NLO 3.1.2 OneNCO 3.2 Time 3.2.1 Five minutes to one Hour depending on option used (flow determination) 32 . 2 Thirty minutes (temperature determination) 3.2.3 One hour and 30 minutes (heat rise calculation) 3.3 Frequency 3.3.1 Prior to an actual release and every four hours during the release when RL discharge flow instrumentation or the BAC is inoperable.

3.3.2 Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when RL discharge flow instrumentation or the OAC is inoperable.

3.3.3 Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when RL temperature instnnnentation or either unit OAC is inoperable.

4. Prerequisite Tests None

5. Test Equipment Calibrated Keithly 872 Digital Thermometer OR Calibrated Fluke 5 1 or 52 Digital Thermometer with type "K" immersible style probe

6. Limits and Precautions None

7. Required Unit Status None

PTiO/A/4250/011 Page 4 of 8

8. Prerequisite System Conditions

--- 8.1 Flow exists through the RL System.

8.2 Both OACs are inoperable or at least one of the following is inoperable:

• RL discharge header flow instrumentation RL intake temperature instrumentation e RL discharge temperature instrunrentation OACpointsClP1515 (RLDelta~-HourlyAverage)andC2P1515(RLDeltaT-Hourly Average)

9. Test Method 9.1 The RL discharge header flow will be determined and recorded using various RL,RN and RC instrumentation when the discharge header or the OAC flow monitoring instnunentation is inoperable.

9.2 The FU System temperature will be obtained (using a calibrated thermometer) and recorded when the RL System temperature indication is inoperable.

9.3 The KL heat rise (AT) is calculated from the manually determined values of RL temperature and discharge flow. A comparison is then made to the WISES limit and appropriate action taken.

PTiO/A/4250/011 Page 5 of 8

10. Data Required 10.1 E R L flow instrnments are inoperable, complete the following enclosures as required:

Enclosure 13.2 (Total Discharge Flow Calculation Sheet)

Enclosure 13.3 (OAC Point Total RL Discharge Flow Calculation) 10.2 If RL. intake temperature instruments inoperable, complete Enclosure 13.4 (KL Intake Temperature Determination) as required.

10.3 If FA discharge temperatwe instruments inoperable, complete Enclosure 13.5 (RL Discharge Temperature Determination) as required.

10.4 If both OACs are inoperable, complete the following enclosures as required:

• 13.1 (RL Discharge Flow Determination) 13.2 (Total Discharge Flow Calculation Sheet) 13.3 (OAC Point Total RL Discharge Flow Calculation)

• 13.4 (R% Intake Temperature Determination)

• 13.5 (RL Discharge Temperature Determination) 13.6 (EX.System Heat Rise (AT)Calculation) 10.5 If Enclosure 13.1 JRL Discharge Flow Determination) is being performed and there is an RL or RN flow change, complete Enclosure 13.2 (Total Discharge Flow Calculation Sheet) and log in Autolog.

PT/o/A/4250/011 Page 6 of 8

11. Acceptance Criteria 11.1 When both OACs are inoperable or R discharge header flow instrumentation is inoperable, the RL discharge flow is determined and recorded as follows:

11.1.1 If ORLP5080 (KL Disch Flow) is inoperable, prior to an actual relcase and every four hours during the release. (SLC 16.11-2) 11.1.2 Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (SLC 16.11-2) 11.2 When Enclosures 13.4 (RL Intake Temperature Detcrmination) and 13.5 (RL Discharge Temperature Determination) are being performed, the RL System temperature is determined and recorded once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (NPBES) 11.3 When Enclosure 13.6 (RL System Heat Rise (AT) Calculation) is being performed, the RL Heat Rise (AT) is calculated once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and action is taken to correct over limit conditions. Limits: AT 5 10.0'F (April-Scpt.) 5 14.O"F (0ct.-Mar.) (NPDES)

12. Procedure 12.1 Complete the appropriate enclosures based on the foliowing conditions:

NOTE: For the following QAC points to be considered inoperable, they must be inoperable on Unit 1 and Unit 2 OAC.

s _ 12.1.1 E any ofthe following components are inoperable, perform Enciosure 13.1 (RL Discharge Flow Determination):

12.1.1.1 ORLPSOXO (RL Disch Flow Summer)

OR ORLFTSOSO (RL Line A Disch Flow)

OR ORLFTS930 (RL Line B Disch Flow)

OR C1P0903 (ELine A Disch Flow-Hourly Average) AM) C2POYO3 (RL Line A Disch Flow-Hourly Average)

OR C1P0904 (RL Line B Disch Flow-Hourly Average) AND C2P0904 (RL Line B Disch Flow-Hourly Average)

PT/O/N4250/011 Page 7 of 8

__ 12.1.2 Ip the following RL intake tcmperature instrument OAC point is inoperable, complete Enclosure 13.4 (RL Inntake Temperature Determination).

ORLTT7420 (RL Intake Temperature)

• ClP1521 (Low Press Service Wtr Inlet Temp 11. hvg.) AND C2P1521

~

(Low Press Service Wtr Inlet Temp - Hr. Avg.)

12.1.3 any of the following RL discharge temperature instruments OR QAC points are inoperable, complete Enclosure 13.5 (RL. Discharge Temperature Determination).

6 ORLTT5060 (RL Line h Disch Temp)

ORLTT5070 (RL Lime B Disch Temp) 0 -

C1P1376 (RL Line A Discharge Temp # 1 Hourly Avg) ANB C2P1376 (RL Line A Discharge Temp #1 Hourly Avg)

~

0 ClP1377 (RL Line B Discharge Temp #1 - Hourly Avg) AND C2P1377 (RL Line B Discharge Temp #1 - Hourly Avg) 12.1.4 both Unit OACs are out of service, complete Enclosure 13.6 (RL System Heat Rise (AT) Calculation).

PT/&A/4250/011 Page 8 of 8 12.2 Evaluate the acceptance criteria by performing one of the following:

__ 12.2.1 Verify the acceptance criteria specified in Section 11 is met.

OR

__ 12.2.2 the acceptance criteria are pI'oT met, perform the following:

gl Notify the UnitWCC SRO that the acceptance criteria is NOT met.

_ _I_ _

UniWCC SRO Contacted Date Time 17 Initiate a PIP to document the test failure.

El Document all issues on a procedure discrepancy sheet.

Kl Notify the Enviromental Compliance Engineer for determination of repottability.

- 12.3 my discrepancy is noted during the performanse of this test that does NOT keep the test from meeting the acceptance criteria, it shall be given to the UniWCG SRO for evaluation via a discrepancy sheet.

-- 12.4 Submit PT/O/A/425O!Oi 1 (RL Temperature and Discharge Flow Determinations) to the UnitlWCC SRO.

13. Enclosures 13.1 KL Discharge Flow Determination 13.2 Total Discharge Flow Calculation Sheet 13.3 OAC Point Total RL Discharge Flow Calculation 13.4 Intake Temperature Determination 13.5 RL Discharge Temperatwe Determination 13.6 RL System Heat Rise (AT) Calculation 13.7 RL Pump Head Capacity Curves

Enclosure 13.1 PT/O/IV4250/01 I RL Discharge Flow Determination. Page 1 o f 4

1. Procedure 1.1 To calculate RL discharge flow, complete the following steps:

1.1.1 ORLP5080 (RL Disch Flow) is capable of terminating WL discharge when FtL discharge flow decreases below an LWR setpoint, place ORLP5080 (RL Disch Flow) in TSAIE.

1.1.2 E a release is being made ORLP5080 (RL Disch Flow) is inoperable, calculate the RL discharge flow every four hours and after an RL RN discharge flow change.

1.1.3 flow is NOT being calculated every four hours per Step 1.1.2, calculate the RL discharge flow rate every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a f w an RL OR RN discharge flow change.

1.1.4 a calculation is required either of the following OAC points are inoperable, perform the following steps:

• ClPO903 (RL Line A Discharge Flow - Hourly Average) AND C2P0903 (RL Line A Discharge Flow - Hourly Average)

OR ClP0904 (RL Line B Discharge Flow - Hourly Average) AND C2P0904 (RL Line B Discharge Flow - Hourly Average) 1.1.4.1 Ensure Chemistry has secured inputs to YT AND YF from RL for a minimum of 10 minutes. {PIP 96-0822)

NOTE: e If 0RNg7388 (Lake WyIie level) is unavailable, RN pit level indication may be used as lake Ievel indication if the RN pit is aligned to the lake.

0 RN Pit A indications are 1RNP7400 (1MC9), 2RNP7400 (2MC9), or QAC point CIA1453 RN Pit B indications are 1RNP7370 (1MC9), 2RNP7370 (2MC9), or OAC paint CIA1459 1.1.4.2 Calculate and record "Total Discharge Head" on Enclosure 13.2 (TotaI Discharge FIow Calculation Sheet).

1.1.4.3 Calculate and record the individual "RL Pump Flow" for the operating RL pumps on Enclosure 13.2 (Total Discharge Flow Calculation Sheet). [Refer to Enclosure 13.7 (RL Pumps Head Capacity Curve) for pump capacity curves.]

Endosure 13.1 PT/o/A/4250/011 RL Discharge Flow Determination. Page 2 of 4 I .I .4.4 RM discharge is aligned to the RL discharge header, record the operating RN pump(s) discharge flow on Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

1.1.4.5 Calculate "Total RL Disch Flow" as follows on Enclosure 13.2 (Total Discharge Flow Calculation Sheet):

A. Record "Total RL. Supply" B. Record "Total RN Flow".

C. Calculate "Total Evaporation".

D. Calculate and record "Total RL Disch Flow".

1.1.4.6 Inform Chemistry they may resume any inputs secured in Step 1.1.4.1. {PP 96-0822) 1.1.4.7 Unit 1 OAC is operable AND RL flow is through both headers, insert a value for the foliowing OAC points using the Insert Value application:

A. Insert value for OAC point ClP0903 (IU. Line A Discharge Flow - Hourly Average) of 95 the "Total RL Disch Flow" obtained from Enclosure 13.2 (Tot31 Discharge Flow Calculation Sheet).

B. Insert value for OAC point C1P0904 (RL Line B Discharge Flow - Hourly Average) of % the "T~taalRL Disch Flow" obtained from Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

1.1.4.8 Unit 2 OAC is operable AND RL flow is through both headers, insert a value for the following OAC points using the Insert Value application:

A. Insert value for OAC point C2PO903 (RL Line .4Discharge Flow - Hourly Average) af % of the "Total RL Disch Flow" obtained from Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

B. Insert value for OAC point C2PO904 (RL Line B Discharge Flow Hourly Average) of % the "Total RL Disch Flow"

~

obtained from Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

Enclosure 13.1 PTIQIAI~ZSOI~I~ 1 RL Discharge Flow Determination. Page 3 of 4 1.1.4.9 Unit 1 OAC is operable RL flow is through Header A only, insert a value for the following OAC points using the Insert Value application:

A. Insert value for OAC point ClP0903 (RL Line A Discharge Flow - Hourly Average) of Total RL Disch Flow obtained from Enclosure 13.2 (Total Discharge Flow Cdculation Sheet).

B. Insert a value of 0 far OAC point ClPO904 (RL Line B Discharge Flow - Hourly Average).

1.1.4.10 Unit 1 OAC is operable AND RL flaw is through Header B only, insert a value for the following OAC points using the Insert Value application:

A. Insert a value of 0 for QAC point ClPO903 (RL Line A Discharge Flow - Hourly Average).

B. Insert a value for OAC point ClW904 (RL Line B Discharge Flow Hourly Average) of Total RL Disch Flow obtained

~

fiom Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

1.1.4. I1 E Unit 2 OAC is operable RL flow is through Header A only, insert a value for the following QAC points using the Insert Value application:

A. Insert a value for OAC point C2P0903 (RL Line A Discharge Flow - Hourly Average) of Total RL Disch Flow obtained from Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

B. Insert a value of 0 for OAC point C2P0904 (RL Line 3 Discharge Flow Hourly Average).

I. 1.4.12 Unit 2 OAC is operable AND RL flow is through Header 3 only, insert a value for the following OAC points using the Insert Value application:

A. Insert a value o f T for OAC point C2P0903 (RL Line A Discharge Flow - Hourly Average).

B. Insert a value for OAC point C2P0904 (Rb, Line B Discharge Fiow - Hourly Average) ofTota1 RL. Disch Flow obtained from Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

Enclosure 13.1 PTI~IA/4250/011 RL Discharge Plow Determina6on. Page 4 of 4

1. I .4.13 WHEN the following OAC points are restored to operable, perform the foilowzing steps:

ClP0903 (RL Line A Discharge Flow - Hourly Average)

• C2P0903 (RL Line A Discharge Flow - Hourly Average)

CEP0904 (RL Line B Discharge Flow Hourly Average)

~

C2P0904 (RL Line B Discharge Flow Hourly Average)

- A. E a value was inserted for OAC point Cilp0903 (RL Line A Discharge Flow - Hourly Average), remove the inserted value from Unit 1 OAC.

__ B. @ a value was inserted for OAC point ClP0904 (KL Line E Discharge Flow - Hourly Average), remove the inserted value from Unit I OAC.

- C. E a value was inserted for OAC point C2P0903 (Rb, Line A Discharge Flow - Hourly Average), remove the inserted value from Unit 2 OAC.

- D. a value was inserted for OAC point C2P0904 (RL Line B Discharge Flow - Hourly Average), remove the inserted value from Unit 2 OAC.

1.1.5 a calculation is required ANB the following conditions exist, complete Enclosure 13.3 (OAC Point Total RL Discharge Flow Calculation).

e At least one ofthe following OAC points are operable:

0 CIP0904 (RL Line B Discharge Flow - Hourly Average) e C2P0904 (RL Line E Discharge Flow - Hourly Average)

AND o At least one of the following OAC points are operable:

ClP0903 (RL Line A Discharge Flow - Hourly Average) a C2P0903 (RL Line A Discharge Flow - Hourly Average) 1.1.6 WHEN any affected RL system flow instrumentation is returned to service, evaluate status. Refer to Section 12.

Enclosure 13.2 PT/OlAA250/011 Total Discharge Flow Calrulation Sheet Page I of2 0 To obtain Total RL. Supply, perfom the following:

RL Disch Pressure = F& HDR PRESS (ORLP5030) + 5.6 psi RL Disch Pressure Lake Elevation Total Discharge Head

( psig X 2.31 1 fb'psig) + (571.25 - fij = ft RL Pump A Flow RL Pump B Flow KL Pump C Flow Total RL Supply e D m +e D mfA m = ----Qrn (A)

To obtain Total RN Flow, perform the following:

RN Pump Train A Flow RN hunp Train B Flow Total RN Flow

[(lRNP7520) + (2RNP7520)J [(1RhT7510) t (2RNP751Q)I gpm + gpm = pm(B) 0 To obtain Total Cooling Tower Evaporation, perform the following:

IF OAC is in service for Unit 1 Cooling Tower evaporation, perform the following calculations:

( +19) x 6.837 =

ClPI355 CIA1632 mw Cooling Tower Evaporation IF OAC is in service for Unit 2 Coolhg Tower evaporation, perform the foilowing calculation:

( +19) x 6.837 gpn~= {PIE' 96-0822)

C2P1355 C2A1632 mw Cooling Tower Evaporation

+ -

(C)

Unit 1 Unit 2 Total Evaporation Evaporation Evaporation

Enclosure 13.2 PTf~/8/4250/011 Total Discharge Flow Calculation Sheet Page 2 of 2 O K is NOT in service for either both Units, Cooling Tower Evaporation is calculated by the following:

Cooling Tower Evaporation = ((341 Ih.iw) (%Rx Power) + 19 Germ MW)(6.837 MW Unit 1 Cooling Tower Evaporation =((a41 IMW) ( __ ) t 19 - __ ) (6.834 g&=

% Rx Power Gen MW Unit 1 (ex. 95%=0.95) MW Evaporation (am)

Unit 2 Cooling Tower Evaporation =((3411MW) (-) f 19 -)

~ (6.837 &=

% Rx Power Gen MW Unit2 (ex. 95%=0.95) MW Evaporation (mm)

Total Cooling Tower Evaporation = f _.

(C) unit 1 Unit 2 Total Evaporation Evaporation Evaporation (mw (mm) (mm) e To obtain Total RL Disch Flow, perform the following:

Total Total RL Disch Total RL Supply RN Fiow Total Evaporation Flow Data Recorded By Operatorhitials Datemime Data w By Operatorhitials DatdTime

Enclosure 13.3 PT/O/A/4250/011 OAG Point Total RL Discharge Flow Page 1 of 1 Calculation

1. Procedure

_p I. 1 Ensure Chemistry has secured inputs to YT and YF from RL for a minimum of 10 minutes

{PIP 96-0822)

__ I .2 Perform the following calcu1ation:

-f -

ClP0903 CIPO904 Total RL Disch Flow OR OR C2P0903 C2P0904 Data Recorded by Operatorhitiah DatdTime Data W By Opemtorhitials DateEirne

_s 1.3 Inform Chemistry they may resume any inputs secured in Step 1.1.

Enclosure 13.4 PT/O/N4250/011 RL Intake Temperature Determination Page I of 2

1. Procedure 1.1 both the OAC points for WL intake temperature ClP1521 (Low Press Service Wtr Inlet Temp - Hr Avg) AND C2P1521 (Low Pressure Service Wtr Intake Temp - Kr Avg) their input device ORLTT7420 (RL Intake Temperature) is inoperable, perform the following steps once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the indication is inoperable:

1.1.1 ORLTT4420 (RL Intake Temperature) is operable. obtain reading from chart recorder ORLCR5060 point (1) (RE Intake Temp (OF)).

1.1.2 E ORLTT7420 (RL Intake Temperature) is inoperable, perfomi the following:

NOTE: Temperature read out should be allowed to stabilize before measurement is recorded.

1,1.2.I Using a calibrated thermometer, obtain the RL intake temperature by grab sample (sample bottle suspended from handrail by rope at NW comer of RL Intake Structure).

1.1.2.2 Return sample bottle to lake. (Ensure sample bottle is totally submerged.)

1.1.a Record the intake temperature on the attached RL INTAKE TEMPERATURE DATA SHEET.

1.1.4 E OAC is operable, insert the temperature for the current date recorded on the attached RL INTAKE TEMPERATURE DATA SHEET for both of the following points using the Insert Value (INSERT) application:

ClP1521 (LQWPress Service Wtr Inlet Temp - IIr Avg)

C2P152 1 -

(LowPress Service Wtr Inlet Temp Kr Avg) 1.1.5 WHEN RL intake temperaturc OAC point its input device is restored to operable, remove any inserted values from the following OAC point(s):

__ o ClP1521 (Low Press Service Wtr Inlet Temp - Hr Avg)

- C2P1521 (bow Press Service Wtr Inlet Temp Hr Avg)

Enclosure 13.4 PTIOIA/4250/011 RI, intake Temperature Determination Page 2 of 2 RL INTAKE TEMPERATURE DATA SHEET

Enclosure 13.5 PT/~/AI4250/011 RL Discharge Temperature Determination Page 1 o f 4

1. Procedure 1.1 OAC point ClPl376 (RL Line A Discharge Temp #I -Hourly Avg) 62PI376 (RL Line A Discharge Temp #1 Hourly Avg)

~ input device ORLTT5060 (RL Line A Disch Temp) are inoperable, perform the following steps once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the indication is inoperable:

1.1.1 Using a calibrated thermometer, obtain the RL line A discharge temperature as follows:

1.1.1.1 Obtain the key for RL Discharge Structure Gate 22A from Environmental Chemistry (Water Chemistry Building).

1.1.1.2 At the RL discharge structure, obtain the RL line A discharge temperature as follows:

A. Raise the access cover on the structure (when facing the lake A train is on the left).

E. Lower the sample bottle into the discharge pipe.

C. AlIow the sample bottle to remain in the pipe for one minute.

NOTE: Temperature readout should be allowed to stabilize before the measurement is recorded.

D. Raise the sample bottle and measure the temperature using the thermometer.

1.1. I .3 Record the "Discharge A Temp" on the attached RL DISCHARGE TEMPERATURE DATA SHEET.

1.1.1.4 Ensure RL Discharge Structure Gate 22A is closed.

1.1.1.5 Ensure RL Discharge Structure Gate 22A is lacked.

1.1.1.6 Return the key to Environmental Chemistry.

1.1.2 OAC is operable, insert the current temperature value from attached RL DISCHARGE TEMPERATURE DATA SHEET for both of the following OAC points using Insert VaIue (INSERT) application:

• ClPI346 (RLLine A Discharge Temp #I - Hourly Avg) 0 CZP1376 (RE Line A Discharge Temp # I - Hourly Avg)

Enclosure 13.5 PT/O/A/4250/011 RL Discharge Temperature Determination Page 2 o f 4 1.1.3 the following OAC points input device ORLTT5060 (RL Line A Disch Temp) are restored to operabie, remove the inserted value from the following OAC point(s):

__

• C 1P 1376 (RL Line A Discharge Temp # 1 - Hourly Avg)

__ C2P1376 (RL Line A Discharge Temp #I ~ Hourly Avg) 1.2 OAC point ClP1337 (Rk Line B Discharge Temp #I -Hourly Avg), AND C2PI377 (RL Line B Discharge Temp # l - Hourly Avg) input device ORLTT5070 (RL Line B Disch temp) are inoperable, perfom the following steps once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the indication is inoperable:

1.2.1 Using a calibrated thermometer, obtain the Rk line B discharge temperature as follows:

E 2.1.1 Obtain the key for RL Discharge Structure Gate 22A from Environmental Chemistry (Water Chemistry Building).

1.2.1.2 At the RE Discharge Structure, obtain the RE line B discharge temperature:

A. Raise the access cover on the structure (when facing the lake I3 train is on the right).

B. Lower the sample bottle into the ducharge pipe.

C. Allow the sample bottle to remain in the pipe for one minute.

I NOTE: Temperature readout should be allowed to stabilize before the measurement is recorded. I D. Raise the sample bottle and measure the temperature using the thermometer.

1.2.1.3 Record the "Discharge B Temp" attached RL DISCHARGE TEMPERATURE DATA SHEET.

1.2.1.4 Ensure Rh. Discharge Structure Gate 22A is closed.

1.2.1.5 Ensure RL Discharge Structure Gate 22A is locked 1.2.1.6 Return the key to Environmental Chemistry.

Enclosure 13.5 PT/&A/4250/011 RL Discharge Temperature Determination Page 3 of 4 1.2.2 OAC is operable, insert the current temperature value from attached liL DISCHARGE TEMPERATURE DATA SKEET for both of the following OAC points using Insert Value (INSERT) application:

ClP1377 (RL Line B Discharge Temp #1 - Hourly Avg)

C2P1377 (RL Line B Discharge Temp #I - Hourly Avg) 1.2.3 the following OAC points input device ORLTT5070 (RL Line I3 Disch Temp) are restored to operable, remove the inserted value from the following OAC point(s):

-0 ClPI377 (WL Line B Discharge Temp #1 Hourly Avg)

~

__ e C2P1377 (RL Line B Discharge Temp #1 - Hourly Avg)

Enclosure 13.6 PT/O/A/4250/011 RL System Heat E s e (AT) Calculation Pagc 1 of 2 NOTE: Completion of this enclosure is required only when both Units OAC is inoperable for more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and then once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until one OAC is restored operable.

1. Procedure 1.1 Determine the variables of the calculation as follows:

1. I .1 Complete Enclosure 13.1 (RL Discharge Flow Determination).

1.1.2 Complete Enclosure 13.4 (RL Intake Temperature Determination).

1.1.3 Complete Enclosure 13.5 (RL Dischargc Temperature Determination).

1.2 Calculate RL System Heat Rise 1.2.1 Record RL Discharge Temperatures from Enclosure 13.5 (RL Discharge Temperature Determination).

A Train "F (RLADT)

B Train O F (RLBDT) 1.2.2 Record RL Discharge Flows from Enclosure 13.2 (Total Discharge Flow Calculation Sheet).

A Train !Pm (RLAF)

B Train gpm (RLBFJ 1.2.3 Record RL Make Temperature from Enclosure 13.4 (RL Intake Temperature Determination).

O F (KIT) 1.2.4 Calculate RL Heat Rise (AT).

( X ) + L X 1 -

EADT RLAF RLBDT RLRF -- I "P

( + 1 RLIT RL Hcat Rise (AT)

RLAF RLBF 1.3 Determine whether RL Heat Rise (AT) Step 1.2.4 is less than limits listed RL Heat Rise (AT) 5 10.O°F (Apr. 1 - Sep. 30) 5 14.O"F (Oct. I -Mar. 31)

Enclosure 13.6 PT/~/A/4250/011 RL System Neat Rise (AT) Calculation Page 2 of 2 NOTE: Cooling Tower blowdown is the largest variable heat load on the RL S y s t e m s 7

___ 1.4 the RL Heat Rise (AT) is greater than the limits of Step 1.3 (NPDES Permit), notify the Operations Shift Manager that a piant heat load reduction on the RL System is required.

-1.5 Make 2 copies of this enclosure and:

Attach one copy to the Switchboard Log,page 10

• Route one copy to the Environmental Management Manager (CN04EM).

P m h 95 e

0 0

m 0

M N

0 0

N st r

0 0

F Q

UJ

Y 0

m A

-+

t Y

5 cu 0 Y PI Y

.^

I I I I 0 0 0 0 0 0

m 8 8 10 r

0 T

isd tsm h 5

isN M x

?i r E 0

0 m

0 M

N 0

0 N

0

? -

0 0

0 In

System:

Job Measures

Page 1 of 16 CATAWBA INITIAL. LICENSE EXAMINATION JOB PERFORMANCE MEASURE Respond to Inadvertent Dilution While Shutdown CANDIDATE EXAMINER

xxxxxxxxxx Applicants:

Page 2 of 16 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

~Task:

Trip the reactor and establish boration flow from the FWST per AQ/I/A/5500/13 (Boron Dilution), Case 8 1 (Boron Dilution While Shutdown).

Alternate Path:

YES Facilitv JPM #:

Modifid from NV-1I 9 KIA Ratinafs):

004 A2.06 (4.2/4.3)

Task Standard:

The reactor is tripped and boration from the FWST is initiated per AP/l/N5500/13, Case II.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator in-Plant - Perfom X Simulate -

References:

AQ/I/A/5500/13 (Boron Dilution), Case II (Boron Dilution While Shutdown) Revision 15 Validation Time: 11 min. Time Critical: No

---

__s_________________-------------------------------------------

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ _ ~ ~ _ ~ ~ _ ~ ~ s s s _ _ _ _ _ _ _ _ - - - - - - _

Candidate: Time Start :

NAME Time Finish:

Performance Ratina: SAT -UNSAT - Question Grade - Performance Time -

Examiner: I NAME SIGNATURE BATE COMMENTS

Page 3 of 16 SIMULATOR SET-UP SHEET

1. Reset to any Cooldown IC Set

2. Run simulator and acknowledge annunciators.

3. lnsert VLV-NV044F, (NV238A Failed Position) Severity bevel = 0.

4. Close Reactor Trip Breakers and withdraw Shutdown Banks A through E.

5. Ensure 1NV153A in Demin position.

6. Insert MAL NVO14A, (Boric Acid Pump 1A Failure).

7. Insert MAL NV0443,(Boric Acid Pump 4B Failure).

8. Insert OVR - NVQ47A(BlA Xfer Pmp 9B §el Off Light); Vafue = OFF

9. Place red rag sticker on 1B Boric Acid Transfer Pump.

I O . Insert OVR NVO4 1D (Boric Acid Transfer Pump On Position; Value = OFF

11. lnsert BVR-NVQ47B[BlA Xfer Pmp 1B Sel On Lt - OFF

12. Ensure Train A and Train B BQMS setpoints are updated so that BDMS will NOT actuate during the performance ofthis JPM.

13., MAL-NC001 (Variable RCS Boron Concentration), Set Malfunction Value = 1300, Ramp = 60 sec. 0 time delay, Trigger = 7 14.Freeze simulator, write a snap and fill in the temperature of this setup in the Initiating Cues on pages 4 and 16.

SIMULATOR OPERATOR INSTRUCTIONS:

I.Reset to IC 217

2. Ensure train A and train B BDMS setpoints are updated so BDMS will NOT actuate during this JPM.

3. When instructed by the examiner, activate Trigger 1 to begin dilution.

Page 4 of 16 Toois/Eauipm%nffPraced~resNeeded:

Have enough copies of AQ/I/N55Q0/13revision 15 available for each candidate.

READ TO OPERATOR DiRECTlON 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 CONDITIQNS:

Unit 1 is in Mode 3 preparing to start up.

Boric Acid Transfer Pump 1B is tagged out for maintenance iNlTlATiNG CUE:

You are the Operator at the Controls. It has been determined that source range counts and BDMS counts are increasing unexpectedly. The SRO instructs you to address the situation using AQ/13 Case B

I (Boron Dilution While Shutdown).

Page 5 of 16 START TIME:

STEP 1: Obtain a copy of the appropriate procedure.

-SAT STANDARD: Operator locates API/A/5500/13.

EXAMINER CUE: When the candidate locates AQll/A15500/13, hand himlher a clean copy of Case 2 and tell himlher that it is current and -UNSAT complete.

COMMENTS:

STEP 2: Verify boron dilution event - IN PROGRESS. (Step 1 .)

STANDARD: Candidate recalls from the initiating cue that count rate is increasing, -SAT or checks count rate increasing on source range meters or Boron Dilution Mitigation System on MC-5 to verify boron dilution event In progress.

-UNSAT

• • CUE: Count rate is increasing on the source range meters and on the Boron Dilution Nlitlgafion System.**

COMMENTS:

• • Italicized Cues Are To Be Used Onry I f JPM Performance Is Being Simulated.

Pme 6 of 16 STEP 3: Verify reactor trip: (Step 2.) -SAT All red bottom lights - LIT All reactor trip and bypass breakers - OPEN S/R counts - STABLE or DECREASNG -UNSAT STANDARD: Candidate determines that the shutdown banks are withdrawn by any the following indications and transitions to Step 2 RNO column.

Rod bottom lights NOT lit on Shutdown Banks A through E.

e Red CLOSED light for reactor trip breaker l a is LIP Red CLOSED light fur reactor trip breaker 1B is LIT

• • CUE: Rod bottom lights for shutdown banks A through E are DARK. The Red CLOSE light for reactor trip breaker 1A is LiT and the Green OPEN light is DARK. The Red CLOSE light for reactor trip breaker I S is 6lT and the Green OPEN lfght is DARK. **

COMMENTS:

STEP 4: Manually trip the reactor. (Step 2. RNO) CRITICAL STEP STANDARD: Candidate rotates the handles for reactor trip breakers A and I3 to the OPEN position and verifies all r d bottom lights LIT The candidate -SAT I transitions to AlER Step 3.

• • CUE: The handle for reactor trip breaker f A has been rotated to the -UNSAT OPEN position. The Green QPN light is LIT and the Red CLOSED iight is DARK. The handle for reactor trip breaker I S has been rotated fo fhe OPEN position. The Green OPEN fight is LIT and the Red CLOSED right is DARK. The rod boftwm lights for shutdown banks A through B are LIT.**

COMMENTS:

• • italicized Cues Are To Be Used Only I f JPM Performance Is Being Simulated.

Page 7 of 16 I SKEP5: WHEN manpower AND time permits, THEN - REFER TO A19/1/8/5500/05 (Reactor Trip or Inadvertent S/I below P-l l).(Step 3.) -SAT STANDARD: No action required by the candidate.

EXAMINER CUE: Another operator will refer to AP105. -UNSAT COMMENTS:

STEP 6: Verify core alterations - IN PROGRESS. (Step 4.) -SAT STANDARD: Candidate determines from the Initiating Cue that core alterations are not in progress and goes to Step 6.

-UNSAT COMMENTS:

STEP 7: Evacuate personnel from reactor building using the following: (Step 6.)

XANDARP): Candidate actuates the Containment Evacuation Alarm (1MC-1) and -SAT makes a plant page.

• • CUE: The Red ON pushbutton for the Unit 1 Cont Evac Alarm has -UNSAT been depressed. The RED ON light is LIT, and the GREEN OFF ljght is DARK. Announcement is heard over the paging system. **

COMMENTS:

• • Stalicized Cues Are To Be Used QnIy If JPM Performance Is Being Simulated.

Page 8 of 16 STEP 8: Stop any dilutions in progress as follows: -SAT Place NC MAKEUP CONTROL switch to STOP. (Step 73.)

STANDARD: Candidate positions the NC MAKEUP CONTROL switch to STOP.

-UNSAT

• • CUE: The NC MAKEUP COWR0Lswitch is in the STOP position **

COMMENTS:

STEP 9: Place both resctor makeup water pumps to OFF. (Step 7.b)

-§AT STANDARD: Candidate places the switch for reactor makeup water pump I A in the OFF position and verifies the Green OFF light is LIT and the Red ON light is DARK. Candidate places the switch for reactor makeup water pump 1B in the OFF position and verifies the Green OFF light is LIT -UNSAT and the Red ON light is DARK.

• • CUE: The switch for reactor makeup water pump 1A is in the OFF position. The Green OFF light is LIT and the Red ON light is DARK. The switch for reactor makeup water pump I B is in the OFF position The Green OFF light is LIT and the Red ONlight is DARK.**

COMMENTS:

w/talicized Cues Are TOBe Used Only If JPM Performance Is Being Simulated.

Paae 9 of 16 STEP 10: Isolate NV Demineralizers as follows: (Step 7.c.)

1) Place 1NV-153A (Letdn Hx 0th 2-Way Wv) in the VCT position -SAT

2) Ensure the following valves - CLOSED:

1NV-353 8, 364 (Mixed Bed Demin 1A Isol) CLOSED INV-368 & 379 (Mixed Bed Demin I B Isol) CLOSED -UNSAT STANDARD: Candidate performs the following:

Positions 1NV-153A to the VCT position.

Depresses CLOSE for 1NV-353 8,364 and verifies green CLOSED light lit.

Checks 1NV-368 8, 379 green CLOSED light lit.

• • CUE lNV 153A is in the VCT position. The Green CL0SEDlight for INV-368 and 379 Is LIT and the Red QPEN light is DARK. The CL0SEDpushbutfon for 1NV 353 and 364 has been depressed.

The Green CLOSED light for is LIT and the Red QPEN light is DARK. The Green CLOSED right for INV 368 and 379 is LIT and fhe Red OPEN light is DARK.**

COMMENTS:

• • ltalicEzed Cues Are To Be Used Qnry Ef JPM Performance Is Being Simulated.

Pam? 10 of 16 STEP 1-I: Ensure proper BDMS operation as follows: (Step 8.)

Verify at least one of the following alarms LIT: (Step 8.a.) -SAT

• 1AD-2, El2 TRAIN A SHUTDOWN MARGIN ALARM OR 0 IAD-2. F/2 TRAIN B SHUTDOWN MARGIN ALARM -UNSAT STANDARD: Candidate verifies the following alarms are DARK and transitions to step

83. RNO. Candidate determines no action is required and goes to Step 9 NER.

• IAD-2, E12 TRAIN A SHUTDOWN MARGIN ALARM IAD-2. F/2 TRAIN B SHUTDOWN MARGIN ALARM

• • CUE: Alarms IAD-2, Y 2 TRAIN A SHUTDOWN MARGlN ALARMand IAD-2, F/2 TRAIN B SHUTDOWN MARGlN ALARWare DARK.**

COMMENTS:

STEP 12: Initiate boration of the NC system as follows: (Step 9.)

Ensure one NV pump - ON. (Step 9.a.) -SAT STANDARD: Candidate verifies the Red ON light lit for NV pump 1A is LIT and the Green OFF light is DARK and pump amps are indicated.

-UNSAT

• • CUE: The Red ON Iight lit for NVpump I A is LIT and the Green OFF light is DARK. Pump amps are indicated.**

COMMENTS:

• • italicized Cues Are To Be Used Qnry If JPM Performance Is Being Simulated.

Paee 11 of 16 STEP 13: Ensure at least one boric acid transfer pump - ON (Step 9.b.)

-SAT TANDARD: Candidate selects ON for Boric Acid Transfer Pump 1A and observes that the Red O N light is DARK and the Green OFF light is LIT.

Transitions to step 9.b. RNO.

-UNSAT

• • CUE The switch for the Boric Acid Transfer Pump I A is in the ON position. The Red ON light is DARK and the Green OFF lighf is LIT.**

COMMENTS:

STEP 14: Establish boric acid flow from the FWST as follows: CRITICAL (Step 9.b. WNO) STEP (Step 9.b.I) RNO)

2) Open the following valves -SAT 1NV-252A (NV Pumps Suct from FWST)

• 1NV-2533 (NV Pumps Suct from W S T )

STANDARD Candidate depresses the OPEN pushbuttons for 1NV-252A and -LJNSAT INV-253B. Verifies the Ked OPEN light is LIT and the Green CLOSEDlight is DARK for INV-252A and verifies the Red OPEN light is LIT and the Green CLOSEC)light is BARK for 1NV-253B.

• • CUE: The 8PENpushbutton for 1NW-252A has been depressed. The Red OPEff light is LIT and the Green CLOSED light is DARK.

The OPEN pushbutton for INW-253B has been depressed. The Red OPEN light is LIT and the Green C6OSED jight is DARK.**

EXAMINER NOTE: It is only necessary to open one of the above valves to satisfy the critical step.

COMMENTS:

• • Italicized Cues Are To B e Used Only If JPM Performance Is Being Simulated.

Page 12 of 26 Close the following valves: (Step 9.b.2) RNO) CRlnCAL

• 1NV-2 88A (VCT Otlt 1~01) STEP

• 1NV-I898 (VCT 0th IsoI)

SAT STANDARD Candidate depresses the CLOSED pushbuttons for 1NV-I88A and 1NV-I89B. Verifies the Green CLOSED light is LIP and the Red OPENlight is DARK for 1NV-1888 and the Green CLOSED light is LIT and the Red OPEN light is DARK for INV-289B. -UNSAT

• • CUE: The %LOSED pushbuffon for INV-18813 has been depressed.

The Green CLOSED light is LIT and the Red OPEN light is DARK. The *CLOSEDpushbuffon for INV-189B has been depressed. The Green CLOSED light is LIT and the Red OPEN light is DARK^ **

EXAMINER NOTE: It is only necessary to close one of the above valves to satisfy the critical step.

COMMENTS:

STEP 16: Maintain charging Row greater than or equal to 105 GPM (Step 9.b.3) RNOj -SAT STANDARD: Candidate adjusts INV-294 (NV PMPS A&B DISC# FLOW CNTRL) as required and verifies on 1NVP5630 on 1MC-11 that charging flew is greater than 105 GPM and transitions to Step 10. UNSAT

• • CUE: Charging flow is greater then 105 GPM.**

COMMENTS:

STEP 17: Ensure compliance with appropriate Tech Specs: (Step IO.)

-SAT STANDARD: No action required by the candidate.

EXAMINER CUE: The SRO will ensure compliance with Tech Specs.

-UNSAT COMMENTS:

• • lalicked Cues Are To Be Used Only IPSPM Performance k Being Simulated.

Page 13 of 16 Determine required notifications. (Step 11.)

-SAT 2TANDARD: No action required by the candidate.

EXAlUllNER CUE: The SRO will make any required notifications.**

-UNSAT COMMENTS:

STEP 79: Ensure adequate shutdown margin as follows: (Step 12.)

Obtain current NC boron concentration from Primary Chemist. -SAT (Step f2.a.)

STANDARD: Candidate calls Primary Chemist at 5603 to obtain current NC boron concentration. -UNSAT EXAMINER CUE: Current NC boron concentration is 1300 ppm.

COMMENTS:

STEP 20: WHEN current NC boron concentration is obtained, THEN perform shutdown margin calculation. (Step 12.b.) -SAT STANDARD: No action required by the candidate.

EXAMINER CUE: The Unit 2 BOP has performed a shutdown margin -UNSAT calculation and determined that adequte shutdown margin exists.

COMMENTS:

• • italicized Cues Are To Be Used Qnry If JBM Performance Is Being Simulated.

Paae I 4 of 16 I

I STEP 21: WHEN adequate shutdown margin is obtained, THEN stop NC boration as follows: (Step 12. c.1))

Ensure shutdown margin monitors - RESET.

-SAT STANDARD: Candidate verifies the following alarms are BARK:

e IAD-2, E/2 TRAIN A SHUTDOWN MARGIN ALARM

-UNSAT e IAD-2, Fl2 TRAIN B SHUTDOWN MARGIN ALARM

• • CUE: Alarms 7AD-2, U2 TRAIN A SHUTDOWN MARGlN ALARM and 1 , 4 0 4 F/2 TRA!N B SHUTDOWN MARGIN ALARM are DARK.**

COMMENTS:

STEP 22: IF borating from the W S T , THEN:

Ensure the following valves - OPEN: (Step 12.Z.a)) -SAT e INV-188A (VCT 6tlt leol)

INV-189B (VCT Otlt Isel)

STANDARD: Candidate depresses the OPEN pushbuttons for 1NV-188A and -UNSAT 1NV-189B. Verifies the Red OPEN light is LIT and the Green CLOSED light is DARK for INV-188A and the Red OPEN light is LIT and the Green CLOSEB light is DARK for 1NV-I 89B.

• • CUE: The 0PENpushbutton for 7NV-788A has been depressed. The Red OPEN light is LIT and the Green CLOSED l/ght is DARK. The 0PENpushbutton for 7NV-789B has been depressed. The Red OPEN iighf is LIT and fhe Green CL0SEDIight is DARK.**

COMMENTS:

• • Italicized Cues Are To Be Used Only I f JPM Performance Is Being Simulated.

Page 15 of 16 I STEP23: Ensure the following valves - CLOSED: (Step 12.2.b))

1NV-2528 (NV Pumps Suct from FWST) _s SAT INV-2538 (NV Pumps Suct from FWST)

STANDARD: Candidate depresses the CLBSEBpushbuttons for 1NV-252A and lNV-253B. Verifies the Green CLOSEB light is LIT and the -UNSAT Red OPEN light is DARK for 1NV-2528 and verifies the Green CLOSED light is LIT and the Red OPEN light is DARK for 1NV-2538.

• • CUE: The CLOSED pushbuffon for 1NV-25261 has been depressed.

The Green CLOSEQ light is U T end the Red OPEN light is DARK. The CLOSED pushbutton for 1NV-2536 has been depressed. The Green CL0SEDlight is LIT and the Red OPEN light is DARK.**

COMMENTS:

STEP 24: Control charging as required for piant conditions.

-SAT STANDARD: Candidate adjust charging flow using INV-294 (NV PMPS A&B DlSCH FLOW CNTRL) as required by present plant conditions.

• • CUE: Chargling flow has been adjusted.* -UNSAT COMMENTS:

TERMINATING CUE: The BOP will complete the remainder of this procedure.

This JPM is complete TIME STOP:

• • Sfalicized Cues Are TO Be Used Only If JPM Performance Is Being Simulated.

Page 16 of 16 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

e Unit 1 is in Mode 3 preparing to start up.

Boric Acid Transfer Pump 16 is tagged out for maintenance.

INITIATING CUE:

You are the Operator at the Controls. It has been determined that source range counts and BDMS counts are increasing unexpectedly. The SRO instructs you to address the situation using AP//13 Case II (Boron Dilution While Shutdown).

• • ltaIicized Cues Are To Be Used Qnry If JBM Performance Is Being Simulated.

Procedure No.

Duke Power Company Catawba Nuclear gation Boron Dilution TRQLLEDFORPRINT * *********

(ISSUED) - PDF Format

BORON DILUTION AP/1/8/5500/13 To provide guidance to enswe the proper response in the event of an accidental boron dilution of the NC System while at power or shutdown.

B. Smotorns Case 1. Boron Dilution At Power:

e IAD-2, A19 "CONTROL ROD BANK LO LIMIT" LIT s 0 IAD-2, B/9"CONTROL ROB BANK LO-LO LIMIT LIT -

Unanticipatedcontrol rod insertion 0 Unexplained increase in T-Avg.

Case (1. Boron Dilution While Shutdown:

0 Unanticipated neutron flux level increase 4AD-2, U2 "TRAIN A SHUTDOWN MARGIN ALARM" - LIT 0 IAD-2, F/2 "TRAIN 0 SHUTDOWN MARGIN ALARM" - LIT

• IAD-2, D/3 "S/R HI FLUX LEVEL AT SHUTDOWN' - LIT

CNS BORON DILUTION PAGE NO.

APllIA/5500/13 2 of 14 Case I Boron Dilution At P o w r Revision 15 C. w r a t o r Actions

- 1. -

Ensure reactor power MAlNTAlNED LESS THAN 100%.

- 2. -

Verify reactor power STABLE. Perform the following:

- a. Stabilize unit at current power level.

- b. Maintain control rods above insertion limits.

c. Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

- Turbineload

- Control rods

- Boron concentration.

3. Stop any dilutions in progress as follows:

- a. Place "NC MAKEUP CONTROL" switch to "STOP."

- b. Place both reactor makeup water pumps to "OFF".

c. Isolate the NV demineralizers as follows:

- 1) Place 1NV-1538 (Letdn Hx Otlt 3-Way Vlv) in the "VCT" position.

2) Ensure the following valves CLOSED:

- e NV-353 &. 364 (Mixed Bed Demin 1A Isol)

- NV-368 8 379 (Mixed Bed Demin 1B Isol).

CNS BORON DILUTION PAGE NO.

APiliN5500i13 3of 14 Case I Boron Dilution At P o w r Kevision 15 I

I'

4. Verify boration of NC System required as follows:

a. Verify one of the following: a. Perform the following:

- OAC point CIL4409(Ctrl Bank Tech 1) IF AT ANY TIME either of the Spec Insertion Lmt Reached) - IN following occurs, THEN RETURN ALARM. -

TO Step 4.

OR - OAC point C1b4409 (Ctrl Bank Tech Spec Insertion Lmt

- Control rods below insertion limits. Reached) alarms.

REFER TO R.O.D. Book (Section

~-

2.2). OR

-* Control rods are below the insertion limits of the R.Q.D.

Book.

- 2) WTQStep 6

BORON DILUTION APlflN550Oll3 Boron Dilution At Power CAUTION Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6.

- 5. Borate NC system as required, to restore Borate NC system from the FWST as rods above insertion limits. REFER TO required, to restore rods above insertion OP!1!A/615Q/O09 (Boron Concentration limits:

Control).

a. Open the following valves:

- 1NV-2524 (NV Pumps Suct From FWST)

- 0 1NV-253B (NV Pumps Sud From FWSTJ.

b. Close the following valves:

- 1NV-188A (VCT Otlt Iso~)

- 1NV-189B (VCTOtlt Iso~).

c. WHEN desired to stop boric acid flow from the W S T , THEN:

1) Open the following valves:

- f NV-188A (VCT Otlt 1 ~ 0 1 )

- ZNV-189B (VCT Otlt Iso~).

2) Close the following valves:

- a 'lNV-2524 (NV Pumps SuGt From FWST)

- 1NV-253B (NV Pumps Suct From FWST).

- d. Repeat Step 5 RNO as required, to restore rods above insertion limits.

- 6. Ensum comdiance with Tec Spec 3. 6 (Control Bank Insertion Limits).

BOKON DILUTION AQ/I/A/5500/13 I 7. Determine and correct cause of dilution to include the following:

a. Notify Primary Chemistry to perform the fdlowing:

- Sample the mixed bed demineralizers.

Investigate any possible BAT changes as follows:

- Level changes Batching evolutions

- Concentration changes.

- b. Evaluate recent trends in VCT level and boron concentration,

8. Borate control rods to desired height.

REFER TO OQ/l/Ai6150/009 (Boron Concentration Control).

9. Request Chemistry sample the foSSowing for boron concentration:

IO. Determine required notifications:

- - REFER IB RP/O/N5000ED02 (Classification Of Emergency)

- 0 REFER TO RP/0/B/50QOK)13 (NRC Notification Requirements),

11. Notify Reactor Group Engineer of QCCUITen68.

BORON DILUTION AQll/N5500/13 CAUTION To prevent an inadvertent dilution of the NC system, Boron Saturation ob the Mixed Bed Demineralizer may be required prior to returning it to service.

- 12. WHEN the cause of the dllution has been corrected, P "realign MV System to normal operation. Ts OP/l/A/62001001 (Chemical and Volume Control System).

- 13. Determine long term plant status.

RETURN To procedure in effect.

BORON DILUTION APll/N55QQ/13 Boron Dilution While Shutdown C. Operator Actions

- 1. -

Verify boron dilution event IN E entry symptoms were due to the PROGRESS. following, THEN GO TO Step 13.

- 0 Failure to reset Source Range High Flux at Shutdow alarm setpoints when required

!2!3

- 0 Failure to block Source Range High Flux at Shutdown alarm when required m

- 0 Failure to reset Shutdown Margin Alarm setpoints during heatup OR

- Instrument failure.

2. Verify Reactor Trip: Pelform the following:

- All rod bottom lights LIT

~ - a. Manually trip the reactor.

-

• All reactor trip and bypass breakers ~ - b. E reactor will not trip, manually WEN insert rods.

- 3. WHEN manpower AND time permits, THEN REFER TO A P / I W 3 3 " 5 (Reacbr Trip Or Inadvertent Si1 Below P-I 1).

- 4. -

Verify core alterations IN PROGRESS. _- GO - TO Step 6.

BORON DILUTION AP/l/N5500/13 Boron Dilution While Shutdown RESPONSE NOT OBTAINED

5. Notify fuel handling operators to perform the following:

- Place components being handled in a safe position

_. e Suspend mre alterations.

6. Evacuate personnel from reactor building using the following:

-e Containment evacuation aiarm

- Plant page.

7. Stop any dilutions in progress as fdl0WS:

- a. Place "NC MAKEUP CONTROL" switch to "STOP."

- b. Place both reactor makeup water pumps to "OFF".

c. Isolate the NV dernineraliners as follows:

- I)Place INV-l53A(Letdn HxOtlt 3-Way Vlv) in the "VCT" position.

2) Ensure the folio\Ming valves -

CLOSED:

- e NV-353 & 364 (Mixed Bed Demin 1A Isol)

- s NV-368 & 379(Mixed Bed Bemin 15 Isol).

tion While Shutdown

8. Ensure proper BDMS operation as follows:

a. Verify at least one of the following a. Perform the following:

alarmfs) LIT:

~

I ) IF AT ANY TIME any of the

- IAD-2, EY2 ' T W I N A SHUTDOWN following alarms are lit, V" MARGIN ALARM" perform Step 8.

OR 1AB-2. EY2 "TF?ALN A

- e IAD-2, F12 "TWIN B SHUTDOWN MARGIN ALARM. OR

- IAB-2, F/2 "TRAIN B SHUTDOWN MARGIN ALARM".

- 2) w T O S t e p 9 .

b. Ensure the following valves - OPEN:

- 1NV-252A (NV Pumps Suct From FWST)

- 1NV-253B (NV Pumps Suct From RNST).

c. Ensure the following valves - CLOSED:

- 1NV-188A (VCT Otlt Iso~)

- 0 1NV-189B (VCT Otlt Iso~).

- el. Ensure one NV pump - ON.

- e. Maintain charging flow greater than or equal to 105 GPM.

- f. W T O S t e p I O .

CNS BORON DILUTION FAG NO.

APll/AI5500/13 10 of 14 Case II Boron Dilution While Skutdcwn Revision 15 ofnthe NC System as

9. Initiate l a ~ ~ t l o follows:

- a. Ensure one NV pump - ON.

- b. Ensure at least one boric acid transfer b. Establish boric acid flow from the pump -ON. W S T as follows:

1) Open the following valves:

- 1NV-25% (NV Pumps Suct From FWST)

- 0 1NV-253B (NV Pumps Sud From WST).

2) Close the following valves:

- 1NV-188A (VCT Otlt kol)

- 0 INV-189B (VCT Otlt Iso~).

- 3) Maintain charging flow greater than or equal to I 0 5 GPM.

- 4) G Q m s t e p 10.

c. Align boration flowpath as follows: c. Perform the following:

- 1) Ensure INV-238A(B/A To Hendr - 1) Ensure 1NV-236B (Boric Acid To Ctrl VIV) OPEN.

s NV Pumps S U ~- )OPEN.

- 2) Ensure INV-186A (B/A Blender Otlt - 2) Maintain boration flow greater than TO VCT Otlt) - OPEN. or equal to 30 GPM as indicated on 1NVP5440 (Emer Borate Flow).

- 3) Maintain boration flow greater than or equal to 30 GPM as indicated on - 3) IF AT ANY TIME boration flow 1NVCR5450. greater than or equal to 30 GPM cannot be maintained, THEN RETURN Ip Step 9.b RNO.

- d. Maintain charging flow greater than or equal to 30 GPM.

AP/l/N5500/13 Case II IO. Ensure compliance with appropriate Tech Specs:

- m 3.1.1 (Shutdown Margin)

- 0 3.3.1 (Refueling - Boron Concentration).

11. Determine required notifications:

- - REFER RP/IO/Ai5000R)OI (Classification Of Emergency)

- 0 _R E F E R M RP/O/B/5000K?I3(NRC I

Notification Requirements).

12. Ensure adequate shutdawn margin ids

~QIIQWS:

- a. Obtain current NC boron concentration from Primary Chemist.

- b. WHEN current NC boron concentration is obtained, THEN perform shutdown margin calculation. REFER TO OPIO/Ai6100/006 (Reactivity Balance Calculation).

I

c. WHEN adequate shutdom margin is obtained, stop NC System boration as follows:

BORON DILUTIQN APll/N55QQ/13

12. (Continued)

2) E bmting from the W S T ,

a) Ensure the following valves.

OPEN:

- 1NV-188A (VCT Otlt I d )

- a INV-1898 (VCT Otlt IS^).

b) Ensure the following valves -

CLOSED:

- INV-252A (NV Pumps Sud From FWST)

- 0 1NV-253B (NV Pumps Suct From WST).

- c) Control charging as required for plant conditions.

3) E borating from the BAT, THEN:

a) Close the following valves:

- 1NV-238A (BIA To Blendr Ctrl VIV)

- 1NV-186A @/A Blender Otlt To VCT Otlt).

- b) Ensure 1NV-23613 (Boric Acid TO NV Pumps S U ~- )CLOSED.

- c) Step boric acid transfer pump(s).

- d) Control charging as required for plant conditions.

Dilution While Shutdown Il -

13. Realign from inadvertent actuation as follows:

a. Ensure shutdown margin monitor RESET.

b. Ensure the following valves OPEN:

- 1NV-188A (VCT OtR Iso~)

- INV-189B (VCT Otlt 1~01).

c. Ensure the following valves CLOSED:

- e 1NV-252A (NV Pumps Suct From RNST)

-e 1NV-253B (NV Pumps Suct From RNST).

- d. Control charging as required for plant conditions.

I - e. Stop any NC System heatup in prcgress.

f. WHEN NC System heatup is stopped, - f. RETURN TO Step 2.

THEN verify the following:

I - Source Range indication -

STABLE OR DECREASING

- e Shutdown Margin Monitors -

STABLE OR DECREASING.

- g. E required, THEN notify IAE to reset setpoints for S/R Hi Flux Level at Shutdown alarms.

h. Ensure compliance with appropriate Tech Specs:

- 0 3.3.1 (Reactor Trip System Instrumentation)

- 3.3.9 (Boron Dilution Mitigation System)

- 0 3.9.2 (Refueling Instrumentation).

s

BORON DILUTION AP/I/A/5500/13 Case II Boron Dilution While Shutdown ACTION/EXPECTED RESP OMSE I I RESPONSE NOT OBTAINED I

13. (Continued)

i. Determine required notifications:

-

• RFFER TO RPIOIN5000X104 (Classification Of Emergency)

-e - REFERTO - RP/Q/13/5000~13(NRC Notification Requirements).

- 14. Notify Reactor Group Engineer of occumence.

CAUTION To prevent an inadvertent dilution of the NC system, Boron Saturation of the Mixed Bed Demineralizer may be required prior to returning it to service.

- 15. the cause of the dilution has been corrected, realign NV System to normal operation. REFER TO OP/1/A16200~001(Chemical and Volume Control System).

- 16. Determine long term plant status.

RETURN TO procedure in effect.

Page 1 of 13 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM/SI M-2 Align the NS System to Cold Leg Recirculation CANDIDATE EXAMINER

Page 2 of 13 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Align the NS System to Cold Leg Recirculation Alternate Path:

YES Facilitv JPM #

NS-104 (Modified)

KIA RatincW:

026 A204 (3.9/4.2)

Task Standard:

NS Pump16 is in operation with its suction aligned to the containment sump and proper RN flow established to the NS 1B NS heat exchanger.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant - Perform Simulate ~

References:

EP/l/A/5000/ES-I .3 (transfer to Cold Leg Recirculation) Enclosure 2; Revision 11 Candidate: Time Start :

NAME Time Finish:

Performance Ratino: SAT __ UNSAT - Question Grade __ Performance Time ~

Page 3 of 13 SIMULATOR SET-UP SHEET

1. Reset to any power IC set.

2. Ensure RN Bump I A is NOT in sewice.

3. Insert the following:

0 MAL-MC013B (Cold Leg Leak) set malfunction value = 27.0.

MAL-RNQO3A (Nuclear Service Water Pump I A Failure) Value = BOTH.

MAL-NSQ01B (Containment Spray Pump 1B Faifure) Value =AUTO VLV-NlQ38F (NI-1858 CNMT Sump Line 1A I S 0 (Stem) Fail To Position)

Value = 0.

4. Run the simulator until the FWST LO-LO LEVEL alarm is received while performing aH required actions of PIE-0, PIE-1 and PIES-2.3 up through step 7a by stopping NS pumps.

5. Freeze the simulator and write snap.

6. Selected IC 216 SIMULATOR OPERATOR INSTRUCTIONS:

1. Reset to IC 216

Page4of13 ToolslEaubmenff Procedures Needed:

Have enough copies of EQ/l/A/5000/ES-l.3 Revision 11 Enclosure 2 for each candidate.

REA5 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.

INITIATING CUE:

EP/l/A/5000/S-l 3, Transfer to Cold beg Recirculation has been implemented following a LOCA. The containment spray system is in operation. "RNST Lo-Lo Level" alarm is received and the NS pumps have been stopped per ES-1.3 step 7. SWO instructs you to align NS to Cold Leg Recirculation per Enclosure 2 of EWES-7.3.

~ - __

Page 5 of 13 I I

1- Obtain a copy of the appropriate procedure.

-SAT 1 STANDARD: Operator locates , Enclosure 2 of EP/l/N500tl/ES-I.3 EXAMINER CUE: When the candidate locates EPll/A15000ES-1.3, hand himlher a clean copy of Enclosure 7 and tell himlher that it is current -UNSAT and complete.

COMMENTS:

• "Italicized Cues Are To Be Used Only If JPlM Performance Is Being Simulated.

Page 6 of 13 Align NS as follows. (Enclosure 2,Step 1) CRITICAL STEP

• a. Close INS-20A (NS Pump I A Suct From FWST).

STANDARD: Candidate depresses the GREEN CLOSE pushbutton for INS90A -SAT (IMC-11). Verifies GREEN CLSD light LIT and RED OPEN light DARK.

• • CUE.The GREEN 6CLOSEDDpushbuffonfor lNS90A has been -UNSAT depressed. lNS-20A RED 0PENlight is DARK and the GREEN CLSD light LIT.**

COMMENTS:

• b. Close 1NS3B (ND Pump IB Suct From FWST).

STANDARD: Candidate depresses the GREEN CLOSE pushbutton for 1NS-35 (IMC-11). Verifies GREEN CLSI) light lit and RED OPEN light dark.

• • CUEThe GREEN CLOSEDDpMshbUffOnfor INS-SB has been depressed. The RED OPEN right is DARK and the GREEN CCSD light is LIT.**

COMMENTS:

c. Verify 1NI-185A (ND Pump 1A Cent Sump Suct) open.

STANDARD: Candidate verifies RED OPEN light DARK and GREEN CLSD light LITfor INI-185A (IMC-11). Transitions to Step 1.b. RNO.

• • CUE. The fNI-185A RED OPEN light is DARK and GREEN CLSDlight is LIT **

COMMENTS:

• • Italicized Cues Are To Be Used On& IfJPlM Performance Is Being Simulated.

Page 7 of 13 EXMAlNER NOTE: NS pump 1B will not automatically start in the next step. The candidate may attempt to start the pump at this point or may wait until directed by step JPM Step 5 (Enclosure 2, step 4).

STEP 2: (Continued)

1) Open INS-1B (NS PMP 1R Suct From Cont Sump). (Step 1.b. CRITICAL RNO). STEP STANDARD: Candidate depresses the RED OPEN pushbutton for 1NS-1B (1MC- -SAT 1I). Verifies RED OPEN light LIT. GREEN CLSD light DARK, Continues to Step 2.

• • CUE.The RED OPEN pushbuffon for 1NS-16 has been -UNSAT depressed. The RED OPEN fight is LIT end the GREEN CLSQ light is DARK. **

COMMENTS:

STEP 3: Verify containment pressure has exceeded 3 psig.: (Enclosure 2, STEP 2). -SAT STANDARD: Candidate verifies containment pressure is greater than 3 psig on 1B\ISCR5Q48/5390(pen 1) (1MC-9) or 1MICR5340/535Q(pen 3) (1MC-7). -UNSAT EXAMINER CUE: Provide cue IF pressure is less than 3 psig.

Containment Pressure has exceeded 3 psig

• • CUE: Containment pressure is greater than 3 psig.**

COMMENTS:

• • ltallcized Cues Are To Be Used Onry If JPM Performance Is Being Simulated.

Page 8 of I 3 STEP 4: Verify containment pressure greater than 1 p i g . (Enclosure 2, Step 3)

-SAT TANDARB: Candidate verifies containment pressure is greater than 1 psig 1NSP5040/5050/506C/5070 (ZMC-11) or 1NSCR504C/5390 (pen 1)

(IMC-7) or IMICR5340/5350 (pen 3) (IMC-9).

-UNSAT

• • CUE: Containment pressure is greater than I psig.**

COMMENTS:

STEP 5: Ensure NS pump (s) aligned to an open containment suction valve- CRITICAL ON. (Enclosure 2, Step 4) STEP STANDARD: Candidate determines NS Pump 1B is not running. NS Pump 1B RED OW light DARK and 1NI-184B RED OPEN light LIT and GREEN CLSD light DARK. Candidate depresses the REQ ON pushbutton for NS pump 1El and verifies the RED ON light is LIT and the GREEN OFF light is DARK.

-UNSAT IXAMINER NOTE: NS pump 1B may have been started in JPM Step 2 (Enclosure 2, step 1.b. RNO).

• • CUE: The RED ON pushbuffon for NS pump I8 has been depressed.

The RED ON light is LIT and the GREEN OFF light is DARK.**

COMMENTS:

• • ItalicizedCues Are To Be Used Only If JPlM Performance Is Behg Simulated.

STEP 6: Verify all Unit 1 and Unit 2 RN pumps on. (Enclosure 2. Step 5) -SAT STANDARD: Candidate verifies RN Pump 1A RED ON light IS DARK and the GREEN OFF light is LIT. RN Pump 1B RED ON light LIT with pump current at midscale on ammeter, RN Pump 2A RED -UNSAT ON light LIT and RN Pump 2B RED ONlight LIT.

Candidate transitions to step 5 RNO and goes to Step 7

• • CUE:

e The RED ON fight for RN pump 4A is BARK, and the GREEN OFF light is Llf The RED ON light for RN pump 1B is LIT, and the GREEN OFF light is DARK.

The RED ON light for RN pump 2A is LIT, and the GREEN OFF light is BARK.

The RED ON light for RN pump 28 is LIT, and the GREEN OFF light is DARK.

COMMENTS:

• • Italicized Cues Are To Be Used O d y If JPM Performance Is Being Simulated.

Page 10 of 13 I STEP?: Align RN to NS HX(s) based on RN and NS pumps status: (Enclosure 2, Step 7)

CRITICAL STEP

a. Verify NS Pump 4A on:

STANDARD: Candidate determines that NS pump 1A is not running and transitions to Step 7.a. RNO

-SAT

• • CUE: NS pump 1A RED :ON light is DARK and the GREEN OFF light is LIT.** -UNSAT COMMENTS:

a. Perform the following:

1) IF only one B Train RN pump is on, THEN close 2RN-47A (RN Supply X-Over)

STANDARD: Candidate determines that BOTH El Train RN pumps are running.

Continues to step 7. RNO a.2)

• • CUE. RN pump 1B RED :ON light is LIT and fhe GRE.&N OFF right is DARK and RN pump 2B RED :OW light is LIT and the GREEN OFF fight is DARK ,**

COMMENTS:

2) IF only B train RN pumps are on, THEN STANDARD Candidate determines that 2A RN pump is running Continues to step 7 RN0.a.3)

• • CUE:. RN pump 2A RED :ON light is LIT and the GREEN OFF light is DARK.**

COMMENTS:

Vtalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 11 of 13 STEP 7 (Continued) CRITICAL

2) Open 1UN-225B JNS HX 1B Inlet Isol). STEP

-SAT STANDARD: Candidate depresses the RED OPEN pushbutton for 1RN-2256 (IMC-11). Verifies RED OPEN light is LIT and the GREEN CLSD light is DARK.

-UNSAT

• • CUE.The RED QPENpushbuffon for IRN-225B has been depressed. IRN-2256 RED OPEN light LIT and GREEN CLSD light DARK COMMENTS:

4) Throttle open IRN-229B (NS HX Outlet Isol) to obtain one of the following:

4600 GPM flow through NS Hx 16 08 1RN 2298 full open STANDARD: Candidate depresses RED OPEN pushbutton for 1UN-229B until flow meter for 16 NS HX (1RNP5850 on 1MC-9) indicates 4600 gpm or 1 RN-2296 is fully open, with the RED OPEN light LIT and the GREEN CLSDlight BARK.

• • CUE.The RED OPENpushbutton for IRN-229B has been depressed. IRN-229B RED OPEN light LIT and GREEN CLSD light DARK COMMENTS:

5) Go to Step 8

• • Italicized Cues Are TO Be Used On& I f JPM Performance Is Being Simulated.

Page 12 of 13 STEP 8.: Verify adequate RN heat sink as follows: (Enclosure 2,Step 8) -SAT RN system suction aligned to Lake Wylie STANDARD: Verifies RN pump suctions open from hake Wylie:RED OPEN lights lit -UNSAT and GREEN CLSBlights dark:

1RN-1A RED OPEN light LIT and GREEN CLSD light DARK:

a 1RN-213 RED OPEN light LIT and GREEN CLSD light DARK 1RN-5A RED OPEN light LIT and GREEN CLSD light DARK IRN-6B KED OPEN light LIT and GREEN CLSD light BARK

• • CUE:

IRN-IA RED OPEN light LIT and GREEN CLSD light DARK 0 7RN-2B RED OPEN light LET and GREEN CLSD light DARK 0 7RN-5A RED OPEN light LET and GREEN CLSD Eight DARK a 7RN-6B RED OPEN light LIT and GREEN CLSD Eight DARK COMMENTS:

STEP 9: RN essential header temperatures at one of the following locations- -SAT LESS THAN OK EQUAL TO 82.5OF.:

• IMC-9 OR 0 ROLogbook -UNSAT STANDARD: Candidate determines from either 1RNP5000 or 1RNP5010 that RN essential header temperature is approximately 69 F.or determines temperature from RO Logbook.

• • CUE: RN essential header temperature is 69 4.**

COMMENTS:

This JPM is complete.

TIME STOP:

• • /ta/icized Cues Are To Be Used Only MJPM Performance Is Being Simulated.

Page 13 of 13 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIATING CUE:

EP/1/8/50QQ/ES-1.3,Transfer to Cold Leg Recirculation has been implemented following a LQCA. The containment spray system is in uperation. "FWST bo-bo Level" alarm is received and the NS pumps have been stopped per §-I .3 step 7. SRQ instructs you to align N§ to Cold Leg Recirculation per Enclosure 2 of EP/ES-I .3.

• • Italicized Cues Are To Be Used Only I f JPM Performance Is Being Sirnulafed.

TRANSFER TO COLD LEG RECIRCULATION EP/I/N500Q/ES-1.3

1. Align NS as fellows:

a. Close the following valves:

- 7NS-20A (NS Pump 1A Suct From WST)

-e INS-3B (NS Pump 1B Suct From WSP).

- b. Verity lNI-l85A(ND Pump IACont b. Perform the following:

Sump Suct) OPEN.

~

- 1) Open I N S l B ( N S Pmp B Suct From Cont Sump).

- 2) QQ To Step 2.

- c. Open 1NS-1EA (NS Prnp A Suct From Cent Sump).

- d. Verify IN[-1848 (ND Pump 15 Cont - d. Q Q m S t e p 2.

Sump Suct) OPEN.

~

- e. Open 1NS-15 (NS Pmp B Suct From Cont Sump).

- 2. Verify containment pressure HAS EXCEEDED 3 PSIG.

- _- GO To Step 5.

- 3. -

Verify containment pressure GREATER THAN 1 PSIG.

Perform the following:

- a. Reset NS.

- b. Stop NS pumps.

- c. W I Q S t e p 5.

- 4. Ensure NS pump@) aligned to an open containment sump suction valve ON.

- 5. Verify all Unit I and Unit 2 RN pumps - -- GO Step 7.

ON.

TRANSFER TO COLD LEG RECIRCULATION EP/I/N§OOO/ES-I .3 CAUTION Exceeding 49QO GPM RN flow through an NS Hx will cause damage to the Hx tubes.

6. Align RN to NS Hx(s) as follows:

- a. Open 1RN-144A (NS Hx 1A Inlet Isol).

b. Throttle open lRN-I48A(NS Hx 1A Outlet Isol) to obtain one of the following:

- 4600 GPM flow through NS Hx 1A OR

- 0 1RN-148A full open.

- c. Open 1RN-2233 (NS Hx I B Inlet Isol).

d. Throttle open iRN-229B (NS Hx I B Outlet !sol) to obtain one of the following:

- 0 4600 GPM flow through NS Hx 18 OR

- 0 1RN-229B full open.

- e. SQTsStep8.

CAUTION Exceeding 4900 GPM RN flew through an NS Hx will cause damage to the Hx tubes.

7. Align RN to NS Hx(sJbased on RN and NS pump status as follows:

- a. V e r i i NS Pump 1A - 5N. a. Perform the following:

I)E only one B Train RN pump is on, close 2RN-47A (F3d Supply X-Over).

2) E only B Train RN pumps are on,

=close one of the following valves:

2RN-48B (RN Supply X-Over Isd)

OR a 2RN-47A (RN Supply X-Over Isol).

Isol). IRN-225B (NS Hx 1B Inlet

- 3) Open

4) Throttle open IRN-229B (NS Hx lf3 Outlet Isol) to obtain one of the foliowing:

-* 4600 GPM flow through NS Hx 18 OR

-

• 1RN-2298 full open.

5) m m S t e p 8 .

TRANSFER TO COLD LEG RECIRCULATION EP/l/A/5000/ES-4.3

7. (Continued)

- b. -

Verify NS Pump 1B ON. b. Perform the following:

- I)E! only one A Train RN pump is OR, close 2RN43B (RN Supply X-Over).

2) E only A Train RN pumps are on, close one of the following valves:

- 2RN-47A (RN Supply X-Over Isol)

OR

- 2RN-488 (RN Supply X-Over Isol).

- 3) Open IRN-1448 (NS Hx i A Inlet isol).

4) Throttleopen IRN-l48A(NS Hx 1A Outlet Isol) to obtain one of the following:

- 0 4600 GPM flow through NS Hx

?A OR

- 1RN-148A full open.

- 5) S m S t e p 8 .

TRANSFER TO COLD LEG RECIRCULATION EP/I/N5000/ES-1.3 ACTIOH/EXPECTED RESP ONSE RESPONSE HOT CBTAINE B

7. (Continued)

- c. Verify at least one A Train WN pump c. Perform the following:

ON.

1) E both B Train RN pumps are on, w close one of the following valves:

- e 2RN-48B (RN Supply X-Qver)

OR

- 2RN-478 (RN Supply X-Over).

- 2) only one B Train RN pump is OR, w close 2RN-47A (RN Supply X-Over).

- 3) Open IRN-2258 (NSHx 1B Inlet Isol).

4) Throttle open 1RN-229B (NS Hx 1B Outlet Isol) to obtain one d the following:

- 0 4600 GPM flow through NS Hx 1B OR

- IWN-229B full open.

- 5) GOlQStep 6.

d. Perform the following:

1) LE both A Train RN pumps are on, THEN close one of the following valves:

- 2RN-47A (RN Supply X-Over)

OR

- 0 2RN-48B (RN Supply X-Over).

- 2) E only one ATrain RN pump is on, THE_N close 2RN-48B (RN Supply X-Qver).

- 3) Open 1RN-144A (NS H x 1A Inlet Isol).

4) Throttle open IRN-?48A(NSHx 1A Outlet lsol) to obtain one of the fdlowing:

- 0 4600 GPM flow through NS Hx 1A OR

- 1RN-14814 full open.

- 5) G O m S t e p 8.

EG RECIRCULATION Enclosure 2 - Page 7 of 10

7. (Continued)

- e. Verify RN Pump ?Aand 2A ON.

~

e. Perform the following:

1) E only one RN pump is on in each train, m a l i g n RN to only one NS Hx as follows:

- a) Open 1RN-144A (NS Hx 1A Intd Isol).

b) Throttle open lRN-l48A(NS Hx I A Outlet Isol) to obtain one of the following:

- Hx ?AGPM flow through NS 4600 OR

- 1RN-148A full open.

c) ==Step 8.

OR

• NSHxIB:

- a) Open ZRN-2258 (NS Hx ?B Inlet Isol).

b) Throttle open ?RN-2298(NS Hx 1B Outlet isol) to obtain one of the following:

4600 GPM flow through NS HX 1B OR

- 8 1RN-229B full open.

- c) !X!M Step 8.

- 2) Open ZRN-225B (NS Hx 1B Inlet ISOl).

(RNO continued on next page)

TRANSFER 80 COLD LEG RECIRCULATION EP/lNV5000/ES-1.3 I

RESPONSE NOT OBTAINE 0

7. (Continued)

3) Throttle O ~ W I1RN-229B (NS HX 1B Outlet Isol) to obtain one d the fobwing:

- 4600 GPM flow through NS Hx as OR

- 1RN-229B full open.

- 4) E o W S t e p 8.

- f. Open IRN-144A (NS Hx I A Inlet Isol).

g. Throttle open IRN-148A (NS Hx 1A Outlet Isol) to obtain one of the following:

- 4600 GPM flow through NS Hx 18 OR

- 0 lRN-148Afull open.

TRANSFER TO COLD LEG RECIRCULATION EP/lIN5000/ES-1.3

8. Verify adequate RN heat sink as follows: Perform the following:

- RN System - SUCTION ALIGNED TO a. Ensure the following valves - OPEN:

LAKE WYLlE

- 1RN-3A (RN P/H Pit A Is01 From e RN essential header temperatures at one of the following locations - LESS THAN OR QUAL TO 825°F:

1MC-9

- - SNSWP) 1RN-4B (RN ?/HPit B Is01From SNSWP)

OR

- IRN-58B (RN Hdr B Ret To SNSWP) 1RN-63A (RN Hdr A Ret To SNSWP)

- 0 RQLogbook.

- 1RN-846A (DIG 1A Hx Ret To SNSWP) 2RN-8468 (DIG 2A HX Ret TO SNSWP)

-* 2RN-848B (DIG 28 HX Ret TO SNSWP).

(RNO continued on next page)

TRANSFER TO COLD LEG RECIRCULATION EPIlIN5000IES-1.3

8. (Continued)

b. Ensure the following valves - CLOSED:

- I RN-1A (RN PIH Pit A Is01 From Lake)

- 4RN-2B (RN P/H Pit A Is01 From Lake)

- IRN-5A (RN PI# Pit B Is01 From bake) 1RN-6B (RN P/H Pit B Is01 From Lake)

- 1RN-54B (Station RN Disch Hdr X-over)

- 1RN-54A (Station RN Disch Hdr X-over) 1RN-57A (Station RN Disch To RL SYS) 1RN-&t3B (Station RN Disch To RL Sys)

-e 1RN-8498 (D/G1A Hx Ret To Lake)

- 1RN-8498 (D/G 1B Hx Ret To Lake)

- 2RN-847A (Dl6 2A Hx Ret To Lake)

- 0 2RN-849B (D/G 2B Hx Ret To Lake).

.--.- ~

~

Page Iof 9 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM /CR-3 Take Power Range Drawer Out of Service CANDIDATE EXAMINER

Page 2 of 9 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task; Remove Power Range Channel N-41 from service per AP11/8/55001016 (Malfunction of Nuclear Instrumentation System), Case IV Power Range Malfunction.

Alternate Path:

NO Facilitv JPM #:

OP-CN-IC-ENE-002 KIA Ratina(sL 015 A403 (3.813.9)

Task Standard:

Power Range Detector is N 4 1 removed from service with Control Power fuses removed Preferred Evaluation Simulator: Preferred Evaluation Perform Control Room X In-Plant __ Perform __ Simulate X

References:

Examiner: I NAME SIGNATURE DATE

Page 3 of 9 SIMULATOR SETUP SHEET

1. Place simulator on Run.

2. Insert MAL-ENB011A (Power Range Detector N-41A Failure), Severity Value = 100%.

3. Perform actions of APll6 through step 5.

4. FREEZE simulator.

5. Write to Protected IC SNAPNo.: 211 SIMULATOR OPERATOR INSTRUCTIONS:

None.

~-

Page 4 of 9 Teois/EoulomenffProCedUres Needed:

Ensure enough copies of AP/I/A/5500/16 for each candidate.

READ TO OPERATOR DIRECTION TO TRAINEE:

B 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 wili provide initiating cues and repork 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 is operating at 100% power.

N-41, Power Range, Upper Detector has failed offscale high W/l/A/5500/16, Case IV, Power Range Malfunction, has been implemented.

INlTlATlNO CUES:

The Control Room SRO instructs you to remove N-41 from service per step 6 through 9 of Case IV of AP/I/A/5500/16.

Page 5 of 9 START TIME:

I 5TEP 4 : Perform the following actions at the Miscellaneous Control and CRlTlCAb Indication Panel: (Step 6)

Place the appropriate "ROD STOP BYPASS" switch to the STEP

. affected channel position.

Verify NUC OVER PWR ROB STOP CH BYP status light (ISI-

19) fer affected channel - LIT.

-SAT m Place "POWER MISMATCH BYPASS" switch to the affected channel position. -UNSAT STANDARD: Locates Miscellaneeus Control and Indication Panel and performs the following:

Places ROD STOP BYPASS switch to BYPASS PRN41.

"CUE The ROD STOP BYPASS switch is rotated to the BYPASS PRN41 position.

s 'Locates ?SI-29and verifies NUC OVER PWR ROD STOP CH BYP status light for N-47 -LIT.

• • CUE: The NUC OVER PWR ROD STOP CH BYP status right for N41 is UT.

. Places POWER MISMATCH BYPASS switch to BYPASS PRN41.

• • CUE: The POWER MISMATCH BYPASS switch is rotated to the BYPASS PRN41 position.

EXAMINER NOTE: *This step not critical.

COMMENTS:

• • ItaKci+edCues Are TO Be Used Only If JPM Performance Is Being Simulated.

Page 6 of 9 I STEP2: Perform the following actions at the Detector Current Comparator panel: (Step 7)

CRITICAL STEP 0 Place "UPPER SECTION" channel defeat switch to the e

affected channel.

Verify "CHANNEL DEFEAT" light for upper section-LIT.

-SAT e Place "LOWER SECTION" channel defeat switch to the affected channel.

0 Verify "CHANNEL DEFEAT" light for lower section-L!T. -UNSAT STANDARD: Locates Detector Current Comparator Panel and performs the following:

Races "UPPER SECTION channei defeat switch to PR N41.

• CUE: The UPPER SECTION channel defeat switch is rotated to fhe PR N41 position.

e *Verify "CHANNEL DEFEAT" light for upper section lit.

^^CUE:The CHANNEL DEFEATlight for the upper section is LIT.

Places "LOWER SECTION" channel defeat switch to PR N41

• • CUE: The LOWER SECTION channel defeat switch is rotated to the PR N41 position.

• Verify "CHANNEL DEFEAT" light lit fer lower section.

• • CUE: The CHANNEL DEFEATlight for the lowersection is LIT.

EXAMlNER NOTE: *These steps are net critical.

COMMENTS:

• • italicized Cues Are To Be Used Only I f JPM Performance Is Being Simulated.

Page 7 of 9 I

1 STEP3: At the Comparator and Rate panel, place the "COMPARATOR CHANNEL DEFEAT" switch to the affected channel position. (Step 8 )

CRITICAL STEP STANDARD: Locates Comparator and Rate panel and places "COMPARATOR CHANNEL DEFEAT" switch to N41.

-§AT

• • CUE: The COMPARATOR CHANNEL DEFfAT switch is rotated to the N41 position. -UNSAT COMMENTS:

STEP 4 :

.De-energize affected channel. (Step 9.a)

Remove "CONTROL PQWER" fuses at Power Range A drawer.

CRITICAL STEP STANDARD: Locates N41 Power Ranae Drawers:

-SAT

• Remove fuses -far enough to de-energize "CONTROL POWER".

-UNSAT "CUE: The CONTROL POWER fuse holders are rotafed counter-clockwise and pulled Q U ~

EXAMINER NOTE: The candidate should warn the RQ of the alarm he is about to initiate (IAD-2, B6), however this is NOT required to meet the critical step.

COMMENTS:

NOTE: Replacement of the affected P/R control power fuses shall not occur without authorization of the Superintendent of Operations or his designee.

• • !talicized Cues Are To Be Used Only if JPM Performance Is Being Simulated.

Page 8 of 9 STEP 5: Request the OSM to maintain the "CONTROL POWER fuses under -§AT his control. (Step 9.b)

STANDARD: Operator hands both "Control Powef fuses to the OSM to maintain under hislher control. -UNSAT EXAMINER CUE: OSM replies that he will keep the control power fuses in his possession.

COMMENTS.

STEP 6: Verify the affected Power Range cabinet shows no physical signs of -SAT damage. (Step 9.c)

STANDARD: Operator checks outside of the Power Range cabinet for signs of damage. -UNSAT

• • CUE: The Power Range cabinet shows no sign of damage.

COMMENTS:

TIME STOP:

• • italicized Cues Are To Re Used Only If JPM Performance Is Being Simulated.

Page 9 of 9 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

N 4 I , Power Range, Upper Detector has failed offscale high.

APll/N5500/16, Case IV, Power Range Malfunction, has been implemented INITIATING CUES:

The Control Room SRO instructs you to remove N-41 from service per steps 6 through 9 of Case IV of AP/Z/N5500/16.

• • italicized Cues Are To Be Used On/y If JPM Performance Is Being Simulated.

Catawba Nuclear Station 019 Malfunction of Nuclear Instrumentation System Electronic Reference No.

AQ/llAl5500116 A. Purpose e To verify the proper response in the event of a nudear instrumentation malfunction.

B. Swmwtoms Case 1. Source Range Malfunction

• Indication lost or erratic IAD-2, D/1 "SF? HI VOLTAGE FAILURE" - LiT

?AD-2, 813 "SIR Hi FLUX LEVEL AT SHUTDOWN" - LIT IAD-2, D/4 "SIR HI FLUX LEVEL AT SHUTDOWN" - LIT.

Case II. Audio Count Rate Malfunction Audible count rate lost.

Case 111. Intermediate Range Malfunction indication lost or erratic 0 IAB-2, C/1 "VR HI VOLTAGE FAILURE - LIT a IAD-2, C/2 "i/R COMPENSATING VOLTAGE FAILURE" - LIT 1AD-2, 73 "IIR HI FLUX LEVEL ROD STOP" - LIT SIR failure to re-energize during shutdown.

Case IV. Power Range Malfunction e lndicatiin lost or erratic IAD-2, All "P/R HI NEUTRON FLUX RATE M E R 7 - LIT

• IAD-2, N2 "PIR HI NEUTRQN FLUX LO SETPOINT ALERT" - LIT IAD-2, A13 "PIR Hi NEUTRON FLUX HI SETPOINT ALERT" - LIT IAD-2, 8/3"COMPAKATOR P/R CHANNEL DEVIATION" LIT IAD-2, 815 "PIW HI VOLTAGE FAILURE" - UT

~

• IAD-2, El8 "OVER POWER ROD STQP" - LIT 1AD-4, C/5 "BFCS TROUBLE" LIP. ~

MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM APll/N5500/16 C. Operator Actions

- 1. Stop any positive reactivity additions.

- 2. -

Verify core alterations IN PROGRESS. ---

GO TO Step 4.

3. Notify fuel handling operators to perform the following:

- e Race components being handled in a safe position

- Suspend m e alterations.

4. Identify the affected SIR channel:

- 0 N31 OR

- N32.

5. Verify the following alarms DARK Patform the following:

- lAB-2.0/3 "SIR HI FLUX LEVEL AT - a. Depress "OFF" for the containment SHUTDOWN" evacuation alarm.

- IAD-2, D/4"SR HI FLUX L E M L AT - b. Notify plant personnel to disregard the SHUTDOWN". containment evacuation alarm.

6. At the affected SIR drawer, perform the following:

- a. Place the "LEVEL TRIP" switch for the affected channel in "BYPASS'.

- b. Verify the "LEVEL TRIP BYPASS" light on the affected SIR drawer - LIT.

- 7. Verify the affected S/R channel trip bypass status light (ZSI-19) LIT.

ll I 11 CNS AP/I/N5500/16 MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM I-^^^ I I PAGE NO.

30f12 1I

- 8. Verify 1AB-2, C14 "NII SYS SIR 8, liR TRIP BYPASS" LIT.-

9. Block the high flux at shutdown function as follows:

- a. At the affected S R drawer, place the "HIGH FLUX AT SHUTDOWN" switch for the affected channel in "BLOCK".

- b. Verify lAl2-2, Di2 "SIR HI SHUTDOWN FLUX ALM BLOCKEB" LIT. ~

IO. Ensure the following components ALIGNED TO THE OPERABLE SIR CHANNEL:

- "CHANNEL SELECTOR switch on the Audio Count Rate Channel panel

- "NIS RECORDER".

- 11. Determine and correct cause of SIR malfunction.

12. Ensure compliance with appropriate Tech Specs:

3.3.1 (Reactor Trip System ( R E )

Instrumentation)

- 0 3.9.2(Nuclear Instrumentation)

-

• 3.3.9 (Boron Dilution Mitiation Sy§teM(BBMS)).

23. Determine required notifications:

REFER TO RP/O/N5000D01 (Classification Of Emergency)

- 0 REFER TO WPIO/B/5000D13 (NRC Notification Requirements).

I' CNS AP/l /N550Q/T6 MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM Case I Source Ranae Malfundions I

L PAGE NO.

4of 12 Revision 19 I I1

- 14. Notify Reactor Group Engineer ob occumence.

- 15. WHEN the affected S/R channel is repaired, THENensure IAE returns the channel to sewice.

__ 16. Determine long term plant status.

RETURN TQ. procedure in effect.

AQlllAi5500116 C. Onerator Actions

- 1. -

Verify the unit IN MODE 6. Perform the following:

- a. Stop any positive reactivity additions until audible count rate indication is restored or station management approval is obtained.

- b. ==Step 3.

- 2. Verify audio count rate signal -AUDIBLE --IF the count rate is audible in the control IN CONTAINMENT. room, THEN shift the "AMPLIFIER SELECTOR switch (inside and at the back of the Audio Count Rate Drawer) to the "Al" position. (Key #18).

3. Verify SIR channels operable as follows: IF a single S/R channel has failed, THEN:

- N ON SCALE - a. At the Audio Count Rate panel, place

- N ON SCALE. the "CHANNEL SELECTOR" switch to the operable SIR channel position.

- b. GOTO Case 1 (Source Range Malfunctions).

- 4. Determine and correct cause of audio count rate malfunction.

- 5. RETURN TO procedure in effect.

I I II hPll/AJ5500/16 Case 111 C. QDerator Actions

- 'l. -

Verify reactor power GREATER THAN - Stop any power increase.

10%.

- 2. Verify IAD-2, Ci3 "IIR HI FLUX LEVEL ROD STOP" DARK.

- Adjust turbine load to maintain T-Avg at T-Ref.

3. Identify affected IIR channel:

-

• N-35 OR

- 0 N-36.

4. At the affected IIR drawer, perform the following:

- a. Place the "LEVEL TRIP" switch for affected channel in "BYPASS".

- b. Verify the "LEVEL TRIP BYPASS" iight on the affected IIR drawer - LIT.

Verify the affected channel IIR channel trip bypass status light (251-29) UT.

Verify IAD-2, 614 "Nil SYYS SiR & IIR TRIP BYPASS" LIT.-

Ensure the "NIS RECORDER" ALIGNED-TQ THE OPERABLE IIR CHANNEL.

WHEN the operable IIR channel is less than l W I o Amps, THEN ensure %/R channels are reset.

Determine and correct cause of IIR malfunction.

AP/liN5500/16

- 10. Ensure compliance with Tech Spec 3.3.1 (Reactor Trip System (RTS)

Instrumentation).

11. Determine required notifications:

- REFER TO RPIOIN5005D51 (Classification Of Emergency)

- REFER TO RP/5/B/500OD13 (NRC Notification Requirements).

- 12. Notify Reactor Group Engineer of occurrence.

CAUTION Installing IIR fuses with any PIR channel inoperable or in a tripped condition, may result in a reactor trip on PIR rate trip due to voltage spikes.

- 13. the affected IIR channel is repaired, m e n s u r e IAE returns the channel to service.

- 14. Determine long term plant status.

RETURN TO procedure in effect.

APll/N5500/16 Case IV C. Oaerator Actions

-0 Verify alt rod motion = STOPPED. - IF-unwarranted rod motion is occurring, THEN place "CRD BANK SELECT to manual.

- 2. Verify IAD-2, E18 "OVER POWER ROD - Adjust Turbine load to maintain T-Avg at STOP" DARK. T-Ref.

3. Identify failed PIR channel:

- N-41 OR

- N-42 OR

- N-43 OR

- 0 N-44.

- 4. Ensure unaffectedchannels -

OPERABLE.

5. Request WE to place the following bistaMes in the tripped condition.

REFER TO Model WiO #NO02943

- OT DELTA T

- OP DELTAT.

1 ACTIONlEXPECTEO RESP ONSE I I RESPONSE NOT OBTAINED 1

6. Perform the following actions at the Miscellaneous Control And Indication panel:

- a. Place the appropriate "ROD STOP BYPASS" switch to the affected channel position.

- b. Verify the affected nuclear overpower rod stop channel bypassed status light (1s-19) -LIT.

- c. Place "POWER MISMATCH BYPASS" switch to the affected channel position.

7. Perform the following actions at the Detector Current Comparator panel:

- a. Place "UPPER SECTION" channel defeat switch to the affected channel.

- b. Verify the "CHANNEL DEFEAT" light for the upper section - LIT.

- c. Place "LOWER SECTION" channel defeat switch to the affected channel.

- d. Verify the "CHANNEL DEFEAT' light far the lower section LIT.

- 8. At the Comparatorhd Rate panel, p!ace the "COMPARATOR CHANNEL DEEAP" switch to the affected channel position.

9. De-energize the affected channel as follows:

- a. Remove the controi power fuses at Power Range A drawer.

NBTE Replacement of the affected P/R control power fuses shall not occur without authorization of the Superintendent of Opefations or his designee.

- b. Request the BSM to maintain the control power fuses under his control.

- c. Verify the affected Power Range - c. Remove the instrument power fuses at cabinet shows no physical signs of Power Range 3 drawer.

damage.

- IO. Ensure affected channel bistables are in the required state. REFER TO E R C ~ ~ S U W 1(PIR Bistables That Must Be Tripped).

- 11. Ensure "NIS RECORDER" SELECTED TO AN OPERABLE PIR CHANNEL.

- I 2 Determine and correct cause of P/R malfunction.

13. Ensure compliance with appropriate Tech Specs:

- e 3.2.4 (Quadrant Power Tilt b t i o (QPTW

- 3.3.1 (Reactor Trip System (RTS)

Instrumentation)

TIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED

14. Determine required notifications:

- - REFER- TO RP/O/~%QOOigQl (Classification Of Emergency)

- - R E F E R m RP/Q/B/50QOX)13(NRC Notification Requirements).

- 15. Notify Reactor Group Engineer of occumnce.

- 16. WHEN the affected PIR channel is repaired, THEN ensure IAE returns the channel to sewice.

- 17. Determine long term plant status.

.RETURN TO procedure in effect.

II 1.

Ensum the following reactor trip system intedocks in the required state (IS-18) for existing unit conditions within 1 hour:

P-7 I - 0 P-IO.

I 2. Ensure the following bistables for the affected channel are placed in the tripped condition within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s:

- e NC loop OTDT reador trip status light (IS-7) - LIT

- e NC loop OPDT reactor trip status light (IS-7) LIT.~

NBTE The following bistables can only be assured to stay in the tripped condition by the removal of the affected channel's control power fuses.

3. Ensure the following bistables for the affected channel are in the tripped condition within 6

- PIR high flux low setpoint status light (ISI-3) - LIT

- PIR high flux high setpoint status light (ISI-3) - LIT

- PiR high flux rate status light (4SI-3) - LIT.

Enclosure 4.1 OP/1/A/6 150/002A Startup and Operation of the NC Pumps Page 1 of 7

1. Initial Conditions 1.1 Review the LimiB and Precautions.

1.2 Verify seal injection flow has been established to each Reactor Coolant Pump per OP/l/.4/6200/001 (Chemical and Volume Control System).

1.3 Verify Component Cooling System is in Operation per OP/I/A/6400/005 (Component Cooiing System).

1.4 Verify Reactor Coolant Pumps are aligned per OPll/N6150/002B OJCPump Motor Oil Pill and Drain System).

1.5 Verify Reactor Coolant System is filled per OP/l/A/6150/001 (Filling and Venting The Reactor Coolant System).

1.6 Verify the NCDT is aligned for operation per (3P/1/.4/650010/014 (Operations Controlled Liquid Waste Systems).

1.7 Verify NCP motor cooling water from W (preferred) or RN has been established.

1.8 Ensure that a Written prejob briefing has been performed per Site Directive 3.0.21 (Prejob Briefing) that includes B discussion of reactivity management concerns with this procedure.

Enclosure 4.1 OP/1/A/6150/002A Startup and Operation of the NC Pumps Page 2 of 7

2. Procedure essential switchgear lETA or lETB and switchyard voltage is less than or equal to 223 KV or only one off-site source of power is available

2. NC F?mp operational configuration restrictions, as foliows, will ensure adequate PZR spray for press controi, maintain spray line water solid, and prevent thermal stratification of spray line {PIP C-00-04752}:

Pump combination should include NC Pump A or NC Pump B,

• If NC Pump A is in service, at least two other pumps should be in service, 6 If single pump operation is required, ensure NC Pump B is in service, otherwise, Auxiliary PZR spray flow should be established.

2.1 E Unit 1 is in Mode 5, refer to Tech Spec Table 3.4.12-1 (Reactor Coolant Pump Operating Restrictions For Low Temperahue Overpressure Protection) for temperature limitations on NC Pump starts.

2.2 E the pump to be started will bo the fourth NC Pump in service on Unit 1, verify NC temperature is 1 130°F. {PIP 96-1290, PIP 02-484)

I NOTE: If #1 Seal AP gauge overranged, AF' can be determined using 1NV125B (Excess Let& I3x 0 t h Ctri) "VCT" or "NCDT" switch position as follows:

6"VCT" position: NC Press minus Excess Letdn Hx Otlt Press = #I Seal AP

• "NCDT" position: NC Press minus VCT Press = #1 Seal AP 2.3 Verify that No. 1 seal AP is greater than 200 psig for the pump to be started per the following gauges: (Control Board 1MC5) 0 IANCP: 1NVP5230 IBNCP: 1NVP5220 0 ICNCP: 1NVP52IO 0 IDNCP: INVP5200

Enclosure 4.1 OP/1IAI6150/002A Startup and Operation of the NC Pumps Page 3 of 7 2.4 Verify that the standpipe level for the pimp to be started is normal by its associated annunciator BARK:

IJ "NCP A #2 SEAL S-PIPE HILO LVL" 1AD-7 A/I CI "NCP B #2 SEAL S-PIPE BLZO LVL" 1AD-7 A/2 El "NCP C #2 SEAL S-PIPE HI/LO LVL" 1AD-7 AI3 R "NCP D #2 SEAL S-PIPE BULO LVL" IAD-7 A/4 2.5 Verify that VCT pressure is 2 15 psig.

2.6 Verify 7-10 gpm seal injection flow on the pump to be started by the following gauges:

(Control Board 1MC5) 0 IANCP: 1wvP5330 0 1BNCP: 1NVP5320 0 1CNCP: INVP5310 IDNCP: 1WP5300

Enclosure 4.1 Startup and Operation of the NC Pumps Page 4 of 7 I NOTE: I ~ If #I Seal Leakoff Flow rate is < 1.O gpm, the # I Seal Low Flow indication shall he used. 1

2. If adequate # I Seal krtkoff Flow is NOT indicated in the following step, refer to Enclosure 4.4 (Operator Action For Low #1 Seal Leakoff Flow).

3. If #I Seal AF' gauge ovemnged, AP can be determined using 1NV125B (Excess Let& Hx Otlt Ctrl) "VCT" or "NCDT" switch position as follows:

• "VCT" position: NC Press minus Excess Let& Hx Otlt Press = #I Seal AF'

• "NCDT position: NC Press minus VCT Press = #1 Seal AP 2.7 Verify adequate #1 Seal Leakoff Flow on the pump to be started as follows:

2.7.1 Determine required #1 Seal Leakoff Flow from Revised Data Book Figure 26 (NC Pump No. 1 Seal Nonnal Operating Range).

2.7.2 Add 0.26 gpm to the minimum required #I Seal Leakoff Flow of Figure 26 to correct for an expected drop in leakof flow on pump start (0.20 gpm) and instrument inaccuracy (0.06 gpm).

2.7.3 Verify the indicated #1 sed Leakoff Flow is within the range of Data Book Figure 26 as adjusted per Step 2.7.2 per one of the following:

El Unit 1 Reactor Coolant Pumps graphic (NCPWALL)

OR 1NVCR5140 (NC Pump Lo Leakoff Flow) (1MC5)

OR El INVCR5121 (NC Pump Hi Leakoff Flow) (1MC5)

OR e Appropriate OAC point 0 ClA1370 (NC Pmp A No. 1 Seal LeakoffLo Flow)

El CIA0436 @'C Pmp A No. 1 Seal Leakoff Flow) 0 ClA1396 (NC Pmp B No. 1 Seal Leakoff Lo Flow) 0 ClA0442 (NC Pmp B No.1 Seal Leakoff Flow) 0 ClA1382 (NC Pmp C No. 1 Seal Leakoff Lo Flow)

CIAO4448 (nC Pnrp C No.1 Seal Leakoff Plow)

CIA1388 (NC Pmp D No. 1 Seal LeakoffLo Flow) 0 CIA0454 (NC Pmp D No. 1 Seal Leakuff Flow)

Enclosure 4.1 OPikAI61501002A Startup and Operation of the NC Pnmps Page 5 of 7 2.8 Verify upper and lower oil pot levels normal, for the p u p to be started, via one of the following:

61 Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR 3 Visual inspection (local)

OR Associated annunciators DARK:

0 "NCP A UPPEWLOWER OIL RESERVOIR LO LEVEL" 1AD-6 F/1 0 "NCP B UPPEIULOWER OIL RESERVOIR LO LEVEL" IAD-6 F12 3 "NCP C UPPERILOWER OIL RESERVOIR LO LEVEL" IAD-6 F/3 0 "NCP D UPPEWLOWER OIL RESERVOIR LO LEVEL" 1AD-6 F/4 NOTE: KC flow is NOT required to the Thermal Barrier Hx whenever NC System temperature is less than 200°F. I 2.9 Verify KC flow to the Thermal Barrier Heater Exchanger normal, for the pump to be started, via one of the foilowing:

0 Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR Associated annunciators DARK:

CI "NCP A THERMAL BARRIER KC OUTLET HIILQ FLOW" 1AD-6 El1 "NCP B THERMAL BARRIER KC OUTLET HIILO FLOW" 1AD-6 E/2 0 "NCP C THERMAL BARRIER KC OUTLET HVLO FLOW" 1AD-6 lY3 "NCP D T K E W L BARRIER KC OUTLET HILO FLOW" 1AD-6 E14 2.10 Verify KC flow to the Upper Motor Bearing Oil Cooler normal, for the pump to be started, via one of the following:

Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR Associated annunciators DARK:

0 "NCP A MTR UPPER BRG KC OUTLET HJLO FLOW" 1AD-6 C/1 D "NCP 5 MTR UPPER 5RG KC OUTLET IIEEO FLOW" 1AD-6 C/2 0 "NCP C MTR UPPER BRG KC OUTLET H X O FLOW" 1AD-6 C/3 0 "NCP D MTR UPPER BRG KC OUTLET IIYLO FLOW" IAD-6 Ci4

Enclosure 4.1 OP/hA/6150/002A Startup and Qperation of the NC Pumps Page 6 of 7 2.1 1 Verify KC flow to the Lower Motor Bearing Oil Cooler normai, for the pump to be started, via one of the following:

0 Unit 1 Reactor GooIant Pumps graphic (NCPMPALL)

OR

• Associated annunciators DARK:

"NCP A MTR LOWER BRG KC OUTLET HVLO FLOW" 1AD-6 D/I 0 "NCP B MTR LOWER BRG KC OUTLET H E 0 FLOW" 1AD-6 B/2 0 "NCP C MTR LOWER ERG KC OUTLET H m O FLOW" IAD-6 D/3 "NCP D MTR LOWER BRG KC OUTLET HILO FLOW" IAB-6 D/4 2.12 Verify annunciator IAD-11, K-6, "230 KV SWlTCHYAFUI VOLTAGE LO" is dark.

2.13 Two minutes prior to starting NC pump, start one oil lit? pump for NCP to be started by pressing the "ON" pushbutton for:

0 "NC PMP OIL LIFT PMP AI" 0 "NC PMP OIL LIFT PMP A2" 0 "NC PMP OIL LIFT PMP B 1" 0 "NC PMP OIL LIFT PMP B2" 0 "NC PMP OIL LIFT PMP C 1" 0 "NC PMP OIL LIFT PMP C2" 0 "NC PMP OIL LIFT PMP D1" "NCP W OIL LIFT PMP D2"

2. The Degraded Bus Voltage Relays (27N) may actuate on the essential bus being supplied by the 6.9KV Switchgear associated with the NC Pwnp to be started in the following step. The alarm condition should clear within 36 seconds.{PIP 95-0287) 2.14 Start desired NC punip by pressing the "ON" pushbutton fer:

0 "NC PMP 1A" "NC PMP 1B" 0 "NC PMP 1C" 0 "NC FMP ID"

Enclosure 4.1 OP/1 /A/6150/002A Startup and Operation of the NC Pumps Page 7 of 7 2.15 Ohserve all pump and motor parameters to verify proper operation.

NOTE: If # l Seal AP gauge overranged, AF' c'an he determined using 1NV125B (Excess Let& IIx Qtlt Ctrl) "VCT" or "NCDT" switch position as follows:

e"VCT"position: NC Press minus Excess Let& Hx Otlt Press = # 1 Seal AP 2.15.1 #I SealAP~2200#.

2.15.2 Inlet Seal Water Flow 7 gpm to 10 gpm.

NOTE: If #I Seal Leakoff Flow B t e is 6 1.0 gpm, the #I Seal Lcw Flow indication shall be used.

The 0.26 gpm flow correction for the required flow rate per Step 2.7.2 of Enclosure 4.1 (Startup and Operation of the NC Pumps),

shall be reduced to 0.06 gpm (instrument accuracy).

2.15.3 #1 Sea1 LeakoffFlow per Step 2.7.

2.15.4 Pump Radial Bearing Temp. 6 225°F.

2.15.5 No. 1 Seal Outlet temp. between 60°F and 235'F.

2.15.6 Pump shaft vibration < 15 mils.

2.15.4 Motor bearings 6 190°F.

2.15.8 Motor winding temp. 6 302°F.

2.15.9 Motor frame vibration 6 3 mils.

2.16 Three minutes after flow in the affected NC Loop exceeds 90%, stop the oil lift pump started in Step 2.13.

2.17 Repeat Steps 2.1 through 2.16 of this enclosure for starting additional NC pumps 2.18 Do NOT file this enclosure in the Control Copy folder of this procedure.

Page 1 of 18 i CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM/CR-4 Start Reactor Coolant Pump 1B CANDIDATE EXAMINER

Page 2 of 18 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Start Keactor Coolant Pump 16.

Alternate Path:

YES Facilitv JPM #:

NCP-081 KIA Ratinnkl:

003 A4.01 (3.313.2)

Task Standard:

Seal injection flow to 1B NCP is restored to 7-10 gpm and I t 3 reactor coolant pump is successfully started.

Preferred Evaluation Location: Preferred Evaluation Method:

Control Room 1 In-Plant - Perform - Simulate X

References:

Candidate: Time Start :

NAME Time Finish:

Performance Ratina: SAT -UNSAT __ Question Grade - Performance Time -

Examiner: I NAME SIGNATURE DATE

Page 3 of 1%

SIMULATOR SET-UP SHEET 1 Reset to any at power SNAP.

I

2. Manually trip the reactor at 1MC-I.

3. Place Steam dumps in Pressure Mode.

4. Trip all (4) four NCP breakers at IMC-10.

5. Reset CA and control flow to maintain SIG levels at 38% NIB level.

6. Place I NV-309 in manual and reduce total seal water flow to - 12 gpm.

7. Freeze the simulator and write to SNAP.

IC SELECTED 213

Page 4 of 18 Teols/Eauipment/Proceduree Needed:

Have enough copies of QP/IIAJ615Q/OO2AEnclosure 4.1 available for each candidate.

READ TO OPERATOR DlRECTlON 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.

INITIATING CUE:

EP/l/A/5QQQ/ES-0.2, Natural Circulation Cooldown has been implemented following a Reactor Trip.

Control problems with INV-309 require the valve be operated in manual. The SRQ instructs you to attempt to start NC Pump 15 by completing OP/l/AJ615Q/QQ2A, NC Pump Operation Enclosure. 4.1 The Initial Conditions of Enclosure. 4.1 have been satisfied.

Page 5 of 1%

START TIME:

jTEP: Obtain a copy of the appropriate procedure

-SAT STANDARD: Operator locates OP/l/A/6158/002A, Enclosure 4.1 EXAMINER W E : When the candidate locates OP/1~Al6150M)02A,hand himlher a clean copy of Enclosure 4.1 and tell himlher that it is current -UNSAT and complete.

COMMENTS:

STEP 2: Caution prior tu Step 2.1: An NC Pump should not be started if associated 6.9 KV switchgear is supplying essential switchgear 1ETA -SAT or IETB and switchyard voltage is less than or equal to 224 KV or only one off-site source of power is available.

STANDARD: Candidate determines that both offsite power sources are available by -UNSAT verifying that the Red CLOSEB lights for PCBs 14, 15, 17 and 18 are LIT and the Green OPEN lights for PCBs 14, 15, 17 and I 8 are DARK and that switchyard vultage is greater than 223 KV on the OAC graphic or on the SWYD VOLTS meter on 1MC-11.

• • CUE: The Red CLOSED lights for PCBs 14, 15, f 7 and 18 are LIT and the Green OPEN lights for PCBs 14, 15, 17 and 18 are DARK.

Switchyard voltage is 230 KV.**

COMMENTS:

• Italicized Cues Are Po Be Used Onfy if JPM Petformanee Is Belnng Simulated.

Page6of18 STEP 3: Note prior to Step 2.1:

1. In order to start an NC Pump, the underfrequency condition should -SAT be cleared by having at least three ef four 6908 V breakers (1TA, 5, 6, D-3) racked in and energized.

2. NC Pump operational configuration restrktions, as follows, will ensure adequate PZR spray for press control, maintain spray line -UNSAT water solid, and prevent thermal stratification of spray line:

e Pump combination should include NC Pump A or NC Pump B, if NC Pump A is in sewice, at least two other pumps should be in service,

• If single pump operation is required, ensure NC Pump B is in sewice, Otherwise, Auxiliary PZR spray flow should be established.

STANDARD: Candidate verifies the Red "6bSD"light is LIT and the Green "OPEN" light is DARK for all four 6900 V breakers. Candidate recognizes from the hitiating Cue that NC Pump 1B is to be started.

• • CUE The Red "CLSD" light is LIT and the Green "QBEN" light is DARK for all four 6900 V breakers."

COMMENTS:

STEP 4: IF Unit 1 is in Mode 5, refer to Tech Spec 3.4.12-1 for temperature limitations on NC Pump starts. (Step 2 . l ) -SAT STANDARD: Candidate determines from NC System temperature that Unit 1 is in Mode 3.

-UNSAT

• • CUE: NC temperature is 557"F.**.

COMMENTS:

• • Italicized Cues Are To Be Used only I f JPM Perfsrmance Is Being Simulated.

Paae 7 of 18 SWP 5: If the pump to be started will be the fourth NC pump in service on Unit 1, verify NC temperature is greater than or equal to 130°F. (Step 2.2) -SAT STANDARD: Per the initiating cue this is the first pump tQ be started. Candidate should go on to step 2.3.

-UNSAT COMMENTS:

STEP 6: Note prior to Step 2.3: If #I Seal AP gauge overranged, AP can be -SAT determined using INV-125B (Excess Letdn Hx Otlt Ctrl) VCT or NCDT switch position as follows:

VCT position: NC Press minus Excess Letdn Hx Otlt Press =

1. I Seal AP -UNSAT m NCDT position: NC Press minus VCT Press = # I Seal AP STANDARD: No action required by candidate.

COMMENTS:

STEP 7: Verify No. 1 Seal DIP is greater than 200 psig for the pump to be started per the following gauges: (Control Board 1MC-5)

• lBNCP: ZNVP 5220 (Step 2.3) -SAT STANDARD: Candidate verifies D/P indication (1MC5: 1NVP5220) for 1 5 NC Pump

_ . UNSAT is overranged. Determines by method described in Note that #I Seal AP is approximately 2200 psid.

• • CUE: NC pressure is 2235 psis and VCT pressure is 30 psig..

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 8 of 18 STEP 8: Verify that the standpipe level for the pump to be started is normal by its associated annunciator DARK. -SAT "NCP B #2 SEAL S-PIP HliLO LVC' IAB-7 A12 (Step 2.4)

I STANDARD: Candidate verifies IAB-7 N2 "NCII B #2 SEAL §-PIPE HVLO LVL" -UNSAT alarm is dark.

• • CUE:. IAD-7 A/2 "NCP R #2 SEAL S-PIPE HULO LVL" alarm is dark.**

COMMENTS:

STEP 9: Verify VCT pressure is equal to or greater than I 5 psig. (Step 2.5)

-SAT STANDARD: Candidate verifies VCT pressure (1MC5: 1NVP5500 or NV GRAPHIC) is greater than 15 psig.

-UNSAT

• • CUE: VCT pressure is 30 psig**

COMMENTS:

STEP IO: Verify 7-10 gpm seal injection flow on the pump to be started by the following gauges: (Control Board MC-5) SAT e 1B NCP: 1NCP5320 (Step 2.6)

STANDARD: Candidate observes seal injection flow (1 NVP5320 on 1MC-5) is

-UNSAT approximately 4-5 gpm

• • CUE: Sea/ injection flow to NC Pump f R is 4 gpm.**

COMMENTS:

• • Italicized Cues Are TQBe Used Onry If JPM Perfsrmance Is Being Simulated.

Page 9 Of 18 I

Increase seal injection flow to NC Pumps CRITICAL STEP XANDARD: Candidate manually adjusts NV-309 to restore seal injection flow to 8 gpm per pump. -SAT EXAMINER CUE: if candidate states he/ske would notify the CRSRO, responc as the CRSRO and instruct the candidate to restore seal injection to its normal value. D UNSAT COMMENTS:

STEP 12: Note prior to Step 2.7:

I.If #1 Seal beakoff Flow is less than 1 gpm, the #ISeal Low SAT Flaw indication shall be used.

2. if adequate #Z Seal Leakoff Flow is NOT indicated in the following step, refer to Enclosure 4.4.

3. If #I Seal AP gauge overranged, AP can be determined using -UNSAT 1NV-125B (Excess Letdn Hx 8tlt Ctrl) "VCT" or "NCDT" switch position as follows:

0 "VCT" position: NC Press minus Excess Let& Hx Otlt Press =

1. I Seal AP "NCDB" position: NC Press minus VCT Press = #1 Seal AP STANDARD: No action required by the candidate COMMENTS:

• • kalicized Cues Are To Be Used O d y I f JPM Performance Is Being Simulated.

Page 10 of 18 I STEP 13: Verify adequate No. ISeal Leakoff flow OR the pump to be started as follows: (Step 2.7)

-SAT Determine required #I Seal Leakoff Flow from Revised Data Book Figure 26. (Step 2.7.1)

-UNSAT STANDARD: Candidate determines required #1 Seal Leakoff Flow from Revised Data Book Figure 26 to be between 1 gpm and 5 gpm.

COMMENTS:

STEP 14: Add 0.26 gpm to the minimum required #I Seal Leakoff Flow of Figure

-SAT 26 to correct for an expected drop in leakoff flow OR pump start (0.20 gpm) and instrument inaccuracy (0.06 gpm). (Step 2.7.2)

-UNSAT STANDARD: Candidate adds 0.26 gpm to the minimum required #I Seal Leakoff flow of Figure 26 for a minimum acceptable value of 1.26 gpm.

CQMMENTS:

• • !tali&& Cues Are To Be Used Qn!y I f JPM Performance Is Being Simulated.

Paae 11 of 18

-SAT STEP 15: Verify the indicated #1 Seal Leakoff flow is within the range of Data Book Figure 26 as adjusted per step 2.7.2 per one of the following.

(Step 2.73)

-UNSAT 0 Unit 1 Reactor Coolant Pumps graphic (NCPMPALL) or 0

1NVCR-5140 (NC Pump Lo Leakoff Flow) (IMC-5) or ZNVCR-5121, (NC Pump Hi Leakoff Flow) (1MC-5) or Computer OAC computer point ClA1376, or CIA0442 STANDARD: Candidate determines indicated #Seal I Leakoff Flow is between 1.26 gpm and 5.0 gpm.

• "CUE: Indicated #1 Seal Leakoff Flow is 3.0 gpm.**

COMMENTS:

STEP 16: Verify upper and lower oil pot levels normal, for the pump to be SAT started, via one of the following. (Step 2.8) e Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR -UNSAT Visual inspection (local)

OR 1AD-6 F/2"NCP B UPPERlLOWER OIL RESERVOIR LO LEVEL" DARK.

STANDARD: Candidate determines that the upper and lower oil pot levels are normal by any of the following:

OAC Graphic indicates normal oil levels 1AD6 F/2 annunciator is DARK.

""CUE: Upper and lower oil pot levels are norma!.**

COMMENTS:

• • !falickedCues Are Po Be Used Only HJPM Performance is Being Simulated.

Page 12 of 18 Verify KC flow to Thermal Barrier Heat Exchanger normal, for the -SAT pump to be started, via one of the following: (Step 2.9) 0 Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR -UNSAT

?AD-6 W 2 ,"NCP B THERMAL BARRIER KC BUTLET HVLO FLOW", BARK STANDARD: Candidate determines that KC flow exists to the thermal barrier heat exchanger by any of the following:

Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR

• IAO-6 E12, "NCPB THERMAL BARRIER KC OUTLET HllLO FLOW. DARK

• • CUE: NC Pump 1B has adequate KC flow to fhe Thermal Barrier Heat Exchanger.**

COMMENTS:

• • ltallcized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 63 of 18 Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

-UNSAT OR IAD-6 Ct2, "NCP 5 MTR UPPER BRG KC OUTLET HVLO FLQW", DARK STANBARD: Candidate determines that KC flow exists to the Upper Motor Bearing. Oil Cooler by any of the following:

Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR e 1AD-6 C/2 "NCP El MTR UPPER BRG KC OUTLET HVLB FLOW", DARK

• • CUE: NC Pump 1B has adequate KC flow fo the upper motor bearing oil cooler.**

COMMENTS:

• • Italicized Cues Are To Be Used Onry If JPM Performance Is Being Simulated.

Page 14 of 18 I STEP 18: Verify KC flow to Lower Motor Bearing. Oil Cooler normal, for the pump to be started, via one of the following: (Step 2.1 I )

-SAT 0 Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OW

-UNSAT

• 1AD-6 Dl2 MCP B MTR LOWER RRG KC OUTLET HllbO FLOW. DARK STANDARD: Candidate determines that KC Row exists to the Lower Motor Bearing. Oil Cooler by any of the following:

e Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR

?AB-6Di2 NCPB W R LOWEK BRG KC OUTLET HI/LO FLOW, DARK

• • CUEAIC Pump I B has adequate KC dEow to the lower motor bearing oil cooler.

COMMENTS:

STEP 20: Verify annunciator 1AD-11, 230KV SWITCHYARD VOLTAGE L O is dark. (Step 2.12)

STANDARD: Candidate verifies alarm 1AD-11~W6 is DARK

• CUE:230KV SWlTCHYARD VOLTAGE 60 Annunciator on 1AD-44, WE is DARK. **

COMMENTS:

• • italicized Cues Are To Be Used Only If JPM Performance is Being Simulated.

Page 15 of 18 STEP 21 : Two minutes prior to starting NC pump, start one oil lift pump for CRfTICAb NCP to be started by pressing the on pushbutton for: (Step 2.13) STEP Ne PMP OIL LIFT PMP B1 (or 82) -SAT STANDARD: Candidate depresses the Red OW pushbutton for NC PMP OIL LIFT PMP B1 or 8%and verifies that the Red ONlight is LIT and the Green OFFlight is BARK for the lift pump started. Candidate then -UNSAT waits two minutes before starting NC Pump I B .

CUE: The ONpusbutton for the oil lift pump has been depressed. The Red ON (ight is LIT and the Oreen OFF light is DARK. Two minutes have passed.**

COMMENTS:

STEP 22: Note prior to Step 2.14:

-SAT

1. If NC pump is NOT started, the oil lift pump should be secured to minimize stress on oil nozzles.

2. The Degraded Bus Voltage Relays (27N) may actuate on the essential bus being supplied by the 6.9KV Switchgear -UNSAT associated with the NC Pump to be started in the following step.

The aiarm condition should clear within 36 seconds.

STANDARD: No action required by the candidate.

COMMENTS:

• • !talicized Cues Are TO Be Used Only If JPM Performance Is Being Simulated.

Page 16 of 18 STEP 23: Start desired NC pump by pressing the ON pushbutton for: CRITICAL NC PMP 1B (Step 2.14) STEP STANDARD: Candidate depresses the Red *ONpushbutton for NG PMP 4 3 and -SAT verifies Red ON light is LIT and the Green OFFlight is DARK and pump amps have stabilized near midscale on ammeter.

• • CUE: The Red ONpushbutton for NC PMP f B has been depressed. -UNSAT The Red ON light is LIT and the Green OFF iighf is DARK and pump amps have stabilized near midscale on ammeter.**

COMMENTS:

STEP 24: Observe all pump and motor parameters to verify proper operation. -SAT (Step 2.15)

STANDARD: Candidate monitors the following parameters and verifies all are normal: -UNSAT

1. I Seal DIP greater than or equal to 200 psid.

Inlet Seal Water Fiow 7-10 gprn (may be greater than 10 due to pump start) e #1 Seal Leakoff Flow appropriate for current Delta P per Revised Data Book Figure 26.

Pump Radial Bearing Temp less than 225°F (1MC5: 1NVP5360 or NCP GFMPHIC).

1. I Seal Outlet Temp between 60°F & 235°F (fMC5: 1NVP5400 or NCP GRAPHIC).

Pump Shaft Vibration less than 15 mils. (NCP GRAPHIC or PANEL on rear of 1MC-6).

Motor Bearings less than 190°F (NCP GRAPHIC).

- Motor Winding Temp less than 302°F (NCP GRBPHIC).

Motor Frame Vibration iess than 3 mils. (NCP GRAPHIC or PANEL on rear of IMC-6).

• CUE: AN operating parameters are normal. **

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 17 of 18 j STEP 25: Three minutes after flow in the affected NC loop exceeds 90%, stop the oil lift pump started in step 2.13. (Step 2.16)

-§AT STANDARD: Candidate waits three minutes and then depress the Green O F F pushbutton and verifies the Green OFF light is LIT and the Red ON: -UNSAT light is DARK.

• • CUE: Three minutes have passed. The Green OFF pushbutton has been depressed. The &reen OFF light is LIT and the Red ON right is DARK.

COMMENTS:

This JPM is complete.

TIME STOP:

• • ltaiicized Cues Are To Be Used Onry If JPh? Performance ! s Being Simuhted.

Page 18 of 1%

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

INlTlATiNG CUE:

EP/1/N5000/ES-0.2, Natural Circulation Cooldown has been implemented following a Reactor Trip.

Control problems with Z NV-309 require the valve be operated in manual. The Sa0 instructs you to attempt to start NC Pump 1B by completing 0P/l/N6150/002A, NC Pump Operation Enclosure. 4.1.

The Initial Conditions of Enclosure 4.2 have been satisfied.

• • /falicizedCues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 1 of 13 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPMICR-5 Establish Feedwater to a Hot Dry Steam Generator GANDKIATE EXAMINER

Page 2 of 13 CATAWBA INlTlAL LICENSE EXAMINATION JOBPERFORMANCEMEASUaE Establish auxiliary feedwater flow to a hot, dry steam generator using Enclosure 8 of EPll/A/5000/FR.H-l (Response to Loss of Secondary Heat Sink).

Alternate Path:

NO Facilitv JPM #:

CSF-005 KIA Ratinnls):

061 A2.04 (3.4/3.8)

Task Standard:

Candidate establishes CA flow to 1B steam generator based on the trend of Core Exit Thermocouples stable or decreasing.

Examiner: /

NAME SIGNATURE DATE COMMENTS

Page 3 Of 13 SIMULATOR SET- UP SHEEP

1. hit to 100% power.

2. Rackout both motor driven CA pumps (LOA-CA017& CA-02%)and close the CAPT T&T valve.

3. Trip both CFPT's and perform actions of E 4 and ES-0.1 until entry conditions to FR-H.1 are satisfied.

4. Allow the steam generators to decrease level until all are less than 12%

WIR. Establish Bleed and Feed and ensure all steps up to Step 33 are complete. The intent is to have all actions fail to restore CA or CMICF until step 33. Ensure CA is reset.

5. Rack-in CA pump 1A (CA-827) and ensure it is capable of being manually started per Enclosure 7.

6. Freeze simulator and write to a snap.

IC SELECTED 248 SIMULATOR OPERATOR INSTRUCTIONS:

1. Reset to IC selected in the setup.

Page4of13 ToolslEquipmemt/Precedures Needed:

Have enough copies of EQ/W50QQ/FR-H.l (Response to Loss of Secondary Heat Sink)

Revision 22 available for each candidate.

READ TO OPERATOR DIRECTIQN TO TRAENE:

B 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.

INITIATING CUE:

The unit is cumently in a Bleed and Feed alignment per EP/l/A/5QQO/FR-H.I (Response to Loss of Secondary Heat Sink). A source of feedwater has been aligned to CA pump 1A and the SRO has directed you to establish CA flow to 1B steam generator per Enclosure 8 (Hot Dry Feed flow Restoration Limits).

Page 5 of 13 START TIME:

STEP 1: Obtain a copy of the appropriate procedure.

-§AT STANDARD: Operator locates EPI1/N50OOIFR-H.I1 Enclosure 8.

EXAMINER CUE: When the candidate locates EPll/A/5000/FR-H.I, hand himlher a clean copy of Enclosure 8 and tell himlher that it is current UNSAT and complete.

COMMENTS:

STEP 2: Establish feedwater flow to only one S/G (Enclosure 8, Step 1)

-SAT STANDARD: From initiating cue, the candidate will feed only 1B §/G COMMENTS:

-UNSAT

• • Italicized Cues Are TO Be Used only If JPM Performance Is Being Simulated.

Page6of13 Close the following valves for the three SlGs to be isolated: CRITICAL (Enclosure 8, Step 2) STEP

-SAT STANDARD: Candidate closes the following valves S/G 1A:

a. Close ICA-62A (CA Pmp A Disch BO S/G l A Isel -UNSAT

• • CUE: The Close pushbuffon for 1CA-62A has been depressed. The Green CLOSED fight is LIT and the Red OPEN fight is BARK.

b. Close ICA-66B (CA Pmp 1 Disch To SIG I A Isel)

• • CUE: The Close pushbutton for ICA-66B has been depressed. The Green CLOSED Iight is LIT and the Red OPEN right is DARK.

e SIG I C :

a. Close 1CA-46B (CA Pmp B Disch To SI6 16 Is01

• • CUE: The Close pushbutton for 1CA-46B has been depressed. The Green CLOSED light is LIT and the Red OPEN light is DARK.

b. Close ICA-SOA (CA Pmp 1 Bisch To SI6 1C Isol)

• • CUE: The Close pushbutton for 1CAdOA has been depressed. The Green CLOSED light is LIT and the Red OPEN light is DARK.

0 SIG I D :

a Close 1CA42B (CA Pmp B Disch To S/G 1D lsol

• • CUE: The Close pushbuffon for 1CA-42B has been depressed. The Green CLOSED light is LIT and the Red OPEN light is DARK.

b. Close 1CA-38A (CA Pmp 1 Disch To S/G 1B Isol)

• • CUE: The Close pushbuffon for ICA-38A has been depressed. The Green CLOSD light is LIT and the Red OPEN fight is DARK.

COMMENTS:

• • italicized Cues Are To Be Used Only if JPM Performance Is Being Simulated.

Page 7 cf 13 STEP 4: Ensure CA System valve control - RESET (Enclosure 8, Step 3)

-SAT XANDARD: Candidate ensures CA system reset by verifying the yellow CA SYS VLV CTRL TRAIN A (B) RESET lights are lit.

-UNSAT CUE: The Yellow CA SYS VLV CTRL TRAlN A RESET light is LIT and the Yellow CA SYS VLV CTRL TRAIN B RESET right is L I F * ~

COMMENTS:

• • italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 8 of 13 STEP 5: Close the following CA flow control valves: (Enclosure 8, Step 4) CRlTlCAb STEP STANDARD: Candidate turns the potentiometer for the following valves in the counter-clockwise direction until 0.0 is displayed: -SAT ICA-64 JCA Pump #I Flow TO S/G I A )

• • CUE: The potentiometer for ICA-64 is turned in the counter-clockwise direction. The controller display indicates O.O** -VNSAT

• 1CA-BO (CA Pump 1A Flow To S/G I A )

• • CUE: The potentiometer for ICA-60 is turned in the counter-clockwise direction. The controller display indicates O.O**

ICA-52 (CA Pump #1 Flow To S/G 1B)

EXAMINER NOTE: It is critical that the flow controller to steam generator 1B from CA pump l A (ICA-52) be closed to prevent feeding the steam generator in an uncontrolled manner. Closing the other controllers is not critical since no source of feedwater is available via that flow path.

• • CUE: The potentiometer for 1CA-52 is turned in the counter-clockwise direction. The controller display indicates O.O**

• ICA-56 (CA Pump I A Flow TQS/G1B)

• • CUE: The potentiometer for ICA-56 is turned in the counter-clockwise direction. The controller display indicates 0.0"'

ICA-48 (CA Pump #I Flow To S/GIC)

"*CUE: The potentiometer for ICA-48 is turned in the counter-clockwise direction. The controller display indicates 0.0**

1CA-44 (CA Pump 1B Flow To S E IC)

'*CUE: The potentiometer for ICA-44 is turned In the counter-clockwise direction. The controller display indicates O.O**

1CA-36 (CA PUMP#? Flow To S/G 1D)

• • CUE: The potentiometer for ICA-36 is turned in the counter-clockwise direction. The controller display indicates OB**

1CA-40 (CA Pump 1El Flow To S/G 1D)

• • CUE: The potentiometer for ICA-40 is turned in the counter-clockwise direction. The controller display indicates 0.0**

COMMENTS:

• • \talicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 9 of 13 I STEP6: Do not continue in this enclosure until a source of feedwater is available to the SIG(s). (Enclosure 8, Step 5)

-SAT STANDARD: Candidate determines from the initiating cue that 1A CA pump is -UNSAT available)

EXAMINER CUE: The SRO directs you to start the 1A CA pump.

COMMENTS:

STEP 7: Verify core exit T/Cs - Stable or Decreasing (Enclosure 8:Step 6)

STANDARD: Candidate determines from the RVklS display on 1MC-I or from the -SAT OAC the core exit thermocouple trend.

EXAMINER NOTE: This JPM has two different operator actions depending on the temperature trend of the TICS. -UNSAT If the TICS are stable or decreasing, the candidate will perform JPM step 8.

If the T/Cs are increasing the candidate will transition to the step 6 RNQ end perdorm JPM step 9.

• • CUE: The core exit thermocouples are increasing**

COMMENTS:

• • ltalicired Cues Are To Be Used Qniy If JPM Performance Es Being Simulated.

Paae 10 of 13 1 STEP81 Maintain feed flow rate less than or equal to 105 GPM until W/R SIG level is greater than 12% (22% ACC) (Enclosure 8, Step 7)

CRITICAL STEP STANDARD: Candidate starts the I A CA pump by depressing the ONpushbutton -SAT and verifying that the Red ON light is LIT and the Green OFF light is BARK. Candidate then turns the potentiometer for 1CA-56 in the clockwise direction to obtain a flow rate to 1B steam generator of less than or equal to 155 gpm. -UNSAT CUE: The 0Npushbutton for the 1A CA pump has been depressed.

The RED ON light for CA Pump 7A is LIT and the GREEN OFF light is DARK. The potentiometer for 1CA-56 has been turned in the clcckwise direction. Flow rate to 113 steam generator is 95 gpm. **

COMMENTS:

STEP 9: If core exit TlCs are increasing THEN feed S/G at a rate required to CRITICAL decrease core exit T/Cs temperature. (Enclosure 8,Step 6. RNO.) STEP STANDARD: Candidate starts the I A CA pump by depressing the ON pushbutton -SAT and verifying that the Red ON light is LIT and the Green OFF light is DARK. Candidate then turns the potentiometer for ICA-56 in the clockwise direction to obtain a flow rate to I 6 steam generator that results in a decrease in core exit thermocouple readings. -UNSAT

• • CUE: The OW pushbutton for the 1A CA pump has been depressed.

The RED ON light for CA Pump 1A is LIT and the GREEN OFF light is DARK. The potentiometer for 7CA-56 has been turned in the clockwise direction. Flow rate to 1B steam generator has increased. Core exit thermocouple temperatures are decreasing.**

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page I 1 of 13 STEP I O : When W/R S/G level is greater than 12% @I%), then feed flow can be increased to desired rate. (Enclosure 8, Step 8 ) §AT STANDARD: Candidate determines that wide range steam generator level is less than 12% and continues to monitor level increase. Candidate continues to step 9. -UNSAT

• • CUE: 1B steam generator wide range Eevel is less than 72%**.

COMMENTS:

EXAMINER NOTE If this jpm is performed on the simulator, loop B Thot will be greater than 550°F in the next step STEP 11: Verify NC T-HOT associated with the SIG being fed - LESS THAN 550°F. (Enclosure 8,Step 9) -SAT STANDARD: Candidate verifies temperatures for IT Hot leg using OAC NC graphic, WVLlS monitors. recorderlNCCR5850 for Loop f B Thot on 1MC-05 is approximately 562°F

• • CUE: B loop hot reg temperature is indkating 530 4**.

30MMENTS:

EXAMINER NQTE: If this JPM is being performed in the control room, continue with JPM Step 12 after providing the cue in JPM Step 12. If this JPM is being performed on the simulator, terminate the JPM by telling the candidate that another operator will complete Enclosure 8.

• • italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 12 of 13 Step 12 Verify SIG being fed - Intact. (Enclosure 8, step I O )

-SAT STANDARD: Candidate verifies the following:

• S I 6 1B pressure not decreasing in uncontrolled manner using 1MC-2, Steam pressure Channels 1,2,3.

Ail 1B SIG related EMR: 29, 92,73, 33 trip 1 lights DARK. -UNSAT SIG IB lwei increase is under control of the candidate

• • CUE:

Steam generator I B is pressurized and pressure is not decreasing in an uncontroNed manner.

• EMF-27, 72, 73 and 33 trip 1 lights are BARK 0 Sfeam generator 1B level is under operator control COMMENTS:

This JPM is complete.

TIME STOP:

• • !falicked Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page13of13 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) lNlTlATlMG CUE:

The unit is currently in a Bleed and Feed alignment per EP/1/Af5000/FR-H.1 (Response to Loss of Secondary Heat Sink). A source of feedwater has been aligned to CA pump 1A and the SRO has directed you to establish CA flow to 1B steam generator per Enclosure 8 (Hot Dry Feed flow Restoration Limits).

• • italicized Cues Are To Be Used Only If JPM Petformame Is Being Simulated.

RESPONSE TO LOSS OF SECONDARY HAT SINK EP/l/A/5000/FR-#.I I ACTION/EXPECTEO RESPONSE I RESPONSE NOT OBTAINE 17 1

- I. Establish feedwater to only one SiG.

2. Close the following valves fortbe three S/Gs to be isolated:

e S/G la:

- a. Close ICA-62A (24 Prnp A Bisch To a. Perform the following:

S/G 1A Isol).

- 1) Close TCA-60 (CA Pump 1A Flow To SIG IA).

- 2) Dispatch operator to close ICA-62A (CAPmp A Disch To S/G I A 1 ~ 0 1 ) (DH-589, DD-EE, 44-45, Rm 591).

- b. Close ICA-66B (CA Pmp IDisch To b. Perform the following:

S/G 1A Isol).

1) Close 1CA-64 (CA Pump #1 Flow To S/G ?A).

- 2) Dispatch operator to close ICA-66.B (CA Pmp 1 Bisch To S/G 1A I d ) (DH-584, DDEE, 44-45, Rm 591).

SIG 1B:

- a. Close ICA-58A (CA Pmp A Disch o a. Perform the follcwing:

S/G 1B Isol).

- 1) Close ?CA-56 (CA Pump ? A Flow To SIG 15).

- 2) Dispatch operator to close 1CA-58A (CA Pmp A Disch To S/G 1B Iso~) (DH-586, DD-EE, 52-53, Rm 572).

- b. Close ICA-54B (CA Prnp 1 Bisch To b. Perform the following:

SIG 1B lsol).

- 1) Close ICA-52 (CA Pump # I Flow To SIG 1B).

- 2) Dispatch operdor to close 1CA-54B (CA Pmp 1 Disch To S/G 1B IsoI) (DH-584, DD-E, 52-53, 572).

I A C T I O N / E X P E C T E D RESPONSE RESPONSE NOT O B T A I N E D

2. (Continued) 0 S/G I C :

- a. Close ICA46B (CA Pmp B Bisch To a. Perform the following:

S/G ? C Isol).

- 1) Close 1CA-44 (CA Pump 1B Flow To SIG IC).

- 2) Dispatch operator to close 1CA46B (CA Pmp B Disch To S/GI C Isol) (DH-586, m, 53-54 Rm 572).

- b. Close 1CA-50A (CA Pmp Disch To b. Perform the following:

SIG 1C Isol).

- 1) Close 1CA-48 (CA Pump #IFlow To SI6 1C).

- 2) Dispatch operator to close ICA-5OA (CA Pmp ? Disch To SIG I C Isol) (DH-584, E-53, Rm 572).

SiG ID:

- a. Close ICA-42B (CA Pmp B Bisch To a. Perform the following:

SIG 1D Isol).

- 4 ) Close 1CA-40 (CA Pump 1B Flow To S/G D).

- 2) Dispatch operator to close ICA-4213 (CA Pmp B Disch To SIG I D IsoI) (DH-586, DD-EE, 43-44, Bm 591).

- b. Close ICA-38A (CA Pmp 1 Disch To b. Perform the following:

SIG I D Isol).

- 1) Close 1CA-36 (CA Pump #I Flow To SIG ID).

- 2) Dispatch operator to close 1CA-38A (CA Pmp I Disch To SIG 4D 1 ~ 0 1 ) (DH-584, DD-EE, 43-44, Rm 591).

- 3. Ensure CA System valve control ~

RESET.

I I

I Hot Drv Enclosure 8 - Page 3 of 4

• SiG Feed Flow Restoration Limits I I

4. Close the following CAflova control valves:

- 1CA-64 (04Pump #1 Flow To S/G IA)

- e ICA-60 ((34 Pump 1A Flow To S/G IA)

-e 1CA-52 (CA Pump # I Flow To S G IB)

-* ICA-56 (CA Pump 1A FlowTo SIG le)

- 0 1CA-48 (CA Pump # I Flow TO S/G1C)

- 1CA-44 (CA Pump 1B FlowTo 36 I C )

- 1CA-36 (CA Pump #9 Flow To S/G 4 D)

-

• 4 CA-40 (CA Pump 1B Flow TO S16 ID).

- 5. Do not continue in this enclosure until a source of feedwater is available to the WC(S).

- 6. Verify core exit T/Cs DECREASING.

- STABLE OR Perform the following:

- a. core exit T/Cs are increasing, T U feed S/G at rate required to decrease core exit Tics temperature.

- b. a m s t e p 8.

NOTE

_ I CF fiow indication is not accurate at I00 GPM. If CF or CM flow established, flow rate of 100 GPM may be observed on the CA flow instrumentation, or approimated by feeding at minimum rate that obtains S G WR level response or increase in feed f(ow indication.

- 7. Maintain feed flow rate less than or equal to IO0 CPM until WIR SIC level is greater than 12% (21% ACG).

8. WIR S/G level is greater than 14%

(21% ACC), feed flow can be increased to the desired rate.

I, i RESPONSE TO LOSS OF SECONDARY HEAT SINK EPIl/N5000/FR-H. 1 Enclosure 8 Page 4 of 4

~

ACTIONlEXPECTED RESPONSE RESPONSE NOT OBPAINE D

- 9. Verify NC T-Hot associated with the S/G - Do not continue in this endosure until being fed LESS THAN 550°F. NC T-Hot associated with S/G being fed Is less than 55WF.

- 10. Verify SIG being fed INTACT. Perform the following:

- a. IE.S/G being fed is faulted OAruptured, TYN establish feedwater flow to another SIG observing previous flowrate requirements.

- b. E an intact S G is not available to be fed, T#EN establish feed Row lo a ruptured or faulted S/G.

- c. WHEN a ruptured -faulted S/G is no longer required for heat sink, THEN isolate feed flow to the ruptured or faulted SIG.

Page 1 of 16 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM SIM-6 Transfer Emergency Care Cooling System to Hot Leg Recirculation CANDIDATE EXAMINER

- ~~

Page 2 of 16 CATAWBA INITIAL LlCENSE EXAMINATION JOBP~BFORMANCEMEASURE

~

Task Trt sfe the nergency core cooling systems to hot leg recirculation with flow indicated from both trains of the ND System Alternate Path:

YES Facility JPM #:

NI-098 KlA Ratinca6sk 006 A4.07 (4.4/4.4)

Task Standard:

Candidate establishes hot leg recirculation with flow indicated from both trains of the ND System p Preferred Evaluation Method:

Simulator 1 In-Plant ~ Perform Simulate ~

References:

EP/l/N5000/ES-l .4 Transfer to Hot Leg Recirculation Revision 005.

Candidate: Time Start :

NAME Time Finish:

Performance Ratinq SAT __ UNSAT __ Question Grade m _ Performance Time ___

COMMENTS

Page 3 of 16 SIMULATOR SEP-UP SHEET

1. Reset to any at power IC set.

2. Insert MAL-NI001B SI Pump B Failure Set = BOTH

3. Insert MAL-NIOOIA SI Pump A Failure Set = MANUAL

4. Insert MAL-NCO13A (Cold Leg Break), Severity Value = 27.5 inch.

5. Complete all procedure actions (EWE-0, E-l, ES-1.3) up to point of placing ECCS systems in Hot Leg Recirc alignment.

6. Freeze simulator and write snap.

7. IC selected 214 SIMULATOR OPERATOR INSTRUCTIONS: .-

I. Reset to snag 214.

Page 4 of 16 ToolsiEquilament/Procedures Needed:

Have enough copies of EQ/l/A/5000/ES-1.4 (Transfer to Hot Leg Recirculation) Revision 5 available for each candidate.

READ TO OPERATOR DIRECTION TO TRAINEE:

Iwill 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.

INITIATING CUE:

A LOCA on the NC System has been in progress for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The Emergency Core Cooling System (ECCS) is in the Cold Leg Recirculation lineup. 1B NI Pump failed to start OR the Safety Injection and could not be started manually. The SRO instructs you to transfer the ECCS System to Hot Leg Recirculation per EPil/AMJ05/ES-1.4.

Page 5 of I 6 START TIME:

STEP 1: Obtain a copy of the appropriate procedure.

-SAT STANDARD: Operator locates EP/l/N5000/ES-1.4 EXAMINERS CUE: When the candidate locates EPillA15000lES-2.4

, hand himlher a copy and tell himlher that it is current -UNSAT and complete.

COMMENTS:

STEP 2: Align NI Pumps for Hot Leg Recirculation: (Step 1.)

Stop Nl Pump IA. (Step 1.a) -SAT STANDARD: Candidate depresses NI Pump A OFF pushbutton (1MC-11).

Verifies the Green OFF light is LIT, and the Wed ON light is -UNSAT DARK.

• • CUE: The 1\11 pump A OFF pushbuffon has been depressed. The Green OFF light is LlT and the Red ON light is DARK.**

COMMENTS:

STEP 3: Close 4NI-2 18A (NI Pump 1A C-Leg Inj Isol). (Step 1.b.)

-SAT STANDARD: Candidate depresses INI-I 18A CLOSE pushbutton (IMC-I 1).

Verifies the Green CLSD light is LIT and Red OPEN light is DARK

• • CUE: The close pushbuffon for INI-118A has been depressed. The -UNSAT Green CLOSED light is LIT and the Red OPEN light is DARK.

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulateds

Page 6 of 16 STEP 4: Place the PWR BISCON For 1Ni-121A switch to the ENABLE position. (Step 1.c.) -SAT STANDARD: Candidate places the PWK DISCQN For 4NI-221A switch to the ENABLEposition UNSAT

• • CUE: The POWER DISCONNECT for JNI-IZIA switch is in the ENABLY position. **

COMMENTS:

STEP 5: Open 1NI-121A (NI Pump 1A To H-Legs B&C) (Step 1.d.)

-SAT STANDARD: Candidate depresses 1 NI-121A (NI Pump A to H-Legs B & C) OPEN pushbutton (1MC-11). Verifies the Red OPEN light is LIT and the Green CLSD light is BARK.

-UNSAT

• CUE: The OPEN pushbutton for 1N1-121A as been depressed. The RED OPEN light is UT, and the GREEN CLOSED light is DARK.

COMMENTS:

STEP 6: WHEN INI-121A is open, THEN start NI Pump 1A. (Step 1.e.) -SAT STANDARD: Candidate depresses NI Pump 1A ON pushbutton (IMC-11).

Observes that the Green O W light is LIT and the Red ON light is DARK, no amps indicated OR meter. -UNSAT

• • CUE: The Green QFF light is LIT and the Red ON light is DARK for NI Pump 1A. No amps are indicated on the meter**

COMMENTS:

• • Italicized Cues Are To Be Used Qnly If JPM Performance Is Being Simulated.

Page 7 of 16 Stop Ni Pump ZB. (Step 1.f.)

TANBARD

Candidate determines that Ni Pump B is currentiy off. Determines -SAT the Green OFFlight is LIT, and the Red ON light is DARK.

• • CUE: MI pump B is off. The Green OFFFIigM is LIT and the Red O N -UNSAT light is DARK. **

COMMENTS:

STEP 8: Close 1NI-450B(NI Pump 1B C-Leg Inj [sol). (Step .l.g.)

-SAT STANDARD: Candidate depresses 1NI-150B CLOSE pushbutton (1MC-1 I).

Verifies the Green ChSD light is LIT and Red OPEN light is DARK

• • CU: The close pushbuffon for fNbl50B has Been depressed. The -UNSAT Green CLOSED light Ls U T and the Red OPEN fighfis DARK.

COMMENTS:

STEP 9: Place the PWR DISCON For 1NI-162A switch in ENABLE.

(Step 1.h.) -SAT STANDARD: Candidate places the PWR DISCON For INI-162A switch in ENABLE.

-UNSAT

• • CUE: The POWR DISCQNNECT for IMI-162A swifch is in the ENABLE position.**

• • italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 8 of 16 (Step 1.L)

-SAT STANDARD: Candidate depresses 1Nl-162A CLOSED pushbutton (1MC-1 I).

Verifies the Red OPENlight is LIT and the Green CLSD light is DARK.

-UNSAT

• • CUE: The CLOSED pushbutton for INI-162A as been depressed. The RED OPEW light is DARK, and the GREEN CLOSED right is LIT. **

CQMMENTS:

STEP 14: Place the PWR DISCON For IN!-1528 switch in ENABLE.

(Step 1.j.) -SAT STANDARD: Candidate places the PWR DISCON For INI-1528 switch in ENABLE.

-UNSAT

• • CUE: The BOWER DISCONNECT for INI-15213 switch is in fhe ENABLE posifion.**

COMMENTS:

STEP 12: Open 1NI-152B (NI Pump 15 To H-begs A&D) (Step 1k.)

-SAT STANDARD: Candidate depresses 1NI-152B OPENpushbutton (1 MC-4 1).

Verifies the Red OPEN light is LIT and the Green CLSD light is BARK.

-UNSAT CUE: The OPEN pushbutton for INI-152B as been depressed. The RED OPEN right is UT, and the GREEN CLOSED light is DARK.

COMMENTS:

• • italicized Cues Are To Be Used Only MJPM Performance !s Being Simulated.

Page 9 of 16

-SAT 3TANDARD: Candidate depresses NI Pump IF3 ON pushbutton (IMC-4 1).

Observes that the Green OFF light is LIT and the Red ON light is BARK, no amps indicated on meter. UNSAT

• • CUE: The Green OFF light is LIP and the Red OM light is DARK for NI Pump 16. No amps are indicated on the meter**

COMMENTS:

STEP $4: Verify flow from at least one train of NI. (Step 2.)

-SAT STANDARD: Candidate determines 0 flow on NI flow meters. Transitions to Step 2 RNO and proceeds to Step 5.

• • CUE: No flow is indicated from either hll Wain.** -UNSAT COMMENTS:

STEP 15: a. Notify station management that Nl flow not indicated SAT (Step 2. RNO)

b. GO TO Step 4 STANDARB: Notifies management of RO NI flow indicated. Goes to step 4 -UNSAT Examiner Cue: When management is called, say I understand that NO NI flow indicated.

COMMENTS:

• • italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 10 of 16 Align ND Pumps for Hot Leg Recirc as follows: (Step 4.a.)

a. Verify following valves - CLOSED CRITICAL 1NB-IS (ND Pump la Sur3 From Loop B) STEP e 1ND-2A (ND Pump 1A Suct From Locp B IND-36B (ND Pump 1B Suct From Loop C) 1ND-37A (ND Pump 1B Suct From Loop C)

-SAT 0 1NB-32A (NB Train 1A Hot Leg lnj Isol) -UNSAT e 1ND-65B (ND Train 113 Hot Leg Inj Isol)

STANDARD: Candidate verifies the following:

0 IND-1B (NB Pump I A Suct From Loop B) Red OPEN light dark and Green CLOSED light lit.

0 1NDZA (ND Pump 1A Suct From Loop B) Red OPEN light dark and Green CLOSED light lit.

0 1NB-46B (ND Pump 18 Suct From Loop C) Red OPEN light dark and Green CLOSED light lit.

0 1ND-37A (ND Pump 1B Suct From Loop 6 ) Red OPEN light dark and Green CLOSEDlight lit.

e IND-328 (ND Train ?A Hot Leg lnj Isol) Red OPEN light dark and Green CLOSED light lit.

0 1ND-65B (ND Train I B Hct Leg hj Isol) Red OPENlight dark and Green CLOSED light lit.

• • CUE:

. qND45 Red OPEN Eight DARK and Green CLOSED light LIT.

0 IND-2A Red QPEN light DARK and Green CLOSED lighf LIT.

e IND-365 Red OPEN I i h t DARK and Green CLOSED light LIT.

0 7ND-378 is closed.

e IND-32A Red OPEN [ight DARK and Green CLOSED light

. LIT.

7ND-655 Red OPEW light DARK and Green CLOSED light LIT.

COMMENTS:

• • Italicized Cues Are To Be Used Only If JBM Betformance Is Being Simulated.

Page 11 of 16 STEP 17: Place PWR DISCON FOR IN[-1838 to ENABLE (Step 4.b.) CRITICAL STEP 3TANDARD: Candidate places the PWR DISCON For IN!-1838 switch to the ENABLE position -SAT

• • CUE: The POWER DISCONNECT for 1Nb183B switch is in the ENABLE position. **

-UNSAT COMMENTS:

STEP 1%: Open 1NI-2838 (ND HdrA&B Hot Leg inj Isol) (Step 4.c.) CRDTICAL STEP STANDARD: Candidate depresses 1Nl-483B OPEN pushbutton (1 MC-11).

Verifies the Red OPEN light is LIT and the Green CLSD light is -SAT DARK.

• CUE: The OPEN pushbutton for 1Pl!-183B as been depressed. The RED OPEN light is LIT and the GREEN CLOSfDDlight is -UNSAT DARK**.

ZOMMENTS:

STEP 19: For A ND Train: (Step 4.d.)

-SAT

1) Verify 1NS-438 (ND Pmp 1A to Cont Spray Hdr) - CLOSED STANDARD: Candidate observes INS-438 Red OPEN light is DARK and the Green CLSD light is LIT. -UNSAT

• • CUE: The INS-43A Red OPEN light is DARK and the GREEN CLOSED light Is LIP*.

COMMENTS:

• • /talicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

P a w 12 of 16 STEP 20: Place PWR DISCON FOR ZNI-173A in ENABLE. (Step 4.d.2))

-SAT 5TANDARD: Candidate places the PWR DISCON For INI-1738 switch in the ENABLE.

• CUE: The PQWER DISCONNECT for 7NL773A switch is in the -UNSAT ENABLE position. **

COMMENTS:

STEP 21: Close 1NL173A (ND Hdr 1A to Cold Legs C&D). (Step 4.d.3)) -SAT STANDARD: Candidate depresses 1NI-193A CLOSED pushbutton (4 MC-11).

Verifies the Red OPENlight is BARK and the Green CLSB light is LIT. -UNSAT

• • CUE: The CLOSED pushbuffen for INE-lT3A has been depressed.

The RE5 OPEN light is DARK, and the GREEN CLOS5 fight is LU. **

COMMENTS:

EXAMINER NOTE: It is critical for the candidate to open EITHER 1NB-32A (ND Train I A Hot Leg inj. Isol) OR ZND 658 (ND Train 1B Hot Leg hi. Isol).

• • ltaliclzedCues Are To Be Used Only If JBM Performance Is Being Sirnulafed.

Paae 13 of 16 CRITICAL STEP 22: Open 1ND-32A (ND Train I A Hot Leg lnj. Isol). (Step 4.d.4)) STEP STANDARD: Candidate depresses 1ND-328 OPEN pushbutton (IMC-I 1). -SAT Verifies the Red OPEN light is LIT and the Green CLSD light is DARK.

• CUE The OPEN pushbutton for 7ND-32A has been depressed. The -UNSAT RED QPEiV light is &IT and Ute GREEN CLOSED light is DARK**.

COMMENTS:

STEP 23: For El ND Train: (Step 4.e.l))

-SAT

2) Verify INS-38B (RID Pmp 15 to Cent Spray Hdr) - CLOSED STANDARD: candidate observes INS-333 Red OPEN light is DARK and the Green CLSD light is LIB. -UNSAT

• • CUE: The 1NS-38B Red OPEN Eight is DARK and the G R E N CLOSED light is UT**.

COMMENTS:

STEP 24: Place PWR DISCON FOR 1NI-1788 to ENABLE (Step 4.e.2))

-SAT STANDARD: Candidate places the PWR DISCON For lNI-1788 switch to the ENABLE? position

• • CUE: The POWER DISCQNNECT for INE-f78B switch is in the -UNSAT ENABLE posifion. **

COMMENTS:

• • ltalkized Cues Are To Be Used Qn/y I f JPM Petformance k Being Simulated.

Page 14 of 16 STEP 25: Close INI-1785 (ND Hdr B to Cold Legs C&D) (Step 4.e.3)) -SAT STANDARD: Candidate depresses 1Nl-1788 CLOSED pushbutton (IMC-11).

Verifies the Red OPEN light is DARK and the Green CLSD light is LIT.

-UNSAT

• • CUE: The CLOSEDpushbuffon for 1NI-178B as been depressed. The RED OPEN light is DARK, and the GREEN CLOSED light is LIT.*

COMMENTS:

CRITICAL STEP 26: Open IND-65B (ND Train 15 Hot Leg Inj. Isol). (Step 4.12.4)) STEP STANDARD: Candidate depresses 1NB-6513 OPEN pushbutton (1MC-11). -SAT Verifies the Red OPEN light is LIT and the Green CLSD light is BARK.

• • CUE: The OPEN pushbuffon for 1ND-65B as been depressed. The -UNSAT RED OPEN light is LIT and the GREEN CLOSED light is DARK**.

COMMENTS:

STEP 27: Ensure Maniter Light Panel Group 6 HLR lights - LIT. (Step 5.)

-SAT STANDARD: Candidate verifies Monitor Light Panel Group 6 HLR lights are LIT.

• • CUE: The Monitor Light Panel Group 6 HLR lights are /it.**

-UNSAT COMMENTS:

• • italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 15 of 16 STEP 28: Verify flow to NC Hot Legs from at least one train of ND. (Step 6.) -SAT STANDARD Verify flow to NC Hot Legs as indicated on NB to Hot Legs B$C flow meter jZNIP5010) on 1 MC-11.

-UNSAT

• • CUE Flow to the NC Hot begs is reading 4500 gpm on 1NIP5010.**

COMMENTS:

STEP 29: RETURN TO procedure and step in effect.

TIME STOP:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 16 of 16 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMlNER UPON COMPLETION OF TASK)

INITIATING CUE:

A LOCA on the NC System has been in progress for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The Emergency Core Cooling System (ECCS) is in the Cold Leg Recirculation lineup. 4s NI Pump failed to start on the Safety Injection and could not be started manually. The SRO instructs you to transfer the ECCS System to Hot Leg Recirculation per EP/l/A15OOO/ES-I.4.

• • Italicized Cues Are To Be Used On& If JPM Performance Is Being Simuk$ed.

Duke Power Company ?rocedure No.

Catawba Nuclear Station EP/l/A/50QO/ES-I.4 Cevision No.

QQ5 rransfer to Hot Leg Recirculation iloctronic Reference No.

CPOO94CX

A. Puraose This procedure provides the necessaty instructions for transferring the safety injection system to Hot Leg Recirculation.

B. Svm~t5msor Entw Conditions This procedure is entered from:

a. EP/l/N5000/-1 (Loss Of Reactor Or Swndary Coolant), Step 20, vhen the specified time interval has elapsed.

b. When a decision is made, based u p ~the l recommendation of station management, that transfer to Hot Leg Recirc is required. Transfer to Hot Leg Reciffi might be required eventually, after transferring to Cold beg Reeirc during the implementation of:

a EP/l/N5000/ES-1.2 (Post bOCA Cooldovm And Depressurization) a EP/1/N5000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired)

EP/l/N500(3/ECA-3.2(SGTR With Loss Of Reador Coolant - Saturated Recovery Desired).

II CNS EP/I/N500WES-1.4 I TRANSFER TO HOT LEG RECIRCULATION 1 PAGENQ.

20f5 11 ACTIONlEXPECTED RESP ONSE I I RESPONSE NOT OBTAINE D 1 C. Operator Actions

1. Align NI pumps for Hot Leg Reeirc as fQlhVS:

- a. Stop NI Pump IA.

- b. Close INI-118A (NI Pump I A C-Leg inj h. Perform the failawing:

Isol).

- 1) Dispatch operator to close 5NI-7 18A (NI Pump I A C%eg inj Isol)

(A5-553, GG-HH, 5554, Rm 235).

- 2) &&!4 INI-118A is closed, T&@l perform steps 1.c through 1.e.

- 3) a m Step l.f.

- c. Place "PWR DISCON FOR INI-12IA" switch in "ENABLE".

- d. Open INI-121A (Nl Pump 1A To - d. Dispatch operator to open 1NI-l21A(NI

1. -begs WC). Pump 1A To H-Legs B&C) (AB-572, FF-GG, 52, Rm 348).

- e. 4NI-I21Aisopen,~stari NI Pump 18.

- f. Stop NI Pump 1B.

- g. Close ZNI-I508 (NI Pump 18 &Leg Inj g. Perform the following:

Isol).

- 1) Dispatch operator to close 1NI-I505 (NI Pump 1B C-Leg Inj Isol)

(AB-550, HH-JJ, 53-54, Rm 234).

- 2) W m 1NI-150B is closed, THEN perform steps I.h through 1.1.

- 3) GQPOStep 2.

- h. Place "PWR BlSCON FOR 1NI-162A" switch in "ENABLE".

- I. Ciose INI-1628 (NI To C-Legs Inj Hdr - i. Dispatch operator to dose lNI-l62A(NI Isol). Bo C-begs Inj Mdr Isol) (AB-567, J4-51, Rm 318A).

I - j. Place "PWR DlSCClN FQR 1NI-152W switch in "ENABLE".

k. Open IN!-I526 (NI Pump 1B To - k. Dispatch operator to open 1Nl-1525 (NI H-Legs A&D)~ Pump 4E1 To H - L ~ sA&D) (AB-580, GG-HH, 9-53, Rrn 419).

- I. 1NC452B is open, THEN start NI Pump 15.

2. Verify flow from at least one trails of NI. Perform the following:

- a. Notify stathn management that Ni flow not indicated.

- b. GQIQStep4.

- 3. RETURN TO Procedure and step in effect.

4. Align ND pumps for Hot Leg Redrc a s follows:

a. Verify the foilowing valves - CLOSED. a. Perform the fQllOVdng:

- E 1NB-2B (ND Pump 1A Suct Frm - 1) Contact station management for Loop 5) guidance to align NI or ND for Hot

- 1ND-24 (ND Pump 1A Suct Frm Loop e)

Lee Redrc.

-e 1ND-468 (NDPump 1B Suct Frm - 21 RETURN TO Procedure and step in Loop C) effect.

- 0 1 ND97A (ND Pump 1B Suct Frm Loop C)

- 1ND-32A (NDTrain 1A Hot k g h j isol) e 1ND-65B (ND Train 1B Hot Leg Inj Isol).

Ir II CNS EP/1/A/5000/ES-1.4 I

TRANSFER TO HOT LEG RECIRCULATION I PAGE NO.

4 of 5 11

4. (Continued)

- c. Open INI-I838 (ND Hdr A&B Hot Leg c. Perform the following:

Inj Isol).

1) Close ND train discharge crossovers:

- e IND-32A (ND Train I A Hoot Leg Inj Isol)

- 0 1ND-65B (ND Train 113 Hot beg lnj Isol).

- 2) Open lNI-l73A(ND Hdr IAtoCold Legs C&D).

- 3) Dispatch operator to open INI-1835 (ND Hdr A&B Hot Leg Inj Isoi)

(AB-571, E-FF, 52-53, Rm 333A).

- 4) Y&j&l INI-183B is open, perform Step 4.

- 5) QQmStep 5.

d. For A NB Train:

- 1) Verify INS-43A(ND Pmp 1ATo - 1) mmStep4.e.

Cent Spray Hdr) - CLOSED.

- 2) Place "PWR DISCON FOR 1NI-I73A" switch in "ENABLE".

- 3) Close lNI-l73A(ND Hdr I A T o - 3) Dispatch operator to close INI-173A Cold Legs C&D). (ND Hdr 1A To Cald Legs 0)

(AB-566, "-52, Wm 318A).

- 4) Open f ND-32A (NDTrain 1A Hot 4) Dispatch operator l o open IND-328 beg Inj Isol). (ND Train 4A Hot Leg Inj Isdj (85-568, IL-MM, 51-52, Rm 434).

ACTIONIEXPECTED RESP ONSE RESPONSE NOT OBTAINE 0 I

4. (Continued)

e. For El NB Train:

- 1) Verify 4NS-38B (ND Pmp IBTo - 1) GQT4 Step 5.

Cont Spray Hdr) CLOSED.

~

- 2) Place "PWR DISCON FOR 4NI-198B"switch in "ENABLE.

- 3) Close 1NI-178B (NB Hdr 1BTo - 3) Dispatch operator :lose INI-I788 Cold Legs A&B). (ND Hdr 1B To Cold Legs A&B)

(AB-562, FFGG, 52-53, Rm 3184.

- 4) Open 4ND-655 (ND Train 1B Hot -4 ) Dispatch operator to open WKl-65B Leg Inj Isol). (ND Train 1B Hot Leg Inj Isol)

(AB-570, KK-CL, 51-52, Rm 435).

- 5. Ensure Monitor Light Panel Group 6 HLR lights LIT.

- 6. Verify flow to NC hot legs from at least - Contact station management fer one train of NB. guidance to align MB for Hot Leg Recirc.

- 7. RETURN TO procedure and step in effect.

CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Respond to a Leak in the KC System CANDIDATE EXAMINER

.- ~- -

Page 2 of 15 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

-.I Perform Enclosure 1 actions of APIl/N55QQ/Q21 (Lossof Component Cooling) during a leak in the KC system Alternate Path:

YES Facilitv JPM #:

NEW KIA RatinaEsb:

008 A2.02 (323.5)

Task Standard:

Reactor coolant pumps are tripped. The reactor is tripped and the Immediate Actions of EP/1/N50QO/E-B (Reactor Trip or Safety Injection) have been performed from memoly.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator in-Plant __ Perform Simulates_

References:

AP/l/A/55Q0/021 "Loss of Component Cooling" Rev. 30 Candidate: Time Start:

NAME Time Finish:

Performance Riatina: SAT s_ UNSAT - Question Grade p_ Performance Time __

Examiner: I NAME SIGNATURE DATE

Page 3 of 15 SlMUbATOR SETUP SHEET:

1. Recall IC #

2. Insert LOA - KC018 (KC 186 KC Surge Tank 1A Drn Block), severity = 1.0, insert.

3. Insert LOA - KC-014 (KC 123 KC Surge Tank 1B Drn Block), severity = I.O, insert.

4. lnsert MAL - KCO02A (KC System Relief Valve KC-64 Failure); value = OPEN

5. Insert MAL - KC002B (KC System Relief Valve KC-330 Failure); value = OPEN

6. Insert MAL - KCQ02C(KC System Relief Valve KC-386 Failure); value = OPEN

7. Insert MAL - KCOO2B (KC System Relief Valve KC-86Faiiure); value = OPEN

8. Insert MAL - KC002E (KC System Relief Vake KC-313 Failure); value = OPEN

9. Insert MAL - EHC002 (Turbine Trip Failure); value = 0 (AUTO)

IO.Go to run until the KC SURGE TANK A and B Lobo LVL annunciators alarm.

1. Ensure both KF pumps are OFF

12. Clear the following when surge tank low level alarms are received:

1 LOA

~ - KC-014 (KC 123 KC Surge Tank 1B Drn Wock)

MAL - KC0028 (KC System Relief Valve KC-61 Failure) 0 MAL - KC0025 (KC System Relief Valve KC-330 Failure)

• MAL - KC002C (KCSystem Relief Valve KC-386 Failure)

MAL - KC502D (KC System Relief Valve KC-86Failure)

MAL - KC002E (KC System Relief Valve KC-313 Failure)

$2. Run the simulator until NC pump motor bearing temperatures are approximately 185°F.

I 3 Acknowledge alarms, Freeze the simulator, and write to a SNAP.

SNAP No.: 212 Place simulator in run when directed by the examiner.

Page 4 of 15 SIMULATOR OPERATOR INSTRUCTIONS:

None

Page 5 of 15 ToolslEaui~menffProceduresNeeded:

Ensure a copy of AP-21 Enclosure Iis available far each candidate.

READ TO OPEWTOR DIRECTION TQ 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:

You are the Unit 1 O A K Unit 1 is at 100% power Annunciators 1AB-10, N1 and N2, "KC Surge Tank A and El b o l o Level" have alarmed, along with various OAC level and sump alarms.

AP/l/N5500/021 (Loss of Component Cooling) has been implemented.

INITIATING CUE:

The Control Room SRO instructs you to monitor Enclosure 1 and perform any required actions.

Page6of15 START TIME:

EXAMINER NOTE: When AP/l/A/55001021 is located, give the candidate a copy of the procedure.

STEP1: SSF Manning Criteria: Step t )

(Enclosure I,

-SAT CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within ten minutes will cause damage to the NC pump seals resulting in NC System inventory loss. -UNSAT IF KC AND NV seal cooling for any NC pump is lest, THEN STANDARD: Candidate observes that 1B NV pump is in service and that seal cooling is available to all four reactor coolant pumps. Determines that step does not apply.

• • CUE: The Red "OM" iight for NVpump 16 is LIT and the Green "OFF" lighf is DARK Seal injection flow is indicated to all four reactor COQkflf PMmpS.""

COMMENTS:

EXBMINR NOTE: The trip criteria for the reactor coolant pumps may not be met the first time the candidate reads this step. If the trip criteria are not met, the candidate will continue to Step 3 of Enclosure 1 and continue to monitor all Enclosure 1 items until the trip criteria are met.

• • Italicized Cues Are To Be Used On!y MSPM Performance Is Being Simulated

?7of15 STEP 2: NC pump trip criteria: (Enclosure 1, Step 2) -SAT IF any of the following NC pump trip criteria is met:

I outlet temperature - GREATER THAN 235°F

1. Seal OR -UNSAT Lower bearing temperature GREATR THAN 225°F OR Motor bearing temperature - GREATER THAN 195°F.

THEN:

STANDARD: Once any of the reactor coolant pump trip criteria are met, the candidate will perform-the required actions.

• • CUE: Motor bearing temperature all four reactor coolant pumps is

$97F.**

COMMENTS:

STEP 3: Place the steam dumps in pressure mode. (Enclosure 1, Step 2.a.)

-SAT STANDARD: Candidate places the STEAM DUMP SELECT switch in the PESS position.

-UNSAT

• • CUE The STEAM DUMP SELECT swifch is in the PRESS pOSifiQIr. **

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

P; ?8ef15 STEP 4: Ensure the Reactor - TRIPPED. (Enclosure 1, Step 2.b.) CRITICAL STEP STANDARD: Candidate rotates both reactor trip handles counter clockwise to the -SAT trip position

• • CUE: Both reactor trip switches have been rotated counter clockwise -UNSAT ta the trip position**

COMMENTS:

STEP 5: Trip all NC pumps. (Enclosure 1, Step 2.c) CRITICAL STEP STANDARD: Candidate depresses the OFF buttons for the NCPMP ?A. I$, 1C -SAT and 1D switches and verifies Ked ON lights are BARK and the Green OFF lights are LIT for all four reactor coolant pumps.

-UNSAT

• • CUE The Red ON light is DARK and the Green OFF light is LIT ffor reactor coolant pump IA The Red ON light is DARK and fhe Grem OFF light is LIT ffor reactor coolant pump IS.

The Red ON light is DARK and the Green OFF right is LIT ffor reactor coolant pump IC.

The Red ON light is DARK and the Green OFF Eight is LIT ffcr reactor cocianf pump ID.**

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Petformame Is Being Simulated

P ?9of15 STEP 6: Ensure spray valves for the affected NC pumps IN MANUAL AND CLOSED. (Enclosure I,Step 2.d.) -SAT STANDARD: Candidate places the manuallauto stations for 1NC-27 and 1NC-29 in manual and ensures the demand is at 0 . -UNSAT

• • CUE: The manuallauto stations for INC-27 and INC-29 in manual and ensures the demand is af 0.**

COMMENTS:

STEP 7: Secure any dilutions in progress. (Enclosure 1, Step 2s.)

-SAT STANDARD: Candidate determines that no dilutions are in progress by determining that the NV make up controls are set for automatic makeup.

-UNSAT

^*CUE:No dllutbns are in progress.**

COMMENTS:

• • Italicized Cues Are To Be Used Sn/y If JPM Performance Is Being Simulated

Page 10 of 15 STEP 8: IF the reactor trip breakers were closed, THEN perform one of the following while continuing with this procedure as time and conditions -SAT allow:

e IF above PI1, GO TO EP/I/A/5000/-0 (Reactor Trip Or Safety Injection). -UNSAT OR IF below P 4 1, GO TO AP/l/A/5500/05 (Reactor Trip Or Inadvertent SA Below P-?1). (Enclosure 1, Step 2.f.)

STANDARD: Candidate determines that the reactor trip breakers were closed and goes to EP/l/A/5000/-0 and performs the immediate actions from memory.

"CUE: The reactor trip breakers were previously closed". **

COMMENTS:

EXAMINER NOTE: Steps 3 and 4 of Enclosure 1 may not be monitored depending on the rate of increase of the reactor coolant pump temperatures. The intent of the JPM is for the candidate to be rquired to trip the reactor and perform the immediate actions of EPE-Q. If reactor coolant pump trip criteria are met at this point, continue to JPM Step 9. If reactor coolant pump trip criteria are NOT met, go to JPM Step 14.

• • Italicized Cues Are To Be Used Onjy MJPM Performance Is Being Simulated

Page I 1 of 15 STEP 9: Verify Reactor Trip: ( L O , Step 2)

• All rod bottom lights - LIT -SAT

• All reactor trip and bypass breakers - OPEN IIR amps - DECREASING

-UNSAT STANDARD: Candidate determines that all rod bottom lights are lit, all reactor trip and bypass breakers are open and IIR amps are decreasing.

• • CUE: All rod bottom lighfs are lit, all reactor trip end bypass breakers are open and UR amps are decreasing.**

COMMENTS:

STEP 10: Verify Turbine Trip: ( L O , Step 3.) -SAT All turbine stop valves -CLOSED STANDARD: Candidate determines that the turbine is not tripped and performs -UNSAT Step 2 RNO.

• • CUE: TMrbine stop valves are not closed.**

COMMENTS:

Waficished Cues Are To Be Used O d y I f JPM Performance Is Being Simulated

Page 12 of 15 STEP 11: Manually trig the turbine. (Ea, Step 3. RNQ) CRITICAL STEP STANDARD Candidate depresses the manual trip pushbutton on the turbine control -SAT panel and determines that the turbine trips by observing that the turbine stop valve status lights are lit.

-UNSAT

• • CUE: The manual trip pushbutton on the turbine control panel has been depressed. The turbine stop valve status rights are lit .**

COMMENTS:

STEP 12: Verify 1ETA and 1ETB - ENERGIZED. ( L O , Step 4.)

-SAT STANDARD: Candidate verifies that 1ETA and IETB are energized by checking power availability to loads supplied from the essential busses.

-UNSAT

• • CUE: IETA and 1ETB are energized.**

COMMENTS:

• • Italicized Cues Are TOBe Used Onjy MJPM Performance Is Being Simulated

P< ! 1 3 0 f 1 5 II STEP 13: Verify SA is actuated: (E-0, Step 5.)

a. "SAFETY INJECTION ACTUATED status light (ISI-13) - LIT. -SAT

b. E/§ load sequencer actuated status lights (1Sl-14) LIT.

-UNSAT STANDARB: Candidate observes status lights and determines that "SAFETY INJECTION ACTUATEB" status light (IS-13) and IS load sequencer actuated status lights (ISI-14) are LIT.

• • CUE:. ** SAFEWINJECTION ACTUATED Status light (IS!-13) blT. -

U S load sequencer actuated status lights (1SI-14) LIT. **

1 COMMENTS:

STEP 14: IF AT ANY TIME the following conditions are met:

(Enclosure 1, Step 3.)

0 Train E) KC non-essential header isolation valves - CLOSED AND 1KC-81B (KC TO ND HX 1B SUPIso~) - CLOSED.

THEN: Ensure less than 2 train B KC pumps - IN SERVICE STANDARD: Candidate determines that only IB1 KC pump is in service.

• • CUE: I81 KC Pump is in serv!ce.**

COMMENTS:

I

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

Page 14 of 15 STEP 15: IF AT ANY TIME both trains of KC are lost, Then return to Section C SAT (Operator Actions), Step 2 (Enclosure 1, Step 4.)

STANDARD Candidate determines that 1Bl KC pump is operating.

-UNSAT

• • CUE: l B 1 KC Pump is in setvice.**

COMMENTS:

STEP 16: IF operators are dispatched to align alternate cooling to NV pump IA, -SAT Then perform the following:

a. When alternate cooling is aligned, Then perform Enclosure 7 (Maximize NV Pump Run Time) Step 7. (Enclosure 1, Step 5.)

-UNSAT 3TANBARB: No action required by candidate. 1B1 KC pump is in service

• • CUE: Operators hawe not been dispatched fo align alternate c m h g to NVpurnp IA.**

COMMENTS:

EXAMINER NOTE: At thio point, if the reactor coolant pumps have not been tripped, the candidate will return to Step 1 of Enclosure and perdorm the steps again. If the reactor coolant pumps have been tripped, this JPM is complete.

TERMlMATlNG CUE: Another operator will perform the remainder of the procedure. JPM is complete.

TIME STOP:

• • !talisized Cues Are To Be Used Only If JPM Performance Is Being Simulated

Page 15of 15 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Unit 1 BATC Unit 1 is at 100% power Annunciators IAD-10, Ail and Ai2, "KCSurge Tank A and B Lo-Lo Level" have alarmed, along with various OAC level and sump alarms.

AP/l/A/5500/021 (boss of Component Cooling) has been implemented.

INlTlATlNG CUE:

The Control Roem SRB instructs you to monitor Enclosure 4 and perform any required actions.

• • Italicized Cues Are To Be Used Only I f JPM Performance Es Being Simulated

LOSS OF COMPONENT COOLING APll I1v55c10l21 I. SSF Manning Criteria:

CAUTION Failure to restore NC pump sea! cooling via themal barrier coding or NV seal injection within ten minutes will cause damage to the PLC pump seals resulting in NC System inventory loss.

IF KC

- AND NV seal cooling for any NC pump is lost, T U perform the following:

a. Notify Security Officer at SSF (Ext. 5251) to perform Enclosure 3 (Establishing NC Pump Seal injection From The SSF) of AP/I/N5508/21 (LOSS Of Component Cooling).

b. !E f EMXS is de-energized, THEN dispatch operator to locally swap power supply. REFER 10Enclosure 2 (Swapping Power Supply For IEMXS).

c. Dispatch operator to the SSF to locally establish seal injection. REFER TO Enclosure 3 (Establishing NC Pump Seal Injection From The SSFJ.

LOSS OF COMPONENT CQOLING AQll /A/5500121

2. NC Pump Trip Criteria:

-IF any of the following NC pump trip criteria is met:

1. I Seal outlet temperature - GREATER THAN 235'F OR Lower bearing temperature - GREATER THAN 225°F QEi Motor beafing temperature - GRHTER THAN I95"F.

P":

a. Place the steam dumps in pressure mode.

b. Ensure the Reactor - TRIPPED.

c. Trip all NC pumps.

d. Ensure spray valves for the affected NC pumps - IN MANUAL AND CLOSED.

e. Secure any dilutions in progress.

f. the reactor trip breakers were closed, T'Iperform one of the folloving while continuing with this procedure as time and conditions allow:

E above P-I I,m T p EP/1/N500CKE-0 (Reactor Trip Or Safety Injection).

OR E below P-I 1, (;B m AP/l/A/5500105 (Reactor Trip Or Inadvertent S/I Below P-I 1).

I

I CNS LOSS OF COMPONENT COOLING PAGE NO.

APll/N5500/2 1 f ? of 35 Enclosure 1 Page 3 of 3 Revision 30

~

Foldout Paae a The folloving step prevents damage to the 152 KC pump as a result of deadheading. (PIP #00-5862)

3. IF AT ANY TIME the followiflg conditions are met:

Train E3 KC non-essential header isolation valves - CLOSED AND

• IKC-81 B (KC To ND Hx 1B SUP ISOl) - CLOSED.

THEN ensure less than 2 train B KC pumps - IN SERVICE.

NOTE Monitoring of the following steps must continue while KC maifunction exists even if a transition is made to the emergency procedures.

4. IF AT ANY TIME both trains of KC are lost, RETURN To Section C. (Operator Actions), Step 2.

5. E operators are dispatched to align alternate cooling to NV pump 'iA, THENpeffosrnthe following:

a. alternate coolirsg is aligned, T#EN perform Enclosure 7 (Maximize NV Pump Run Time), Step 7.

Page 1 of 10 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM/CR-8 Vent the Reactor Vessel Head Following a Small Break LOCA CANDIDATE EXAMINER

Page 2 of 10 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Vent the reactor vessel head following a small break LOCA.

Alternate Path:

NO Facilitv JPM #

CSF-001 (modified)

WA Ratlnn(s1:

002 Azo7 (4.3M.4)

Task Standard:

Head venting termination criteria satisfied with flow isolated via INC-250A andlor 1NC-251B Candidate: Time Start '

NAME Time Finish:

Performance Ratifla: SAT ~ UNSAT - Question Grade __ Performance Time __

Page 3 of 18 SIMULATOR SET-UP SHEET None SIMULATOR OPERATOR INSTRUCTIONS:

Page 4 of 10 TOal§/~QuiRmefltlProcedU~e§ Needed:

Have enough copies of EQll/N5500/FR-1.3 (Response to Voids in Reactor Vessel) Revision I O for each candidate.

DlRECTlON 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.

INITIATING CUE:

A LOCA has occurred on Unit 1. EP/I/A/5500/FR-1.4 (Response to Voids in Reactor Vessel) is in progress. Reactor Coolant Pump I A was started per Step 13.

The following conditions currently exist:

Pressurizer level: 93%

0 NC pressure (recorded in step 18): 1865 psig and stable 0 NC Subcooling based on core exit TICS: 75°F 0 All NC T-Hots: 530T and stable 0 PRT pressure: 5 psig e Reactor Vessel UR Level Train A: 95%

• Reactor Vessel UR Level Train B: 92%

The Control Room SRO has directed you to review the reactor vessel venting termination criteria listed in step 22 of EP/l/N5500/FR-l.3 (Response to Voids in Reactor Vessel) and then vent the reactor vessel head per step 23.

Page 5 of 10 START TIME:

m: Obtain a copy of the appropriate procedure.

SAT STANDARD: Operator locates EP/l/A/5000/FR-I.3.

EXAMINER CUE: When the candidate locates EP/l/A15080/FR-1.3, hand himlher a clean copy and tell himlher that it is current and complete. -UNSAT COMMENTS:

STEP 2:

~

- reactor vessel venting- termination criteria:

Review the following (Step 22.) -SAT STANDARD: Candidate reviews the reactor vessel venting termination criteria.

'*CUE: Maxhurn venting t h e calculated in Step 21 is 1 minute 42 seconds** -UNSAT COMMENTS:

STEP 3: Vent reactor vessel head as follows: (Step 23.)

-SAT Ensure operator monitors Endosure 6 (Reactor Vessel Venting Limits)

(Step 23.a.)

STANDARD: Candidate locates Enclosure 6 and monitors the enclosure while -UNSAT continuing with Step 23. b.

COMMENTS:

• • italicized Cues Are To Be Used only If JPM Performance Is Being Simulated.

Page 6 of 10 ign vent path by opening the following valves: (Step 23. b.) CRlTlCAL STEP

• 1NC-250A (Rx Head Vent Block)

STANDARD: Candidate depresses the Red OPENpushbutton for INC-250A and

-SAT verifies that the Red OPENlight is LIT and the Green CLOSED light is DARK.

• • CUE: The Red OPEN pushbuffon for INC-250A has been deoressed.

-UNSAT

~_._

The Red 0PENlight is LIT and the Green CLOSE5iight is DARK. **

COMMENTS:

STEP 5: Align vent path by opening the following valves: CRITICAL (Step 23. b. continued) STEP a 1NC-25lB (ax Head Vent) -SAT XANDARD: Candidate depress6S the Red OPEN pushbutton for 1NC-251B and verifies that the Red OPENlight is LIT and the Green CLOSED light is DARK. -UNSAT

• • CUE: The Red OPEN pushbuffon for IN6-251B has been depressed.

The Red OPEN light is LIT and the Green CL0SE5D l@ht is DARK. **

COMMENTS:

• • !talicized Cues Are To Be Used Q d y I f JPM Petformance Is Being Simulated.

Page 7 of 10 Verify any venting termination criterion - EXCEEDED. -SAT (Step 23. c.)

STANDARD: Candidate reviews the reactor vessel venting termination criteria on -UNSAT Endosure 6 and determines that the criterion for Reactor Vessel UR Level is exceeded.

• • CUE:

.. NC Subcooling Based on core exit T / C k Pressurker level:

40 F 76%

0 NC pressure: 1750 psig

. All NC T-HofS:

PRT pressure:

Venting time:

530 F and stable 20 psis 30 seconds have

. Reactor Vessel UR Level Train E:

elapsed 103%

COMMENTS:

STEP 7 : Ensure all of the following valves - CLOSED: (Step 23.d.) CRITICAL

• 1NC-250A (Rx Head Vent Block) STEP STANDARD: Candidate depresses the Green CLOSED pushbutton for 1NC-250A -SAT and verifies that the Green CLOSED light is LIT and the Red OPEN light is DARK.

• • CUE: The Green CLOSED pushbuffon for fNC-250A has been -UNSAT depressed. The Green CLOSED light is LIT and the Red OPEN light is DARK. **

COMMENTS:

• • /talicizedCues Are To Be Used only If JPM Performance Is Being Simulated.

Page 8 of l a CRITICAL (Step 23. d. continued) STEP

-1 NC-251B (ax Head Vent)

-SAT STANDARD: Candidate depresses the Green CLOSED pushbutton for 1NC-251B and verifies that the Green CLOSED iight is LIT and the Red OPEN light is DARK.

^*CUE: The Green CL0SEDpushbutton for fNC-251B has been

-UNSAT depressed. The Green CLOSED light /sLIT and the Red OPEN right is DARK. **

COMMENTS:

EXAMINER NOTE: As long as Step 7 or Step 8 above is completed and flow is isolated. the CRITICAL STEP is satisfied.

EXAMINER NOTE: In JPM steps 9 and 10, the candidate is directed to ensure 4NC-252Band INC-253A are closed. These valves are normally closed with power removed. When the candidate is directed to ensure these valves are closed,it is permissible to state that the valves were not repositioned and that the last known position was closed.

STEP 9: Ensure all of the following valves -CLOSED:

(Step 23. d. continued)

-1 NC-2523 [Rx Head Vent Block)

STANDARD: Candidate determines that 1NC-252B was not opened previously and that the last known position was CLOSED.

• • CUE: 1NC-252B is CLOSED. **

COMMENTS:

• • ltaiicized Cues Are To Be Used Only MJPM Performance Is Being Simulated,

Page 9 of 10 STEP 10: Ensure all of the following valves - CLOSED: -SAT (Step 23. d. continued)

• INC-253A (Rx Head Vent Block)

-UNSAT STANDARD: Candidate determines that 1NC-253A was not opened previously and that the last known position was CLOSED.

• • CUE: ING253A is CLOSED. **

COMMENTS:

EXAMINER CUE: Another operator will complete the rest of the procedure.

This JPM is complete.

TIME STOP:

• • Italicized Cues Are To Be Used Only FJPM Performance Is Being Simulated.

Page 10 of 10 CANDlDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIATING CUE:

A LOCA has occurred on Unit I.EP/I/N55OR/FR-1.3 (Response to Voids in Reactor Vessel) is in progress. Reactor Coolant Pump 1A was started per Step 13.

The following conditions currently exist:

Pressurizer level: 93%

NC pressure (recorded in step 18): 1865 psig and stable 0 NC Subcooling based on core exit T/C's: 75°F All NC T-HQtS: 530°F and stable 0 PRT pressure: 5 psig Reactor Vessel UR Level Train A: 95%

Reactor Vessel UR Level Train B: 92%

The Control Room SRO has directed you to review the reactor vessel venting termination criteria listed in step 22 of EP/l/N550CIFR-i.3 (Response to Voids in Reactor Vessel) and then vent the reactor vessel head per step 23.

• • /talisized Cues Are To Be Used only If JPM Performance Is Being Simulated.

Duke Power Company 'rocedure No Catawba Nuclcar Station EP/f/A/5000/FR-L3 Levision No.

010 Response to Voids in Reactor Vessel Electronic Reference No.

CP0034FO

RESPONSE TO VOIDS IN REACTOR VESSEL EP/l/N5000/FR-1.3 A. PurDose This procedure provides actions to reswnd to d d s in the reactor vessel head.

B. SvmDtoms or Entrv Conditions This procedure is entered from EP~l/A/5000/F-O(Critical Safety Function Status Trees)

(REACTOR COOLANT INVENTORY) on a YELLOW COnditfOR.

C. Otaerator Actions

- 1. IF EP/l/A(500Q/ES-Q.3(Natural Circulation Cooldown With §team Void In Vessel) is in progress, T m RETURN TO procedure and step in effect.

2. Verify §/I has been terminated as - RETURN TO procedure and step in follows.. effect

-* Both NI p U M P - OFF

- 1NI-9A (NV Prnp C/b lnj [sol)- CLOSED

- INI-208 (NV Prnp C/L Inj Isd) ~

CLOSED.

3.

PSIG.

Verify VI pressure GREATER THAN 50 In subsequent steps, control room control is lost for the following valves and local operation will be required

- 1NV-294 (NV Pmps A&B Disch Flow Gtrl)

- 0 1NV-303 (Seal Water Injection Flow).

EP/l/A/5OOO/FR-1.3 ACTION/EXPECTED RESP ONSE 1 I RESPONSE NOT OBTAIN D 1

4. Verify charging Row has bean established as follows:

- a. At least one NV pump - ON. a. Perform the following:

1) Verify the fallowing annunciators -

BARK:

-e ZAQ-6, '31 "NCP A THERMAL BARRiER KC OUTLET HVLO FLOW" e ?AD-6, E/2 "NCP B THERMAL BARRIER KC 0UTI-m HllLO FLOW IAD-6, U3 "NCP C THERMAL BARRIER KC OUTLET HIlbO FLOW"

- IAD-6, El4 "NCP D THEKMAL BARRIER KC OUTLET HllLO FLOW".

(RNO continued on next page)

EP14 /N5OOO/FR-I .3

4. (Continued)

2) 1E.KC flow to any NC pump thermal barrier is lost, THEN perform the following before starting a NV pump:

- a) Dispatch operator to restore power to the NC pump seal supply containment isolation valve for the affected NC pump(s). REFER TO Enclosure 1 (Power Restoration to NC Pump Seal Supply Isolation Valves).

b) WHEN power is restored, close valve for the affected NC pumP(s):

- INV-44A (NC Pmp A Seal Supply Cont isol)

- 1NV-554 (NC Pmp B Seal Supply Cont Isol)

- 1NV-66A (NC Pmp C Seal Supply Cont Isol)

- e 1NV-77A (NC Prnp B Seal Supply Cont Isol).

3) Ensure the following valves -

OPEN:

- 1NV-2038 (NV Pumps A&B Recirc Isol)

- . 1NV-202B Isol).

Pmps A&B Recirc

-4) Manually close 1NV-294 (NV Pmps A&B Disch Flow Ctrl).

(RNO continued on next page)

I

RESPONSE TO VOIDS IN REACTOR VESSEL EPll /NSQOO/FR-I.3

4. (Continued)

5) E control of 1NV-294 is lost from the control room, THEN:

- a) Place the controller for 1NV-294 in the 100% demand position.

- b) Dispatch operator with a radio to close 1NV-295 (NV Pmps A & B Disch Ctrl Isol) (AB-551,JJ-55, RM 231).

- C) Throttle INV-295 to control charging flow as required in subsequent steps.

- 6) Start one NV pump.

b. Establish VI to containment as follows: b. PeffOllll the fdIOWiRg:

- . Ensure IVI-77B (VI Cont Isol) -

OPEN.

1) Align NZ to the Pn PORVs by opening the following valves:

Verify VI pressure - GREATER THAN -0 1NI-4388 (Emer N2 From CLA A 85 PSIG. TO 1NC-34A)

- 1Nl-4396 (Emer N2 From CLA B TO 1NC-32B).

- 2) E VI pressure is less than 85 PSIG, THEN dispatch operator to ensure proper VI compressor operation.

11 CNS EP/l/A1500O/FR-1.3 I RESPONSE TO VOIDS IN REACTOR VESSEL 1 PAGE NO.

6 of 40 11

4. (Continued)

c. Verify charging is in service as follows: c. Perform the following:

- INV-3124 (Chrg Line Cont Isol) 1) Establish charging as follows:

OPEN a) Ensure the following valves.

-= 1NV-314B (Chrg Line Cont Isol) - OPEN:

OPEN

-

• INV-203A (NV Pumps A&B

- e Charging flow - INDICATING FLOW. Recirc Isol)

- 0 1NV-202B (NV Pmps A&B Recirc Isol).

- b) Manually throttle 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to establish 8 GPM Seal water flow to each NC pump with an open seal injection flowpath.

c) E control of INV-294 is lost from the control room, THEN:

- (1) Place the controller for 1NV-294 in the 100%

demand position.

- (2) Dispatch operator with a radio to throttle 1NV-295 (NV Pmps A & B Disch Ctrl Isol) (AB-557, JJ-55, Rm 231) to establish 8 GPM seal water flow to each NC pump with an open seal injection flowpath.

- (3) Throttle 1NV-295 to control charging flow as required in subsequent steps.

- d) Manually close 1NV-303 (Seal Water Injection Flow).

(RNO continued on next page)

I

e) E controi of INV-309 is lost from the control room, THEN:

- ( 4 ) Place INV-309 the in controller the 100% for demand position.

- (2) Dispatch operator with a radio to throttle 1NV-308 (Seal Wtr Inj Flow Ctrl Isol)

(AB-554, JJ-54, Rm 233)

(Ladder needed) tu maintain 8 GPM seal water flow to each NC pump with an open seal injection flowpath in subsequent steps.

9 Open the following valves:

- INV-322A (Chrg Line Cont Isol)

- 0 INV-3148 (Chrg Line Cunt Isol).

9) E lNV-322A&@ INV-3148 cannot be opened, W &

JJ dispatch operator to open the affected valve@):

- INV-31% (Chrg Line a n t Isol) (AB-553, HH-JJ, 52, Rm 217) (Ladder needed)

- INV-314B (Chrg Line Cont IsoI) (AB-553, GG-HH, 52-53, Rm 217) (Ladder needed).

- h) E NC pump seal injection flow is being controlled from the control room M all NC pump seal supply containment isolation vaive.4 are open, THEN place INV-309 in " A U T C (RNO continued on next page)

RESPONSE TO VOIDS IN REACTOR VESSEL EPll /N5000/FR-i .3

4. (Continued) i) Control charging and seal injection flow to maintain the following:

- Charging flow less than 180 GPM

- 6 GPM seal injection flaw to each NC pump with an open seal injection flowpath.

2) LE charging flow cannot be established, THEN:

- a) Establish Excess letdown.

REFER TO Enclosure 2 (Establishing Excess Letdown).

- b) Step 7.

- 5. -

Verify letdown ISOLATED. ---GO TO Step 7.

6. Establish normal letdown as follows:

- a. Verify VI pressure - GREATER THAN a. Perform the following:

35 PSIG.

- 1) YV" VI pressure is greater than 35 PSIG, THEN pertorrn Steps 6.b through 6.171.

- 2) =TO Step 7.

b. Ensure the follawing valves - CLOSED:

- 1KC-56A (KC To ND Hx I A Sup Isal)

-

• 1KC-61B (KCTO ND HX 1B SUP1~01).

RESPONSE TO VOIDS IN REACTOR VESSEL EP11/N5000/FR-1.3

6. (Continued)

c. Verify the following EMF trip 1 lights - c. Petform the following:

BARK:

- 1) Notify station management to

-

• 1EMF-538 (Containment Trn A) evaluate restoring normal letdown

- e 1EMF-53B (Containment Trn B). with high NC System activity.

- 2) Establish excess letdown. REFER To Enclosure 2 (Establishing Excess Letdown).

- 3) WHEN station management approval to establish normal letdown is obtained, perform Steps 6.d through 6.m.

- 4) COT0 Step 7.

d. Verify the following valves for the - d. Manually open valve(s).

operating KC train(s) - OPEN:

Train A:

- IKC-1A (Aux Bldg Non-Ess Ret Hdr Isol)

- 1KCdOA (Aux Bldg Non-Ess Hdr Isol).

I Train B:

-

• 1KCdB (AUXBldg t 4 o n - E ~Ret ~

Hdr lsol)

- e 1KC-53B (Aux Bldg Non-Ess Hdr Isol).

- e. While performing the following steps, adjust 4NV-148 (Letdn Press Control) to maintain letdown pressure at 350 PSIG.

- f. Ensure 1NV-849 (Letdn Flow Var Orif Ctrl) valve demand position - 0%.

RESPONSE TO VOIDS IN REACTOR VESSEL EP/l/N5000/FR-1.3

6. (Continued)

g. Open the following valves: g. Perform the following:

- INV-1A (NC Letdn To Regen Hx Isol) 1) Ensure the following valves.

CLOSED:

- 1NV-2A (NC Letdn To Regen Hx Isol)

- 1NV-1A (NC Letdn To Regen Hx

-e INV-158 (Letdn Cont Isol). Isol)

-e 1NVQA (NCLetdn To Regen Hx Isol)

- 4NV-15B (Letdn Cont I s ~ l ) .

- 2) Establish excess letdown.

To Enclosure 2 (Establishing Excess Letdown).

- 3) G O m S t e p 7.

- h. While performing the following steps, manually adjust charging flow to maintain letdown subcooled.

- i. Open INV-dOA(Letdn Orif 1B Otlt Cont Isol).

- j. Throttle INV-849 (Letdn Flow Var Orif Ctri) until valve demand position is 10%

open.

- k. Monitor letdown flow and letdown pressure.

RESPONSE TO VOIDS IN RI3CTOR VESSEL EPll /N5BBO/FR-1.3 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAIME D

6. (Continued)

- I. Verify letdown flow and letdown I. Perform the foliowing:

pressure - INCREASES.

1) E INV-849 valve demand position is 100% open, THEN:

a) Close the following valves:

- 1NV-849 (Letdn Flow Var Orif Ctrl)

- INV-IOA(Letdn Orif I B Otlt Cont ISOI)

- e INV-1A (PIC Letdn To Regen Hx Isol)

- INV-24 (NC Letdn Bo Regen Hx Isol).

- b) Establish excess letdown.

REFER TO Enclosure 2 (Establishing Excess Letdown).

- c) Step 7.

2) Throttle open 1NV-849 until one of the following conditions are met:

- Letdown flow and letdown pressure increases OR

- Valve demand position increases by 10%

OR

- e Valve demand position is 100%

open.

- 3) RETURN TO Step 6.k.

6. (Continued)

m. WHEbl5 minutes has passed,

- 1) Adjust INV-849 (Letdn Flow Var Orif Ctrl) to &tempt to increase letdow flew to greater than 30 GPM.

2) Open one of the following valves: 2) Perform the following:

- 1NV-13A (Letdn Orif 4A Otlt Cont a) Close the following valves:

Isol)

OR - INV-849 (Letdn Flow Var Orif Ctrl)

INV-11A (Letdn Orif IC Otlt Cont isol).

-e lNV-IQA(Letdn Orif I B Otlt Cont Isol)

-e INV-1A (NCLetdn To Regen Hx Isol)

- INV-2A (NC Letdn Po Regen wx Isol).

b) Establish excess letdovm.

REFER TO Enclosure 2 (Establishing Excess Letdorm).

- c) Step 7.

- 3) Close INV-1OA (Letdn Orif 1B Otlt Cont Isol).

- 4) Close 1NV-849 (betdn Flow Var Orif Ctrl).

- 5) Ensure 1NV-148 (Letdn Press Control) IN "AUTO.

RESPONSE TO VOIDS IN REACTOR VESSEL EP/l/A45000/FR-I.3

7. Establish stable NC System conditions as follcws:

- a. Verify Pzr level - GREATER THAN - a. Control charging and letdown as 90%. required to increase h r level to greater than 90%.

- b. Verify NC pressure - STABLE. b. Perform the following:

- 1) Energize Pzr heaters and use normal Pzr spray to stabilize NC pressure.

2) nofrnal Pzr spray is not available

@Dletdown is in service, use NV aux spray as follows:

a) Ensure the following valves -

CLOSED:

- 1NC-27 (Pzr Spray Ctrl Frm Loop A)

- 1NC-29 (Pzr Spray Ctrl Frm Loop B)

- 1NV-39A (NV Supply TO LOOP D Isol)

- 1NV-32B (NV Supply To Loop A Isol).

- bj Maintain charging flow iess than 180 GPM.

I c) Throttle 7 NV-37A (NV Supply To Pnr Aux Spray) and charging flow as required to stabilize NC pressure.

- c. Verity all NC T-Hots STABLE.

~

- c. Bump steam to stabilize NC T-Hots.

- 8. Verify all NC pumps OFF. ~ --- GO TO Step 16.

OlDS IN REACTOR VESSEL I 9. Determine NC System pressurization requirements as follows:

a. Verify at least one of the following - a. CO Step 9.c.

conditions exist:

- Unisolated LOCA OR

- SGTR OR

- Repressurization prohibited by EP/l/N5000/FR-F'.1 (Response To Imminent Pressurized Thermal Shock Condition).

- b. G o v q s t e p 12.

- c. Verify NC pressure - AT LEAST 100 - c. G O m s t e p 1 2 .

PSI6 LESS THAN ALLOWED BY TECH SPEC 3.4.3, Figure 3.4.3-2.

- d. Verify NC pressure - LESS THAN - d. GQTOStep12.

1854 PSIG.

- e. Energize Pzr heaters to increase NC pressure 50 PSIG.

- 10. Control charging and letdown to maintain Prr level greatesthan 25%

(34% ACC).

11. Verify reactor vessel level indication as follows:

- a. "REACTOR VESSEL UR LEVEL" - - a. B T A S t e p 12.

INCREASING.

- b. "REACTOR VESSEL UR LEVEL - - b. RETURN Step 9.c GREATERTHAN 100%.

- c. Operate Pzr heaters as required to stabilize NC pressure.

d. RETURN TO procedure and step in effect.

12. Verify reactor vessel head void is ---

GO TO Step 16.

eondensible as follows:

- "REACTOR VESSEL bB LEVEL" - HAS REMAINED ABOVE 61%.

Verify one of the following:

- 0 NC pressure - HAS REMAINEB GREATERTHAN 170 PSIG OR CLAS - ISOLATED OR VENTED PRIOR TO NC PRESSURE DECRWSING TO 170 PSIG.

1.

11 CNS EPiliN5QQWFR-1.3 I R§PONSE TO VOIDS IN REACTOR VESSEL 1

Preference should be given to running NC Pump I B and then NC Pump 1A to provide Pzr spray capability.

23. Attempt to start one NC pump as fellows:

a. Verify NC pump seal coding has been a. Perform the following:

maintained from une of the following:

- 1) Notify station management to

- e Seal injection flow perform a status evaluation prior to starting an NC pump.

OR

- 2) m m S s t e p 16.

- KC flow tu thermal barriers.

b. Establish the following conditions prior - b. E conditions cannot be established, to NC pump start: THEN GO TQ Step 16.

- Pnr level - GREATER THAN 90%

- NC subcooling based on core exit T/Cs - GREATER THAN 36°F

- Pzr - SATURATED.

- 6. Start one NC pump. REFERTO - c. G$nStep 16.

Endosure 3 (NCPump Start).

- 14. Verify "REACTOR VESSEL UR LEVEL" _- GO -TO Step 16.

(from diagnostic page) GREATER THAN REQUIRED FROM TABLE BELOW.

RSPONSE TO VOIDS IN REACTOR VESSEL EP/1/A/5OOO/FR-I .3

- 15. ==Step25

16. Obtain containment Ha concentration as follows:

- a. Ensure operator has been dispatched to secure all ice condenser air handling units. REFER TO Endosure 4 (Securing All Ice Condenser Air Handling Units).

b. Verify containment HZ analyzers - IN b. Perform the following:

SERVICE.

- 1) Dispatch operator to place containment HZ analkers in service. REFER TO OP/I/A1645(KOlO(Containment Hydrogen Controi Systems).

- 2) Y!!" H2 analyzers are in service, perfom Steps 16.c through 16.e.

- 3) G Q m S t e p 17.

- c. Verify containment HZ concentration - e. Perform the following:

LESS THAN 6%.

- 1) Obtain recommendation from station management for method to reduce HZ concentration.

- 2) S m S t e p 17.

- d. Verify containment H2 concentration - - d. Dispatch operator to place the H2 LESS THAN 0.5%. recombiners in service. REFER BP/Z/A1645Q/OZO(Containment Hydrogen Control Systems).

- e. lYjEN the ice condenser air handling units are off HZ concentration is less than 6%, energize the H2 igniters (1MC7).

17. Block LOWPzr pressure S/l as follows:

- a. Verify Pzr pressure - LESS THAN a. Perform the following:

1905 PSIG.

- 1) Decrease Pzr pressure to less than 1905 PSIG using normal Pnr spray.

2) normal Pzr spray is not available, THEN perform the following:

a) E letdown is in service, THEN decrease NC pressure to less than I905 PSIG using NV aux spray as follows:

(1) Ensure the following valves

- CLOSED:

- 1NC-27 Frm Loop(Pzr A) Spray Ctrl INC-29 (Pzr Spray Ctrl Frm Loop B)

- f NV-39A Loop (NV Supply TO D Isol)

- 1NV-32B (NV SUPPI?TO Loop A Isol).

- (2) Maintain charging flow less than 180 GPM.

- (3) Throttle 1NV-37A (NV Supply To Pzr Aux Spray) and charging flow as required.

b) E letdown is isolated QEI NV aux spray is not available, decrease NC pressure to less than 2905 PSIG using one Pzr PORV.

- b. Depress ECCS Pzr pressure "BLOCK' pushbuttons.

c. Verify Pzr low pressure SI1 blocked status lights (ISI-13) - LIT.

RESPONSE TO VOlBS IN REACTOR VESSEL EP/l/A/5000/FR-I.3

17. (Continued)

- d. Maintain NC pressure less than 1905 PSIG.

e. IF AT ANY TIME conditions degrade, m:

- 1) Manually actuate §/I.

- 2) RFTURN TO procedure and step in effect.

- 18. Record NC pressure Enclosure 5 I[AJlowablle Hydrogen Venting Time).

II CNS I I

RESPONSE TO VOIDS IN REACTOR VESSEL I

19. Establish the following NC System conditions:

- a. Verify Pzr level - GREATER THAN - a. Control charging and letdown as 90%. required to increase Pzr level to greater than 90%.

- b. NC pressure - STABLE. b. Perform the following:

- 1) Energize Pzr heaters and use normal P a spray to stabilize NC pressure.

2) E normal Pn spray is not availat AND letdown is in service, use NV aux spray as follows:

a) Ensure the following valves ~

CLOSED:

- 1NC-27 (Pzr Spray Ctrl Frm hoop A)

INC-29 (PnSpray Ctrl Frm Loop B)

- 1NV-39A D Isol) (NV Supply To hoop

- A1NV-32BIsol). (NV S ~ p p l yTO LOOP

- b) Maintain charging Row less than 180 GPM.

- c) Throttle INV-37A (NV Supply To Pzr Aux Spray) and charging flow as required to stabilize NC pressure.

c. NC subcooling based on core exit Tics - c. Bump steam to restore NC subcooling.

- GREATER THAN 50°F.

- d. All NC T-HOtS - STABLE. I d. Dump steam to stabilize NC T-Hots.

RESPONSE TO VOIDS IN REACTOR VESSEL EPll/A/50OO/FR4.3

20. Prepare containment for reador vessel venting asfollows:

a~ Ensure the following VQ isolation valves - CLOSED:

- IVQ-2A (VQ Fan Suct From Cont Isol)

- IVQ-3B (VQ Fan Suct From Cont Isol)

- IVQ-193 (Cont Air Add Cont Isol)

- 1VQ-16A (Cont Air Add Cont Isol).

- b. Ensure HZ Skimmer System is in operation. REFER TO OP/iiN6450/010 (Containment Hydrogen Control Systems).

21. Determine maximum allowable venting time as follows:

- a. Verify containment HZ concentration ~ a. Perform the following:

LESS THAN 3%.

- 1) E Hz concentration is greater than 6%, THEN obtain recommendation from station management for method to reduce HZ concentration.

- 2) Bo not continue in this procedure until containment HZ concentration is iess than 3%.

- b. Calculate maximum venting time.

REFER TO Enclosure 5 (Allowable Hydrogen Venting Time).

REACTOR VESSEL I -

OR NC subcooling based on core exit T/Cs -

LESS THAN 0°F

- Pzr level - LESS THAN 25% (34% ACC)

OR

- 0 NC pressure - DECREASES BY 203 PSI6 FROM VALUE RECORDED IN STEP 18 OR

- e PRT pressure - GREATER THAN 50 PSlG OR

- Venting time - GREATER THAN MAXIMUM CALCULATED IN STEP 21 OR RVLlS indication:

-0 E all NC pumps off, "REACTOR VESSEL UR LEVEL" is greater than 500%

II 11 I

CNS EP/liA/5COO/FR-1.3 I RESPONSE TO VOIDS IN REACTOR VESSEL

22. (Continued)

- E one NC pump on, "REACTOR VESSEL UR LEVEC' (from diagnostic page) is greater than required from table below:

RESPONSE TO VOiDS IN REACTOR VESSEL EP/I/N5000/FR-1.3 ACTION/EXPECTED RESP ONSE

23. Vent reactor vessel head as follows:

- a. Ensure operator monitors Enclosure 6 (Reactor Vessel Venting Limits).

b. Align vent path by opening the following b. E vent path cannot be aligned, T m valves:

1) Ensure the following valves -

- INC-250A (Rx Head Vent Block) CLOSED:

- INC-2518 (Rx Head Vent).

2) Dispatch operator to remove white tags and dose the f o l l o ~ n g breakers:

- 1EMXL-F1OC (Reactor Vessel Head Vent Valve INC252E)

(AB-568, 8847,Rm 372)

- 0 1EMXS-FO3E (Reactor Vessel Head Vent Valve 1NC253A)

(AB-577, BB-49, RM 496).

3) Align alternate vent path by opening the following valves:

- 0 lNC-252B (Rx Head Vent Block)

- 1NC-253A (RxHead Vent).

- c. Verify any venting termination criterion - 6. Perform the following:

EXCEEDED.

- I)Continue venting

- 2) Do not continue in this procedure until any venting termination criterion is exceeded.

d. Ensure all of the following vent valves -

CLOSED:

-0 ?N6-250A (Fa Head Vent Block)

-e 1NC-251B (aX Head Vent)

-e INC-252B (Rx Head Vent Block)

-0 1NC-253A (Rx Head Vent).

RESPONSE TO VOIDS IN REACTOR VESSEL EPll/A/5000!FR-1.3

24. Verify proper RVLlS indication as Perform the following:

follows:

- a. Increase NC pressure to value recorded

- E all NC pumps are off, T m v e r i f y in Step 18.

"REACTOR VESSEL UR LEVEL" is greater than 100% - b. E PRT intact, TJ&l reduce PRT pressure to less than 3 PSIG. REFER

- E one NC pump on, I#ENverify -

TO OP/1/A/6150/004 (Pressurizer "REACTOR VESSEL UR LEVEL (from Relief Tank).

diagnostic page) is greater than required from table below: - c. RETURN TO Step 16.

l- 25. Verify Prr level -STABLE. - Control charging and letdown to stabilize Pzr level.

RESPONSE TO VOiDS IN REACTOR VESSEL EP/l/A!5OQO/FR-1.3

- 1. E any delay occurs while performing this endosure, T m i m m e d i a t e l y notify control room personnel.

2. Place the following breakess on IEMXA (AB-577, FF-54 Rm 478) to "ON":

- 1EMXA-RO5D (1A NC Pump Seal Supply Outside Containment [sol Motor (INVUA))

- IEMXA-RQIC (IB NC Pump Seal Supply Outside Containment lsoi Motor (lNV55A))

- IEMXA-R04B ( I C NC Pump Seal Supp!y Outside Containment lsol Motor (1NV66A))

- 0 1EMXA-R04C (1D NC Pump Seal Supply Outside Containment lsol Motor (?NV77A)).

- 3. Notify control room personnel that the required valve bseakefls) is closed.

- 4. Return this enclosure to the Control Room SRO.

I CNS RESPONSE TO VOIDS IN REACTOR VESSEL PAGE NO.

EP/1/N5000/FR-I.3 27 of 40 Enclosure 2 - Page 1 of 5 Revision 10 Establishina Excess Letdown I

I I'

1. -

Ensure the following valves CLOSED:

- 1KC-568 (KC TO ND HX I A SUPIso~)

- IKC-81B (KCTo ND Hx 1B §up Isol).

2. Align KC to excess letdown heat exchanger by opening the following valves:

- 1KC-230A (Rx Bldg Nan-Ess Hdr Isol)

- 0 1KC8A (kE3ldg NOn-EsS Ret Hdr IsoI)

- 1KC-22m (Rx Bldg Non-Ess Hdr Isol)

- IKC-18B (Rx Bldg NomEss Ret Hdr Isoi)

-e IKG375B (Exs Letdn Hx Ret Cont Isol).

3. Establish NC pump seal return flow as follows:

a. Verify the following EMF trip 1 lights - a. Perform the following:

DARK:

- I)Notify station management to

-

• 1EMF-53A (Containment f r n A) evaluate restoring NC pump seal

- IEMF-538 (Containment f r n 8). return and excess letdown outside containment with high NC System activity.

- 2) WHEN station management approval is obtained, THEN RETURN TO Step 3.b.

- 3) a m s t e p 10.

- b. Verify NC pump seal injectionflow - b. Perform the following:

GRWTEFS THAN 6 GPM TO EACH NC PUMP. - 1) Y&& jJ NC pump seal injection is restored, THEN RETURN To Step 3.b.

- 2) 60T 9 Step I O .

It I RESPONSE TO VOIDS IN REACTOR VESSEL EP/1/N5000/FR-1.3 I 3. (Continued)

I - C. Verfy IAD-7, R/1 "SEALWATER HX KC HIILO FLOW - BARK.

C. Perform the following:

- 1) Notify station management to evaluate restoring NC pump seal return flow.

- 2) WHEN notified by station management 1AD-7, D/1 dark, THEN RETURN TO Step 3.d.

- 3) G P I Q S t e p IO.

I - d. Verify NCDT pressure LESS THAN VCT PRESSURE.

d. Perform the following:

- I)WHEN NCDT pressure is less than VCT pressure, THEN RTURN TO Step 3.d.

- 2) W T O S t e p 1 0 .

e. Open the following valves:

- 1NV-89A (NC Pmps Seal Ret Cont Isol)

-

• 1NV-91B (NC Pmps Seal Ret Cont Isslj.

f. IF AT ANY TlME NCDT pressure is greater than VCT pressure, THEN perform the following:

- I)Monitor NC Pump #I seal AP.

- 2) Verify excess letdown - ISOLATED. 2) Ensure the manual loader for 1NV-124B (Excess betdn Press Ctrlj is adjusted to 0%.

3) Close the following valves:

INV-89A

- m Cont Isol)(NC Pmps Seal Ret

- 1NV-91B (NC Pmps Seal Ret Cont Isol).

I - 4) GQTOStep10.

RESPONSE TO VOIDS IN REACTOR VESSEL EF'/l/AJ5000/FR-1.3 RESPONSE NOT OBTAINE D

4. Notify Primary Chemistry of the following:

-* Excess Letdown will be placed in service.

- VCT pressure will be reduced to 25 PSIG.

- 5. Dispatch operator to adjust the VCT hydrogen pressure to 25 PSIG. Refer to OP\il\A16200/001 (Chemical and Volume Control System).

- 6. Ensure the manual loaderfor 1NV-124B (Excess Letdn Press CtrI) is adjusted to 0%.

9. Verify the following conditions: Pel. nn the following:

~

- VCT pressure - BEWEEN 25 a. Place INV-12% (Excess hetdn Hx Otlt PSlG AND 30 PSIG. Ctrl) in the "NCDT" position.

a The following valves - OPEN: - b. WHEN conditions met, THEN RETURN TO Step 6.

CT Otlt Isol)

CT Otlt lsol). - c. &Q. Io Step 10

- 8. Place 1NV-125B (Excess Letdn Hx 0th Ctrl) in the "VCT' paltion.

- 9. GQTOStep15.

IO. Verify the following EMF trip 1 lights - ---GO TO Step 14.

DARK

- IEMF-53A (Containment Trn A) 1EMF-53B (Containment Trn B).

RESPONSE TO VOIDS IN REACTOR VESSEL EP/1/N5QQO/FR-l.3

14. Align KC to the NCDT heat exchanger by opening the following valves:

- 0 ZKC-32OA (NCDT Hx Cool Supply Ccnt

- IKC-333A (NCDT Hx Cool Ret Cunt Isol)

I - e IKC-3328(NCDT Hx Cool Ret Cont Isoi).

- 12. Ensure at least one NCDT pump ON.-

13. Open the following valves:

- IWL805A ( N O T Pump Disch Cont Issl)

- 0 1WL-807B (NCDT Pumps Disch Cont ISQI).

- 14. Place INV-1258 (Excess Letdn HX Otlt Ctrl) in the "NCDT" position.

15. Open the following valves:

INV-122B (Losrp C Tu Exs Letdn Hx isol) e INV-1235 (Loop C To Exs betdn Hx Isoi).

- 16. Select "OPEN" on INV-2248.

- 17. Slowly adjust the manual loader for 1NV-1248 to 8% open.

RESPONSE TO VOIDS IN REACTOR VESSEL EP/1/N5000/FR-1.3

18. Maflually throttle 1NV-f24B until the required excess letdown flow is achieved and within the following parameters:

- Excess letdown Hx outlet temperature -

LESS THAN 170°F

- Excess letdown Hx outlet pressure ~

LESS THAN OR EQUAL TO 45 PSIG.

1. Verify all of the following KC valves OPEN:

- Perform the following:

- a. M ~ i u a l l yopen affected valve(s).

- IKC-23OA (RxBldg Non-Ess Hdr IsoI) 1KCBA (Rx Bldg Non-Ess Ret Hdr Isol) 1KC-394A (NC Pump 1A Therm Bar Otlt)

- b. E KC cooling cannot be established from one operating KC train to the NC pumps, BkI return this enclosure to the Cmtrol Room SRO.

- fKC-425A (NC Pumps Ret Hdr Cont Isol)

IKC-345A (NC Pump I C Therm Bar Otlt)

IKC-228B (WX Bldg Non-Ess Hdr Isol)

- e IKC-188 (bBldg Non-Ess Ret Hdr Isol)

- 1KC364B (NCPump 1B Therm Bar Otlt)

- 0 1K6-3388 (NC Pumps Sup Hdr Cont

- - kd)

IKC-424B (NC Pumps Ret Hdr Cont Isol)

- e IKC-4138 (NC Pump I D Therm Bar Otlt).

- 2. Place normal Prr s p a y valves in manual and closed

II 3. Establish NC pump motor cooling as follows:

a. Ensure the following valves - OPEN:

- 1RN-484A ( b c w r Cont Vent Unit Ret)

- 1RN-489B (Lover Cont Vent Unit Ret)

-* 1RN-437B (Lower Cont Vent Unit SUP).

- b. Verify "W OPERABLE" light (rear of b. Perform the following:

1MC7) - LIT.

- 1) Dispatch operator to restore W System to normal. REFER TO OP/I/A/6458/020 (Containment Chill Water System).

2) If:W System cannot be restored to normal, I "  :

- a) Select "RN" on "YV/RN COOL WATEU MODE".

b) Ensure the following valves -

OPEN:

- 1 RN-49A Hdr IsoI) (NM-ESS Supply

- 1RN-50B (Non-Ess Supply Hdr Isol)

- E 1RN-51A (Non-Ess Ret Hdr Iscl)

. 1RN-52B (Ncn-Ess Ret Hdr Isol).

(RNO continued on next page)

RESPONSE TO VOIDS IN REACTOR VESSEL EQ/I/N5000/FR-1.3 Enclosure 3 - Page 3 of 6 NC Pump Start ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINE 0

3. (Continued) c) Ensure at least one of the following valves - OPEN:

- 1WN-48B (RN Supply X-Over

[sol)

- 1RN-47A (RN Supply X-Over Isol).

- 3) NC pump motor cooling cannot be established, THEN return this enclosure to the Control Room SRO.

4. Verify the following conditions am - Return this enclosure to the Control satisfied for the NC pump to be stalted: Room SRO.

- #1 seal AP - GREATER THAN OR EQUAL TO 200 PSID KC flow to NC pump thermal barrier between 35 GPM and 60 GPM by one of the following methods:

- NC pump thermal barrier KC outlet

1. i/Lo flow alarm (1AD-6) - DARK OR

-

• OAC NC pump graphic OR

- 0 Qispatch operator to locally verify adequate KC cooling to NC pump thermal barrier (88-543, FF-54, Rrn 200).

RESPONSE TO VOIDS IN REACTOR VESSEL EPll/N5000/FR-I.3

4. (Continued)

KC flow to NC pump motor upper bearing between 153 GPM and 200 GPM by one of the following methods:

- NC pump motor upper bearing KC outlet HilLo flow alarm (IAD-6) -

DARK OR

-

• OAC NC pump graphic OR

- e Dispatch operator to locally verify adequate KC cooling to NC pump motor upper bearing (AB-543, FF-54, Rm 200).

KC flow to NC pump motor lower bearing between 4 GPM and 9.5 GPM by one of the following methods:

- NC pump motor lower bearing KC outlet Hi/Lo flow alarm (1AD6) -

DARK OR

- OAC NC pump graphic OR

- 0 Dispatch operator to losally verify adequate KC cooiing to NC pump motor lower bearing (AB-543, FF-54, Rm 200).

- NC pump upper/lower oil reservoir Lo level alarm (IAD-6) - DARK

- NC pump seal injection flow - GREATER THAN 6 GPM

- NC pump seal leakoff flow - WITHIN LIMITS OF UNIT 1 REVISED DATA BOOK FIGURE 26

RESPONSE TO VOIDS IN REACTOR VESSEL EP/l/N5000/FR-1.3 RESPONSE NOT OBTAINE D 4.(Continued)

- IAB-7 1, W6 "230 KV SWITCHYARD VOLTAGE LO' - DARK.

5. Start one NC pump oil lift pump on the NC pump to be started.

- 6. B  !. "2 minutes has elapsed, THEN start the NC pump.

- 7. \"EN 3 minutes has elapsed after MC pump reaches full speed, T-ensum the NC pump oil lift pump stops.

II 1 RESPONSE TO VOIDS IN REACTOR VESSEL EQ/l/N5000/FR-1.3 I

8. Verify the following conditions satisfied Perform the following:

for the NC pump that was started:

- a. Stop the affected NC pump.

- #I seal BP GREATER THAN OR

~

EQUAL TO 200 PSID - b. Return this enclosure to the Control Room SRO.

- 0 #I seal outlet temperature - LESS THAN 235°F

- NC pump lawer bearing temperature -

LESS THAN 225°F

- 0 NC pump seal injection flow GREATER

~

THAN 6 GPM

- 0 NC pump Seal leakoff flow - WITHIN LIMITS OF UNIT 1 REVISED DATA BOOK FIGURE 26

- NC pump shaft vibration - LESS THAN 20 MILS

- NC pump motor frame vibration - LESS THAN 5 MILS 0 OAC is available, THEN verify the following:

- 0 Stator winding temperature - LESS THAN 311°F

- Motor bearing temperature - LESS THAN 195°F.

I I RESPONSE TO VOIDS IN REACTOR VESSEL EP/I/N50OOFR-1.3

- 1. Place the toggle switch in the "DEF" position for each backdwft damper located on the Ice Condenser System Backdraft Damper Status Light Panel (AB-594, DD-52, Rm 576).

- 2. Stop each ice condenser air handling unit fan located on the Ice Condenser Air Handler Unit Control Panel IAHU-1 (AB-594, DD-52, Rm 576).

- 3. Notify control room personnel that the ice condenser air handling units are off.

- 4. Return this enclosure to the Control Room SRO.

I I RESPONSE TO VOIDS IN REACTOR VESSEL EP/1/A/5000/FR-1.3 N C SYSTEM PRESSURE ( P S I G )

2400 2200 2000 CALCULATION O F M A X I M U Y 1800 ALLOWABLE V E N T I N G T I M E STEP 1 Calculate A 1600 ( P + 14.7) 492 A = 9.500 x X 14:/ ( 7 + 460) 1400 where: P Containvent pvessure (PSIG)

T = Lower c o n t a i n m e n t 1200 t e m p e r a t u r e (de? F )

STEP 2: C a l c u l a t e E 1000 6 = ( 3 - H ) x A where: H = C o n t a i n m e n t hydrogen c o n c e n t r d t i on ( % )

800 S.IEP 3: D e t e r m i n e C f r o 9 t h e c u r v e 600 f o r t h e c u r r e n t N C system pressure.

400 STEP 4: C a l c u l a t e 1 T = S I C = Venting t i m e i n minutes 200 0

0 2000 4000 6003 8COG C = HYDROGEN FLGW KATE (SCFM)

NC pressure PSIG Maximiini a l l o w a b l e ve n t i n g t i m e -minutes

II I I ,I CNS RESPONSE TO VOIDS IN REACTOR VESSEL PAGE NO.

EP/l/N50001FR-1.3 40 of 40 Enclosure 6 Page Iof 1 Revision I O Reactor Vessel Venting- Limits I' I

1. WHEN at Seast one of the following criteria is met, W d n o t i f y the Control Room SRO:

- NC subcooling based on core exit T/Cs - LESS THAN 0 "F OR

- Pzr level - LESS THAN 25% (34%ACC)

OR

- NC pressure - DECREASES BY 200 PSlG FROM VALUE RECORDED It STEP 18 OR

- 0 PRT pressure GREATER THAN 50 PSlG

~

OR

- 0 Venting time - GREATERBHAN MAXIMUM CALCULATED IN STEP 22 QR RVLlS indication:

- E all NC pumps are off, T""Ri3CTOR VESSEL UR LEVEL" is greater than 100%

- one NC pump on,W " R E A C T 0 R VESSEL UR LEVEL" (from diagnostic page) is greater than required from table be10t-v

Page 1 of 10 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE J PM/PLANT-9 Transfer HVAC Control to LOCALFollowing Control Room Evacuation CANDIDATE EXAMINER

Page 2 of 10 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Tran: r HVAC Con "LOCAL following Control Room Evacu: m per AP/1/ '5500/017 (Loss of Control Room), Enclosure 5.

Alternate Path:

NO Facilitv JPM #:

OP-CN-CP-RSS-003 KIA Ratinafs):

013 A4.02 (4.314.3)

Task Standard:

Candidate: Time Start :

NAME Time Finish:

Performanee Ratina: SAT ~ UNSAT - Question Grade - Performance Time -

Examiner: /

NAME SIGNATURE DATE COMMENTS

- ~ - ~ ~

Page 3 of 10 SIMULATOR SET-UP SHEET SIMULATOR OPERATOR INSTRUCTIONS:

NONE

Page 4 of 10 ToolslEauigmentllaroc~uresNeeded:

Have enough copies of Enclosure 5 of AP/l/A/55OO/O17 available for each candidate READ TO OPERATOR DIRECTION TO TRAINEE?

B will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM, including any required communications. ! 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:

A train VCNC is out of sewice fo condenser tube cleaning .

A tire has occurred that causes a Control Room evacuation.

INITIATING CUES:

You are the Auxiliary Building operator and are directed by the ASP 1A operator to perform Enclosure 5 of APll/A15500/017 (Loss of Control ROOM).

You are to ensure W train VCNC equipment and A and B train VA equipment are operating.

Page 5 of 10 START TIME:

STEP 1: Provide a copy of Enclosure 5 HVAC Actions to the candidate. -SAT STANDARD: None COMMENTS: -UNSAT STEP 2: Verify Train A VCNC desired to be started in "LOCAL. (Step 1)

-SAT STANDARD: Examinee should determine from initiating cue that "B" train is to be placed in service (per step 1 RNO) and proceeds to Step 5 of End. 5.

COMMENTS: -UNSAT NOTE. The following step will cause Unit 1 and Unit 2 B train VA equipment to start.

STEP 3: Place "VCNC AHU TRAIN B" switch to "LOCAL". (STEP 5.a) CRITICAL STEP STANDARD: VCNC AHU TRN B switch on 2ELCP0058 (85-594, "-58, Rrn 560) turned to the 'LOCAL" position. -SAT

• • CUE: VCffC AHU TffN B switch 6UrRed io the "LOCAL" position.

COMMENTS.: -UNSAT STEP 4: Place "VCNC AHU TRAIN B" switch to "ON". (STEP 5.b) CRITICAL STEP STANDARD: VCMC AHU TRN B on/off switch positioned to the "ON" position. RED "QN" light is LIT above local control switch on 2ELCP0058. -SAT

• • CUE: VCffC AHU TRN B on/off switch is in the "ON" position. The RED "ON" light is LIT.

-UNSAT COMMENTS:

• • italicized Cues Are TO Be Used Only If JPM Performance Is Being Simulated.

Page 6 of 10 STEP 5: Verify Train 5 VCNC HVAC equipment in operation: (STEP 5.c) a VCNC AHU Train 5 - ON -SAT 2CM-AHU OM

• 2CR-AHU-I - ON ISWGR-AHU-2 OW ~

• 2SWGR-AHU ON -UNSAT

• 1SWGR-AHU ON 2SWGR-AHU ON STANBARD: Indications on 2ELCP0058.

RED ON status light LIT RED ON status light LIT, left panel, third row RE5 ON status light LIT, left panel, third row RED ON status light LIT, left panel. first row RED ON status light LIT, left panel, first TOW RE5 ON status light LIT, left panel, first row RED ON status light LIT, left panel, first row After substep read, give the following cue:

• • CUE: RED ON status light is LIT fer each AHU.

COMMENTS:

STEP 6: After 2 minutes; verify 2CM-P-I ON.

~ -§AT STANDARD: Verify RED O N status light LIT, right panel, fourth row

• • CUE: 2 minutes have passed; RED ON light is UT. -UNSAT COMMENTS:

• • lta/icized Cues Are To Be Used Onry If JPM Perfamance Is Being Simuiated.

Page 7 of 10 I - - -

STEP 7: Place VCNC AHU Train A switch to LOCAL. (STEP 6.a) CRlTlCAL STEP STANDARD: VCNC AHU TRN A switch on 1ELCPOQ58 (AB 594, -56, RM 5713) turned to the LOCAL Position. -SAT

• • CUE: VCMC AHU TRN A switch is in the L0CALpositlon.

COMMENTS: -UNSAT STEP a: Ensure VCNC AHU T W I N A switch - QFF.(STEP 6.b)

-SAP STANDARD: Rotate VCNC AHU TRAIN A switch to the OFF position on 1ELCP0058.

• • CUE: The switch is pofnffng to the 0FFposition. -UNSAT COMMENTS:

Italicized Cues Are Po Be Used Only If JPM Performance Is Being Simulated.

_. Page 9 of 10 STEP I O : Verify VA equipment in operation. (STEPS 7d, e, and 9

-SAT At 2EbCPOOI1 (AB-594, LL-58, Rm 588) e "AUXILIARY BLBG. SUPPLY UNIT 28" (ABSU9A) - ON "AUXILIARY BLDG. SUPPLY UNIT 2W (ABSU-26) - ON -UNSAT "AUX. BLDG. UNFILTERED EXHAUST FAN 2A" (ABUXF-2A) - ON e "AUX. BLDG. UNFILTERED EXHAUST FAN 2W (ABUXF-2B) - ON AT 2ELCP0112 (AB-594, HH-58, Rm 500)

"AUX. BLDG. FlLTD EXH FAN 28" (ABFXF-2A) - ON AT 2ELCP0113 (AB-594, bb-62, Rrn 500)

"AUX. BLDG. FlLTD EXH FAN 2 6 (ABFXF-25) - ON STANDARD: Indication on each panel:

0 e

ABSU9A Red "ON" light lit on left panel on 2ELCPO11I ABSU-2B Red "ON" light lit on left panel on 2ELCPB111 ABUXF9A Red "ON" light lit ora right panel on 2ELCPO1I 1 e ABUXF-2B Red "ON" light lit on right panel on 2EbCPO111 0 ABFXF-2A Red "ON" light lit on right panel on 2ELCPO112 e ABFXF9B Red "ON" light lit on 2ELCPO113

• • CUE: REQ "ON" light LIT for each fan.

COMMENTS:

STEP f 0: Notify ASP operator (~5549,~5548) status of VCNC and VA equipment. (Step 8) -SAT STANBARD: Call ASP operator (5549 OF 5548) and reports that B Train VCMC is in service, and that A and B Train VA equipment is in operation.

-UNSAT

• • CUE; This is the ASP Operator. I understand that B Train VCNC and A and 3 Train VA are operathg.

COMMENTS:

This JPM is complete.

TIME STOP:

• • lfaliciaed Cues Are To Be Used Only if JPM Performance Es Being Simulated.

Page 1Qof 10 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMlNER UPON COMPLETION OF TASK)

INlTlAb CONDITIONS:

K train VCRC is out of service fo condenser tube cleaning .

A fire has occurred that causes a Control Room evacuation INlTlATlNG CUES:

You are the Auxiliary Building operator and are directed by the ASP 1A operator to perfom Enclosure 5 of APll/A15500/017 (Loss of Control Room).

You are to ensure E! train VCNC equipment and A and B train VA equipment are operating.

• • ltaiEcized Cues Are To Be Used Only if JBM Performance Is Being Simulated.

I r l CN3 APlliAI550QI17 s

LOSS OF CONTROL ROOM Enclosure 5 Page 1 of 5

~

HVAC Actions I PAGE NO.

a9 of 50 Revision 43 I~ -

Verify Train A VCWC DESIRED TO BE -- IF desired to start Train B VCMC in STARTED IN "LOCAL". "LOCAL", THEN GO TO Step 5.

2. At 1iLCP0058 (WC System Control Panel) (AB-594, "-56, RIM 570), perform the following:

The following step will cause Unit 1 and Unit 2 A train VA equipment to start.

I - a. Place 'VCNC AHU TWIN A" switch to "LOCAL".

I - b. Place "VCAIC AHU TRAIN A" switch to C.

"ON".

Verify Train A VCMC HVAC equipment in opwation as follows:

- I)"VCNC AHU TRAIN A" ON. s

- 2) "ICBA-AHU-1"- ON.

3) "ICR-AHU-1" - ON.

- 4) VSWGR-AHU-1" ON. -

5) "2SGR-AHU-3"- ON.

- 6) "ISWGR-AHU-3 ON. -

- 7) "2SWGR-AHU-3" ON. ~

3. At 2ELCP0058 (VC System Control Panel) (AB-594, HH-58, Rm 560), perform the following:

~NOTE The following step will MUS& Unit 1 and Unit 2 B train V A equipment to start

- a. Place "VCNC AHU TRAIN W switch to "LOCAL".

- b. Ensure "VCNC AHU TRAIN B" switch -

"OFF".

LOSS OF CONTROL ROOM APlliAJ5500l17

5. At 2ELCPOQ58 (VCSystem Control Panel) (AB-594, "-58, Rm 560), perform the following:

NOTE The following step will cause Unit 1 and Unit 2 B train VA equipment to start

- a. Place "VCNC AHU TRAIN E switch to "LOCAL".

- b. Place "VCNC AHU TRAIN 8" switch to "ON".

c. Verify Train B VCNC HVAC equipment in operation as follows:

- I)"VCNC AHU TRAIN B" ON.

- 2) "2CRA-AHU-1" - ON.

- 3) "2CR-AHU-1" - ON.

- 4) "ISWGR-AHU-2" ON.

- 5) "2SWGR-AHU-2" - ON.

- 6) "ISWGR-AHU-4" - ON.

- 7) "2SWGR-AHU-4" -ON.

- 8) After 2 minutes, verify 2CRA-P ON.

6. At IELCPQ058 (VC System Control Panel) (AB-594, "-56, Rm 570), perform the following:

NOTE The following step will muse Unit 1 and Unit 2 A train VA equipment to start.

- a. Place "VCNC AHU T W I N A switch to "LOCAL".

- b. Ensure "VCIYC AHU T W I N A switch -

"OFF.

LOSS OF CONTROL ROOM AQll/N5500/17

7. Verify VA equipment in operation:

a. At IELCPOI II(VA System Control Panel) (88-594, "-55, Rm 500) verify the following:

- "AUXILIARY BLBG SUPPLY UNIT 1 A (ABSU-IA) - ON

- * "AUXILIARY BLDG SUPPLY UNIT 1 5 (ABSU-le) ON

~

- e "AUX. ELDG. UNFILTERED EXHAUST FAN 1 A (ABUXF-1A) -

ON

- * "AUX. BLDG. UNFILTERED EXHAUST FAN 1W (ABUXF-1B) -

ON.

- b. At lELCPO112 (VA System Control Panel) (AB-594. "-55, Rm 500)veri&

"AUX BLDG FILTB EXXH FAN I A (ABFXF-1A) - ON,

- c. At 1ELCPOl13 (VA System Control Panel) (AB-594, bb-52. Rrn 500) verify "AUX BLDG FLTD EXH FAN 1B (ABFXF-IB) ON.

d. At 2ELCPQ111(VA System Control Panel) (AB-594, HH-58, Rm 500) verify the following:

- "AUXILIARY BLDG SUPPLY UNIT 2 A (AESU-2A) - ON

- "AUXILIARY BLDG SUPPLY UNIT 28" (ABSU-2s) - ON

- "AUX. BLDG. UNFILTERED EXHAUST FAN 2 A (ABUXF-2A) -

ON

- "AUX. BLBG. UNFILTERED EXHAUST FAN 2B" (ABUXF-2B)

ON.

CNS LOSS OF CONTROL ROOM PAGE NO.

APlliAi5500l17 43 of 50 Endosure 5 - Page 5 of 5 Revision 43 HVAG Actions I' I I

7. (Continued)

- e. At 2ELCPQ112(VA System Control Panel) (AB-594. HH-58, Rm 500) verify "AUX BLDG FILTD EXH FAN 2A" (ABFXF-2A) - ON.

- f . At 2ELCPO113 (VA System Control Panel) (AB-594, LL-62, Rm 500) verify "AUX BLDG FILTD EXH FAN 28" (ABFXF-2B) ON.

- a. Notify ASP operator (~5549,~ 5 5 4 8 )

status of VCNC and VA equipment.

Page 1 of 14 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPMIPLANT-10 Startup Backup Temporary VI Compressor CANDIDATE EXAMINER

Page 2 of 14 CATAWEA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MAASURE Start the Backup Temporary VI Compressor and place it in service on the VI header.

Alternate Bath:

NO Facilitv JPM #

VI-002 WA Ratina(s):

098 K4.UZ (3.23.5)

Task Standard:

Temporary VI Cornpfessar started and aligned to the Instrument Air Header through 1V1-417.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator -- In-Plant X Perform - Simulate X

References:

BP/O/Ni450/005(Instrument Air System, Enclosure 4.10) Revision I 0 7 Validation Time: I 5 min. Time Critical: No

---

__ssssss_______s____-------------------------------------------

---

_____________sssms__-------------------------------------------

Candidate: Time Start :

NAME Time Finish:

Performance Ratinq: SAT __ UNSAT ___ Question Grade - Performance Time -

Examiner: I NAME SIGNATURE DATE

Page 3 of 14 ToelslEquiDnaenffBrocedures Needed:

Have enough copies of OP/O/N6450/005 Endosure 4.10 available for each candidate.

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 when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIATING CUE:

Unit 1 and 2 are at 100% power. VI bo Pressure Annunciator is lit and VI pressure is 75 psig and slowiy decreasing. AP/O/N5500/22, Loss of Instrument Air, is implemented and the CR SRQ directs you to startup and align the Backup Temporary VI Compressor to the Instrument Air Header per OP/O/N6450/085, Instrument Air System, Enclosure 4.10.

Page 4 of 14 START TIME:

I m: Obtain a copy of the appropriate procedure

-SAT STANDARD: Operator locates OPIO/A/6450/005Enclosure 4.10 EXAMINER CUE: When the candidate locates OB/O/A/6458/0O5 Enclosure 4.10, hand hirnlher a clean copy of Enclosure 4.10 and tell himlher -UNSAT that it is current and complete.

COMMENTS:

Review the Limits and Precautions. (Step I.I1

-SAT STANDARD: Candidate reads Limits and Precautions and determines that 2.1 1 and 2.12 are applicable

-UNSAT COMMENTS.

.dOTE: The following step may be performed out of sequence at UnitiWCC SRO Notify Catawba Garage at ext. 3590 (or Shift Work Manager on backshift) that the Backup Temporary VI Compressor will be operated -SAT and servicing may be required during or after the run. (Step 1.a)

STANDARD: Candidate locates a telephone and simulates calling the Catawba Garage. UNSAT

• • CUE: This is George at the Catawba Garage. I understand that you are going to operate the Backup Temporary VI Compressor.**

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 5 of 14

-SAT jTANDARD: Candidate opens panel door on Turbine Building side of compressor and locates dipstick next to the oil filter. Candidates states helshe would remove dipstick to check oil level.

-UNSAT

• • CUE: Oil level is near the "F" mark. **

COMMENTS:

STEP 5: Verify the compressor oil is visible in sight glass (sight glass should be full with compressor shutdown) beside the control panel. (Step 1.4) -SAT STANDARD Candidate locates the sight glass on oil tank inside the large door on the front side of compressor next to the control panel door. Candidate indicates the sight glass should be full. -UNSAT

• • CUE: The sight $!ass is FULL. **

COMMENTS:

STEP 6: Start the Backup Temporary Vi Compressor as follows: (Step 2.1) -§AT Unplug the battery charger. (Battery charger is located inside engine compartment opposite side from battery.) (Step 2.1.1)

STANDARD: Candidate simulates unplugging battery charger by disconnecting -UNSAT cable from turbine building side of cornpressor housing.

• • CUE: The batfery charger is unplugged. **

COMMENTS:

• • Italicized Cues Are To Be Used On!y If JPM Performance is Being Simulated.

Page 13of 14 STEP 9: Ensure ITVI-20 (Compressor Service Valve) is open. (Step 2.12)

XANDARD: Candidate ensures ITVI-20 (Compressor Service Valve) is open by -SAT positioning the handle such that it is in parallel with the hose.

• • CUE: The handle fer 1Wb-20 is peralle! to the hose.**

-UNSAT COMMENTS:

NOTE: The following steps are performed from the compressor control panel located on the front of the compressor.

STEP 8: Place the POWERtoggle switch in the ON position. (Step 2.1.3) CRITICAL STEP STANDARD: Candidate raises the POWEB toggle switch to the ON position on -SAT the control panel.

• CUE: The POWER toggle switch is in the ON posifion.**

-UNSAT COMMENTS:

STEP 9: Ensure fuel level is adequate. (Step 2.1.4)

-SAT STANDARD: Candidate locates fuel level gauge inside control panel (front of cornpressor).

• • CUE: Fuel oil level is at 3/4 full ark,** UNSAT COMMENTS:

EXAMINER NOTE: JPM step IO will only be petformed if freezing weather conditions exists. If freezing weather conditions DO NOT exist, proceed to JPM step 11.

• • Italicized Cues Are To Be Used Only If JPM Betformance is Being Simulated.

STEP IO: In freezing weather perform the following: (Step 2.1.5)

1. Place the HEATERS toggle switch in the ON position to -SAT energize cylinder head glow plugs. (Step 2.1.5.1)

2. Proceed after 60 seconds(tirne permitting) (Step 2.1.5.2)

STANDARD: Cmdidate simulates placing HEATERS toggle switch to ON and -UNSAT states he/she will wait 60 seconds.

• • CUE: The HEATERS toggle switch k in the ON position. 60 seconds have passed.**

COMMENTS:

STEP 11: Press and hold the BYPASS switch for I O - 15 seconds. CRITICAL (Step 2.1.6) STEP STANDARD: Candidate simulates depressing the BYPASS switch and indicates s _ SAT helske would hold it for 10 to 15 seconds.

• • CUE: The BYPASS swifch is depressed. 15 seconds have passed.**

-UNSAT COMMENTS:

STEP 12: While holding the BYPASS switch press the START button. CRITICAL (Step 2.1.7) STEP STANDARD: Candidate presses the START button while still holding the -§AT BYPASS switch..

• • CUE: The START button has been pressed and the BYPASS switch is being held. -UNSAT COMMENTS:

• • italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

Page 8 of 14 STEP 13: When the engine starts, release the "START button. (Step 21.8)

-SAT 5TANDAWD: Candidate releases the "START button when the engine starts and continues to hold the "BYPASS" switch.

• • CUE: Engine starting sounds are heard.** -UNSAT COMMENTS:

STEP 74: When the engine speed is > 1000 rpm, release the "BYPASS button. (Step 2.2.9) SAT STANDARD: Candidate locates the engine speed indication and states that the "BYPASS" button will be released when engine speed is greater than or equal to 1000 rpm. UNSAT

• • CUE: Engine speed is 1200 rpm. The "BYPASS" button has been released.**

COMMENTS:

STEP 15: After the engine has run for 5 minutes (time permitting), press the CRITICAL "SERVICE AIW button to load the compressor. (Step 2.1.10) STEP STANDARD: Candidate locates and presses the "SERVICE AIR" button on the -SAT compressor control panel.

• • CUE:5 minutes have passed. The "SERVICE AIR" button has been pressed. ** -UNSAT COMMENTS:

• • ltalieked Cues Are To Be Used Qnly If JPM Petformanee Is Being Simulated.

Page 9 of 14 1 STEP 16: Verify COMPRESSOR DISCHARGE PRESSURE increases to approximately 110 psig. (Step 2.1.1 I) -SAT STANDARD: Candidate locates the COMPRESSOR DISCHARGE PRESSURE gauge on the compressor control panel and states that he/she would expect pressure to read approximately 115 psig. UNSAT

• • CUE: COMPRESSOR DISCHARGiZ PRESSURE is f f 5 psig.**

COMMENTS:

STEP 27: Ensure the Heater toggle switch is in the OFF position.

(Step 2.1.12) -SAT STANDARD: Candidate places the HEATER toggle switch in the OFF position.

• • CUE: The HEATER toggle switch is in the OFF position. -UNSAT COMMENTS:

S E P 18: align the temporary aftercooler and air dryer for service as follows:

(Step 2.2) -SAT Press the START button on the TEMPORARY AFTERCOOLER VI SYSTEM control panel (TB-598, 2C-2D, 34) (Step 2.2.1)

STANDARD: Candidate presses the Green START button on the -UNSAT TEMPOMBY AFTERCOOLER VI SYSTEM control panel.

• • CUE: The START bufton on the TEMPORARY AFTERCOOLER Vi SYSTEM control panel has been pressed.

COMMENTS:

• • !talkiredCues Are To Be Used On/y if JPM Performance I5 Being Simulated.

Page 10 of 24 i sTEp19: Cycle IVI-540 (Port Aux Air Comp Dryer inlet Brain)to drain any water out of the dryer inlet piping. (Step 2.2.2) -SAT STANDARD: Candidate turns the handwheel fer 1VI-540 (T5-598, 2C-34) in the counter clockwise direction until motion stops. Once water is drained, candidate turns the handwheel in the ciockwise direction until motion UNSAT Stops.

• • CUE: IVI-540 is moving in the counter clockwise direction. Motion has stopped. Water is observed draining from the line. Water drainage stops. IVI-540 is moving in the clockwise direction.

Motion has stopped.**

COMMENTS:

STEP 20: Slowly open the following valves: (Step 2.2.3) CRITICAL 4V8-512 (Port Aux Air Comp Dryer Inlet) (T5-598, 2C-34) (Step STEP 2.2.3.1)

-SAT STANDARD: Candidate rotates the handwheel for IVI-512 in the counter clockwise direction until metion stops and the stem is exposed.

• • CUE: The handwheel for I K 5 f 2 is moving in the counter clockwise -UNSAT direction. Motion has stopped and fhe stem is exposed.**

COMMENTS:

• • italicized Cues Are To Be Used On!y If JPM Performance Is Being Simulated.

STEP 21: Slowly open the following valves: (Step

. . 2.2.3) CRITICAL 1VI-513 (Port Aux Air Comp Dryer Inlet) (TB-598, 2C-34) (Step STEP 2.2.3.2)

STANDARD: Candidate rotates the handwheel for IVI-513 in the counter clockwise direction until motion stops and the stern is exposed.

• • CUE: The handwheel for 1 V M f 3 is moving in the counter clockwise -UNSAT direction. Motion has stopped and the stem is exposed-**

COMMENTS:

STEP 22: Place the AIR DRYER CONTROL POWER switch to ON.

(TB-598, 2B-34). (Step 2.2.4) -SAT STANDARD: Candidate moves the Black switch to the right to the ON position.

The Green light is LIT.

-UNSAT

• • CUE: The Black switch has been moved io the O N position. The Green iight Is LIT.**

~~JIMENTS:

STEP 23: Align to the VI System as follows: (Step 2.3) CRITICAL Open IVI-417(Port ILRT Comp Disch) (TB-598, 32-34), STEP (Step 2.3.1)

-SAT STANDARD: Candidate rotates the handwheel for 1VI-417 in the counter clockwise direction until motion stops and the stern is exposed.

• • CUE: The handwheel for IVI-447 is moving in the counter clockwise -UNSAT direction. Motion has stopped and the stem is exposed.**

COMMENTS:

• • Italicized Cues Are To Be Used Onry If JBM Performance Is Being Simulated.

Page 12 of 14 1 STEP 24: Verify compressor is maintaining apprexirnately 110 psig as read on the compressor control panel. (Step 2.3.2) -SAT STANDARD: Candidzte verifies that "COMPRESSOR DISCHARGE PRESSURE" is reading approximately 110 psig on the control panel.

-UNSAT

• • CUE: "COMPRESSOR DISCHARGE PRESSURE? is reeding approximately f10 psig***

COMMENTS:

STEP 25: Verify pressure drop across the temporary filters is less than 15 psid by subtracting the outlet pressure from the inlet pressure. SAT "FILTER A "FILTER B" (Step 2.3.3)

-UNSAT STANDARD: Candidate locates "FILTER A" and "FILTER B" inlet and outlet pressure gauges. Determines from values given in following cue that pressure drop across each filter is less than 15 psid.

"A FILTER" 95 p i g minus 92 psig = 3 psid "B FILTER" 90 psig minus 88 psig = 2 psid

• • CUE: Provide the candidate with the following values as each pressure gauge is located:

OVIPGB-01 "A Inlet Pressure is 95 psig OVlPGT-02 "A Outlet Pressure is 92 psig OVIPGT-03 "W Inlet Pressure is 90 psig OVIPGT-04 "B" Outlet Pressure is 88 psig.

COMMENTS:

NOTE: The Backup Temporary VI Compressor DIG fuel oil tank holds approximately 180 gallons and lasts less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when compressor is running fully loaded.

• • Italicized Cues Are To Be Used Onry If JPM Performance Is Being Simulated.

STEP 26: If the Backup Temporary VI Compressor is to be left in service for the Compressor DIG fuel oil tank levei on a regular frequency and initiate refill at less than %tank.

STANDARD: Candidate states that he will notify an SRO to complete step 2.4.

• • CUE: An Sa0 will perform step 2.4.**

COMMENTS:

TIME STOP:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 14 of 14 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIATING CUE:

Unit 1 and 2 are at 100% power. VI LQ Pressure ~nnunciatoris lit and VI pressure is 75 psig and slowly decreasing. APIOIA15500/22, boss of Instrument Air, is implemented and the 68 SRQ directs you to startup and align the Backup Temporary VI Compressor to the Instrument Air Header per OPIOIAl6450/005, Instrument Air System, Enclosure 4.10.

• • itaiicimed Cues Are To Be Used OnQ If JPM Performance Is Being Simulated.

OPIOIN645O!OOS Page 2 of 3 Instrument Air System

1. Purpose l o define the operation of the Instrument Air System.

2. Limits and Precautions 2.1 VI Compressors D, E and F motors are limited to 2 starts in a one hour period.

2.2 Maintain maximum KR temperature differential across compressor intercoolers, aftercoolers and oil coolers 2 25°F AT.

2.3 Verify compressor oil temperature > 95°F before starting.

2.4 "Autoniatically Controlled" on the main window of the VI Compressor Computer, "COMPRESSOR READY" displayed on microprocessor control panel and "LOCALIWCOM" switch in "INCOM" position will allow compressors to be started, loaded, unloaded and stopped by the VI Compressor Computer as required by system demands.

2.5 The VI Compressor Computer will go "Not Active" when it is shutoff, looses power or communications link.

2.6 After local manipulation ofVI Compressors, ensure the VI Compressors are returned to the "Automatically Controlled" list on the main window of the VI Compressor Computer.

2.4 When manually operating any motor operated valve, minimize the torque applied to handwhcel.

2.8 After manual operation, maintenance or packing adjustments of any safety related valves, it shall he cycled electrically to ensure reliable automatic operation.

INOTE: The following maximum allowable AI' across the filters and drye.rs may be exceeded as long as total prefilteTldryeriafter~~lterAP is 5 10 psid as read on OVIPG6260. I 2.9 Maximum allowable A' across prefilters, dryers and afterfilters is as follows:

Across prefilters is 7 psid Across Afterfilters is 5 psid Across dryers is 7 psid 2.10 Station air to instrument air oil filters require inspection and/or replacement any time station air is used as a backup to instrument air.

OPIOIA/6450/005 Page 3 of 3 2.1 1 When the Backup Temporary VI Compressor is started it shall be tun for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to maintain battery charge. {PIP 94-1749) 2.12 If the backup Temporary VI Cornpressor trips, allow the "COMPRESSOR DISCIIARGE PRESSURE" to bleed down to 0 psig before re-starting to prolong battery and starter life.

2.13 Racknp starting air cylinders shall be aligned per Enclosure 4.9 (Backup Starting Air System for VI Compressors) when starting air pressure is < 60 psig as read on 0VIPG6270 or OVIpG6280 (TD-545, V-32) for startup or continued operation of VI Compressors D, E and F. {PIP 95-2210)

3. Procedure Refer to Section 4 (Enclosures)

4. Enclosures 4.1 Alignment of VI Compressors D, E and F for Startup 4.2 Manual Startup of VI Compressors D, E and F 4.3 Manual Shutdown and Isolation of VI Compressors D, E and F 4.4 Start and Stop Rotation of VI Compressors Using VI Computer 4.5 Statup of lnstrument Air Dryers 4.6 Shifting Instrument Air Filters 4.7 Shifting Instrument Air FiltedDryer Trains 4.8 Alignment for VI System to Supply VS System 4.9 Backup Starting Air System for VI Compressors 4.10 S t a d p , Place in Service on VI Header and Shutdown of Backup Temporary VI Compressor 4.11 Operability Startup Test of Backup Temporary VI Cornpressor 4.12 Loss of VI Compressor Computer 4.13 Placing Desiccant Dryers in Service 4.14 Removing Desiccant Dryers Prom Service 4.15 Starting VI Compressors D, E or F for h4aintenance Checkout 4.16 Status Verification of VI Compressors Using VI Computer

Enclosure 4.10 OPI@'A/6450/005 Startup, Place in Service on VI Header Page 1 o f 4 and Shutdown of Backup 'Temporary VI Compressor

1. lnitial Conditions

~- 1.1 Review the Limits and Precautions.

NOTE: The following step may be pe8omed out of sequence at IJnitiWCC SRO discretion to prevent garage personnel being called in itnnecessariiy. I

__ 1.2 Noti@ Catawba Garago at ext. 3590 (or Shih Work Manager on hackshift) that the Backup Temporary VI Compressor will he operated and servicing may be required during or after the run.

Person notified

.- 1.3 Verify the engine oil level is full (dipstick on side of engine),

__ 1.4 Verify the compressor oil is visibie in sight glass (sight glass should be full with compressor shutdown) beside compressor control panel.

Enclosure 4.10 OP/O~k~6450/005 Startup, Place in Service on VI Header Page 2 of 4 and Shutdown of Backup Temporary VI Compressor

2. Procedure

- 2. I Start the Backup Temporary VI Compressor as follows:

61 2.1.1 Unplug the battery charger. (Battery charger is located inside engine compartment opposite side from battery.)

0 2.1.2 Ensure ITVI-20 (Compressor Service Valve) is open. {PIP 96-2352)

NOTE: The following steps to be performed from the compressor control pmel located on the front of the compressor.

2.1.3 Place the "POWER" toggle switch in the "ON" position.

2.1.4 Ensure fuel level is adequate.

0 2.1.5 In freezing weather perform the following:

2.1.5.1 Place the "HEATERS" toggIe switch in the "ON" position to energize cylinder head glow plugs.

2.1.5.2 Proceed afier 60 seconds (time permitting).

2.1.6 Press and hold the "BYPASS" swiich for 10-15 seconds.

2.1.7 While holding the "BYPASS" switch, press the "START" button.

2.1.8 WHEN the engine starts, release the "STARY button.

2.1.9 \I'" the cngine speed is ? 1000 rptn, release the "BYPASS" button.

n 2.1.10 After the engine has run for 5 minutes (time permitting), press the "SERVICE AIR" button to load the compressor.

0 2.1.11 Verify "COMPRESSOR DISCHARGE PRESSURE" increases io approximately 110 psig.

2.1.12 Ensure the "HEATER" toggle switch is in the "OFF" position.

Enclosure 4.10 OP!o/A/64SO/OOS Startup, Place in Service on VI Header Page 3 of 4 and Shutdown of Backup Temporary VI Compressor

-~.-- 2.2 Align the temporary aftercooler and air dryer for service as follows:

2.2.1 Press the "START" button on the "TEMPOIPARY AFTERCOOLHR VI SYSTEM" control panel (TB-S98,2C:-2E). 34).

E! 2.2.2 Cycle 1VI-540 (Port Aux Air Conlp Dryer Inlet Drain) (TB-594,2C-34) to drain any water out of the dryer inlet piping.

2.2.3 Slowly open the following valves:

El 2.2.3.1 1VI-512 (Port Aux Air Comp Dryer Inlet) (TB-S98,2C-34)

E! 2.2.3.2 1VI-513 (Port A m Air Comp Dryer Outlet) (TB-S98,2C-34) 3 2.2.4 Place the "AIR DRYER CONTROL POWER" switch to "ON" (TR-S98,2B-34).

... .- 2.3 Align to the VI System as follows:

El 2.3.1 Open 1Vi-417 (Port II.RT Camp Disch) (TB-598,2(1-34).

3 2.3.2 VeRflT compressor is maintaining approximately 110 psi&as read on the compressor control panel.

2.3.3 Verify the pressure drop across the temporary filters is Iess than 15 psid by subtracting the outlet pressure from the inlet pressure.

E! "FILTER A" 61 "FILTER B" NOTE: The Backup Temporary VI Compressor D K fuel oil tank holds than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when compressor is running fully loaded.

- 180 gallons and lasts less I I

-2.4 the Backup 'Temporary VI Compressor is to be left in service for greater thm 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, SKO notify the Unit 2 Turbine Rounds NLO to inspect the Compressor DIG fuel oil tank level on a regular frequency and initiate refill at Iess than li4 tank.

Enclosure 4.10 OPiOiAi64SOiO05 Stmtup, Place in Service on VI Header Page 4 of 4 and Shutdown of Backup Temporary VI Compressor NBTE: The Backup Temporary VI Cornpressor and Air Dryer is now supplying the VI System. The following steps are to shutdown the compressor and the dryer.

CADTION: In the following step, 1VI-417 (Port ILRT Comp Disch) should be closed slowly to prevent any sudden drop in VI header pressure which could result in the autostart of a

-_ 2.5 Shutdown the Backup Temporary VI Compressor, as follows:

2.5.1 Close the following valves:

0 2.5.1.1 1VI-417 (Port ILRT Comp Uisch) (TB-S98,2<;-34) 0 2.5.1.2 IVI-512 (Port Aux Air Comp Dryer Inlet) (TB-598; 2C-34) 0 2.5.1.3 1VI-513 (Port Aux Air Comp Dryer Outlet) (TR-598, 2C-34) 0 2.5.2 Place the "AIR DRYER CONTROL POWER" switch in the "OFF" position (TB-598,2B-34).

63 2.5.3 Press the "STOP RESET" button on the "TEMPORARY AFTERCOO1,ER VI SYSTEM" panel (TB-598,2C-2D, 34).

gl 2.5.4 Ensure the Backup Temporary VI Compressor has run for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

0 2.5.5 After the engine has run isolated for approximately 5 minutes, place the "POWER" toggle switch to the "OFF" position (located inside compressor controi panel).

0 2.5.6 Ensure the battery charger is plugged in. (Flattery charger is located inside engine compartment opposite side from battery.)

0 2.5.7 Cycle 1VI-540 (Port Aux Air Comp Dryer Inlet Drain) (TR-594, 2C-34) to drain any water out of the dryer inlet piping.

2.6 Do NOT file this enclosure in the Control Copy folder of this procedure

Page 1 of 11 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPMIPLANT-I 1 Place SSF Diesel in Operation CANDIDATE EXAMINER

Page 2 of 11 CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Stapt the SSF Diesel, energize ?SLXGand start the Standby Makeup Pump with the proper alignment to establish NCP Seal Injection within 10 minutes Alternate Path:

NO Facility JPM #:

AD003 KIA Ratinafs):

064 A4.01 (4.0M.3)

Task Standard:

Within 10 minutes the SSF Diesel is started, 1SLXG energized, and the Standby Makeup Pump is started with the proper alignment to establish NCP Seal Injection.

Candidate: Time Start :

NAME Time Finish:

Performance Rating: SAT ___ UNSAT - Question Grade ~ Performance Time -

Page 3 of 11 ToolslEsuiprmentlProcedures Needed:

Have enough copies of EQilN5000/ECA-0.0 Enclosure 2 available for each candidate.

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 ether 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.

INITIATING CUE:

Unit 1 has just suffered a loss of all AC power while operating in Mode 1. A Security Officer has been directed to establish Seal Injection from the SSF per Enclosure 2 of EP/1/A/5000/ECA-5.0. Another operator has been dispatched to swap power to IEMXS. The CR SRO directs you to establish seal injection from the SSF per Enclosure 2 of EP/l/A/5000/ECA-O.Q. This JPM is time critical once you get to the SSF~

Page 4 of I 1 START TIME:

EXAWNER NOTE: The time limit for this JPM is based on the time to perform the actual task considering each step must be explained to the examines with verbal feedback as appropriate. The JPM evaluates the operators ability to perform the task under simulated conditions, not real time. Safety considerations are made to preclude operators from running through the plant to satisfy JPM time requirements.

Record the time the candidate enters the SSF.

STEP 1: Obtain a copy of the appropriate procedure.

STANDARD: Operator locates EP/ZA/500O/CA-O.O Endosure 2 in the SSF.

EXAMINER CUE: When the candidate locates EP/1A/5000/ECA-0.0 Enclosure 2, hand himlher a clean copy of Enclosure 7 and tell himlher that it is current and complete.

COMMENTS:

NOTE Indications of ISLXG being de-energized are as follows:

e Normal lighting i n SSF off with emergency lights on

• LIN VOLTS on OCNSLOOOI indicating zero volts -SAT OAD-I1,8/6 LOAD CENTER ISLXG TROUBLE- LIT e LOAD CENTER ISLXG BUS VOLTAGE on ISLXG indicating zero volts.

-LJNSAT STEP 2: -IF I S U G has been de-energized, THEN place the SSF diesel in operation as follows: (Step 1) -SAT STANDARD: Candidate locates LINE VOLTS indication on OCNSLOOOI

• • CUE When the candidate \ocafes OCNSLQOOI. indicate that voltage is -UNSAT reading zero. If asked, inform the candidate that the normal SSF iighfing is OFF and the emergency lighting is ON, QAD-if B/6 is LIT and LOAD CENTiZR I S U G BUS VOLTAGE on ISLXG hndicafes zero volts. **

COMMENTS:

• • Micited Cues Are To Be Used Only If JPM Peaformanee Is Being Simulated.

Page 5 of 11 CRITICAL STEP 2TANDARD: Candidate places SSF B/G MODE switch in "EMERG" position.

• • CUE: SSF D/G MODE switch in "EMERG" position**

-SAT COMMENTS:

-UNSAT STEP 4: Start the DIG by placing the "SSF B/6" switch in the "ON" position. CRITICAL (Step 1.b.) STEP STANDARD: Candidate places the "SSF D/G" switch in the "ON" position.

• • CUE: SSF BIG switch in "0N"position. BIG fires and engine rpm

-SAT increases to a constant speed.**

COMMENTS: -UNSAT STEP 5: If the engine does not start within 30 seconds, THEN: (Step I C )

STANDARD: Candidate notes from previous cue that engine started and step does

-SAT not apply. Goes to Step 1.d.

COMMENTS:

-UNSAT

• Stalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Page 6 of 11 CRITICAL STEP

TANBARB

Candidate locates SSF DIG GOV CTRL and frequency meter to adjust SSF diesel speed to 60 He.

-SAT

• • CUE: Frequency is 60 Hz. **

COMMENTS: -UNSAT S E P 7: Adjust the SSF DIG VOLT ADJUST until VOLTS is 600 to 660 CRlTlCAL vults. (Step 1.e.) STEP STANDARD: Candidate locates SSF DIG VOLT ADJUST and volt meter and states he/she would adjust SSF diesel voltage to 600 tu 660 volts

-§AT

• • CUE: Volfage is reading 6fQ voEfs.**

COMMENTS:

-UNSAT Press the TRIP pushbutton on ISLXG NORM FDR FRM ITA on CRITICAL the SSF console. (Step 1.f.) STEP STANDARD: .Candidate depresses the TRIP pushbutton on the SSF Control -SAT Panel for ISLXG NORM FDR FRM ITA. Verifies Green OPEN light is LIT and the Red CLOSED light is BARK.

I -UNSAT

• • CUE: The TR1Ppushbuttonon the SSF Control Panel for ISLWG NORM FDR FRM ITA has been delpressed. The Green OPEN light is LITand ihe Red CLOSED light is DARK.*

COMMENTS:

• • ItalicizedCues Are To Be Used Onry If JPM Petformance Is Being Simulated.

Page 7 of I 1 STEP 9: Open the following breakers: (Step 1.g.)

e ISU(G4C (MCC SMXG Feeder) -SAT e 1SLXG-4D (SSF Batt. Charger SDSClj e ISLXG-5C (SSF Batt. Charger SDSC2) 1SLXG-5D (SSF Batt. Charger SDSCS) -UNSAT STANDARD: Candidate locates each breaker on I S M G . As each breaker is located, candidate states that he/she would rotate the operating handle in the counterclockwise direction =would depress the "OPEN" pushbutton on the breaker face. The Green "OPEN" light is LIP and the Red

'CLOSED" light is DARK.

• • CUE: The operating handie has been turned in the counterclockwise direction. The Gmen "OPEW' light is LIT and the Red "CLOSED" fight ls DARK for each breaker.**

COMMENTS:

STEP 10: Press the "CLOSE pushbutton for the "SSF D/G BKR" OR the SSF CRlTlCAL console. (Step1.h.) STEP STANDARD: Candidate depresses the "CLOSE" pushbutton for the "SSF'DIG BKR" on the SSF control panel. Verifies the Red "CLOSED" light is -SAT LIT and the Green "OPEN" light is BARK.

• • CUE: The "Cb0SE"pushbutton for the "SSF 'DIG BKR" has been depressed. The Green "OPEN" light is LIT and the Red "CLOSED" -UNSAT light is DARK.**

COMMENTS:

Walicized Cues Are Po Be Used Onfy E f JPM Performance Is Being Simulated.

Page 8 of I 1 STEP 11: When SSF DIG has been running ~ Q 10 F seconds, then close breaker 1SLXG-C (Motor Control Center SMXG Supply). (Step 1.i.) CRITICAL STEP STANDARD: Breaker lSbXG4C closed by turning the operating handle clockwise to CLOSF position after allowing DIG to run for 10 seconds Verifies the Red CLOSED light is LIT and the Green OPENlight is -SAT DARK and breaker noise is heard when closed.

• • CUE: THE operating handle for fSu(e-4C. has been turned in the clockwise direction. The Red CLOSED right is LITand the Green -UNSAT OPEN light is DARK. Breaker noise is heard.**

COMMENTS:

STEP 12: Close the following breakers on 1SLXG at 10 second intervals:

(Step Z .j.) -SAT ISLXG-4B (SSFBatt. Charger SDSCl Feeder) 1SkXG-5C (SSF Batt. Charger SQSC2 Feeder) 0 1SLXG-5B (SSFBatt. Charger SQSCS Feeder) -UNSAT STANDARD: Candidate locates each breaker on ISLXG. As each breaker is located, candidate states that he/she would rotate the operating handle in the clockwise direction or would depress the CLOSEpushbutton on the breaker face. The Red CLOSEBlight is LIT and the Green OPEN light is DARK.

• • CUE: The operating handle has been turned in the clockwise direction.

The Red CLOSED light is LIT and the Green OPN light is DARK for each breaker.**

COMMENTS:

• • Italicized Cues Are To Be Used Onry If JPM Performance Is Being Simulated.

Page 9 of 11

-SAT

• • CUE: 1EMXS is energized.**

a. Ensure INV-876 (Stdby MIU To Cont Equip Smp IA) - CLOSED.

-UNSAT STANDARD: Candidate ensures the Green CLOSED light is LIT and the Red OPENlight is DARK (SSF Control Console)

^*CUE: 1NV-876 Green CLOSED fight is LIT end the Red OPEN light is DARK.**

COMMENTS:

STEP 14: Ensure the following valves - OPEN: (Step 2.b.j 1NV-865A (Stdby MIU Prnp Suct Frm Xfer Tube CRITICAL 1NV-89214 (Stdby MIU Pmp Filt Otlt) STEP INV-877 (Stdby MIU Prnp To NC Prnp Seal inj)

STANDARD: Candidate ensures the Red OPEN light is LIT and the Green -SAT CLOSED light is DARK for each valve.

• • CUE: The Red OPEM light is LIT and the Green CLOSED light is BARK for each valve.** -UNSAT 1 COMMENTS:

• • Italicized Cwes Are TQBe Used Only I f JPM Perfcrmance Is Being Simulated.

Page 10 of 1I STEP 75: Start "STBY M/U PUMP #I" by depressing "ON" pushbutton on SSF Console. (Step 2. c.) CRITICAL STEP EXAMINER NOTE: Record the time the Standby Makeup Pump is started.

STANDARD Candidate depresses the STBBY M/U PUMP #Red I "ON" pushbutton -SAT and verifies the Red "ON" light is LIT and the Green "OFFslight is DARK. (SSF Control Console).

• • CUE:The Standby Makeup Pump Red "ON fight k LIP and the Green -UNSAT "OFF" light is DARK. **

COMMENTS:

STEP 16: Notify the Control Room SRO of status. (Step 2.d.)

-SAT EXAMINER NOTE: Do Not allow the candidate to pick up the telephone receiver as this Could hinder communications during an actual emergency.

-UNSAT STANDARD: Candidate locates telephone and simulates calling the Control Room.

"CUE: This is the Control Room SRO. I understand that seal injection has been established to the Unit 1NC pumps from the SSF**.

COMMENTS:

STEP 17: Monitor SSF QIG operation s SAT EXAMINER CUE: Another operator will monitor SSF DIG operation.

-UNSAT This JPM is complete TIME STOP:

• • Italicized Cues Are To Be Used O d y If JPM Performance Is Being Simulated.

Page 11 of I 1 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INlTlATlNG CUE:

Unit 1 has just suffered a loss of all AC power while operating in Mode 1. A Security Officer has been directed to establish Seal Injection from the SSF per Enclosure 2 of EP/I/A/5000/ECA-0.0.Another operator has been dispatched to swap power to 1EMXS. The CR SRQ directs you to establish seal injection from the SSF per Enclosure 2 of EP/?/A/5000/ECA-O.O. This JPM is time critical once you get to the SSF.

• • italicized Cues Are To Be Used Onfy If JPM Performance Is Being Simulated.

II 1

I CNS LOSS OF ALL AC POWEK I PAGE NO. 11 EP/1/A1500~

&QE Indications of ISLXG being de-energized are as follows:

e Normal lighting in SSF off with emergency lights on "LINE VOLTS" on QCNSLOQOIindicating zero volts 0 QAD-71, B16 "LOAD CENTER 1SLXG TROUBLE" LIT ~

"LOAD CENTER I S M 6 BUS VOLTAGE on ISLXG indicating zero volts.

1. E 1 S U G has been deenergized, =place the SSF diesel in operation as follows:

- a. Ensure the "SSF B/G MODE" switch is in the "EMERG" position on the SSF console.

- b. Start the D/G by placing tRe "SSF D/G" switch in the "ON" position.

c. IF the engine does not start within 30 seconds, T I ' .

- 1) Place the "SSF B/G" switch in the "OFF" position.

- 2) E DIG turned over but did net tire during the W G start attempt, T u t u r n the manual override knob on the shutdown valve clockwise to permit fuel flow through the valve.

3) WHEN 1to 2 minutes has passed, THEN RETURN TO Step 1.a.

- d. Adjust the "SSF D/G GOV CTRL" to bring frequency to 60 fl.2 Hz.

- e. Adjust the "SSF DIG VOLT ADJUST" until "VOLTS" is 600to 660 volts.

- f. Press the "TRIP" pushbutton on "tSLXG NORM FDR FRM ITA' on SSF console.

g. Open the following breakers:

- e ISLXG-4C (Motor Control Center SMXG Supply)

E 1SLXG-4D (SSF Normal Battery Charger SDSCl Feeder)

- ISLXG-5C (SSF Normal Battery Charger SCSC2 Feeder)

-

• ZSLXG-5B (SSF Standby Battery Charger SBSCS Feeder).

- h. Press the "CLOSE" pushbutton fer the "SSF D/G BKR" on the SSF Panel.

- i. WHEN SSF D/G has been running for 10 seconds, T m c l o s e breaker 1SLXG-4C (Motor Control Center SMXG Supply).

LOSS OF ALL AC POWER EP/l/N5000/ECA-O.O

1. (Continued)

j. Close the following breakers on ISWG at 10 second intervals:

- e ISU(G4D (SSF Normal Battery Charger SDSCl Feeder)

-

• ISu(G5C (SSF Normal Battery Charger SDSC2 Feeder)

- e 1SLXGdD (SSF Standby Battery Charger SDSCS Feeder).

2. WHEN IEMXS has been energized, m:

- a. Ensure INV-876 (Stdby M/U To Cont Equip Smp 4A) - CLOSED.

b. Ensure the following valves OPEN:

~

- 1NV-86% (Stdby M/U Pmp Suct Frm Xfer Tube)

- 1NV-872A (Stdby MIU Prnp Fiit Otlt)

- 1NV-877 (Stdby MIU To NC Bmp Seal lnj).

- c. Start "STBBY WU PUMP #I" by depressing "ON" pushbutton on SSF consnle.

- d. Notify Control Room SRO of status.

- 3. Monitor SSF DIG operation. REFER TO 08/0/8/6350/011 (Standby Shutdown Facility Diesel Operation).