ML023100411

Final - Section a Operating

ML023100411
Person / Time
Site:	Limerick
Issue date:	10/04/2002
From:	Wasong A Exelon Nuclear
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-352/03-302, 50-353/03-302, ES-301, ES-301-1, NUREG-1021, Rev 8 50-352/03-302, 50-353/03-302
Download: ML023100411 (49)

Text

Rev 2 Rev. 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Generating Station Date of Examination: 10/07/02 Examination Level SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A. 1 Process computer 2.1.19 (3.0) Ability to use plant computer to obtain and evaluate parametric information on system or component status JPM: Evaluate jet pump operability License 2.1.1 (3.8) Knowledge of conduct of operation requirements Maintenance JPM: Determine status of license from working hour records A.2 Safety Systems 2.2.10 (3.3) Knowledge of the process for determining the proposed Status change, test, or experiment increases the probability of occurrence or consequences of an accident during the change, test, or experiment JPM: Determine required compensatory actions for barrier breach (SRO ONLY)

A.3 Release Controls 2.3.3 (2.9) Knowledge of SRO responsibilities for auxiliary systems that are outside the control room JPM: Determine compensatory actions for a failed radiation monitor prior to a planned liquid release (SRO ONLY)

A.4 Emergency Plan 2.4.41 (4.1) Knowledge of emergency action level thresholds and classifications JPM: Evaluate plant conditions and determine EAL (SRO ONLY)

NUREG-1021, Revision 8 21 of 26

Rev 2 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: 10/07/02 Exam Level: SRO(I)

Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

a.

Manual Depressurization of RHR (Alternate Path - Drain Valve NAS 2

trips on thermals)

b.

Operate RCIC Full Flow test CST to CST (Alternate Path - Test NAS 4

valve pressure locks)

c.

Venting Primary Containment (OT-1 01) (Alternate Path - High Rad NAS 5

alarm annunciates)

d.

Control Rod Exercise Test (ST-6-107-760-*)(Alternate Path - Rod NAS 1

stuck)

e.

Shutdown D14 Diesel Generator MS 6

f.

Bypass Isolations and Restore RECW (ON-1 13)

DS 8

g.

Establish Main Condenser Vacuum Using the 2 nd Stage SJAE NSL 9

B.2 Facility Walk-Through

a.

Install SLC Squib Valve Bypass Line DR 1

b.

Defeat HPCI and RCIC High Temperature Isolation DR 4

c.

Supply Emergency DIV 1 Power to RCIC Inboard Isolation Valve DR 6

Rev. 1

"' Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

Rev 2 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: 10/07/02 Exam Level: SRO(U)

Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

a.

Operate RCIC Full Flow test CST to CST (Alternate Path - Test NAS 4

valve pressure locks)

b.

Venting Primary Containment (OT-101) (Alternate Path - High Rad NAS 5

alarm annunciates)

c.

Establish Main Condenser Vacuum Using the 2nd Stage SJAE NSL 9

d.

e.

f.

g.

B.2 Facility Walk-Through

a.

Install SLC Squib Valve Bypass Line DR 1

b.

Supply Emergency DIV 1 Power to RCIC Inboard Isolation Valve DR 6

C.

NUREG-1021, Revision 8

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA 22 of 26

EXELON NUCLEAR TITLE: DETERMINE STATUS OF LICENSE FROM WORKING HOUR RECORDS TASK PERFORMED BY:

EVALUATOR SIGNATURE:

DIRECTIONS TO EVALUATOR:

None EVALUATOR:

DATE:

EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

15 MINUTES IMPORTANCE RATING(S):

3.7/3.8 SYSTEM NUMBER(S):

2.1.1 Knowledge of conduct of operation requirements

REFERENCES:

OP-AA-1 05-102, NRC ACTIVE LICENSE MAINTENANCE TASK STANDARD(S):

Determine that the license status is inactive due to insufficient hours stood AI-2 Page 3 of 7 A1-2 Page 3 of 7

I EXELON NUCLEAR TASK CONDITIONS:

A reactor operator has stood the following shift schedule over the last three months:

Date Hours Position 10/01 6

RO 10/19 12 RO 11/21 12 PRO 11/29 6

PRO 12/15 12 RO 12/17 4

PRO 12/31 12 RO INITIATING CUES:

Determine the status of the Reactor Operator's license and whether he may stand the watch as RO today, January 2 "d.

AI-2 Page 4 of 7 A 1-2 Page 4 of 7

F EXELON NUCLEAR Critical Element(s) indicated by "*" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT (CUE)

Provide copy of OP-AA-105-102, NRC ACTIVE LICENSE MAINTENANCE

1.

The quarterly shift watch requirement Determine that the dates with 6 and 4 may be completed with a combination hour watches do not count toward the of complete 8 and 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts minimum requirements

• 2.

Evaluate the watchstanding record for Determine that the required seven 8 meeting the minimum number of 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> watches were NOT stood hour shifts

• 3 Evaluate the watchstanding record for Determine that the required five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> meeting the minimum number of 12 watches were NOT stood hour shifts

• 4 Determine the status of the license Determine the license is inactive and the operator may NOT take shift.

(CUE: You may stop here, you have met the N/A N/A termination criteria for this JPM.)

A1-2 Page 5 of 7 A 1-2 Page 5 of 7

I EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT AI-2 Page 6 of 7 A1-2 Page 6 of 7

I EXELON NUCLEAR TASK CONDITIONS:

A reactor operator has stood the following shift schedule over the last three months:

Date Hours Position 10/01 6

RO 10/19 12 RO 11/21 12 PRO 11/29 6

PRO 12/15 12 RO 12/17 4

PRO 12/31 12 RO INITIATING CUES:

Determine the status of the Reactor Operator's license and whether he may stand the watch as RO today, January 2nd.

CANDIDATE

EXELON NUCLEAR TITLE: PARTIAL PROCEDURE PREPARATION TASK PERFORMED BY: _EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

1. Provide copy of ST-6-001-761-1 at the beginning of the JPM

2. Provide copy of A-3 or access to A-3 once the cues have been given EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

15 MINUTES IMPORTANCE RATING(S):

2.5 SYSTEM NUMBER(S):

2.2.11

REFERENCES:

A-3, TEMPORARY CHANGES TO APPROVED PROCEDURES AND PARTIAL PROCEDURE USE TASK STANDARD(S):

Procedure steps for BPVs 1-8 marked out A.2R0 Page 3 of 7 A.2 RO Page 3 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. Unit 1 is in OPCON 1

2. ST-6-001-761-1 is to be re-performed for the No. 9 Bypass Valve only

3. The reason for the performance of the ST is for post-maintenance testing

4. All other bypass valves are operable INITIATING CUES:

The Control Room Supervisor has directed you to prepare ST-6-001-761-1, MAIN TURBINE BYPASS VALVE EXERCISING for partial execution on the No. 9 Bypass Valve up to the point where it is ready for SQR review.

A.2R0 Page 4 of 7 A.2 RO Page 4 of 7

F EXELON NUCLEAR Critical Element(s) indicated by "`" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT (CUE): Provide copy of ST and copy of A-3 to candidate

"*1. The preparer shall enter "PARTIAL" on "PARTIAL" entered on the cover sheet the first page

• 2.

Preparer shall mark out unnecessary Step 4.3.3 BPV 1-8 marked out with steps, sections or pages...

lineouts or "X"

3.

... and initial and date each mark out Initials and date entered next ot the marked out steps

2.

Preparer shall mark out unnecessary (Restoration) BPV 1-8 steps, sections or pages...

marked out with lineouts or "X"

3.

... and initial and date each mark out Initials and date entered next to the marked out steps

4.

Preparer shall enter name, initials and Name, initials, and date entered in the date in the procedure comments comments section of the cover sheet section. (i.e. prepared by: name, initials, date)

(CUE: You may stop here, you have met the N/A N/A termination criteria for this JPM.)

Page 5 of 7 A 

t.-I.

"-*,J

EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A.2 KU Page 6 of 7 A.2 RO Page 6 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. Unit 1 is in OPCON 1

2. ST-6-001-761-1 is to be re-performed for the No. 9 Bypass Valve only

3. The reason for the performance of the ST is for post-maintenance testing

4. All other bypass valves are operable INITIATING CUES:

The Control Room Supervisor has directed you to prepare ST-6-001-761-1, MAIN TURBINE BYPASS VALVE EXERCISING for partial execution on the No. 9 Bypass Valve up to the point where it is ready for SQR review.

CANDIDATE

EXELON NUCLEAR TITLE: EVALUATE JET PUMP OPERABILITY TASK PERFORMED BY:

EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

Provide attached copies of blank ST and PMS screens at the beginning of the JPM EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

15 MINUTES IMPORTANCE RATING(S):

SYSTEM NUMBER(S):

3.0/3.0 2.1.19

REFERENCES:

ST-6-043-320-1, DAILY JET PUMP OPERABILITY VERIFICATION FOR TWO RECIRCULATION LOOP OPERATION TASK STANDARD(S):

Determine that the surveillance is failed

/41-7 Page 3 of 7 A.7-7 Page 3 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. The following were observed on Unit 1:

"* Unexplained drop in reactor power

"* Unexplained rise in core flow indication

2. ON-100 Jet Pump Failure has been entered

3. Permission to start ST-6-043-320-1 has been obtained INITIATING CUES:

You are directed to perform ST-6-043-320-1 and report the results Al-I Page 4 of 7 A1-1 Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by "'" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/U NSAT J Examiner provide PMS computer screen shots and blank ST to candidate.

Examiner refer to marked-up ST key.

"*1.

Determine if Loop A flow is within 10%

Determine that loop "A" is not within the of the loop flow values on the limits established pump speed-loop flow characteristics curve

2.

Determine if Loop B flow is within 10%

Determine that Loop "B" is within the of the loop flow values on the limits established pump speed-loop flow characteristics curve

• 3.

Determine if the value of total core Determine that total core flow is not flow is within 10% of the established within the limits Total Core Flow value derived from Recirc Loop Flow Measurements

• 4.

Determine if Loop A jet pump diffuser-Determine that some jet pumps on Loop to-lower plenum differential pressure "A" are not within the limits is within 10% of the established patterns

5.

Determine if Loop B jet pump diffuser-Determine that all jet pumps on Loop "B" to-lower plenum differential pressure are within the limits is within 10% of the established patterns 1

F-71 Page 5 of 7

EXELON NUCLEAR STEP STANDARD SAT/UNSAT

• 6 Verify at least two of the step Determine that three areas are combinations in the surveillance are unsatisfactory and the ST results are satisfactory:

Unsatisfactory 4.3.1.3 and 4.3.2.3 (Pump speed vs drive Report the unsatisfactory results flow) 4.3.3.4 (Total loop flow vs total core flow) 4.3.4.4. and 4.3.5.4 (Indiv JP DP vs Drive Flow)

CUE: (You may stop here. You have reached the termination criteria for this JPM)

Al-I Page 6 of 7 A1-1 Page 6 of 7

EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A7-'1 Page 7 of 7

EXELON NUCLEAR I

TASK CONDITIONS:

1. The following were observed on Unit 1:

"* Unexplained drop in reactor power

"* Unexplained rise in core flow indication

2. ON-100 Jet Pump Failure has been entered

3. Permission to start ST-6-043-320-1 has been obtained INITIATING CUES:

You are directed to perform ST-6-043-320-1 and report the results CANDIDATE

vNORM=A i CTMTNORMAL 016-I f-0.6 MA E R

L W RANGE REACTOR PRE3SSURE NM 1034 PSIG 900 1060 Group Point Display I

Change Group Group Data Display on LG1 PA M Group Definition U

List Groups Group Number:

Group Name:

RECIRC Group Status:

ACTIVE Current Engineering Low High Point ID Description Status Value Units Plot Limit Plot Limit 8037 (19)

A RECIRC PMP Al(DRIVE) FLOW m

17.063 HLB/H 0.000 L20.000 (20)

(21)

(22)

(23)

A RECIRC

• RECIRC

• RECIRC A RECIEC (24) A RECIRC (25) 3 RECIRC (26) 3 RECZRC A RECIRC PUMP B RECIRC PUMP P P2 (DRIVZ)

PXP BI(DRIVE)

PMP B2 (DRIVE)

LOOP Al TEMP LOOP A2 TEMP LOOP B1 TEMP LOOP B2 TEM SPEWD SPEED FLOW FLOW FLOW 11 21242 REACTOR CORE FLOW 12 13 14 is 16 17 17.063 13.688 13.688 527.5 527.5 527.4 527.4 78.585 78.165 MLSIN HLB/H a3/H DEOF DEGF DEGF DZGF PERCENT PERCENT 0.000 0.000 0.000 270.0 270.0 270.0 270.0 18.000 18.000 MM 73.308 NLB/ER 0.000

.4

,.1 4

.4Z 20.000 20.000 20.000 570.0 570.0 570.0 570.0 102.000 102.000 125.000 is 19 CANDIDATE 20 07.40:36 PS-PRINT I

'.SYSTEM-S-NORMAL LI3MRICK I FWD BW 13-AUG-02 1

2 3

4 5

6 7

1 9

10 B038 3039 B040 B055 B056 B057 3058 E1266 E1267 7:40:52

PV NORMAL NTMT NORMAL B016 iR A

~WIDE RANGE REACTOR PRESSURE NML 1048 PSIG 960 1060 Group Point M

Change Group Display

- Group Data Display on LG1 PA Group Definition M

List Groups Group Number:

£ Group Name:

JET PUMP D/P'S ("Z-SHIFT ST)

Group Status:

ACTIVE Current Engineering Low High Point ID Description Status Value Units Plot Limit Plot Limit 1

2 3

4 5

SINGLE SINGLE SINGLE SINGLE SINGLE TAP DP TAP DP TAP DP TAP DP TAP DP 4

6 7

8 10 12

13 15 E1084 E1103 E1105 81247 E1249 E1255 31257 E1259 E1263 E1265 E1037 E1097 E1104 E1235 E1254 E1248 E1256 E1258 E1260 E1264 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 TAP TAP TAP TAP TAP TAP TAP TAP TAP TAP NML NML NML NML NML NML NML NML NML WML NML NML

• MEL NKL NML DP DP DP DP DP DP DP DP DP DP 31.416 31.323 29.318 30.552 31.756 33.422 29.873 28.330 30.861 31.756 31.413 31.599 28.650 30.481 31.009 33.244 28.557 31.319 4.306 4.488 o~~~~~~ooo~~~~~~

i

........................]i2*i.llil o ~ o 0.000 mz 100.000 0.000 100.000 0.000

.100.000

0. 000 J~ 100.000 0.00 oo*"

iiiiiiiii.i*

100__

L o.000 0.000 I100.o000 0.000 100.000_

0.000 100.000 0.000

.100.000 0.000 j100.000

6

6

6

6

6

6 9'

6 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000

%SYSTEM-S-NORMAL FWD B

w- --

.100.000 a-bý100.000 100.0 0 0 I................

I...............

1 0 0.0 0 0 i~ii~i'iiii~iiii*...ii~~iii1-00o.000 16100.000 I.......... ~ ~...

,i OO OO J100.000 MONK-100.0 00

~E7~~7§100.000 177 p100.000

.~ ~ ~ ~ ~

LIMERICK 1 13-AUG-02 7:04 JET PUMP JET PUMP JET PUMP JET PUMP JET PUMP 6 SINGLE TAP DP "7 SINGLE TAP DP 8 SINGLE TAP DP 9 SINGLE TAP DP 10 SINGLE TAP DP 16 17 18 19

20 11 12 13 14 15 16 17 18 19 20 07:30:39 JET JET JET JET JET JET JET JET JET JET JET JET JET JET JET PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PUMP PS-PRINT CANDIDATE SINGLE SINGLE SINGLE SINGLE SINGLE SINGLE SINGLE SINGLE SINGLE SINGLE

EXELON NUCLEAR__

TITLE: DETERMINE OFFGAS EFFLUENT ACTIVITY RELEASE RATE TASK PERFORMED BY:

-EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

1. Provide copy of GP-5, "STEADY STATE OPERATIONS" at the start of the JPM

2. Provide calculator to candidate if needed EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

15 MINUTES IMPORTANCE RATING(S):

2.7 SYSTEM NUMBER(S):

2.3.11

REFERENCES:

GP-5, "STEADY STATE OPERATIONS" TASK STANDARD(S):

Average pre-treatment release rate calculated to be 4619 to 5105 (4862 +/- 5%)

Page 3 of 7 A



/-.0.

,.1 'U

I EXELON NUCLEAR TASK CONDITIONS:

1.

2.

3.

4.

Unit 1 is in OPCON 1 RR-26-1 R601 "A" SJAE Discharge Rad Monitor reads 110 mRem/hr RR-26-1R601 "B" SJAE Discharge Rad Monitor reads 131 mRem/hr FR-69-*15 (scfm) Point 2 Reads 35 scfm The following placard is mounted to the 1 0C600 panel:

U/1 OFF GAS SUM OF SIX 5060 K"A" 1.18 K" B" 1.13 DATE:

10/6/02 INITIATING CUES:

The CRS has directed you to calculate the average offgas pre-treatment radioactivity release rate per GP-5, "STEADY STATE OPERATIONS" A.3 KU Page 4 of 7 A.3 0O Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by "' in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT

1. CALCULATE Off-gas release rates for N/A the A AND B channels using the following equation:

RR = RL x F x K Where:

RR = Release Rate for A(B)

(pCi/second)

RL = Radiation Level of SJAE as indicated on RR-26-*R601 (mRem/hour)

F = Off-gas flow as indicated by FR-69-*15 (scfm), Point 2 Conversion Factor for A(B) data (posted on panel *0C600)

2. Channel A (Point 1)

Calculate "A" channel release = 4543 RR =_

._mRem/hour x

CFM x Kuci/sec 110 x 35 x 1.18 = 4543 RR = _

Ci/second

3. Channel B (Point 2)

Calculate "B" channel release = 5181 RR =

mRem/hour x GCFM x _K uci/sec 131 x 35 x 1.13 = 5181 RR = _

Ci/second A.3R0 Page 5 of 7 A.3 RO Page 5 of 7

EXELON NUCLEAR STEP STANDARD SAT/UNSAT

• 4. CALCULATE the average of the A Calculate the average release rate AND B channel values to obtain the average Off-gas pretreatment release rate as follows:

ARR= (4543 +5181)/2 = 4862 uCi/sec ARR = (RR "A") + (RR "B")

2 Where:

Acceptable band is 4619 to 5105 (4862

+/- 5%)

ARR = Average Off-gas Pretreatment Release Rate (gCi/second)

RR "A" = Release Rate value for "A" Channel (pCi/second)

RR "B" = Release Rate value for "B" Channel (piCi/second)

ARR =

) +

2 ARR =

liCi/second (CUE: You may stop here, you have met the N/A N/A termination criteria for this JPM.)

Page 6 of 7 A.15 KU

EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A



Page 7 of 7

.^A.,

rx"{

EXELON NUCLEAR I

TASK CONDITIONS:

1. Unit 1 is in OPCON 1

2. RR-26-1R601 "A" SJAE Discharge Rad Monitor reads 110 mRem/hr

3. RR-26-1R601 "B" SJAE Discharge Rad Monitor reads 131 mRem/hr

4. FR-69-'1 5 (scfm) Point 2 Reads 35 scfm The following placard is mounted to the 10C600 panel:

UlI OFF GAS SUM OF SIX 5060 K"A" 1.18 WK1319 1.13 DATE:

10/6/02 INITIATING CUES:

The CRS has directed you to calculate the average offgas pre-treatment radioactivity release rate per GP 5, "STEADY STATE OPERATIONS" CANDIDATE

EXELON NUCLEAR TITLE: DETERMINE EMERGENCY ACTION LEVEL TASK PERFORMED BY:

(SRO ONLY) EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

1. Provide ERP-101 or access to the procedure at the beginning of the JPM EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

15 MINUTES (Time Critical)

IMPORTANCE RATING(S):

SYSTEM NUMBER(S):

4.1 2.4.41

REFERENCES:

ERP-101, CLASSIFICATION OF EMERGENCIES TASK STANDARD(S):

Site Area Emergency identified A.4 SRO Page 3 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. Unit 1 has been scrammed due to LOCA

2. The mechanical vacuum pump was started and caught fire. The fire burned for 20 minutes before being extinguished

3. All rods are inserted

4. RPV level is - 60 inches

5. Drywell pressure is 45 psig and rising

6. Drywell post - LOCA monitors read 30 R/hr INITIATING CUES:

This is a time critical JPM You are directed to classify the event and give the reason for the classification A.4 SRO Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by "'" in Performance Checklist.

PERFORMANCE CHECKLIST:

Note: Begin the 15 minute time limit after the candidate has reviewed the task conditions STEP J

STANDARD SAT/UNSAT

1.

Review Emergency Action Levels for Select Fire (8.2) and Fission Product categories selected Barrier (3.0) EALs

2.

Classify the event based on selected Determine the classification based on categories and most severe EALs the fire is limited to an Unusual Event

• 3 Classify the event based on selected Determine the most severe EAL is Site categories and most severe EALs Area Emergency based on Reactor Coolant System loss and Primary Containment Potential loss within 15 minutes (CUE: You may stop here, you have met the N/A N/A termination criteria for this JPM.)

A.4 Sl-C)

Page 5of7 A. 4 S.H Page 5 of 7

EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A.4.SRO Page 6 of 7 A. 4 SRO Page 6 of 7

EXELON NUCLEAR TASK CONDITIONS:

1.

2.

3.

4.

5.

6.

Unit 1 has been scrammed due to LOCA The mechanical vacuum pump was started and caught fire. The fire burned for 20 minutes before being extinguished All rods are inserted RPV level is - 60 inches Drywell pressure is 45 psig and rising Drywell post - LOCA monitors read 30 RPhr INITIATING CUES:

This is a time critical JPM You are directed to classify the event and give the reason for the classification CANDIDATE

EXELON NUCLEAR TITLE: DETERMINE COMPENSATORY ACTIONS FOR BARRIER BREACH TASK PERFORMED BY:

EVALUATOR SIGNATURE:

DIRECTIONS TO EVALUATOR:

1. Provide A-C-134 at the start of the JPM (SRO ONLY) EVALUATOR:

DATE:

EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

15 MINUTES IMPORTANCE RATING(S):

3.3 SYSTEM NUMBER(S):

2.2.10

REFERENCES:

1. A-C-134, CONTROL OF HAZARD BARRIERS

2. A-C-134-5, CONTROL OF HAZARD DOORS/HATCHES/PANELS AT LIMERICK GENERATING STATION TASK STANDARD(S):

Barrier breach identified as requiring Tech Spec compensatory actions A

9 jq. L-cfl-(LJ Page 3 of 7 A.Z-Orvu Page 3 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. OPCON 1

2. Door 73 on the Unit 2 177' elevation of Unit 2 has been damaged and cannot be closed.

Maintenance has reported that the door must be removed and a new hinge welded in place.

3. No barrier breach permit currently exists for this door

4. Maintenance has reported that the repairs are expected to take four days due to parts availability INITIATING CUES:

Determine any required actions to support Door 73 being propped open for repair and the most limiting Limiting Conditions for Operation due to the above conditions.

A.2-SRO Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by "*" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP J

STANDARD (CUE): Provide A-C-1 34 and A-C-1 34-5

1.

(Step 7.4.2) Review Barrier Breach Book to determine if a BBP exists for this breach

2.

If a BBP does not exist for a door/hatch breach, Shift shall:

3.

Return door/hatch to its closed position

4.

If breach is in a security barrier, contact Security 5

If door/hatch can not be closed, review Exhibit A-C-1 34-5 [LGS] or Exhibit A-C-1 34-6 [PBAPS]....

• 6 to determine what compensatory measures are needed for the breach (CUE: You may stop here, you have met the termination criteria for this JPM.)

N/A N/A N/A N/A Review A-C-I134-5 and determine that door 73 is a hazard door Determine that a fire watch must be posted Determine that "2A" and "2C" RHR Pumps must be declared inop Determine that the most limiting required actions are to restore the door to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (LCO 3.6.2.3 - SP Cooling)

N/A A 9AC

Page 5 of 7 N/A N/A A"1 o.--QJ!\\n.

I

I EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A ' C'rr

Page 6 of 7

/.-OM*P[

I EXELON NUCLEAR I

TASK CONDITIONS:

1. OPCON 1

2. Door 73 on the Unit 2 177' elevation of Unit 2 has been damaged and cannot be closed.

Maintenance has reported that the door must be removed and a new hinge welded in place.

3. No barrier breach permit currently exists for this door

4. Maintenance has reported that the repairs are expected to take four days due to parts availability INITIATING CUES:

Determine any required actions to support Door 73 being propped open for repair and the most limiting Limiting Conditions for Operation due to the above conditions.

CANDIDATE

EXELON NUCLEAR TITLE: LIQUID RAD RELEASE INOP MONITOR ACTIONS TASK PERFORMED BY:

(SRO ONLY) EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

1. Provide access to Offsite Dose Calculation Manual (ODCM) at start of JPM EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

ANY APPROXIMATE COMPLETION TIME:

15 MINUTES IMPORTANCE RATING(S):

2.9 SYSTEM NUMBER(S):

2.

3.3 REFERENCES

LGS Offsite Dose Calculation Manual LGS ST-5-061-570-0, RADWASTE DISCHARGE PERMIT TASK STANDARD(S):

Determine that radwaste discharges may continue provided the ODCM or ST compensatory actions are taken A

' Cr

I"i.

/

Page 3 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. Radwaste and Chemistry are preparing to make a liquid radwaste discharge to the cooling tower blowdown line

2. Radwaste effluent rad monitor 00S368 has been inoperable for the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> INITIATING CUES:

You are directed to determine the actions necessary if the release is to proceed, and any time limits associated with those actions A. 3-SRO Page 4 of 7 A. 3-SRO Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by "'" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT ODCM 3.2.2 Determine that the monitor is required per the ODCM and the minimum

1. Locate ODCM Liquid Effluent Monitors required channels is one. (Note-There is section. Gross Radioactivity Monitors only one monitor installed)

Providing Automatic Termination of Release Liquid Radwaste Effluent Line

2.

Action 100-With less than the Determine that Action 100 applies and Minimum Required Channels releases may continue for 14 days operable, effluent releases may continue for up to 14 days provided that prior to initiating a release...

"*3.

At least two independent samples are Determine that two independent analyzed in accordance with Table chemistry samples of the effluent are 13.2-3, and required

• 4.

At least two technically qualified Determine that two chemistry members of the facility staff technicians are required to verify the independently verify the release rate calculations and two operators are calculations and discharge line valving required to verify the valve lineup (CUE: You may stop here, you have met the N/A N/A termination criteria for this JPM.)

A. 3-SRO Page 5 of 7 A.3-SRO Page 5 of 7

I EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT jq.J-'KU Page 6 of 7 A.L -,bZi(J Page 6 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. Radwaste and Chemistry are preparing to make a liquid radwaste discharge to the cooling tower blowdown line

2. Radwaste effluent rad monitor 00S368 has been inoperable for the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> INITIATING CUES:

You are directed to determine the actions necessary if the release is to proceed, and any time limits associated with those actions CANDIDATE

EXELON NUCLEAR Review page from ODCM (Delete after review)

A-3 SRO ODCM Excerpt TABLE 13.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT

1.

Gross Radioactivity Monitors Providing Automatic Termination of Release

a.

Liquid Radwaste Effluent Line

b.

A/B RHR Service Water Effluent Line *

2.

Gross Radioactivity Monitors Not Providing Automatic Termination of Release

a.

Service Water Effluent Line 3

Flow Rate Measurement Devices

a.

Liquid Radwaste Effluent Line

b.

Discharge Line MINIMUM CHANNELS_

OPERABLE ACTIONT 1

1/loop 1

1

-v Termination of the release is accomplished by auto trip remote manual closure of isolation valves.

of the RHRSW pumps and ACTION STATEMENTS Action 100-With less than the Minimum Required Channels operable, effluent releases may continue for up to 14 days provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Table 13.2-3, and

b.

At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

100 101 101 102 102

• T*

I EXELON NUCLEAR__

TITLE: INITIATE SITE EVACUATION TASK PERFORMED BY:

EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

1. Provide ERP-120 at the start of the JPM EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

SIMULATOR APPROXIMATE COMPLETION TIME:

15 MINUTES IMPORTANCE RATING(S):

2.9 SYSTEM NUMBER(S):

2.4.29

REFERENCES:

ERP-120, STATION EVACUATION TASK STANDARD(S):

Alarm activated for entire plant and announcement made to evacuate to Pottstown Limerick Airport A

A nr

/i.- f+

U Page 3 of 7

EXELON NUCLEAR TASK CONDITIONS:

1. A Site Area Emergency drill has been declared

2.

Drill conditions require a site evacuation to the Pottstown Limerick Airport

3. Individuals will exit via the front gate INITIATING CUES:

The Control Room Supervisor has directed you to sound the site evacuation alarm for the entire plant and make the plant announcement for evacuation per ERP-1 20, STATION EVACUATION, Step 2.3.1 A.4 KU Page 4 of 7 A.4 0O Page 4 of 7

EXELON NUCLEAR Critical Element(s) indicated by "`" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT

1.

Set the Siren tone generator to the Switch set to SIREN SIREN (Preferred) Position

• 2.

Pull out "EVACUATION ALARM AND Set switch to PLANT ALARM and push RIVER WARNING SELECT" switch back in to sound the alarm located on MCR Panel 00C650 AND rotate to desired position THEN push selector switch in A. CONT 1 - Sounds alarm in Unit 1 primary containment only.

B. CONT 2 - Sounds alarm in Unit 2 primary containment only.

C. PLANT ALARM - Sounds alarm in entire plant.

3.

Sound alarm for approximately 30 Sound alarm for approximately 30 seconds seconds

• 4.

Return "EVACUATION ALARM AND Switch selected to OFF RIVER WARNING SELECT" switch to "OFF" position to silence alarm.

A A r¶%

ti. 1

(

M U Page 5 of 7

EXELON NUCLEAR STEP I

STANDARD SAT/UNSAT

• 5. WHEN alarms are silent, THEN announce Announcement made per the script with over the Priority Page System:

the following critical elements:

"ATTENTION ALL PERSONNEL. THIS Exit via the front gate (IS/IS NOT) A DRILL. THIS (IS/IS NOT A

° Re-assemble at the Pottstown DRILL). A SITE EVACUATION HAS BEEN Limerick Airport ORDERED BY THE EMERGENCY DIRECTOR. DESIGNATED It is not critical that the other portions are EMERGENCY RESPONSE PERSONNEL exactly verbatim REPORT TO ASSIGNED ASSEMBLY NOTE:

AREA OR FACILITY. ALL OTHER PERSONNEL EVACUATE THE SITE The procedure requires the Operator IMMEDIATELY. EVACUATING to repeat the alarm and PERSONNEL SHALL:

announcement. The JPM is terminated in the next step following A. EXIT THE PAB VIA THE TSC GUARD the FIRST announcement STATION EXIT LANES B. EXIT THE SITE VIA (THE FRONT GATE USING EVERGREEN ROAD AND/OR THE BACK GATE USING LONGVIEW ROAD).

C. REASSEMBLE AT (CROMBY GENERATING STATION/OR POTTSTOWN-LIMERICK AIRPORT)_

THIS (IS/IS NOT) A DRILL. THIS (IS/IS NOT) A DRILL."

(CUE: You may stop here, you have met N/A N/A the termination criteria for this JPM.)

A.4 RO Page 6 of 7 A.4 RO Page 6 of 7

EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT A A On~

Page 7 of 7

/"t. "*' F'* %./

EXELON NUCLEAR TASK CONDITIONS:

1. A Site Area Emergency drill has been declared

2. Drill conditions require a site evacuation to the Pottstown Limerick Airport

3. Individuals will exit via the front gate INITIATING CUES:

The Control Room Supervisor has directed you to sound the site evacuation alarm for the entire plant and make the plant announcement for evacuation per ERP-120, STATION EVACUATION, Step 2.3.1 CANDIDATE