Text

Initial Exam 2009-301 Draft Administrative JPMs
	ML100470442
Person / Time
Site:	Catawba
Issue date:	02/02/2010
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CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE JPM IRIS ADMIN Calculate Reactor Vessel Head Venting Time CANDIDATE EXAMINER JPM IRIS 2009 Page 1 of 7

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, 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.

SIMULATOR SETUP Insert the following malfunctions:

(1WP5090 LOWER CNT AIR TEMP A METER).

XMT-W012 (1WPS090 METER), VALUE=140 (1WP5110 LOWER CNT AIR TEMP B METER).

XMT-W013 (1WPS110 METER), VALUE=140 (1WP5170 LOWER CNT AIR TEMP C METER).

XMT-W014 (1WPS170 METER), VALUE=140 XMT-W015 (1VVPS190 XMT-W01S (1WP5190 LOWER CNT AIR TEMP 0 D METER).

METER), VALUE=140 IND-W030 (1 MIPS320 INO-W030 MIP5320 CNT TRN A H2 ANAL METER), VALUE=1.5 METER). VALUE=1.S IND-W032 (1 MIP5330 CNT TRN B H2 ANAL METER).

INO-W032 (1MIPS330 METER), VALUE=1.S VALUE=1.5 IND-CNT003 (1 NSPS070 INO-CNT003 NSP5070 CNT PRESS METER PI-937 METER). METER), VALUE=3.0 IND-CNT004 NSP5060 CNT PRESS METER PI-936 METER).

INO-CNT004 (1 NSPS060 METER), VALUE=3.0 IND-CNT005 NSP5050 CNT PRESS METER PI-93S INO-CNTOOS (1 NSPSOSO PI-935 METER).

METER), VALUE=3.0 INO-CNT006 (1 NSPS040 IND-CNT006 NSP5040 CNT PRESS METER PI-934 METER). METER), VALUE=3.0 INO-NC036 (1NCP5120 LOOP B HOT LEG W/R PRESS METER PI-40S IND-NC036 (1NCPS120 PI-405 METER).

METER), VALUE=1000 IND-NC037 (1NCP5140 LOOP C HOT LEG W/R PRESS METER PI-403 METER).

INO-NC037 (1NCPS140 METER), VALUE=1000 Take digital photographs of the gauges listed above.

INITIATING CUE:

A LOCA is in progress on Unit 1. The CRS directs you to calculate and record the maximum reactor EP/11A15000/FR-1.3 Response to Voids in Reactor Vessel.

vessel head venting time per Enclosure 5 of EP/lIN5000/FR-1.3 JPM IRIS 2009 Page 3 of7 of 7

Time.: _

Start Time:. __ ___

iJ-J

~ EP/11A15000/FR-1.3, EP/11A15000/FR-1.3, Enclosure 5, Step 1 CRITICAL STEP Calculate A where A =

~ 9500 X (P + 14.7) X 492 14.7 (T+460)

(T+460)

=

Where: P ~ Containment pressure (PSIG)

(PSI G)

T==Lower Containment temperature rF)

(OF)

STANDARD

_ _ SAT Calculate A

_ _ UNSAT Determined containment pressure to be 3.0 psig to 3.2 psig based on pictures provided.

Determine Lower Containment Temperature to be 135 OF of -145 OF based on

- 145 of pictures provided 3.0, 135 A Using 3.0,135 =9500 X (3.0 + 14.7) X

~ 492 = 9458.6

=

14.7 (135+460) 3.0, 145 A Using 3.0,145 =

~ 9500 X (3.0 + 14.7) X 492 = 9302.3

=

14.7 (145+460)

Using 3.2, 135 A ~

3.2,135 = 9500 X (3.2 + 14.7) 14.71 X 492 = 9565.5

~

14.7 (135+460)

Using 3.2, 3.2,145 145 A =

~ 9500 X (3.2 + 14.7) 14.71 X 492 =

= 9407.4 14.7 (145+460) 3.1, 140 A = 9500 X (3.1 + 14.7) X 492 Using 3.1,140 = 9432.8 14.7 (140+460)

(A = 9302 to 9566 is acceptable)

COMMENTS JPM IRIS 2009 Page 4 of 7

~ EP/1/A15000/FR-1.3,

~ EP/1/A/5000/FR-1.3, Enclosure 5, S1ep Step 2 CRITICAL STEP Calculate B where B = = (3 - H) X A

=

Where H = Containment Hydrogen Concentration (%)

STANDARD

_ _ SAT Determine H2 concentration from pictures provided to be between 1.25 and 1.75.

_ _ UNSAT Using bounding values of A (9302 to 9566):

9566):

B = (3 -1.25) X 9566 = 16740.5

B = (3 -1.75) X 9302 = 11627.5 Using middle value of 9483 8 = (3-1.5) X 9483 =14224.5 (8 range of 11627 to 16741 is acceptable)

COMMENTS P

~ EP/EP/1/A/5000/FR-1.3, 1/A15000/ FR-1.3. Enclosure 5,

5. Step 3 CRITICAL STEP Determine C from the curve for the current NC system pressure.

STANDARD

_ _

_ _ SAT Determines NC pressure from pictures to be 950 psig to 1050 psig.

psig.

_ _ UNSAT Reads approximately 3250 SCFM from graph.

(range of 3000-3500 SCFM is acceptable)

COMMENTS JPM IRIS 1R1 S 2009 Page 5 of 7

f.i-J EP/11A15000/FR-1.3,

~ EP/lIAl5000/FR-1.3, Enclosure 5, Step 4 CRITICAL STEP Calculate T T

T== BIC = Venting time in minutes STANDARD

_ _ SAT Using bounding values for Band C: C:

_ _ UNSAT T= = 11627/3500 = =3.32 minutes T = 16741/3000 16741 / 3000 = 5.58 minutes (3.3 - (3 minutes, 18 seconds) to 5,60 5.60 (5 minutes, 36 seconds) is acceptable)

Using actual values: T =14224/3250 =4.37 minutes =4 minutes, 23 seconds COMMENTS TIME STOP: _ __

JPM IRIS 2009 Page 6 of 7

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

INITIATING CUE:

A LOCA is in progress on Unit 1. The CRS directs you to calculate and record the maximum reactor EP/11A15000/FR-1.3 vessel head venting time per Enclosure 5 of EP/1/N500 0/FR-1.3 Response to Voids in Reactor Vessel.

CNS RESPONSE TO VOIDS IN REACTOR VESSEL PAGE NO.

EP/1/A15000/FR-1.3 41 of 46 Enclosure 5 - Page 1 of 1 Rev 15 DCS DeS Allowable Hydrogen Venting Time NC SYSTEM PRESSURE (PSIG) 2400 I If I

2200 I I

I 2000 If I CALCULATION OF MAXIMUM II ALLOWABLE VENTING TIME 1800 I

I STEP 1: Calculate A I (P + 14 1600 J

.7) 14.7) 492 I A A -= 9.500 9,500 x - - - - x - - - -

II 14.7 IT (T + 460) 1400 I where: P - Containment pressure I IPSIG)

(PSIG)

I T -= Lowe Lowerr containment 1200 I temperature (deg F) 1/

I STEP 2: Calculate B 1000 I B =- (3 - H) x A B A where: H -= Containment hyd hydrogen rogen I

I concentration (X)(%)

800 I STEP 3: Determine C from the curve 1

I for the cucurrent rrent NC system 600 pressure.

I If 400 STEP 4: Calculate T I T -= BIC B/C -= Venting time in minutes I

I 200 I L

o '£ o 2000 4000 6000 8000 C =- HYDROGEN FLOW RATE (SCFM)

NC pressure _____ __ PSIG. PS IG. Maximum allowable venting time _ ____

_ _ minutes.

"'Q'"

QVlVl~TNMENT SUUPlEVEl I AINMENT SUMP LEI/Et.

TRAIN A H2ANA/.

H2 ANAL PRESS PRE88 CONTAINMENT TRAIN B SUMP LEVEL H2 AN4L PRESS PRE8S IJ l

[

r t- 1O f -10

-5 PAM 1llRl fR) -- CONT , DIATION (RlHRl RlADIATION IRIHRl 22161

( &) --

CONT VENT UNIT MNT RADIATION RAOIATION (RJHR>

IRIHRl VE n

I

--r.~r - --

-~~-- _._-

f~~CTO~~

INCORE INST RM TEMP A II UPPE R . CO NT AIR A TE MP B B I A LOWER CONT AIR TEMP B

B C D

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE JPM 2R2S ADMIN Determine the amount of boric acid required to get Control Bank D above the Rod Insertion Limits CANDIDATE EXAMINER JPM 2R2S 2009NRC Page 1 of 7

CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task Determine the amount of boric acid required to get Control Bank D above the Rod insertion limits.

Alternate Path DYES DNO r2l N/A

[ZJ Time Critical DYES r2l [ZJ NO Evaluation oD Simulator Din-Plant ~ Classroom IS]

Safety Function ____ r2l N/A

[ZJ Location Evaluation Validation 25 minutes

~ Perform IS] DSimulate Method Time JPM Type oD Bank o DNewNew r2l

[ZJ Modified KIA GENERIC 2.1.25 (3.9/4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12)

Standard Candidate determines that rod insertion limit at 60% power using the Reactor Operating Data, R.O.D book or COLR is 65-75 steps on Control Bank D. Performs calculation and determines that 1067-1223 gallons is the amount of boric acid required to be added to withdraw control bank D rods to that position.

References AP/1/A/55001003 (Load Rejection), revision 036 Rod Book sections 2.2,4.1, 5.5, 5.6.3 COLR Figure 3 NOTE: REPLACE APPLICABLE SECTIONS OF ROD BOOK AND COLR IN THE REFERENCE SETS TO BE USED FOR THIS JPM.

Candidate Start Time End Time ------

Duration Performance Rating 0 D Satisfactory o Unsatisfactory D

Examiner (Printed Name) (Signature) (Date)

Comments JPM 2R2S 2009NRC Page 2 of 7

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

Core burnup is 25 EFPD.

Boron concentration is 1360 ppm CURRENT CONDITIONS:

AP/1/Af55001003, Load At 1030 today, Unit 1 CF Pump 1A tripped. The crew entered AP/11A155001003, Rejection.

At 1040, plant stabilization is in progress with the following conditions:

o Reactor power is 60%

o No dilutions are in progress o 1AD-2, B/9 "Control Rod Bank Lo-Lo Limit" is LIT o Control rods are in manual o Control Bank Positions:

A==226 steps

=

B =226 steps

=

C 110 steps

=

D 0 steps

The OAC is unavailable INITIATING CUE:

AP/1/Af5500/003, You have been directed to perform Enclosure 3, Rod Insertion Limit Boration, of AP/11A155001003, Load Rejection.

Without any consideration for the effects of Xenon for rod insertion limits (RIL) requirements, calculate the MINIMUM (i.e.(Le. INTERPOLATE) gallons of boric acid addition required to meet RIL.

JPM 2R2S 2009NRC Page 3 of 7

Start Time:-_- __-

~ AP/1/55001003, Enclosure 3, Step 1.a If the control rods cannot be maintained above the rod insertion limits, then:

Stop any dilutions in progress.

STANDARD

_ _ SAT Determines no dilutions are in progress based on the cue provided from initial conditions.

_ _ UNSAT COMMENTS

~ AP/1/55001003, Enclosure 3, Step 1.b CRITICAL STEP CAUTION: Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6.

NOTE: OAC point C1 L4409 (Ctrl Bank Tech Spec Insertion Lmt Reached) and ROD Book (Section 2.2) provide rod insertion limit indication.

b. Borate NC system as required, to restore rods above insertion limits.

STANDARD

_ _ SAT Student reads the caution and note in step 1.b and determines that ROD Book section 2.2 is needed.

_ _ UNSAT EXAMINER NOTE: The procedure says to use Section 2.2 of the ROD book; however some students may use Figure 3 of the COLR. This is equally acceptable. If the student uses the COLR, the RIL could be based on the calculation included with the graph. If they use the ROD Book, it will be based solely on reading a graph.

If COLR is used: 2.3 X 60 - 69 = 69 steps on Bank D.

If Rod Book Section 2.2 is used, range of 65-75 steps on Bank D 0 is acceptable.

COMMENTS JPM 2R2S 2009NRC Page 4 of 7

ll-J

~ AP/1/55001003, Enclosure 3, Step 1.b CRITICAL STEP

b. Borate NC system as required, to restore rods above insertion limits.

STANDARD

_ _ SAT Using 69 steps withdrawn on Bank D:

_ _ UNSAT Uses RO.D. book section 5.6.3 pg 2 of 6 for IRW HFP, Eq Xe, Eq Sm, and uses data from the 4 EFPD column (0-50 EFPD), and determines:

Bank C @ 110 step, rods are worth 1212 pcm

Bank D 65-75 steps, rods are worth 630 to 552 pcm for a difference of

-660 to -582 pcm of reactivity.

Uses RO.D. book section 5.5 for HFP ARO and determines differential boron worth is -6.04 pcm/ppmb.

Calculates -6601-6.04 = = 110 ppm

=

-582/-6.04 96 ppm (96-110 ppm is acceptable)

Calculates final required boron concentration:

=

1360 ppm current [B] + 96 ppm = 1456 ppm final [B]

1360 ppm current [B] + 110 ppm = 1470 ppm final [B]

(1456-1470 ppm is acceptable)

Uses table 4.1 in the RO.D. book for Hot RCS (Modes 1,2 and 3) to determine the gallon of boric acid to go from 1360 to the range of 1456-1470 ppm 1360 ppm to 1440 ppm = 888 gals 1440 to 1456 =(224/20)*16 =179.2

=

179.2+888 = 1067.2

=

1360 ppm to 1460 ppm = 1111 gals 1460 to 1470 = =(224/20)*10 == 112

=

112+1111 = 1223 (1067 - 1223) gallons is acceptable (1067*1223)

COMMENTS JPM 2R2S 2009NRC Page 5 of 7

Li-J

~ AP/1/55001003, Enclosure 3, Step 1.c

c. Ensure compliance with Tech Spec 3.1.6 (Control Bank Insertion Limits).

STANDARD SAT Determines that the unit is NOT currently in compliance with 3.1.6.

UNSAT COMMENTS TIME STOP: _ __

JPM 2R2S 2009NRC Page 6 of 7

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

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

Core burnup is 25 EFPD.

Boron concentration is 1360 ppm CURRENT CONDITIONS:

At 1030 today, Unit 1 CF Pump 1A tripped. The crew entered AP/1/AJ55001003, AP/1/A/55001003, Load Rejection.

At 1040, plant stabilization is in progress with the following conditions:

o Reactor power is 60%

o No dilutions are in progress o 1AD-2, B/9 "Control Rod Bank Lo-Lo Limit" is LIT 1AD-2, o Control rods are in manual o Control Bank Positions:

A= =226 steps

=

B = 226 steps

=

C = 110 steps D = 0 steps

The OAC is unavailable INITIATING CUE:

AP/1/AJ55001003, You have been directed to perform Enclosure 3, Rod Insertion Limit Boration, of AP/1/A/55001003, Load Rejection.

Without any consideration for the effects of Xenon for rod insertion limits (RIL) requirements, calculate the MINIMUM (Le. INTERPOLATE) gallons of boric acid addition required to meet RIL.

JPM 2R2S ADMIN

CNS LOAD REJECTION PAGE NO.

AP/1/Al5500/003 AP/1 IN55001003 35 of 36 Enclosure 3 - Page 1 of 1 Revision 36 Rod Insertion Limit Boration

1. IF the control rods cannot be maintained above the rod insertion limits, THEN:

a. Stop any dilutions in progress.

CAUTION Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6.

NOTE OAC point C1 L4409 (Ctrl Bank Tech Spec Insertion Lmt Reached) and R.O.D Book (Section 2.2) provide rod insertion limit indication.

b. Borate NC system as required, to restore rods above insertion limits.

c. Ensure compliance with Tech Spec 3.1.6 (Control Bank Insertion Limits).

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE JPM 3RADMIN Classify a DIG Start and Complete a Logbook Entry CANDIDATE EXAMINER JPM 3R 2009 NRC Page 1 of 7

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE Task Classify a DIG Start and Complete a Logbook Entry Alternate DYES DNO ~N/A

[gI NIA Time Critical DYES [gI ~NO NO Path

~N/A

[gI Evaluation Location o Simulator Din-Plant ~ Classroom Safety Function __ __ NIA Evaluation Validation 14 minutes

~ Perform DSimulate Method Time JPM Type ~ Bank

[gI o New o Modified KIA 2.2.12 Knowledge of surveillance procedures. (CFR: 41.10/45.13) 41.10 I 45.13) (3.7/4.1)

Standard Classify the DIG start as a VALID FAILURE and correctly enters data into the logbook.

References OMP 2-28 (Diesel Generator Logbook) rev 025 Candidate Start Time End Time ------

Duration Performance Rating D Satisfactory D Unsatisfactory Examiner (Printed Name) (Signature) (Date)

Comments JPM 3R 2009 NRC Page 2 of 7

SIMULATOR SETUP UseSNAP _ _

NIA READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Unit 2 is in Mode 1. You were an extra operator on shift and assisting the Operation Test Group in a scheduled surveillance test of the 2B Emergency Diesel Generator. The test was conducted using procedure PT/21A143501002B (DIG Operability Test).

The history of what occurred during the 2B DIG test was as follows:

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

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

The DIG was started at 0820

The DIG ran loaded to 3600 KW from 0830 to 0905

At 0905, the DIG tripped

DIG annunciator panel light Al5 "TRIP LOW LOW PRESS LUBE OIL" was LIT INITIATING CUE:

Classify the test and complete Diesel Generator Logbook entries for this test per Attachments 10.1 and 10.2 of OMP 2-28 and submit to the CRS for review.

JPM 3R 2009 NRC Page 3 of 7

START TIME: _ __

LLJ LU Based on initial conditions, candidate refers to OMP section 6 to determine the CRITICAL STEP TEST CLASSIFICATION.

STANDARD

_ _ SAT Candidate determines that the test is a VALID FAILURE based on criteria 6.4 A

_ _ UNSAT EXAMINER NOTE: When student is ready to fill out the logbook provide a blank copy of enclosure 10.1 and a filled out copy of enclosure 10.2 as provided.

COMMENTS JPM 3R 2009 NRC Page 4 of 7

~

8-J Operator enters appropriate information on Attachment 10.1 using information CRITICAL STEP from the initial conditions.

STANDARD

_ _ SAT Enters 2B DIG

_ _ UNSAT Enters his name Enters start attempt based on last entry on 10.2 (2009-12)

Enters today's date Checks PT/1 (2)/4350/002A(B) as procedure used Checks SCHEDULED SURVIELLANCE as Reason for DIG Operation Enters TURBO PRE LUBE for type of start Enters engine start time 0820 Enters engine shutdown time 0905 Enters run time as 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Calculates total run time as 20.55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months (19.8+0.75)

Enters classification (VALID FAILURE)

Enters reason DIG start was not a valid success (tripped on LOLO Lube Oil Pressure prior to reaching one hour at greater that 2875 KW)

Checks MCE Rotating Equipment supervisor or designee (and may state that they will notify him)

EXAMINER CUE: If notified, state "MCE Rotating Equip supervisor notified"

Checks PIP block since a PIP is required for this start EXAMINER CUE: "PIP C-09-07500 was written by another operator. The CRS will review the Log Sheet and route it."

DENOTES CRITICAL ITEMS COMMENTS JPM 3R 2009 NRC Page 5 of 7

~

2J Logs the start into the Index Sheet (Enclosure 10.2)

STANDARD

_ _ SAT Enters Start # as 2009-12 Enters Date as todays date _ _ UNSAT Enters Test Classification as "VALID FAILURE" Enters run time as 0.75 hrs Enters yearly run time as 20.55 hrs Enters PIP # as C-09-07500 COMMENTS TIME STOP: _ __

JPM 3R 2009 NRC Page 6 of 7

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

INITIAL CONDITIONS:

Unit 2 is in Mode 1. You were an extra operator on shift and assisting the Operation Test Group in a scheduled surveillance test of the 2B Emergency Diesel Generator. The test was conducted using procedure PT/21A143501002B (DIG Operability Test).

The history of what occurred during the 2B DIG test was as follows:

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

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

The DIG was started at 0820

The DIG ran loaded to 3600 KW from 0830 to 0905

At 0905, the DIG tripped

DIG annunciator panel light Al5 "TRIP LOW LOW PRESS LUBE OIL" was LIT INITIATING CUE:

Classify the test and complete Diesel Generator Logbook entries for this test per Attachments 10.1 and 10.2 of OMP 2-28 and submit to the CRS for review.

Operations Management Procedure 2-28 Page 1 of 1 Attachment 10.1 Diesel Generator Log Sheet DIESEL GENERATOR _ _ _ _ _ _ __

RECORDED BY -----------------

START ATTEMPT NUMBER DATE _ _ _ _ _ _ _ _ _ __

PROCEDURE USED: REASON FOR DIG D/G OPERATION:

oD PT/1(2)/A/4350/002A(B) (DIG (D/G Operability Test) 0D Scheduled Surveillance oD OP/1(2)/A/6350/002 (DIG Operation) 0D Opposite Train Inoperable oD Other, Specify: 0D Functional Verification (Maintenance) oD Other, Specify: _

__ __ __ ___ _______

TYPE OF START: TEST CLASSIFICATION:

oD Turbo Prelube (See OMP 2-28, Sect. 6.)

oD Non-Prelube 0D VALID SUCCESS Time required to achieve a frequency of

> 57 Hz

~ sec.

OPERATING DATA: Time required to achieve a voltage of DIG Engine Start DatelTime Date/Time ________________

_ _ _ _ _ _ _ __ ~ 3950 volts

sec.

DIG Engine Shutdown DatelTime ___________

_ _ _ _ __ _ Time Load ~ 2875 KW ______

Load:::: _ _ _ _ _ hrs.

Run Time (hrs) _________

_ _ _ _ ___ Steady state voltage and frequency of

Total DIG Engine Yearly Run Time _______ Hrs. 3950-4580 volts and 58.8 to 61.2 Hz.

oD INVALID TEST oD INV INVALID ALID FAILURE oD VALID FAILURE Explain in detail the reason DIG D/G operation was not a VALID SUCCESS/failed SUCCESSlfailed to meet acceptance criteria.

oD MCE ROTATING EQUIPMENT SUPERVISOR OR DESIGNEE Required if Valid or Invalid Failure oD PIP # (Refer to 8.1.K for PIP applicability) _ _

__ __ __ __ ____ ___ __ __ __ ____ __

__ __

oD REVIEW (CRS) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

o ROUTE COPY to MCE Rotating Equipment Supervisor or Designee D

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

Operations Management Procedure 2-28 Page 1 of 1 Attachment 10.2 Index Sheet DIG 28 Yearly Run Time Run Time Start # Date Test Classification Hrs. Hrs. PIP #

2009-10 10/16/09 VALID SUCCESS 1.8 18 2009-11 11/13/09 VALID SUCCESS 1.8 19.8

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE JPM 3S ADMIN Determine SLC requirements and complete a Unit Vent Flow Manual Calculation per PT/1/A14450/017 CANDIDATE EXAMINER JPM 38 35 2009 NRC Page 1 019 of 9

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE Task Determine SLC actions and calculate Unit Vent flow manually per PT/1/A/44501017 PT/1/N4450/017 (Unit Vent Venl Flow Manual Calculation).

Calculation).

Alternate DYES DNa DNO ~N/A

[8J N/A Time Critical DYES [8J ~NO NO Path

~N/A Evaluation Location oD Simulator Din-Plant [8J Classroom

[8]

Safety Function _ __ _ [8J N/A Evaluation Validation 14 minutes

[8J

[8] Perform DSimulale DSimulate Method Time JPM Type ~ Bank

[8J o DNewNew oD Modified KIA 2.2.12 Knowledge of surveillance procedures. (CFR: 41.10 / 45.13) (3.7/4.1) 41.10/45.13)

Standard Determine SLC action D applies. Perform the Unit Vent Flow PT within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 0 applies.

restore OOS meiermeter to operable within wilhin 30 days.

days. Unit Vent flow is calculaled to be 117450 calculated 10 scfm +1 sclm +1-- 1000 scfm.

sclm.

References PT/1/N4450/017 (Unit Vent Flow Manual Calculation) Rev 012 PT/1/A/44501017 SLC 16.11-7 (Radioactive Gaseous Effluent Monitoring Instrumentation)

PT/1/N4600/002A (Mode 1 Periodic Surveillance Items) Rev 212 PT/1/A/46001002A Candidate Start Time End Time _ _ _ _ __ Duration

- -----

Performance Rating 0 Satisfactory D o Unsatisfactory D

Examiner (Printed Name) (Signature) (Date)

Comments JPM 3S 2009 NRC Page 2 of9 of 9

SIMULATOR SETUP UseSNAP _ _

Fail VFP 5310 to 0 Place 005DOS sticker on VFP 5310 (1A VF Flow)

SET VA FLOW TO 56000 READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions.

conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications 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:

Both Units are operating at 100% power.

No va release is in progress.

progress.

No GWRs are in progress.

The Waste Evaporator and Recycle Evaporator are secured secured..

All systems are in normal alignment.

INITIATING CUE:

The RO performing the Unit 1 Mode 1 Periodic Surveillance notified you that flow on OAC CAC point C1A1104 C1A1 104 was 94000 scfm during the Unit Vent Stack Flow Rate Meter Channel Check. Determine what actions (if any) are required to comply with SLCs and the method used to verify any required actions.

JPM 35 3S 2009 NRC Page 3 of 9

START TIME: _ __

~

LLJ Determines if any applicable SLCs exist. CRITICAL STEP STANDARD

__ SAT Operator determines directly or through reference to Daily Surveillance PT that - -

PT/11A144501017 (Unit Vent Flow applies. This requires PT/11A14450/017 SLC 16.11-7 action D applies.

__

- - UNSAT Manual Calculation) be performed every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the instrument retumed returned to operable within 30 days.

Student may also state that Action K applies (30 day report).

EXAMINER CUE OSM requests that you complete PT/11 A14450/017.

PT/11A144501017.

EXAMINER NOTE: Provide candidate with a copy 01 of PT/11A14450/017 provided.

PT/11A144501017 COMMENTS LJ fLJ Operator locates and records VA System flow.

Operator locates and records VA System flow. CRITICAL STEP STANDARD

_ _ SAT Operator locates 1 WAP5280 VAP5280 on 1MC-3 and records 56,000 scfm.

_ _ UNSAT EXAMINER NOTE: May provide a picture of the control board gauge instead of locating in the simulator.

EXAMINER NOTE: Range 01 of 55000 to 57000 scfm is acceptable.

COMMENTS p

...LJ Operator locates and records VE 1 1A A flow to stack.

STANDARD

_ _ SAT Locates 1VEP5180, nOlesnotes VE 1A is shutdown and records 0 scfm.

_ _ UNSAT EXAMINER NOTE: May provide a picture of the control board gauge instead of locating in the simulator.

COMMENTS JPM 3S 2009 NRC of 9 Page 4 019

~

Operator locates and records VE 1B flow to stack.

STANDARD

_ _ SAT Locates 1VEP5200, notes VE 1 18 B is shutdown and records 0 scfm.

_ _ UNSAT EXAMINER NOTE: May provide a picture of the control board gauge instead of locating in the simulator.

COMMENTS

...u

...LJ Operator locates and records VF 1 1AA flow to stack. CRITICAL STEP STANDARD

_ _ SAT Locates 1VFP5310, notes VF reading is OOS DOS and uses 33130 scfm from enclosure 13.2.

_ _ UNSAT EXAMINER NOTE: May provide a picture of the control board gauge instead of locating in the simulator.

COMMENTS

-.U

...LJ Operator locates and records VF 1B flow to stack.

STANDARD

_ _ SAT Locates 1VFP5340, notes VF 18 sefm.

1B is shutdown and records 0 scfm.

_ _ UNSAT EXAMINER NOTE: May provide a picture of the control board gauge instead of locating in the simulator.

COMMENTS JPM 3S 2009 NRC of 9 Page 5 019

...u LLJ 1ABU X~AFMD*1 flow reading locally.

Determines need to get 1ABUX-AFMD-1 CRITICAL STEP STANDARD

_ _ SAT NLO dispatched.

_ _ UNSAT EXAMINER CUE: 1ABUX-AFMD-1 reads 27000 selm. scfm.

COMMENTS

-.LJ f.URecords 1ABUX-AFMD-1 flow. flow. CRITICAL STEP STANDARD

_ _ SAT Records 27000 scfm based on examiner cue.

_ _ UNSAT COMMENTS uu f.U Operator records VP flows.

flows.

STANDARD

_ _ SAT Based on initial cues VP is secured. Flows recorded as 0 scfm or N/A.

_ _ UNSAT COMMENTS UQJ

~

Operator records WG flow and va flow.

STANDARD

_ _ SAT Based on initial cues records flow as 0 scfm or N/A

_ _ UNSAT COMMENTS JPM 3S 2009 NRC Page 6 of9 of 9

.JjJ fill Operator records TL flow CRITICAL STEP STANDARD SAT Based on initial cue and procedure notes records 1260 scfm.

UNSAT COMMENTS

~

.J1J Operator records NB and WL flows.

flows.

STANDARD Based on initial cues records flow as 0 scfm or N/A. SAT UNSAT COMMENTS

...ill

..ill Operator records ZJ flow to stack. CRITICAL STEP STANDARD SAT Based on initial cue and procedure notes records 60 scfm.

UNSAT COMMENTS JPM 3S 2009 NRC Page 7 of 9

U1J f-ill Calculate total vent flow.

flow. CRITICAL STEP STANDARD

_ _ SAT Calculates total vent flow to stack as 117450 scfm.

_ _ UNSAT

=

(56000)+(33130)+(27000)+(1260)+(60) = 117450 EXAMINER NOTE Due to reading instruments, 116450 *118450

-118450 scfm is considered acceptable.

COMMENTS

~

Complete PT and submit to WCCSRO.

STANDARD

_ _ SAT Records that acceptance criteria is met and signs off remaining procedure steps.

_ _ UNSAT EXAMINER NOTE Candidate may create a Discrepancy Sheet based on gauge VFP5310 having an ODS sticker on it. Although not required, it is not incorrect to submit one.

OOS one.

COMMENTS TIME STOP: _ _ ___

JPM 3S 2009 NRC Page 8 of 9

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

INITIAL CONDITIONS:

Both Units are operating at 100% power.

power.

va release is in progress.

No VO

No GWRs are in progress.

progress.

The Waste Evaporator and Recycle Evaporator are secured.

secured.

All systems are in normal alignment.

INITIATING CUE:

The RO performing the Unit 1 Mode 1 Periodic Surveillance notified you that flow on OAe OAC point C1A1104 was 94000 sclm scfm during the Unit Vent Stack Flow Rate Meter Channel Check. Determine what actions (if any) are required to comply with SLCs and the method used to verify any required actions.

Duke Power Company Procedure No.

Catawba Nuclear Station rTf PTI lllAl4450/017

/Al4450/017 Revision No.

012 Unit Vent Flow Manual Calculation Electronic Reference No.

No.

CN005G80 CNOOSG80 Continuous Use PERFORMANCE I

'"* ** *

'" '"* '"* *

'" *

'" ** *

'" '"* UNCONTROLLED FOR PRINT * '" *

'" *

- - *

'" '"* ***

(ISSUED) - PDF Format

PT/l!Al4450/017 PT/ l!Al4450/017 Page 2 of of44 Unit Vent Flow Manual Calculation

1. Purpose To provide a means to calculate the flow to the Unit Vent when the Unit Vent Stack Flow Rate Meter is inoperable or flow is less than 97,500 sefm.

scfm.

2. References 2.1 SLC 16.11-7 2.2 UFSAR Section 11.5.1.2.2.1 11.5.1.2.2. 1

3. Time Required 3.1 Manpower - One NLO 3.2 Time - 30 minutes 3.3 Frequency - Every four hours

4. Prerequisite Tests None

5. Test Equipment None

6. Limits and Precautions None

7. Required Unit Status None

8. Prerequisite System Conditions 8.1 The Unit Vent Stack Flow Rate Meter is inoperable or flow is less than 97,500 scfm.

8.2 The Unit Vent is in service.

PT/I/A/44501017 PTlliAl44501017 Page 3 of4

9. Test Method 9.1 The various systems exhaust flow to the Unit Vent will be obtained using local indication and recorded on Enclosure 13.1 (Total Unit Vent Flow Calculation Sheet).

9.2 The individual exhaust flows will be added to obtain total exhaust flow to the Unit Vent and recorded on Enclosure 13.1 (Total Unit Vent Flow Calculation Sheet).

10. Data Required Complete Enclosure 13.1 (Total Unit Vent Flow Calculation Sheet).

11. Acceptance Criteria The Unit Vent Stack Flow Rate is estimated at least once per four hours. (SLC 16.11-7)

12. Procedure 12.1 Complete Enclosure 13.1 (Total Unit Vent Flow Calculation Sheet) as follows:

12.1.1 Record the individual systems exhaust flows.

12.1.2 Calculate the total Unit Vent exhaust flow by adding together the individual systems exhaust flows.

12.1.3 Record the date and time the calculation was completed.

NOTE: Additional copies of Enclosure 13.1 (Total Unit Vent Flow Calculation Sheet) may be made as necessary and attached.

12.2 Repeat Step 12.1 every four hours until the Unit Vent Stack Flow Rate Meter is declared operable and flow is greater than or equal to 97,500 scfin.

scfm.

12.3 Ensure any additional copies of Enclosure 13.1 (Total Unit Vent Flow Calculation Sheet) used are attached.

PT/ ltN4450/0 17 PT/I/AJ44501017 Page 4 of4 12.4 Evaluate the acceptance criteria by perfonning performing one oftbe of the following:

12.4.1 Verify the acceptance criteria specified in Section 11I I is met.

OR 12.4.2 !f IF the acceptance criteria is NOT met, perfonn perform the following:

o UnitIWCC SRO that the acceptance criteria is NOT met.

Notify the Unit/WCC

________ I1_______

UnitIWCC SRO Contacted

--cc---

Date

--=-

Time

-

o Initiate a PIP to document the test failure.

o Docwnent all issues on a procedure discrepancy sheet.

Document 12.5 IF any discrepancy is noted during the perfonnance petfonnance of this test that does NOT keep the test from meeting the acceptance criteria, it shall be given to the UnitIWCC SRO for evaluation via a discrepancy sheet.

12.6 Submit PT/ IIN4450/017 (Unit Vent Flow Manual Calculation) to the Unit/WCC PT/lIAJ44501017 UnitIWCC SRO.

13. Enclosures 13.1 Total Unit Vent Flow Calculation Sheet 13.2 Systems Design Flow Rates

Enclosure 13.1 PT/ I /N44S0/017 PT/I/A/44501017 Total Unit Vent Flow Calculation Sheet Page 1I of 1I S¥S'fEM FWW'lNSTRUMEN:r tocAaION )illADWo,(CFM) iNlTlALS

~ t< "- . .

VA 1IVAPS280 ABFXU-I Air Flow VAP5280 ABFXU-l IMC3 VE I VEPSI80 VE lA IVEP5180 IA Flow To Stack IMC5 VE I VEPS200 VE IB Flow To Stack IVEP5200 IMC5 VF 1I VFP531 VFP53 10 0 VF Otlt Air Flow Tm A IMC5 VF 1IVFP5340 VF OUt Odt Air Flow Tm B IMC5 VA lABUXF Discharge Air Flow IELCPO III lELCPOl11

( IABUX-AFMD-I))

(IABUX-AFMD-l (1AB-ECP-l)

( IAB-ECP- I)

AB-594, HH-55 VP 1I VPP5200 VP Exhaust Air Flow lELCPOllO I ELCPO I 10

((1RB-CP-l)

I RB-CP-I)

AB-594, LL-52 AB-594 VP 1IVPP5180 VPPS 180 Incore lncore Instrument Room 1IELCPO ELCPO 1l 10 lO Exhaust Air Flow ((1RB-CP-l)

I RB-CP- I)

AB-594, LL-52 WG OWGPS941 WG Discharge OWGP5941 Discbarge Flow To AB-543, QQ-59 Unit Vent (On wall beside WG WGPanell VQ (1)

(I) N/A TL (2) N/A N/A NB (3) N/A WL (3) N/A ZJ (4) N/A TOTAL UNIT VENT FLOW (sum of ofall aU readings)

DATEI TIME COMPLETED

((1)

I) If a VQ release is in progress, use 350 CFM; otherwise, NI Ifa N/A.

A.

(2) If the TL System is in operation, use 1260 CFM; otherwise, N/A.

(3) If the Waste Evaporator or Recycle Evaporator Evaporator is operating, use 92 CFM; otherwise.

otherwise, N/A.

(4) the ZJ System is in operation, use 60 CFM; otherwise, N/A.

Ifthe If NOTE: If an instrument is out of service, enter the design flow at the exhaust line if exhausting to the Unit Vent, or enter '0'

'0' if ifisolated isolated from the Unit Vent. Design flows are listed on Enclosure 13.2 (Systems Design Flow Rates).

Enclosure Enclosure 13.2 13.2 PTil IA/445 010 17 PT/liAl4450/017 Systems Design Flow Rates Page 1 of 1I System Flow Rate VA Filtered Exhaust (two trains in service) din 60,000 cfin VA V A Filtered Exhaust (one train in service) cfm 30,000 cfin VE cfm 9000 cfin VF 33,130 cfm cfin VA Unfiltered Exhaust (two trains in service) 40,700 cfm 40,700cfin VA Unfiltered Exhaust (one train in service) cfm 20,350 cfin VP Containment Purge Exhaust cfm 25,000 cfin VP Incore Instrument Room Purge Exhaust 1000 cfm 1000cfin WG 20cfm 20cfin

on TRN A I TRNT,RN B I

VF OTLT AIR FLOW VF INL tNLT AIR FLOW

- 30 - 30

,

_:0

~i:!

33

./* - 20 20 0 **

~ _. tJ

~ fl "

i d~

10 "IR ,j 10

VF EXH FAN lA2 v.

VF VF TRAIN B SUP UNIT OF, X* TRN INTlK X-TRN 8VPA88 I

I

ABFXU-l AIR FLOW CAUTION INSTRUMENT INACURATE '

WIll READ INACURATE SIN6lE TRAIN DURING SINGLE OPERATION

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE JPM 5RADMIN Activate the Oil Spill Response Team CANDIDATE EXAMINER JPM 5R 2009 Page 1 of 7

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE Task Activate the Oil Spill Response Team Alternate DYES DNa [gJ N/A Time Critical DYES [gJ NO Path Evaluation Location

~ Simulator

[g] Din-Plant oD Classroom Safety Function _ _ [gJ N/A Evaluation Validation 11 minutes

~ Perform

[g] DSimulate Method Time JPM Type [gJ Bank DNew D Modified KIA GENERIC 2.4.11 (4.0/4.2) Knowledge of abnormal condition procedures.

Standard RP/O/B/50001008 (Spill Response) Enclosure 4.3 and Perform the immediate actions of RP/0/B/50001008 RP/O/B/50001008 (Spill Response) Enclosure activate the Oil Spill Response Team per RP/0/B/50001008 4.5 References RP/O/B/50001008 (Spill Response), revision 031 RP/0/B/50001008 Candidate Start Time End Time ------

Duration Performance Rating D 0 Satisfactory o Unsatisfactory D

Examiner (Printed Name) (Signature) (Date)

Comments JPM 5R 2009 Page 2 of 7

READ TO OPERATOR DIRECTION TO TRAINEE:

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

SIMULATOR SETUP CAUTION:

THIS KEYPAD IS CAPABLE OF ACTIVATING THE EMERGENCY BEEPERS AND IS USED FOR DRILLS. ENSURE QUIKTEL KEYPAD OUTPUT JACK IS UNPLUGGED PRIOR TO STARTING JPM.

INITIATING CUE:

You are the Unit 1 BOP. The Control Room Supervisor has just received a 4911 call stating there is an oil spill on the Standby Nuclear Service Water Pond. The Control Room SRO is performing the immediate actions of RP/0/B/50001008 (Spill Response).

The Control Room Supervisor directs you to perform all the immediate actions of Enclosure 4.3 of RP/0/B/50001008 (Spill Response).

JPM 5R 2009 Page 3 of 7

Start Time: _ __

L1-J

---.:LJ RP/O/B50001008 RP/0/B50001008 Enclosure 4.3, Step 1.1 Upon receiving notification of a spill of oil(petroleum products, synthetic oils, hydraulic oils, etc.) to Lake Wylie or the Standby Nuclear Service Water Pond which requires cleanup, request the caller's name and phone number:

Name: _ _ _ _ _ _ _ _ _ _ __

Name: Phone: _ _ _ _ __

STANDARD

_ _ SAT Candidate records the caller's name and phone number in the blanks in the first immediate action of Enclosure 4.3 UNSAT CUE: "This is Jim Barnes, my extension is 3038. This oil spill requires cleanup."

COMMENTS LU

-.U RP/O/B50001008 RP/0/B50001008 Enclosure 4.3, Step 1.2 Dispatch the Fire Brigade Leader to investigate and report status of the spill.

STANDARD SAT Contacts Fire Brigade leader to evaluate the spill.

UNSAT CUE: "The Fire Brigade Leader has been contacted and the spill has been confirmed."

COMMENTS

~ RP/O/B50001008 RP/0/B50001008 Enclosure 4.3, Step 1.3 CRITICAL STEP Activate the CNS HazMat Emergency Response Team pagers to obtain the assistance of the duty HazMat Team technician. Refer to Enclosure 4.5 to initiate a response.

STANDARD SAT Refers to Enclosure 4.5 to initiate the pagers.

_ _ UNSAT COMMENTS JPM 5R 2009 Page 4 of 7

L+/--J RP/O/B50001008 I-+/--J Enclosure 4.5, Step 1.1 CRITICAL STEP If the HazMat Emergency Response Team is being called out for a drill, go to Step 2.

_ _ SAT STANDARD

_ _ UNSAT Determines from the Initial Conditions that this is not a drill and an actual spill has occurred. Step 1.1 is N/A.

COMMENTS

~ RP/O/B50001008 Enclosure 4.3, Step 1.2 CRITICAL STEP Activate the off-site emergency pager system Quiktel Key Pad located in the ControlRoom.

1.2.1 Press the <EXIT> key to assure the key pad is cleared.

1.2.2 Type "SPILL" 1.2.3 Press <ENTER>

1.2.4 Press <M> key (for Message) 1.2.5 Type in the following message:

"Oil spill to water at CNS. HazMat members respond. Duty person call 803-701-5164."

1.2.6 Press <ENTER>

STANDARD _ _ SAT Candidate locates the Quiktel Key Pad and enters information and transmits.

UNSAT EXAMINER NOTE: The keypad will display an error condition since it is unplugged (to avoid an actual transmission).

CUE: "Message has been sent."

COMMENTS JPM 5R 2009 Page 5 of 7

~ RP/O/B50001008 RP/0/B50001008 Enclosure 4.3, Step 1.3 If the Quiktel Key Pad is unavailable, dial 9-999-777-8091 and enter your phone number (e.g., 803-701-5164), and press #. The HazMat Emergency Response Team duty person will return your call.

STANDARD SAT Determines this step is N/A.

_ _ UNSAT COMMENTS TIME STOP: _ __

JPM 5R 2009 Page 6 of 7

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

INITIATING CUE:

You are the Unit 1 BOP. The Control Room Supervisor has just received a 4911 call stating there is an oil spill on the Standby Nuclear Service Water Pond. The Control Room SRO is performing the immediate actions of RP/O/B/50001008 (Spill Response).

The Control Room Supervisor directs you to perform all the immediate actions of Enclosure 4.3 of RP/O/B/50001008 (Spill Response).

Enclosure 4.3 RP/O/B/SOOO/008 RP/O/B/50001008 Oil Spills to Navigable Waters (Lake Wylie Page 1 of2 OR SNSW Pond)

1. Immediate Actions 1.1 Upon receiving notification of a spill of oil (petroleum products, synthetic oils, hydraulic oils, etc.) to Lake Wylie or the Standby Nuclear Service Water Pond which requires clean-up, request the caller's name and phone number:

Name: _____________________________ Phone:

Name: ----------------------------- ------------------

1.2 Dispatch the Fire Brigade Leader to investigate and report status of the spill.

NOTE: CNS HazMat Emergency Response Team will call the Control Room upon arrival on site.

1.3 Activate the CNS HazMat Emergency Response Team pagers to obtain the assistance of the duty HazMat Team technician. Refer to Enclosure 4.5 to initiate a response.

2. Subsequent Actions 2.1 Contact EHS at extension 3333 for assistance in reporting to state, local, or federal authorities. After hours, contact the EHS Duty person by phone or pager. IF no answer, use the EHS group page 777-3333, which will page all EHS personnel.

2.2 IF an emergency has NOT been declared, perform the following:

2.2.1 Notify York County Emergency Management about the event through the York County Telecommunicator (selective signal phone number 513) and, as necessary, request additional support from the county. {PIP # C-OO-1689}

NOTE: 1. A request for emergency response support (except an ambulance) from an off-site agency requires a 4-hour notification of the NRC as an "Off-site Notification" per RP/O/B/5000/013 (NRC Notification Requirements).

RP/O/B/50001013

2. A request for ambulance support for a "contaminated injury" is an 8-hour notification and the request for transport of a "clean injury" does not require a NRC notification.

2.2.2 IF the assistance of the York County HazMat Technicians is requested AND they respond, notify the NRC under the 4-hour notification requirement for off-site notifications.

Enclosure 4.3 RP/O/B/50001008 RP/O/BISOOOI008 Oil Spills to Navigable Waters (Lake Wylie Page 2 of2 OR SNSW Pond) 2.2.3 IF the NRC will NOT be notified of this event per RP/O/B/SOOOI013, perfonn the following:

A. Notify the duty Emergency Planner.

B. Notify the Public Affairs duty person.

C. Make a courtesy notification to states and counties per Enclosure 4.6.

2.3 In the event that a responsible group is not identified, the Operations Shift Manager (or designee) shall initiate a PIP. Refer to Environmental Work Practice S.l5.1 for infonnation to include in the PIP.

2.4 WHEN this procedure has been completed, perfonn the following actions:

2.4.1 Send a copy of the completed procedure to Emergency Planning (CN01EP).

(CNOIEP).

2.4.2 Send the completed procedure to Document Management.

Enclosure 4.5 10IB/5 000100 8 RP/O/B/50001008 RP HazMat Emergency Response Team Page 1 of2 Activation for Oil Spills NOTES: 1. The HazMat Emergency Response Team will call the Control Room to determine any personnel or radiological safety hazards associated with their response to the site.

2. The HazMat Emergency Response Team will respond to warehouse #9 unless the Control Room advises them otherwise.

3. Pager activation can be delayed up to 5 minutes depending on pager system status.

1. HazMat Emergency Response Team Notification for an Actual Oil Spill 1.1 IF the HazMat Emergency Response Team is being called out for a drill, go to Step 2.

1.2 Activate the off-site emergency pager system Quiktel Key Pad located in the Control Room.

1.2.1 Press the <EXIT> key to assure the key pad is cleared.

1.2.2 Type "SPILL" 1.2.3 Press <ENTER>

1.2.4 Press <M> key (for Message) 1.2.5 Type in the following message:

"Oil spill to water at eNS. HazMat members respond. Duty person call 803-701-5164."

1.2.6 Press <ENTER>

1.2.7 Monitor the confirmation pagers located at the Quiktel Key Pad to verify proper pager activation.

1.3 IF the Quiktel Key Pad is unavailable, dial 9-999-777-8091 and enter your phone number (e.g., 803-701-5164), and press #. The HazMat Emergency Response Team duty person will return your call.

Enclosure 4.5 RP/O/B/SOOOI008 HazMat Emergency Response Team Page 2 of2 Activation for Oil Spills

2. HazMat Emergency Response Team Notification for a Drill 2.1 Activate the off-site emergency pager system Quiktel Key Pad located in the Simulator.

2.1.1 Press the <EXIT> key to assure the key pad is cleared.

2.1.2 Type "SPILL" 2.1.3 Press <ENTER>

2.1.4 Press <M> key (for Message) 2.1.5 Type the following message:

"This is a Drill. Oil spill to water at eNS. HazMat members respond.

Duty person call 803-701-5164. This is a Drill."

2.1.6 Press <ENTER>

2.2 IF the Quiktel Key Pad is unavailable, dial 9-999-777-8091 and enter your phone number (e.g., 803-701-5164), and press #. The HazMat Emergency Response Team duty person will return your call.

I I

I

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE 4S ADMIN JPM 4SADMIN Determine Reporting per RP/O/B/5000/013 (NRC Notification Requirements)

CANDIDATE EXAMINER JPM 48 4S 2009 Page 1 of 5

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE Task Determine Reporting per RP/0/B/50001013 RP/O/S/SOOOI013 (NRC Notification Requirements)

Alternate Path DYES DNO lSI N/A Time Critical DYES lSI NO Evaluation D Simulator Din-Plant [2J

[SJ Classroom Safety Function ____ lSI N/A Location Evaluation Validation 10 minutes

[2J

[SJ Perform DSimulate Method Time JPM Type D D Bank Sank lSI New D Modified D

KIA GENERIC 2.3.14 (3.4/3.8) Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Standard Detemines that 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months notifications are required per parts OCFRSO. 72(b )(2)(xi) and 10CFR50.

10CFR50. OCFRSO. 72(b )(3)(xii) respectively.

References RP/O/S/SOOOI013 RP/0/B/50001013 (NRC Notification Requirements) rev 030 Candidate Start Time End Time ------

Duration Performance Rating D Satisfactory D Unsatisfactory Examiner (Printed Name) (Signature) (Date)

Comments JPM 4S 2009 Page 2 of S 5

Start Time:. _ _ _ -_-

--.:LJ

---.:LJ RP/O/B/50001013 Step 2.1 Determine the appropriate NRC notifications from the following sources: CRITICAL STEP

Enclosure 4.1, "Events Requiring Immediate NRC Notification"

Enclosure 4.2, "Events Requiring 1-Hour NRC Notification"

Enclosure 4.3, "Events Requiring 4-Hour NRC Notification"

Enclosure 4.4, "Events Requiring 8-Hour NRC Notification"

Enclosure 4.5, "Events Requiring 24-Hour NRC Notification"

Enclosure 4.6, "Events Requiring 30 Day NRC Notification"

Enclosure 4.7, "Events Requiring 60 Day NRC Notification"

Enclosure 4.8, "List of System (ESF) Actuations for Catawba"

NSD 201, "Reporting Requirements"

NSD 202, "Reportability" STANDARD

_ _ SAT Per the standard, the following notifications are required:

UN8AT

_ _ UNSAT 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification 10CFR50.72{b)(2)(xi) 10CFRSO.72(b)(2)(xi) Offsite Notification (News Release)

Any event or situation related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an on-site fatality, transport of an injured or ill employee to a hospital by ambulance, or an inadvertent release of radioactively contaminated materials.

8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months notification 10CFRSO.72(b)(3)(xii) Offsite Medical (Contaminated Injury) 10CFR50.72{b)(3)(xii)

Any event requiring the transport of a radioactively contaminated person to an off-site medical facility for treatment.

COMMENTS TIME STOP: _ __

JPM 4S 48 2009 Page 4 of 5

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

INITIATING CUE:

A vendor performing a S/G bowl entry during No Mode was overcome with heat exhaustion and fell.

The fall caused a compound fracture on his right leg that pierced his bubble suit. Due to congested conditions and other delays in lifesaving activities, the injured individual received an estimated exposure of 16 Rem. When the individual was removed from containment, he was immediately transported to Piedmont Medical Center. A news van is parked at the access road and site personnel are preparing a press release for immediate delivery to the media.

Determine all applicable NRC notifications of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or less per RP/O/B/50001013 RP/O/S/50001013 (NRC Reporting Requirements).

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIATING CUE:

A vendor performing a 8/G S/G bowl entry during No Mode was overcome with heat exhaustion and fell.

The fall caused a compound fracture on his right leg that pierced his bubble suit. Due to congested conditions and other delays in lifesaving activities, the injured individual received an estimated exposure of 16 Rem. When the individual was removed from containment, he was immediately transported to Piedmont Medical Center. A news van is parked at the access road and site personnel are preparing a press release for immediate delivery to the media.

Determine all applicable NRC notifications of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or less per RP/0/B/5000/013 RP/O/S/SOOOI013 (NRC Reporting Requirements ).

48 2009 JPM 4S Page 3 of 5 S

Duke Energy Procedure No.

Catawba Nuclear Station RP/O/B/SOOO/013 NRC NOTIFICATION REQUIREMENTS Revision No.

030 Electronic Reference No.

CN005GOS CNOOSGOS Reference Use PERFORMANCE I

- - - - UNCONTROLLEDFORPRmT**********

(ISSUED) - PDF Format

RP/O/B/50001013 RP/O/B/SOOOI013 Page 2 of6

1. Symptoms NOTE: Unless otherwise noted, the terms Tech Spec or Technical Specifications refer to both Unit 1 and Unit 2 Technical Specifications.

1.1 Plant conditions requiring Immediate, I-hour, 4-hour, 8-hour, 24-hour, 30 day OR 60 day NRC notification in accordance with the following:

1.1.1 10CFR20.1906 10CFR20.1906 1.1.2 10CFR20'.2202 1.1.3 10CFR26.73 10CFR26.73 1.1.4 10CFRS0.36 10CFR50.36 1.1.S 1.1.5 10CFRSO.72 10CFR50.72 1.1.6 10CFRSO.73 10CFR50.73 1.1.7 10CFR70.S2 10CFR70.52 1.1.8 10CFR72.7S 10CFR72.75 1.1.9 10CFR73.71 10CFR73.71 1.1.10 Declaration of any emergency classification 1.1.11 Security or Safeguards Event 1.2 All non-emergency notifications to the NRC (1.1.1 through 1.1.9 and 1.1.11) where no other notification is required shall be made to the state and county emergency preparedness management agencies as courtesy notifications. Community Relations shall be notified of all "courtesy" notifications to the states and counties. {PIP O-COO-01689}

2. Immediate Actions 2.1 Determine the appropriate NRC notification from the following sources:

Enclosure 4.1, "Events Requiring Immediate NRC Notification"

Enclosure 4.2, "Events Requiring I-Hour NRC Notification"

Enclosure 4.3, "Events Requiring 4-Hour NRC Notification"

Enclosure 4.4, "Events Requiring 8-Hour NRC Notification"

Enclosure 4.S, 4.5, "Events Requiring 24-Hour NRC Notification"

Enclosure 4.6, "Events Requiring 30 Day NRC Notification"

Enclosure 4.7, "Events Requiring 60 Day NRC Notification"

Enclosure 4.8, "List of System (ESF) Actuations for Catawba"

NSD 201, "Reporting Requirements"

NSD 202, "Reportability"

RP/O/B/500010 13 RP/O/B/5000/013 Page 3 of6 2.2 Select one of the following enclosures based on the circumstances of the event:

Enclosure 4.10, "Safeguards ENS Event Report"

Enclosure 4.11, "Event Notification Report"

Enclosure 4.13, "Fitness for Duty Event Notification Report" 2.3 IF the Event Notification Report is being prepared for an "Immediate" or a "I-Hour" NRC notification, perform the following:

2.3.1 Complete the form based on available technical information 2.3.2 "MEDWPRESS RELEASE" block as "WILL BE."

Mark the "MEDIAIPRESS 2.3.3 Mark the other "NOTIFICATION" blocks based on the personnel/agency notified or intentions to notify.

NOTE: 1. A request for emergency response support (except an ambulance from an off-site agency) requires a 4-hour notification of the NRC as an "Off-site Notification."

2. A request for ambulance support for a "contaminated injury" is an 8-hour notification and the request for transport of a "clean injury" does not require a NRC notification.

2.4 IF a "4-Hour," "8-Hour," or "24-Hour" NRC notification maybe may be required, perform the following:

NOTE: The Controller bridge line (803-831-4011 or extension 4011) can be used in non-emergency situations to conduct a conference call. Up to 6 callers from offsite onsite and off site can be connected simultaneously.

2.4.1 Notify the following individuals to participate in a discussion and decision to notify the NRC, the media, and the states and counties:

Duty Regulatory Compliance Representative (see current station duty list)

Duty Community Relations person (see current station duty list)

Duty Station Manager (see current station duty list)

Duty Emergency Planner (see current duty list)

RP/O/B/5000/013 Page 4 of6

Duty Safety/Environmental Management professional (see current duty list) for the following events:

o On-site Fatality (a 4-hour notification may be required if OSHA is notified) o Transport of an injured or ill employee to the hospital by ambulance 2.4.2 Complete the Event Notification Report based on the decision reached during the conference call.

2.5 IF a "60 day" NRC notification is to be made per 10 CFR 50.73(a)(I),

50.73(a)(1), Regulatory Compliance will prepare the notification form and obtain the appropriate management review. Operations or Regulatory Compliance may make this notification.

2.6 IF the event involves a Fitness for Duty Event Report, the General Office Fitness for Duty Program Administrator should provide the information necessary to complete Enclosure 4.13. This information will be transmitted to the Regulatory Compliance duty person.

2.7 The Regulatory Compliance duty person will complete Enclosure 4.13 and notify Operations after completion. Operations or Regulatory Compliance may make this notification.

__

- _ 2.8 Notify the NRC Operations Center by one of the following means:

Primary: Emergency Notification System (ENS) Phone 1-301-816-5100

Alternate: Commercial Telephones:

o 1-800-532-3469 o 1-301-951-0550 o 1-301-415-0550 o 1-301-415-0553

3. Facsimile:

o 1-301-816-5151 o 1-800-449-3694 2.9 IF requested by the NRC Operations Center, maintain continuous communications with them.

RP/O/B/SOOOlO13 RP/O/B/SOOOI013 Page 5 of6

3. Subsequent Actions NOTE: Person to person contact is required in the following step to ensure newsworthy infonnation is consistently known and understood.

3.1 Ensure the following individuals are notified:

Duty Regulatory Compliance Representative (see current station duty list)

Duty NRC Resident Inspector (see current station duty list)

Duty Station Manager (see current station duty list)

Duty Emergency Planner (see current duty list)

Duty Safety/Environmental Management Professional (see current duty list) for the following events:

o On-Site Fatality (a 4-hour notification may be required if OSHA is notified) o Transport of an injured or ill employee to the hospital by ambulance 3.2 IF an ENS Notification requires retraction, follow the guidance in Enclosure 4.12, ENS Notification Retraction.

NOTE: Notification of state and county emergency preparedness management agencies using the following step is a "courtesy" notification.

3.3 IF the NRC is being notified of a plant condition AND an emergency has NOT been declared, notify the state and county emergency preparedness management agencies and Community Relations by referring to Enclosure 4.9. {PIP O-COO-OI689}

0-COO-01689}

- - 3.4 Place a copy of the notification fonn that was faxed to the NRC Operations Center in the Resident NRC Inspector's mailbox in the WCC:

Enclosure 4.10, Safeguards ENS Event Report Enclosure 4.11, Event Notification Report Enclosure 4.13, Fitness for Duty Event Notification 3.5 Forward a copy of the completed procedure to the Emergency Planning Group.

3.6 Forward the original signed completed procedure to Document Management.

RP/0 /B/5000/0 13 Page 60f6

4. Enclosures 4.1 Events Requiring Immediate NRC Notification 4.2 Events Requiring I-Hour NRC Notification 4.3 Events Requiring 4-Hour NRC Notification 4.4 Events Requiring 8-Hour NRC Notification 4.5 Events Requiring 24-Hour NRC Notification 4.6 Events Requiring 30 Day NRC Notification 4.7 Events Requiring 60 Day NRC Notification 4.8 List of System (ESF) Actuations for Catawba 4.9 Courtesy Notification to States and Counties of Non-emergency Plant Conditions 4.10 Safeguards ENS Event Report 4.11 Event Notification 4.12 ENS Notification Retraction 4.13 Fitness for Duty Event Notification Report

Enclosure 4.1 RP/O/B/50001013 RP/O/B/5000/013 Events Requiring IMMEDIATE NRC Notification Page 110f2 of2 Complete the reportmg reporting requirements ree mrements for the following followmgevents events as soon as practical after the occurrence becomes known to the licensee:

10CFR Section Descril2!io~

Event Description Reporting Requirement 1lOCFR20.1906 OCFR20 .1906 I Events involving receiving and opening packages when removable I Notify the final delivery carrier.

radioactive surface contamination of the package (as determined by Transportation events Radiation Protection) exceeds the limits of 10CFR71.87(i) or when Notify the Region II Administrator at 404-involving receiving external radiation levels (as determined by Radiation Protection) 562-4400. An Emergency Notification and opening packages exceed the limits of 10CFR71.47 System (ENS) phone call does not need to be made unless specified by Region II.

There is not an enclosure for reporting to Region II pursuant!()

pursuant to 10CFR20.1906(dl-10CFR20.1906(d}.

10CFR20.2201a(i) 10CFR20.220 la(i) Events involving any lost, stolen, or missing licensed material in an Notify the NRC Operations Center aggregate quantity equal to or greater than 1,000 times the quantity Material/Exposure specified in Appendix C to 10CFR20.1001 - 20.2401 (as determined events involving theft by Radiation Protection) under such circumstances that it appears or loss of stolen that an exposure could result to persons in unrestricted areas.

licensed material 110CFR20.2202 OCFR20 .2202 Any event involving byproduct, source, or special nuclear material Notify the NRC Operations Center that may have caused or threatens to cause an individual to receive Material/Exposure any of the following:

events involving radiological exposure

A total effective dose equivalent of 25 rems or more

An eye dose equivalent of75 of 75 rems or more

A shallow-dose equivalent to the skin or extremities of 250 rads or more

May have caused or threatens to cause the release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the individual could have received an intake five times the occupational annual limit on intake (does not apply to locations where personnel are not normally stationed duringroutine during routine operations).

Enclosure 4.1 RP/O/B/50001013 RP/O/B/5000/0 13 Events Requiring IMMEDIATE NRC Notification Page 2 of2 Complete the reporting re( Ulrements for the following requirements followmg events as soon as practical after the occurrence becomes known to the licensee IOCFR Section IOCFR50.72 10CFR50.n 10CFRn.75 (a) ISFSI 10CFR72.75 I. Event Description

Declared emergency classification as specified in RP/O/A/50001001, RP/O/A/5000/001, "Classification of Emergency."

I Reporting Requirement RepQrting Notify the NRC Operations Center immediately after notification of the appropriate state or local agencies and not later than 1I hour after the time Emergency

Change from one emergency classification to another one of the emergency classes is declared.

Classification Notifications

Termination of an emergency classification Activate the Emergency Response Data System (ERDS) as soon as possible but not later than

Any further degradation in the level of safety of the plant or one hour after declaring an Alert or higher other worsening plant conditions, including those that emergency classification.

require the declaration of any of the emergency classes, if such a declaration has not been previously made Refer to Enclosure 4.3 (4-hour notification) TS Deviation

The results of ensuing evaluations or assessments of plant conditions

The effectiveness of response or protective measures taken.

Information related to plant behavior that is not understood

As a courtesy in situations deemed necessary.

10CFR73.71 Events involving physical protection of plant and materials Notify the NRC Operations Center.

Physical protection of ** The loss of any shipment of special nuclear material or spent Notify the NRC Operations Center of significant plant and materials fuel (also notify the NRC Operations Center within 1I hour supplemental information, which becomes after recovery of or accounting for such lost shipment) available.

Safeguards events as determined by Security personnel

Enclosure 4.2 RP/O/B/500010 RP/O/B/50001013 13 Events Requiring I-HOUR NRC Notification Page 10f2 Complete the reporting requirements for the following events as soon as practical and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the occurrence becomes known to the licensee:

10CFR Section 10CFR Event Description Reporting Requirement I 10CFR50. n(b)(2)(i)

Reasonable action that departs from a license condition or a technical Notify the NRC Operations Center I specification may be taken in an emergency when this action is immediately TS Deviation needed to protect the health and safety of the public and no action consistent (IOCFR50.54(x)

(IOCFRSO.54(x) with the license condition or technical specification that can provide Declarations) adequate or equivalent protection is immediately apparent.

Deviation from the intent of an emergency procedure constitutes a 10CFR50.54(x) action.

Actions taken per 10CFR50.54(x) shall be approved, as a minimum, by a Licensed Senior Reactor Operator prior to taking such action.

10CFR50.54(x) decisions shall be documented in the Reactor Operators 10CFR50.54(x)

Logbook and the TSC Logbook.

If not reported as a declaration of an emergency classification, the NRC shall be notified as soon as practical but always within one hour of the occurrence of a 10CFR50.54(x) action.

{PIP 2-C96-0273}

Enclosure 4.2 RP/O/B/5000/013 I-HOUR NRC Notification Events Requiring 1-HOUR Page 2 of2 Complete the reporting requirements for the following events as soon as practical and in all cases within 1I hour after the occurrence becomes known to the licensee:

10CFR IOCFR Section Event Description Reporting Requirement 10CFR70.52 IOCFR70.52 Events involving accidental criticality or loss or theft or attempted theft of Notify the NRC Operations Center special nuclear material Accidental criticality or loss or theft or

Any case of accidental criticality or any loss, other than normal operating attempted theft of loss, of special nuclear material special nuclear material

Any loss or theft or unlawful diversion of special nuclear material or any incident in which an attempt has been made or is believed to have been made to commit a theft or unlawful diversion of such material

Enclosure 4.3 RP/O/B/50001013 Events Requiring 4-HOUR NRC Notification Page 1I of3 on Complete the reporting requirements for the following events as soon as practical and in all cases within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the occurrence becomes known to the licensee:

10CFR Section Event Description Reporting Requirement Repo1"ting 1IOCFR50.72(b)(2)(i)

OCFR50. 72(b )(2)(i)

Initiation of a shutdown is defined as: "A reduction in power required Notify the NRC Operations Center by an Action statement of Technical Specifications to enter Mode 3."

Initiation of any plant shutdown required by

I. Shutdown is defined (for reporting requirements) as: "Mode 3 and Technical Specifications below from Mode 1I or Mode 2."

Cooldown to comply with an Action statement of Technical Specifications does not constitute "Shutdown initiation of any plant shutdown." reporting requirements.

Example: If the unit is already shut down and a cooldown is required to comply with a Technical Specification ACTION statement, no further reporting requirements apply because of the cooldown S/G Tube Integrity Notify the NRC of Steam Generator Tube Plugging in accordance with Notify the NRC Operations Center Technical Specification Technical Specifications 5.5.9, Table 5.5.2.

Enclosure 4.3 RP/O/BISOOOI013 RP/O/B/50001013 Events Requiring 4-HOUR NRC Notification Page 2 of3 Complete the reporting requirements for the following events as soon as practical and in all cases within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the occurrence becomes known to the licensee:

10CFR Section Event Description Reporting Requirement 10CFRSO. n(b)(2)(iv)(A)

OCFR50. 72(b Any event that results or should have resulted in ECCS discharge into the Notify the NRC Operations Center reactor coolant system as a result of a valid signal except when the ECCS discharge into actuation results from and is part of a pre-planned sequence during testing the Reactor Coolant or reactor operation.

System

Valid signal refers to those signals automatically initiated by measurement of an actual physical system parameter that was within the established setpoint band of the sensor that provides the signal to the protection system logic, or manually initiated in response to plant conditions. Valid signals also include passive system actuations that occur as a function of system conditions like differential pressure (i.e.,

cold leg accumulators) whereby no SSPS or other electrical signal is involved. The validity of an ECCS signal may not be determined within 1I hour; ECCS signals that result or should have resulted in injections should be considered valid until firm evidence proves otherwise.

Invalid ECCS injections are still considered a System actuation, but are NOT reportable to the NRC per 10 CFR sO.n.50.72. It is still reportable under 10 CFR SO.73 50.73 as an LER. (Refer to Enclosure 4.8 for guidance as to what constitutes a System actuation.)

110CFRSO. n(b )(2)(iv)(B)

OCFR50. 72(b Any event or condition that results in actuation of the reactor protection Notify the NRC Operations Center system (RPS) when the reactor is critical except when the actuation is part RPS Actuation of a pre-planned sequence during testing or reactor operation.

10CFRSO.n(b 10CFR50. 72(b )(2)(xi) Any event or situation related to the health and safety of the public or on- Notify the NRC Operations Center 10CFRn.7S(b)(2) ISFSI 10CFR72.75(b)(2) site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be Offsite Notification made. Such an event may include an on-site fatality, transport of an injured (News Release) or ill employee to a hospital by ambulance, or an inadvertent release of radioactively contaminated materials. i

Enclosure 4.3 RP/O/B/50001013 Events Requiring 4-HOUR NRC Notification Page 3 of3 10CFR Section 10CFR Event Description Reporting Requirement 10CFR72.75(b)(1) For the ISFSI, an action taken in an emergency that departs from a Notify the NRC Operations Center condition or a technical specification contained in a license or certificate of ISFSI compliance issued under this part when the action is immediately needed to TS Deviation protect the public health and safety, and no action consistent with license or certificate of compliance conditions or technical specifications that can provide adequate or equivalent protection is immediately apparent. ---~----- ---

Enclosure 4.4 RP/O/B/SOOOI013 Events Requiring 8-HOUR NRC Notification Page 110f2 of2 Complete the reporting requirements for the following events as soon as practical and in all cases within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the occurrence becomes known to the licensee:

10CFR Section Event Description Reporting Requirement OCFRSO. n(b )(3 1lOCFRSO.72(b )(ii)

)(3)(ii) Any event or condition that results in: Notify the NRC Operations Center A. the condition of the plant, including its principal safety barriers, being Degraded Condition seriously degraded or B. The Nuclear Power plant being in an unanalyzed condition that significantly degrades plant safety.

1lOCFRSO.n(b)(3)(iv)(A)

OCFRSO. 72(b)(3)(iv)(A) Any event of condition that results in valid actuation of any of the systems Notify the NRC Operations Center listed in Enclosure 4.8 of this procedure, except when the actuation results System Actuation from and is part of a pre-planned sequence during testing or plant o~eration.

operation.

OCFRSO. n(b)(3)(v) 1lOCFRSO.72(b )(3)(v) Any event or condition that at the time of discovery could have prevented Notify the NRC Operations Center the fulfillment of the safety function of structures or systems needed to:

Safety Function Prevented From A. shut down the reactor and maintain it in a safe shutdown condition, Functioning B. remove residual heat, C. control the release of radioactive material, or D. mitigate the consequences of an accident 10CFRn.7S(c)(1) 10CFR72.7S(c)(1) Discovery of a defect in an ISFSI structure, system or component that is Notify the NRC Operations Center important to safety.

ISFSI Defects 10CFRn.7S(c)(2) 10CFR72.7S(c)(2) A significant reduction in the effectiveness of the ISFSI confinement Notify the NRC Operations Center system.

ISFSI Degraded Confinement System

Enclosure 4.4 RP/O/B/50001013 RP/O/B/5000/0 13 Events Requiring 8-HOUR NRC Notification Page 2 of2 Complete the reporting requirements for the following events as soon as practical and in all cases within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the occurrence becomes known to the licensee:

10CFR Section Event Description Reporting Requirement 10CFR50.72(b )(3)(xii) 10CFRSO.72(b)(3)(xii) Any event requiring the transport of a radioactively contaminated person Notify the NRC Operations Center 10CFR72.75(c)(3) ISFSI to an off-site medical facility for treatment Offsite Medical (Contaminated Injury) 10CFR50. 72(b)(3)(xiii) 10CFR50.72(b Any event that results in a major loss of emergency assessment capability Notify the NRC Operations Center or communications capability (e.g., significant portion of control room Major loss of indication, Emergency Notification System (ENS), Health Physics emergency assessment Network (HPN), unavailability ofTSC or off-site notification system capability or (i.e., loss of22 (25%) or more of the plant's Emergency Planning Zone communications sirens for more than one hour) capability or sirens

Should either or both of the emergency communications subsystems (ENS and HPN fail, the NRC Operations Center should be so informed over normal commercial telephone lines. When notifying the NRC Operations Center, licensees should use the backup commercial telephone numbers provided.

If the NRC 012erations Center notifies the licensee that an ENS or HPN line is inoperable, a report is not required. The Operations Center contacts th~ap~riate the appropriate repair organization.

Enclosure 4.5 RP/O/B/500010 RP/O/B/5000/o13 13 Events Requiring 24-HOUR NRC Notification Page 1 of3 Complete the reporting requirements for the following events as soon as practical and in all cases within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the occurrence becomes known to the licensee:

10CFR Section Event Description Reporting Requirement 10CFR20.2202 10CFR20.2202 of licensed material that may have Any event involving loss of control oflicensed Notify the NRC Operations Center caused, or threatens to cause an individual to receive, in a period of 24 Radiological Exposure hours

A total effective dose equivalent exceeding 5 rems, or

An eye dose equivalent exceeding 15 rems, or

A shallow-dose equivalent to the skin or extremities exceeding 50 rems Or that may have caused, or threatens to cause the release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the individual could have received an intake in excess of one occupational annual limit on intake (does not apply to locations where personnel are not normally stationed during routine operations)..

operations)

Enclosure 4.5 RP/O/B/SOOOI013 RP/O/B/500010 13 Events Requiring 24-HOUR NRC Notification Page 2 of3 Complete the reporting requirements for the following events as soon as practical and in all cases within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the occurrence becomes known to the licensee:

10CFR26.73 Significant Fitness For Duty events including: Notify the NRC Operations Center Fitness For Duty

Sale, use, or possession of illegal drugs within the protected area and

Any acts by any person licensed under 1lOCFR55 OCFR5 5 to operate a power reactor or by any supervisory personnel assigned to perform duties within the scope of this Part

Involving the sale, use, or possession of a controlled substance,

Resulting in confirmed positive tests on such persons,

Involving use of alcohol within the protected area, or

Resulting in a determination of unfitness for scheduled work due

. to the consumption of alcohol

Enclosure 4.5 RP/O/B/50001013 Events Requiring 24-HOUR NRC Notification Page 3 of3 Page30f3 Complete the reporting requirements for the following events as soon as practical and in all cases within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the occurrence becomes known to the licensee:

Operating License Operating license condition deviations requiring a 24-hour report Notify the NRC Operations Center Condition Deviations

Catawba must implement and maintain in effect all provisions of the approved fire protection program as described in the UFSAR and the SLCs. Violations of this program are potentially reportable as a 24-hour notification. Regulatory Compliance should always be notified concerning potentially reportable fire protection events.

Duke Energy, Catawba Nuclear Site, is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% power) in accordance with the conditions specified in the License. Exceeding actual 100% power level is potentially a 24-hour notification as required by the Facility Operating License. Regulatory Compliance should be consulted to help determine the reportability when power level exceeds 100%.

1I OCFR72. 75(d)(l)(i),(ii)

OCFR72. For the ISFSI, any event in which important equipment is disabled or Notify the NRC Operations Center fails to function as designed. Specifically, that equipment required by ISFSI Safety Function regulation, license condition or certificate of compliance to be Availability and available and operable:

Operability

to prevent releases that could exceed regulatory limits

to prevent exposures to radiation or radioactive materials that could exceed regulatory limits, or

to mitigate the consequences of an accident, and for which no redundant equipment was available and operable to perform the safety function.

safe_ty

Enclosure 4.6 RP/O/B/50001013 RP/O/B/SOOOIO 13 Events Requiring 30-DAY NRC Notification Page 1 of 1 Complete the reporting requirements for the following events as soon as practical and in all cases within 30 days after the occurrence becomes known to the licensee:

10CFR Section Event Description Reporting Requirement 10CFR20.220 OCFR20 .22011 Alllicensed All licensed material in a quantity greater than ten times the quantity Notify the NRC Operations Center via specified in Appendix C to 1lOCFR20.1001 OCFR20.1 00 1 - 20.2401 (as determined by the Emergency Notification System Theft, Loss or Missing Radiation Protection) that is still missing at this time Licensed Material

Enclosure 4.7 RP/O/B/SOOOIO RP/O/B/SOOOI01313 Events Requiring 60 DAY NRC REPORT Page 1I of 1I Complete the reporting requirements for the following events as soon as practical and in all cases within 60 days after the occurrence becomes known to the licensee:

10CFR Section 10CFR Event Description Reporting Requirement Licensee Event Report Any event which requires the preparation of a Licensee Event Report Notify the Duty Regulatory (LER) (the event mayor may not be reportable under 10CFRSO.72).

10CFRSO.72). Compliance Engineer The Shift Work Manager shall ensure a Problem Investigation Process (PIP) report for a more significant event (MSE) is generated and forwarded to the Safety Review Group to accurately reflect the condition.

LER submitted to NRC.

10CFRSO.73(a)(1)

IOCFRSO.73(a)(1) An invalid actuation of any of the systems listed in Enclosure 4.8 The licensee may, at its option, provide reported under 10CFRSO.73(a)(2)(iv),

10CFRSO.73(a)(2)(iv), other than actuation of the reactor a telephone notification to the NRC protection system (RPS) when the reactor is critical. Operations Center within 60 days after discovery of the event instead of submitting a written LER.

Enclosure 4.8 RP/O/B/SOOOI013 RP/O/B/500010 13 List of System (ESF) Actuations for Catawba Page 1 of2

1. Any reactor trip (P-4)

2. Safety injection (UFSAR 6.3.1,6.3.2)

A. NV charging path B. NI charging path C. ND charging path D. CLA injection E. DIG sequencer activation F. Reactor trip signal G. FWST - containment sump ND suction swap

If a second NV pump is manually started in order to maintain NC inventory, this is also a system actuation.

3. Containment spray (UFSAR 6.2.2)

A. NS pump start/valve alignment B. Actual spraydown of containment

4. Containment isolation (UFSAR 6.2.4)

A. Phase A (St)

B. Phase B (Sp)

C. Closure of the VP or VQ valves upon receipt of ofaa high radiation signal from EMF-38, 39, or 40 does not constitute a reportable system actuation during any mode.

D. NW system injection

5. Steam line isolation (UFSAR 10.3.2)

A. Individual steam line valve closure*

B. System isolation C. Actuation ofofP-12 P-12 to close steam dumps is NOT a system actuation

Individual component activation due to component failure not reportable per this requirement

Enclosure 4.8 RP/O/B/50001013 List of System (ESF) Actuations for Catawba Page 2 of2

6. Auxiliary feedwater system A. Auxiliary feedwater pump start, automatic or manual, unless the start was the expected result of a controlled (documented) test or procedure.

Example: A feedwater transient is in progress with S/G levels decreasing toward the reactor trip setpoint. If the operator starts a CA pump(s) to supplement CF flow and prevent the trip, the start is reportable under the 8-hour NRC notification criterion.

B. Pump suction swap to RN

7. Emergency AC Electrical Power Systems A. Diesel Generator starts, automatic or manual, unless the start was the expected result of a controlled (documented) test or procedure.

8. Ice condenser lower inlet door opening as a result of unplanned mass or energy release into containment A. Door openings resulting from planned evolutions such as containment ventilation fan starts, personnel entries into containment, etc., do not constitute system actuations.

9. Combustible Gas Control in Containment A. Containment air return and hydrogen skimmer (VX) operation (UFSAR 6.2.5.2)

1. Any unanticipated system operation B. Hydrogen Recombiners (UFSAR 6.2.5)

C. Hydrogen Purge (UFSAR 6.2.5)

D. Hydrogen Igniters (UFSAR 6.2.5)

Enclosure 4.9 RP/O/B/50001013 Courtesy Notification to States and Counties Page 1 of 4 for a Non-emergency Plant Event NOTE: notifYing state and county emergency preparedness This enclosure provides instruction for notifying management agencies (primary WP/EOCs) and EnergyQuest of non-emergency plant events by completing a Courtesy Notification Form (page 4 of 4) and faxing it to each verifYing its receipt with a follow-up phone call. {PIP O-COO-OI689}

agency, then verifying O-COO-01689}

1. Complete the Courtesy Notification Form as follows:

1.1 Provide the time and date of:

Notification

Event 1.2 Mark the event(s) that describes the reason for the notification.

1.3 Describe the event briefly, especially any impact to the site (damage, impact on operations, and any requested support received from off-site agencies).

NOTE: 1. The confirmation code number is randomly assigned to each message. This provides a method for authenticating an offsite agency official that calls the site over normal phone lines requesting additional information about the reported event. Knowing the confirmation code number shall be the authorization for site personnel to provide information about the event to the caller.

2. Calls received over selective signal lines are considered to be secure and do not require knowledge of the confirmation code number to receive additional information about the event.

1.4 Assign a 2-digit confirmation code number to the notification form.

1.5 Print the name and title of the individual authorizing the notification.

2. Notification by Group Fax NOTE: Step 2 sends a group fax and step 3 sends the fax to agencies individually.

2.l 2.1 WPIEOCs) of a non-emergency plant Notify the states and county agencies (primary WP/EOCs) event(s) by completing a Courtesy Notification Form (page 4 of 4) and transmitting it to the states and counties as follows:

Enclosure 4.9 RP/O/B/SOOOI013 RP/O/B/50001013 Courtesy Notification to States and Counties Page 2 of 4 for a Non-emergency Plant Event NOTE: Performing steps 2.1.1 through 2.1.3 sends the Courtesy Notification Form (page 4 of 4) to Perfonning multiple locations in sequence.

2.1.1 Place the completed form (page 4 of 4) face down into the fax machine.

2.1.2 Press the pre-programmed one-touch speed dial pushbutton for each of the following agencies:

o Q WPIEOC York Co WPIEOC o

Q Gaston Co. WP/EOC WPIEOC o

Q MeckCo. WP o

Q NCWPIEOC NCWP/EOC o

Q SCWPIEOC SCWP/EOC o

Q EnergyQuest 2.1.3 Press START 2.2 Verify by one of the following means that the form (page 4 of 4) was received by each of ofthe the agencies:

oQ Selective Signal (Enclosure 1.5, Emergency Response Telephone Directory)

Qo Duke or Commercial Telephone (Enclosures 1.12 -1.16,

- 1.16, Emergency Response Telephone Directory) 2.3 Community Relations duty person of the Courtesy Notification Form transmittal.

Notify CommlUlity 2.4 IF any agency did not receive the group fax, then make the courtesy notification to the agency( s) by performing step 3.

2.S 2.5 Fax a copy of the Courtesy Notification Form (page 4 of 4) to Emergency Planning at ofthe 831-3151.

2.6 Report any communications equipment failures to the duty Emergency Planner.

Enclosure 4.9 RP/O/B/SOOOI013 RP/O/B/5000/013 Courtesy Notification to States and Counties Page 3 of 4 for a Non-emergency Plant Event

3. Notification by Individual Fax 3.1 Notify the states and county agencies (primary WP/EOCs) of a non-emergency plant event(s) by completing a Courtesy Notification Form (page 4 of 4) and transmitting it to the states and counties as follows:

NOTE: Performing steps 3.1.1 through 3.1.3 sends the Courtesy Notification Form (page 4 of 4) to individual agencies one at a time.

3.1.1 Place the completed form (page 4 of 4) face down into the fax machine.

NOTE: SC WP/EOC and EnergyQuest list two fax numbers. Use the fax number for sending Emergency Notifications.

3.1.2 Enter the individual fax phone number (Enclosures 1.12 through 1.16 in the Emergency Response Phone Book) for the desired individual agency (WP/EOC).

EnergyQuest fax number is listed in Enclosure 1.19, Emergency Response Telephone Directory.

3.1.3 Press START.

3.1.4 Repeat steps 3.1.1 through 3.1.3 until all of the desired agencies have been faxed the form (page 4 of 4).

3.2 Verify by one of the following means that the form (page 4 of 4) was received by the agency(s):

o 1:1 Selective Signal (Encl (Encl1.5, 1.5, Emergency Response Telephone Directory) o 1:1 Duke or Commercial Telephone (Enclosures 1.12 -1.16,- 1.16, Emergency Response Telephone Directory) 3.3 Notify Community Relations duty person of the Courtesy Notification Form transmittaL ofthe transmittal.

3.4 Fax a copy of the completed Courtesy Notification Form (page 4 of 4) to Emergency Planning at 831-3151.

3.5 Report any communications equipment failures to the duty Emergency Planner.

Enclosure 4.9 RP/O/B/SOOOI013 RP/O/B/50001013 Courtesy Notification to States and Counties Page 4 of 4 for a Non-emergency Plant Event DUKE ENERGY CATAWBA NUCLEAR STATION COURTESY NOTIFICATION FORM NON-EMERGENCY EVENTS TimelDate Of Notification: _ _ _ _ _ _ _ / _ _ _ _ _ _ __

_/---------------

TimelDate Of Event: ________________

_ _ _ _ _ _ _ _ _ / ____________

_ _ _ _ _ _ __

Event (X):

_ Earthquake Toxic Gases _ Fatality Flood Civil Disturbance _ Fire Response by BethellNewport Hurricane Bomb Threat _ Medical Response by Ambulance Ice/Snow Vehicle Crash _ HazMat /Spill

Response

Tornado _ Explosion Other Events

==

Description:==

Confirmation Code Number: (This number is authentication for any off-site agency caller to be given information about the event.).

Confirmation Phone Number: (803) 831-8185 Reported By: _ _ _ _ _ _ _ _ _ _ __

Title:

- ----------

Enclosure 4.10 RP/O/B/SOOO/013 RP/O/B/5000/013 Safeguards ENS Event Report Page 110f2 of2 Date/Time of Notification _ _ _ __ __ __ __ __ __ ____ __

_____

NRC Person Notified _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ NRC Report No. _ _ _ __

State the following to the NRC Operations Center:

"This notification is made in accordance with 10CFR73.71. This is Duke Energy's Catawba Nuclear Station in NRC Region II making the notification. "

My Name is: _ _ _ _ _ _ _ _ _ _ _ My title is: _ _ _ _ _ _ _ _ _ _ _ _ __

I can be reached at -

-- -- --- ---- -- -- -- - -- -- -

"Your Name Please" - - ---- -- ----------- -- -- ----

1. *Date of occurrence: -

2. *Time of occurrence: - - --

- --

3. *Power level of units:

Unit 1 - - - - - Unit 2 - - - - -

If date and time of occurrence are not known, indicate the date and time of discovery.

4. Description of event: ____________________________________________________

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____

5. Security response/compensatory measures established:

6. LLEA (Local Law Enforcement Agency) Notified? YES _ ___ NO ___ _

(If yes, name of organization and telephone number) ____________________________

______________ __

Enclosure 4.10

/0 /B/5000/0 RP10 IB/500010 13 Safeguards ENS Event Report Page 2 of2

7. NRC Region II notified? YES _ _ NO _ _

(If yes, name of person notified) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

8. Who to contact for more information:

9. Consequences at plant:

Description of Equipment Systems Affected _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NOTE: After verbal transmission of this Enclosure, a copy should be sent by Fax to:

NRC Operations Center 301-816-5151 APPROVED BY: ____ _-=-____

_ _=-=--__

___ =-____

__ =--=--_________________

_ _ _ _ _ TIMEIDATE: _ _ _ _ _ __

OPERATIONS SHIFT MANAGER OR EMERGENCY COORDINATOR

Enclosure 4.11 RP/O/B/500010 RP/O/B/50001013 13 Event Notification Report Page 1 of2 STATE: "THIS IS THE CATAWBA NUCLEAR SITE IN NRC REGION 2 MAKING AN EVENT NOTIFICATION REPORT' EN#

NOTIFICATION UNIT CALLER'S NAME CALLBACK TELEPHONE #: NRC OPERATIONS OFFICER TIMEIDATE I -803-83 1-3920 (C/R)

ENS 1-803-831-3920 CONTACTED or 1-803-831-2674 (TSC)

NRC OPERATION TELEPHONE NUMBER: PRIMARY 301-816-5lO0 1-301-816-5100 or 1-800-532-3469; BACKUPS - [lst]I-301-951-D550

[1st] 1-301-951-0550 or 1-800-449-3694;

[2nd] 1-301-415-0550; and [3rd] 1-301-415-0553 EVENT TIME &ZONE EVENT POWER/MODE BEFORE POWERIMODE POWER/MODE AFTER (time)

Region II (zone)

DATE I 8-HR NON-EMERGENCY 10CFR72.7S(c) 10CFR72.75(c)

IMMEDIATE 4-HR NON-EMERGENCY 10CFR72.7S(b)ISFSI 10CFR72.75(b)ISFSI ISFSI EVENT CLASSIFICATION (GE, SAE, ALERT, (1) TS Deviation for ISFSI (1) Defect in ISFSI SSC (ISFSn NOUE) 50.72 or 72.75 (ISFSI) (2) Offsite Notification for ISFSI (2) ISFSI Confinement System PHYSICAL PROTECTION OF PLANT OR (3) Offsite medical (ISFSI)

Offsite (ISFSn MATERIALS 8-HR NON-EMERGENCY 10 CFR 50.72(b)(2) SO.72(b)(2)

TRANSPORTATION (10 CFR 20) (ii)(A) Degraded Condition 24-HOUR NON-EMERGENCY ISFSI MATERIALIEXPOSURE (10 (10 CFR 20) (ii)(B) Unanalyzed Condition Radiological Exposure 10CFR20.2202 IOCFR20.2202 (iv)(A) Valid System Actuation Fitness For Duty 10CFR26.73 IOCFR26.73 I-HR NON-EMERGENCY 10CFR50.72(b)(I) 10CFRSO.72(b)(I) (v)(A) Safe SID Capability Operating License Deviation TS Deviation pursuant to 10CFRSO.54(x) 10CFR50.54(x) (v)(B) RHR Capability Accidental Criticality or Lossffheft of Material (v)(C) Control of Radiological 24-HOUR NON-EMERGENCY ISFSI (v)(D) Accident Mitigation ISFSI Lost Safety Function 72.75(d)(I) 4-HR NON-EMERGENCY 10CFRSO.72(b)(2) 10CFR50.72(b)(2) (xii) Offsite Medical (i) TS Required SID (xiii) Lost ENS 30 DAY NON EMERGENCY (iv)(A) ECCS Discharge to RCS (xiii) Lost Emergency Assessment 10CFR20.2201 (iv)(B) RPS Actuation when Rx is critical (xiii) Lost Offsite Communications Theft, Lost or Missing Material (xi) Offsite Notification (xiii) Emergency Siren Inoperable 60-DAY OPTIONAL 10CFRSO.730s)(1) 10CFRSO.730s)(1)

Invalid Specified System Actuation OTHER UNSPECIFIED REQUIREMENT (IDENTIFy)

(IDENTIFY)

Retraction EVENT DESCRIPTION (Include: Systems SYstems affected actuations & their initiating signals causes effect of event on plant actions taken or planned PARs etc.)

CATEGORY INITIATION SIGNAL

- - REACTOR TRIP

- - ESF ACTUATION

- - ECCS ACTUATION

- - SIFLOW

- - LCO SYSTEM COMPONENT CAUSE: - - MECHANICAL - - ELECTRICAL

- - PERSONNEL ERROR - - OTHER Continue on Enclosure 4.11 page 2 of 2 if necessary.

NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NOT UNDERSTOOD? o 0 YES o NO NRC RESIDENT (Explain above)

STATE(s) NC DID ALL SYSTEMS FUNCTION DYES o NO SC AS REQUIRED? (Exp lain above)

(Explain LOCAL York County MODE OF OPERATION UNTIL ESTIMATED Gaston County CORRECTED: RESTART DATE Mecklenburg County OTHER GOV AGENCIES MEDUVPRESSRELEASE :

Enclosure 4.11 RP RP/O/B/50001013 10IB/500010 13 Event Notification Report Page 2 of2 IKADIOLOGICAL RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specitic (specific details/explanatIOns shonld be covered III event descnptlOn) 1-'1!.,.lUW KbLbA~b iLll...IUW KbLtA~b I I jUA~bUU~ RELEASE PASEOUS KbLbA~b UNPLANNED RELEASE IUN1'LANNbU KbLbA~b I I rjPLANNhl*'RELEASE RELEASE J

pERMINATED jlbKMINAlbU MUNIIUKbU IMONITORED I

IUNMONITORbIJ IUNMONlTUKbD PI'I'SITE vrr~l1b RbLEASE KbLbA~b [r.s.

I IL~. FAI~A/{MS

~ ~~tATED

~ERSONNEL PERSONNEL EXPOSED OR CONTAMINATED PFFSITE PROTECTNE ACTIONS RECOMMENDED OFFSITE PROTECTIVE State release path in description NOTE: Contact Radiation Protection Shift to obtain the following release information.

ConIact IF the notification is due dne and the information is not available mark "Not Available" and complete the notification.

Releases Rate (CIIsec)

(Cl/sec) %T.S. LIMIT HOOGUIDE ToIaI Total Activity (CI) %T.S. LIMIT HOOGUIDE Noble Gas

[Noble 0.1 Ci/sec 1000 CI Iodine 10 nCi/sec uCi/sec O.oI Cl O.oJ CI articnlate Particulate 1I nCi/sec uCi/sec 1ImCI mCI

~iquid Liqnid (exclnding tritinm (excluding tritium &

& 10uCIImin 10nCl/min 0.1 CI

~issolved dissolved noble I!obkgases) gases)

~iquid iqnid (tritinm)

(tritium) 0.2 CIImin Cl/min SCI Total Activity

[Total UIHbK UIHbR li.1R~~ MU1'uIURS

~lKk~ lVlVl'ojlIUK~

(~~~js~jt,~~

&t.Pf15~ jt,~~ A~EJECTrR AnaEJECI?R ~~~~llfi~

~Mfrf~tr~Aft f/~r il~f 29 ~U

~u (k~tr ~4) W N (EMF 34)WN EMF 33 IT2-EMFIO II IT2-EMFI0 1I'12'13)

'12'13)

~

RAJ) MONITOR READINuS READINUS ALARM ::>1Ol1'U11'U::>:

f'\LAKM ~tlrVli'H~: TKIP TRIP 11 II

o T.S.

us. LIMIT LIMIi (11 lit appllCable) NUl fNUT Al't'. NUL NUl Al't'. NOT NUl APPI.lCAH .1" NOT NUL APPLICAHIF KC~

~CS UK ::>U OR SU TUBb1 utili LEAKS:

LbAKS: CHECK OR CHbCK APPL1(:A HI .h. ITbMS UK FILL IN Al'PJ ITEMS (SpecltJc lspecltic detalls/explanatlOns should shonld be covered III m event descnptlOn) descnptlon)

LOCATION

~UCAnUN OF UF THbTHE LbAK LEAK (e.g. SO#,

~UII, valve, plpe, etc.):

etc. :

LbAKRAlb: gpmlgpd

~bAKKAlb: IL~. LIMll~

Il.~. LlMll~ : ISUDDEN I~UUUbN OR UK LONU LUNU TERM IbKM DEVELOPlVlbN UbV IT:

I:

LbAK

~bAK~IAKI ~lAKT VAllO:

UATb: 11Mb TIME .)( "AN~*.f!<;T! v 11

~ECOND1ttllV r(Last ::>ample):

II Y~Last Sample): PKIMAK Y

~ECONDARY-1ST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL:

LIST EVENT DESCRIPTION (Continned (Continued from Enclosnre Enclosure 4.11 Page 1I of 2)

ADDITIONAL INFORMATION MAY BE ATTACHED.

APPROVEDBY:

APPROVED ________________~------~--~--- T~EIDATE:

BY: ----=-c-,:--:-------:::::--------::::-----:c:--- TIMEmATE: ________________

_ _ _ _ _ _ _ ____ _ --_/ __//----- _--

yy Operations Shift Manager/Emergency Coordinator (eastern) mm dd

Enclosure 4.12 RP/O/B/SOOO/013 RP/O/B/SOOOI013 ENS Notification Retraction Page 1 of of11 In some cases, after an event or condition is reported to the NRC, it is subsequently determined that the event or condition is not reportable. The following guidance should be used when making an ENS Notification Retraction.

1. An ENS notification should be retracted via a phone call to the NRC Operations Center on the ENS telephone.

2. The retraction should include sound logical basis and explain the rationale used in determining that the event or condition is not reportable. Retractions should be reviewed by appropriate members of Operations Management, Regulatory Compliance, and/or Engineering before being transmitted to the NRC.

3. Retractions should be documented in Enclosure 4.11. Fill in the applicable sections of Enclosure 4.11. Ensure that under the "Event Classification" section the block next to "Retraction" is checked.

4. There is no set time limit for retractions. However, since most retractions occur following completion of an engineering and/or management review, it is expected that retractions would occur shortly after such review.

5. A retracted ENS report is retained in the NRC's ENS database along with the retraction.

Enclosure 4.13 RP/O/B/5000/013 Fitness for Duty Event Notification Report Page 1 of3 Fitness for Duty Reportable Event Report (Report # _ _ _ _ _ _ _ _ _.))

Date/Time of Notification -------------------

_ _ _ _ _ _ _ _ __ NRC Staff Notified _ _ _ _ _ _ __

StaffNotified State the following information to the NRC Operations Center:

"This notification is being made in accordance with 10 CFR Part 26. 73. This is Duke Energy's 26.73.

Catawba Nuclear Station in NRC Region II making the notification. "

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___

My name is: ___________________________________________________________ _

My title is: _____________________________________________________________

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

I may be reached at: (______

_ _ _ _ _) _ _ _ ____ __ ____ __ __ ___

DATE OF OCCURRENCE:

TIME OF OCCURRENCE:

Type of FFD Event:

Involves sale, use, or possession of illegal drugs with the protected area Involves sale, use, or possession of a controlled substance Involves use of alcohol with the protected area Determination of unfitness of scheduled work due to the consumption of alcohol by a licensed operator or supervisory personnel NRC employee believed to be under the influence of any substance or otherwise unfit for duty Confirmed positive test by a licensed operator or supervisory personnel False positive error on blind performance testing (administrative error)

Other / Explanation: _________________________________________________

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Individual involved:

Supervision assigned to perform duties within the scope of 10 CFR Part 26 Individual licensed under 10 CFR Part 55 to operate a power reactor NRC employee

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Other / Explanation: _________________________________________________

Enclosure 4.13 RP/O/B/SOOO/013 RP/O/B/SOOOI013 Fitness for Duty Event Notification Report Page 2 of3 Type of substance:

Alcohol Cocaine Marijuana Other (Specify): _ _ _ __ __ __ ____ __

__ __ __ __ __ __ _ _ ___ __ __ __ __ __ ___ _

Other Notifications:

Date I Time Site Vice President _-

- _- ---'1I-

_-_--

Station Manager _-

- _- -,1I- _-_--

Operations Shift Manager _

___ _---'11_ _-

NRC Resident Inspector _-

- _- ---'1I-

_-_--

Site Nuclear Training __

_ __ -,1,1_ __--

Site Security _ _-,1 ---'1_ _-

Anticipated Questions from the NRC Operations Officer:

FacilityName Facility Name _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Caller's Name & Telephone Number _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date && Time of Occurrence _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job Function of personnel involved (e.g., Licensed Operator, SRO, Electrical Supervisor, etc.)

Type of offense (e.g., use, sale, or possession of drugs inside the protected area, use of alcohol with the protected area, confinned confirmed positive test result on a licensed operator, SRO, or supervisory personnel, etc.) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

How offense was discovered _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Substance detected or involved

Evaluation of event (e.g., Did the substance abuse involve a failure in the individual's perfonnance performance resulting in an actual or potential degradation of the level of the plant safety?) _ _ _ _ _ __

Enclosure 4.13 RP /0 /B/5000/0 13 Fitness for Duty Event Notification Report Page 3 of3 Initial Management Action(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___

Follow-up Management Action(s) (if known) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Other notifications made (e.g., local law enforcement agency, FBI, DEA, State, News Media, NRC Resident, etc.) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Current Plant Status, effect Event had on plant, and plant status one day prior to event _ _ __

,

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE JPM 55 ADMIN Perform RP/O/Al5000/007 (Natural Disaster and Earthquake) for an Earthquake CANDIDATE EXAMINER JPM 582009 5S 2009 Page 1 of 10

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE Task RP/0IAl5000/007 (Natural Disaster and Earthquake) for an Earthquake Perform RP/0IAl50001007 Alternate DYES DNO [g] N/A

[2J Time Critical [g] YES DNO

[2J Path Evaluation Safety Function _

__ _ [2J

[g] N/A Location D Simulator Din-Plant L8J Classroom Evaluation Validation 22 minutes Method L8J Perform DSimulate Time JPM Type [2J Bank

[g] DNew o D Modified KIA GENERIC 2.4.40 (2.7/4.5) Knowledge of SRO responsibilities in emergency plan implementation.

Standard The procedure, RP/0IAl5700/007 RP/0IAl57001007 (Natural Disaster and Earthquake) Enclosure 4.4, is implemented with technical correctness through Step 1.6. The classification is RP/0IAl5000/001 within 15 minutes correctly identified as an ALERT per 4.7.A.1-1 of RP/0IAl50001001 of reaching the step to classify the event.

References RP/OIAl5000/007 (Natural Disaster or Earthquake), revision 029 RP/OIAl50001007 Candidate Start Time End Time ------

Duration Performance Rating D Satisfactory D Unsatisfactory Examiner (Printed Name) (Signature) (Date)

Comments JPM 5S 2009 Page 2 of 10

READ TO OPERATOR DIRECTION TO TRAINEE:

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

SIMULATOR SETUP N/A INITIATING CUE:

The following conditions exist:

Unit 1 is at 100% power

Unit 2 is in Mode 5, at 110°F and depressurized for maintenance

"OBE Exceeded" annunciator (1AD-4, B8) comes in alarm

The Control Room floor vibrates for several seconds.

A Seismic event alarm SMA-3 on 1MC8 has actuated.

There is a light on the Peak Shock Annunciator PSA-1575 on 1MC8 The Time History Accelerograph System computer alarm (CID2252) has activated and is collaborated by indications of a 0.06g Vertical and a 0.07g Horizontal quake.

Implement RP/0IAl57001007 (Natural Disaster and Earthquake) and take any necessary actions.

JPM 5S 2009 Page 3 of 10

Start Time:-_- __-

L1-J

~ RP/O/A/50001007 RP/0IAl50001007 2. Immediate Actions CRITICAL STEP IF an earthquake is detected by instrumentation OR felt in plant, perform Enclosure 4.4 (Earthquake).

STANDARD

_ _ SAT Candidate determines that the symptoms based on the initiating cue are for earthquake and implements Enclosure 4.4.

_ _ UNSAT COMMENTS l1-J

~ RP/O/B50001008 RP/0/B50001008 Enclosure 4.4 NOTE:

1. Immediate Actions may be performed simultaneously.

2. The four Reactor Coolant Leakage Detection Systems are not seismically qualified and must be assumed to be inoperable following any seismic event.

EMF38(L) can be verified to be operable based on power availability and sample pump operation.

3. Reactor Coolant Leakage Detection Systems are not required to be operable during Cold Shutdown.

4. Technical Specification 3.0.3 is entered until one of the Reactor Coolant leakage detection systems identified in step 1.1 is declared operable. {6}

5. An OAC Alarm at point CID 2252 indicates that there has been a recording of an event by seismic instrumentation. This alarm is in addition to an event indicator and initiation by starter unit MIMT 5090.

STANDARD

_ _ SAT Acknowledges note.

UNSAT COMMENTS JPM 5S 2009 Page 4 of 10

~ RP/0/A/5000/007 Enclosure 4.4, Step 1.1 CRITICAL STEP Following any earthquake that is felt in the plant or is recorded on instrumentation, including earthquakes smaller than OBE, declare all four Reactor Coolant Leakage Detection Systems (listed below) as inoperable:

1.1.1 Containment Floor and Equipment Sump Level and Flow Monitoring System 1.1.2 VUCDT Level Monitoring System) 1.1.3 EMF38(L)

STANDARD SAT Tech Spec 3.4.15 Condition "G" is entered for Unit 1 and 3.4.15 does not apply to Unit 2 but may state that U2 would be entered in TSAIL for tracking. _ _ UNSAT EXAMINER NOTE: A follow-up question may need to be asked if he does not consult Technical Specifications at this time.

EXAMINER CUE: "The WCC SRO will make entries in TSAIL."

COMMENTS li-J

~ RP/0/A/5000/007 Enclosure 4.4, Step 1.2.1 CRITICAL STEP Determine the operable status of 1(2)EMF38(L) from the Control Room by the following methods:

1.2.1 Perform a source check to verify that power is available:

1EMF38(L)

2EMF38(L)

STANDARD SAT States he would perform a source check.

_ _ UNSAT EXAMINER CUE: "1 EMF-38L did NOT respond to the source check."

COMMENTS JPM 5S 2009 Page 5 of 10

~ RP/O/A/50001007 RP/0IAJ50001007 Enclosure 4.4, Step 1.2.2 1.2.2 Visually verify that the sample pumps are operational:

"ON" indicating light for "1EMF38 "1 EMF38 CONTAINMENT PAR" - LIT

One indicating light on "SAMPLE FLOW SELECT PANEL" (Unit 1) - LIT

"ON" indicating light for 2EMF 38 CONTAINMENT PAR" - LIT

One indicating light on "SAMPLE FLOW SELECT PANEL" (Unit 2) - LIT STANDARD SAT Candidate states they would check all indicating lights "ON"Candidate locates the

_ _ UNSAT Quiktel Key Pad and enters information and transmits.

EXAMINER CUE: "All indicating lights are LIT."

COMMENTS LLJ

~ RP/O/A/50001007 RP/0IAJ50001007 Enclosure 4.4, Step 1.2.3 Verify the following annunciators - Dark:

"1EMF38 "1 EMF38 CONTAINMENT LOSS OF FLOW" (1RAD-1, (1 RAD-1, 0/4)

D/4)

"2EMF38 LOSS OF CONTAIN SAMPLE FLOW" (2RAD-1, E/3)

STANDARD SAT Checks status of 1RAD-1, 0/4 D/4 and 2RAD-1, E/3.

_ _ UNSAT EXAMINER CUE: "1RAD-1, D/4 and 2RAD-1, E/3 are DARK."

COMMENTS JPM 5S 2009 Page 6 of 10

---.U

~ RP/0/A/5000/007 Enclosure 4.4, Step 1.2.4 RP/0/Al5000/007 CRITICAL STEP IF the EMFs are inoperable, apply the appropriate action statement for Technical Specification 3.4.15.

STANDARD

_ _ SAT Notes 1EMF-38L is inoperable.

_ _ UNSAT EXAMINER NOTE: Examinee may be assured that unit 1 is in 3.0.3 from notes above and not look at Tech Specs. Examiner may need to ask examinee to show which Tech Specs apply. Examinee should go to Tech Spec 3.4.15 when asked and show Unit 1 in Condition "G", and Unit 2 is not applicable.

COMMENTS JLJ RP/0/A/5000/007 Enclosure 4.4, Step 1.3 RP/0/Al5000/007 1.3.1 Notify the WWM or WCC SRO to perform an "(a) 4 risk assessment" utilizing the risk assessment tool. PRA code "OSSA_ADWH" should be used for the duration of the event.

1.3.2 Based on the results of the assessment, implement risk management actions that do not interfere with other actions implemented by this procedure.

1.3.3 IF either unit is in Mode 5, 6, or NO MODE:

Protect and secure/prevent switchyard work

Protect and secure/prevent work on or near energized main power sources (transformers and associated systems)

Protect and secure/prevent work on available Diesel Generators {18}

STANDARD

_ _ SAT Contacts the WWM or WCC SRO.

_ _ UNSAT EXAMINER CUE: "The WCC SRO will perform the remainder of Step 1.3."

COMMENTS JPM 5S 2009 Page 7 of 10

JLJ

~ RP/O/A/50001007 RP/0/A/5000/007 Enclosure 4.4 NOTE:

1. Decision on Shutdown IF the OBE has been exceeded OR significant damage is found during operator walkdowns, the plant should be shutdown in an orderly manner for more detailed inspections. IF the plant has tripped under conditions which would warrant shutdown, the plant should remain shutdown for detailed inspections.

2. Pre-Shutdown Inspections Following a decision to shutdown the plant, but prior to initiating shutdown, visual inspections of essential safe shutdown equipment should be performed to determine its readiness. Other factors outside of the control of the plant that could affect the timing of the shutdown (e.g.

availabilitylreliability of off site power), should also be evaluated at this time.

availability/reliability

3. Normal Shutdown When plant capability to safely shutdown has been verified, normal shutdown would proceed. Under all circumstances the method and pace at which the Reactor is brought to a safe condition should continue to be based upon all instrumentation indications and the operator's judgment.

STANDARD _ _ SAT Acknowledges note.

_ _ UNSAT COMMENTS

---.!QJ J..QJ RP/O/A/50001007 Enclosure 4.4, Step 1.4 RP/0/A/5000/007 CRITICAL STEP 1.3.1 IF the Operational Bases Earthquake (OBE) Exceeded Alarm 1AD-4, B/8, is received AND the effects of an earthquake are felt, immediately take the Unit(s) to Hot Standby (Mode 3). For the initiation of any unit shutdown, carry out the RP/O/B/50001013, (NRC Notification Requirements).

reporting provisions of RP/0/B/5000/013, STANDARD

_ _ SAT Determines Unit 1shutdown to Mode 3 required.

_ _ UNSAT EXAMINER CUE: "The control room crew is beginning a shutdown."

COMMENTS JPM 5S 2009 Page 8 of 10

U!J

.J1J RP/O/A/SOOOI007 RP/0IAl50001007 Enclosure 4.4, Step 1.5 1.S CRITICAL STEP IF the Operational Bases Earthquake (OBE) Exceeded Alarm 1AD-4, B/8, is received AND the effects of an earthquake are felt, swap RN to the Standby Nuclear Service Water Pond in accordance with OP/0IAl64001006C OP/O/A/64001006C (Nuclear Service Water System).

STANDARD SAT Determines that an RN swap to the SNSWP is required.

_ _ UNSAT EXAMINER CUE: "An RO is performing the swap to the SNSWP."

COMMENTS

~ RP/O/A/SOOOI007 RP/0IAl50001007 Enclosure 4.4, Step 1.6 CRITICAL STEP*

RP/01Al50001001, (Classification of Classify the emergency as appropriate per RP/O/A/SOOOI001, Emergency), and commence notification and other protective measures as directed by appropriate Emergency Response Procedure.

STANDARD

_ _ SAT Classifies the emergency as an ALERT per 4.7.A.1-1 of RP/O/A/SOOOI001.

RP/01Al50001001.

_ _ UNSAT EXAMINER NOTE: The classification shall be determined within 15 minutes.

EXAMINER CUE: Once the classification is determined, state:

RP/O/Al5000/001 paperwork.

"The OSM will complete RP/OIAl5000/001

RP/O/Al5000/007."

"Another SRO will complete the remainder of RP/OIAl5000/007."

COMMENTS TIME STOP: _ __

JPM SS5S 2009 Page 9 of 10

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

INITIATING CUE:

The following conditions exist:

Unit 1 is at 100% power

Unit 2 is in Mode 5, at 110°F and depressurized for maintenance

"OBE Exceeded" annunciator (1AD-4, B8) comes in alarm

The Control Room floor vibrates for several seconds.

A Seismic event alarm SMA-3 on 1MC8 has actuated.

There is a light on the Peak Shock Annunciator PSA-1575 on 1MC8 The Time History Accelerograph System computer alarm (CID2252) has activated and is collaborated by indications of a 0.06g Vertical and a 0.07g Horizontal quake.

Implement RP/O/A/57001007 RP/0IAl57001007 (Natural Disaster and Earthquake) and take any necessary actions.

Duke Energy Procedure No.

Catawba Nuclear Station RP/O/ AlSOOO/007 RP/O/A/SOOO/007 NATURAL DISASTER AND EARTHQUAKE Revision No.

029 Electronic Reference No.

CNOOSGNT Reference Use PERFORMANCE I

* * * * * * * *

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

(ISSUED) - PDF Format

RP/OIA/50001007 Al50001007 Page 2 of3 Natural Disaster and Earthquake

1. Symptoms NOTE: The Duke Power Company System Coordinator will notify the Control Room for all severe weather warnings issued for York County. The Control Room is also provided with a NOAA radio.

1.1 Tornado watch issued for York County 1.2 Tornado warning issued for York County OR tornado on-site 1.3 Hurricane winds are expected on-site within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.4 Earthquake is detected by instrumentation or felt in plant 1.4.1 Seismic event alarm SMA-3 on 1MC8IMC8 1.4.2 OBE EXCEEDED alarm on lAD-4, B/8 1.4.3 Light on Peak Shock Annunciator PSA-1575 on 1MC8 IMC8 1.4.4 Effects of an earthquake are seen, felt or heard.

1.5 Flooding due to high lake level (lake elevation> 593.5 Mean Sea Level (MSL)) or seiche (lake tidal wave).

1.6 Low lake level (lake elevation < 557.5 Ft. MSL)

2. Immediate Actions 2.1 IF a tornado watch has been issued for York County, perform Enclosure 4.1.

2.2 IF a tornado warning has been issued for York County OR tornado on-site, perform Enclosure 4.2.

2.3 IF Hurricane winds are expected on-site within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , perform Enclosure 4.3.

2.4 IF an Earthquake is detected by instrumentation OR felt in plant, perform Enclosure 4.4.

2.5 IF flooding due to high lake level (lake elevation> 593.5 MSL) or seiche (lake tidal wave),

perform Enclosure 4.5.

2.6 IF low lake level (lake elevation < 557.5 Ft. MSL), perform Enclosure 4.6.

RP/OI RP/0/Al5000/007 A!5000/007 Page 3 of3

3. Subsequent Actions 3.1 IF communications are lost or communications trouble is encountered, refer to the Emergency Response Telephone Directory.

3.2 IF at anytime this procedure requires that the NRC be notified per RP/O/B/SOOO/013, RP/O/B/5000/013, contact the Catawba Nuclear Site NRC Resident Inspector (duty person). {9}

4. Enclosures 4.1 Tornado Watch Issued For York County 4.2 Tornado Warning Issued For York County OR Tornado On-site 4.3 Hurricane Winds Are Expected On-site Within 12 Hours 4.4 Earthquake 4.5 Flooding Due to High Lake Level (Lake Elevation> 593.5 MSL) OR Seiche (Lake Tidal Wave 4.6 Low Lake Level (Lake Elevation < 557.5 Ft. MSL) 4.7 a Non-emergency Plant Event Courtesy Notification to States and Counties for aNon-emergency 4.8 Corrective Actions or Commitments

Enclosure 4.1 RP/O/A/5000/007 Tornado Watch Issued For York County Page 1 of3

1. Immediate Actions NOTE: 1. A tornado watch indicates conditions are favorable for a tornado to occur.

infonnation > 90 mph shall be obtained from the National Weather

2. Wind speed information>

Service located in Greenville/Spartanburg, S.C.

S.c. at (800) 268-7785 or (864) 879-1085 (unpublished).

3. Immediate hmnediate Actions may be performed perfonned simultaneously.

1.1 Announce the following over the P PA A System:

personnel. Attention all plant personneL "Attention all plant personneL personnel. This is the Operations Shift Manager. A tornado watch has been issued for York County. Be prepared to take shelter should a tornado develop on site. Please ensure all tornado doors remain closed except for personnel transit. Further updates will be provided as conditions warrant."

{I}

NOTE: detennination should be made for system(s) required to be shut down by this Further determination response procedure but required to be operating by a compensatory action item.

1.2 Notify WCC SRO to review open items in the Hazard Barrier Manual for applicability.

1.3 Perfonn Perform the following while continuing in this procedure: {II {II 1.3.1 Notify the WWM or WCC SRO to perform perfonn an "(a) 4 risk assessment" utilizing the tool. PRA code "OSSA ADWH" should be used for the duration risk assessment tooL of the event. 1.3.2 Based on the results of the assessment, implement risk management actions that do not interfere with other actions implemented by this procedure. 1.3.3 IF either unit is in Mode 5, 6 or NO MODE:

Protect and secure/prevent switchyard work
Protect and secure/prevent work on or near energized main power sources (transfonners (transformers and associated systems)
Protect and secure/prevent work on available Diesel Generators {18}

1.4 Evaluate implementation of the following: 1.4.1 Contact Security and verify that exterior doors are being closed and tornado doors are closed per Security procedures. 1.4.2 IF a personnel safety hazard does not exist due to lightning or high winds, the WCC SRO will utilize appropriate personnel to lower crane booms.

Enclosure 4.1

                                                                                   /0/A!5000/007 RP/O/A/5000/007 RP Tornado Watch Issued For York County               Page 2 of3 1.4.3               RP/Radwaste Chemistry to minimize all handling of radioactive Notify RPlRadwaste materials and releases of radioactive waste to the environment for the duration of the tornado watch.

1.4.4 IF RN swapover to the Standby Nuclear Service Water Pond has NOT occurred automatically on low low lake level of 557.5 ft. MSL, refer to AP/0/A/5500/020 (Loss of Nuclear Service Water). AP/0/A!5500/020 1.5 IF any of the following activities are in progress OR are scheduled to begin within the ofthe time frame of the tornado watch, terminate the activity {2}:

NS pump tests
NS heat exchanger tests
FWST makeup to the Spent Fuel Pool 1.6 Review status of alternate power sources and safety related equipment to assure safe shutdown equipment availability (D/Gs, CA, condensate sources, S/G PORVs, ND, KC, RN).

2. Subsequent Actions 2.1 Severe Weather InformationIForecast To obtain the latest severe weather information/forecast for York County, consult the National Weather Service located in Greenville/Spartanburg, S.c. S.C. at (800) 268-7785 or (864) 879-1085 (unpublished).

2.2 Meteorological Conditions As a backup to the Catawba site meteorological system (i.e., wind speed, wind direction, etc.), consult the National Weather Service located in Greenville/Spartanburg, S.c., S.C., at (800) 268-7785 or (864) 879-1085 (unpublished). CAUTION: The site inspection is meant to be done before a tornado arrives on site. It would NOT be prudent to send a team out to survey the site in the middle of a tornado. Operations Shift Manager discretion based on safety considerations should determine sending personnel for any site inspection. 2.3 IF time and personnel safety permit, notify the Work Control Center SRO and Nuclear Site Services personnel (ext. 3329) to have appropriate personnel inspect the site (including the switchyard) for the following items and secure, relocate them away from the site or relocate to the NE side of the plant, if possible. {3} {8}

Large cranes (lower boom to ground, if possible)
Lifting devices secured
Vehicles (ensure materials stacked on truck are tied down)

Enclosure 4.1 RP/O/A/SOOO/007 RP/OIAl50001007 Tornado Watch Issued For York County Page 3 of3

Hazardous material containers
Trash bin or equipment on wheels
Compressed gas cylinders
Loose lumber or material near critical equipment
Move fire brigade equipment to an area inside plant as applicable 2.4 This procedure remains in effect until one of the following conditions is met:
Termination of tornado watch for York County by National Weather Service
Duke Power Meteorological Group (704-382-0139) verifies that a tornado threat to the Catawba Nuclear Site no longer exists. {4{4}}

Enclosure 4.2

                                                                                 /0 /AlSOOO/007 RP/O/A/SOOO/007 RP Tornado Warning Issued For York County                Page 1 of6 OR Tornado On-Site

1. Immediate Actions NOTE: 1. Tornado warning indicates that an actual tornado has been reported to the National Weather Service (NWS) or has been sighted on radar.

information>

2. Wind speed infonnation > 90 mph shall be obtained from the NWS located in Greenville/Spartanburg, S.C.,

S.c., at (800) 268-7785 or (864) 879-1085 (unpublished).

3. Immediate Actions may be perfonned performed simultaneously.

1.1 Should the sustained winds, lasting 15 minutes, in excess of 95 mph develop on site which jeopardize the safe operation of the reactor, take the unites) unite s) to Hot Standby (Mode 3). For the initiation of any unit shutdown, carry out the reporting provisions of RP/0/B/5000/013 (NRC Notification Requirements). 1.2 RP/O/ Al5000/001 (Classification of Classify the emergency as appropriate per RP/0/A/5000/001 Emergency). 1.3 Commence notification and other protective measures as directed by appropriate Emergency Response Procedure. 1.4 Announce the following over the PA System:

Tornado is not expected to pass over the site "Attention all plant personnel. Attention all plant personnel. This is the Operations Shift Manager. A tornado warning has been issued for York County from _ __

to hours. Be prepared to take shelter should a tornado develop on site. Further updates will be provided as conditions warrant."

Tornado is expected to pass over the site "Attention all plant personnel. Attention all plant personnel. This is the Operations Shift Manager. A tornado warning has been issued for York County. Take shelter immediately. Do not take shelter in temporary buildings or trailers. Please ensure all tornado doors remain closed except for personnel transit. Further updates will be provided as conditions warrant." {I}

NOTE: determination should be made for system(s) required to be shut down by this Further detennination response procedure but required to be operating by a compensatory action item. 1.5 Notify WCC SRO to ensure contingency actions for hazard barrier restoration are performed perfonned as needed per the Hazard Barrier Manual.

Enclosure 4.2 RP/O/A/5000/007 Tornado Warning Issued For York County Page 2 of6 OR Tornado On-Site 1.6 Perfonn the following while continuing in this procedure: {11} {II} {14} 1.6.1 Notify the WWM or WCC SRO to perfonn an "(a) 4 risk assessment" utilizing the risk assessment tool. PRA code "OSSA ADWH" should be used for the duration of the event. 1.6.2 Based on the results of the assessment, implement risk management actions that do not interfere with other actions implemented by this procedure. 1.6.3 IF either unit is in Mode 5, 6 or NO MODE:

Protect and secure/prevent switchyard work
Protect and secure/prevent work on or near energized main power sources (transfonners and associated systems)
Protect and secure/prevent work on available Diesel Generators {18}

NOTE: Grid instabilities may continue up to 12 hours following a loss of grid. 1.7 AP/l(2)/A/5500/007 (Loss ofNonnal Power), EPI1(2)/A/5000/ECA-O.O Review API1(2)/A/5500/007 EP/1(2)/A/SOOO/ECA-O.O (Loss of All AC Power), and OP/O/B/6100/013 (Standby Shutdown Facility Operation). Take the necessary actions to ensure equipment required for station blackout response is available. 1.8 Ensure the following steps have been perfonned: 1.8.1 Notify Security to perfonn the following actions per Security procedures:

Close all exterior doors
Close and latch tornado door S303A (access to SPA, 574 elevation, Auxiliary Service Building) (mod CE-61506)
Ensure all non-CAD tornado doors are closed per list in Security procedures
Verify CAD tornado doors are closed via alanns per Security procedures 1.8.2 IF any of the following activities are in progress OR are scheduled to begin ofthe within the time frame of the tornado warning, tenninate the activity {2}:
NS pump tests
NS heat exchanger tests
FWST makeup to the Spent Fuel Pool

Enclosure 4.2 RP/O/A/SOOO/007 RP/O/A/50001007 Tornado Warning Issued For York County Page 3 of6 OR Tornado On-Site CAUTION: The site inspection is meant to be done before a tornado arrives on site. It would NOT be prudent to send a team out to survey the site in the middle of a tornado. Operations Shift Manager discretion based on safety considerations should determine sending personnel for any site inspection. I.S.3 1.8.3 IF time and personnel safety permit, notify the Work Control Center SRO and Nuclear Site Service personnel (ext. 3329) to have appropriate personnel inspect the site (including the switchyard) for the following items and secure, relocate them away from the site, or relocate to the NE side of the plant, if possible: {3} {8}{S}

Large crane (lower boom to ground, if possible)
Lifting devices secured
Vehicles (ensure materials stacked on truck are tied down)
Hazardous material containers
Trash bin or equipment on wheels
Compressed gas cylinders
Loose lumber or material near critical equipment
Move fire brigade equipment to an area inside plant as applicable

1. S.4 1.8.4 Review status of alternate power sources and safety related equipment to assure safe shutdown equipment availability (DIGs, CA, condensate sources, S/G PORVs, ND, KC, RN).

I.S.5 1.8.5 Coordinate with Chemistry to increase CACST, UST and hotwell inventories. I.S.6 1.8.6 Coordinate with lAB to return to service any available'out available out of service battery chargers. I.S.7 1.8.7 RP/Radwaste Chemistry to stop all handling of radioactive materials and Notify RPlRadwaste releases of radioactive waste to the environment for the duration of the tornado warnmg. I.S.S 1.8.8 Ensure fuel handling operations are secured. I.S.9 1.8.9 IF a DIG is NOT available in modes 4,5, 4, 5, or 6 to provide backup power for a potential loss of offsite power, evacuate the affected unit's containment. {13} I.S.10 1.8.10 IF a unit is in Modes 5, 6 or No Mode, perform the following:

Ensure the Reactor Building Equipment Hatch is secured.
Ensure the Equipment Hatch Missile Shield is in position protecting the Equipment Hatch. {I O}

{1O}

Enclosure 4.2 RP101Al50001007 RP/O/A/5000/007 Tornado Warning Issued For York County Page 4 of6 OR Tornado On-Site

Ensure NC System level is greater than and maintained above 7.25% level (midloop operation).

1.8.11 IF lake level decreases to 557.5 feet MSL AND the RN System suction has NOT swapped to the Standby Nuclear Service Water Pond, refer to AP/OIAl55001020 (Loss of Nuclear Service Water). AP/0/A/5500/020 1.8.12 Ventilation Systems shall be aligned as follows: A. Ensure the VF Systems are shutdown per OP/1(2)/A/6450/004 OPIl(2)1A164501004 (Fuel Pool Ventilation System). B. Ensure the following ventilation systems are shut down:

OPII (2)1Al645 010 17 (Containment Air Release and Addition VQ per OP/1(2)/A/6450/017 System)
VP per OP/1(2)/A/6450/015 OPIl(2)1A164501015 (Containment Purge System)
OP/1(2)IAl64501002 (Annulus Ventilation System)

VE per OP/1(2)/A/6450/002 1.8.13 Notify the responsible System Engineer on duty that all ventilation systems are being shut down, and they need to consider the possibility of condensation. 1.9 IF a tornado is reported on site property, perform the following steps: 1.9.1 Ensure all VA System fans are off. NOTE: The action taken in the next step causes the VA System to be inoperable. TS 3.0.3 is applicable on both units. 1.9.2 Depress the "INITIATE" pushbuttons on "TORNADO ISOL TRN A(B)" on 1MC-5 and 2MC-5 ensuring all automatic functions occur as expected. 1.9.3 WHEN conditions permit, coordinate a survey of plant structures and equipment (similar to normal daily rounds) to determine the extent of damage as follows: A. Following any incident or natural phenomenon event that is applicable to this procedure, a visual inspection of the ISFSI Vertical Concrete Cask (VCC) is required within 4 hours. This inspection is required by NAC-UMS Technical Specification A5.4. Perform this inspection per VMS Operations procedure PT/OI PT/0/A/4600/031 (NAC-UMS Cask Surveillance). Al46001031 (NAC-VMS B. lAB and Mechanical Maintenance to assist Notify personnel from IAE Operations in the evaluation of weather induced damage as necessary.

Enclosure 4.2 RP/O/AJ5000/007 RP/O/Al5000/007 Tornado Warning Issued For York County Page 5 of6 OR Tornado On-Site C. Notify Radiation Protection personnel to survey the Reactor, Auxiliary and Fuel Pool Buildings to ensure shielding integrity. D. Notify Chemistry personnel to survey areas where damage may release dangerous chemicals (e.g. Sulfuric Acid Storage). E. Record the findings of the survey in the associated unit's Nuclear Shift Supervisor Log. F. Inspect and clean debris from Control Room intake area, if necessary, after tornado/wind event. {12} G. Inspect and clean debris from the intake canallSNSWP, canal/SNSWP, if necessary, after tornado/wind event. {17} {17} H. Following a tornado onsite, inspect the diesel generator(s)'s fuel oil storage tank fill and vent lines for damage per Enclosure 4.15 ofOP/1/AJ6550/001 of OP/1/Al655 0/00 1 and OP/2/A; 6550/001 {19}. 1.9.4 IF the survey identifies plant damage, perform the following: A. Determine the emergency classification for current plant conditions. B. Make required notifications C. Notify management of plant status and any potential for a unit shutdown. 1.9.5 IF an emergency has NOT been declared, notify York County Emergency Management about the event through the York County 911 Telecommunicator Te1ecommunicator and as necessary, request emergency response support. {5} NOTE: 1. A request for emergency response support (except an ambulance) from an off-site agency requires a 4-hour notification of the NRC as an "Off-site Notification" per RP/O/B/SOOO/013 (NRC Notification Requirements).

2. A request for ambulance support for a "contaminated injury" is an 8-hour notification and the request for transport of a "clean injury" does not require a NRC notification.

1.9.6 IF emergency response support from York County Emergency Management is requested AND an emergency has NOT been declared, notify the NRC under the 4-hour notification requirement for Off-site Notifications.

Enclosure 4.2 RP/O/A/5000/007 Tornado Warning Issued For York County Page 6 of6 OR Tornado On-Site

2. Subsequent Actions 2.1 Severe Weather InformationIForecast To obtain the latest severe weather information/forecast for York County, consult the National Weather Service located in Greenville/Spartanburg, S.C. at (800) 268-7785 or (864) 879-1085 (unpublished).

2.2 Meteorological Conditions As a backup to the Catawba site meteorological system (i.e., wind speed, wind direction, S.c. at etc.), consult the National Weather Service located in Greenville/Spartanburg, S.C. (800) 268-7785 or (864) 879-1085 (unpublished). 2.3 Restore affected plant systems to normal operation per applicable site procedures 2.4 IF an emergency has NOT been declared for this event AND the NRC has NOT been notified of this event, perform the following: 2.4.1 Notify the duty Emergency Planner. 2.4.2 Notify the Public Affairs duty person. 2.4.3 IF aatornado tornado touched down on site and a classification was not needed, make a courtesy notification to the states and counties using Enclosure 4.7. NOTE: Permission for unit startup is required from FEMAlNRC after a plant shutdown due to a natural disaster that affects both the plant and the local government emergency response capability. 2.5 IF a unit restart is desired, consult site management for unit startup criteria. 2.6 This procedure remains in effect until one of the following conditions is met:

Termination of tornado watch for York County by National Weather Service
Duke Energy Meteorological Group (704-382-0139) verifies that a tornado threat to the Catawba Nuclear Site no longer exists.

Enclosure 4.3 RP/O/A/5000/007 RP/O/A/SOOO/007 Hurricane Winds On-Site Within 12 Hours Page 1 of5

1. Immediate Actions NOTE: infonnation > 90 mph shall be obtained from the National Weather

1. Wind speed information>

Service (NWS) located in Greenville/Spartanburg, S.c. S.C. at (800) 268-7785 or (864) 879-1085 (unpublished). '

2. Immediate Actions may be performed perfonned simultaneously.

3. Tornadoes often develop in the northeast quadrant of a hurricane.

1.1 Announce the following over the P A System:

       "Attention all plant personnel. Attention all plant personnel. This is the Operations Shift Manager. Hurricane force winds are projected to be on site within 12 hours. Be prepared to take shelter should the hurricane force winds develop on site. Further updates will be provided as conditions warrant."

NOTE: Further determination detennination should be made for system(s) required to be shut down by this response procedure but required to be operating by a compensatory action item. 1.2 Notify WCC SRO to ensure contingency actions for hazard barrier restoration are perfonned performed as needed per the Hazard Barrier Manual. 1.3 Perfonn the following while continuing in this procedure: {II} {14} Perform 1.3.1 Notify the WWM or WCC SRO to perfonn perform an "(a) 4 risk assessment" utilizing the risk assessment tool. PRA code "OSSA ADWH" should be used for the duration of the event. 1.3.2 Based on the results of the assessment, implement risk management actions that do not interfere with other actions implemented by this procedure. 1.3.3 IF either unit is in Mode 5, 6 or NO MODE:

Protect and secure/prevent switchyard work
Protect and secure/prevent work on or near energized main power sources (transfonners (transformers and associated systems)
Protect and secure/prevent work on available Diesel Generators {18}

NOTE: Grid instabilities may continue up to 12 hours following a loss of grid. 1.4 Review AP/l(2)/A/5500/007, API1(2)/A/5500/007, (Loss of ofNonnal Normal Power), EPI1(2)/A/5000IECA-0.0, EP/l(2)/A/5000/ECA-0.0, (Loss of All AC Power) and OP/0/B/6100/013, OP/0/B/61 00/0 13 , (Standby Shutdown Facility Operation). Take the necessary actions to ensure equipment required for station blackout response is available.

Enclosure 4.3 RP10I Al50001007 RP/O/A/50001007 Hurricane Winds On-Site Within 12 Hours Page 2 of5 NOTE: 1. Sustained winds (lasting 15 minutes) in excess of73 mph is used as the indicator of the arrival of the hurricane on-site. As the hurricane moves across the site wind speeds could exceed the design basis wind speed of 95 mph.

2. The Station Blackout rule (NUMARC 8700) applies when hurricanes affect nuclear stations and requires the units to be placed in Mode 3, two hours prior to the arrival of hurricane force winds on site.

1.5 Discuss with site management the timing and method for shutting down the plant so as to be in Hot Standby (Mode 3) two hours before the anticipated hurricane arrival at the site. NOTE: Travel to the site could be restricted or prohibited based on the intensity and path of the storm. 1.6 Discuss with site management the potential for on-site 24-hour staffing for shift relief and Emergency Response Organization (ERO). 1.7 Review status of alternate power sources and safety related equipment to assure safe shutdown equipment availability (DIGs, CA, condensate sources, S/G PORVs, ND, KC, RN). 1.8 Coordinate with Chemistry to increase CACST, UST and hotwell inventories. 1.9 Coordinate with lAB to return to service any available out of service battery chargers. 1.10 IF a personnel safety hazard does not exist due to lightning or high winds, the WWCCCC SRO will utilize appropriate personnel to lower crane booms. 1.11 Evaluate running the Diesel Generators based on previous run history prior to the arrival of hurricane force winds on site. 1.12 IF any of the following activities are in progress OR are scheduled to begin, terminate the activity: {2}

NS pump tests
NS heat exchanger tests
FWST makeup to the Spent Fuel Pool

2. Subsequent Actions 2.1 Shut down the unites) to be in Hot Standby (Mode 3) two hours prior to the arrival of hurricane force winds (sustained wind speeds, lasting 15 minutes, in excess of73 mph).

For the initiation of any unit shutdown, carry out the reporting provisions of RP/O/B/50001013 RP10/B/500010 13 (NRC Notification N otification Requirements).

Enclosure 4.3 RP/O/A/50001007 Hurricane Winds On-Site Within 12 Hours Page 3 of5 2.2 Complete the following steps prior to the arrival of hurricane force winds on site: 2.2.1 RPlRadwaste Chemistry to stop all handling of radioactive materials Notify RP/Radwaste and releases of radioactive waste to the environment for the duration of the hurricane. 2.2.2 Ensure fuel handling operations are secured. 2.2.3 IF a DIG is NOT available in modes 4, 5 or 6 to provide backup power for a potential loss of offsite power, evacuate the affected unit's containment. {13} 2.2.4 IF a unit is in Modes 5, 6 or No Mode, perform the following:

Ensure the Reactor Building Equipment Hatch is secured.
Ensure the Equipment Hatch Missile Shield is in position protecting the Equipment Hatch. {I O}
Ensure NC System level is greater than and maintained above 7.25% level (midloop operation).

2.2.5 IF RN swapover to the Standby Nuclear Service Water Pond has NOT occurred automatically on low low lake level of 557.5 ft. MSL, refer to AP/O/A/55001020 (Loss ofRN System). AP/OIA/55001020 2.2.6 Ventilation Systems shall be aligned as follows: A. Minimize releases from VQ System while controlling containment pressure throughout the emergency per OPI1OP /l (2)/A/645010 (2)1 A/645010 17 (Containment Air Release and Addition System). B. Ensure the following ventilation systems are shut down: oD VF per OPI1(2)/A/64501004 OP/l(2)/A/64501004 (Fuel Pool Ventilation System) oD VP per OPI1(2)/A/64501015 OP/l(2)/A/64501015 (Containment Purge System) oD VE per OPI1(2)/A/64501002 OP/l(2)/A/64501002 (Annulus Ventilation System) 2.2.7 Notify the responsible System Engineer on duty that VF, VP, and VE ventilation systems are being shut down, and they need to consider the possibility of condensation. 2.2.8 Inspect RL intake screens and screen backwash system to ensure they are in good operating condition. {17} 2.2.9 Inspect the cooling tower screens to ensure they are in good operating condition. {17}

Enclosure 4.3 RP/O/A/5000/007 Hurricane Winds On-Site Within 12 Hours Page 4 of5 2.3 IF hurricane force winds are on site, perform perfonn the following steps: 2.3.1 Ensure all VA fans are off. NOTE: The action taken in the next step causes the VA system to be inoperable. TS 3.0.3 is applicable on both units 2.3.2 Depress the "INITIATE" pushbuttons on "TORNADO ISOL TRN A(B)" on 1MC-5 and 2MC-5 ensuring all automatic functions occur as expected. 2.4 Classify the emergency as appropriate per RP/0/A/5000/001 (Classification of Emergency) and commence notification and other protective measures as directed by appropriate Emergency Response Procedure. 2.5 Severe Weather InformationIForecast InfonnationIForecast To obtain the latest severe weather information/forecast infonnationlforecast for York County, consult the National Weather Service located in Greenville/Spartanburg, S.C. at (800) 268-7785 or (864) 879-1085 (unpublished). 2.6 Meteorological Conditions As a backup to the Catawba site meteorological system (i.e. wind speed, wind direction, etc.), consult the National Weather Service located in Greenville/Spartanburg, S.C. at (800) 268-7785 or (864) 879-1085 (unpublished). 2.7 WHEN conditions permit, pennit, coordinate a survey of plant structures and equipment to determine the extent of damage as follows: detennine 2.7.1 Following any incident or natural phenomenon event that is applicable to this procedure, a visual inspection of the ISFSI Vertical Concrete Cask (VCC) is required within 4 hours. This inspection is required by NAC-UMS Technical Specification A5.4. Perfonn Perform this inspection per Operations procedure PT/0/A/4600/031(NAC-UMS PT /0/A/4600/031 (NAC-UMS Cask Surveillance). 2.7.2 Notify personnel from lABIAE and Mechanical Maintenance to assist Operations in the evaluation of weather induced damage as necessary. 2.7.3 Notify Radiation Protection personnel to survey the Reactor, Auxiliary and Fuel Pool Buildings to ensure shielding integrity. 2.7.4 Notify Chemistry personnel to survey areas where damage may release dangerous chemicals (e.g. Sulfuric Acid Storage). 2.7.5 Record the findings of the survey in the associated unit's Nuclear Shift Supervisor log.

Enclosure 4.3 RP101AlSOOOI007 RP/O/A/50001007 Hurricane Winds On-Site Within 12 Hours Page S5 of5 2.7.6 Notify Maintenance to ensure debris is removed from the area near the VC system air intakes. {12} {12} 2.7.7 Notify Maintenance to ensure debris is removed from the area near the intake canallSNSWP. {17} canaVSNSVVP. 2.8 IF the survey identifies plant damage, perform the following: 2.8.1 Determine the emergency classification for current plant conditions. 2.8.2 Make required notifications. 2.9 Restore affected plant systems to normal operation per applicable site procedures. 2.10 IF an emergency has NOT been declared, notify York County Emergency Management about the event through the York County 911 Telecommunicator and as necessary, request emergency response support. {5} {S} NOTE: 1. A request for emergency response support (except an ambulance) from an off-site agency requires a 4-hour notification of the NRC as an "Off-site Notification" per RP/O/B/50001013 RP/O/B/SOOO/013 (NRC Notification Requirements).

2. A request for ambulance support for a "contaminated injury" is an 8-hour notification and the request for transport of a "clean injury" does not require a NRC notification.

_ _ 2.11 IF emergency response support from York County Emergency Management is requested AND an emergency has NOT been declared, notify the NRC under the 4-hour notification requirement for off-site notifications. NOTE: Permission for unit startup is required from FEMAlNRC after a plant shutdown due to a natural disaster that affects both the plant and the local government emergency response capability. 2.12 IF a unit restart is desired, consult site management for unit startup criteria. 2.13 This procedure remains in effect until the Duke Power Meteorological Group (704-594-0341) verifies that the threat of hurricane force winds to the Catawba Nuclear Site no longer exists. 2.14 IF an emergency has NOT been declared for this event AND the NRC has NOT been notified of this event, perform the following: A. Notify the duty Emergency Planner. B. Notify the Public Affairs duty person. C. Make a courtesy notification to the states and counties using Enclosure 4.7.

Enclosure 4.4 RP/O/ A/5000/007 RP/O/A/5000/007 Earthquake Page 1 of6

1. Immediate Actions NOTE: 1. Immediate Actions may be perfonned simultaneously.

2. The four Reactor Coolant Leakage Detection Systems are not seismically qualified and must be assumed to be inoperable following any seismic event. EMF38(L) can be verified to be operable based on power availability and sample pump operation.

3. Reactor Coolant Leakage Detection Systems are not required to be operable during Cold Shutdown.

4. Technical Specification 3.0.3 is entered until one of the Reactor Coolant leakage detection systems identified in step 1.1 is declared operable. {6}

5. An OAC Alann at point CID 2252 indicates that there has been a recording of an event by seismic instrumentation. This alarm alann is in addition to an event indicator and initiation by starter unit MIMT 5090.

1.1 Following any earthquake that is felt in the plant or is-recorded is recorded on instrumentation, including earthquakes smaller than OBE, declare all four Reactor Coolant Leakage Detection Systems (listed below) as inoperable: 1.1.1 Containment Floor and Equipment Sump Level and Flow Monitoring System 1.1.2 VUCDT Level Monitoring System) 1.1.3 EMF38(L) 1.2 Determine Detennine the operable status of 1(2)EMF38(L) from the Control Room by the following methods: 1.2.1 Perfonn a source check to verifY verify that power is available:

lEMF38(L)
2EMF38(L) 1.2.2 verify that the sample pumps are operational:

Visually verifY

                    *  "ON" indicating light for "lEMF38 "IEMF38 CONTAINMENT PAR" - LIT

One indicating light on "SAMPLE FLOW SELECT PANEL" (Unit 1) - LIT

                    *  "ON" indicating light for 2EMF 38 CONTAINMENT PAR" - LIT

One indicating light on "SAMPLE FLOW SELECT PANEL" (Unit 2) - LIT

Enclosure 4.4 RP/O/A/5000/007 Earthquake Page 2 of6 1.2.3 Verify the following annunciators - Dark:

                     *  "lEMF38 CONTAINMENT LOSS OF FLOW" (lRAD-l, D/4)
                        "IEMF38
                     *  "2EMF38 LOSS OF CONTAIN SAMPLE FLOW" (2RAD-l, E/3) 1.2.4       IF the EMFs are inoperable, apply the appropriate action statement for Technical Specification 3.4.15.

1.3 Perform the following while continuing in this procedure: {II} {14} 1.3.1 Notify the WWM or WCC SRO to perform an "(a) 4 risk assessment" utilizing the risk assessment tool. PRA code "OSSA ADWH" should be used for the duration of the event. 1.3.2 Based on the results of the assessment, implement risk management actions that do not interfere with other actions implemented by this procedure. 1.3.3 IF either unit is in Mode 5, 6, or NO MODE:

Protect and secure/prevent switchyard work
Protect and secure/prevent work on or near energized main power sources (transformers and associated systems)
Protect and secure/prevent work on available Diesel Generators {18}

NOTE: 1. Decision on Shutdown IF the OBE has been exceeded OR significant damage is found during operator walkdowns, the plant should be shutdown in an orderly manner for more detailed inspections. IF the plant has tripped under conditions which would warrant shutdown, the plant should remain shutdown for detailed inspections.

2. Pre-Shutdown Inspections Following a decision to shutdown the plant, but prior to initiating shutdown, visual inspections of essential safe shutdown equipment should be performed to determine its readiness. Other factors outside of the control of the plant that could affect the timing of the shutdown (e.g. availability/reliability of off site power), should also be evaluated at this time.

3. Normal Shutdown When plant capability to safely shutdown has been verified, normal shutdown would proceed. Under all circumstances the method and pace at which the Reactor is brought to a safe condition should continue to be based upon all instrumentation indications and the operator's judgment.

1.4 IF the Operational Bases Earthquake (OBE) Exceeded Alarm lAD-4, B/8, is received AND the effects of an earthquake are felt, immediately take the Unite Unites) s) to Hot Standby (Mode 3). For the initiation of any unit shutdown, carry out the reporting provisions of RP/O/B/5000/013, (NRC Notification Requirements).

Enclosure 4.4 RP/O/A/50001007 Earthquake Page 3 of6 1.5 IF the Operational Bases Earthquake (OBE) Exceeded Alann 1AD-4, IAD-4, B/8, is received AND the effects of an earthquake are felt, swap RN to the Standby Nuclear Service OP/OIA/64001006C (Nuclear Service Water System). Water Pond in accordance with OP/O/A/64001006C 1.6 Classify the emergency as appropriate per RP/O/A/50001001, (Classification of Emergency), and commence notification and other protective measures as directed by appropriate Emergency Response Procedure. 1.7 IF the FWST level is decreasing, verify valves 1(2)FW33A 1(2)FW33A and 1(2)FW49B 1(2)FW49B are closed. 1.8 Notify Chemistry to close both Unit 1I and Unit 2 NS Hx Chemical Wetlay-Up System isolation valves per OP/1(2)/A/64001064 OP/I(2)/A/64001064 (Addition of Chemicals to NS Wetlay-Up System). {7} {16} 1.9 WHEN appropriate, announce the impending condition over the plant PA System. 1.10 IF an emergency has NOT been declared, notify York County Emergency Management about the event through the York County 911 Telecommunicator and as necessary, request emergency response support. {5} NOTE: I. A request for emergency response support (except an ambulance) from an off-site 1. agency requires a 4-hour notification of the NRC as an "Off-site Notification" per RP/O/B/SOOOI013 RP10/BI50001013 (NRC Notification Requirements).

2. A request for ambulance support for a "contaminated injury" is an 8-hour notification and the request for transport of a "clean injury" does not require a NRC notification.

1.11 IF emergency response support from York County Emergency Management is requested AND an emergency has NOT been declared, notify the NRC under the 4-hour notification requirement for off-site notifications.

2. Subsequent Actions 2.1 Notify lAE to perfonn Data Retrieval and Interpretation using the Kinemetrics Seismic AM/O/B/S1 0010 10, "Kinemetrics Seismic Monitoring System Monitoring System per AMIO/B/51001010, Post Accident Data Collection." Section 3.0 of this enclosure is provided as a reference for seismic monitoring instrument locations.

2.2 IF the earthquake intensity is >O.lSg

                                        >0.15g horizontal OR >O.lg vertical (> Safe Shutdown IMIMT S070 Earthquake) as measured by 1MIMT        5070 (provided by lAB from step 2.1), shut down unites) the unite s) to Cold Shutdown (Mode S). 5). For the initiation of any unit shutdown, carry RP/O/B/SOOOIO 13 , (NRC Notification Requirements).

ofRP/0/B/50001013, out the reporting provisions of 2.3 Seismic verification may be obtained by calling the National Earthquake Infonnation Service at (303) 273-8S00. 273-8500. 2.4 All records made by accelerographs and recorders shall be evaluated to verify the extent of the earthquake.

Enclosure 4.4 RP/O/A/50001007 RP/OI A/SOOOI007 Earthquake Page 4 of6 2.4.1 Notify lAE to perform Data Retrieval and Plate Replenishment in the Engdahl IP/O/B/33411005, "Engdahl Seismic Monitoring Seismic Monitoring System per IP/O/B/3341100S, System Post Seismic Event Maintenance." Section 3.0 of this enclosure is provided as a reference for seismic monitoring instrument locations. 2.4.2 Notify MCE Civil Engineer that an analysis of the results from the etched plate evaluations is required per section 3.7.4.4 of the UFSAR. 2.5 2.S IF the earthquake was determined to be >OBE, Regulatory Compliance shall make a report to NRC Region II within 24 hours via telephone. (10CFR SO.72) 50.72) 2.6 IF the earthquake was determined to be <OBE but recorded on seismic instrumentation, Regulatory Compliance shall prepare and submit a special report to the NRC as defined in Selected Licensee Commitments (SLC) Section 16.7-2, Seismic Instrumentation, Testing Requirements, b. 2.7 WHEN conditions permit, coordinate a survey of plant structures and equipment (similar to normal daily rounds) to determine the extent of damage, as follows: 2.7.1 Following any incident or natural phenomenon event that is applicable to this procedure, a visual inspection of the ISFSI Vertical Concrete Cask (VCC) is required within 4 hours. This inspection is required by NAC-UMS Technical AS.4. Perform this inspection per Operations procedure Specification A5.4. PT/OIA/46001031(NAC-UMS Cask Surveillance). 2.7.2 Notify personnel from lAE and Mechanical Maintenance to assist Operations in the evaluation of damage as necessary. 2.7.3 Notify Maintenance to complete ice condenser inspection if required by MP/OIA/7150/142 (Ice Condenser Inspection for Ice Fallout due to Seismic MP/OIA/71S0/142 Disturbance) within 24 hours of seismic event. {{IS}IS} I Person Notified Date Time 2.7.4 Notify Radiation Protection personnel to survey the Reactor, Auxiliary and Fuel Pool Buildings to ensure shielding integrity. 2.7.5 2.7.S Notify Chemistry personnel to perform the following: A. Survey areas where damage may release dangerous chemicals (e.g. Sulfuric Acid Storage). 2.7.6 Record the findings of the survey in the associated unit's Nuclear Shift Supervisor Log.

Enclosure 4.4 RP/OI AlSOOOI007 RP/O/A/5000/007 Earthquake Page 5S of6 2.8 IF the earthquake exceeds OBE AND the survey identifies plant damage, perform the following: 2.8.1 Evaluate overall plant conditions and consider emergency classifications based on Emergency Coordinator's judgement. 2.8.2 Make required notifications. 2.9 Restore affected plant systems to normal operation per applicable site procedures. NOTE: Permission for unit startup is required from FEMAlNRC after a plant shutdown due to a natural disaster that affects both the plant and the local government emergency response capability. 2.10 IF a unit restart is desired, consult site management for unit startup criteria. 2.11 IF an emergency has NOT been declared for this event AND the NRC has NOT been notified of this event, perform the following: 2.11.1 2.ll.l Notify the duty Emergency Planner. 2.11.2 2.ll.2 Notify the Public Affairs duty person. 2.11.3 2.ll.3 Make a courtesy notification to the states and counties using Enclosure 4.7.

Enclosure 4.4 RP/O/A/50001007 Earthquake Page 6 of6

3. Station Seismic Monitoring Instruments Instrument # Location 1MIMT-5010 IMIMT-SOIO Peak Acce1erograph Accelerograph Cold Leg Accumulator 1A lA 1MIMT-5020 IMIMT-5020 Peak Accelerograph NC Pipe at PZR Surge Line IMIMT-5030 lMIMT-5030 Peak Accelerograph NIPump NIPumplA 1A NOTE: IMIMT-S040 IMIMT -5040 also provides input to Peak Shock Annunciator (pSA1575)

(PSAlS7S) 1MIMT-S040 IMIMT-S040 Spectrum Recorder RB Basement 0° 1MIMT-SOSO IMIMT-SOSO Spectrum Recorder PZR Lower Support 1MIMT-S060 IMIMT-S060 Spectrum Recorder Aux Bldg. S77 EL (PP-S6) NOTE: IMIMT-SOOO IMIMT -SOOO provides indication of OBE Exceeded on lAD-4, B/8 in Control Room ofOBE 1MIMT-SOOO IMIMT-SOOO Seismic Switch RB Basement 0° 1MIMT-S070 IMIMT-S070 Strong Motion Accelerograph RB Basement 0° 1MIMT-S080 IMIMT-S080 Strong Motion Accelerograph Annulus 619 EL 0° 1MIMT-S090 IMIMT-S090 Starter Unit for SMA-3 RB Basement 0° Seismic Instrumentation System Information Seismic switch 1MIMT-SOOO 1AD4/B8 for indication ofOBE IMIMT-SOOO provides a Control Room Annunciator lAD41B8 exceeded. 1MIMT S070lS080 receive a start signal from 1MIMT-S090. IMIMT S070/S080 lMIMT-S090. 1MIMT S070lS080 provide lMIMT S070/S080 magnetic tape recordings which must be played back on SMP-l SMP-1 to get a recording ofthe of the data to be analyzed. 1MIMT-S040 lMIMT-S040 provides Control Room indication of greater than 70% OBE (amber light) or greater 2S.4 Hz. than 100% OBE (red light) for certain frequencies between 2 and 25.4 1MIMT-S010IS0201S0301S0401S0501S060 IMIMT -SO 10/S020/S030/S040/S050/S060 contain removable scratch plates. These scratch plates provide indication of peak accelerations.

Enclosure 4.5 RP/O/A/50001007 RP/O/Al5000/007 Flooding Due to High Lake Level Page 1 of3 (Lake Elevation> 593.5 MSL) or Seiche (Lake Tidal Wave)

1. Immediate Actions NOTE: 1. Seiche is same as High Lake Level.

LeveL Immediate Actions may be performed simultaneously.

2. hnmediate 1.1 Should the lake level exceed 593.5 Ft MSL AND jeopardize the safe operation of the reactor, shut down the unites) to Hot Standby (Mode 3). For the initiation of any unit RP/O/B/5000/0 13 , (NRC Notification shutdown, carry out the reporting provisions of RP/O/B/50001013, Requirements). '.

1.2 Contact SPOC to close the Auxiliary Service Building rolling doors AR2 (Hot Tool Crib) and AR5 (Waste Shipping Area). IF the rolling doors are damaged to the extent 7W' barrier is installed across the door opening they cannot be closed, ensure a suitable 7lh." above the 594+0 Floor Slab until the door(s) can be repaired. 1.3 Ensure fuel handling operations are stopped. 1.4 IF a DIG is NOT available in modes 4, 5 or 6 to provide backup power for a potential loss of offsite power, evacuate the affected unit's containment. {13} 1.5 IF a unit is in Modes 5, 6 or No Mode, perform the following:

Ensure the Reactor Building Equipment Hatch is secured.
Ensure NC System level is greater than and maintained above 7.25% level (midloop operation).

1.6 RP/O/A/5000/001, (Classification of Classify the emergency as appropriate per RP/OIA/50001001, Emergency), and commence notification and other protective measures as directed by appropriate Emergency Response Procedure. 1.7 WHEN appropriate, announce the impending condition over the plant P PA A System. 1.8 IF an emergency has NOT been declared, notify York County Emergency Management about the event through the York County 911 Telecommunicator and as necessary, request emergency response support. {5}

Enclosure 4.5 101Al50001007 RP/O/A/SOOO/007 RP Flooding Due to High Lake Level Page 2 of3 (Lake Elevation> 593.5 MSL) or Seiche (Lake Tidal Wave) NOTE: 1. A request for emergency response support (except an ambulance) from an off-site agency requires a 4-hour notification of the NRC as an "Off-site Notification" per RP/O/B/50001013 (NRC Notification Requirements). RP/O/B/SOOO/013

2. A request for ambulance support for a "contaminated injury" is an 8-hour notification and the request for transport of a "clean injury" does not require a NRC notification.

1.9 IF emergency response support from York County Emergency Management is requested AND an emergency has NOT been declared, notify the NRC under the 4-hour notification requirement for off-site notifications.

2. Subsequent Actions 2.1 WHEN conditions permit, coordinate a survey of plant structures and equipment to determine the extent of damage as follows:

2.1.1 Following any incident or natural phenomenon event that is applicable to this procedure, a visual inspection of the ISFSI Vertical Concrete Cask (VCC) is required within 4 hours. This inspection is required by NAC-UMS Technical Specification AS.4. A5.4. Perform this inspection per Operations procedure PT/OIAl46001031(NAC-UMS Cask Surveillance). PT/O/A/4600/031(NAC-UMS 2.1.2 Notify personnel from IAE and Mechanical Maintenance to assist Operations in the evaluation of weather induced damage as necessary. 2.1.3 Notify Radiation Protection personnel to survey the Reactor, Auxiliary and Fuel Pool Buildings to ensure shielding integrity. 2.1.4 Notify Chemistry personnel to survey areas where damage may release dangerous chemicals (e.g. Sulfuric Acid Storage). 2.1.5 Inspect and clean debris from intake canallSNSWP. {17} 2.1.6 Record the [mdings findings of the survey in the associated unit's Nuclear Shift Supervisor Log. 2.2 IF the survey identifies plant damage, perform the following: 2.2.1 Evaluate the overall plant condition and consider emergency classifications based on Emergency Coordinator's judgment. 2.2.2 Make required notifications. 2.3 Restore affected plant systems to normal operation per applicable site procedures.

Enclosure 4.5 RP/OI RP/O/A/5000/007 A/50001007 Flooding Due to High Lake Level Page 3 of3 593.5 MSL) (Lake Elevation> 593:5 or Seiche (Lake Tidal Wave) NOTE: Pennission Permission for unit startup is required from FEMAlNRC after a plant shutdown due to a natural disaster that affects both the plant and the local government emergency response capability. 2.4 IF a unit restart is desired, consult site management for unit startup criteria. 2.5 IF an emergency has NOT been declared for this event AND the NRC has NOT been notified of this event, perfonn perform the following: 2.5.1 Notify the duty Emergency Planner 2.5.2 Notify the Public Affairs duty person. 2.5.3 Make a courtesy notification to the states and counties using Enclosure 4.7.

Enclosure 4.6 RP/O/A/50001007 RP/O/A/5000/007 Low Lake Level Page 1 of2 (Lake Elevation < 557.5 Ft. MSL)

1. Immediate Actions NOTE: Immediate Actions may be perfonned simultaneously.

1.1 Classify the emergency as appropriate per RP/OIA/50001001 RP/O/A/5000/001 (Classification of Emergency), and commence notification and other protective measures as directed by appropriate Emergency Response Procedure. 1.2 Lake level elevations below 557.5 FT. MSL shall be obtained from the Duke Power Company System Coordinator on the Control Room System Coordinator phone or at (704) 382-4413. 1.3 Should the lake level decrease below 550.4 Ft MSL AND jeopardize the safe operation of the reactor, shut down the unites) to Hot Standby (Mode 3). For the initiation of any ofthe ofRP/0/B/50001013 (NRC Notification unit shutdown, carry out the reporting provisions ofRP/0/B/5000/013 Requirements) . Requirements). 1.4 WHEN appropriate, announce the impending condition over the plant PA System. 1.5 IF an emergency has NOT been declared, notify York County Emergency Management about the event through the York County 911 Telecommunicator and as necessary, request emergency response support. {{5} 5} NOTE: 1. A request for emergency response support (except an ambulance) from an off-site agency requires a 4-hour notification of the NRC as an "Off-site Notification" per RP/O/B/5000/013 (NRC Notification Requirements). RPIOIB/50001013

2. A request for ambulance support for a "contaminated injury" is an 8-hour notification and the request for transport of a "clean injury" does not require a NRC notification.

1.6 IF emergency response support from York County Emergency Management is requested AND an emergency has NOT been declared, notify the NRC under the 4-hour notification requirement for off-site notifications.

2. Subsequent Actions 2.1 pennit, coordinate a survey of plant structures and equipment to WHEN conditions permit, detennine the extent of damage as follows:

2.1.1 Following any incident or natural phenomenon event that is applicable to this procedure, a visual inspection of the ISFSI Vertical Concrete Cask (VCC) is required within 4 hours. This inspection is required by NAC-UMS Technical Specification A5.4. Perfonn this inspection per Operations procedure PT/OIA/46001031(NAC-UMS Cask Surveillance). PT/O/A/4600/031(NAC-UMS

Enclosure 4.6 RP/O/A/SOOO/007 RP/O/A/5000/007 Low Lake Level Page 2 of2 (Lake Elevation < 557.5 Ft. MSL) 2.1.2 Notify personnel from IAE lAE and Mechanical Maintenance to assist Operations in the evaluation of weather induced damage as necessary. 2.1.3 Notify Radiation Protection personnel to survey the Reactor, Auxiliary and Fuel Pool Buildings to ensure shielding integrity. 2.1.4 Notify Chemistry personnel to survey areas where damage may release dangerous chemicals (e.g., Sulfuric Acid Storage). 2.1.S 2.1.5 Record the findings of the survey in the associated unit's Nuclear Shift Supervisor Log. 2.2 IF the survey identifies plant damage, perform the following: 2.2.1 Evaluate the overall plant condition and consider emergency classifications based on the Emergency Coordinator's judgement. 2.2.2 Make required notifications. 2.3 Restore affected plant systems to normal operation per applicable site procedures. 2.4 IF an emergency has NOT been declared for this event AND the NRC has NOT been notified of the event, perform the following: 2.4.1 Notify the duty Emergency Planner. 2.4.2 Notify the Public Affairs duty person. 2.4.3 Make a courtesy notification to the states and counties using Enclosure 4.7.

Enclosure 4.7 RP/O(Al5000/007 RP/O(A/5000/007 Courtesy Notification to States and Counties Page 1 of4 for a Non-emergency Plant Event NOTE: This enclosure provides instruction for notifying state and county emergency preparedness management agencies (primary WP/EOCs) WPIEOCs) and EnergyQuest of non-emergency plant events by completing a Courtesy Notification Form (page 4 of 4) and faxing it to each agency, then verifying its receipt with a follow-up phone call. {5} {S}

1. Complete the Courtesy Notification Form as follows:

1.1 Provide the time and date of:

Notification
Event 1.2 Mark the event(s) that describes the reason for the notification.

1.3 Describe the event briefly, especially any impact to the site (damage, impact on operations, and any requested support received from off-site agencies). NOTE: 1. The confirmation code number is randomly assigned to each message. This provides a method for authenticating an offsite agency official that calls the site over normal phone lines requesting additional information about the reported event. Knowing the confirmation code number shall be the authorization for site personnel to provide information about the event to the caller.

2. Calls received over selective signal lines are considered to be secure and do not require knowledge of the confirmation code number to receive additional information about the event.

1.4 Assign a 2-digit confirmation number to the notification form. 1.5 Print the name and title of the individual reporting the notification.

Enclosure 4.7 RP/O/A/50001007 Courtesy Notification to States and Counties Page 2 of 4 for a Non-emergency Plant Event NOTE: Step 2 sends a group fax and step 3 sends the fax to agencies individually.

2. Notification by Group Fax 2.1 Notify NotifY the states and county agencies (primary WP/EOCs)

WPIEOCs) of a non-emergency plant event(s) by completing a Courtesy Notification Form (page 4 of 4) and transmitting it to the states and counties as follows: NOTE: 1. Performing steps 2.1.1 through 2.1.3 sends the Courtesy Notification Form (page 4 of

4) to multiple locations in sequence.

2. Failure to press the preprogrammed buttons in a rapid sequence will result in sending the fax to only an individual agency.

2.1.1 Place the completed form (page 4 of 4) face down into the fax machine. 2.1.2 Press the pre-programmed one-touch speed dial pushbutton for each of the following agencies in quick succession (i.e., press each button in approximately one second intervals until completed). o [J York Co WP/EOC WPIEOC o [J Gaston Co. WP/EOC o [J MeckCo. Meek Co. WP o [J NC WP/EOC WPIEOC o [J SCWPIEOC SCWP/EOC o [J EnergyQuest o [J DukeECOC 2.1.3 Press START 2.2 Verify by one of VerifY the following means that the form (page 4 of 4) was received by each of ofthe the agencies: o [J Selective Signal (Enclosure 1.5, Emergency Response Telephone Directory) o [J Duke or Commercial Telephone (Enclosures 1.12 -1.20,

                                                                         - 1.20, Emergency Response Telephone Directory) 2.3     IF any agency did not receive the group fax, go to step 3 of this enclosure.

2.4 Fax a copy of the Courtesy Notification Form (page 4 of 4) to Emergency Planning at 3151. 2.5 Report any communications equipment failures to the duty Emergency Planner. {I} {l}

Enclosure 4.7 RP/O/A/5000/007 RP/O/A/50001007 Courtesy Notification to States and Counties Page 3 of 4 for a Non-emergency Plant Event

3. Notification by Individual Fax 3.1 WP/EOCs) of a non-emergency plant Notify the states and county agencies (primary WPIEOCs) event(s) by completing a Courtesy Notification Form (page 4 of 4) and transmitting it to the states and counties as follows:

NOTE: Performing steps 3.1.1 through 3.1.3 sends the Courtesy Notification Form (page 4 of 4) to individual agencies one at a time. 3.1.1 Place the completed form (page 4 of 4) face down into the fax machine. NOTE: SC WPIEOC WP/EOC and EnergyQuest list two fax numbers. Use the fax number for sending Emergency Notifications. 3.1.2 Enter the individual fax phone number (Enclosures 1.12 through 1.16 in the Emergency Response Phone Book) for the desired individual agency (WPIEOC). (WP/EOC). The Duke ECOC is listed in Enclosure 1.18. EnergyQuest fax number is listed in Enclosure 1.19. 3.1.3 Press START. 3.1.4 Repeat steps 3.1.1 through 3.1.3 until all of the desired agencies have been faxed the form (page 4 of 4). 3.2 Verify by one of the following means that the form (page 4 of 4) was received by the agency(s): D [J Selective Signal (Encl. (Enci. 1.5, Emergency Response Telephone Directory) D [J Duke or Commercial Telephone (Enclosures 1.12 -1.20, - 1.20, Emergency Response Telephone Directory) 3.3 Fax a copy of the completed Courtesy Notification Form (page 4 of 4) to Emergency Planning at 3151. 3.4 Report any communications equipment failures to the duty Emergency Planner. {I} {1}

Enclosure 4.7 RP/O/A/50001007 RP/O/A/5000/007 Courtesy Notification to States and Counties Page 4 of 4 for a Non-emergency Plant Event DUKE POWER COMPANY CATAWBA NUCLEAR STATION COURTESY NOTIFICATION FORM NON-EMERGENCY EVENTS TimelDate Of Notification: _ _ _ _ _ _ _ / _ _ _ _ _ _ __ TimelDate Of Event: _ _ _ _ _ _ _ _ _ / _ _ _ _ _ _ __ Event (X): _ Earthquake Toxic Gases _ Fatality Flood Civil Disturbance _ Fire Response by BethellNewport Hurricane Bomb Threat _ Medical Response by Ambulance Ice/Snow Vehicle Crash _ HazMat /Spill

Response

Tornado _ Explosion Other Events

== Description:==

Confirmation Code Number: (This number is authentication for any off-site agency caller to be given information about the event). Confirmation Phone Number: (803) 831-8185 Reported By: _ _ _ __ __ __ __ __ __ __ __ __

Title:

_ _ _ _ _ _ _ __

                                                         ------------------

Enclosure 4.8 RP/OIAlSOOOI007 Al50001007 Corrective Actions or Commitments Page 1I of 1 {I} {l} PIP C03-06681 C03-066SI {2} PIP C99-032IS C99-032I5 {3} PIP C03-03463 {4} PIP C03-0390I f-} {S} )) PIP 0-COO-OI689 0-COO-016S9 {6} PIP C03-03280 C03-032S0 {7} PIP COI-03239 {S} {8} PIP C04-02009 {9} PIP C04-04373 {1O} PIP C04-04924 {ll {ll}} PIP COS-00460 C05-00460 {I2} {12} PIP C04-03S38 C04-0353S {13} PIP COS-00843 C05-00S43 {I4} {14} C07-00S39 PIP C07-00839 {IS} {15} COS-03334, CA#I PIP C08-03334, {l6} {16} C05-03I79 PIP COS-03I79 {l7} {17} SOER 07-2, Commitments S, 5, 7, and S 8 {I8} {IS} PIP C08-0I77S COS-01775 {l9} {19} PIP C08-07I40 COS-07I40

I I

CATAWBA NUCLEAR STATION

 , I JOB PERFORMANCE MEASURE JPM IRIS ADMIN Calculate Reactor Vessel Head Venting Time CANDIDATE EXAMINER JPM 2R2S ADMIN                                Page 1 of 7

 , .                                         CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task        Calculate Reactor Vessel Head Venting Time Alternate DYES               DNO           ~N/A cgJ N/A              Time Critical   DYES cgJ   ~NO NO Path Evaluation                                                        Safety Function __         ~N/A cgJ N/A

[gJ cgj Simulator Din-Plant D Classroom Location Evaluation Validation 11 minutes [gJ cgj Perform DSimulate Method Time JPM Type ~ Bank cgJ DNew D Modified KIA GENERIC 2.1.7 (3.7/4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. Standard Reactor vessel head venting time calculated to be between 4.5 to 5.25 minutes. References EP/1/A/5000/FR-1.3 Response to Voids in Reactor Vessel, Enclosure 5 Candidate Start Time End Time ------ Duration Performance Rating D D Satisfactory D Unsatisfactory D Examiner (Printed Name) (Signature) (Date) Comments JPM 2R2S ADMIN Page 2 of 7

READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. SIMULATOR SETUP INITIATING CUE: A LOCA is in progress on Unit 1. The CR SRO directs you to calculate and record the maximum EP/11A15000/FR-1.3 Response to Voids in Reactor reactor vessel head venting time per Enclosure 5 of EP/1/Al5000/FR-1.3 Vessel. JPM 2R2S ADMIN Page 3 of 7

Start Time: _ __ LLJ ~ EP/1/A/5000/FR-1.3, EP/1/A15000/FR-1.3, Enclosure 5, Step 1 CRITICAL STEP Calculate A A =9500 X (P + 14.7) X 492 14.7 (T+460)

Where: P = Containment pressure (PSIG) T==Lower Containment temperature (OF) STANDARD SAT Calculate A UNSAT Determined NC pressure at any of the following:

Wide Range Containment Pressure Chart Recorders, #3 Pen, on 1MC-7.
Narrow Range Containment Pressure Chart Recorders, #1 Pen, on 1MC-9.
CNT Pressure Meters on 1MC-11 1NSP5060 and 1NSP5070.

EXAMINER CUE: Once indication location identified, show reading at 4 psig. (Range of 3.9 to 4.1 psig is acceptable.) Determine Lower Containment Temperature on any of the following:

meters on rearof1MC-31WP5090, rear of 1 MC-3 1WP5090, 1WP5110, 1WP5170, 1WP5190
Computer point P1501, Lower Containment Average Temperature -

Operating Units on the OAC. EXAMINER CUE: Once indication location identified, show reading at 150°F. Range at 145 to 155°F.

A = 9500 X (P + 14.7) X 492 14.7 (T+460)

3.9, 145 A = 9500 X (3.9 + 14.7) X 492 Using 3.9,145 = 9775.3

14.7 (145+460) Using 3.9, 155 A = 9500 X (3.9 + 14.7) X 492 = 9616.3

14.7 (155+460)

Using 4.1, 145 A = 9500 X (4.1 + 14.7) X 492 = 9880.4

14.7 (145+460)

Using 4.1, 155 A = 9500 X (4.1 + 14.7) X 492 = 9719.7

14.7 (155+460)

(A = 9616 to 9881 is acceptable) COMMENTS JPM 2R2S ADMIN Page 4 of 7

_~ ~. __J EP/1/A15000/FR-1.3, Enclosure 5, Step 2 EP/1/A/5000/FR-1.3, CRITICAL STEP Calculate B B= =(3 - H) X A Where H = Containment Hydrogen Concentration (%) STANDARD SAT Determine H2 concentration from the H2 Analyzer meters on Chart recorders, 1MICR5340, 1MICR5350, #2 Pen, on 1MC-7. _ _ UNSAT CUE: Once indication location identified, show needle reading 2. Range of 1.75 to 2.25. Using bounding values of A (9616 to 9881): B = (3 --- 2) X 9616 = 9616

      =(3 - 2) X 9881 =9881 B=(3-2)X9881 B                    =9881 (B range of 9616 to 9881 is acceptable)

COMMENTS l1.-J 2J EP/1/A/5000/FR-1.3, EP/1/A15000/FR-1.3, Enclosure 5, Step 3 CRITICAL STEP Determine C from the curve for the current NC system pressure. STANDARD _ _ SAT Determines NC pressure from PLASMA DISPLAY on 1MC-1 TRAIN A or B; or B W/R Pressure (1NCP5120) or C W/R Pressure (1NCP5140). UNSAT CUE: Once indication location identified, if B or C WR Pressure used, show needle reading 600 psig. If PLASMA is used state 600 psig is indicated. Range of 575 to 625 psig. Reads approximately 2000 SCFM from graph. (range of 1900-2100 SCFM is acceptable) COMMENTS JPM 2R2S ADMIN Page 5 of 7

~ EP/1/A/5000/FR-1.3, Enclosure 5, Step 4 Calculate T T= BIC = Venting time in minutes STANDARD SAT Using bounding values for Band C: _ _ UNSAT T = 96161 1900 = 5.06 minutes T = 9616/2100 = 4.58 minutes T = 98811 1900 = 5.20 minutes T = 9881/2100 = 4.71 minutes (4.5 - 5.25 (4 minutes, 30 seconds) to 5.25 (5 minutes, 15 seconds) is acceptable) COMMENTS TIME STOP: _ __ JPM 2R2S ADMIN Page 6 of 7

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIATING CUE: A LOCA is in progress on Unit 1. The CR SRO directs you to calculate and record the maximum reactor vessel head venting time per Enclosure 5 of EP/11A15000/FR-1.3 Response to Voids in Reactor Vessel. JPM 2R2S ADMIN

CATAWBA NUCLEAR STATION JOB PERFORMANCE MEASURE

                   ~2R2S AD~          '6 0 ..,-,\:
                                      '60  '-"

Determine the amount of boric acid required to get Control Bank D above the Rod insertion limits CANDIDATE EXAMINER JPM 2R2S ADMIN Page 1 of 7

CATAWBA INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task Determine the amount of boric acid required to get Control Bank D above the Rod insertion limits. Alternate Path DYES DNO IZl N/A Time Critical DYES IZl NO Evaluation D Simulator Din-Plant ~ Classroom Safety Function __ IZl N/A Location Evaluation Validation 25 minutes

             ~ Perform         DSimulate Method                                                            Time JPM Type    IZl Bank          DNew          o D Modified KIA         GENERIC 2.1.25 (3.9/4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. I (CFR: 41.10/43.5/45.12) 41.10 1 43.5 1 45.12)

Standard Candidate determines that rod insertion limit at 50% power using the Reactor Operating Data, R.O.D book, is 44-50 steps on Control Bank D. Performs calculation and determines that 493 - 578 gallons is the amount of boric acid required to be added to withdraw control bank D rods to that position. References AP/1/A/55001003 (Load Rejection) Rod Book sections 4.1, 5.5, 5.6.3 Candidate Start Time End Time ------ Duration Performance Rating D Satisfactory D Unsatisfactory Examiner (Printed Name) (Signature) (Date) Comments JPM 2R2S ADMIN Page 2 of 7

READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: Unit 1 operating at 100% power. Core burnup 250 EFPD. Boron concentration is 1020 ppm CURRENT CONDITIONS:

At 1030 today, Unit 1 experienced a Zone A lockout. The crew entered AP/11A155001003, Load Rejection.
At 1040, plant stabilization is in progress with the following conditions:

o Reactor power is 50%. o No dilutions are in progress. o 1AD-2, B/9 "Control Rod Bank Lo-Lo Limit" is LIT o Control rods are in manual. o Control Bank Positions: A= =226 steps B==226 steps

C = 126 steps

D = 10 steps INITIATING CUE: You have been directed to perform Enclosure 3, Rod Insertion Limit Boration, of AP/11A155001003, Load Rejection. Without any consideration for the effects of Xenon for rod insertion limits (RIL) requirements, calculate the MINIMUM gallons of boric acid addition required to meet RIL. The GAC OAC is unavailable. JPM 2R2S ADMIN Page 3 of 7

Start Time:-__ -_- U-J 0-J AP/1/55001003, Enclosure 3, Step 1.a If the control rods cannot be maintained above the rod insertion limits, then: Stop any dilutions in progress. STANDARD _ _ SAT Determines no dilutions are in progress based on the cue provided from initial conditions. _ _ UNSAT COMMENTS l1.-J ~ AP/1/55001003, Enclosure 3, Step 1.b CRITICAL STEP CAUTION Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6. NOTE OAC point C1 L4409 (Ctrl Bank Tech Spec Insertion Lmt Reached) and ROD Book (Section 2.2) provide rod insertion limit indication.

b. Borate NC system as required, to restore rods above insertion limits.

STANDARD SAT Student reads the caution and note in step 1.b and determines that ROD Book section 2.2 is needed. UNSAT EXAMINER NOTE: The procedure says to use Section 2.2 of the ROD book; however some students may use Figure 3 of the COLR. This is equally acceptable. If the student uses the COLR, the RIL could be based on the calculation included with the graph. If they use the ROD Book, it will be based solely on reading a graph.

If COLR is used, 2.3 X 50 - 69 = 46 steps on Bank D. If Rod Book Section 2.2 is used, range of 44-50 steps on Bank D. COMMENTS JPM 2R2S ADMIN Page 4 of 7

ll-J ~ AP/1/5500/003, Enclosure 3, Step 1.b CRITICAL STEP

b. Borate NC system as required, to restore rods above insertion limits.

STANDARD SAT Using 50 steps withdrawn on Bank D: UNSAT Uses RO.D. book section 5.6.3 pg 2 of 6 for IRW HFP, Eq Xe, Eq Sm, and uses data from the 200 EFPD column (176-250 EFPD), and determines:

Bank D 10 steps, rods are worth 1082 pcm
Bank D 44-50 steps, rods are worth 742 to 792 pcm for a difference of

      -340 to -290 pcm of reactivity.

Uses RO.D. book section 5.5 for HFP ARO and determines differential boron worth is -6.50 pcm/ppm.

Calculates -340/-6.50 = 52 ppm

                 -290/-6.50 = 45 ppm (45-52 ppm is acceptable)

Calculates final required boron concentration:

1020 ppm current [B] + 45 ppm = 1065 ppm final [B]
1020 ppm current [B] + 52 ppm = 1072 ppm final [B]

(1065-1072 ppm is acceptable) Uses table 4.1 in the RO.D. book for Hot RCS (Modes 1,2 and 3) to determine the gallon of boric acid to go from 1020 to the range of 1065-1072 ppm 1060 ppm to 1080 ppm = 211 gals 211/20ppm=1 211/20ppm=10.550.55 gals/ppm

                ~ 419 + 5 X 10.55 = 471 gal 1065 -7
                ~ 419 + 12 X 10.55 = 546 gal 1072 -7 (471 - 546) gallons is acceptable COMMENTS JPM 2R2S ADMIN                                                                     Page 5 of 7

~ AP/1/55001003, Enclosure 3, Step 1.c

c. Ensure compliance with Tech Spec 3.1.6 (Control Bank Insertion Limits).

STANDARD _ _ SAT Determines that the unit is NOT currently in compliance with 3.1.6. _ _ UNSAT COMMENTS TIME STOP: _ __ JPM 2R2S ADMIN Page 6 of 7

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS: Unit 1 operating at 100% power. Core burnup 250 EFPD. Boron concentration is 1020 ppm CURRENT CONDITIONS:

At 1030 today, Unit 1 experienced a Zone A lockout. The crew entered AP/11 Al55001003, AP/1/A/55001003, Load Rejection.
At 1040, plant stabilization is in progress with the following conditions:

o Reactor power is 50%. o No dilutions are in progress. o 1AD-2, B/9 "Control Rod Bank Lo-Lo Limit" is LIT o Control rods are in manual. o Control Bank Positions:

A = 226 steps

B = 226 steps

C = 126 steps

D = 10 steps INITIATING CUE: AP/1/A/55001003, You have been directed to perform Enclosure 3, Rod Insertion Limit Boration, of AP/11A155001003, Load Rejection. Without any consideration for the effects of Xenon for rod insertion limits (RIL) requirements, calculate the MINIMUM gallons of boric acid addition required to meet RIL. The GAC OAC is unavailable. JPM 2R2S ADMIN

Catawba 2006 Initial License Examination Job Performance Measure ADMIN SRO 2 CANDIDATE: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

            ------------------

EXAMINER: Admin S2.doc Page 1 of 8

Catawba Initial License Examination Job Performance Measure Task: Complete a DG Logbook Entry Per OMP 2-28 (DG Logbook). Alternate Path: No Facility JPM #: New KIA Rating(s): SAFETY FUNCTION: KIA: 2.1.18 (2.9/3.0) Ability to make accurate, clear and concise logs, records, status boards, and reports. Task Standard: Complete a DG logbook entry for 2B DG local start and locally load, RN-292B does not open. DG secured per procedure (Valid Failure). Preferred Evaluation Location: Preferred Evaluation Method: Control Room _ _ In-Plant X Perform X Simulate _ __ Procedure

References:

Operations Management Procedure 2-28 (DG Logbook). Validation Time: 10 Minutes Time Critical: No

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

Candidate: __ Time Start: _ _____ NAME Time Finish: _ __

                                                                                    ----

Performance Ratings: SAT _ __ UNSAT _ __ Question Grade _ __ Performance Time: -

                                                                                   - -----

Examiner: _ _ _ __ __ __ __ __ ____ ___

                                            ------------~/_----
                                            --------------~/_----

NAME SIGNATURE DATE

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

COMMENTS Admin S2.doc Page 2 of 8

Tools/Equipment/Procedures Needed: Operations Management Procedure 22RN-292B (2B DIG Hx Inlet Isol). READ TO OPERATOR DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. Information sheet: Unit 2 has suffered a loss of all AC power to 2ETB. An operator was sent to 2B DIG to start it AP/21N55001007 (Loss of Normal Power) enclosure 11 (Energizing 2ETB From DIG). per AP/21A155001007 During the performance of this enclosure 2RN-292B (2B DIG Hx Inlet Isol) would not open and the DIG was shutdown using procedural guidance. Initiating Cue: Complete the DIG logbook entries for this start attempt per OMP 2-28 (Diesel Generator Logbook) Attachments 10.1 and 10.2. Admin S2.doc Page 3 of 8

START TIME: _ __ _ _ EXAMINER NOTES: Provide the initiating cue, attached copies of OMP 2-28 attachments 10.1 & 10.2, and a copy of OMP 2-28 (DIG Logbook) .

          *** This JPM should be administered after Plant JPM     I. ***

STEP 1: Operator completes OMP 2-28, Attachment 10.1 as shown below. CRITICAL STEP STANDARD: See below. Operator answers are in ITALICS. The Critical Task is to _SAT determine that the DG start is a VALID FAILURE. _UNSAT EXAMINER NOTE: As the operator asks for information, provide the following cues.

**EXAMINER CUE: A copy will be routed to MCE by the Shift Support Tech.
**EXAMINER CUE: PIP number 06-09999 has been written.
**EXAMINER CUE: Ray Kaylor is the System Engineer.

DIESEL GENERATOR: 2B RECORDED BY Operator Name START ATTEMPT NUMBER: 168 DATE: Today's date PROCEDURE USED: 0 Other, Specify: API2IAl55001007 AP121A/55001007 (Loss of Normal Power) REASON FOR DIG OPERATION: 0 Other, Specify: Restore 2ETB TYPE OF START: 0 Non-Prelube TEST CLASSIFICATION: (See OMP 2-28, Sect. 6.) 0VALID FAILURE DIG Engine Start DatelTime: Today's Date I 20 minutes ago DIG Engine Shutdown DatelTime Today's Date I 20 minutes ago + 12 minutes Run Time (hrs) 0.2

*Total DIG Engine Yearly Run Time (hrs): 55 (from cue) + 0.2 = 55.2 Explain in detail the reason DIG operation was not a VALID SUCCESSlfailed to meet acceptance criteria: 2RN-292B (2B DIG Hx Inlet Isol) would not open (electrically or manually) and the DIG was shutdown using procedural guidance.

NOTE: If a VALID or INVALID failure, route copy to MCE. Per the cue REVIEW: Operators Name (CRSRO) PIP # per the cue CRSRO KaY/or Req'd if other than Valid Success SYS.ENG.lDesignee: Ray Kaylor

Notify Environmental Management if Total Run Time exceeds 260 hours per calendar year for any DIG. Note is not applicable.

COMMENTS: Admin S2.doc Page 4 of 8

STEP 2: Operator completes logbook entry on Attachment 10.2 Index Sheet.

                                                                                 -  SAT STANDARD: Operator completes Attachment 10.2 Index Sheet.
                                                                                  - UNSAT EXAMINER NOTE: After the operator completes Attachments 10.2 and 10.2, provide the following cue.
 **EXAMINER CUE: This JPM is complete.

This JPM is complete. STOP TIME: _ __ Admin S2.doc Page 5 of 8

CANDIDATE CUE SHEET (To Be Returned To Examiner Upon Completion Of Task) Information sheet: Unit 2 has suffered a loss of all AC power to 2ETB. An operator was sent to 2B DIG to start it per AP/21A155001007 (Loss of Normal Power) enclosure 11 (Energizing 2ETB From DIG). During the performance of this enclosure 2RN-292B (2B DIG Hx Inlet Isol) would not open and the DIG was shutdown using procedural guidance. Initiating Cue: Complete the DIG logbook entries for this start attempt per OMP 2-28 (Diesel Generator Logbook) Attachments 10.1 and 10.2. Use the following data: The start date is today's date. The start time was 20 minutes ago The DIG ran for 12 minutes. You are the SRO. Admin S2.doc Page 6 of 8

Operations Management Procedure 2-28 Attachment 10.1 Diesel Generator Sheet DIESEL GENERATOR_________ _ _ _ _ _ _ __ RECORDED BY ----------------- _ _ _ _ _ _ __ START ATTEMPT NUMBER _ _ _ _ __ DATE _ _ _ __ ____ __ __ __ __ __ ___ PROCEDURE USED: REASON FOR DIG OPERATION: D PT/1(2)/A/4350/002A(B) (DIG Operability Test) D Scheduled Surveillance OP/l(2)/A/6350/002 (DIG Operation) D OP/1(2)/A/6350/002 D Opposite Train Inoperable D Other, Specify: _____________ _ _ _ _ _ _ _ _ _ ___ D Functional Verification (Maintenance) D D Other, Specify: _ _ __ __ __ __ __ __ ___ TYPE OF START: TEST CLASSIFICATION: (See OMP 2-28, Sect. 6.) D Turbo Prelube D VALID SUCCESS D Non-Prelube D Time required to reach> 441 RPM (98% speed) and Frequency> 60 +/- 1.2 Hz _____ _ _ _ sec. OPERATING DATA: Time required: Voltage> 4160 +/- 420 volts _ ___

                                                          - - - - - - sec.

Time Load> 2875 KW - _______

                                                                                       - - - - - hrs.

D INVALID TEST D/G Engine Start DatelTime DIG Date/Time _ _ _ _ _ _ __ _ _________ D INVALID FAILURE D INVALID D/G Engine Shutdown DatelTime DIG _______ Date/Time _________ _ __ D VALID FAILURE Run Time (hrs) __________ _______ _ D/G Engine Yearly Run Time

Total DIG Hrs.

Explain in detail the reason DIG D/G operation was not a VALID SUCCESS/failed SUCCESSlfailed to meet acceptance criteria. NOTE: If a VALID VALID or INV ALID failure, route copy to MCE. INVALID REVIEW _ _ _ _ _ _ _ _ _ _ _ PIP # _ _ _ _ _ _ _ _ _ _ (CRSRO) CRSRO SYS.ENG.lDesignee _ SYS.ENG./Designee __ __ __ ___ __ ____ ___ __ __ ____ Req'd if other than Valid Success

NotifY Notify Environmental Management if Total Run Time exceeds 260 hours per calendar year for any DIG.

Admin S2.doc Page 7 of 8

Operations Management Procedure 2-28 Attachment 10.2 Index Sheet D/G _ _2B_ _ Start # Date Test Classification Run Time Hrs. Yearly PIP # Run Time Hrs. 166 07/01/2006 VALID SUCCESS 1 54 NA 167 08/01/2006 VALID SUCCESS 1 55 NA

Admin S2.doc Page 8 of 8}}

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