Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML16085A249
Person / Time
Site:	FitzPatrick
Issue date:	02/25/2016
From:	David Silk; Operations Branch I
To:	Kelly D; FitzPatrick
Shared Package
ML15195A060	List: ML15201A472; ML16055A001; ML16063A251; ML16081A077; ML16081A159; ML16081A169; ML16081A192; ML16081A201; ML16085A246; ML16085A247; ML16085A248; ML16085A249; ML16145A369; ML16145A383;
References
	TAC U01932
	Download: ML16085A249 (255)
	v • d • e

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD APPL. TO JPM NUMBER Pump REV: DATE: NRC KIA SYSTEM NUMBER: _2_.2_._13_(._4_.1..._)- - - - -

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE:

- - - Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRIN"f.ED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD APPL. TO JPM NUMBER Pump Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD APPL. TO JPM NUMBER Pump I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-OP-102, Protective and Caution Tagging B. FM-27A and FM-27B C. OP-25 Ill. TOOLS AND EQUIPMENT

None IV. SET UP REQUIREMENTS A. Ensure copies of the following references are available:

EN-OP-102

FM-27A and FM-27B (full size)

OP-25 V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this .task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Maintenance is required on CRD pump A.

C. The maintenance activity will be intrusive to the impeller casing for impeller replacement.

D. eSOMS is unavailable.

-3 of 8-

RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD Pump

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Generate a tagout isolation boundary for CRD pump A maintenance. Record the devices to be tagged and their required positions on the worksheet provided. Record additional amplifying instructions that are required, if any, in the space below."

STEP STANDARD EVALUATION I COMMENT

1. Obtain required references. Obtains and utilizes required references, which may SAT I UNSAT include:

EN-OP-102

FM-27 A and/or FM-278

OP-25 EVALUATOR NOTE: Component names and Required Position terminology may vary slightly from what is written below due to unavailability of eSOMS.

2. Determine CRD pump A control switch Identifies CRD pump A control switch should be tagged in SAT I UNSAT tagged position. the green flag after stop position.

EVALUATOR NOTE: The CRD pump A control switch

.doe!:? not have a pull-to-lock P._osition.

3. Determine CRD pump A breaker Identifies CRD pump A breaker (71-11516) should be CRITICAL STEP tagged position. tagged in the racked out or removed position. SAT I UNSAT

4. Determine CRD pump A discharge Identifies CRD pump A discharge isolation valve (03CRD- CRITICAL STEP isolation valve tagged position. 176A) should be tagged in the closed position. SAT/UNSAT

-4 of 8-

RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD Pump STEP STANDARD EVALUATION I COMMENT

- . - CRITICAL STEP

5. Determine CRD pump A suction Identifies CRD pump A suction isolation valve (03CRD-isolation valve tagged position. 153A) should be tagged in the closed position. SAT/UNSAT

6. Determine CRD pump A minimum flow Identifies CRD pump A minimum flow isolation valves CRITICAL STEP isolation valves tagged position. (03CRD-177 A and 03CRD-154A) should be tagged in the SAT I UNSAT closed position.

7. Determine CRD pump positive Identifies CRD pump positive pressure seal isolation CRITICAL STEP pressure seal isolation valve tagged valve (03CRD-39) should be tagged in the closed SAT/UNSAT position. position.

8. Determine CRD pump A venting path Identifies tagging one or more of the following paths for CRITICAL STEP tagged position. venting CRD pump A casing: SAT I UNSAT

CRD pump A suction pressure indicator root valve (03CRD-163) open with the pressure indicator removed/uninstalled.

CRD pump A suction pressure relief valve (03CRD-RV14A) gagged open.

CRD pump A suction from SLC system isolation valve (03CRD-88A) open (with cap removed).

May also list casing vents 03CRD-416A 1 or A2 .

EVALUATOR NOTE: Only one vent or drain path is required by procedure.

-5 of 8-

RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD Pump STEP STANDARD EVALUATION I COMMENT

9. Determine this tagout includes high Determines that with CRD pump B running, the discharge SAT I UNSAT energy. isolations for CRD pump A are exposed to high energy

(>500 psig) (may reference EN-OP-102 Section 3.0[15]).

10. Determine need for double valve Determines the discharge of CRD pump A should have SAT/UNSAT protection. double valve protection due to CRD pump B providing high energy (may reference EN-OP-102 Attachment 9.2 Section 5.1 ).

11. Determine availability of double valve Determines double valve protection can only be provided SAT I UNSAT protection and compensatory actions. by taking credit for check valves (03CRD-36A and

..03CRD-37A). -

Indicates that to use check valves as isolation boundary (may reference EN-OP-102 Attachment 9.2 Section 2.8):

Shift Manager concurrence must be obtained .

All individuals working under the tagout shall be informed of the risk.

The risk needs to be listed in the hazards section of the tagout.

EVALUATOR: Terminate the task at this point.

Task Standard: Tagout isolation boundary for CRD pump A developed including components and required positions.

-6 of 8-

HANDOUT Initial Conditions:

The plant is operating at 1OOo/o power.

Maintenance is required on CRD pump A.

The maintenance activity will be intrusive to the impeller casing for impeller replacement.

eSOMS is unavailable.

Initiating Cue:

Generate a tagout isolation boundary for CRD pump A maintenance.

Record the devices to be tagged and their required positions on the worksheet provided.

Record additional amplifying instructions that are required, if any, in the space below .

-7 of 8-

WORKSHEET Component ReQuired Position

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 S/RO TASK TITLE: Manually Compute Average Drywell Air C001 Temperature APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.1.20 (4.6/4.6)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 16-1 TASK TITLE: Manually Compute Average Drywell Air S/RO C001 Temperature APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2of11-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 16-1 TASK TITLE: Manually Compute Average Drywell Air S/RO C001 Temperature APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-40C, Computer Out Of Service Surveillance Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Prepare a copy of ST-40C completed up to step 8.3.4.

B. Provide Drywell temperature readings on ST-40C Attachment 3 to match selected portions of the Evaluator Key provided in this JPM pre-filled in.

C. Student handout only has RTD used "x'd" and the READING column filled in.

D. Student handout does NOT include SUM OF WEIGHTING FACTORS, CORRECTED VALUES, SUM OF CORRECTED VALUES and AVERAGE DRYWELL TEMPERATURE calculation.

V. . EVALUATOR NOTES

A. None VI. TASK CONDITIONS A. EPIC is out of service.

B. ST-40C, Computer Out Of Service Surveillance, is complete up to step 8.3.4.

-3 of 11-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to complete ST-40C section 8.3, Drywell Temperature Check, and record your results in the space below."

EVALUATOR: Provide the candidate with the in-progress copy of ST-40C.

STEP STANDARD EVALUATION I COMMENT

1. Determine average drywell Calculates and records CORRECTED VALUES on SAT I UNSAT temperature by performing the Attachment 3 (see provided key).

following using Attachment 3:

Multiply the recorded READING by the WEIGHTING FACTOR and record the result under CORRECTED VALUE.

2. IF the READING for any Calculates and records sum of all used WEIGHTING SAT/UNSAT DRYWELL AREA was FACTORS on Attachment 3 (see provided key).

recorded as "none" on Attachment 3, THEN perform the following:

Record the sum of all the used WEIGHTING FACTORS in the SUM OF USED WEIGHTING FACTORS block.

-4 of 11-

STEP STANDARD EVALUATION I COMMENT

3. Record the sum of all the Calculates and records sum of all CORRECTED VALUES SAT I UNSAT CORRECTED VALUES in the on Attachment 3 (see provided key).

SUM OF CORRECTED VALUES block.

4. IF no DRYWELL AREAS had Determines one Drywell Area reading was "none" and SAT I UNSAT a READING recorded as determines this step is n\a.

"none", THEN perform the following ...

5. Determine average drywell Calculates and records average Drywell temperature on CRITICAL STEP temperature by dividing the Attachment 3 (see provided key). SAT/UNSAT SUM OF CORRECTED VALUES by the SUM OF USED WEIGHTING FACTORS and record the result as the AVERAGE DRYWELL TEMPERATURE on Attachment 3.

6. Determine average drywell Reports average drywell temperature is above the allowable CRITICAL STEP temperature is above the value of 135°F. SAT I UNSAT allowable value of 135°F.

-5 of 11-

STEP STANDARD EVALUATION I COMMENT EVALUATOR: For RO candidates, terminate the task at this point.

EVALUATOR: For SRO candidates, provides the following additional conditions and cue (and associated handout):

Initial Conditions:

The plant is operating at 100% power.

You are the CRS.

Initiating Cue:

Assess the results of ST-40C Step 8.3.

Determine any required actions.

Report your findings in the space below.

6. SRO Only Determines Acceptance Criteria 10.1.4 is NOT met. CRITICAL STEP Assesses Acceptance Criteria SAT/UNSAT 10.1.4.

7 SRO Only Determines surveillance is unsatisfactory. CRITICAL STEP Determines required actions. SAT I UNSAT Determines need to notify Operations Manager (or alternate).

Determines CR must be written.

Determines EOP-4, Primary Containment Control, must be entered.

-6 of 11-

STEP STANDARD EVALUATION I COMMENT

7. *Determines Technical Specification 3.6.1.5 Condition A CRITICAL STEP (cont.) must be entered (requires restoring to within limit within 8 SAT I UNSAT hours).

EVALUATOR NOTE: Only the portions of this step marked with an (*)are deemed critical for grading.

EVALUATOR: Terminate the task at this point.

Task Standard: Drywell Temperature check performed in accordance with ST-40C Section 8.3 with calculation revealing Drywell temperature is high out of allowable value.

-7 of 11-

EVALUATOR'S KEY DRYWELL R'TD READING WEJ:GHTING CORRECTED VALUE AREA FACTOR 16-la'TD-

-: .:-'.. -=- (t.:"' 33 J..:f:

1 - *-*.,

"f ,,.. ..........

.:,.t;::;i"-

22 .

"- . -* . 3560 3 .1313 4 ....,, ;:,;;; .(1470 51 5 - --* "::"

l. 3 ?. . 534 7

6 --- 2. .; -:1 .0715 7 135 0. 062!

65 SOM OF CORRECTED VALUES:

P,,.:::~."'"' :1... .. ,:,;:,, :d:

-r -- --

EVALUATOR NOTE: The candidate may round the CORRECTED VALUE entries. An acceptable range for the SUM OF CORRECTED VALUES is 119.9-120.4°F. An acceptable range for the AVERAGE DRYWELL TEMPERATURE is 135.2-135.8°F.

EVALUATOR'S KEY

-8of11-

HANDOUT Initial Conditions:

EPIC is out of service.

ST-40C, Computer Out Of Service Surveillance, is complete up to step 8.3.4.

Initiating Cue:

The CRS directs you to complete ST-40C section 8.3, Drywell Temperature Check, and record your results in the space below.

-9 of 11-

COMPUTE~ OCT O? SERVICE SDF~EILLANCE ;37-4 1 :f 1 DRYWELL RTD READING WEIGHTING CORRECTED VALUE AREA FACTOR 16-lRTD-0 ) l(il !'11) !:e J.11:3 0 l ::o 1 1(1_: l 3:1 0.1 x 11 St

- 103 137 0.3 l

--: J. 4 3 ) (1

=

_! 13E .1313 l t 4 ( l 1)7 133 0.047 Z) l 5

} l 9 133 0. 4 x 17 6 ) 11 l ";,:J.

..J

0.0715 x 111 7 ( ) 11:: 135 0.0 l

": lH:

SUM OF USED WEIGHTING FACTORS:

SUM OF CORRECTED VALUES:

AVERAGE DRYWELL TEMPERATURE:

<., l _;

J. )

cf

ADDITIONAL SRO ONLY HANDOUT Initial Conditions:

The plant is operating at 1OOo/o power.

You are the CRS.

Initiating Cue:

Assess the results of ST-40C Step 8.3.

Determine any required actions.

Report your findings in the space below.

-11 of 11-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.1.5 (2.9/3.9)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 20/25 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 16-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required [gl None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 16-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-OM-123, Fatigue Management Program Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure sufficient copies of EN-OM-123, Fatigue Management Program, are available for the number of candidates.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A Reactor Operator has called out sick for Friday, August 31, Day Shift.

The following is the recent work hour history and upcoming schedule for three Reactor Operators. Their hours worked were and are in the Main Control Room during Mode 1, except for the training week.

Dayshift 6:00 am - 6:00 pm Nightshift 6:00 pm - 6:00 am Training 6:30 am - 2:30 pm The schedules show the day that each work shift begins.

-3 of 16-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER RO - Dave Jones M T w Th F Sa Su Week of August 20 D D D D N N Week of Auqust 27 N N D? D D Week of September 3 D D D Week of September 10 T T T T Week of September 17 N N N RO - Bob Smith M T w Th F Sa Su Week of August 20 N N N N Week of Auqust 27 T T T T D? N N Week of September 3 N N D Week of September 1O D D D D Week of September 17 N N N N RO-Jim Doe M T w Th F Sa Su Week of Auqust 20 ' T T T T Week of Auqust 27 D D D D D? N Week of September 3 N N N N D Week of September 10 D D D Week of September 17 T T T T

-4 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations

CRITICAL STEP VII. INITIATING CUE Inform the candidate of the following:

"Evaluate the work hour history for each of the three Reactor Operators. Determine which operators can take the scheduled watch for a full dayshift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months today, Friday, August 31 (and still be eligible for future scheduled shifts).

If applicable, describe the conditions that would make any operator(s) ineligible to work.

Consider all days after August 31 as scheduled shifts. Consider all days before August 31 as actual worked shifts."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of EN-OM- Obtains a controlled copy of EN-OM-123. SAT I UNSAT 123.

EVALUATOR: Provide working copy.

-5 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations STEP STANDARD EVALUATION I COMMENT

2. [1] Work hour limits for individuals Reviews limitations of EN-OM-123. SAT I UNSAT performing Covered Work consist of three concurrent components:

maximum ceilings, minimum breaks, and minimum days off (MOO).

[2] The maximum ceilings which apply at all times are a maximum of: - -

(a) 16 work hours in any 24-hour period, (b) 26 work hours in any 48-hour period, and (c) 72 work hours in any 7-day period.

[3] The minimum break times which apply at all times are a minimum of:

(a) 10-hour break between successive work periods, except that an 8-hour break is allowed when necessary to accommodate a crew's scheduled transition between work schedules or shifts, and (b) 34-hour break in any 9-day period.

[4] The MOO that applies when the plant is on-line:

54-hour rolling average

-6 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations STEP STANDARD EVALUATION I COMMENT

3. Evaluate Dave Jones for overtime. Determines Dave Jones can work the shift. CRITICAL STEP SAT I UNSAT NOTE: The candidate must indicate that Dave Jones is eligible, but does not need to provide an explanation.

See attached key for example.

4. Evaluate Bob Smith for overtime. Determines Bob Smith can NOT take the shift because CRITICAL STEP he would exceed the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period and\or SAT/UNSAT NOT having a 34 hr break in any 9 day period.

NOTE: The candidate must indicate why Bob Smith is not eligible, but does not have to match the above description exactly. See attached key for example.

5. Evaluate Jim Doe for overtime. Determines Jim Doe can work the shift. CRITICAL STEP SAT/UNSAT NOTE: The candidate must indicate that Jim Doe is eligible, but does not need to provide an explanation.

See attached key for example.

EVALUATOR: Terminate the task at this point for RO Candidates.

Provide SRO Candidates with the additional SRO Only Handout once they have completed the above section.

-7 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations STEP STANDARD EVALUATION I COMMENT Additional SRO Only Information:

Disregard the previous JPM results.

An operator is currently at their Work Hour Limitation.

This operator is needed to cover Shift.

This additional Shift would result in that operator to exceed Work Hour Limits.

Additional SRO Only Cue:

Inform the Candidate, "Determine the required actions to allow this individual to cover the Shift to meet Technical Specification staffing requirements.

Document your findings in the space below."

6. I SRO Only I SRO Only 1 CRITICAL STEP SAT/UNSAT Determine the required actions to allow Determines EN-OM-123 requires the following actions to an Operator to cover the shift. allow an Operator to cover the shift:

Must complete EN-OM-123 Attachment 9.7, EVALUATOR NOTE: Waiver Basis and Approval The Candidate may list individual

Must complete EN-OM-123 Attachment 9.8, requirements vice listing Attachment Covered Worker Capability Assessment numbers. Reference the EVALUATOR ATTACHMENT at the end of this JPM to see the requirements of EN-OM-123 EVALUATOR NOTE: The Candidate may also specify Attachments 9. 7 and 9.8. that a Condition Report must be generated. This is part of completing Attachment 9. 7.

EVALUATOR NOTE: The Candidate may also specify that a face-to-face fatigue assessment must be performed. This is part of completing Attachment 9.8.

EVALUATOR: Terminate the task at this point for SRO Candidates.

Task Standard: Attachment 9. 7 and 9.8 of EN-OM-123 are identified to allow the operator to cover shift.

-8 of 16-

EVALUATOR'S KEY Eligible for Day Shift on Reactor Operator August 31? If not eligible, describe reason:

(circle Yes or No)

Dave Jones GNo Jim Doe GNo Exceeds 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day Bob Smith YesE) period and\or not having a 34 hr break in any 9 day period.

(or similar)

EVALUATOR'S KEY

-9 of 16-

EVALUATOR'S ATTACHMENT

=Entergy NUCLEAR MANAGEMENT MANUAL No~""1l"'Y ~<.fa"~

..\l'OJtlJl\t<"fCfl,l;i- ~~

EN-OM-123 PAGE I

51'.> OF REV 12 Fatigue Management Program ATUCH!rtENT &. 7 REFER TO PROCEDURE SECTION 5.ll A. ADVERSE CON[}ITION REQUIRING A WAIVER lCh'3:~: ai:1:i'h::a~ box a:r:l dBscrih£. ci~-umsta"1C4?'S

=i NE-essary to mtigate or preven: a ccrditC11 ad'<<'rse safety [Defnilion 3 (1.8]

~ Public cw sta:frm pe!s.cnnf?~ be-atth or safe-ty is p:ioardize:t

.J Re:D\'2.I fr0m a ~ha!.enge ~o the sa'ery function ol a system or o:imponenr is de'a)-ed.

.J Coripl1a11ce v>>tth ar;olh"r NRC re2ulalory r;,qu1.,,ment is i'Clpai'E<l or pre-,'£'n10:J.

J t..-ii::9atz::in cl a Tec..'"'1nica! Si:;<EdfK:atbn r.f<q..Jimd reaciGr shuidC"Wfl o .. p:+iter r-educLon impaired or pre:vented~

.J Uni'.kanned mcrease in the plant sta:us nsk c.o~x ass.t;mrnenl

J CG"'lp!iance vvth site e-nvircnmental p.:?rrrt1s is impaired or pmven1ed

.J Et:temal evf!lnts h~tea~her fire, .,..isk to statr:in p.ersoone ,

Descr"ibe circumslanoos and ba 5ts for Date i Tme - - - - - - - -

D ~Je :ess.ary 'or s;K;urity [De'rn t.icm ~ ilB(

'] Co:npliance with the $1:£' secwrity pl;;n 1s 1rrpairoo or pre-vemE<:i.

J Fatur'2 ~o 111~ement a ro~poosatory ITI5'£JEJJfe creat?s a condition s:h'e~se10 safer;;*

De-sc'1De tirc:.t~tatices .and basis ;or .a;:ipro*/a!: - - - - - - - - - - - - - - - - -

Date/ Time*

B. SCOPE OF WORK (brief descnptr.:fl of work to he psrfonmed uoo<?' this wa:-.rer'.1 C. AUTHORIZATION Use of ~'Vet",i-er is apPfV*1ed fa;-r the +oikPNing time j::er;;:>:t t-noi to e-xc~ 14 calendar days)

EFective Oat' i tar*B: E>::::::~cratOO Date i tr,m.e - - - - - - -

Approw*ed: --------*------*--**-***-

!SVP or GMPO:

~Enl&JJY tfOOLEAR MAlllAGEJ.IENT MAlllUAL tf.cjfll-Ql.IA.tf":Y ilrlfl-eo liif-o<<1it>'!u:'+t-'J. use EN-OM-123 PAGE I

~7 REV 12 OF 00 Fatigue Management Program D. CONOmON REPORTING

lni:iale a Condition Report for use of a waiver

Attsoh this Fon"l in !he C*;:w1drtion LfE*Ecrinr.<e*n

Proce!?d !D \f.2 for assessmentls'i ~

Th"' of lh 's CR ;s ID documoo1 ".:Qf'B<:tive ac:tioos tha! may be needed to a*::Jd r"'ss there

-.vas margin in or V#Orl-: schedules. tc* ad-::iress the -wnex;:iec~ed situa::ion the 1.1s-e of waivers. Too eva!ua,ion *:>ondit>::.n adverse 10 desc.ri OOd in Secboo A .

...,--ou&:i be the subject of a oop.arate CR if reqwred. based on proc'8dures EVALUATOR'S ATTACHMENT

-10 of 16-

EVALUATOR'S ATTACHMENT Ar

~E

- - :.nlergy NUCLEAR MANAGEMENT l'!ioN..fJ!.i,llJ.r"Y ~U-'e.t! EN-01111*123 I REV 12 M-4N\JAL ~l"Oft~'*Totf,\i 1.!S! f'll.GE 5llOF Fatigue Management Proqram REFER TO PROCEDURE SECnON 5.t NOTE s.

tr;:il c.

C1 DAY 1 mewrn t::_;ijn>>,, DAY 2 me~ns P1::.:t&<; W* -::cmplt!t"lO thl!-

7 i *1dt-;;;;,nh! D 1or c;?J'w!l'.<htl ~-+iec *.de JJ:"'ld 'N' f*:n a "'H;;;hl *!k'iih $.Cli'fi!*duie A;:;prc¥4T! :J:te \"\cr"m. hetm::. ':tay EVALUATOR'S ATTACHMENT

-11 of 16-

EVALUATOR'S ATTACHMENT NUCLEAR MANAGEMENT MANUAL PAGE ~'90F Fabgue Management Program I! Yeo n CJ Re*:! ,,,,,,,,

J O'.r"'r

*c,

Jdi;::wi Rny1Mri a~~u;::.uo-*1*s "> *_wC?tt schedu'>e 101-rJ1o;ll; ~N'rtie!Z tt';oe ih>:lt i; Jrli>Q t'i~ f.r~4oc !hat \l!:]ft, i"'tOLB' EVALUATOR'S ATTACHMENT

-12 of 16-

EVALUATOR'S ATTACHMENT

-~EnlerJ:lY NUCLEAR MAlllAGEMENT MANI.JIU.

NoM-0U.ALJTY ii?'.t.A-t!!D

~" !J"Hi~J."H)ft,lll Fatigue Management Program

\ht EN-OM-123 PAGE I

~D OF DO REV t.Z C)5 Are L

E. DISTRllBUllON v1orlo: r10ur this work pen:xl (sea FTR is .req;;ired fo; eac,l-i 'll'::irk hour 1D assure ac:urate of waivr """"""" is ao::;;iptable tc attach the Fo.ri-i to only ooe FTRs.

Ema1ii zhe rn1mr11..1*""1"'!

t::lent~ler EVALUATOR'S ATTACHMENT

-13 of 16-

HANDOUT A Reactor Operator has called out sick for Friday, August 31, Day Shift.

The following is the recent work hour history and upcoming schedule for three Reactor Operators. Their hours worked and scheduled were/ are in the Main Control Room during Mode 1, except for the training week.

Dayshift 6:00 am - 6:00 pm Nightshift 6:00 pm - 6:00 am Training 6:30 am - 2:30 pm The schedules show the day that each shift begins:

RO - Dave Jones M T w Th F Sa Su Week of August 20 D D D D N N Week of Auqust 27 N N D? D D Week of September 3 D D D Week of September 10 T T T T Week of September 17 N N N RO - Bob Smith M T w Th F Sa Su Week of Auqust 20 N N N N Week of August 27 T T T T D? N N Week of September 3 N N D Week of September 10 D D D D Week of September 17 N N N N RO-Jim Doe M T w Th F Sa Su Week of Auqust 20 T T T T Week of August 27 D D D D D? N Week of September 3 N N N N D Week of September 10 D D D Week of September 17 T T T T Evaluate the work hour history for each of the three Reactor Operators. Determine which operators can take the scheduled watch for a full dayshift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , Friday, August 31 (and still be eligible for future scheduled shifts).

If applicable, describe the conditions that would make any operator(s) ineligible to work.

Consider all days before August 31 as actual worked shifts.

Consider all days after August 31 as scheduled shifts.

Record your response on the worksheet provided.

-14 of 16-

HANDOUT Eligible for Day Shift on Reactor Operator August 31? If not eligible, describe reason:

(circle Yes or No)

Dave Jones Yes I No I

Bob Smith Yes I No Jim Doe Yes I No

-15 of 16-

SRO ONLY HANDOUT Initial Conditions:

Disregard the previous JPM results.

An operator is currently at their Work Hour Limitation.

This operator is needed to cover Shift.

This additional Shift would result in that operator to exceed Work Hour Limits.

Additional SRO Only Cue:

Inform the Candidate, "Determine the required actions to allow this individual to cover the Shift to meet Technical Specification staffing requirements.

Document your findings in the space below."

-16 of 16-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Worker Exposure for Emergent Work S/RO RC APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.3.4 (3.2/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 12-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Worker Exposure for Emergent Work S/RO RC APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 12-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Worker Exposure for Emergent Work S/RO RC APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None

11. REFERENCES A. EN-RP-201, Dosimetry Administration Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure adequate copies of the procedures referenced above are available.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Two operators are required to enter a locked high radiation area to support an emergent job.

C. The job is expected to take 45 minutes.

D. The job site dose rate is 1500 mRem/hr.

E. Operator #1 has received 1147 mRem of dose so far this year.

F. Operator #2 has received 450 mRem of dose so far this year.

G. Neither operator has received any dose extensions so far this year.

H. Neither operator has any undocumented quarters for this year.

I. No other Operators are available to perform this job.

J. No means of reducing area dose rates are available.

-3 of 12-

SRO/RO 16-1 NRC S/RO RC TASK TITLE: Determine Worker Exposure for Emergent Work

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Determine the expected dose that each operator will receive while performing this job.

Determine if each operator will need a dose extension in order to receive this dose. Report your results on the provided worksheet."

EXAMINER: Provide the candidate with the first handout and worksheet.

STEP STANDARD EVALUATION

/COMMENT

1. Obtain required references. Obtains and utilizes required SAT I UNSAT references, which may include:

EN-RP-201 EXAMINER NOTE: See provided key for remaining steps.

2. Determine the expected dose that each Calculates that each operator will CRITICAL operator will receive while performing receive 1125 mRem while performing STEP this job this job. SAT I UNSAT (45 minutes/60 minutes per hour) x (1500 mRem/hour) = 1125 mRem

3. Determine if Operator #1 will need a Determines that Operator #1 will need CRITICAL dose extension in order to receive this dose extension in order to receive this STEP dose. dose. SAT I UNSAT 1147 mRem + 1125 m,Rem =2272 mRem > 2000 mRem normal dose limit

4. Determine if Operator #2 will need a Determines that Operator #2 will NOT CRITICAL dose extension in order to receive this need dose extension in order to receive STEP dose. this dose. SAT/UNSAT 450 mRem + 1125 mRem = 1575 mRem < 2000 mRem normal dose limit

-4 of 12-

SRO/RO 16-1 NRC S/RO RC TASK TITLE: Determine Worker Exposure for Emergent Work EXAMINER: If the candidate correctly complete JPM steps 2-4, provide them with the extra handout, with the following information:

"Operator #1 has been granted a dose extension to 2500 mRem. Operator #2 has NOT been granted a dose extension.

Determine the maximum stay time allowed for both Operator #1 and for Operator #2, such that they do NOT exceed their dose limits. Document your results in the worksheet below."

5. Determine the maximum stay time Calculates the maximum stay time for CRITICAL allowed for Operator #1 such that dose Operator #1 is approximately 54 STEP limit is NOT exceeded. minutes. SAT/UNSAT (2500 mRem -1147 mRem) I 1500

=

mRem/hr 0.902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months x (60 minutes per hour) = 54.12 minutes

6. Determine the maximum stay time Calculates the maximum stay time for CRITICAL allowed for Operator #2 such that dose Operator #2 is approximately 62 STEP limit is NOT exceeded. minutes. SAT/UNSAT (2000 mRem - 450 mRem) I 1500 mRem/hr = 1.033 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months (60 minutes per hour) =62 minutes EVALUATOR: Terminate the task at this point for RO candidates.

EXAMINER: For SRO candidates, continue JPM by providing SRO Only cue sheet:

INITIATING CUE for SRO Candidates Only:

Inform the candidate, "Determine the required actions necessary for Operator #1 to be allowed to receive a dose of 2500 mRem. Report your results below."

-5 of 12-

SRO/RO 16-1 NRC S/RO RC TASK TITLE: Determine Worker Exposure for Emergent Work STEP STANDARD EVALUATION I COMMENT

7. Prior to dose extension, requesting Per initiating cue, no other operators SAT I UNSAT supervisor should: are available to do this job and no other a) Evaluate dose equalization in means of reducing dose are available.

the department Therefore a), b), and c) are not b) Check other personnel applicable.

qualifications to perform tasks c) Check other means to reduce dose

8 Obtain verification of the worker's Candidate indicates any one of the CRITICAL current year exposure prior to allowing following is required: STEP a worker to exceed 2000 mrem TEDE a) NRC Form 5 or equivalent SAT I UNSAT for the year. Any of the following may be used for verification: b) NRC Form 4 or equivalent a) NRC Form 5 or equivalent c) Electronic, telephone or fax transfer b) NRC Form 4 or equivalent of exposure data provided by the c) Electronic, telephone or fax licensees(s) providing the monitoring.

transfer of exposure data I

provided by the licensees( s) providing the monitoring.

9 Extend a Radiation Worker's Candidate indicates that the Individual's CRITICAL administrative TEDE ADG to the supervisor recommends the extension STEP guidelines described in the following AND RP Manager approves the SAT I UNSAT table, after obtaining the indicated extension.

approvals.

Greater than 2000 mrem and less than or equal to 3000 mrem per year.

10 Document the authorization of the Candidate indicates that Attachment CRITICAL increased in the worker's ADG on 9.1 of EN-RP-201 must be filled out. STEP Attachment 9.1 "Radiation Exposure SAT I UNSAT Guideline Extension Authorization" EVALUATOR: Terminate the task at this point for SRO candidates.

Task Standard: Expected dose, stay time and dose extension determined based on given radiological conditions.

-6 of 12-

EVALUATOR'S KEY

1. Expected dose that each operator will receive while performing this job:

1125 mRem

2. Will Operator #1 need a dose extension in order to receive the dose calculated above? (circle one)

G No

3. Will Operator #2 need a dose extension in order to receive the dose calculated above? (circle one)

Yes 8 EVALUATOR'S KEY

-7 of 12-

EVALUATOR'S KEY

1. Maximum stay time allowed for Operator #1 (record final answer in minutes):

54 minutes

2. Maximum stay time allowed for Operator #2 (record final answer in minutes):

62 minutes EVALUATOR'S KEY

-8 of 12-

HANDOUT Initial Conditions:

The plant is operating at 1OOo/o power.

Two operators are required to enter a locked high radiation area to support an emergent job.

The job is expected to take 45 minutes.

The job site dose rate is 1500 mRem/hr.

Operator #1 has received 1147 mRem of dose so far this year.

Operator #2 has received 450 mRem of dose so far this year.

Neither operator has received any dose extensions so far this year.

Neither operator has any undocumented quarters for this year.

No other Operators are available to perform this jot>.

No means of reducing area dose rates are available.

Initiating Cue:

Determine the expected dose that each operator will receive while performing this job.

Determine if each operator will need a dose extension in order to receive this dose.

Report your results on the provided worksheet.

-9 of 12-

WORKSHEET

1. Expected dose that each operator will receive while performing this job:

2. Will Operator #1 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

3. Will Operator #2 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

-10 of 12-

EXTRA HANDOUT Operator #1 has been granted a dose extension to 2500 mRem.

Operator #2 has NOT been granted a dose extension.

Determine the maximum stay time allowed for both Operator #1 and for Operator #2, such that they do NOT exceed their dose limits.

Document your results in the worksheet below.

EXTRA WORKSHEET

1. Maximum stay time allowed for Operator #1 (record final answer in minutes):

2. Maximum stay time allowed for Operator #2 (record final answer in minutes):

-11 of 12-

SRO Candidates Only:

"Determine the required actions necessary for Operator #1 to be allowed to receive a dose of 2500 mRem. Report your results below."

-12of12-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 16-1 NRC SRO EC TASK TITLE: Review Tagout Isolation Boundary For CRD Pump APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: _2_.2_._13_(.._4_.3.......

) _ _ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE:

- - - Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 16-1 NRC SRO EC TASK TITLE: Review Tagout Isolation Boundary For CRD Pump APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 16-1 NRC SRO EC TASK TITLE: Review Tagout Isolation Boundary For CRD Pump APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-OP-102, Protective and Caution Tagging B. FM-27 A and FM-27B C. OP-25 Ill. TOOLS AND EQUIPMENT

None IV. SET UP REQUIREMENTS A. Ensure copies of the following references are available:

EN-OP-102

FM-27 A and FM-27B (full size)

OP-25 V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Maintenance is required on CRD pump A.

C. The maintenance activity will be intrusive to the impeller casing for impeller replacement.

D. eSOMS is unavailable.

-3 of 9-

16-1 NRC SRO EC TASK TITLE: Review Tagout Isolation Boundary For CRD Pump

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Review the given isolation boundary for CRD pump A maintenance. Document your findings below or on the isolation boundary sheet."

EVALUATION I STEP STANDARD COMMENT

1. Obtain required references. Obtains and utilizes required references, which may include: SAT I UNSAT

EN-OP-102

FM-27 A and/or FM-278

OP-25 EVALUATOR NOTE: Component names and Required Position terminology may vary slightly from what is written below due to unavailability of eSOMS.

2. Review isolation boundary for Reviews isolation boundary. SAT/UNSAT adequacy.

3. Determine CRD pump A breaker Identifies CRD pump A breaker (71-11516) should be tagged in CRITICAL STEP should be added to the isolation the racked out or removed position. SAT I UNSAT boundary.

-4 of 9-

16-1 NRC SRO EC TASK TITLE: Review Tagout Isolation Boundary For CRD Pump EVALUATION I STEP STANDARD COMMENT

4. Determine isolation is incomplete for Identifies CRD pump A discharge isolation valve (03CRD-176A) CRITICAL STEP CRD pump A discharge. should be tagged in the closed position. SAT/UNSAT EVALUATOR NOTE: The Candidate may also mention that 03CRD-36A does not need to be tagged because it is a check valve. This is not critical, and is further discussed in JPM Step

9.

5. Determine incorrect isolation is Identifies CRD pump B minimum flow isolation valve (03CRD- CRITICAL STEP identified for CRD pump B minimum 1778) should NOT be tagged in the closed position. SAT I UNSAT flow line.

-EVALUATOR NOTE: The Candidate may also mention that no tag should be placed on 03CRD-154B, but this is not critical because this is a normally closed valve that will not affect CRD pump B performance.

-5 of 9-

16-1 NRC SRO EC TASK TITLE: Review Tagout Isolation Boundary For CRD Pump EVALUATION I STEP STANDARD COMMENT

6. Determine need for CRD pump A Identifies tagging one or more of the following paths for venting CRITICAL STEP venting path. CRD pump A casing: SAT I UNSAT

CRD pump A suction pressure indicator root valve (03CRD-163) open with the pressure indicator removed/uninstalled.

CRD pump A suction pressure relief valve (03CRD-RV14A) gagged open.

CRD pump A suction from SLC system isolation valve (03CRD-88A) open (with cap removed).

May also list casing vents 03CRD-416A 1 or A2 .

EVALUATOR NOTE: Only one vent or drain path is required by procedure.

7. Determine this tagout includes high Determines that with CRD pump B running, the discharge SAT/UNSAT energy. isolations for CRD pump A are exposed to high energy (>500 psig) (may reference EN-OP-102 Section 3.0[15]).

8. Determine need for double valve Determines the discharge of CRD pump A should have double SAT I UNSAT protection. valve protection due to CRD pump B providing high energy (may reference EN-OP-102 Attachment 9.2 Step 5.1 ).

-6 of 9-

16-1 NRC SRO EC TASK TITLE: Review Tagout Isolation Boundary For CRD Pump EVALUATION I STEP STANDARD COMMENT

9. Determine availability of double valve Determines double valve protection can only be provided by SAT I UNSAT protection and compensatory actions. taking credit for check valves (03CRD-36A and 03CRD-37 A).

Indicates that to use check valves as isolation boundary (may reference EN-OP-102 Attachment 9.2 Section 2.8):

. Shift Manager concurrence must be obtained.

All individuals working under the tagout shall be informed of the risk.

The risk needs to be listed in the hazards section of the ta gout.

EVALUATOR: Terminate the task at this point.

Task Standard: Tagout isolation boundary for CRD pump A reviewed with discrepancies noted.

-7 of 9-

HANDOUT Initial Conditions:

The plant is operating at 100% power.

Maintenance is required on CRD pump A.

The maintenance activity will be intrusive to the impeller casing for impeller replacement.

eSOMS is unavailable.

Initiating Cue:

As a Tag Reviewer, review the given isolation boundary for CRD pump A maintenance. '

If any components are incorrect\ inadequate or missing, state the discrepancy.

Document your findings below or on the isolation boundary sheet.

-8 of 9-

Handout Component Required Position CRD pump A control switch Pu II-to-Lock 03CRD-153A, CRD Water Pump A Suet lsol Closed Valve 03CRD-36A, CRD Water Pump A Disch Closed Check Valve 03CRD-177 A, CRD Water Pump A Min Flow Closed lsol Valve I

03CRD-154A, CRD Water Pump A Min Flow Closed lsol Valve CRD-177 A Bypass Valve 03CRD-177B, CRD Water Pump B Min Flow Closed lsol Valve .

03CRD-154B, CRD Water Pump B Min Flow Closed lsol Valve CRD-177B Bypass Valve 03CRD-39, CRD Water Pump A & B Positive Closed Press Seal lsol Valve

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 16-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification (Time Critical)

REV: DATE: NRC KIA SYSTEM NUMBER: _2_.4_._40_(._4_.5..._)_ _ _ __

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes

PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

.. EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 16-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification (Time Critical)

Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 16-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification (Time Critical)

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. IAP-1 B. IAP-2 C. EAP-1.1 Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available, including extra copies of the Part 1 notification form.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

-3 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 16-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification (Time Critical)

VI. TASK CONDITIONS A. The plant was initially operating at 100% power with no equipment out of service.

B. An earthquake was felt in the Control Room and confirmed with both JAF and Nine Mile Point Unit 2 seismic instrumentation.

C. JAF seismic instrumentation indicates >0.1 g for both horizontal and vertical acceleration.

D. The earthquake resulted in a loss of DC power system A.

E. The earthquake also caused a coolant leak in the Drywell.

F. The Reactor was manually scrammed five minutes ago.

G. The following conditions exist now:

All Control Rods full in

Reactor pressure is 200 psig and lowering.

Reactor water level is 0 inches and rising.

Drywell pressure is 15 psig and slowly rising.

Torus pressure is 12 psig and slowly rising.

Torus water temperature is 105°F and slowly rising.

Reactor Building differential pressure is negative (-) 0.25" H20.

Stack 13nd Reactor Building ventilation radiation monitors are stable at the pre-transient values.

Chemistry reports that Reactor coolant activity is 400 µCi/gm 1-131 dose equivalent.

200' elevation wind speed is 10 mph from 190°.

30' elevation wind speed is 5 mph from 190°.

Stability class is E.

-4 of 9-

SRO 16-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification (Time Critical)

VII. INITIATING CUE Inform the candidate of the following:

"Classify the event and complete the Part 1 Notification per EAP-1.1, Offsite Notifications. This is a time critical JPM. Your time clock starts once you acknowledge this task."

- CRITICAL STEP STEP STANDARD EVALUATION I COMMENT

1. Obtain applicable reference documents Obtains a copy of applicable reference documents, as SAT I UNSAT needed:

IAP-1

IAP-2

EAP-1.1 EVALUATOR: Ensure sufficient copies of these documents are available.

2. Classify the event Classifies the event as Site Area Emergency FS 1.1 CRITICAL STEP based on loss of Fuel Clad and RCS barriers within 15 SAT I UNSAT minutes of JPM start time.

JPM start time:

Time of classification:

Time difference:

-5 of 9-

SRO 16-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification (Time Critical)

STEP STANDARD EVALUATION I COMMENT

3. Implement EAP-1.1, Offsite Completes EAP-1.1 Attachment 1, Part 1 notification CRITICAL STEP Notifications, in order to notify offsite form per attached key within 15 minutes of classification SAT I UNSAT agencies time Time of classification:

Time of offsite notification:

Time difference:

EVALUATOR NOTE: Only item 3, 4, 5, 6, and 7 of EAP-1.1 Attachment 1 are deemed critical for this JPM.

These items are individually graded in the JPM steps below. All other items are non-critical. See attached key.

4. Completes Part 1 Notification step 3 Indicates "SITE AREA EMERGENCY" in Part 1 CRITICAL STEP Notification step 3 (see attached key) SAT I UNSAT

5. Completes Part 1 Notification step 4 Records today's date and time of declaration in Part 1 CRITICAL STEP Notification step 4 (see attached key) SAT/UNSAT

6. Completes Part 1 Notification step 5 Indicates "No Release" in Part 1 Notification step 5 (see CRITICAL STEP attached key) SAT I UNSAT

-6 of 9-

SRO 16-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification (Time Critical)

STEP STANDARD EVALUATION I COMMENT

6. Completes Part 1 Notification step 6 Indicates "NO NEED for PROTECTIVE ACTIONS CRITICAL STEP outside the site boundary" in Part 1 Notification step 6 SAT/UNSAT (see attached key)

7. Completes Part 1 Notification step 7 Indicates EAL# "FS1 .1" in Part 1 Notification step 7 (see CRITICAL STEP attached key) SAT I UNSAT EVALUATOR: Terminate the task at this point.

Task Standard: The emergency event is classified and the Part 1 Notification form is filled out.

-7 of 9-

EVALUATOR'S KEY 1 of 1

"(EW YORK sr ATt:

t;l'SJAIE RADIOUJGICAL EMERG*:NCY DATA FORM l'AR*r Not1f1Catmn ~

"Thill Ill to report an l!lcident at IM Jaml!5 A, Flllf>alricl< POW111' Plant S!!lfld!Jv I~ coolirmalml't* !COO!ltlet roli cam to lnduOO me f(j!OW!flf stalklrts:) 0 N-Yolt! State D O.WltQO County D NIM Miltl Point Unit IJ1 0 NIM Miltl J>omt Unit 112 FRou: (CR, TSC, &Q.E,,QTHER) ED Approval: rSignaturel G ERAL INFORMATION Note: 0 Wtien ctiecitud lndlcatn ctian in status, NOT for L liMf::IKif::t-<C:Y TIRMl"A1"f'l}

f. Otoor al Rclauc of Radiooctivc Mmcrials clue 10 !he d*ml1cd event:

A. No llelcM¢

. Release BELOW federal ltmlt!> Teclmic.al Spct'1fa:11tim1 u T<>Atmosphere To Water C. Release ABOVE fedarnl l!mits Techrua! Spei:1ficahoo fo Atmosphere To Willet D Unmooilored rde11~ uim1

06. The follmvmg Pl'Olcctive ACli(lfl!l llrll

@NO NEED for PROTECTIVE ACTIONS 001>>1d.1100 sale boond;ary

8. H' ACUATE and IMPLEMENT tile KJ PU:"! f<< the lbllmving ERPAs and All remaining EIU'As MO!lllTOR dlt EMERGENCY ALERT S'l"STL'l.t I 2 3 4 S 6 7 i! \I 10 U 12 13 14 15 16 17 la l9 20 t!QTE. QFt:'>U,~ ,HJTHOBJ1lt:SSHQIJW CONSJDER: Slft:LlEIHN*fL.ICE ~ TAU,' Kl ff £.ViK'l/.iilO,V ISNOTFEAS!Bf.£ C SHELTER*IN*PLACE and L\1.PLEMENT the Kl PLAN f<< !be following £1tl'A~ and All rermmiing l:.RPAs \toNITOR the EMERGENCY ALERT SYSTEM t 2 3 4 5 6 7 8 9 Hl l I 12 lJ 14 15 l6 l7 !8 19 20 21 22 2J ;:4 25 26 27 21< 2\1 BnefEvent here - not critical l De>aiptioo &

Other Significant lnforJl\i!LiM

08. 8S)

09. Wint! Speed: A._..._ __

R 5 Miles/Hour at ele\*atioo 30 Feet !Ground o yoo lllMI any questiorn>T D New York StllW D Oswewo Cwnty D Nina Mila Pa4nt Unit t1 0 NIM Mlt. Point Ufllt n u James A. FitzPalnck Nuclear Power f>lanl out at (date time)"

EVALUATOR'S KEY

-8 of 9-

HANDOUT Initial Conditions:

The plant was initially operating at 1OOo/o power with no equipment out of service.

An earthquake was felt in the Contrbl Room and confirmed with both JAF and Nine Mile Point Unit 2 seismic instrumentation.

JAF seismic instrumentation indicates >0.1 g for both horizontal and vertical acceleration.

The earthquake resulted in a loss of DC power system A.

The earthquake also caused a coolant leak in the Drywell.

The Reactor was manually scrammed five minutes ago.

The following conditions exist now:

o All Control Rods full in o Reactor pressure is 200 psig and lowering.

o Reactor, water level is 0 inches and rising.

o Drywell pressure is 15 psig and slowly rising.

o Torus pressure is 12 psig and slowly rising.

o Torus water temperature is 105°F and slowly rising.

o Reactor Building differential pressure is negative

(-) 0.25" H20.

o Stack and Reactor Building ventilation radiation monitors are stable at the pre-transient values.

o Chemistry reports that Reactor coolant activity is 400

µCi/gm 1-131 dose equivalent.

o 200' elevation wind speed is 10 mph from 190°.

o 30' elevation wind speed is 5 mph from 190°.

o Stability class is E.

Initiating Cue:

Classify the event and complete the Part 1 Notification per EAP-1.1, Offsite Notifications.

This is a time critical JPM.

Your time clock starts once you acknowledge this task.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 A TASK TITLE: Transfer Bus 10100 from Reserve to Normal (Alt Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 262001 A4.04 (3.6/3. 7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

15 ESTIMATED COMPLETION TIME:

-- - Minutes SUBMITIED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion D Simulated ~ Performed Location: D Plant ~ Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 16-1 A TASK TITLE: Transfer Bus 10100 from Reserve to Normal (Alt Path)

APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required C2:] None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2of10-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 16-1 A TASK TITLE: Transfer Bus 10100 from Reserve to Normal (Alt Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-46A, 4160 V and 600 V Normal AC Power Distribution Ill. TOOLS AND EQUIPMENT A. Synch Key IV. SET UP REQUIREMENTS A. Plant in a startup/shutdown situation with Main Generator load -75 MWe {IC-126).

B. Ensure Buses 10300 and 10400 are aligned to Reserve.

C. Ensure Buses 10100 and 10200 are aligned to Reserve.

D. Ensure T-4 position is adjusted such that 10100 will need to be adjusted to facilitate transfer.

E. Ensure the following simulator programming:

Override meter ED ZA0098SYNC17 A, 0%, Delay Time = 1 second, Trigger 1 (fails RUNNING voltage meter downscale)

Event Trigger 1, event= ZDl251HONA03(2)==1, command= none (activates when 10100 sync key is taken to NORM)

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A plant startup is in progress.

B. Another operator is stationed to adjust 71T-4 load tap changer, if required.

C. Nine Mile Point Unit 1 Control Room and Power Control have been notified of all impending bus transfers and tap changer operations.

D. All prerequisites have been met for the bus transfer.

E. Both RPS buses are powered from their respective MG sets.

F. Main Generator load is approximately 77 MWe.

-3 of 10-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to transfer Bus 10100 from Reserve to Normal per OP-46A Section D.20."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-46A. SAT/UNSAT OP-46A.

2. Select the correct section to Selects section D.20. SAT I UNSAT perform the task.

3. WHILE performing the Acknowledges step. SAT I UNSAT remainder of this subsection maintain 4KV and 600V bus voltage per Section E.

4. IF a degraded or undervoltage Acknowledges step. SAT/UNSAT condition occurs while transferring bus, THEN immediately establish GREATER THAN 3.9 KV -

using T-4 LTC CONTROL.

5. IF Main Generator is Observes Main Generator load is greater than 70 MWe and SAT/UNSAT synchronized to 345 KV stable.

System, THEN verify Main Generator has a stable load of at least 70 MWe.

-4 of 10-

STEP STANDARD EVALUATION I COMMENT

6. Ensure Nine Mile Point 1

Determines Nine Mile Point~ has been notified per initial SAT/UNSAT Control Room (due to effect conditions.

on 115 KV line loading) has been notified that 10100 Bus will be transferred from reserve to normal service.

7. Perform the following: Determines Power Control has been notified per initial SAT/UNSAT conditions.

Notify Syracuse Power Control that 71T-3 tap changer will be taken to manual.

8.

Ensure AUTO MANUAL T- Rotates AUTO MANUAL T-3 LTC CONTROL switch to SAT/UNSAT 3 LTC CONTROL switch is MAN.

in MAN.

9. Station operators as follows: Determines another operator has been stationed for T-4 SAT I UNSAT load tap changer operation per initial conditions.

One to adjust bus voltage at T-4 LTC CONTROL

One to operate breaker control switches

10. Place BUS 10100 FDR Inserts synch key and rotates clockwise to NORM for Bus CRITICAL STEP SYNCH SW switch in NORM. 10100. SAT/UNSAT

-5 of 10-

STEP STANDARD EVALUATION I COMMENT

11. IF voltages on NON-EMERG Acknowledges step. SAT I UNSAT BKRS INCOMING and RUNNING volt meters cannot be matched in following step, EVALUATOR NOTE: This step forms the basis of the THEN perform Subsection alternate path in this JPM. In the next steps, the candidate G.14, Single Meter Voltage will determine volt meters cannot be adequately matched Match Method. and will transition to OP-46A section G.14 to complete the task using an alternate method of matching voltages.

12. Match voltages on NON- Observes that the RUNNING volt meter fails downscale. SAT I UNSAT EMERG BKRS INCOMING and RUNNING volt meters using T-4 LTC CONTROL Determines that INCOMING and RUNNING volt meters switch. CANNOT be matched within 1.5 meter increments.

Transitions to OP-46A section G.14.

EVALUATOR CUE: If the candidate reports the malfunction and asks for direction, direct the candidate to make a recommendation and then carry out that recommendation. If the candidate states the volt meter mismatch exceeds that normally allowed for use of single meter match method, then give the Design Engineering cue in JPM step 13.

EVALUATOR NOTE: The steps below are from OP-46A section G.14.

-6 of 10-

STEP STANDARD EVALUATION I COMMENT

13. IF voltage mismatch is Determines that voltage mismatch is greater than 6 meter SAT I UNSAT GREATER THAN 6 meter increments.

increments, THEN obtain guidance for performing bus transfer from Design Notifies CRS and/or contacts Design Engineering for Engineering. guidance.

EVALUATOR CUE: Inform the candidate that Design Engineering has determined that OP-46A section G.14.2 should be used to match voltages and transfer the 10100 bus.

14. IF transferring 4.16 KV bus Rotates synch key counterclockwise to RES for Bus 10100. CRITICAL STEP from reserve to normal, THEN SAT/UNSAT perform the following:

Place 4.16 KV bus FDR SYNCH SW switch in RES.

15. Note voltage on incoming Observes voltage on incoming volt meter. SAT/UNSAT meter.

EVALUATOR NOTE: The candidate may either write down this value or remember it for use in subsequent steps.

16. Place 4.16 KV FDR SYNCH Rotates synch key clockwise to NORM for Bus 10100. CRITICAL STEP SW switch in NORM. SAT/UNSAT

-7 of 10-

STEP STANDARD EVALUATION I COMMENT

17. Match voltage on NON- Rotates T-4 LTC CONTROL switch as required to set CRITICAL STEP EMERG BRKS INCOMING voltage on INCOMING volt meter within 1.5 meter SAT/UNSAT volt meter with voltage taken increments of voltage observed in JPM step 15.

in Step busing T-4 LTC CONTROL switch.

EVALUATOR CUE: If the candidate asks for another operator to adjust T-4 LTC, direct the candidate to perform the T-4 LTC manipulation for the other operator.

EVALUATOR NOTE: The candidate will now transition

. bac_k to OP-46A section D.29 at step D.20.10.

18. IF phase angle is GREATER Observes phase angle on NON-EMERG BKRS SAT I UNSAT THAN 17 degrees on NON- SYNCHROSCOPE is less than 17 degrees.

EMERG BKRS SYNCHROSCOPE,THEN perform the following ...

19. WHEN incoming and running Closes breaker 10102 by rotating control switch clockwise. CRITICAL STEP voltages are matched, AND SAT I UNSAT synchroscope is at approximately 12 o'clock, perform the following bus transfer using the same hand, without unnecessary delay, to perform each breaker operation:

Close NSS TO BUS 10100 BKR 10102.

-8 of 10-

STEP STANDARD EVALUATION I COMMENT

20.

Open RSS TO BUS 10100 Opens breaker 10112 by rotating control switch CRITICAL STEP BKR 10112. counterclockwise. SAT/UNSAT

21. Place BUS 10100 FDR Rotates synch key clockwise to OFF and removes. SAT I UNSAT SYNCH SW switch in OFF and remove handle.

22. Verify all white lights for RPS Observes all RPS A and B white lights are lit. SAT/UNSAT A and RPS B power source selectors are on at panel 09-16.

EVALUATOR CUE: If asked about further bus transfers involving T-3, report no further bus transfers are immediately planned involving T-3.

23. Perform the following: Determines Power Control has been notified per initial SAT/UNSAT conditions.

Notify Syracuse Power Control that 71T-3 tap EVALUATOR NOTE: The candidate may make a changer will be taken to notification for this step. If so, acknowledge notification.

auto.

24.

Place AUTO MANUAL T-3 Rotates AUTO MANUAL T-3 LTC CONTROL switch to SAT/UNSAT LTC CONTROL switch in AUTO.

AUTO.

EVALUATOR: Terminate the task at this point.

Task Standard: Bus 10100 is transferred from Reserve to Normal using the Single Meter Voltage Match Method.

-9 of 10-

HANDOUT Initial Conditions:

A plant startup is in progress.

Another operator is stationed to adjust 71 T-4 load tap changer, if required.

Nine Mile Point Unit 1 Control Room and Power Control have been notified of all impending bus transfers and tap changer operations.

All prerequisites have been met for the bus transfer.

Both RPS buses are powered from their respective MG sets.

Main Generator load is approximately 77 MWe.

Initiating Cue:

The CRS directs you to transfer Bus 10100 from Reserve to Normal per OP-46A Section D.20.

-10 of 10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 B TASK TITLE: Perform Actions For Fire In Plant (Alt Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 600000 AA2.17 3.1/3.6 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion D Simulated ~ Performed Location: D Plant ~ Simulator QATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 B TASK TITLE: Perform Actions For Fire In Plant (Alt Path)

APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 B TASK TITLE: Perform Actions For Fire In Plant (Alt Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-28, Operation During Plant Fires 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset the simulator to a power-operating IC. (IC-127)

B. Insert malfunction FP02:Z01, Smoke - Zone 1 - RB 227 West Crescent C. Insert malfunction HP06, HPCI Steam Line Break, to bring in HPCI high temperature isolation, then delete malfunction.

D. Insert annunciator 09-3-3-38, HPCI Aux Oil Pmp Overload Or Control Pwr Loss.

E. Override RWR pump B control switch trip and pull to lock contacts OFF (RR ZDl2AS1 Bin NASTR)

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use 1 self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. A serious fire is in progress in the West Crescent area.

B. The fire has caused a spurious isolation of HPCI and loss of control power to the HPCI Aux Oil pump.

-3 of 8-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to perform the immediate actions for Attachment 2 of AOP-28, Operation During Plant Fires."

STEP STANDARD EVALUATION I COMMENT

1. Obtains a controlled copy of AOP-28 and selects SAT/UNSAT Obtain a controlled copy of AOP-28 Attachment 2.

EVALUATOR: Provide working copy.

2. IF RPV isolation is desired, THEN Determines RPV isolation is NOT desired. SAT/UNSAT ensure closed the following valves to isolate the RPV ...

EVALUATOR: If candidate asks about need for RPV isolation, report that RPV isolation is NOT currently desired.

3. Manually scram reactor and execute At panel 09-05: CRITICAL STEP AOP-1 concurrently. SAT I UNSAT

Depresses MANUAL SCRAM A and MANUAL SCRAM B pushbuttons.

Places RX MODE switch in SHUTDOWN .

EVALUATOR CUE: Tell candidate that another operator will complete the rest of AOP-1.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

4. Ensure RWR Pumps 02-2P-1 A and 02- Runs RWR pump A to minimum speed by rotating RWR SAT/UNSAT 2P-1 Bare shut down as follows: MG A SPEED CNTRL knob counterclockwise.

a. Ensure both RWR pumps are at Runs RWR pump B to minimum speed by rotating RWR LESS THAN OR EQUAL TO MG B SPEED CNTRL knob counterclockwise.

minimum speed.

5. b. Ensure both RWR pumps are Trips RWR pump A by rotating control switch CRITICAL STEP tripped at Panel 09-4. counterclockwise to TRIP and Pull-to-Lock. SAT/UNSAT Attempts to trip RWR pump B by rotating control switch counterclockwise to TRIP and Pull-to-Lock.

NOTE: The failure of RWR pump B to trip initiates the JPM alternate path.

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

6. c. IF an RWR pump fails to trip from Determines RWR pump B failed to trip. CRITICAL STEP Panel 09-4, THEN trip AND place in. - SAT/UNSAT Pull-To-Lock the following 4 KV bus Rotates NSS TO BUS 10200 BKR 10202 control switch feeder breakers at Panel 09-8:

counterclockwise and places in Pull-to-Lock.

02-2P-1A NSS TO BUS 10100 NOTE: Only tripping of the one BKR 10102 AND *Rotates RSS TO BUS 10200 BKR 10212 control breaker is critical. Placing the RSS TO BUS 10100 switch counterclockwise and places in Pull-to-Lock. control switch in Pull-to-Lock is BKR 10112 NOT critical. The 10100 bus

02-2P-1B NSS TO BUS 10200 breakers are also likely to be opened based on procedure BKR 10202 AND wording.

RSS TO BUS 10200 BKR 10212

7. IF an RWR pump fails to trip from Determines both RWR pumps have tripped. SAT/UNSAT Panels 09-4 and 09-8, THEN depress mechanical TRIP pushbutton on the following 4 KV breakers ...

8. NOTE: JPM steps *8 & *9 may be Closes RWR PMP A DISCH 02MOV-53A by rotating CRITICAL STEP completed in either order or control switch counterclockwise to CLOSE.

SAT/UNSAT concurrently.

Dispatches operator to close 02-2RWR-39A (RWR Attempt to isolate RWR Pump 02-2P-pump A seal purge upstr isol valve).

1A as follows:

a. Close RWR PMP A DISCH 02MOV- EVALUATOR ROLE PLAY: When requested, report 53A.

that 02-2RWR-39A is closed.

b. Close 02-2RWR-39A (RWR pump A seal purge upstr isol valve). Closes RWR PMP A SUCT 02MOV-43A by rotating

c. Close RWR PMP A SUCT 02MOV- control switch counterclockwise to CLOSE.

43A.

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

9. Attempt to isolate RWR Pump 02-2P- Closes RWR PMP B DISCH 02MOV-53B by rotating CRITICAL STEP 1Bas follows: control switch counterclockwise to CLOSE.

SAT/UNSAT

a. Close RWR PMP B DISCH 02MOV-Dispatches operator to close 02-2RWR-39B (RWR 53B.

pump B seal purge upstr isol valve).

b. Close 02-2RWR-39B (RWR pump B seal purge upstr isol valve). EVALUATOR ROLE PLAY: When requested, report

c. Close RWR PMP B SUCT 02MOV- that 02-2RWR-39B is closed.

43B.

Closes RWR PMP B SUCT 02MOV-43B by rotating control switch counterclockwise to CLOSE.

10. Place the following keylock switches in Rotates 10MOV-16B AUTO CONTROL BYPASS 10A- CRITICAL STEP BYPASS at panel 09-3: S21 B keylock switch clockwise to BYPASS. SAT I UNSAT

10MOV-16B AUTO CONTROL BYPASS 1OA-S21 B Rotates 1OMOV-25B AUTO CONTROL BYPASS 1OA-Sf2B keylock switch clock.YVise to BYPASS.

1OMOV-25B AUTO CONTROL -

BYPASS 10A-S22B

1OMOV-27B AUTO CONTROL Rotates 1OMOV-27B AUTO CONTROL BYPASS 1OA-BYPASS 1OA-S23B S23B keylock switch clockwise to BYPASS.

11. Ensure open MIN FLOW VLV 1OMOV- Observes MIN FLOW VLV 10MOV-16B green light off, SAT/UNSAT 16B. red light on.

12. Refer to Section 2.0 for guidance on Refers to Section 2.0 SAT/UNSAT instrument and component usage.

EVALUATOR: Terminate the task at this point.

Task Standard: The Rx is scrammed, both RWR pumps are tripped and isolated, and RHR keylock switches are in BYPASS.

-7 of 8-

HANDOUT Initial Conditions:

A serious fire is in progress in the West Crescent area.

The fire has caused a spurious isolation of HPCI and loss of control power to the HPCI Aux Oil pump.

Initiating Cue The CRS directs you to perform the immediate actions of of AOP-28, Operation During Plant Fires.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 C TASK TITLE: Perform HPCI Full Flow Test (Alt Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 206000 A4.03 (3.1/3.0)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion D Simulated ~ Performed Location: D Plant ~ Simulator DATE PERFORMED: TIME TO COMPLETE: Miriutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER Page 1 of 11

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 C TASK TITLE: Perform HPCI Full Flow Test (Alt Path)

APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required L2J None Comments:

Current Update By:

Date Int Previous Revision Date:

Page 2of11

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 C TASK TITLE: Perform HPCI Full Flow Test (Alt Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-4N, HPCI Quick-Start, lnservice, and Transient Monitoring Test 111. TOOLS AND EQUIPMENT A. Stopwatches IV. SET UP REQUIREMENTS A. Reset the simulator to approx. 99% power (IC-120).

B. Place one loop of RHR in torus cooling mode per OP-13B section D.

C. Start GLAND SEAL CNDSR BLOWER 23P-140.

D. Open HPCI & RCIC TEST VLV TO CST 23MOV-24.

E. Throttle open TEST VALVE TO CST 23MOV-21 for 5 seconds.

F. Ensure Trigger 1 HP06, HPCI Steam Line Break, ~inal: 10. (Event Trigger 1 = hpfd>100)

G. Malfunction HP10, HPCI System Auto Isolation Fail.

H. Markup copy of ST-4N, HPCI Quick-Start, lnservice, and Transient Monitoring Test, completed up to step 8.4.9.

I. Initiate EPIC four-parameter plot TRHPCI.

J. Place 23VM-100 toggle switch to up position.

K. Start SGT Train B with vent on Torus via 27MOV-117, 123, 121.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the*change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at power.

B. Field personnel are briefed and stationed to support performance of ST-4N.

C. One loop of RHR is in Torus Cooling Mode.

D. Another operator is monitoring and controlling Torus level and temperature.

E. Another operator is standing by with a stop watch to perform timing.

F. Torus venting is in progress per OP-37 section E.

Page 3 of 11

- CRITICAL STEP

INITIATING CUE:

Inform the candidate, "The CRS directs you to continue performance of ST-4N, HPCI Quick-Start, lnservice, and Transient Monitoring Test at Step 8.4.9."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of procedure The candidate obtains a controlled copy of ST-4N. SAT/UNSAT ST-4N EVALUATOR: Provide working copy of ST-4N.

2. IF RPV pressure is GREATER THAN Opens 23MOV-16 by rotating control switch clockwise CRITICAL STEP OR EQUAL TO 165 psig, THEN open and determines stroke time to be within limits.

and time OUTBO STM SUPP VLV SAT I UNSAT 23MOV-16.

EVALUATOR CUE: Role Play as stopwatch Operator Opening time secs and report opening time was 7 seconds.

(IST: 5.0 to 8.3)

3. Ensure open OUTBO STM SUPP VL V Observes 23MOV-16 red light on, green light off. SAT I UNSAT 23MOV-16.

4. Verify the following: Utilizes computer and observes EPIC-0-457 indicates SAT/UNSAT OPEN and EPIC-0-458 indicates NFC.

EPIC-0-457 HPCI STM OUTB ISO-C indicates OPEN

EPIC-0-458 HPCI STM OUTB IS0-0 indicates NFC Page 4of11

STEP STANDARD EVALUATION I COMMENT

5. NOTE: Loss of inventory to torus will Reviews procedure NOTE. SAT I UNSAT cause hotwell level will trend down.

Automatic or manual compensation may be required to maintain hotwell level.

6. Perform the following in any order, just Acknowledges cue. SAT I UNSAT before turbine startup:

A. Initiate EPIC manual transient data EVALUATOR CUE: Another operator has initiated capture per CDS0-3.600. EPIC manual transient data capture.

B. IF RPV pressure is GREATER THAN -

OR EQUAL TO 165 psig, AND this test EVALUATOR CUE: If candidate asks about reason for is being performed for Cold Quick-Start test, report that the test is being performed for Cold Once per Cycle purposes ... THEN direct Quick-Start Once per Cycle purposes.

l&C to start all installed transient l&C has started all installed transient recorders at the recorder(s) at desired speed (normally desired speed.

25 mm/sec).

7. IF test is being performed to satisfy SR Determines test is not being performed to satisfy SR SAT/UNSAT 3.5.1.9, THEN RPV pressure must be 3.5.1.9.

>150 psig but <165 psig and HPCI steam supply pressure must be ~135 psig.

EVALUATOR CUE: If candidate asks about reason for test, report that the test is NOT being performed to satisfy SR 3.5.1.9.

Page 5of11

STEP STANDARD EVALUATION I COMMENT

8. Ensure RX power s2530 MWT. Observes Rx power is less than 2530 MWT. SAT I UNSAT

9. Simultaneously perform the following: Performs the following simultaneously: CRITICAL STEP SAT I UNSAT

Open TURB STM SUPP VLV

Opens 23MOV-14 by rotating control switch 23MOV-14. clockwise.

Start AUX OIL PMP 23P-150.

Starts HPCI Aux Oil Pump by rotating control switch clockwise.

IF RPV pressure is GREATER THAN OR EQUAL TO 165 psig, EVALUATOR CUE: Other operators are standing by THEN Start stopwatches. and will control stop watches. If asked, times are in spec.

EVALUATOR NOTE: When HPCI flow rises, Trigger 1 is automatically inserted. This will cause annunciator 09-3-3-12 and 2 to alarm in approximately 10 seconds.

Subsequent verification steps will likely NOT be fully completed before the candidate addresses the alarm and isolates HPCI.

Candidate may proceed directly to JPM Step 13.

Page 6of11

STEP STANDARD EVALUATION I COMMENT

10. IF test is being performed to satisfy Determines test is not being performed to satisfy Step SAT I UNSAT I NA Step Transient Monitoring, THEN Transient Monitoring.

perform the following:

EVALUATOR CUE: If candidate asks about reason for A. Direct l&C to commence null voltage test, report that the test is NOT being performed to trace for approximately 1 to 2 minutes satisfy Step Transient Monitoring.

(cold condition).

B. Obtain and record null voltage from l&C Fluke or multi meter.

11. When HPCI flow rate reaches Acknowledges cue and records response time. SAT I UNSAT I NA GREATER THAN OR EQUAL TO 3400 gpm on 23Fl-108-1, stop the EVALUATOR CUE: The stopwatch has been stopped response time stopwatch. and response time was 20 seconds.

TIME Sec.

~ 60.0 Sec.

Page 7 of 11

STEP STANDARD EVALUATION I COMMENT

12. Verify the following: SAT I UNSAT I NA

Turbine speed stabilized after Observes proper HPCI turbine speed.

startup transient and remained LESS THAN 4200 rpm during the startup transient (23SPl-161 or EPIC TRHPCI speed trace)

Contacts field operator regarding operation of 23HOV-1.

23HOV-1 opens smoothly by local observation EVALUATOR CUE: 23HOV-1 opened smoothly.

Turbine vibration is LESS THAN OR EQUAL TO limits (0.385 IPS) Observes HPCI turbine vibration is less than limits.

Turbine accelerates smoothly (by Observes HPCI turbine accelerated smoothly.

observing TURB SPEED 23SPl-161 OR EPIC TRHPCI speed trace)

Observes HPCI flow rate stabilized ~ 3400 gpm.

HPCI pump discharge flow rate stabilizes at GREATER THAN OR EQUAL TO 3400 gpm on 23Fl-108-1 Observes 23MOV-25 green light on, red light off.

MIN FLOW VLV 23MOV-25 is closed Observes 23AOV-43 green light on, red light off.

STM LINE ORN TO RADW 23AOV-43 is closed Observes 23AOV-42 green light on, red light off.

STM LINE ORN TO RADW 23AOV-42 is closed Page 8of11

STEP STANDARD EVALUATION I COMMENT

13. Respond to annunciator 09-3-3-02, 12 Refers to ARP 09-3-3-02/12 DIV 1/2 AMBIENT TEMP SAT I UNSAT I NA DIV 1 AMBIENT TEMP HIGH. HIGH.

DIV 2 AMBIENT TEMP HIGH EVALUATOR CUE: If asked as NPO to investigate, immediately report that you see a large amount of steam at the Drywell entrance area.

Recognize HPCI failed to automatically isolate.

14. Depress TURB TRIP 23A-S19 Secures HPCI by depressing TURBINE TRIP SAT I UNSAT pushbutton. pushbutton.

EVALUATOR NOTE: Procedural guidance for isolation comes from ARP 09-3-3-02 (DIV 1 AMBIENT TEMP HIGH), OP-15 (HPCI) or EN-OP-115 (CONDUCT OF OPERATIONS) or OSD0-49 (STRATEGIES FOR SUCCESSFUL TRANSIENT MITIGATION).

EVALUATOR CUE: If asked for guidance on how to respond to the alarm\ steam leak condition, direct the candidate to make a recommendation and then carry out that recommendation.

Page 9 of 11

STEP STANDARD EVALUATION I COMMENT

15. Isolate HPCI steam line by ensuring Observes closed \ *manually closes the following SAT I UNSAT closed the following valves: valves:

INBD STM SUPP VLV * *INBD STM SUPP VLV 23MOV-15 CRITICAL STEP 23MOV-15

TURB STOP VL V 23HOV-1

TURB STOP VLV 23HOV-1

OUTBD STM SUPP VLV 12MOV-16

OUTBD STM SUPP VL V 12MOV-16

MIN FLOW VLV 12MOV-25

MIN FLOW VLV 12MOV-25

INBD TORUS SUCT VLV 23MOV-58

INBD TORUS SUCT VLV 23MOV-58

OUTBD TORUS SUCT VL V 23MOV-57

OUTBD TORUS SUCT VLV

- - . STM LINE WARMING ISOL VLV 23MOV-60 23MOV-57

INJ VLV 23MOV-19

STM LINE WARMING ISOL VL V 23MOV-60

INJ VLV 23MOV-19 EVALUATOR: Terminate the task at this point.

Task Standard: HPCI is started for surveillance testing. Steam line break is detected and HPCI inboard steam supply valve is isolated.

Page 10 of 11

HANDOUT Initial Conditions:

The Plant is operating at power.

Field personnel are briefed and stationed to support performance of ST-4N.

One loop of RHR is in Torus Cooling Mode.

Another operator is monitoring and controlling Torus level and temperature.

Another operator is standing by with a stop watch to perform timing.

Torus venting is in progress per OP-37 section E.

Initiating Cue:

The CRS directs you to continue performance of ST-4N, HPCI Quick-Start, lnservice, and Transient Monitoring Test at Step 8.4.9.

Page 11 of 11

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 D TASK TITLE: Reset ARI and Scram, Perform Post Scram Reset Control Rod Position Check APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 212000 A4.14 (3.8/3.8)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion D Simulated ~ Performed Location: D Plant ~ Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 16-1 D TASK TITLE: Reset ARI and Scram, Perform Post Scram Reset Control Rod Position Check APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items 0 Technical Review 0 Additional Information 0 Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 7-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 16-1 D TASK TITLE: Reset ARI and Scram, Perform Post Scram Reset Control Rod Position Check APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-1, Reactor Scram, Current Revision 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Initialize the simulator (IC-128).

B. Ensure the Mode Switch to SHUTDOWN.

C. Ensure ARI is NOT reset.

D. Ensure all scram signals are clear EXCEPT SDIV Hi Level.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. During a Reactor startup, the reactor was scrammed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago due to a Feedwater malfunction.

B. The scram condition has been identified and cleared.

C. All Reactor scram signals are now clear with the exception of the scram discharge volume high level signal.

-3 of 7-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS has directed that you reset the scram per AOP-1."

NOTE: All actions performed at Panel 09-5 STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of The candidate determines where to obtain a controlled copy SAT I UNSAT AOP-1, Reactor Scram. of AOP-1. (Control Room, Merlin)

EVALUATOR: Provide candidate a current copy of AOP-1

2. Select the correct section to The candidate selects Section F.1 of AOP-1. SAT/UNSAT perform the task.

EVALUATOR: Provide candidate a copy of section F.1

3. IF ARI actuated, THEN reset Resets ARI as follows: SAT I UNSAT ARI as follows:

Verify following annunciator Observes annunciators are clear:

clear:

09-4-2-16 (RWR MG A ATWS TRIP)

09-4-2-16 (RWR MG A ATWS TRIP)

09-4-3-14 (RWR MG B ATWS TRIP)

09-4-3-14 (RWR MG B ATWS TRIP)

-4 of 7-

STEP STANDARD EVALUATION I COMMENT

4 Depress pushbutton 1-PB- Depresses pushbutton 1-PB-ARIR at panel 09-5. CRITICAL STEP ARI R at panel 09-5.

SAT I UNSAT

5. Verify closed the following ARI Observes the following ARI valves closed: SAT I UNSAT valves:

(green light on, red light off)

03SOV-201

03SOV-201

03SOV-202

03SOV-202

03SOV-203

03SOV-203

03SOV-204

03SOV-204

03SOV-205

03SOV-205

6. Verify annunciator 09-5-1-35 Observes annunciator 09-5-1-35 ATWS ARI TRIP is clear. SAT I UNSAT ATWS ARI TRIP is clear.

7. Verify annunciator 09-5-1-33 Observes that the annunciator window for annunciator 09 SAT I UNSAT MODE SW IN SHUTDOWN 1-33 is in alarm.

TRIP BYPASSED is in alarm.

8. Place the SDIV HI LVL TRIP Places the SDIV HI LVL TRIP switch in BYPASS. CRITICAL STEP keylock switch in BYPASS. (09-5-1-11 alarms) SAT I UNSAT

9. Place RX SCRAM RESET Places the REACTOR SCRAM RESET selector switch, (5A- CRITICAL STEP switch to Group 2 & 3, then to S5), momentarily to the GP2 and GP3 position then back SAT I UNSAT 1 & 4, spring return to NORM. thru "NORM" to the GP1 and GP4 position then back to "NORM".

-5 of 7-

STEP STANDARD EVALUATION I COMMENT

10. Verify RPS A and B SCRAM Verifies the scram has been reset by ensuring that the SAT I UNSAT GROUPS 1, 2, 3 and 4 lights following lights are lit:

are on.

A. RPS A Scram Groups 1, 2, 3 and 4 on Panel 09-5 B. RPS B Scram Groups 1, 2, 3 and 4 on Panel 09-5

11. Verify closed all scram inlet Observes closed all scram inlet and outlet valves using one SAT/UNSAT and outlet valves using one or or a combination of the following methods: NO Blue scram a combination of the following lights on.

methods:

Blue scram lights or

Local indication .

12. IF any scram inlet or outlet Determines step N\A SAT I UNSAT valve fails to close, then perform the following:

A. Depress the following pushbuttons:

MANUAL SCRAM A

MANUAL SCRAM B EVALUATOR: Terminate the task at this point.

Task Standard: The Reactor scram is reset.

-6 of 7-

HANDOUT Initial Conditions:

During a Reactor startup, the reactor was scrammed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago due to a Feedwater malfunction.

The scram condition has been identified and cleared.

All Reactor scram signals are now clear with the exception of the scram discharge volume high level signal.

Initiating Cue:

The CRS has directed that you reset the scram per AOP-1.

-7 of 7-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 E TASK TITLE: Place Shutdown Cooling in Service APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 205000 A4.01 (3.7/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion D Simulated [8J Performed Location: D Plant [8J Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 16-1 E TASK TITLE: Place Shutdown Cooling in Service APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items 0 Technical Review 0 Additional Information 0 Questions and Answers 0 Validation 0 Procedural Change Required ISi None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 16-1 E TASK TITLE: Place Shutdown Cooling in Service APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-30, Loss of Shutdown Cooling Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to a low-power IC (IC-128).

B. Ensure RHR B was initially in Shutdown Cooling lineup but is now isolated by closing valves 258, 17, and 18.

C. Ensure the following tags are hanging:

RHR KEEP-FULL PMP 1OP-28 control switch - in STOP with yellow tag

MIN FLOW VLV 10MOV-168 control switch -yellow tag

RHR TEST TORUS CLG & SPRAY 1OMOV-398 - yellow tag

RWR isolation valves: 02RWR-43\53 (A\B) - yellow tags V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

8. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. RHR B was in Shutdown Cooling.

8. A spurious isolation signal caused Shutdown Cooling to isolate.

C. The cause of the isolation signal has been determined and corrected.

D. No LOCA has occurred.

-3 of 8-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to restore Shutdown Cooling using RHR B per AOP-30 Attachment 1."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of AOP-30 Attachment 1. SAT/UNSAT AOP-30 Attachment 1.

2. Determine and correct cause. Determines cause has been corrected per initial conditions. SAT I UNSAT

3. For conditions other than Acknowledges step and continues in AOP-30 Attachment 1. SAT I UNSAT those listed in this subsection, -

restore either loop of SOC per Section D of OP-130.

4. IF a SOC isolation has not Determines a SOC isolation has occurred per initial SAT/UNSAT occurred, AND loss of coolant conditions.

is not indicated, THEN perform any of the following as appropriate ...

5. IF shutdown cooling was lost Determines the SOC isolation was NOT due to loss of an SAT/UNSAT due to a shutdown cooling RPS bus.

isolation caused by a loss of an RPS bus(s) ...

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

6. IF a SOC isolation has Observes Reactor pressure is less than 70 psig. SAT I UNSAT occurred, AND loss of coolant is not indicated, THEN perform the following:

Verify RPV pressure is LESS THAN 70 psig.

7. Place control switch for OW Rotates DW FLOOR ORN 20AOV-83 control switch CRITICAL STEP FLOOR ORN 20AOV-83 in counterclockwise to CLOSE. SAT I UNSAT CLOSE.

8. Place control switch for OW Rotates OW EQUIP ORN 20AOV-95 control switch CRITICAL STEP EQUIP ORN 20AOV-95 to counterclockwise to CLOSE, then releases back to AUTO. SAT I UNSAT CLOSE, spring return to AUTO.

9. Verify the following relays Dispatches operator to verify relays 16A-K28 and -K50 SAT I UNSAT indicate ON: indicate ON.

16A-K28 in panel 09-41

16A-K50 in panel 09-42 EVALUATOR CUE: Relays 16A-K28 and -K50 indicate ON.

10. Simultaneously rotate the Simultaneously rotates PCIS VLV RESET switches 16A- CRITICAL STEP following PCIS VL V RESET S32 and -S33 to both RESET position, then releases back SAT/UNSAT switches to both RESET to NOR.

positions, spring return to NOR:

16A-S32

16A-S33

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

11. Verify the following relays Dispatches operator to verify relays 16A-K29, -K53, -K30, SAT/UNSAT indicate ON: and -K54 indicate ON.

16A-K29 in panel 09-41

16A-K53 in panel 09-41 EVALUATOR CUE: Relays 16A-K29, -K53, -K30, and -K54

16A-K30 in panel 09-42 indicate ON .

16A-K54 in panel 09-42

12. IF white HI OW PRESS OR Observes white HI OW PRESS OR LO LVL CLOSE OF SAT I UNSAT LO LVL CLOSE OF 1OMOV- 1OMOV-258 IN SHUTDOWN CLG 1OA-DS85A(8) light is 25A(8) IN SHUTDOWN CLG not lit.

1OA-DS85A(8) light is on, THEN reset logic as follows:

13. Ensure open HX A(8) 8YP Observes 1OMOV-668 green light off, red light on. SAT/UNSAT VLV 10MOV-66A(8).

14. Open SHUTDOWN CLG Opens 10MOV-18 by rotating control switch clockwise. CRITICAL STEP SUCT 10MOV-18. SAT I UNSAT

15. Open SHUTDOWN CLG Opens 10MOV-17 by rotating control switch clockwise. CRITICAL STEP SUCT 10MOV-17. SAT/UNSAT

16. Ensure closed HX A(8) Closes 10MOV-128 by rotating control switch CRITICAL STEP OUTLET VLV 10MOV-12A(B). counterclockwise. SAT I UNSAT

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

17. Ensure RPV water level is Observes Reactor water level is above 215 inches. SAT I UNSAT GREATER THAN 215 inches.

18. Start RHR pump that was in Starts RHR pump 8 by rotating control switch clockwise. CRITICAL STEP service prior to isolation. SAT/UNSAT

19 Open LPCI IN8D INJ VLV Opens 1OMOV-258 by rotating control switch clockwise. CRITICAL STEP 1OMOV-25A(8). SAT/UNSAT EVALUATOR CUE: Direct the candidate to establish Reactor coolant temperature control in a band of 120-140°F.

20. Establish normal temperature Throttles open 1OMOV-128 by rotating control switch CRITICAL STEP control per Section E of OP- clockwise. SAT I UNSAT 130.

EVALUATOR: Terminate the task at this point.

Task Standard: SDC system is restored to service with RHR pump B running.

-7 of 8-

HANDOUT Initial Conditions:

RHR B was in Shutdown Cooling.

A spurious isolation signal caused Shutdown Cooling to isolate.

The cause of the isolation signal has been determined and corrected.

No LOCA has occurred.

Initiating Cue:

The CRS directs you to restore Shutdown Cooling using a

RHR per AOP-30 Attachment 1.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 F TASK TITLE: Recover Turbine Building Ventilation After Exhaust Duct Radiation Monitor Trip Isolation APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 288000 A4.01 (3.1/2.9)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion D Simulated ~ Performed Location: D Plant ~ Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 16-1 F TASK TITLE: Recover Turbine Building Ventilation After Exhaust Duct Radiation Monitor Trip Isolation APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2of10-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 16-1 F TASK TITLE: Recover Turbine Building Ventilation After Exhaust Duct Radiation Monitor Trip Isolation APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-52, Turbine Building Ventilation Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset the simulator to an IC with the following conditions (IC-128):

Ensure 'A' Turbine Building Supply/Exhaust Fans are in service and 'B' are in standby.

Fail both TBV exhaust radiation monitors upscale using malfunctions RM01 :23 and RM01 :24.

Allow Turbine Building Ventilation to respond to the isolation.

Delete the RM01 malfunctions.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A steam leak in the Turbine Building and a loss of coolant accident in the Drywell has occurred.

B. Turbine Building Ventilation isolated due to high exhaust radiation monitor readings.

C. The steam leak has been isolated by closing the MSIVs.

D. The Turbine Building Ventilation exhaust radiation monitors have returned to normal background readings.

-3 of 10-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to recover Turbine Building Ventilation per OP-52 Section G.9. Place the 'B' Turbine Building Ventilation Supply and Exhaust Fans in service."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-52. SAT I UNSAT OP-52.

2. Select the correct section to Selects Section G.9. SAT I UNSAT perform the task.

3. Ensure control switch for each *Rotates TURB BLDG SUPP 67FN-5A control switch CRITICAL STEP of the following fans is green counterclockwise to green flag.

SAT I UNSAT flagged at panel 09-75:

Observes TURB BLDG SUPP 67FN-5B control switch is

TURB BLDG SUPP 67FN-green flagged.

5A

TURB BLDG SUPP 67FN-

Rotates TURB BLDG EXH 67FN-6A control switch 5B counterclockwise to green flag.

TURB BLDG EXH 67FN-6A Observes TURB BLDG EXH 67FN-6B control switch is green flagged.

TURB BLDG EXH 67FN-6B

-4 of 10-

STEP STANDARD EVALUATION I COMMENT

4. IF there is no steam flowing Determines there is no steam flow through the main steam CRITICAL STEP through main steam lines, lines. SAT I UNSAT THEN ensure control switch for each of the following fans is green flagged at panel 09- *Rotates STM TUN EXH 67FN-23A control switch 75: counterclockwise to green flag.

STM TUN EXH 67FN-23A I Observes STM TUN EXH 67FN-23B control switch is green flagged.

STM TUN EXH 67FN-23B

5. Verify 1?RM-431 radiation Observes 1?RM-431 indicates less than 25,000 cpm on SAT/UNSAT level is LESS THAN upscale EPIC or dispatches operator to verify indication at 67HV-1.

trip setpoint (25,000 cpm).

EVALUATOR CUE: If dispatched to verify 1?RM-431 indication, report it indicates approximately 50 cpm.

6. Depress the following Dispatches operator to depress the following pushbuttons at CRITICAL STEP pushbuttons at panel 67HV-1: panel 67HV-1: SAT I UNSAT

RESET pushbutton below

RESET pushbutton below white HIGH RADIATION -

white HIGH RADIATION - TRIP A light TRIPA light

ALARM RESET pushbutton on 1?RM-431 TURB BLDG

ALARM RESET EXH RAD MONITOR pushbutton on 1?RM-431 TURB BLDG EXH RAD MONITOR EVALUATOR CUE: The directed pushbuttons have been depressed.

-5 of 10-

STEP STANDARD EVALUATION I COMMENT

7. Verify white HIGH Contacts operator to verify status of white HIGH SAT/UNSAT RADIATION -TRIP A light is RADIATION - TRIP A light at panel 67HV-1.

off at panel 67HV-1.

EVALUATOR CUE: The white HIGH RADIATION - TRIP A light is OFF at panel 67HV-1.

8. Verify 17RM-432 radiation Observes 17RM-432 indicates less than 25,000 cpm on SAT/UNSAT level is LESS THAN upscale EPIC or dispatches operator to verify indication at 67HV-1.

trip setpoint (25,000 cpm).

EVALUATOR CUE: If dispatched to verify 17RM-432 indication, report it indicates approximately 50 cpm.

9. Depress the following Contacts operator to depress the following pushbuttons at CRITICAL STEP pushbuttons: panel 67HV-1: SAT/UNSAT

RESET pushbutton below

RESET pushbutton below white HIGH RADIATION -

white HIGH RADIATION - TRIP Blight TRIP Blight

ALARM RESET pushbutton on 17RM-432 TURB BLDG

ALARM RESET EXH RAD MONITOR pushbutton on 17RM-432 TURB BLDG EXH RAD MONITOR EVALUATOR CUE: When dispatched, direct applicant to call the simulator booth for these actions.

BOOTH OPERATOR: When requested, insert trigger 30.

EVALUATOR CUE: Once annunciator 09-75-2-22 has cleared, report that the directed pushbuttons have been depressed.

-6 of 10-

STEP STANDARD EVALUATION I COMMENT

10. Verify white HIGH Contacts operator to verify status of white HIGH SAT/UNSAT RADIATION - TRIP Blight is RADIATION - TRIP Blight at panel 67HV-1.

off.

EVALUATOR CUE: The white HIGH RADIATION - TRIP B light is OFF at panel 67HV-1.

11. Verify annunciator HV-1-1-23 Contacts operator to verify status of annunciator HV-1-1-23. SAT/UNSAT TURBINE BLDG EXHAUST RAD MONITOR HI/INOPERATIVE is clear. EVALUATOR CUE: Annunciator HV-1-1-23 is clear.

12. Verify annunciator 09-75-2-22 Observes annunciator 09-75-2-22 is clear. SAT I UNSAT TURB EXH RAD MON INOP -

OR HI is clear.

13. Place turbine building exhaust Starts TURB BLDG EXH 67FN-6B by rotating its control CRITICAL STEP fans in normal operating switch clockwise to ON, spring return to normal. SAT I UNSAT lineup as follows at panel 09-75:

NOTE: The turbine building exhaust fan will start when its outlet damper is open.

Start TURB BLDG EXH 67FN-6A or 6B by placing its control switch to ON, spring return to normal.

-7 of 10-

STEP STANDARD EVALUATION I COMMENT

14. Ensure control switch for the Observes TURB BLDG EXH 67FN-6A control switch is SAT/UNSAT other turbine building exhaust green flagged.

fan (TURB BLDG EXH 67FN-6A or 6B) is green flagged.

15. Place turbine building supply Starts TURB BLDG SUPP 67FN-5B by rotating its control CRITICAL STEP fans in normal operating switch clockwise to ON, spring return to normal. SAT/UNSAT lineup as follows at panel 09-75:

NOTE: The turbine building supply fan will start when its outlet damper is open.

Start TURB BLDG SUPP 67FN-5A or 5B by placing its control switch to ON, spring return to normal.

16. Ensure control switch for the Observes TURB BLDG SUPP 67FN-5A control switch is SAT/UNSAT other turbine building supply green flagged.

fan (TURB BLDG SUPP 67FN-5A or 5B) is green flagged.

-8 of 10-

STEP STANDARD EVALUATION I COMMENT

17. Place steam pipe tunnel Starts STM TUN EXH 67FN-23B by rotating its control CRITICAL STEP exhaust fans in normal switch clockwise to ON, spring return to normal. SAT I UNSAT operating lineup as follows at panel 09-75:

NOTE: The steam pipe tunnel exhaust fan outlet damper will open after fan is started.

Ensure STM TUN EXH 67FN-23A or 23B is running with its control switch red flagged.

18. Ensure control switch for the Observes STM TUN EXH 67FN-23A is green flagged with SAT I UNSAT other steam pipe tunnel green light on, red light off.

exhaust fan (STM TUN EXH 67FN-23A or 23B) is green flagged.

EVALUATOR: Terminate the task at this point.

Task Standard: The Turbine Building Ventilation exhaust radiation monitor trips are reset. The 'B' Turbine Building Ventilation supply and exhaust fans are in service. The 'A' Turbine Building Ventilation supply and exhaust fans are in standby. The 'B' steam tunnel exhaust fan is in service and the 'A' steam tunnel exhaust fan is in standby.

-9 of 10-

HANDOUT Initial Conditions:

A steam leak in the Turbine Building and a loss of coolant accident in the Drywall has occurred.

Turbine Building Ventilation isolated due to high exhaust radiation monitor readings.

The steam leak has been isolated by closing the MSIVs.

The Turbine Building Ventilation exhaust radiation monitors have returned to normal background readings.

Initiating Cue:

The CRS directs you to recover Turbine Building Ventilation per OP-52 Section G.9.

Place the 'B' Turbine Building Ventilation Supply and Exhaust Fans in service.

-10of10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 G TASK TITLE: Supply Ventilation Loads with Emergency Service Water APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 400000 A4.01 (3.1/3.0)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion 0 Simulated C2l Performed Location: 0 Plant C2] Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PE;RFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 16-1 G TASK TITLE: Supply Ventilation Loads with Emergency Service Water APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 7-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRG 16-1 G TASK TITLE: Supply Ventilation Loads with Emergency Service Water APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-11, Loss of RBCLC B. OP-21, Emergency Service Water Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset the simulator to IC-130.

v. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A complete loss of Reactor Building Closed Loop Cooling (RBCLC) has occurred.

B. AOP-11 (Loss of RBCLC) is being executed.

C. A loss of coolant accident (LOCA) has NOT occurred.

D. Emergency Service Water (ESW) is necessary for drywell cooling.

-3 of 7-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you supply ESW to all Drywell Coolers per AOP-11 Section F.2.4."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of AOP-11. SAT/UNSAT AOP-11.

2. Select the correct section to Selects Section F.2.4. SAT I UNSAT perform the task.

3. CAUTION: Supplying ESW Candidate reads CAUTION. SAT/UNSAT or re-injecting RBC to drywell loads during a LOCA could cause failure of the RBCLC piping due to water hammer and jeopardize primary containment integrity. During LOCA conditions, this lineup is prohibited.

-4 of 7-

STEP STANDARD EVALUATION I COMMENT

4. IF ESW is necessary for Determines ESW is necessary for drywell cooling. SAT I UNSAT drywell cooling as determined by the CRS, THEN perform the following:

5. Verify a LOCA has not Determines a LOCA condition does NOT exits per Initiating SAT/UNSAT occurred. Cue and/or observing Plant parameters.

6. To supply Drywell Cooler A, 1) Starts 46P-2B by rotating its control switch on Panel CRITICAL STEP perform the following: 09-6 clockwise to ON, spring return to normal, red SAT I UNSAT flag.

1) Ensure 46P-2B (ESW Pump B) in service.

7. 2) Open ESW TO OW 2) Opens 15MOV-102 by rotating its control switch on CRITICAL STEP CLR 15MOV-102. Panel 09-75 clockwise to ON, spring return to SAT I UNSAT normal, red flag.

-5 of 7-

STEP STANDARD EVALUATION I COMMENT

8. To supply Drywell Cooler B, 1) Starts 46P-2A by rotating its control switch on Panel CRITICAL STEP perform the following: 09-6 clockwise to ON, spring return to normal, red SAT/UNSAT flag.

1) Ensure 46P-2A (ESW Pump A) in service.

9. 2) Open ESW TO DW 2) Opens 15MOV-103 by rotating its control switch on CRITICAL STEP CLR 15MOV-103. Panel 09-75 clockwise to ON, spring return to SAT I UNSAT normal, red flag.

EVALUATOR: Terminate the task at this point.

Task Standard: ESW is being supplied to Drywell Coolers A and B.

-6 of 7-

HANDOUT Initial Conditions:

A complete loss of Reactor Building Closed Loop Cooling (RBCLC) has occurred.

AOP-11 (Loss of RBCLC) is being executed.

A loss of coolant accident (LOCA) has NOT occurred.

Emergency Service Water (ESW) is necessary for drywell cooling.

Initiating Cue:

The CRS directs you supply ESW to all Drywell Coolers per AOP-11 Section F.2.4.

-7 of 7-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC 16-1 H TASK TITLE: Perform Main Turbine Roll APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 241000 A4.11 (3.1/3.1)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion D Simulated IZI Performed Location: D Plant IZI Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST RO NRC 16-1 H TASK TITLE: Perform Main Turbine Roll APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required [g] None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 10-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION RO NRC 16-1 H TASK TITLE: Perform Main Turbine Roll APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-9, Main Turbine Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset the simulator to IC-129.

B. Place EPIC TGO screen up on Slave 2.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A plant startup is in progress.

B. The Main Turbine is ready to be rolled per OP-9 (Main Turbine).

C. An operator is stationed on the turbine deck.

D. Another operator will assist while performing OP-9 step D.8.6.e (verifying Turbine trip indications).

-3 of 10-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to roll the Main Turbine per OP-9 section D.8."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-9. SAT I UNSAT OP-9.

2. Select the correct section to Selects Section D.8. SAT I UNSAT perform the task.

3. CAUTIONS: Candidate reads CAUTIONS. SAT I UNSAT Operating the Main Turbine at low speed could result in large rotor bows being generated by rubbing with no indication of high vibration being evident from Turbine Supervisory Instrumentation.

If rotor bowing caused by rubbing is allowed to occur, damage to buckets, covers, and possibly a permanently bowed rotor could occur. -

Operating the Main Turbine at a steady-state speed LESS THAN 800 rpm for GREATER THAN 5 minutes could cause rotor bowing due to rubbing.

-4 of 10-

STEP STANDARD EVALUATION I COMMENT

4. Station an operator on turbine Recalls an operator is stationed on turbine deck per SAT I UNSAT deck. lniti_ating Cue. -

5. Verify open ISV-1, 2, 3, and 4. Verifies ISV1, 2, 3, 4 are open by observing position SAT I UNSAT indicators.

6. Depress 100 (RPM) 100 (RPM) pushbutton depressed. CRITICAL STEP pushbutton. SAT I UNSAT

7. Verify the following valves Verifies TSV1, 2, 3, 4 are open by observing position SAT I UNSAT open: indicators.

TSV-1, 2, 3, and 4 Verifies IV1, 2, 3, 4 are open by observing position

IV-1, 2, 3, and 4 indicators .

-5 of 10-

STEP STANDARD EVALUATION I COMMENT

8. Immediately perform main turbine trip test as follows:

a) Depress both TRIP

Depresses both TRIP pushbuttons CRITICAL STEP pushbuttons.

SAT I UNSAT b) Verify closed the following valves: Verifies closed the following valves by observing position SAT I UNSAT indicators:

TSV-1, 2, 3, and 4

TCV-1, 2, 3, and 4

TSV-1, 2, 3, and 4

ISV-1, 2, 3, and 4

TCV-1, 2, 3, and 4

IV-1, 2, 3, and 4

ISV-1, 2, 3, and 4

IV-1, 2, 3, and 4

9. Immediately reset main turbine trip as follows:

a. Verify main turbine trip Observes main turbine trip condition annunciators at SAT I UNSAT condition annunciators at annunciator window section 09-5-2 are clear.

annunciator window section 09-5-2 are clear.

EVALUATOR NOTE: Annunciator 09-5-2-9 will be in alarm until the Turbine trip is reset.

b. Ensure ALL VALVES Observes ALL VALVES CLOSED pushbutton backlight is SAT I UNSAT CLOSED pushbutton backlight on.

is on.

c. Verify VACUUM NORMAL light is on. Observes VACUUM NORMAL light is on. SAT I UNSAT

-6 of 10-

STEP STANDARD EVALUATION I COMMENT

10. NOTE: TRIP RESET Reads NOTE. SAT/UNSAT pushbutton will be held depressed until Step D.8.6f.

11. Depress and hold TRIP Depresses and holds TRIP RESET pushbutton until Step CRITICAL STEP RESET pushbutton. D.8.6.f. SAT/UNSAT

12. Verify the following: Evaluator Cue: Inform candidate that ALL items in this SAT/UNSAT verification step are satisfactory.

RESETTING light is on

ISV-1, 2, 3, and 4 open

The following valves remain closed:

- TSV-1, 2, 3, and 4

- TCV-1, 2, 3, and 4

-IV-1, 2, 3, and 4

RESET light is on at RESET pushbutton

RESET light is on at MECHANICAL TRIP section

RESET light is on at CNDSR VAC TRIP STATUS section

TRIPPED light is off at MECHANICAL TRIP section

TRIPPED light is off at CNDSRVAC TRIP STATUS section

Annunciator 09-5-2-9 MAIN TURB TRIP clears

-7of10-

STEP STANDARD EVALUATION I COMMENT

13 Release TRIP RESET Releases the TRIP RESET pushbutton after confirmation of CRITICAL STEP pushbutton. above Evaluator Cue. SAT/UNSAT

14 Depresses MEDIUM Depresses the MEDIUM STARTUP RATE pushbutton. CRITICAL STEP STARTUP RATE pushbutton. SAT/UNSAT Evaluator Cue: Another Operator will monitor parameters listed in Step D.8.7.

Evaluator Cue: Step D.8.8 has been completed SAT.

-8 of 10-

15 Roll Main Turbine as follows: SAT I UNSAT

a. Verify open ISV 1, 2, 3, and 4. a. Observes ISV 1, 2, 3, and 4 are open.

b. Depress 100 (RPM) pushbutton. b. Depresses the 100 RPM pushbutton. CRITICAL STEP

c. Verify the following valves c. Observes TSV and IV 1,2,3,4 are open.

open:

. TSV 1, 2, 3, and 4

IV 1, 2, 3, and 4

d. Verify servo current meter indicator d. Observes meter needles for TCV-1,2,3,4 needle moves for turbine control valves move.

TCV-1, TCV-2 and TCV-3.

e. Verify TURB TURN GEAR 94TTG-3 is e. Observes 94TTG-3 is disengaged (right disengaged. most red light ON only).

f. Place control switch for TURB TURN f. Places control switch 94TTG-3 in Trip.

GEAR 94TTG-3 to TRIP, spring return to normal.

g. Verify TURB TURN GEAR 94TTG-3 is g. Verifies 94TTG-3 has stopped.

stopped. Evaluator Cue: 94TTG-3 has stopped.

h. Begin walkdown of main turbine; listen for h. Evaluator Cue: Walkdown has rubbing or unusual noise. commenced.

EVALUATOR: Terminate the task at this point.

Task Standard: The Main Turbine has been rolled and speed is increasing.

-9 of 10-

HANDOUT Initial Conditions:

A plant startup is in progress.

The Main Turbine is ready to be rolled per OP-9 (Main Turbine).

An operator is stationed on the turbine deck.

Another operator will assist while performing OP-9 step D.8.6.e (verifying Turbine trip indications).

Initiating Cue:I "The CRS directs you to roll the Main Turbine per OP-9 section D.8."

-10of10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC I TASK TITLE: Vent Torus to Lower Primary Containment APPL. TO JPM NUMBER Pressure (Alt Path)

REV: DATE: NRC KIA SYSTEM NUMBER: 295010 AA1.05 (3.1/3.4)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

~--------------

JPM Completion ~ Simulated D Performed Location: ~ Plant D Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC I TASK TITLE: Vent Torus to Lower Primary Containment APPL. TO JPM NUMBER Pressure (Alt Path)

Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required [gl None Comments:

Current Update By:

Date Int Previous Revision Date:

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC I TASK TITLE: Vent Torus to Lower Primary Containment APPL. TO JPM NUMBER Pressure (Alt Path)

I. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. EP-6, POST ACCIDENT CONTAINMENT VENTING AND GAS CONTROL 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Current copy of EP-6 including Attachment 1.

V. EVALUATOR NOTES A. The candidate should, at a'minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. INITIAL CONDITIONS A. An event has occurred whi~h requires venting the containment.

B. The EOPs have been entered.

C. Action to preclude the failure of containment must be completed.

D. One train of SGT is in service. The other train of SGT is secured.

E. Containment purge is NOT in progress.

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to vent the Torus using EP-6, Section 5.7 "Venting Containment". Start at step 5.7.6."

NOTE: Unless otherwise noted, all controls are located on Panel 27PCP in the Relay Room.

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of procedure Applicant obtains a controlled copy of procedure EP-6 SAT/UNSAT EP-6. from: the Relay Room equipment box or Control Room or MERLIN.

EVALUATOR: Evaluator to provide working copy.

2. Reviews prerequisites, precautions and Reviews applicable portions of procedure. SAT/UNSAT special instructions associated with the procedure.

3. Selects section 5.7, Venting Selects the correct section of the procedure to be SAT/UNSAT Containment. performed.

4. NOTE: Reviews Note and selects step 5.7.6 to perform as SAT I UNSAT Steps 5.7.6 and 5.7.7 may be directed.

performed and repeated in any order to alternate between torus and drywell venting. Torus venting is preferred. - -

STEP STANDARD EVALUATION I COMMENT

5. {Step 5. 7 .6) Verifies Torus pressure is less than PCPL and Torus SAT/UNSAT IF Torus will be vented THEN perform level is less than 29.5 ft.

the following:

Verify torus pressure is LESS THAN PCPL Verify primary containment water - EVALUATOR CUE: lf\when candidate inquires about

pressure and level, inform the candidate that Torus level is LESS THAN 29.5 feet.

Pressure is 50 psig and Primary Containment Water

While venting torus, frequently Level is 29.0 ft.

monitor torus pressure and primary containment water level.

IF primary containment water level reaches 29.5 feet while venting the torus, THEN vent drywell per Step 5.7.7.

STEP STANDARD EVALUATION I COMMENT

5. cont. (Step 5.7.6.D) Candidate places TORUS EXH INNER BYP VLV CRITICAL STEP

Open TORUS EXH INNER BYP 27MOV-117 control switch to the OPEN position.

SAT I UNSAT VLV 27MOV-117.

EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.

(Step 5.7.6.E) Candidate places TORUS EXH OUTER BYP VLV CRITICAL STEP

Open TORUS EXH OUTER BYP 27MOV-123 control switch to the OPEN position.

SAT I UNSAT VLV 27MOV-123.

EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.

EVALUATOR CUE: After 27MOV-117 & 123 are open, inform the candidate that the control room has called to inform the candidate that Primary Containment Water Level is 30 ft .

EVALUATOR NOTE: Candidate should recall and invoke the IF\ THEN statement of EP-6 Step 5.7.6.C

STEP STANDARD EVALUATION I COMMENT (Step 5.7.6.F} For each valve, candidate locates its red/green position SAT I UNSAT

Ensure closed the following valves: lights and indicates it should be closed.

0 OW EXH OUTER BYP VL V 27MOV-113.

EVALUATOR CUE: When candidate inquires about 0 OW EXH INNER BYPASS VLV light status, inform the candidate the green light is on, 27MOV-122. red light is off.

0 OW EXH INNER ISOL VLV 27AOV-113.

0 OW EXH OUTER ISOL VL V 27AOV-114.

6. (Step 5.7.6.C) Candidate refers to section 5.7.7 SAT I UNSAT IF primary containment water level reaches 29.5 feet while venting the torus, THEN vent drywell per Step EVALUATOR CUE: If candidate wants direction from 5.7.7. the control room, inform the candidate that for the purposes of this JPM, no further guidance can be given.

STEP STANDARD EVALUATION I COMMENT

7. (Step 5. 7. 7) Verifies Torus pressure is less than PCPL. SAT I UNSAT IF drywell will be vented, THEN perform the following:

Verify torus pressure is BELOW EVALUATOR CUE: lf\when candidate inquires about PCPL pressure and level, inform the candidate that Torus Pressure is 50 psig and Primary Containment Water Level is 30.0 ft (Step 5.7.7.B) Candidate places OW EXH OUTER BYP VL V 27MOV- CRITICAL STEP

Open OW EXH OUTER BYP VLV 113 control switch to the OPEN position.

SAT I UNSAT 27MOV-113 EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.

(Step 5.7.7.C) - Candidate places OW EXl:l INNER BYPASS VLV CRITICAL STEP

Open OW EXH INNER BYPASS 27MOV-122 control switch to the OPEN position.

SAT I UNSAT VLV 27MOV-122.

EVALUATOR CUE: When candidate indicates placing the control switch to open, inform the candidate that the green light is off, red light is on.

STEP STANDARD EVALUATION I COMMENT 7 cont. (Step 5.7.7.D)

Ensure closed the following valves:

0 TORUS EXH INNER Candidate places TORUS EXH INNER BYP VLV CRITICAL STEP BYP VLV 27MOV-117 27MOV-117 control switch to the CLOSE position.

SAT/UNSAT EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on, red light is off.

0 TORUS EXH OUTER Candidate places TORUS EXH OUTER BYP VLV CRITICAL STEP

BYP VLV 27MOV-123 27MOV-123 control switch to the CLOSE position.

SAT/UNSAT EVALUATOR CUE: When candidate indicates placing the control switch to close, inform the candidate that the green light is on, red light is off.

0 TORUS EXH INNER For each valve, candidate locates its red/green position SAT/UNSAT ISOL VLV 27AOV-117 lights and indicates it should be closed.

0 TORUS EXH OUTER ISOL VLV 27AOV-118 EVALUATOR CUE: When candidate inquires about light status, inform the candidate the green light is on, red light is off.

STEP STANDARD EVALUATION I COMMENT

8. (Step 5.7.7.E) EVALUATOR CUE: Inform candidate that current rate

IF it becomes necessary to raise of pressure reduction is acceptable.

vent rate, AND torus pressure is LESS THAN PCPL, THEN attempt to open the following valves:

0 DW EXH INNER ISOL VLV 27AOV-113 0 DW EXH OUTER ISOL VL V 27AOV-114 EVALUATOR: Terminate the JPM at this point.

Task Standard: Valving is repositioned to support the Containment vented in accordance with EP-6.

HANDOUT Initial Conditions:

An event has occurred which requires venting the containment.

The EOPs have been entered.

Action to preclude the failure of containment must be completed.

One train of SGT is in service. The other train of SGT is secured.

Containment purge is NOT in progress.

Initiating Cue:

The CRS directs you to vent the Torus using EP-6, Sectior:i 5. 7 (Venting Containment).

Start at step 5.7.6.

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC J TASK TITLE: Vent the Scram Air Header APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 400000 2.4.35 (3.8/4.0)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 13 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion ~ Simulated D Performed Location: ~ Plant D Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO 16-1 NRC J TASK TITLE: Vent the Scram Air Header APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required [2] None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 9-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO 16-1 NRC J TASK TITLE: Vent the Scram Air Header APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-3, Backup Control Rod Insertion 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. None V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstra~e proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. INITIAL CONDITIONS A. A failure to scram has occurred.

B. Numerous control rods have failed to insert.

C. EOP-3, Failure to Scram, is being executed.

D. Scram Air Header pressure is 70 psig and steady.

E. EP-3 (Backup Control Rod Insertion) success path is to vent the Scram Air Header.

-3 of 9-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to vent the Scram Air Header per EP-3 section 5.3."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Applicant would obtain a controlled copy of EP-3 from SAT/UNSAT EP-3. the Control Room or CRD venting rig equipment box or Relay Room equipment box or MERLIN.

EVALUATOR: Provide a working copy of EP-3.

2. Select the correct section to Selects Section 5.3 of EP-3. SAT I UNSAT perform the task.

EVALUATOR NOTE: All remaining actions of this JPM are simulated performed on Reactor Building elevation 272' in the southwest corner.

-4 of 9-

STEP STANDARD EVALUATION I COMMENT

3. (Step 5.3.1) Ensure open the Ensures open 03CRD-2028 and 03CRD-2029 by: SAT I UNSAT following valves:

For initially closed valve, simulates rotating

03CRD-2028 (control rod drive handwheel counterclockwise until it reaches a system inlet instrument air filter hard stop.

278 outlet isol valve) . .

For initially open valve, simulates rotating

03CRD-2029 (control rod drive handwheel to check position.

system inlet instrument air filter 27 A outlet isol valve) EVALUATOR NOTE: One of these valves is initially open and one is initially closed.

EVALUATOR CUE: For the closed valve, the indicated handwheel is turned in the indicated direction and reaches a hard stop. For the open valve, the indicated handwheel will not move counterclockwise, but will move clockwise.

4. (Step 5.3.2) Close the following Closes the following valves by simulating rotating CRITICAL STEP valves: handwheel clockwise until it reaches a hard stop: SAT I UNSAT

03CRD-2030 (control rod drive

03CRD-2030 system inlet instrument air filter

03CRD-2031 27 A inlet isol valve)

EVALUATOR NOTE: If only one filter is aligned to the

03CRD-2031 (control rod drive scram air header based on the candidate's actions in system inlet instrument air filter JPM step 3, then it is only critical for that filter's inlet 278 inlet isol valve) valve to be closed.

EVALUATOR CUE: For each valve, the indicated handwheel is turned in the indicated direction and reaches a hard stop.

-5 of 9-

STEP STANDARD EVALUATION I COMMENT

5. {Step 5.3.3) Open scram air filter Opens scram air filter drain valves by simulating CRITICAL STEP drain valve on both scram air filters rotating valve operators counterclockwise. SAT/UNSAT (valve located on bottom of filter).

EVALUATOR NOTE: Valve 03F-27A is a ball valve and valve 03F-27B is a petcock valve.

EVALUATOR NOTE: It is only critical for one drain valve to be opened. If only one filter is aligned to the scram air header based on the candidate's actions in JPM step 3, then it is only critical for that filter's drain valve to be opened.

EVALUATOR CUE: For each valve, the indicated handwheel is turned in the indicated direction and reaches a hard stop. Flow noise is heard through the valve(s).

6. {Step 5.3.4) Verify scram air Observes indication on 03Pl-229. SAT/UNSAT header pressure lowers to zero psig on 03Pl-229 (HCU scram pilot valve air hdr press indic). - EVALUATOR CUE: Indicate 0 psig on 03Pl-229. If asked, no more flow noise is heard through the drain valves.

EVALUATOR CUE: The control room reports that all control rods are full in. If asked, it is desired to restore the scram air header.

-6 of 9-

STEP - STANDARD EVALUATION I COMMENT

7. (Step 5.3.5) WHEN control rods no Closes both scram air filter drain valves by simulating CRITICAL STEP longer move inward, restore scram rotating valve operators clockwise. SAT I UNSAT air header as follows:

Close scram air filter drain EVALUATOR NOTE: It is only critical that any drain valve on both scram air filters. valve that was opened in JPM step 5 be closed.

EVALUATOR CUE: For each valve, the indicated valve operator is turned in the indicated direction and reaches a hard stop.

8. (Step 5.3.5.B) Open the following Opens both of the following valves by simulating CRITICAL STEP valves: rotating the handwheel counterclockwise. SAT I UNSAT

03CRD-2030 EVALUATOR NOTE: It is only critical that one of these

03CRD-2031 valves be opened.

EVALUATOR CUE: For each valve, the indicated handwheel is turned in the indicated direction and reaches a hard stop.

-7 of 9-

STEP STANDARD EVALUATION I COMMENT

9. (Step 5.3.5.C) Close one of the Closes one of the following valves by simulating SAT I UNSAT following valves: rotating the handwheel clockwise:

03CRD-2028

03CRD-2028 OR OR

03CRD-2029

03CRD-2029 EVALUATOR CUE: The indicated handwheel is turned in the indicated direction and reaches a hard stop.

EVALUATOR: Terminate the task at this point.

Task Standard: All control rods inserted with scram air header vented.

-8 of 9-

HANDOUT Initial Conditions:

A failure to scram has occurred.

Numerous control rods have failed to insert.

EOP-3, Failure to Scram, is being executed.

Scram Air Header pressure is 70 psig and steady.

EP-3 (Backup Control Rod Insertion) success path is to vent the Scram Air Header.

Initiating Cue:

The CRS directs you to vent the Scram Air Header per EP-3 section 5.3.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC K TASK TITLE: Swap CRD Flow Control Valves APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 201001 A2.07 3.2/3.1 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion IZI Simulated D Performed Location: IZI Plant D Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO 16-1 NRCK TASK TITLE: Swap CRD Flow Control Valves APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO 16-1 NRC K TASK TITLE: Swap CRD Flow Control Valves APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-25, Control Rod Drive Hydraulic System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. JPM is written with flow control valve 03FCV-19A .in-service.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. INITIAL CONDITIONS

The Control Rod Drive Hydraulic System is in operation.

The "A" CRD Flow Control Valve (03FCV-19A) is currently in service.

The standby CRD Flow Control Valve must be placed in-service in order to verify its ability to operate correctly in automatic.

-3 of 8-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to swap CRD Flow Control Valves per OP-25 (Control Rod Drive Hydraulic System), Section G.14 (Changing lnservice CRD Flow Control Valves)".

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Applicant would obtain a controlled copy of OP-25 from SAT/UNSAT OP-25. the Control Room or NPO Watch Station or Rad Waste Control Room or CRD Charging Cart or MERLIN.

EVALUATOR: Provide a working copy of OP-25.

2. Select the correct section to Selects Section G.14 of OP-25. SAT I UNSAT perform the task.

EVALUATOR NOTE: All actions are simulated performed on Rx Bldg 272' area west of the West HCU's.

3. (G.14.1) The candidate goes to the Rx Building 272' level to the SAT I UNSAT Establish communication between area West of the West HCU's.

Flow Control Hand Select Station When the candidate states that he/she would establish and the Control Room. communications between the Control Room and the master control station using either the West HCU area Gaitronics or nearby sound powered phone jack or cell phone.

Evaluator Cue: Communications with the Control Room are ESTABLISHED.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

4. (G.14.2) a. Contacts the Control Room to ensure the controller is SAT/UNSAT Line up CRD FLOW CNTRL in AUTO.

03FIC-301 per the following steps:

Evaluator Cue: Controller is in AUTO.

a. Ensure controller is in AUTO.

b. Adjust controller setpoint to zero b. Requests the Control Room place the CRD flow gpm. controller setpoint to zero gpm

- Evaluator Cue: The CRD Flow Controller setpoint is at zero gpm.

5. (G.14.3.a) Verifies 03CRD-68B is open by rotating handwheel in SAT I UNSAT Perform the following for the flow the clockwise (closed) direction then rotating control valve to be placed in handwheel in the counterclockwise (open) direction.

service:

a. Verify open inlet isolation valve: Evaluator Cue: Valve 03CRD-68B is open.

03CRD-68B (CRD water 03FCV-19B inlet isol valve)

6. (G.14.3.b) Opens 03CRD-69B by rotating handwheel full CRITICAL STEP Slowly open outlet isolation valve: counterclockwise. SAT I UNSAT 03CRD-69B (CRD water 03FCV-198 outlet isol valve) Evaluator Cue: 03CRD-69B is open.

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

7. (G.14.4) Closes 03CRD-69A by rotating handwheel full CRITICAL STEP Close outlet isolation valve for flow clockwise. SAT I UNSAT control valve to be removed from service.

03CRD-69A Evaluator Cue: 03CRD-69A is closed.

(CRD water 03CRD-69A outlet isolation valve).

8. (G.14.5) Places AUTO-MAN knob to AUTO at 03HSS-245B. CRITICAL STEP Place AUTO-MAN select knob in SAT/UNSAT AUTO for inservice flow control Evaluator Cue: AUTO-MAN knob is in AUTO.

valve:

AUTO-MAN select knob at 03HSS-245B

9. G.14.6 Places AUTO-MAN knob to MAN at 03HSS-245A. CRITICAL STEP Ensure AUTO-MAN select knob is SAT I UNSAT in MAN for standby flow control valve.

Evaluator Cue: AUTO-MAN knob is in MAN.

AUTO-MAN select knob at 03HSS-245A

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

10. (G.14.7) Requests Control Room slowly raises setpoint on SAT I UNSAT Slowly raise setpoint on CRD 03FIC-301 to 59-61 gpm.

FLOW CNTRL 03FIC-301 to establish 59 to 61 gpm on 03FI- Evaluator Cue: 03FIC-301 is set to 60 gpm; flow is 60 310. - gpm and steady -

11. (G.14.8) Requests Control Room verifies parameters. SAT/UNSAT Verify normal operating values on the following indicators at panel 09-5:

Evaluator Cue: All parameters on the 09-5 panel are

CHG WTR PRESS 03Pl-302: satisfactory.

BETWEEN 1390 and 1580 psig, not to exceed 1670 psig

DRVWTR DIFF PRESS 03DPl-303: 260 to 270 psid

CLG WTR DIFF PRESS 03DPl-304: approximately 10 to 26 psid

ORV WTR FLOW 03Fl-305:

zero when no CRD is being driven

FLOW 03Fl-306: 59 to 61 gpm EVALUATOR: Terminate the task at this point.

Task Standard: The "B" CRD Flow Control valve is in service, in automatic at 60 gpm and the A CRD FCV is in manual and valved out of service.

-7 of 8-

HANDOUT Initial Conditions:

The Control Rod Drive Hydraulic System is in operation.

The "A" CRD Flow Control Valve (03FCV-19A) is currently in service.

The standby CRD Flow Control Valve must be placed in-service in order to verify its ability to operate correctly in automatic.

Initiating Cue:

The CRS directs you to swap CRD Flow Control Valves per OP-25 (Control Rod Drive Hydraulic System), Section G.14 (Changing lnservice CRD Flow Control Valves).

-8 of 8-

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 16-1 NRC EXAMINATION SCENARIO 1 TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 1 SCENARIO NUMBER: NRC 1 PATH: STANDALONE Validation: _ _ _ _ _ _ _ Training: _ _ _ _ _ _ _ Operations: _ _ _ _ _ __

CANDIDATES CRS ATC BOP LOI 16-1 NRC Examination Scenario 1 Page 1of22

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 7/6/15 LOI 16-1 NRC Exam New Scenario T. Hooper D. Kelly LOI 16-1 NRC Examination Scenario 1 Page 2 of 22

A. TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 1 B. SCENARIO SETUP:

1. IC-121

2. Special Instructions:

a. The Plant is operating at approximately 100% power.

b. Core Spray Loop 'A' is out of service (yellow tag on CSP 'A').

c. ST-3PA is in progress with sections 4 and 5 completed.

d. Crew will perform section 8.4 only.

3. Preset Conditions:

a. Trigger 1, M:NM14:8, APRM Channel B failure, Delay: 20 sec, Final: 100

b. Trigger 3, M:RD06:A, CRD pump 'A' trip

c. Trigger 3, M:RD09:18:31, Control Rod 18:31 Accumulator trouble, Delay 30 sec

d. Trigger 5, M:RD13:ALL, Control Rods fail to scram, Delay 1 sec

e. Trigger 8, M:SL01 :A, SLC pump A trip, Delay: 1 min

f. Trigger 9, M:SL01 :B, SLC pump B trip, Delay: 1 min

g. Preset, M:RR13:A, ATWS system fail to initiate RWR pump A trip

h. Preset, M:RR13:B, ATWS system fail to initiate RWR pump B trip

i. Trigger 5, M:RR02A, Recirc pump A controller power failure

j. Trigger 5, M:RR02B, Recirc pump B controller power failure

k. Trigger 6, M:TC04:A, TBV 1 failure I. Trigger 6, M:TC04:B, TBV 2 failure

m. Preset, M:CS01 :A, Core Spray pump A trip

n. Trigger 4, M:TU04:E, Main Turbine high bearing #5 vibes, Ramp: 6 min, Initial: 15 (will show as zero after snap and reset), Final: 27

o. Trigger 4, M:TU04:F, Main Turbine high bearing #6 vibes, Ramp: 6 min, Initial: 15 (will show as zero after snap and reset), Final: 27

p. Trigger 2, R:HP15, 23P-150 HPCI Aux Oil pump ckt brkr, Final: Open

q. Preset, O:CSZL014AS5A(1) Core Spray pump A red light: OFF

r. Preset, O:CSZL014AS5A(2) Core Spray pump A green light: OFF

s. Preset, O:AN931 :21, Core Spray pump A trip or loss of control power: ON

t. Event Trigger 1, Event: zdi14as2a(1 )==1, Command: none

u. Event Trigger 5, Event: (zlo5ads8a == 0) && (zlo5ads8b == 0), Command: none

v. Event Trigger 6, Event: ycx07nmaprmaf<24, Command: none

w. Event Trigger 8, Event: zdi11 s1 (2)==1, Command: dmf sl01 :b

x. Event Trigger 9, Event: zdi11 s1 (1 )==1, Command: dmf sl01 :a

4. Consumable Forms and Procedures:

+ AOP-1 LOI 16-1 NRC Examination Scenario 1 Page 3 of 22

C. SCENARIO

SUMMARY

The scenario will begin at approximately 100% power with Core Spray Loop 'A' out of service for pump maintenance. The crew will begin the shift by performing Core Spray 'A' valve stroke timing per ST-3PA.

During the test, APRM 'B' fails upscale and causes a half scram of RPS 'B'. The SRO will determine that Technical Specifications are satisfied with APRM 'B' bypassed. The crew will bypass APRM Band reset the half scram.

Next, the HPCI Auxiliary Oil pump power supply breaker trips. This will render HPCI inoperable for the remainder of the scenario. The SRO will determine the Technical Specification impact.

Following the HPCI Aux Oil pump issue, the running Control Rod Drive pump will trip. The crew will enter AOP-69, start the standby pump, and restore normal Control Rod Drive parameters. During this evolution, one Control Rod Drive accumulator will develop a low pressure. The SRO will determine the Technical Specification impact.

Main Turbine vibrations will then develop. The crew will enter AOP-66 to address the vibrations. The vibrations will not subside as Reactor power is lowered and eventually reach the procedure threshold for a manual scram and turbine trip to be initiated.

Following the manual scram, all control rods do not fully insert (hydraulic ATWS). Rx power will initially be approximately 40-50%. The Crew will execu~e EOP-3 (Failure to Scram).

The ATWS is complicated due to:

1. Two Turbine Bypass Valves fail to open, resulting in SRV manipulation to control RPV pressure.

2. The first SLC pump will trip after it is started, requiring the second pump to be started.

3. RWR controllers will fail as-is, therefore preventing RWR flow from being reduced to minimum.

4. The ATWS-RPT signal will fail to automatically trip the RWR pumps, requiring the RWR pumps to be manually tripped.

Execution of EOP-3 will eventually result in Rx power being reduced to <2.5%.

The scenario will be terminated when Rx power ' is downscale on APRMs, control rod insertion in progress or completed and RPV level is controlled above zero inches.

LOI 16-1 NRC Examination Scenario 1 Page 4 of 22

Shift Turnover The Plant is operating at approximately 100% power.

Core Spray Loop 'A' is out of service due to maintenance being performed on Core Spray pump 'A'.

Day 1 of 7 for TS LCO 3.5.1.

When you take the shift:

1. Perform ST-3PA Section 8.4 only.

LOI 16-1 NRC Examination Scenario 1 Page 5 of 22

Critical Tasks/Standards Critical Task #1: Given a failure to scram with Reactor power above 2.5%, the crew will lower reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC and CRD

Tripping Recirculation pumps

Injecting boron This task is critical based on:

Safety Significance: With a failure of the Reactor Protection System to automatically shutdown the Reactor when conditions warrant the Reactor to cease heat generation, alternative methods of shutting down \lowering the heat generation of the Reactor will be implemented. This will protect the integrity of the fuel cladding and Primary Containment.

Cueing: A Scram condition present and significant heat generation still present, indicated by any or all of the following: Reactor power above the APRM downscale setpoint, Neutron Monitoring indicators and\or Control Rod position indication will be present to the Crew.

Measurable Performance Indicators: EOP-3 provides direction for manual actions to be taken to lower RPV water level below the Feedwater Sparger level, securing RWR pumps and\or initiating Standby Liquid Control.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in Reactor power lowering thus reducing the heat generation rate of the Reactor.

LOI 16-1 NRC Examination Scenario 1 Page 6 of 22

Critical Task #2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3.

This task is critical based on:

Safety Significance: With a failure of the Reactor Protection System to automatically insert Control Rods when conditions warrant, the Reactor may continue to generate a significant amount of heat and\or regain criticality. Alternative methods of inserting Control Rods will be required to shutdown the Reactor. This will protect the integrity of the fuel cladding and Primary Containment.

Cueing: A Scram condition present and all Control Rods not full in as indicated on the Full Core Display, 4 Rod Display and\or EPIC.

Measurable Performance Indicators: EOP-3 provides direction to manually insert Control Rods per EP-3 to the full in position.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in Control Rod insertion thus reducing the heat generation rate of the Reactor and the potential for re-criticality.

LOI 16-1 NRC Examination Scenario 1 Page 7 of 22

EVENT NO. EVENT SEQUENCE

1. Perform Core Spray Valve Testing (Normal: BOP, SRO)

2. APRM 'B' fails upscale (Instrument: ATC, SRO)

3. HPCI Aux Oil pump power supply loss (Component: SRO)

4. CRD pump trip, one CRD Accumulator low pressure (Component: BOP, SRO)

Main Turbine vibration (Reactivity: ATC, SRO)

5. (Component: BOP)

Hydraulic ATWS (Major: ALL) 6.

7. ' Delayed SLC pump trip (Component : ATC, SRO )

Recirculation Flow Controllers fail as is and (Component: ATC, SRO) 8.

Recirculation pumps fail to auto trip

9. Turbine Bypass valves fail partially closed (Component: BOP, SRO)

D. TERMINATION CUES:

Rx power is downscale on APRMs

Control rod insertion in progress or completed

RPV level is controlled above zero inches.

LOI 16-1 NRC Examination Scenario 1 Page 8 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch Event 1 SRO SAT I UNSAT I NA Core Spray valve test

{ST-3PA)

Perform Crew Brief

Direct ST-3PA section 8.4 performed BOP . . .

SAT I UNSAT I NA

Close and time MIN FLOW VLV 14MOV-5A

Open and time MIN FLOW VLV 14MOV-5A

Ensure closed INBD INJ VLV 14MOV-12A

Close and time OUTBD INJ VLV 14MOV-11A

Open and time OUTBD INJ VLV 14MOV-11A, as time allows LOI 16-1 NRC Examination Scenario 1 Page 9 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 2 ATC

Recognize I report multiple annunciators, including: SAT I UNSAT I NA APRM 'B' fails upscale 0 09-5-2-44, APRM UPSCALE (automatically occurs when 0 09-5-2-55, APRM TRIP SYS B INOP OR UPSCALE TRIP 14MOV-11A is stroked closed)

Recognize I report APRM B indicates upscale

Recognize I report half scram SRO

Acknowledge report SAT I UNSAT I NA

Direct ARP response

Determine Technical Specification Table 3.3.1.1-1 Functions 2b, c, and d are met with APRM B out of service

Determines TRM Table T3.3.B-1 Functions 1a, b, and care met with APRM B out of service

Direct bypassing APRM B per OP-16

Direct reset of half scram ATC

Bypass APRM B per OP-16 Section E.16: SAT I UNSAT I NA 0 Place APRM BYP switch in B 0 Verify APRM B is bypassed using one or both of the following:

APRM B BYPASS indicating light is on

APRM B EPIC alarm indicates bypassed 0 Verify the other two APRM channels associated with the same APRM BYP switch are in service using one or both of the following:

APRM BYPASS indicating lights are off for the other two APRMs

No EPIC bypassed alarms for the other two APRMs

Reset half scram per ARP:

0 Place RX SCRAM RESET switch to GROUP 2 & 3, then to GROUP 1 & 4, spring return to NORM 0 Verify RPS B SCRAM GROUPS 1, 2, 3, and 4 lights are on LOI 16-1NRC Examination Scenario 1 Page 10 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 3 BOP SAT I UNSAT I NA HPCI Aux Oil Pump Power Supply Loss

Recognize I report 09-3-3-38, HPCI AUX OIL PMP OVERLOAD OR CNTRL PWR LOSS (on Lead Examiner Cue:

ACTIVATE TRIGGER 2

Recognize I report loss of power to HPCI Auxiliary Oil pump Role Play: SRO SAT I UNSAT I NA If dispatched to investigate, wait 2 minutes and then report

Acknowledge report that the circuit breaker

Direct ARP response (71 BMCC-4-0E2) for the HPCI Aux Oil Pump is in the

Declare HPCI inoperable tripped position, but nothing

Determine Technical Specification 3.5.1 Condition C must be else is obviously abnormal. entered and requires verifying RCIC operable immediately and No smoke, no fire. restoring HPCI operability within 14 days.

Additionally, 3.5.1 Condition D must be entered which requires either HPCI or Core Spray returned to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

LOI 16-1 NRC Examination Scenario 1 Page 11 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 4 ATC SAT I UNSAT I NA

Recognize I report annunciators:

CRD pump trip \

accumulator alarm 0 09-5-1-9, CRD CHARGING WTR PRESS LO (on Lead Examiner Cue: 0 09-5-1-39, CRD PMP 3P-16A OVERLOAD ACTIVATE TRIGGER 3) 0 09-5-1-49, CRD PMP 3P-16A TRIP 0 09-5-1-43, CRD ACCUM PRESS LO OR LVL HI (delayed)

Recognize I report trip of CRD pump A

Recognize I report accumulator alarm on control rod 18-31 (delayed)

SRO SAT I UNSAT I NA

Acknowledge reports

Enter AOP-69 (Control Rod Drive Pump Trouble)

Direct start of CRD pump B

Determine Technical Specification 3.1.5 Condition A requires declaring control rod 18-31 scram time "slow" or declaring control rod 18-31 inoperable within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Role Play: ATC

Execute AOP-69 SAT I UNSAT I NA If dispatched to investigate accumulator alarm, wait 2

Note override conditions for RPV pressure above 900 psig and minutes, then report that the required scram accumulator pressure for

Monitor ACCUM alarm lights on full core display control rod 18-31 is 850 psig and slowly lowering.

_Ensure CRD FLOW CNTRL 03FIC-301 is in MAN

Rotate manual control knob on CRD FLOW CNTRL 03FIC-301 fully counterclockwise LOI 16-1NRC Examination Scenario 1 Page 12 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC cont. SAT I UNSAT I NA

Verify in-service CRD flow control valve (03FCV-19A or B) is closed

Start CRD PMP 03P-16B

Slowly adjust manual control knob on CRD FLOW CNTRL

- 03F-IC-301 to establish 59 to-61 gpm on 03-Fl-310 or 03FIC-301

Place CRD FLOW CNTRL 03FIC-301 in automatic as follows:

0 Balance controller by adjusting setpoint tape 0 Place controller in AUTO 0 Adjust setpoint to BETWEEN 59 and 61 gpm Event 5 ATC/BOP SAT I UNSAT I NA Main Turbine vibrations

Recognize I report high Turbine vibrations (on Lead Examiner Cue:

Monitor Turbine vibrations ACTIVATE TRIGGER 4)

Report vibrations on bearing 5 & 6 are greater than 9 mils but less than 12 mils SRO SAT I UNSAT I NA Note:

Acknowledge report A Reactor scram is required if vibrations exceeded 12 mils or

Enter AOP-66 (Main Turbine High Vibration) if vibrations exceeded 9 mils for more than 15 minutes.

LOI 16-1 NRC Examination Scenario 1 Page 13 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Role Play: BOP

Execute AOP-66 SAT I UNSAT I NA If dispatched to investigate vibrations, wait 2 minutes,

Notify crew of Reactor scram criteria then report you can feel

Ensure Main Turbine system engineer is notified vibrations on the Turbine Deck but do not see any obvious

Lower MVARs to minimum (expect-175 MVAR, depending on cause. exact plant status)

Coordinate with ATC to lower Recirc flow with RWR MG A(B)

SPEED CNTRL

Monitor Turbine vibrations ATC

Lower Recirc flow with RWR MG A(B) SPEED CNTRL SAT/UNSAT/NA

Monitor APRMs, CTP, Recirc flow, Reactor water level ALL

Report Bearing vibrations >12 mils SAT I UNSAT I NA Booth Operator: SRO

Direct Reactor Scram SAT I UNSAT I NA When directed by lead examiner, ramp malfunctions

Direct Main Turbine trip TU04E(F) to 36(38) over 3 minutes to drive scram. - -

Event 6 ATC

Depress MANUAL SCRAM A and MANUAL SCRAM B SAT I UNSAT I NA Hydraulic ATWS pushbuttons

Place RX MODE switch in SHUTDOWN

Observe Reactor power above APRM downscale and control rods not fully inserted

Initiate ARI

Recognize I report failure to scram LOI 16-1 NRC Examination Scenario 1 Page 14 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Critical Task #1 Given a failure to scram with Reactor power above 2.5%, the Pass I Fail crew will lower reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC and CRD

Tripping Recirculation pumps

Injecting boron Given a failure to scram, the crew will initiate Control Rod Critical Task #2 Pass I Fail insertion, in accordance with EOP-3.

LOI 16-1 NRC Examination Scenario 1 Page 15 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SRO

Acknowledge report SAT I UNSAT I NA

Enter EOP-2 (RPV Control) on Reactor power above 2.5% or unknown when a scram is required

Determine the Reactor will NOT remain shutdown under all conditions without boron

Exit EOP-2

Enter EOP-3 (Failure to Scram)

Direct EOP-3 Failure to Scram Actions

May direct bypassing MSIV low RPV water level isolation interlocks per EP-2 Role Play: When directed to insert MSIV low level jumpers,

Direct terminate and prevent all injection except SLC, RCIC Run GAE EP2 MSIVLEVEL and CRD per EP-5 (may not direct low pressure systems T&P)

Direct Reactor water level controlled between -19" and 11 O"

- with only Group 1 Water Level Control Systems (Condensate/Feedwater, CRD, HPCI, LPCI)

Direct Reactor pressure controlled 800-1000 psig SRVs

Concurs with BOP request to inject SLC

Ensure ADS overridden

Direct control rod insertion per EP-3 ATC

Perform EOP-3 Failure to Scram Actions: SAT I UNSAT I NA 0 Ensure Rx Mode Switch in SHUTDOWN Event 8 0 Ensure ARI initiated RWR controllers fail as is 0 Run Recirc flow to minimum (cannot perform) and RWR pumps fail to auto 0 Determine Rx power greater than 2.5%

trip

Ensure Recirc pumps tripped (manually trip both)

Critical Task #1 LOI 16-1 NRG Examination Scenario 1 Page 16 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC cont. 0 Override ADS SAT I UNSAT I NA 0 Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE 0 Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE 0 Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm 0 Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on 0 Obtain CRS concurrence to inject SLC 0 Inject SLC 0 Verify white SQUIB VLVS READY lights are on 0 Note level on TK LVL 11 Ll-66 0 Place SLC pump keylock switch in START SYS-A or START SYS-B 0 Verify red SLC pump running light is on 0 Verify SLC pump discharge pressure on DISCH PRESS 11 Pl-65 is greater than or equal to RPV pressure 0 Verify the following:

0 CLN UP SUCT 12MOV-18 is closed 0 CLN UP RETURN ISOL VALVE 12MOV-69 is closed Event 7

Recognize I report trip of SLC pump 1st SLC pump started trips 0 Start alternate SLC pump Critical Task #1

Insert IRMs and SRMs

-* Range IRMs as necessary LOI 16-1NRC Examination Scenario 1 Page 17 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC cont. SAT I UNSAT I NA

Perform EP-3 Backup Control Rod Insertion Actions Role Play: When directed to 0 Direct NPO to reset ARI per Subsection 5.4 reset ARI, insert Remote 0 May insert rods using RMCS per Subsection 5. 7:

RP20 to TEST.

0 Ensure ARI is reset 0 Place RWM keylock switch in BYPASS 0 If reactor scram can be reset, then reset reactor scram as follows:

-

Place SDlV HI LVL TRIP switch in BYPASS

Place RX SCRAM RESET switch to GROUP 2&3, then to GROUP 1&4, spring return to NORM 0 Verify the following lights are on:

RPS A SCRAM GROUPS 1, 2, 3, and 4

RPS B SCRAM GROUPS 1, 2, 3, and 4 0 Raise CRD drive water differential pressure using one or more of the following methods:

Closing 03CRD-56, if the scram cannot be reset

Closing CRD DRV WTR PRESS VL V 03MOV-20

Raising CRD System flow rate using CRD FLOW CNTRL 03FIC-301 LOI 16-1 NRC Examination Scenario 1 Page 18 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC cont. 0 Select control rod on ROD SEL matrix SAT I UNSAT I NA 0 Insert control rod using ROD MOVEMENT CNTRL or ROD EMERG IN NOTCH OVERRIDE 0 May insert rods by raising dP using CRD cooling water per Subsection 5.8:

May direct NPO to close 03CRD-56

Direct NPO to close 03CRD-91 Role Play: When directed to close 03CRD-56 and 91,

Ensure open CRD ORV WTR PRESS VL V insert Remote and report 03MOV-20 those valves closed.

Ensure closed CRD CLG WTR PRESS CNTRL VL V 03MOV-22

Raise CRD system flow rate to maximum by adjusting CRD FLOW CNTRL 03FIC-301 in automatic or manual o May attempt repeated manual scrams

Report control rod insertion to CRS Critical Task #2 BOP SAT I UNSAT I NA

Terminate and prevent all injection except SLC, RCIC and CRD per EP-5 0 Feedwater Critical Task #1 0 If RFP A is running:

0 Ensure RFP A FLOW CNTRL 06-84A is in MAN 0 Lower RFP A FLOW CNTRL 06-84A to minimum 0 Ensure open RFP A MIN FLOW 34FCV-135A LOI 16-1 NRC Examination Scenario 1 Page 19 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP cont. 0 If RFP B is running: SAT I UNSAT I NA 0 Ensure RFP B FLOW CNTRL 06-84B is in MAN 0 Lower RFP BFLOW CNTRL 06-84B to minimum

- 0 Ensure open RFP B MIN FLOW 34FCV-135B 0 Ensure closed:

0 RFP A DISCH 34MOV-1 OOA 0 RFP B DISCH 34MOV-100B 0 Ensure FDWTR STARTUP VLV 34FCV-137 in MANUAL 0 Ensure closed FDWTR STARTUP VLV 34FCV-137 Critical Task #1 0 HPCI 0 Trip HPCI by depressing TURB TRIP 23A-S19 pushbutton 0 RHR Loop A(B) (may not T&P low pressure systems) 0 Place 10MOV-27A(B) AUTO CONTROL BYPASS 10A-S23A(B) 0 Verify white light above 1OMOV-27 A(B) AUTO CONTROL BYPASS 1OA-S23A(B) is on 0 Ensure closed LPCI OUTBD INJ VLV 1OMOV-27A(B) 0 Ensure RHR Loop A(B) pumps which are not required to be running are stopped 0 Core Spray Loop A(B) (may not T&P low pressure systems) 0 Place 14MOV-11A(B) AUTO ACTUATION BYPASS SW 14A-S16A(B) switch in BYPASS 0 Verify white 14MOV-11A(B) AUTO ACTUATION BYPASS LT 14A-DS35A(B) light is on 0 Ensure closed OUTBD INJ VLV 14MOV-11A(B) 0 Ensure PMP 14P-1A(B) is stopped LOI 16-1 NRC Examination Scenario 1 Page 20 of 22

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP cont. SAT I UNSAT I NA Event 9

Report Reactor water level is less than 11 O" to CRS TBVs partially open

Recognize \ report only 2 TBVs open

Control Reactor pressure 800-1000 psig using SRVs

Control Reactor water level between -19" and 11 O" with only Group 1 Water Level Control Systems

( Condensate/Feedwater, CRD)

Termination Criteria:

Rx power is downscale on APRMs, control rod insertion in progress or completed and RPV level is controlled above zero inches.

LOI 16-1NRC Examination Scenario 1 Page 21of22

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 100% power.

Core Spray Loop 'A' is out of service due to maintenance being performed on Core Spray pump 'A'.

Day 1 of 7 for TS LCO 3.5.1.

When you take the shift:

1. Perform ST-3PA Section 8.4 only.

LOI 16-1 NRC Examination Scenario 1 Page 22 of 22-

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 16-1 NRC EXAMINATION SCENARIO 2 TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 2 SCENARIO NUMBER: NRC2 PATH: STANDALONE Validation: _ _ _ _ _ _ _ Training: _ _ _ _ _ _ _ Operations: _ _ _ _ _ __

CANDIDATES CRS ATC BOP LOI 16-1 NRC Examination Scenario 2 Page 1of24

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 7/7/15 LOI 16-1 NRC Exam New Scenario T. Hooper D. Kelly I

LOI 16-1 NRC Examination Scenario 2 Page 2 of 24

A. TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 2 B. SCENARIO SETUP:

1. IC-122

2. Special Instructions:

a. The Plant is operating at approximately 73% power.

b. Core Spray Loop 'A' is out of service (yellow tag on CSP 'A').

c. Ensure CWP 'C' is OFF.

d. Crew will perform OP-4 section G.5.3.

3. Preset Conditions:

a. Preset, M:CS01 :A, Core Spray pump A trip

b. Preset, M:RD10:30:31, Control Rod 30-31 stuck

c. Trigger 2, M:ED190, Bus 10400 failure

d. Trigger 3, M:RR15:A, Coolant A leak inside Primary Containment, Ramp: 3 min, Final: 5

e. Trigger 4, M:MS02:A, MSL A steam leak inside Primary Containment, Ramp: 3 min, Final: 50

f. Preset, M:RH14, LPCI failure to auto initiate

g. Trigger 4, M:FW19:A, Condensate pump A trip, Delay 4 min

h. Preset, M:HP01, HPCI failure to auto start

i. Trigger 5, M:HP02, HPCI turbine trip

j. Preset, O:AN931 :21, Core Spray pump A trip or loss of control power: ON

k. Trigger 1, O:AN932:01, Core Spray Header B pipe break detector: ON I. Preset, O:CSZL014AS5A(1) Core Spray pump A red light: OFF

m. Preset, O:CSZL014AS5A(2) Core Spray pump A green light: OFF

n. Event Trigger 4, Event: (zlo5ads8a == 0) && (zlo5ads8b == 0), Command: imf rr15:a 32 20:00 5

o. Event Trigger 5, Event: hpfm>100, Command~ none

p. Event Trigger 16, Event: rdpdrvdp>340, Com~and: dmf rd10:30:31

4. Consumable Forms and Procedures:

+ AOP-1 LOI 16-1 NRC Examination Scenario 2 Page 3 of 24

C. SCENARIO

SUMMARY

The scenario will begin at approximately 73% power with Core Spray Loop 'A' out of service for pump maintenance. The crew will begin the shift by starting Circulating Water pump 'C' and then securing Circulating Water pump 'B'.

After the pump swap is complete, a Control Rod pattern adjustment will be performed. The third rod moved will be stuck. The crew will raise drive water differential pressure to un-stick the control rod and complete the rod pattern adjustment.

Next, the Core Spray Leak Detection alarm is received. The SRO will consult Tech Specs and declare Core Spray Loop 'B' inoperable. This now results in both loops of Core Spray inoperable.

Following the Core Spray Leak Detection TS determination, the 4160 VAC 10400 Bus will de-energize. This results in a half scram on RPS Bus 'B' and a trip of RWR pump 'B'. The crew will execute AOP-17, AOP-8 and AOP-60.

After the plant is stabilized, a coolant leak inside the Drywell develops. Rising DW pressure will dictate a manual scram to be inserted. The scram transient will cause the leak to worsen. The scram response will be complicated due to:

1. The only remaining Condensate pump will trip.

2. HPCI will fail to auto start and then trip after manual start attempt.

3. RHR pumps will fail to auto start.

The Crew will execute the Alternate Level Control leg of EOP-2 (RPV Control) to restore \ maintain RPV water level above the Top of Active Fuel (zero inches) and EOP-4 (Primary Containment Control) to mitigate degrading Primary Containment parameters.

Due to high Drywell pressure, the crew will spray the Torus and Drywell.

Due to lowering RPV water level and insufficient high pressure injection sources available, the crew will perform an Emergency Depressurization to allow low pressure injection sources to restore and\or maintain RPV water level >O inches.

The scenario will be terminated when all control rods are inserted, Emergency Depressurization is in progress and Reactor water level is being controlled above 0 inches.

LOI 16-1 NRC Examination Scenario 2 Page 4 of 24

Shift Turnover The Plant is operating at approximately 73% power.

Core Spray Loop 'A' is out of service due to maintenance being performed on Core Spray pump 'A'.

Day 1 of 7 for TS LCO 3.5.1.

When you take the shift:

1. Start Circulating Water pump 'C' per OP-4

2. Secure Circulating Water pump 'B' per OP-4

3. Perform Control Rod pattern adjustment in accordance with Reactor Engineering instructions.

4. Maintain Reactor power <75% until Circulating Water pump 'B' maintenance is complete.

LOI 16-1 NRC Examination Scenario 2 Page 5 of 24

Critical Tasks/Standards Critical Task #1: Given a coolant leak inside the Containment, the crew will spray the Drywall, in accordance with EOP-4.

This task is critical based on:

Safety Significance: With a primary system leaking into the Primary Containment, Drywell parameters will degrade and challenge the integrity of the Primary Containment. Initiating Drywell spray will mitigate the potential of Primary Containment failure thus preventing a challenge to the Secondary Containment.

Cueing: A coolant leak inside Primary Containment will result in rising Drywell pressure and Drywell temperatures as indicated on multiple, redundant Control Room indicators, alarms and EPIC.

Measurable Performance Indicators: EOP-4 provides direction for manual actions to lineup and spray the I

Primary Containment to lower Primary Containment pressure and temperature*.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in Primary Containment parameters to lower by placing the RHR system in Drywell Spray mode.

LOI 16-1 NRC Examination Scenario 2 Page 6 of 24

Critical Task #2: Given a coolant leak, a loss of high pressure injection system and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization, in accordance with EOP-2.

This task is critical based on:

Safety Significance: With a primary system leaking into the Primary Containment, no high pressure injection systems available and RPV water level unable to be maintained above TAF (0 inches), the fuel cladding is being challenged. This condition requires RPV pressure to be rapidly lowered to within the capability of low pressure injection sources to allow for RPV water level to be restored above 0 inches. This protects the integrity of the fuel cladding.

Cueing: A coolant leak inside Primary Containment will result in rising Drywell pressure and Drywell temperatures as indicated on multiple, redundant Control Room indicators and EPIC.

HPCI, RCIC and Feedwater will be unavailable for use as an injection source. The coolant leak will also result in lowering RPV water level as indicated on multiple, redundant Control Room indicators and EPIC. RPV pressure will be above the shutoff head of the RHR and Core Spray system low pressure injection sources.

Measurable Performance Indicators: EOP-2 provides direction for rapidly depressurizing the RPV by opening 7 SRVs.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in RPV pressure to be 'rapidly lowered using SRVs to below the shutoff head of RHR and Core Spray.

LOI 16-1NRC Examination Scenario 2 Page 7 of 24

EVENT NO. EVENT SEQUENCE

1. Swap Circulating Water Pumps {Normal: BOP, SRO)

2. Perform Control Rod Pattern Adjustment {Reactivity: ATC, SRO)

3. Stuck Control Rod (Component: ATC, SRO)

4. Core Spray Sparger Leak {Component: SRO)

Electrical Fault on 10400 Bus {Component: BOP, SRO) 5.

{Reactivity: ATC, SRO)

6. Loss of Coolant Accident (Major: ALL)

7. RHR Pumps Fail to Automatically Start {Component : BOP, SRO)

Condensate Pump A Trips and (Component: ATC, SRO) 8.

HPCI Fails to Automatically Start

9. HPCI Trips {Component: ALL)

D. TERMINATION CUES:

All control rods are inserted

Emergency Depressurization is in progress

Reactor water level is being controlled above O" LOI 16-1 NRC Examination Scenario 2 Page 8 of 24

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Simulator in RUN Recorder and Alarm Power - -

ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch Event 1 SRO SAT I UNSAT I NA Swap Circ Water pumps

Perform Crew Brief

Direct CWP C started per OP-4

Direct CWP B secured per OP-4 BOP SAT I UNSAT I NA

Obtain OP-4 section G.5.3

May raise 600 VAC bus voltage by "tapping-up" on 71T-4

Place and hold CWP C control switch to START at panel 09-6.

WHEN circulating water pump starts, release control switch .

Verify open circulating water pump C discharge valve .

Role Play as NPO: When

Verify the following:

asked about pump discharge 0 Pump discharge pressure is approximately 12 psig.

pressure, report "pump 0 Pump current is stable.

discharge pressure is 12 psig 0 All white lights for RPS A and RPS B power source and all conditions are normal". selectors are on at panel 09-16.

LOI 16-1 NRC Examination Scenario 2 Page 9 of 24

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY BOP cont.

Stop the circulating water pump B as follows:

0 Place control switch to STOP at panel 09 6. SAT I UNSAT I NA 0 Verify closed circulating water pump discharge valve.

0 Verify circulating water pump motor current is zero.

Restore 600 VAC bus voltage by "tapping-down" on 71T-4, if raised earlier.

Event 2 SRO SAT I UNSAT I NA

Direct ATC to position control rods per provided instructions Control Rod pattern adjustment

Provide oversight of reactivity manipulation ATC Evaluator NOTE: the first rod manipulated is 26-27; going SAT I UNSAT I NA from position 48 to 12.

While inserting control rods, monitor the following:

- 0 Nuclear instrumentation 0 Control rod position indication

Ensure ROD SEL PWR switch is in ON

Ensure control rod to be moved is selected by depressing rod select pushbutton on ROD SEL matrix, if necessary

Verify the following:

0 Select pushbutton is brightly backlit 0 Control rod indicating light is on 0 ROD OUT PERM light is on

Place ROD MOVEMENT CNTRL switch to IN .

Release ROD MOVEMENT CNTRL switch 3 notches before reaching desired rod position:

LOI 16-1 NRC Examination Scenario 2 Page 10 of 24

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY ATC cont.

Verify control rod latches in the expected even numbered SAT I UNSAT I NA position before ROD SETTLE light goes off.

Verify ROD SETTLE light is off

Repeat as necessary Evaluator NOTE: the next four rods manipulated are 22-31, 30-31, 30-23, 22-23; going from position 00 to 04.

While withdrawing control rods, monitor the following:

0 Nuclear instrumentation 0 Control rod position indication

Ensure ROD SEL PWR switch is in ON

Ensure control rod to be moved is selected by depressing rod select pushbutton on ROD SEL matrix, if necessary

Verify the following:

0 Select pushbutton is brightly backlit 0 Control rod indicating light is on 0 ROD OUT PERM light is on

Place ROD MOVEMENT CNTRL switch to OUT NOTCH, spring return to OFF

Verify control rod latches in the expected even numbered position before ROD SETTLE light goes off

Verify ROD SETTLE light is off

Repeat as necessary LOI 16-1 NRC Examination Scenario 2 Page 11 of 24-

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Event 3 ATC

Report Rod 30-31 failed to move from position 00 SAT/UNSAT/NA Stuck Control Rod (Rod 30-31)

SRO

Acknowledge report of rod 30-31 failing to move SAT I UNSAT I NA

Direct OP-25 section E.6 performed Role Play: ATC SAT I UNSAT I NA If dispatched to investigate, wait 2 minutes and then report

Raises CRD drive water differential pressure in 50 psid nothing is obviously abnormal increments per OP-25, Section E.6 at HCU 30-31.

Attempt to withdraw rod 30-31

Report rod 30-31 failed to move Raises CRD drive water differential pressure in 50 psid increments per OP-25, Section E.6

Attempt to withdraw rod 30-31

Report rod 30-31 moved to position 02

Restore CRD drive water differential pressure to 260-270 psid

Continue rod pattern adjustments LOI 16-1 NRC Examination Scenario 2 Page 12 of 24

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Event 4 ATC/ BOP

Recognize\ report Annunciator 09-3-2-1 Core Spray Header SAT I UNSAT I NA Core Spray sparger leak 'B' Pipe Break Detector alarm (on Lead Examiner Cue:

Refer to ARP ACTIVATE TRIGGER 1)

Dispatch l&C \ NPO

Run 3D case Role Play: SRO SAT I UNSAT I NA

Acknowledge reports when contacted as l&C \ NPO, wait 2 minutes and report

Consult TRM 3.3.H (monitor once every 12 hrs)

Core Spray 'B' Leak detector

Declare Core Spray Loop 'B' inoperable dP pegged high (positive) and (TS 3.5.1 Condition A, 7 day LCO) alarm is valid. 14DPIS-43B

Enter TS 3.5.1 Condition H, therefore TS 3.0.3 entered immediately.

Inform Station Management Event 5 ALL

Report loss of 10400 bus SAT I UNSAT I NA Electrical fault on 10400 bus

Report Yz scram RPS B (on Lead Examiner Cue:

Report trip of RWR pump B ACTIVATE TRIGGER 2)

SRO

Enter AOP-17 (Loss of 10400 bus) SAT I UNSAT I NA

May enter AOP-19 (Loss 10600 bus). EDGs re-power bus.

Enter AOP-8 (Unexpected change in Core Flow)

Enter AOP-60 (Loss of RPS Bus B Power)

- Enter AOP-51 (Unexpected Fire Pump Start)

Enter TS LCO 3.8.1 Condition A

If Drywell/Torus D/P is low, enters TS 3.6.2.2 Condition A LOI 16-1NRC Examination Scenario 2 Page 13 of 24

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY BOP

Execute AOP-17 SAT I UNSAT I NA Role Play: if dispatched to 0 Cross tie 10400 Bus L-Gear with 10300 Bus L-Gear per report condition of 10400 Bus, Attachment 2.

report there is a Ground Fault condition on the 10400 Bus.

0 Verify closed L 13 L23 L33 L43 4KV FDR BKR 10340.

Role Play: If dispatched to - -

perform AOP-51 field actions, 0 Cross tie L44 with L43 as follows:

wait 2 minutes, then report task completion.

Place L44 600V FDR BKR 14402 in PTL.

Close L43 L44 Tl E BKR 14304 .

0 Cross tie L34 with L33 as follows:

Place L34 600V FDR BKR 13402 in PTL .

Close L33 L34 TIE BKR 13404 .

0 Cross tie L24 with L23 as follows:

Place L24 600V FDR BKR 12402 in PTL.

Close L23 L24 TIE BKR 12404 .

0 IF 36P-1 Bis not running, THEN ensure closed CIRC WTR PMP DISCH VLV 36MOV-100 LOI 16-1 NRC Examination Scenario 2 Page 14 of 24

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY BOP cont. SAT I UNSAT I NA

Execute AOP-8 0 Determine operating point on the applicable Power-Flow Map (SLO) is in the Buffer Zone 0 Demand a 3D Monicore Official Program edit and review margin to core thermal limits.

0 Stop idle RWR Pump rotation as follows:

Close RWR PMP DISCH 02MOV-53(B)

WAIT until 5 minutes has elapsed since RWR PMP DISCH 02MOV- 53(B) was closed 0 Perform the following steps without delay:

0 Ensure closed RWR PMP DISCH 02MOV-53(B)

. 0 Throttle open RWR F?MP DISCH 02MOV-53(B) for 3.5 seconds.

0 As time allows, perform AOP-8 Attachment 2 o May start TBCLC pump A LOI 16-1 NRC Examination Scenario 2 Page 15 of 24

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY BOP cont. o

Execute AOP-60 . SAT/UNSAT/NA Role Play: if dispatched to 0 Verify the following automatic actions:

restore RPS power, report preparations \ briefs will begin. 0 SGT B Start per Section G of OP-20 0 RWCU Isolation per Section G of OP-28 0 Isolate Reactor Bldg Vent per Section G of OP-51A.

0 As time allows, execute OP-18 section D.2 (may take RPS power source switch to the alternate position)

ATC o Insert Cram Rods (1st group will exit Buffer Zone(14-31, 30-39, SAT I UNSAT I NA 38-23, 22-15), additional rods may be inserted as directed by SRO)

LOI 16-1 NRC Examination Scenario 2 Page 16 of 24

Critical Task #1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4.

Critical Task #2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel {TAF), the crew will initiate actions for an Emergency RPV Depressurization in accordance with EOP-2.

Event 6 All * - Rec-ognize \ report rising OW pressure, OW Floor Drain Sump SAT I UNSAT I NA Loss of Coolant Accident Level (on Lead Examiner Cue:

ACTIVATE TRIGGER 3)

SRO

Acknowledge reports SAT I UNSAT I NA

Direct Reactor scram

Enter AOP-1 (Reactor Scram)

Enter AOP-39 (Loss of Coolant)

Enter EOP-2 (RPV Control) on low Reactor water level

Enter EOP-4 (Primary Containment Control) on high Drywell pressure and high Drywell temperature (as they occur)

Direct Reactor water level controlled 180-220" using HPCI, RCIC, Condensate, SLC, and/or CRD LOI 16-1 NRC Examination Scenario 2 Page 17 of 24

SRO cont.

Acknowledge HPCI fail to auto start SAT I UNSAT I NA

Direct Reactor pressure controlled 800-1000# using Turbine Bypass Valves

Enter AOP-39 (Loss of Coolant)

Direct Control Room and Relay Room Ventilation isolated per OP-558 Section G within 30 minutes

Direct TSC filtered ventilation started per Section D of OP-598 within 60 minutes

Direct Core Spray and RHR injection prevented per EP-5

When Primary Containment pressure exceeds 2. 7 psig and before Torus pressure exceeds 15 psig, direct initiation of Torus Spray

When Torus pressure exceed 15 psig, direct Drywell spray Critical Task #1

Determine Reactor water level cannot be maintained above O"

Enter Alternate RPV Level Control leg of EOP-2

Direct override of ADS

Direct CRD maximized and SLC injection, if not done previously

When Reactor water level reaches 0", enter Emergency Critical Task #2 RPV Depressurization leg of EOP-2

Direct opening 7 ADS valves

Direct Reactor water level restored and maintained 180-220" using Core Spray and/or LPCI

As time allows, directs re-start of Drywell spray LOI 16-1NRC Examination Scenario 2 Page 18 of 24

ATC

Enter AOP-1 SAT I UNSAT I NA

Depress MANUAL SCRAM A and MANUAL SCRAM B pushbuttons

Place RX MODE switch in SHUTDOWN

Fully insert IRMs and SRMs

Observe Reactor power lowering

Ensure closed SDIV vent and drain valves

Ensure Main Turbine is tripped

Verify 4KV loads ( 10300 Bus) transfer to reserve power

May begin Reactor depressurization BOP

Enter AOP-1 SAT I UNSAT I NA

Attempt to control Reactor water level 180-220" using HPCI, Condensate, SLC, RCIC and/or CRD

Report HPCI failed to auto start Event 8 and 9 HPCI fails to auto start

Manually start HPCI:

HPCI trips

Ensure open 23MOV-16 Condensate pump A trip

Ensure running 23P-140

Ensure open 23MOV-14

If 09-3-3-28 is in alarm, then depress 23A-S17

Ensure running 23P-150

Recognize I report trip of HPCI

Report trip of Condensate pump A LOI 16-1 NRC Examination Scenario 2 Page 19 of 24

BOP cont. SAT I UNSAT I NA

Terminate and prevent RHR A per EP-5 (may also do RHR B, Core Spray A and B, but these are all inop already):

0 Place 1OMOV-27 A AUTO CONTROL BYPASS 1OA-S23A switch in BYPASS 0 Verify white light above 1OMOV-27 A AUTO CONTROL BYPASS 1OA-S23A is on 0 Ensure closed LPCI OUTBD INJ VLV 10MOV-27A 0 Ensure RHR Loop A pumps which are not required to be running are stopped ATC/BOP

Attempt to maintain Reactor water level with SLC, RCIC and/or SAT I UNSAT I NA CRD

Recognize I report leakage exceeds capacity of SLC, RCIC and/or CRD Event 7

Report RHR pumps failed to auto start RHR pumps fail to automatically start

Manually start RHR pumps A, B, C, D

Initiate Torus spray:

Place SPRAY CNTRL 10A-S17A switch to MANUAL, spring return to normal

Verify white SPRAY PERM 1OA-DS67 A light is on

Ensure available RHR pumps in RHR Loop A are running (recognize/report failure to automatically start)

Open RHR TEST TORUS CLG & SPRAY 1OMOV-39A

Throttle TORUS SPRAY INBD VLV 10MOV-38A to

. . establish desired torus ~pray flow rate

WHEN RHR Loop A flow is GREATER THAN 1500 gpm, ensure closed MIN FLOW VLV 10MOV-16A

Throttle RHR TEST & TORUS CLG 10MOV-34A to divert excess flow to the torus to maintain > 6,500 gpm RHR Loop A flow with one RHR pump operating or> 13,000 gpm RHR Loop A flow with two RHR pumps operating LOI 16-1 NRC Examination Scenario 2 Page 20 of 24

SAT I UNSAT I NA ATC/BOP

Establish RHRSW flow and temperature control:

cont.

Loop A:

Establish RHRSW flow and temperature control:

Start one of the RHRSW pumps

Throttle RHRSW DISCH VLV FROM HX A 1OMOV-89A to

- . establish 2500 to 4000.gpm

Start the second RHRSW pump if desired

Throttle RHRSW DISCH VLV FROM HX A 1OMOV-89A to establish 2500 to 4000 gpm per RHRSW pump

IF drywell or torus sprays are in service, THEN establish 4000 gpm per RHRSW pump

Close HX A BYP VL V 1OMOV-66A LOI 16-1NRC Examination Scenario 2 Page 21 of 24

ATC I BOP

Ensure Recirc pumps tripped SAT I UNSAT I NA

Ensure Drywell Cooling fans tripped Critical Task #1

Initiate Drywell spray:

Place SPRAY CNTRL 10A-S17A switch to MANUAL, spring return to normal

Verify white SPRAY PERM 1OA-DS67 A light is on

Ensure available RHR pumps in RHR Loop A are running

Open DW SPRAY OUTBD VL V 1OMOV-26A

Throttle DW SPRAY INBD VLV 10MOV-31A to establish desired drywell spray flow rate

Override ADS:

Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE

Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE

Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm

Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on

Maximize CRD, if not done previously

- Initiate SLC injection, if not cfone previously

Verify isolations per AOP-15

As time permits, executes AOP-39 (Loss of Coolant)

LOI 16-1 NRC Examination Scenario 2 Page 22 of 24

SAT I UNSAT I NA ATC I BOP - - -

cont.

Open 7 ADS valves Critical Task #2

Restore and maintain Reactor water level 180-220" using available injection systems

Control LPCI injection by throttling 1OMOV-27 A

Secure RHR pumps if needed Termination Criteria:

All control rods are inserted, Emergency Depressurization is in progress and Reactor water level is being controlled above 0 inches.

LOI 16-1 NRC Examination Scenario 2 Page 23 of 24

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 73% power.

Core Spray Loop 'A' is out of service due to maintenance being performed on Core Spray pump 'A'.

Day 1 of 7 for TS LCO 3.5.1.

When you take the shift:

1. Start Circulating Water pump 'C' per OP-4

2. Secure Circulating Water pump 'B' per OP-4

3. Perform Control Rod pattern adjustment in accordance with Reactor Engineering instructions.

4. Maintain Reactor power <75% until Circulating Water pump 'B' maintenance is complete.

LOI 16-1 NRC Examination Scenario 2 Page 24 of 24

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 16-1 NRC EXAMINATION SCENARIO 3 TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 3 SCENARIO NUMBER: NRC3 PATH: STANDALONE Validation: _ _ _ _ _ _ _ Training: _ _ _ _ _ _ _ Operations: _ _ _ _ _ __

CANDIDATES CRS ,,

ATC BOP LOI 16-1 NRC Examination Scenario 3 Page 1 of 24

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 7/9/15 LOI 16-1 NRG Exam New Scenario T. Hooper D. Kelly LOI 16-1 NRC Examination Scenario 3 Page 2 of 24

A. TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 3 B. SCENARIO SETUP:

1. IC-123

2. Special Instructions:

a. The Plant is operating at approximately 100% power.

b. A power reduction is planned iaw OP-65.

3. Preset Conditions:

a. Trigger 2, M:ED43:A, LHH Line 3 fault

b. Trigger 3, M:RR04:A, RWR pump A #1 seal failure, Ramp: 30 sec, Final: 20

c. Trigger 3, M:RR05:A, RWR pump A #2 seal failure, Delay: 3 min, Final: 30

d. Trigger 4, M:MS02:A, MSL A steam leak inside Primary Containment, Ramp: 8 min, Final: 4

e. Trigger 5, M:RR1 O:A, RHR loop A suction line pipe failure, Ramp: 30 sec, Final: 20

f. Preset, M:RP01A,RPS auto scram failure

g. Preset, M:RP01 B,RPS manual scram failure

h. Preset, M:RD10:02:35, 02-31, 06-31, 10-35, 06:39, 10-39, 06-43, 14-43, 10-47, 14-47, 18-43, 18-47, 18-51,Control Rod xx-yy blade stuck

i. Trigger 2, R:EP09, Seismic event alarm

j. Trigger 30, R:RR09, Recirc pump A seal purge flow, Final 0

k. Trigger 25, R:RH46, RHR keepfull normal lineup valve, Final: 100 I. Trigger 26, R: RH47, RHR keepfull normal lineup valve, Final: 100

m. Trigger 16, O:RH ZDl10AS4C, Torus suction valve, Delay: 5 sec, Final: Open

n. Trigger 16, 0: RH ZL01 OAS4C(1 ), RHR pump 1OP-3C suction valve, Delay: 5 sec, Final: Off

o. Trigger 16, 0: RH ZL01 OAS4C(2), RHR pump 1OP-3C suction valve, Delay: 5 sec, Final: Off

p. Trigger 1, O:RR ZAID218416A, MG Set digital speed controller, Ramp: 3 min, Value: -25, Final: 35

q. Event Trigger 1, Event: rrfpa(1 )<4050, Command: none

r. Event Trigger 4, Event: Available, Command: irf ep09 trip

s. Event Trigger 5, Event: rhftorsprya<-10, Command: none

t. Event Trigger 6, Event: rhftorspryb<-10, Command: trg! 5

u. Event Trigger 7, Event: iapcrd<20, Command: imf ms02:a 40 10:00

v. Event Trigger 16, Event: zdi10as4c==O, Command: imf rh10:a 100 5:00

w. Event Trigger 17, Event: rrp2sa(1 )>800, Command: irf ep09 norm

4. Consumable Forms and Procedures:

+ AOP-1 LOI 16-1 NRC Examination Scenario 3 Page 3 of 24

C. SCENARIO

SUMMARY

The scenario will begin at approximately 100% power with a down-power scheduled to support water box cleaning. The crew will begin the shift by performing an EHC pump auto start capability test per OP-8.

After the test, the crew will begin a down-power with Recirculation (RWR) flow. During the flow reduction, the RWR Pump A controller will drift low. The crew will execute AOP-8 (Unexpected Change in Core Flow),

AOP-32 (Unplanned Power Change) and OP-27 (Recirculation System). The SRO will determine the Technical Specification impact due to this condition.

Next, a Seismic event occurs that results in a loss of one of two 115KV system lines. The crew will execute AOP-14 (Earthquake) and AOP-72 (115 KV Grid Loss, Instability, or Degradation). The SRO will determine the Technical Specification impact for this condition also.

As the crew is executing the above AOP's, RWR pump A will develop a seal failure. This will require the crew to manually trip and isolate RWR loop A. Technical Specifications will be addressed by the SRO.

Following RWR loop A isolation, a second Seismic event will occur. This will cause a steam leak inside of the Primary Containment. Degrading Drywell conditions will dictate a manual scram to be initiated.

The Manual scram pushbuttons and Mode Switch fail to scram the Reactor. Alternate Rod Insertion (ARI) will result in some rods to insert. EOP-2 (RPV Control) and EOP-4 (Primary Containment Control) will be executed.

Multiple control rods do not fully insert (mechanically bound) with ARI initiated. Rx power will be less than the APRM downscale setpoint, however, EOP-3 (Failure to Scram) will be required to be entered and executed.

Primary Containment parameters will require the Torus and Drywell to be sprayed. When Torus spray is placed in service, the suction pipe from the Torus to the RHR system breaks. This break is un-isolable and results in Torus water level lowering.

The crew will determine that Torus water level cannot be* maintained above 9.58 feet and an Emergency Depressurization will be required.

Due to all Control Rods not being fully inserted, the SRO will enter EOP-3a (Failure to Scram-ED) and direct an Emergency Depressurization in accordance with this contingency procedure.

The scenario will be terminated when all Control Rods, with the exception of the 13 stuck control rods are inserted, an Emergency Depressurization is in progress and RPV level is controlled above zero inches.

LOI 16-1 NRC Examination Scenario 3 Page 4 of 24

Shift Turnover The Plant is operating at approximately 100% power.

When you take the shift:

1. Test EHC pump B auto-start capability per OP-8, section G.2.

2. Secure EHC pump A following the test.

3. Lower Reactor power with Recirculation flow.

4. Stop power reduction at approximately 80% power for further Reactor Engineering direction.

LOI 16-1 NRC Examination Scenario 3 Page 5 of 24

Critical Tasks/Standards Critical Task #1: Given the need for a Reactor scram and failure of RPS to insert control rods, the crew will initiate Alternate Rod Insertion (ARI), in accordance with AOP-1 and/or EOP-3.

This task is critical based on:

Safety Significance: With a failure of the Reactor Protection System to automatically insert Control Rods when conditions warrant, the Reactor will continue to generate a significant amount of heat.

Alternative methods of inserting Control Rods will be required to shutdown the Reactor.

This will protect the integrity of the fuel cladding and Primary Containment.

Cueing: A Scram condition present and all Control Rods not full in as indicated on the Full Core Display, 4 Rod Display and\o.r EPIC.

Measurable Performance Indicators: AOP-1 and EOP-3 provides direction to manually insert Control Rods by actuating ARI to insert Control Rods to the full in position.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in Control Rod insertion by placing the ARI Switch to Actuate thus reducing the heat generation rate of the Reactor.

LOI 16-1 NRC Examination Scenario 3 Page 6 of 24

Critical Task #2: Given an un-isolable Torus water leak and the inability to maintain Torus water level above 10. 75 feet, the crew will initiate a manual HPCI turbine trip, in accordance with EOP-4.

This task is critical based on:

Safety Significance: With an un-isolable leak in the Torus, Torus water level cannot be maintained above 10.75 feet. This results in the HPCI turbine steam discharge line becoming uncovered.

Without submergence of the discharge pipe, the Torus air space will become over-pressurized. Tripping HPCI prior to its steam discharge line becoming uncovered will protect the integrity of the Primary Containment Torus.

Cueing: Low Torus water level will be indicated on multiple, redundant Control Room indicators and EPIC.

1 Measurable Performance Indicators: EOP-4 provides direction to manually trip the HPCI turbine prior to Torus water level reaching 10. 75 feet.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in the HPCI turbine being manually tripped by depressing the HPCI Turbine Trip pushbutton prior to over-pressurizing the Torus air space.

LOI 16-1 NRC Examination Scenario 3 Page 7 of 24

Critical Task #3: Given an un-isolable Torus water leak and the inability to maintain Torus water level above 9.58 feet, the crew will perform an Emergency RPV Depressurization, in accordance with EOP-3a.

This task is critical based on:

Safety Significance: With an un-isolable leak in the Torus, Torus water level cannot be maintained above 9.58 feet. This will result in the Drywell downcomer vent openings to become uncovered.

Without submergence of the downcomer pipe, the Torus air space will become over-pressurized. Performing an Emergency RPV Depressurization prior to the downcomer vent opening becoming uncovered will protect the integrity of the Primary Containment Torus.

Cueing: Low Torus water level will be indicated on multiple, redundant Control Room indicators and EPIC.

Measurable Performance Indicators: EOP-4 provides direction to perform an Emergency RPV Depressurization prior to Torus water level reaching 9.58 feet in accordance with EOP-3a due to all Control Rods not being fully inserted.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in the RPV being rapidly depressurized prior to over-pressurizing the Torus air space by opening SRVs.

LOI 16-1 NRC Examination Scenario 3 Page 8 of 24

EVENT NO. EVENT SEQUENCE

1. Test EHC Pump B Auto-Start, Secure EHC Pump A (Normal: BOP, SRO)

2. Lower Reactor Power with Recirculation Flow (Reactivity : ATC, SRO)

3. Recirculation Pump A Speed Drifts Low (Instrument: ATC, SRO)

4. Seismic Event with Loss of Line 3 (Component : SRO)

5. Recirculation Pump A Seal Failure (Component: ALL)

Seismic Event with Steam Leak in Drywell (Component: ALL) 6.

RHR Suction Piping Leak, (Major : ALL) 7.

RHR Suction Fails to Isolate I RPS Fails to Scram the Reactor (Instrument: ATC, SRO) 8.

9. Multiple Control Rods Fail to Insert (Component: ALL)

D. TERMINATION CUES:

All Control Rods, with the exception of the 13 stuck control rods are inserted, an Emergency Depressurization is in progress and RPV level is controlled above zero inches.

LOI 16-1 NRC Examination Scenario 3 Page 9 of 24

INSTRUCTOR ACTIVITY POSITION - OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch Event 1 SRO SAT I UNSAT I NA EHC B Auto start test (OP-8)

Perform Crew Brief

Direct OP-8 section G.2 performed BOP

Depress and hold EHC PMP 94P-7B TEST pushbutton. SAT I UNSAT I NA

Verify EHC PMP 94P-7B starts.

Verify red light above EHC PMP 94P-7B TEST pushbutton is on.

Verify annunciator 09-7-3-17 EHC HYD FLUID PMP B AUTO START is in alarm.

Release EHC PMP 94P-7B TEST pushbutton.

Verify annunciator 09-7-3-17 EHC HYD FLUID PMP B AUTO START is clear.

Verify red light above EHC PMP 94P-7A TEST pushbutton is on.

Place control switch for EHC PMP 94P-7B to CLOSE, spring return to normal.

Stop EHC PMP 94P-7A by placing its control switch to TRIP, spring return to normal LOI 16-1 NRC Examination Scenario 3 Page 10 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 2 SRO

Direct ATC to lower power to 80% with Recirc flow SAT/UNSAT/NA Lower Rx power with RWR

Provide oversight for reactivity manipulation ATC

Lower Recirc flow alternately with RWR MG A(B) SPEED SAT I UNSAT I NA CNTRL

Monitor APRMs, CTP, Recirc flow, Reactor water level BOP

Assist ATC with peer checks and plant monitoring SAT I UNSAT I NA Event 3 ATC SAT I UNSAT I NA RWR A speed drifts low

Recognize I report RWR A speed controller is malfunctioning (automatically occurs after RWR A flow is lowered) . .

Note: SRO SAT I UNSAT I NA The decision to restore loop flow mismatch may be made

Acknowledge report from OP-27 precaution C.2.14

Direct lock-up of RWR A scoop tube per OP-27 Section G.6 or Tech Specs.

Enter AOP-8 (Unexpected Change in Core Flow)

Role Play:

Enter AOP-32 (Unexplained/Unanticipated Reactivity Change)

If asked as Reactor

Direct lowering RWR B flow to restore loop flow mismatch (has Engineering how to respond, 24 hr to perform) - TS 3.4.1 Condition B recommend restoring loop flow mismatch by rapidly lowering RWR loop B flow.

LOI 16-1 NRC Examination Scenario 3 Page 11of24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT I UNSAT I NA

Place RWR A SCOOP TUBE control switch to TRIP

Place SCOOP TUBE A AUTO UNLOCK control switch in ON

Lower RWR B flow to restore loop flow mismatch less than or equal to either 5% of rated core flow (if > 70% flow) or 10% of rated core flow (if <70% flow)

Monitor for Thermal Hydraulic Instabilities 0 May select control rod(s) to monitor LPRMs BOP SAT I UNSAT I NA

Monitor Feedwater response Event 4 ATC\BOP

Recognize I report seismic event alarm SAT I UNSAT I NA Seismic and loss of Line #3 (on Lead Examiner Cue:

ACTIVATE TRIGGER 2)

SRO

Acknowledge reports SAT I UNSAT I NA

Enter AOP-14 (Earthquake)

Enter AOP-72 ( 115KV)

Determine Technical Specification 3.8.1 Condition A must be entered (verify Line 4 alignment/availability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore Line 3 to operable within 7 days)

LOI 16-1NRC Examination Scenario 3 Page 12 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Role Play: BOP SAT I UNSAT I NA If asked about seismic indications in Relay Room,

Execute AOP-14 (Earthquake) wait one minute, then report 0 Ensure open one of the following valves at Panel 27CAD:

that the Seismic Relay Alarm 0 27SOV-129A light is lit, but the OBE 0 27SOV-129B Exceeded light is NOT lit.

Delete EP09 after report.

If asked about position of CAD 0 IF Relay Room Ventilation tripped, THEN restart per valves, report 27SOV-129A is OP-56. (Evaluator Note: is NOT tripped) open - - -

Role Play: 0 Confirm seismic event using any of the following sources:

If contacted as Nine Mile Point 0 JAF seismic instrumentation (Any TRIGGER LED about seismic event, report on seismic indicator panel) that you have also felt a 0 NMP 2 seismic instrumentation seismic event and had 0 National Earthquake Information Center actuation of seismic alarms.

Role Play: BOP SAT I UNSAT I NA

Execute AOP-72 ( 115KV)

When contacted as National 0 Notify the following of electrical status and request Grid, acknowledge that Line rapid restoration of 115 KV line voltage:

3 has de-energized and are 0 National Grid Power Control investigating.

0 Nine Mile Point Unit One Control Room When contacted as NMP, report that NMP has 0 Notify Security there has been an unplanned loss or experienced a loss of Line #3 degradation of the 115 KV system.

also.

When contacted as Security, 0 Monitor 115 KV System parameters report that Security will investigate the switchyard.

LOI 16-1 NRC Examination Scenario 3 Page 13 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 5 BOP\ATC

Recognize I report RWR pump A seal degradation SAT I UNSAT I NA RWR Pump A Seal Failure

Recognize I report rising Drywell leak rate, pressure, and temperature (on Lead Examiner Cue:

ACTIVATE TRIGGER 3)

SRO

Direct shutdown and isolation of RWR pump A SAT/UNSAT/NA

Enter AOP-8 (Loss or Reduction of Reactor Coolant Flow)

Enter AOP-39 (Loss of Coolant)

Recognize Single Loop requirements of OP-27 or AOP-8 Role Play: BOP

Shutdown and isolate RWR pump A per OP-27 section G.2 SAT I UNSAT I NA When dispatched to close 02-2RWR-39A, wait 2 minutes, 0 Close RWR PMP A DISCH 02MOV-53A insert trigger 30, and then 0 Verify RWR PMP 02-2P-1A is tripped report task completion.

0 Place RWR PMP 02-2P-1A control switch in PULL TO LOCK.

0 Verify open RWR MG A GEN FIELD BKR Note:

It is not expected for the crew 0 Dispatch operator to close 02-2RWR-39A (RWR pump A to have time to establish seal purge upstr isol valve) single-loop scram and rod- 0 Close RWR PMP A SUCT 02MOV-43A block settings during the 0 Ensure RWR MG DC LUBE OIL PMP 02-184P-3A is course of this scenario. Prior - stopped to these actions, the next event should be inserted.

LOI 16-1 NRC Examination Scenario 3 Page 14 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC

Execute AOP-8 SAT I UNSAT I NA 0 Monitor for onset of thermal-hydraulic instability per OP-16

_ o _ Ensure RPV water level_ returns to normal and stabilizes 0 Determine operating point on the applicable Power-Flow Map 0 As time permits, coordinate with BOP to insert control rods due to position on Power-Flow Map 0 Demand a 3D Monicore case and review margin to core thermal limits BOP

Execute AOP-39 SAT I UNSAT I NA 0 May direct Operator to Vent the Torus per OP-37 as necessary to maintain primary containment pressure less than 2. 7 psig 0 Direct Operator to isolate Control Room Ventilation per OP-55B section G.1 within 30 minutes 0 Direct Operator to isolate Relay Room Ventilation per OP-56 Section G within 30 minutes 0 Direct Operator to startup TSC Ventilation within 60 min.

LOI 16-1 NRC Examination Scenario 3 Page 15 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 6 BOP\ATC

Recognize \ report additional Seismic alarm SAT I UNSAT I NA Seismic with Steam Leak in Drywell

Recognize \ report rising Drywell pressure (on Lead Examiner cue, insert Trigger 4)

Critical Task #1 Given the need for a Reactor scram and failure of RPS to Pass I Fail insert control rods, the crew will initiate Alternate Rod Insertion (ARI), in accordance with AOP-1 and/or EOP-3.

Event 8 SRO

Acknowledge report SAT I UNSAT I NA RPS fails to scram Rx

Direct Reactor Scram

Enter EOP-2 (RPV Control)

Determine the Reactor will NOT remain shutdown under all conditions without boron

Exit EOP-2

Enter EOP-3 (Failure to Scram)

_ Dire_lct EOP-3 Failure to Scra:_m Actions (Power Leg Hard Card)

Critical Task #1

Ensure \ direct ARI has been initiated

Direct bypassing MSIV low RPV water level isolation interlocks

Direct terminate and prevent Core Spray

Direct Reactor water level controlled between -19" and 220" with only Group 1 Water Level Control Systems (Condensate/Feedwater, CRD, HPCI, LPCI)

Direct Reactor pressure controlled 800-1000 psig TBVs

Direct control rod insertion per EP-3 LOI 16-1 NRC Examination Scenario 3 Page 16 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC o Perform EOP-3 Failure to Scram Actions: SAT/UNSAT/NA 0 Ensure Rx Mode Switch in SHUTDOWN 0 Initiate ARI Critical Task #1 0 Report all Control Rods not full in ( 13 remain out) o Run Recirc flow to minimum o Determine Rx power less than 2.5%

o Insert IRMs and SRMs o Range IRMs as necessary o Perform EP-3 Backup Control Rod Insertion Actions 0 Determine Control Rods cannot be inserted from Control Room.

0 Direct Over-piston volume of HCU's to be vented.

BOP

Terminate/prevent Core Spray per EP-5, as directed: SAT I UNSAT I NA 0 Place 14MOV-11A(B) AUTO ACTUATION BYPASS SW 14A-S16A(B) switch in BYPASS 0 Verify white 14MOV-11A(B) AUTO ACTUATION BYPASS LT 14A-DS35A(B) light is on 0 Ensure closed OUTBD INJ VLV 14MOV-11A(B) 0 Ensure PMP 14P-1A(B) is stopped SRO SAT I UNSAT I NA

Recognize Drywell pressure > 2. 7 psig

Enter EOP-4 (Primary Containment Control)

Direct Torus spray placed in service LOI 16-1 NRC Examination Scenario 3 Page 17 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP SAT I UNSAT I NA

Initiate Torus spray:

Note:

0 Place SPRAY CNTRL 1OA-S17A or B switch to When Torus spray is MANUAL, spring return to normal established, Trigger 5 \ 6 automatically activate to start 0 Verify white SPRAY PERM 1OA-DS67 A or B light is the Torus water leak. on 0 Ensure available RHR pumps are running 0 Open RHR TEST TORUS CLG & SPRAY 1OMOV-39A or B 0 Throttle TORUS SPRAY INBD VLV 1OMOV-38A or B to establish desired torus spray flow rate 0 WHEN RHR Loop A or B flow is GREATER THAN 1500 gpm, ens~re closed MIN FLOW VLV 10MOV-

- 16A or B 0 Throttle RHR TEST & TORUS CLG 1OMOV-34A or Role Play: B to divert excess flow to the torus to maintain >

When directed to close and 6,500 gpm RHR Loop A or B flow with one RHR open two turns 1ORHR-228 or pump operating D, report completed. 0 Establish RHRSW flow and temperature control:

0 Loop B:

0 Ensure closed the RHRSW pump discharge valve for the pump to be started:

Throttle open the valve that is

10RHR-22B or D directed and report completed.

Throttle open two turns the valve closed above 0 Start one of the RHRSW pumps 0 Throttle open the discharge valve for the running pump to establish 2500-4000 gpm or motor current

<Max amps 0 Start the second RHRSW pump if desired LOI 16-1 NRC Examination Scenario 3 Page 18 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP cont.

Loop A: SAT I UNSAT I NA

Establish RHRSW flow and temperature control:

Start one of the RHRSW pumps

Throttle RHRSW DISCH VL V FROM HX A 1OMOV-89A to establish 2500 to 4000 gpm

Start the second RHRSW pump if desired

Throttle RHRSW DISCH VLV FROM HX A 10MOV-89A to establish 2500 to 4000 gpm per RHRSW pump

IF drywell or torus sprays are in service, THEN establish 4000 gpm per RHRSW pump

Close HX A BYP VL V 1OMOV-66A Event 7 ALL

Recognize\ report lowering Torus water level SAT I UNSAT I NA RHR suction piping leak, RHR suction fails to isolate Given an un-isolable Torus water leak and the inability to Critical Task #2 Pass I Fail maintain Torus water level above 10.75 feet, the crew will initiate a manual HPCI turbine trip, in accordance with EOP-4.

Given an un-isolable Torus water leak and the inability to Critical Task #3 Pass I Fail maintain Torus water level above 9.58 feet, the crew will perform an Emergency RPV Depressurization, in accordance with EOP-3a. --

LOI 16-1 NRC Examination Scenario 3 Page 19 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SRO

Re-enter EOP-4 SAT/UNSAT/NA

Direct make-up water to the Torus using OP-13B

Monitor for 10.75 feet and 9.58 feet Torus water level Role Play: BOP

Direct NPO to supply Condensate Transfer water to Torus SAT I UNSAT I NA When dispatched to open - -

10RHR-260/274, wait 1 minute and insert Remotes to open directed valve SRO

Determine Torus water level cannot be maintained > 10. 75 SAT I UNSAT I NA feet

Direct HPCI turbine tripped Critical Task #2 BOP SAT I UNSAT I NA

Trip HPCI turbine by depressing Turbine Trip pushbutton

Report HPCI tripped Critical Task #2 Role Play:

Direct closure of RHR pump C suction valve SAT I UNSAT I NA When dispatched as operator

Acknowledge failure of RHR pump C suction valve to close to investigate Torus leak, wait 3 minutes, then report that there is a large leak on RHR pump C suction between the pump and the suction valve.

LOI 16-1 NRC Examination Scenario 3 Page 20 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION If requested to close MOV- BOP

Attempt to close RHR pump C suction valve SAT/UNSAT/NA 151A, wait 2 more minutes, then report that MOV-151A is

Recognize I report failure of RHR pump C suction valve to stuck open. close If requested to close MOV- SRO

Determine Torus water level cannot be maintained > 9.58 feet SAT I UNSAT I NA 13C, wait 2 more minutes,

Determine Emergency Depressurization required then report that MOV-13C is

Enter EOP-3a (Failure to Scram-ED) stuck open.

Direct all injection into the RPV except from SLC, RCIC and CRD be terminated and prevented

Ensure ADS overridden

Direct 7 ADS valves opened Critical Task #3 BOP\ATC

Terminate and prevent all injection into the RPV except for SAT/UNSAT/NA SLC, RCIC and CRD:

RHR per EP-5:

0 Place 1OMOV-27A(B) AUTO CONTROL BYPASS 1OA-S23A(B) switch in BYPASS 0 Verify white light above fOMOV-27A(B) AUTO CONTROL BYPASS 10A-S23A(B) is on 0 Ensure closed LPCI OUTBD INJ VLV 10MOV-27A(B) 0 Ensure RHR Loop A(B) pumps which are not required to be running are stopped LOI 16-1 NRC Examination Scenario 3 Page 21 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP\ATC

Core Spray per EP-5: SAT I UNSAT I NA cont. - o -Place 14MOV-11A(B) ALlTO ACTUATION BYPASS SW 14A-S16A(B) switch in BYPASS 0 Verify white 14MOV-11A(B) AUTO ACTUATION BYPASS LT 14A-DS35A(B) light is on 0 Ensure closed OUTBD INJ VLV 14MOV-11A(B) 0 Ensure PMP 14P-1A(B) is stopped

Feedwater per EP-5:

0 IF RFP is running, THEN perform the following:

IF RFP A FLOW CNTRL 06-84A(B) is in AUTO, THEN balance RFP A(B) FLOW CNTRL 06-84A using RFP A(B) FLOW CNTRL 06-84A(B) manual control knob.

Ensure RFP A(B) FLOW CNTRL 06-84A(B) in MAN.

Lower RFP A(B) Flow Control 06-84A(B) to minimum.

Ensure open RFP A(B) MIN FLOW 34FCV-135A(B).

0 Ensure closed the following valves:

RFP A DISCH 34MOV-100A(B)

Ensure FDWTR STARTUP VLV 34FCV-137 in MANUAL.

Ensure closed FDWTR STARTUP VLV 34FCV-137.

LOI 16-1 NRC Examination Scenario 3 Page 22 of 24

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP\ATC SAT I UNSAT I NA

Open 7 ADS valves Critical Task #3

Report 7 ADS valves are open

Trend lowering RPV pressure

Monitor\ maintain RPV water level in assigned band Termination Criteria:

All Control Rods, with the exception of the 13 stuck control rods are inserted, an Emergency Depressurization is in progress and RPV level is controlled above zero inches.

LOI 16-1 NRC Examination Scenario 3 Page 23 of 24

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 100% power.

When you take the shift:

1. Test EHC pump B auto-start capability per OP-8; Section G.2 for Post Maintenance Testing.

2. Secure EHC pump A following the test.

3. Lower Reactor power with Recirculation flow.

4. Stop power reduction at approximately 80% power for further Reactor Engineering direction.

LOI 16-1 NRC Examination Scenario 3 Page 24 of 24

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 16-1 NRC EXAMINATION SCENARIO 4 TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 4 SCENARIO NUMBER: NRC4 PATH: STANDALONE Validation: _ _ _ _ _ _ _ Training: _ _ _ _ _ _ _ Operations: _ _ _ _ _ __

CANDIDATES CRS ATC BOP LOI 16-1 NRC Examination Scenario 4 Page 1 of 21

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 7/23/13 LOI 14-1 NRC Exam New Scenario T. Hooper D. Kelly 5/14/14 LOI 14-2 NRC Exam Modified scenario for LOI 14-2 NRC Exam T. Hooper D. Kelly 6/30/15 LOI 16-1 NRC Exam Modified scenario for LOI 16-1 NRC Exam T. Hooper D. Kelly (this scenario was the backup scenario for 14-2; it was not used or released from 14-2 exam)

I LOI 16-1 NRC Examination Scenario 4 Page 2 of 21

A. TITLE: LOI 16-1 NRC EXAMINATION SCENARIO 4 B. SCENARIO SETUP:

1. IC-124

2. Special Instructions:

a. The Plant is operating at approximately 7% power in STARTUP.

b. RWM is bypassed.

c. OP-65 is "open" and place-kept up and including step D.20.2

d. Ensure Rod Withdrawal Sequence A1-2 is "open" and place-kept up to and including Step 25.

e. Have multiple copies of the control rod movement sheets.

3. Preset Conditions:

a. Trigger 1, M:RD08:18:35, Control Rod (18:35) Drift Out

b. Trigger 3, M:CU07, RWCU Pipe Break Between 12-MOV-15 and 12-MOV-18, 2%

c. Preset, M:CU10, RWCU 12MOV-18 Auto Isolation Failure

d. Preset, M:CU12, RWCU 12MOV-15 Auto Isolation Failure

e. Trigger 4, M:RC06, RCIC System Inadvertent Initiation

f. Trigger 5, M:RC09, RCIC Steam Line Break, 2.5%

g. Preset, M:RC12, RCIC Isolation Relay, 13A-K15, Failure

h. Preset, M:AD07:B, Rx Press Relief Valve 71 B Fails to Open

i. Preset, M:AD07:D, Rx Press Relief Valve 71 D Fails to Open

j. Preset, M:AD07:G, Rx Press Relief Valve 71 G Fails to Open

k. Preset, M:AD07:H, Rx Press Relief Valve 71 H Fails to Open I. Preset, M:AD07:1, Rx Press Relief Valve 71J Fails to Open

m. Preset, M:AD07:J, Rx Press Relief Valve 71 K Fails to Open

n. Trigger 2, R:ED23, LPCI AC Input Bkr 'A' Trip

o. Trigger 25, R:RC13, 13-MOV-15 Circuit Breaker, OPEN

p. Preset, O:TC ZDIPNIBVOJI, Bypass Valve Opening Jack, NORMAL

q. Event Trigger 1, Event: rdreed(41)==10, Command: none

r. Event Trigger 6, Event: (zlo5ads8a == O)' && (zlo5ads8b == 0),

Command: imf rc09 (0 0) 8 7:00 4

s. Event Trigger 16, Event: rdreed(41 )>12, Command: dmf rd08:18:35

t. Event Trigger 24, Event: zlo13as2(1 )==1, Command: imf rc09 (0 0) 4 5:00 2.5

u. Event Trigger 25, Event: zlo13as1 (1 )==1, Command: none

v. Event Trigger 26, Event: rcfm>40, Command: dmf rc06

4. Consumable Forms and Procedures:

+ AOP-1 LOI 16-1 NRC Examination Scenario 4 Page 3 of 21

C. SCENARIO

SUMMARY

The scenario will begin at approximately 7% power during a startup. The RWM is bypassed due to a hardware failure. The crew will begin by transitioning to Mode 1 and withdrawing all IRMs per OP-65. Then the crew will continue to raise Reactor power by withdrawing control rods.

The second control rod to be moved, 18-35, will double notch beyond its withdraw limit of 12 to 14. The crew will execute guidance to re-insert the control rod to its intended position. This will clear that associated control rod block and allow continued control rod movement.

The AC input to the A LPCI inverter will fail. The crew will transfer the A LPCI inverter to the alternate AC supply. The SRO will determine the Technical Specification impact.

Reactor Water Cleanup system then develops a leak between the inboard and outboard suction isolation valves. This will cause at least one Reactor Building area temperature to exceed max normal and require entry into EOP-5, Secondary Containment Control. The Reactor Water Cleanup pumps will eventually trip on high room temperature, but the suction line will fail to automatically isolate. The crew can isolate the leak by manually closing 12MOV-15 and 12MOV-18. The SRO will determine the Technical Specification impact of the PCIV automatic isolation failure.

RCIC will inadvertently initiate. The crew will execute AOP-77 in response to the inadvertent start. Once RCIC comes up to near rated flow, the initiation signal will clear, allowing full control of the system. The

, crew will secure RCIC. The SRO will determine the Technical Specification impact.

RCIC will develop a steam leak. This will cause high area temperatures near RCIC and HPCI. HPCI will automatically isolate, however RCIC will fail to automatically isolate. The crew will be able to close 13MOV-16, however the breaker for 13MOV-15 trip open, preventing isolation of the steam leak. The crew will execute EOP-5. The crew will enter AOP-1 and insert a manual Reactor scram. The crew will enter EOP-2, RPV Control. As Reactor Building area temperatures approach max safe levels, the crew will attempt to anticipate Emergency Depressurization by rapidly lowering Reactor pressure with Turbine Bypass Valves.

The Bypass Opening Jack will fail to open Turbine Bypass Valves. The crew may open Turbine Bypass Valves by adjusting the pressure regulator setpoint, but this will limit how quickly Reactor pressure can be lowered. Once two max safe temperatures are exceeded, the crew will perform an Emergency Depressurization.

Only three ADS SRVs will open requiring the Crew to open two additional non-ADS SRVs to obtain 5 SRVs open.

The scenario will be terminated when all control rods are inserted, the Emergency RPV Depressurization is in progress, and Reactor water level is controlled above O".

LOI 16-1 NRC Examination Scenario 4 Page 4 of 21

Shift Turnover The Plant is operating at approximately 7% power with the Mode Switch in STARTUP.

The Drywell has been verified to be clear of personnel.

The RWM is bypassed due to a hardware failure.

When you take the shift:

1. Transition to Mode 1 per OP-65 step D.20.3.

2. Continue OP-65, up to and including, step D.20.6 to withdraw all IRMs.

3. Continue control rod withdrawals per the startup control rod sequence:

The next movement is A 1-2 Sequence

RSCS Group 10

Step 26

Control Rod 26-27

Complete Step 26, and then hold for Reactor Engineering analysis.

LOI 16-1 NRC Examination Scenario 4 Page 5 of 21

Critical Tasks/Standards Critical Task #1: Given the plant operating at power with an un-isolable primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram before the 1st Max Safe temperature is reached, in accordance with EOP-5.

This task is critical based on:

Safety Significance: With an un-isolable primary system discharging in the Secondary Containment, Reactor Building environmental and radiological conditions will deteriorate. This condition warrants rapidly shutting down the Reactor by inserting a manual Reactor scram thus reducing the energy discharging into the Secondary Containment. This will minimize the potential degradation of the Secondary Containment, Secondary Containment equipment and personnel access.

Cueing: Secondary Containment parameters and primary system status will be indicated on multiple, redundant Control Room indicators, alarms and EPIC.

Measurable Performance Indicators: EOP-5 provides direction to enter EOP-2 and manually scram the Reactor when it has been determined that an un-isolable primary system is discharging into the Secondary Containment.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in the Reactor being manually scrammed by depressing the Manual Scram pushbuttons and\or rotating the Mode Switch to Shutdown.

LOI 16-1 NRC Examination Scenario 4 Page 6 of 21

Critical Task #2: Given an un-isolable primary system discharging into Secondary Containment and two areas exceeding Maximum Safe Temperatures, the crew will perform an emergency RPV depressurization, in accordance with EOP-5.

This task is critical based on:

Safety Significance: With an un-isolable primary system discharging in the Secondary Containment, combined with two Reactor Building areas exceeding Max Safe Temperatures, warrants the Reactor to be rapidly depressurized by opening 7 SRVs. This will reduce the energy discharging into the Secondary Containment, which will minimize the potential degradation of the Secondary Containment, Secondary Containment equipment and personnel access.

Cueing: Secondary Containment temperatures and primary system status will be indicated on multiple, redundant Control Room indicators, alarms and EPIC.

Measurable Performance Indicators: EOP-5 provides direction to enter EOP-2 and rapidly depressurize the Reactor using SRVs when it has been determined that an un-isola.ble primary system is discharging into the Secondary Containment and two RB area temperatures are above their Max Safe values.

Performance Feedback: Successful implementation of any\all Performance Indicators will result in the Reactor being rapidly depressurized by opening SRVs.

LOI 16-1 NRC Examination Scenario 4 Page 7 of 21

EVENT NO. EVENT SEQUENCE

1. Transition to Mode 1 (Normal: BOP, SRO)

2. Withdraw Control Rods (Reactivity: ATC, SRO)

3. Double Notched Control Rod (Component: ATC, SRO)

4. LPCI 'A' AC input breakers trips open (Instrument: BOP, SRO)

Reactor Water Cleanup Pipe Break, (Component: BOP, SRO) 5.

Reactor Water Cleanup Fails to Automatically Isolate RCIC Inadvertent Initiation (Component: BOP, SRO) 6.

7. RCIC Steam Leak and Failure to Isolate (Major: All)

8. Bypass Opening Jack Fails (Component: BOP, SRO)

9. Multiple SRVs fail to open (Component: BOP, SRO)

D. TERMINATION CUES:

All control rods are inserted

Emergency RPV Depressurization is in progress

Reactor water level is controlled above O" LOI 16-1 NRC Examination Scenario 4 Page 8 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow All no more than five minutes for panel walkdown

Walkdown the control panels and assume the watch Event 1 SRO SAT I UNSAT I NA Transition to Mode 1

Perform Crew Brief

Direct BOP (ATC) to transition to Mode 1 per OP-65 steps D.20.3 thru D.20.6 BOP (ATC) SAT/UNSAT/NA

Place RX MODE switch in RUN

Ensure all personnel out of drywell (NOTE: status provided on turnover sheet)

Place CHAN SEL switches for the following recorders in APRM\RBM: ..

07PR-46A,B,C,D LOI 16-1 NRC Examination Scenario 4 Page 9 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP cont. SAT I UNSAT I NA

Withdraw IRMs to full out per OP-16:

Ensure POWER ON light is on

Ensure IRMs that will be withdrawn are selected

Verify IRM RETRCT PERMIT lights are on for IRMs that will be withdrawn

Depress DRIVE OUT/DRIVING OUT pushbutton

Verify DRIVE OUT light is on

Verify DRIVING OUT light comes on

WHEN IRMs are at desired position OR detector OUT light comes on, depress DRIVE OUT/DRIVING OUT pushbutton

Verify the following lights are off:

- o DRIVE OUT -

o DRIVING OUT

WHEN operation of IRMs is no longer desired, ensure IRMs are de-selected LOI 16-1 NRC Examination Scenario 4 Page 10 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 2 SRO SAT I UNSAT I NA Withdraw Control Rods

Direct ATC to continue control rod withdrawals

Provide oversight of reactivity manipulation ATC SAT I UNSAT I NA Note:

While withdrawing control rods, monitor the following:

The first five control rods in the withdrawal sequence are 0 Nuclear instrumentation 26-27, 18-35, 34-35, 34-19 0 Control rod position indication and 18-19. These control rods are being moved from position

Ensure ROD SEL PWR switch is in ON 08 to 12. Control rod 18-35

Ensure control rod to be moved is selected by depressing rod will double notch to position select pushbutton on ROD SEL matrix, if necessary 14, which will lead to the next event.

Verify the following:

0 Select pushbutton is brightly backlit 0 Control rod indicating light is on 0 ROD OUT PERM light is on

Place ROD MOVEMENT CNTRL switch to OUT NOTCH, spring return to OFF

Verify control rod latches in the expected even numbered position before ROD SETTLE light goes off

Verify ROD SETTLE light is off

Repeat as necessary LOI 16-1 NRC Examination Scenario 4 Page 11 of21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 3 ATC SAT/UNSAT/NA Double Notched Control Rod

Recognize I report control rod 18-35 double notched SRO SAT/UNSAT/NA

Acknowledge report

Direct re-inserting control rod 18-35 to position 12

Direct continuing control rod withdrawals Role Play: ATC SAT I UNSAT I NA If contacted as Shift Manager, say that you understand the

Execute OP-26 Section E.1.3.c:

event and direct continuing 0 Insert control rod one notch with control rod withdrawals 0 Notify Shift Manager per the startup sequence.

0 Stop all further control rod withdrawals until Shift Manager Role Play: reviews event and approves continued rod withdrawal If asked for Rx Analyst

Continue control rod withdrawals per startup sequence instruction when control rod 18-35 is at 14, report that the Rx Analyst concurs with following the approved station procedure.

Role Play:

If asked for Rx Analyst instruction when control rod 18-35 is at 12, report that the Rx Analyst recommends continuing with control rod withdrawals.

LOI 16-1NRC Examination Scenario 4 Page 12 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 4 ATC/BOP SAT I UNSAT I NA On Lead Examiner Cue:

Recognize I report annunciator 09-8-3-02, LPCI MOV IPS A ACTIVATE TRIGGER 2 71 INV-3A AC INPUT LOSS LPCI Inverter AC Input Loss SRO

Acknowledge reports SAT I UNSAT I NA

Direct ARP response

Determine Technical Specification 3.8.4 Condition D requires LPCI A to be declared inoperable immediately

Declare LPCI A inoperable (TS 3.5.1 Condition A)

Role Play: BOP SAT I UNSAT I NA

Executes ARP 09-8-3-02:

If dispatched to investigate, wait 2 minutes and then report 0 IF alarm is not anticipated, AND LPCI MOVA PWR that the AC input breaker to SUPP control switch is not in ALT PULL TO LOCK LPCI MOV IPS A is tripped, at panel 09-8, THEN place LPCI MOV Bus A on but you do not see any other alternate feed as follows:

obvious problems.

Verify L-15 is energized at panel 09-8

Place LPCI MOVA PWR SUPP switch in ALT PULL TO LOCK at panel 09-8 LOI 16-1 NRC Examination Scenario 4 Page 13 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 5 ATC/BOP SAT I UNSAT I NA On Lead Examiner Cue:

ACTIVATE TRIGGER 3

Recognize I report EPIC area temperature alarm Reactor Water Cleanup Pipe

Recognize I report annunciators 09-3-3-02(12), DIV 1(11)

Break, Reactor Water Cleanup AMBIENT TEMP HI Fails to Automatically Isolate

- Recognize I report RWCU pump trip and failure to isolate SRO SAT I UNSAT I NA

Acknowledge reports

Direct ARP response

Enter EOP-5, Secondary Containment Control, on high area temperature

Direct manual isolation of Reactor Water Cleanup

Direct maximizing Reactor Building area cooling

May direct area/building evacuation

As time permits, exits EOP-5

If isolation failure is revealed based on timing of crew actions:

0 Determines Technical Specification Table 3.3.6.1-1 Function 5.a was not met 0 Determines Technical Specification 3.3.6.1 Conditions A and B were not met and Condition F requires isolating the affected penetration flow path within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

LOI 16-1 NRC Examination Scenario 4 Page 14 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Role Play: BOP SAT I UNSAT I NA

Executes ARP 09-3-3-02( 12)

If dispatched to investigate, wait 2 minutes, then report 0 Respond for system isolation per OP-28 Section G that there is significant steam 0 Identify affected areas using red lights at panel 09- -*

coming from above the RWCU 21 and/or EPIC pump rooms in the 12MOV-18 0 Isolate the leak by closing:

area. Unable to get any closer.

12MOV-15

12MOV-18 After isolation, report that the

12MOV-69 0 Consider evacuation of personnel from affected leak seems to be getting areas better and the area is starting 0 Dispatch operator to check affected areas and to clear of steam. ensure any systems discharging steam in the affected area are isolated SAT I UNSAT I NA

As time permits, executes OP-28 Section G.2 0 Ensure the following pumps are stopped at panel 09-4:

CLN UP PMP 12P-1A Role Play:

CLN UP PMP 12P-1B If dispatched to perform field 0 Dispatch operator to perform field actions.

actions for RWCU isolation, - 0 Ensure closed the following valves:

acknowledge request.

0 CLN UP SUCT 12MOV-15 0 CLN UP SUCT 12MOV-18 0 CLN UP RETURN ISOL VLV 12MOV-69 0 FILTER DEMIN BYP 12MOV-74 0 CLN UP SLOWDOWN FLOW CNTRL 12FCV-55 0 SLOWDOWN ORIFICE BYP 12MOV-53 0 SLOWDOWN TO MAIN CNDSR 12MOV-56 0 SLOWDOWN TO ROW 12MOV-57 LOI 16-1 NRG Examination Scenario 4 Page 15 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 6 BOP/ATC SAT I UNSAT I NA On Lead Examiner Cue:

Recognize I report EPIC RCIC speed alarm ACTIVATE TRIGGER 4 RCIC Inadvertent Initiation

Recognize I report inadvertent RCIC initiation SRO

Acknowledge reports SAT I UNSAT I NA

Enter AOP-77 (Inadvertent Initiation of ECCS or RCIC)

May enter AOP-32 (Unplanned Power Change)

Direct securing RCIC

Determine RCIC is inoperable

Determine Technical Specification 3.5.3 Condition A requires verifying HPCI operable by administrative means immediately and RCIC to be restored to operable status within 14 days.

BOP SAT I UNSAT I NA Note:

Execute AOP-77:

The crew may trip RCIC prior to referencing AOP-77, since 0 Verify by two independent means, initiation is not required these are immediate actions. 0 IF an inadvertent HPCI or RCIC start occurred, THEN depress associated TURB TRIP pushbutton Role Play: 0 IF an unplanned power change occurred, consult with SRO If dispatched to investigate, to enter AOP-32 wait 2 minutes, then report that nothing looks abnormal at 0 Determine cause of ECCS/RCIC initiation signal(s) and the RCIC skid. initiate corrective actions LOI 16-1 NRC Examination Scenario 4 Page 16 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Events 7, 8, & 9 ATC/BOP SAT I UNSAT I NA On Lead Examiner Cue:

Recognize I report EPIC high area temperature alarms ACTIVATE TRIGGER 5 RCIC Steam Leak and Failure

Recognize I report multiple annunciators, including:

to Isolate, Bypass Opening o 09-3-3-33, HPCI ISOL TRIP INITIATED Jack Fails o 09-4-1-22, RCIC ISOL TRIP LOGIC INITIATED

Recognize I report RCIC failed to isolate Critical Task #1 Given the plant operating at power with an un-isolable Pass I Fail primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram before the 1st Max Safe temperature is reached, in accordance with EOP-5.

Critical Task #2 Given an un-isolable primary system discharging into Pass I Fail Secondary Containment and two areas exceeding Maximum Safe Temperatures, the crew will perform an emergency RPV depressurization, in accordance with EOP-5.

LOI 16-1 NRC Examination Scenario 4 Page 17 of 21

i 1NSTRUCTORACTIVITY I POSITION I OPERATORACTIONS/STANDARD I COMMENTS/EVALUATION I SRO

Acknowledge report SAT I UNSAT I NA Note: The severity level of malfunction RC09 may be

Enter I re-enter EOP-5, Secondary Containment Control, on manually raised with lead high area temperatures examiner concurrence as

Direct isolation of RCIC needed based on the crew's control of Reactor pressure.

Direct area/building evacuation, if not previously performed

Acknowledge manual RCIC isolation failure

Enter EOP-2

Direct manual Reactor scram before 1st Max Safe Critical Task #1 Temperature Role Play:

If dispatched to investigate

Enter AOP-1, Reactor Scram high temperature, wait 2

Direct Reactor pressure controlled 800 to 1000 psig using minutes, then report you see TB Vs steam coming from the Drywall Entrance area and

Direct Reactor water level controlled 180 to 220 inches using cannot access the area. Feedwater

May direct Reactor cooldown < 100°F/hr

May direct rapid Reactor depressurization using TBVs

Acknowledge failure of Bypass Opening Jack to open TBVs

Recognize I acknowledge two area temperature above Max Safe Value

Enter Emergency Depressurization leg of EOP-2

Direct 7 ADS valves open

Acknowledge report that only 3 ADS valves opened Note: Only 2 additional SRVs will open, for a total of 5.

Direct additional SRVs opened Critical Task #2 LOI 16-1 NRC Examination Scenario 4 Page 18 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC SAT I UNSAT I NA

Depress manual Scram pushbuttons

Place Mode Switch to Shutdown

Enter AOP-1

Fully insert IRMs and SRMs

Observe Reactor power downscale on APRMs

Observe SDIV vent and drain valves closed

- Transfer APRM/IRM recorders to IRMs

Down-range IRMs BOP SAT I UNSAT I NA

Attempt to isolate RCIC Note:

The crew may attempt to 0 Close 13MOV-16 isolate RCIC by closing 0 Attempt to close 13MOV-15 13MOV-15 and 13MOV-16 0 Recognize I report 13MOV-15 breaker failure and dual before referencing an ARP or OP as a backup to a failed position indication automatic action (EN-OP-115) or based on guidance in EOP-5.

LOI 16-1NRC Examination Scenario 4 Page 19 of 21

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP cont.

Announce Reactor Building Evacuation, if not previously SAT I UNSAT I NA performed

Enter AOP-1 0 Control RPV water level between 180 and 220" using any of the following methods:

0 Take manual control of reactor feed pump and adjust FDWTR STARTUP VLV (34FCV-137)

ATC/BOP SAT I UNSAT I NA

Update crew on RB area temperatures

May attempt to open Turbine Bypass Valves to initiate cooldown or rapidly depressurize RPV in anticipation of Emergency Depressurization

Recognize I report failure of Bypass Opening Jack to open TB Vs

May lower pressure regulator setpoint to initiate cooldown

Report two area temperatures above Max Safe Value

Attempt to open 7 ADS valves

_ Recognize \ report that only- 3 ADS valves opened Note: Only 2 additional SRVs - Critical Task #2 will open, for a total of 5.

Open additional SRVs

Report 5 SRVs are open Termination Criteria:

All control rods are inserted, Emergency RPV Depressurization is in progress, Reactor water level is controlled above O" LOI 16-1 NRG Examination Scenario 4 Page 20 of 21

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 7% power with the Mode Switch in STARTUP.

The Drywell has been verified to be clear of personnel.

The RWM is bypassed due to a hardware failure.

When you take the shift:

4. Transition to Mode 1 per OP-65 step D.20.3.

5. Continue OP-65, up to and including, step D.20.6 to withdraw all IRMs.

6. Continue control rod withdrawals per the startup control rod sequence:

The next movement is A 1-2 Sequence

RSCS Group 10

Step 26

Control Rod 26-27

Complete Step 26, and then hold for Reactor Engineering analysis.

LOI 16-1 NRC Examination Scenario 4 Page 21 of 21

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD APPL. TO JPM NUMBER Pump REV: DATE: NRC KIA SYSTEM NUMBER: _2_.2_._13_(._4_.1..._)- - - - -

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE:

- - - Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRIN"f.ED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD APPL. TO JPM NUMBER Pump Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD APPL. TO JPM NUMBER Pump I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-OP-102, Protective and Caution Tagging B. FM-27A and FM-27B C. OP-25 Ill. TOOLS AND EQUIPMENT

None IV. SET UP REQUIREMENTS A. Ensure copies of the following references are available:

EN-OP-102

FM-27A and FM-27B (full size)

OP-25 V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this .task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Maintenance is required on CRD pump A.

C. The maintenance activity will be intrusive to the impeller casing for impeller replacement.

D. eSOMS is unavailable.

-3 of 8-

RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD Pump

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Generate a tagout isolation boundary for CRD pump A maintenance. Record the devices to be tagged and their required positions on the worksheet provided. Record additional amplifying instructions that are required, if any, in the space below."

STEP STANDARD EVALUATION I COMMENT

1. Obtain required references. Obtains and utilizes required references, which may SAT I UNSAT include:

EN-OP-102

FM-27 A and/or FM-278

OP-25 EVALUATOR NOTE: Component names and Required Position terminology may vary slightly from what is written below due to unavailability of eSOMS.

2. Determine CRD pump A control switch Identifies CRD pump A control switch should be tagged in SAT I UNSAT tagged position. the green flag after stop position.

EVALUATOR NOTE: The CRD pump A control switch

.doe!:? not have a pull-to-lock P._osition.

3. Determine CRD pump A breaker Identifies CRD pump A breaker (71-11516) should be CRITICAL STEP tagged position. tagged in the racked out or removed position. SAT I UNSAT

4. Determine CRD pump A discharge Identifies CRD pump A discharge isolation valve (03CRD- CRITICAL STEP isolation valve tagged position. 176A) should be tagged in the closed position. SAT/UNSAT

-4 of 8-

RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD Pump STEP STANDARD EVALUATION I COMMENT

- . - CRITICAL STEP

5. Determine CRD pump A suction Identifies CRD pump A suction isolation valve (03CRD-isolation valve tagged position. 153A) should be tagged in the closed position. SAT/UNSAT

6. Determine CRD pump A minimum flow Identifies CRD pump A minimum flow isolation valves CRITICAL STEP isolation valves tagged position. (03CRD-177 A and 03CRD-154A) should be tagged in the SAT I UNSAT closed position.

7. Determine CRD pump positive Identifies CRD pump positive pressure seal isolation CRITICAL STEP pressure seal isolation valve tagged valve (03CRD-39) should be tagged in the closed SAT/UNSAT position. position.

8. Determine CRD pump A venting path Identifies tagging one or more of the following paths for CRITICAL STEP tagged position. venting CRD pump A casing: SAT I UNSAT

CRD pump A suction pressure indicator root valve (03CRD-163) open with the pressure indicator removed/uninstalled.

CRD pump A suction pressure relief valve (03CRD-RV14A) gagged open.

CRD pump A suction from SLC system isolation valve (03CRD-88A) open (with cap removed).

May also list casing vents 03CRD-416A 1 or A2 .

EVALUATOR NOTE: Only one vent or drain path is required by procedure.

-5 of 8-

RO 16-1 NRC RO EC TASK TITLE: Determine Tagout Isolation Boundary For CRD Pump STEP STANDARD EVALUATION I COMMENT

9. Determine this tagout includes high Determines that with CRD pump B running, the discharge SAT I UNSAT energy. isolations for CRD pump A are exposed to high energy

(>500 psig) (may reference EN-OP-102 Section 3.0[15]).

10. Determine need for double valve Determines the discharge of CRD pump A should have SAT/UNSAT protection. double valve protection due to CRD pump B providing high energy (may reference EN-OP-102 Attachment 9.2 Section 5.1 ).

11. Determine availability of double valve Determines double valve protection can only be provided SAT I UNSAT protection and compensatory actions. by taking credit for check valves (03CRD-36A and

..03CRD-37A). -

Indicates that to use check valves as isolation boundary (may reference EN-OP-102 Attachment 9.2 Section 2.8):

Shift Manager concurrence must be obtained .

All individuals working under the tagout shall be informed of the risk.

The risk needs to be listed in the hazards section of the tagout.

EVALUATOR: Terminate the task at this point.

Task Standard: Tagout isolation boundary for CRD pump A developed including components and required positions.

-6 of 8-

HANDOUT Initial Conditions:

The plant is operating at 1OOo/o power.

Maintenance is required on CRD pump A.

The maintenance activity will be intrusive to the impeller casing for impeller replacement.

eSOMS is unavailable.

Initiating Cue:

Generate a tagout isolation boundary for CRD pump A maintenance.

Record the devices to be tagged and their required positions on the worksheet provided.

Record additional amplifying instructions that are required, if any, in the space below .

-7 of 8-

WORKSHEET Component ReQuired Position

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 16-1 S/RO TASK TITLE: Manually Compute Average Drywell Air C001 Temperature APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.1.20 (4.6/4.6)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 16-1 TASK TITLE: Manually Compute Average Drywell Air S/RO C001 Temperature APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2of11-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 16-1 TASK TITLE: Manually Compute Average Drywell Air S/RO C001 Temperature APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-40C, Computer Out Of Service Surveillance Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Prepare a copy of ST-40C completed up to step 8.3.4.

B. Provide Drywell temperature readings on ST-40C Attachment 3 to match selected portions of the Evaluator Key provided in this JPM pre-filled in.

C. Student handout only has RTD used "x'd" and the READING column filled in.

D. Student handout does NOT include SUM OF WEIGHTING FACTORS, CORRECTED VALUES, SUM OF CORRECTED VALUES and AVERAGE DRYWELL TEMPERATURE calculation.

V. . EVALUATOR NOTES

A. None VI. TASK CONDITIONS A. EPIC is out of service.

B. ST-40C, Computer Out Of Service Surveillance, is complete up to step 8.3.4.

-3 of 11-

- CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to complete ST-40C section 8.3, Drywell Temperature Check, and record your results in the space below."

EVALUATOR: Provide the candidate with the in-progress copy of ST-40C.

STEP STANDARD EVALUATION I COMMENT

1. Determine average drywell Calculates and records CORRECTED VALUES on SAT I UNSAT temperature by performing the Attachment 3 (see provided key).

following using Attachment 3:

Multiply the recorded READING by the WEIGHTING FACTOR and record the result under CORRECTED VALUE.

2. IF the READING for any Calculates and records sum of all used WEIGHTING SAT/UNSAT DRYWELL AREA was FACTORS on Attachment 3 (see provided key).

recorded as "none" on Attachment 3, THEN perform the following:

Record the sum of all the used WEIGHTING FACTORS in the SUM OF USED WEIGHTING FACTORS block.

-4 of 11-

STEP STANDARD EVALUATION I COMMENT

3. Record the sum of all the Calculates and records sum of all CORRECTED VALUES SAT I UNSAT CORRECTED VALUES in the on Attachment 3 (see provided key).

SUM OF CORRECTED VALUES block.

4. IF no DRYWELL AREAS had Determines one Drywell Area reading was "none" and SAT I UNSAT a READING recorded as determines this step is n\a.

"none", THEN perform the following ...

5. Determine average drywell Calculates and records average Drywell temperature on CRITICAL STEP temperature by dividing the Attachment 3 (see provided key). SAT/UNSAT SUM OF CORRECTED VALUES by the SUM OF USED WEIGHTING FACTORS and record the result as the AVERAGE DRYWELL TEMPERATURE on Attachment 3.

6. Determine average drywell Reports average drywell temperature is above the allowable CRITICAL STEP temperature is above the value of 135°F. SAT I UNSAT allowable value of 135°F.

-5 of 11-

STEP STANDARD EVALUATION I COMMENT EVALUATOR: For RO candidates, terminate the task at this point.

EVALUATOR: For SRO candidates, provides the following additional conditions and cue (and associated handout):

Initial Conditions:

The plant is operating at 100% power.

You are the CRS.

Initiating Cue:

Assess the results of ST-40C Step 8.3.

Determine any required actions.

Report your findings in the space below.

6. SRO Only Determines Acceptance Criteria 10.1.4 is NOT met. CRITICAL STEP Assesses Acceptance Criteria SAT/UNSAT 10.1.4.

7 SRO Only Determines surveillance is unsatisfactory. CRITICAL STEP Determines required actions. SAT I UNSAT Determines need to notify Operations Manager (or alternate).

Determines CR must be written.

Determines EOP-4, Primary Containment Control, must be entered.

-6 of 11-

STEP STANDARD EVALUATION I COMMENT

7. *Determines Technical Specification 3.6.1.5 Condition A CRITICAL STEP (cont.) must be entered (requires restoring to within limit within 8 SAT I UNSAT hours).

EVALUATOR NOTE: Only the portions of this step marked with an (*)are deemed critical for grading.

EVALUATOR: Terminate the task at this point.

Task Standard: Drywell Temperature check performed in accordance with ST-40C Section 8.3 with calculation revealing Drywell temperature is high out of allowable value.

-7 of 11-

EVALUATOR'S KEY DRYWELL R'TD READING WEJ:GHTING CORRECTED VALUE AREA FACTOR 16-la'TD-

-: .:-'.. -=- (t.:"' 33 J..:f:

1 - *-*.,

"f ,,.. ..........

.:,.t;::;i"-

22 .

"- . -* . 3560 3 .1313 4 ....,, ;:,;;; .(1470 51 5 - --* "::"

l. 3 ?. . 534 7

6 --- 2. .; -:1 .0715 7 135 0. 062!

65 SOM OF CORRECTED VALUES:

P,,.:::~."'"' :1... .. ,:,;:,, :d:

-r -- --

EVALUATOR NOTE: The candidate may round the CORRECTED VALUE entries. An acceptable range for the SUM OF CORRECTED VALUES is 119.9-120.4°F. An acceptable range for the AVERAGE DRYWELL TEMPERATURE is 135.2-135.8°F.

EVALUATOR'S KEY

-8of11-

HANDOUT Initial Conditions:

EPIC is out of service.

ST-40C, Computer Out Of Service Surveillance, is complete up to step 8.3.4.

Initiating Cue:

The CRS directs you to complete ST-40C section 8.3, Drywell Temperature Check, and record your results in the space below.

-9 of 11-

COMPUTE~ OCT O? SERVICE SDF~EILLANCE ;37-4 1 :f 1 DRYWELL RTD READING WEIGHTING CORRECTED VALUE AREA FACTOR 16-lRTD-0 ) l(il !'11) !:e J.11:3 0 l ::o 1 1(1_: l 3:1 0.1 x 11 St

- 103 137 0.3 l

--: J. 4 3 ) (1

=

_! 13E .1313 l t 4 ( l 1)7 133 0.047 Z) l 5

} l 9 133 0. 4 x 17 6 ) 11 l ";,:J.

..J

0.0715 x 111 7 ( ) 11:: 135 0.0 l

": lH:

SUM OF USED WEIGHTING FACTORS:

SUM OF CORRECTED VALUES:

AVERAGE DRYWELL TEMPERATURE:

<., l _;

J. )

cf

ADDITIONAL SRO ONLY HANDOUT Initial Conditions:

The plant is operating at 1OOo/o power.

You are the CRS.

Initiating Cue:

Assess the results of ST-40C Step 8.3.

Determine any required actions.

Report your findings in the space below.

-11 of 11-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.1.5 (2.9/3.9)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 20/25 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 16-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required [gl None Comments:

Current Update By:

Date Int Previous Revision Date:

-2 of 16-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-OM-123, Fatigue Management Program Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure sufficient copies of EN-OM-123, Fatigue Management Program, are available for the number of candidates.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A Reactor Operator has called out sick for Friday, August 31, Day Shift.

The following is the recent work hour history and upcoming schedule for three Reactor Operators. Their hours worked were and are in the Main Control Room during Mode 1, except for the training week.

Dayshift 6:00 am - 6:00 pm Nightshift 6:00 pm - 6:00 am Training 6:30 am - 2:30 pm The schedules show the day that each work shift begins.

-3 of 16-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 16-1 NRC TASK TITLE: Determine Work Hour Limitations S/RO C002 APPL. TO JPM NUMBER RO - Dave Jones M T w Th F Sa Su Week of August 20 D D D D N N Week of Auqust 27 N N D? D D Week of September 3 D D D Week of September 10 T T T T Week of September 17 N N N RO - Bob Smith M T w Th F Sa Su Week of August 20 N N N N Week of Auqust 27 T T T T D? N N Week of September 3 N N D Week of September 1O D D D D Week of September 17 N N N N RO-Jim Doe M T w Th F Sa Su Week of Auqust 20 ' T T T T Week of Auqust 27 D D D D D? N Week of September 3 N N N N D Week of September 10 D D D Week of September 17 T T T T

-4 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations

CRITICAL STEP VII. INITIATING CUE Inform the candidate of the following:

"Evaluate the work hour history for each of the three Reactor Operators. Determine which operators can take the scheduled watch for a full dayshift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months today, Friday, August 31 (and still be eligible for future scheduled shifts).

If applicable, describe the conditions that would make any operator(s) ineligible to work.

Consider all days after August 31 as scheduled shifts. Consider all days before August 31 as actual worked shifts."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of EN-OM- Obtains a controlled copy of EN-OM-123. SAT I UNSAT 123.

EVALUATOR: Provide working copy.

-5 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations STEP STANDARD EVALUATION I COMMENT

2. [1] Work hour limits for individuals Reviews limitations of EN-OM-123. SAT I UNSAT performing Covered Work consist of three concurrent components:

maximum ceilings, minimum breaks, and minimum days off (MOO).

[2] The maximum ceilings which apply at all times are a maximum of: - -

(a) 16 work hours in any 24-hour period, (b) 26 work hours in any 48-hour period, and (c) 72 work hours in any 7-day period.

[3] The minimum break times which apply at all times are a minimum of:

(a) 10-hour break between successive work periods, except that an 8-hour break is allowed when necessary to accommodate a crew's scheduled transition between work schedules or shifts, and (b) 34-hour break in any 9-day period.

[4] The MOO that applies when the plant is on-line:

54-hour rolling average

-6 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations STEP STANDARD EVALUATION I COMMENT

3. Evaluate Dave Jones for overtime. Determines Dave Jones can work the shift. CRITICAL STEP SAT I UNSAT NOTE: The candidate must indicate that Dave Jones is eligible, but does not need to provide an explanation.

See attached key for example.

4. Evaluate Bob Smith for overtime. Determines Bob Smith can NOT take the shift because CRITICAL STEP he would exceed the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period and\or SAT/UNSAT NOT having a 34 hr break in any 9 day period.

NOTE: The candidate must indicate why Bob Smith is not eligible, but does not have to match the above description exactly. See attached key for example.

5. Evaluate Jim Doe for overtime. Determines Jim Doe can work the shift. CRITICAL STEP SAT/UNSAT NOTE: The candidate must indicate that Jim Doe is eligible, but does not need to provide an explanation.

See attached key for example.

EVALUATOR: Terminate the task at this point for RO Candidates.

Provide SRO Candidates with the additional SRO Only Handout once they have completed the above section.

-7 of 16-

SRO/RO 16-1 NRC S/RO C002 TASK TITLE: Determine Work Hour Limitations STEP STANDARD EVALUATION I COMMENT Additional SRO Only Information:

Disregard the previous JPM results.

An operator is currently at their Work Hour Limitation.

This operator is needed to cover Shift.

This additional Shift would result in that operator to exceed Work Hour Limits.

Additional SRO Only Cue:

Inform the Candidate, "Determine the required actions to allow this individual to cover the Shift to meet Technical Specification staffing requirements.

Document your findings in the space below."

6. I SRO Only I SRO Only 1 CRITICAL STEP SAT/UNSAT Determine the required actions to allow Determines EN-OM-123 requires the following actions to an Operator to cover the shift. allow an Operator to cover the shift:

Must complete EN-OM-123 Attachment 9.7, EVALUATOR NOTE: Waiver Basis and Approval The Candidate may list individual

Must complete EN-OM-123 Attachment 9.8, requirements vice listing Attachment Covered Worker Capability Assessment numbers. Reference the EVALUATOR ATTACHMENT at the end of this JPM to see the requirements of EN-OM-123 EVALUATOR NOTE: The Candidate may also specify Attachments 9. 7 and 9.8. that a Condition Report must be generated. This is part of completing Attachment 9. 7.